ML110740227
| ML110740227 | |
| Person / Time | |
|---|---|
| Site: | Plum Brook File:National Aeronautics and Space Administration icon.png |
| Issue date: | 03/11/2011 |
| 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: ML110740227 (137) | |
Text
National Aeronautics and Space Administration John H. Glenn Research Center Lewis Field Plum Brook Station Sandusky, OH 44870 March 11, 2011 Reply to Attn of: QD U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555
Subject:
Final Status Survey Report, Attachment 7, Storm Drains, Pipe Trenches & Other Sub-Surface Excavations, 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 7 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 Storm Drains, Pipe Trenches & Other Sub-Surface Excavations.
It supports our conclusion that radiological remediation of the areas have been completed and the areas meet 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 Enclosure 1. Plum Brook Reactor Facility Final Status Survey Report, Attachment 7, Storm Drains, Pipe Trenches & Other Sub-Surface Excavations, revision 0, dated March 10, 2011.
cc: USNRC/C. J. Glenn (FSME)USNRC/J. Webb (FSME)USNRC/J. Tapp RIII/DNMS/DB ODH/M. J. Rubadue Plum Brook Reactor Facility Final Status Survey Report Attachment 7 Revision 0 Storm Drains, Pipe Trenches & Other Sub-Surface Excavations FINAL STATUS SURVEY REPORT ROUTING AND APPROVAL SHEET Document Title: Final Status Survey Report, Attachment 7 Storm Drains, Pipe Trenches & Other Sub-Surface Excavations Revision Number: 0 ROUTING Prepared By Prepared By REVIEW & CONCURRENCE Independent Technical Reviewer R. Case 0;10V A// (Other Reviewer, QA Manager J. Thoma 3 )ý \Other Reviewer N/A FSS/Characterization Manager W. Stoner /NASA Project Radiation Safety Officer W. Stoner ii NASA PBRF DECOMMISSIONING PROJECT CHANGE/CANCELLATION RECORD DOCUMENT TITLE: Final Status DOCUMENT NO: NA REVISION NO: 0 Survey Report, Attachment 7, Storm Drains, Pipe Trenches & Other Sub-Surface Excavations Revision 0: Initial issue of Report Form AD-01/3 Rev 1 111,,
Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 LIST OF EFFECTIVE PAGES DOCUMENT NO: NA -REVISION NO: 0 Page No. Revision Level Page No. Revision Level Page No. Revision Level Cover Page Routing & Approval Sheet Change/Cancellation Record LOEP TOC List of Tables & List 0 of Figures List of Acronyms & 0 Symbols, 3 pages Text, pages 1 through 0 46 Appendix A 0 22 pages Appendix B 41 pages Appendix C 0 17 pages IAD-01/51 Rev 2 iv Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 TABLE OF CONTENTS 1.0 Introd uction ........................................................................................................
.....1 2.0 Storm Drains, Pipe Trenches & Other Sub-Surface Excavations Description
........ 2 2.1 History of Site Operations
.......................................................................................
3 2.2 Site Geology and Soil Description
...........................................................................
4 2.3 Site Soil Characterization
.........................................................................................
5 2.4 Storm Drain System Operation
................................................................................
7 2.5 Storm Drains, Pipe Trenches & Other Sub-Surface Excavations Construction
.........
10 2.6 Final Configuration and Scope of Remediation of SDPTSSE for Final Status Survey 12 2.6.1 Storm Drain System Dismantlement
.................................................................
12 2.6.2 Cold Retention Basin Dismantlement
................................................................
15 2.6.3 Impacted Utility Excavations
..............................................................................
15 2.6.4 Spill Area Excavation
.........................................................................................
16 2.6.5 Removal of Storm Sewer South of SEB (RCRA Area Excavation)
...................
17 3.0 Storm Drains, Pipe Trenches & Other Sub-Surface Excavations History and Operations with Radioactive Materials
...........................................................................
19 3.1 Disposition of Materials in the Post-Shutdown Period .........................................
19 3.2 D ecom m issioning
...................................................................................................
20 4.0 Survey Design and Implementation for Storm Drains, Pipe Trenches & Other Sub-Surface E xcavations
...................................................................................................
21 4.1 FSS Plan Requirements
.........................................................................................
22 4.1.1 Site-Specific DCGL Values for Soil ..................................................................
22 4.1.2 DCGL for Other Media .......................................................................................
23 4.1.3 Radionuclide Mixture for FSS ...........................................................................
23 4.1.4 Surrogate DCGL and the Unity Rule ..................................................................
23 4.1.4.1 Surrogate Equation .........................................................................................
24 4.1.4.2 Unity Rule Equation .......................................................................................
25 4.1.4.3 A rea Factors ...................................................................................................
..25 4.1.4.4 Survey U nit Size ...............................................................................................
26 4.1.4.5 Scan Coverage for Class 1 Areas ....................................................................
26 4.2 Area Classification and Survey Unit Breakdown
.................................................
27 4.2 Number of Measurements and Samples .................................................................
29 4.3 Instrumentation and Measurement Sensitivity
......................................................
32 5.0 Storm Drains, Pipe Trenches & Other Sub-Surface Excavations Survey Results 34 5.1 Surveys and Investigations
....................................................................................
34 5.1.1 Scan Surveys ......................................................................................................
..34 5.1.2 Investigative Measurements and Judgmental Soil Samples ...............................
36 5.1.3 Systematic Soil Sampling ..................................................................................
39 5.1.3.1 Soil Sampling for Class 1 Areas ...........................................................................
39 5.1.3.2 Quality Control Sample Analysis ....................................................................
40 5.2 A LA RA Evaluation
................................................................................................
43 5.3 Comparison with EPA Trigger Levels .................................................................
43 5.4 C onclusions
..........................................................................................................
..44 6.0 R eferen ces .....................................................................................................................
45 v Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 7.0 A p pend ices ....................................................................................................................
46 A ppendix A -Exhibits ......................................................................................................
46 Appendix B -Survey Unit Maps and Tables Showing Measurement Locations
............
46 Appendix C -Final Status Survey Soil Sample Results .................................................
46 LIST OF TABLES Table 1, Spill A rea Sum m ary ......................................................................................................
6 Table 2, Principal Radionuclides and Activity Fractions for Site Soils .....................................
7 Table 3, DCGL Values for Surface Soil ..................................................................................
22 Table 4, Surrogate DCGLs for Soil FSS ...................................................................................
24 Table 5, Surface Soil Area Factors ...........................................................................................
26 Table 6, Recommended Survey Unit Area Size Requirements for FSS ...................................
26 Table 7, Minimum Scan Survey Coverage ..............................................................................
26 Table 8, Storm Drains, Pipe Trenches and Sub-Surface Excavations Survey Unit Classification C om parison to F SSP .....................................................................................................................
27 Table 9, Storm Drains, Pipe Trenches and Other Sub-Surface Excavations Survey Unit Breakdown by MARSSIM Classification
................................................................................
29 Table 10, Storm Drains, Pipe Trenches & Other Sub-Surface Excavations Survey Design Sum m ary .......................................................................................................................................
30 Table 11, Sensitivity Analysis for OL- 1-26 Design .................................................................
31 Table 12, Typical Detection Sensitivities of 44-10 for Co-60 and Cs-137 .............................
33 Table 13, Scan Survey Results .................................................................................................
35 Table 14, Storm Drains, Pipe Trenches & Other Sub-Surface Excavations Systematic Soil Sample Results By Survey Unit ..............................................................................................
41 LIST OF FIGURES Figure 1, Storm Drains, Pipe Trenches & Other Sub-Surface Excavation and Survey Unit L ocation M ap ................................................................................................................................
18 vi Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 LIST OF ACRONYMS & SYMBOLS (X alpha; denotes alpha radiation, also type I error probability in hypothesis testing A Area, also detector open area AEMC Area corresponding to the area factor calculated using the scan MDC AEC Atomic Energy Commission AOC Area of Concern ALARA As Low As Reasonable Achievable ATS Assembly, Test and Storage Building f3 beta; denotes beta radiation, also type II error probability in hypothesis testing bi background counts in observation interval BPL Byproduct License CB Catch Basin CFR Code of Federal Regulations CRB Cold Retention Basin cm centimeters CMP Corrugated Metal Pipe cpm counts per Minute A delta, DCGLw -LGBR d' Scan surveyor sensitivity index DCGL Derived Concentration Guideline Level DCGLEMC DCGL for small areas of elevated activity, used with the Elevated Measurement Comparison test (EMC)DCGLw DCGL for average concentrations over a survey unit, used with statistical tests. (the "W" suffix denotes "Wilcoxon)" DL Drain Line dpm disintegrations per minute dpm/100 cm 2 disintegrations per minute per 100 centimeters squared EMC Elevated Measurement Comparison ERB Emergency Retention Basin EPA US Environmental Protection Agency FH Fan House Building FPR Final Post Remediation FSS Final Status Survey FSSP Final Status Survey Plan FSSR Final Status Survey Report ft. feet y gamma, denotes gamma radiation g gram HL Hot Lab HTD Hard To Detect HRA Hot Retention Area i observation counting interval during scan surveys IM Investigative Measurement vii in.LBGR I2 MARSSIM MDC MDCsca MDCstatic MDCR MOU mrem MW MWH NASA N NA Nal ncpm NRC OL PBOW PBRF PNL PPH QC p pCi/g QC RCP RCRA RESRAD ROLB ROB RSCB 5 S+SDPTSSE SDS SEB Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 LIST OF ACRONYMS & SYMBOLS. Continued inch Lower Bound of the Gray Region square meters Multi-Agency Radiation Survey and Site Investigation Manual Minimum Detectable Concentration Minimum Detectable Concentration for scanning surveys Minimum Detectable Concentration for static surface activity measurements Minimum Detectable Count Rate Memorandum of Understanding millirem Megawatt Mongomery Watson Harza National Aeronautics and Space Administration Number of FSS measurements or samples established in a survey design Not Applicable Sodium Iodide net counts per minute US Nuclear Regulatory Commission Open Land Plum Brook Ordinance Works Plum Brook Reactor Facility Pacific Northwest Laboratory Primary Pump House Quality Control Standard normal distribution function surveyor efficiency for scan surveys picocuries per gram percent Quality Control Rigid Corrugated Pipe Resource Conservation and Recovery Act 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 Reactor Office and Laboratory Building Reactor Office Building Reactor Security and Control Building seconds generic symbol for standard deviation of a population Sign Test statistic Storm Drains, Pipe Trenches and Other Sub-Surface Excavations Storm Drainage System Services Equipment Building viii Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 LIST OF ACRONYMS & SYMBOLS. Continued SNL Sandia National Laboratory SR Survey Request STS Storm System SSS Sanitary Sewer System TBD Technical Basis Document P Mean activity concentration VSP Visual Sample Plan WEMS Waste Effluent Monitoring Station WEP Work Execution Plan WHB Waste Handling Building Zi-I Proportion of standard normal distribution values less than 1-a Z1.1 Proportion of standard normal distribution values less than 1-03 0o Mathematical symbol for infinity ix Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 1.0 Introduction This report presents the results of the final status radiological survey of the Plum Brook Reactor Facility (PBRF) Storm Drains, Pipe Trenches and Other Sub-Surface Excavations (SDPTSSE).
It is Attachment 7 of the PBRF Final Status Survey Report (FSSR) 1. This attachment describes the operational history and final condition for the final status survey (FSS) of the Storm Drains, Pipe Trenches and Sub-Surface Excavations covered by this document.
It describes the methods used in the FSS and presents the results of the survey 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 lOCFR20 Subpart E. The principal criterion is that the dose to future site occupants will be less than 25 mrem/year.
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 and in Table 2-2 of the Technical Basis Document (TBD)PBRF-TBD-09-00l[PBRF 2009]. In accordance with the FSSP and TBD-09-001, the primary DCGLs for surface soil are as follows:* Co-60 is 3.8 pCi/g,* Sr-90 is 5.4 pCi/g, and* Cs-137 is 14.7 pCi/g.Furthermore, surrogate DCGLs for soil of the SDPTSSE were established in Table 5-2 of PBRF-TBD-09-001 and are provided in Table 2 of this report.The survey measurement results and supporting information presented herein demonstrate that residual contamination levels in each survey unit of the SDPTSSE 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 SDPTSSE meets the criteria for unrestricted release.Section 2.0 of the report provides a description of the SDPTSSE. This section also discusses the final configuration of the SDPTSSE 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 for the SDPTSSE. This section includes FSS Plan requirements applicable to the SDPTSSE, breakdown into survey units and assignment of MARSSIM 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 1 OCFR50.82 (b) (6).I Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 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 SDPTSSE 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 analysis results are provided in Appendix C.2.0 Storm Drains, Pipe Trenches & Other Sub-Surface Excavations Description The PBRF site is located near the northern edge of the 6400 acre Plum Brook Station. The site, as described in the NRC license that controls decommissioning activities, comprises 27 acres which contain the Reactor Building and support buildings and facilities.
2 The controlled-access site is bounded on the south by Pentolite Rd., on the west by Line 2 Rd. and on the north and east by a boundary fence. The southwest corner of the site, the intersection of Line 2 and Pentolite Roads is used as a reference location.3 The coordinates are 410 23'03.73" North Latitude and 82' 41' 05.80" West Longitude.
4 Figure 1 shows the principal PBRF buildings and site layout.The site is generally level with grading to promote surface water drainage to the Water Effluent Monitoring System (WEMS) located at the south east corner of the site [USACE 2004]. The site reference grade level at the Reactor Building is 631 ft. above mean sea level[NACA 1956].'The PBRF 27 acre site contains several multi-story buildings and multiple support structures.
Below-grade structures and utilities extend throughout the site. These include underground pipe and utility tunnels, storm drains, catch basins, sanitary sewers, water and gas supply lines, cathodic protection wells and ground water monitoring wells. Prior to the beginning of 2 See Technical Specifications for the License No. TR-3 (Amendment
- 13) and License No. R-93 (Amendment
- 9) [NASA 2007].3 Prior to decommissioning, the Reactor Vessel center was typically used as a local reference location for the PBRF.4 Note that the coordinate grid system used for construction of the PBRF was a local coordinate system established by the Army Corps of Engineers in the 1940's for construction of the Plum Brook Ordinance Works. This local grid system has been balanced (tied in) to the Ohio regional state plane coordinate system by NASA to align Glenn Research Center and Plum Brook Station geographic references with modem high-accuracy geo-reference systems. This provides the ability to reference locations specified on historical drawings to global latitude and longitude
[Hagelin 2010].5 The finished floor elevation of the Reactor Building first floor is designated as the 0 ft. elevation for major PBRF buildings.
This is one ft. above grade level at the Reactor Building location.2 Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 decommissioning, buildings, water processing structures (WEMS, sludge basins, Cold Retention Basins (CRBs), etc.) paved roadways, parking areas, sidewalks and equipment pads covered about 25% of the site. The remainder of the site surface was open land soil areas.Areas adjacent to the PBRF on the north (north of North Rd.) contained utilities and support facilities for PBRF operations.
These included the Assembly Test and Storage (ATS)Building, the former Reactor Office Building (ROB), an electric substation and a deionized water storage tank. All these facilities and the surrounding land area were cleared of licensed radioactive materials and released from the PBRF NRC licenses prior to decommissioning of the PBRF.6 2.1 History of Site Operations Plum Brook Station was formerly a World War II era explosives manufacturing facility and prior to that was occupied by family farms and orchards [Bowles 2006].Construction of the Plum Brook Ordinance Works (PBOW) in 1941-42, involved razing of existing farms, residences and small commercial buildings and construction of explosives manufacturing facilities.
After World War II, the PBOW lay dormant for 10 years. In 1955 the Department of the Army transferred 500 acres in the northern portion of the former Ordinance Works to the National Advisory Committee on Aeronautics (NACA), the NASA predecessor, for construction of the Plum Brook test reactor facility.The first tasks in the PBRF construction were to remove the PBOW facilities and clean up chemical residues from explosives production.
This included removal and cleanup of two large chemical waste water retention basins located in the southeastern portion of the present-day site.Construction of the Plum Brook Reactor and associated facilities required extensive excavation and backfilling.
Soil was excavated to bedrock and bedrock was excavated in construction of the Reactor Building and nearby support buildings and in construction of large water handling facilities, the CRBs and Emergency Retention Basin (ERB) [USACE 2004].Major PBRF milestones are listed below: 7 1956 -September, groundbreaking for PBRF.1956 -Reactor Building construction initiated.
1959 -1960 Major building construction completed.
1961 -June, 60 MW Test Reactor critical.6 License Number TR-3, Amendment No. 6, approved by NRC letter dated Dec. 17, 1976.7 Information sources for the site history include construction drawings and photos, PBRF operating cycle reports, PBRF annual reports, memoranda and other historical files maintained by PBRF Document Control.3 Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 1973 -January 5h, Reactor shutdown.1973 -June 30, PBRF facilities placed in "standby" condition.
1985 -Initial radiological characterization, Teledyne Isotopes Inc.1989 -Follow-up radiological characterization, GTS-Duratek.
2002 -Decommissioning Plan approved.
Equipment removal and initial building decontamination commenced.
2005-2010
-Decommissioning of Buildings and Excavation of Soil and Materials.
2010-2011-FSS on Storm Drains, Pipe Trenches and Other Sub-Surface Excavations.
It is noted that the major buildings were completed in the construction period, 1956 -1960, but modifications to the site that affected areas excavated during decommissioning occurred throughout the operations period. These included installation of cathodic protection wells (1961-62), construction of the Waste Handling Building (1962-64), construction of the Assembly and Test Storage Building (ATS, Building 1142) utility and personnel passage tunnel to the Reactor Building (1964-65), WEMS modifications (several times during 1961 -1973) and modification of storm drains (1968).2.2 Site Geology and Soil Description The Plum Brook Station and the PBRF site are underlain by shale and sandstone formations at varying depths (approximately 2 to 25 ft.) across the station with surface outcrops at some locations.
The depth to bedrock is about 25 ft. in the vicinity of the Reactor Building [NASA 2007a]. Surface deposits constitute a mixture of soils derived from fine sand, silt, clay and unconsolidated glacial till [NASA 1959]. Soils in the vicinity of the PBRF are composed of loam, loamy fine sand and fine sandy loam[USACE 2004].However, the PBRF site soils are highly disturbed and not considered characteristic of native-undisturbed soils in the site vicinity.
A series of major disturbances have occurred dating back to the 1940's. Construction of the PBOW involved extensive excavation to construct the ordinance "production lines" and process waste water retention basins. As a result of PBOW operations from 1942 -1945, the PBRF site was extensively contaminated with chemicals used in the manufacture of Pentolite.
8 A site cleanup campaign was mounted prior to PBRF construction
[Bowles 2006].During this cleanup, unknown quantities of soil were reportedly removed from the site 8 Pentolite is a military grade high explosive.
4 Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 and fill material was likely brought in from off-site [USACE 2004]. And, as described in the previous section, construction of the PBRF involved extensive excavation and backfilling throughout the 27 acre site.2.3 Site Soil Characterization Site soil characterization results are summarized to identify soil areas requiring remediation (excavation) and to present radionuclide profiles of radiological constituents of PBRF origin. Radiological characterization of PBRF soils has been performed on several occasions after the facility shutdown in 1973. The initial post-shutdown characterization survey performed in 1985 (reported in 1987) by Teledyne Isotopes, Inc. included sampling and analysis of site soils [Tele 1987]. In 1998, GTS Duratek performed a characterization survey to confirm the 1985 Teledyne results and to provide additional data on isotopic composition of contamination.
From these studies, it was concluded that the ERB, the Pentolite Ditch, the CRBs and several localized areas required remediation.
9 In 2004, a comprehensive characterization survey of the site was performed by Montgomery Watson to identify contaminated soil areas and develop radionuclide profiles to guide remediation efforts. The area inside the PBRF site was divided into 11 survey units. Two areas outside the site fence that were known to be contaminated were also characterized; an area east of the WEMS and the Pentolite Ditch.Altogether, 610 surface and 1,043 subsurface soil samples were collected and analyzed by gamma spectroscopy
[MWH 2005]. Selected samples were sent to vendor laboratories for analysis of non-gamma emitters.Remediation action levels (RALs) to guide remediation planning were set at 50% of DCGLs published in the FSS Plan [MVWH 2005a]. On this basis and from results of characterization surveys described above, the following areas were identified as requiring remediation: " Emergency Retention Basin (ERB)" Cold Retention Basins" Water Effluent Monitoring System (WEMS)* Storm Drains and Catch Basins* Waste Handling Building (WHB) and Fan House (FH) Building sub-foundation (portions)
- Pentolite Ditch and Environs, identified as Areas of Concern (AOCs)9 It is noted that the Teledyne and GTS Duratek surveys were performed prior to the issuance of the current release criteria in 1 OCFR20 Subpart E and the supporting guidance on acceptable methods for characterization and final status surveys to demonstrate compliance.
The 1985 and 1998 surveys relied heavily on gross activity analysis of soil samples and exposure rate measurements.
These surveys identified locations of contaminated soil but did not provide information needed to determine nuclide profiles, DCGLs, and action levels for remediation and final status survey of site soils.5 Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 In addition, several discrete contaminated areas that resulted from spills were defined.Subsequent to the MWH characterization surveys, additional characterization was performed to further delineate these spill areas. 0 They are summarized in Table 1.Table 1, Spill Area Summary Name Location Approximate Description Size (ft 2) (1)Spill Area No. 1 Along E half of PPH S Contaminated concrete, asphalt and soil wall 25 area. Cs-137 up to 1.67 pCi/g & Co-60 up to 4.48 pCi/g (in soil 0 to 6 in depth).Designated as a Co-60 area. (2)Spill Area No. 2 N of Reactor Building Site of a 300 gallon liquid spill during near Catch Basin 4 transfer of contaminated water in 2005.Was remediated in 2005. Designated as a Co-60 area. (3)Spill Area No. 3 E side of Hot Lab at Cs-137 up to 431 pCi/g & Co-60 up to Rollup Door 1000 271 pCi/g (0 to 6 in depth).Designated as a Co-60 area. (3)Spill Area No. 4 S of WHB Smaller of two distinct sub-areas (small area) 22 identified as Spill area No. 4. Above scan RAL, but no soil samples > 0.5 x DCGL.(3)Spill Area No, 4 W of Line 3 Rd Larger of two distinct sub-areas (main area) approximately 100 ft. S 2400 identified as Spill area No. 4. Scan of WHB results > bkg., but below scan RAL; no soil samples > 0.5 x DCGL. (3)Spill Area No. 5 S of South CRB Above scan RAL, but no soil samples>600 0.5 x DCGL. (3)Spill Area No. 6 E of SEB & S of Sludge Scan surveys in 2006 failed to detect Basins levels above bkg., except in one very 2500 localized area (- 2ft 2) just south of catch basin CB-9A, which was > RAL. (3)WEMS Spill Area E of WEMS outside Soil area contaminated from WEMS Perimeter Fence 2500 overflow-flood events. Cs-137 up to 19.1 pCi/g & Co-60 up to 1.28 pCi/g (0 to 6 in depth). (3)Table 1 Notes: 1.2.3.Approximate surface area of potentially impacted areas investigated.
Descriptive information and survey results from SR-3 Descriptive information and survey results from SR- 16 and personal communication, FSS supervisor.
Using characterization survey results, radionuclide profiles were developed for the areas that were identified as requiring remediation.
These were published in a technical basis document to establish radionuclide mixtures and DCGLs for FSS of the site soils [PBRF 2009]. The site and impacted adjacent environmental areas were divided into groups with similar radionuclide profiles.
Activity fractions of the 10 Survey Request SR-3, Spill Area No.1 (January 2006) and SR-16, Spill Areas No.2 through No.6 (May 2006).6 Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 principal radionuclides, Cs-137, Co-60 and Sr-90 were established for each group. The results are shown in Table 2.11 Table 2, Principal Radionuclides and Activity Fractions for Site Soils Location Activity Fractions Cs-137 Co-60 Sr-90 Default for PBRF site and Spill Areas 4, 5 & 0.912 0.007 0.081 6.Spill Areas 1, 2 & 3 0.201 0.714 0.085 Environs Outside 0.878 0.037 0.085 Perimeter Fence Pentolite Ditch and 0.969 0.014 0.017 Environs 2.4 Storm Drain System Operation The Storm Drainage System (SDS) was designed to control and record the volume of surface and wastewater and their associated radioactivity levels to document compliance with Atomic Energy Commission (AEC)/NRC and other regulatory requirements.
The storm drainage system bounded the 27-acre reactor site and the effluent was directed to a control point located in the southeast comer of the reactor site adjacent to and inside the PBRF fence. That control point was called the Water Effluent Monitoring Station/System (WEMS), Building 1192, [PBRF 2009b].The WEMS 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 limits in the PBRF license. Liquid effluents (such as storm drainage, waste waters including man-made radioactive contamination of PBRF origin, and processed lake dilution water)were released into the Pentolite Ditch via the WEMS.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 (ERB) for temporary storage." Other radionuclides have been measured in PBRF characterization soil samples. In the FSS Plan, soil DCGLs were published for eight radionuclides (Co-60, Cs-137, Sr-90, Eu-152, Eu-154, Fe-55, Ni-69 and Ni-63. The dose to the Resident Farmer from radionuclides other than the principal three was calculated to be only 0.5 mrern/y. Hence, as this dose is well below the NRC 10% criterion, these radionuclides are considered insignificant.
7 Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 The SDS was originally constructed in the 1959 to 1963 time frame.1 2 Major modifications were made to the system several times to improve performance such as adding a hydro-mat liner to the open ditches, reshaping the flow path, and subsequently adding concrete piping and covering the ditches. 13 The storm drainage waters contributed to the dilution of controlled radioactive discharges; they also contributed to flushing of the drainage ditches during periods of heavy rainfall.
Occasionally, storm waters washed radioactive contaminants from spills and fallout from nuclear bomb testing during the early 1960s that had settled on the ground into the ditches. Storm flow rates varied from low flows during minor rainfalls to high flow conditions during heavy rain falls.The main on-site storm drainage system, post shutdown, consisted of five laterals plus an under-drain system. A map identifying the storm drain system including an identification of the laterals is contained in Exhibit 2 of Appendix A. A description of the lateral system is as follows:* Lateral A: Started at Catch Basin 5A near Building 1191 and ran south then east to the WEMS. Lateral A was comprised of about 465' of 30" Rigid Corrugated Pipe (RCP) and 1000' of 18" RCP along with the remains of the hydro-mat liner. Lateral A ran under Line 3 Road in a 43"x 27"x 60'corrugated metal pipe. Laterals C and D joined Lateral A at the south end of Line 3 Road -Lateral C on the west side and Lateral D on the east. (Note-Lateral B was the Pentolite Ditch and was outside the PBRF fenced site.)" Lateral C: Started at Catch Basin 13A south of Building 1133 and ran to Lateral A along the west side of Line 3 Road. Lateral C was comprised of about 360' of 12" RCP along with the remains of the hydro-mat liner." Lateral D: Started at the headwall and Catch Basin 7A near the north Cold Retention Basin and ran south along the east side of Line 3 Road, finally connecting to Lateral A. Approximately 70' of hydro-mat liner (intact) was abandoned near the junction of Lateral D and Lateral A because it originally entered Lateral A at a 450 angle, instead of the present (near 900). There was approximately 650' of 18" RCP, the remains of the hydro-mat liner, plus 50' of 18" RCP added to straighten the lateral where it connected to Lateral A." Main Lateral: Started at the headwall north of Catch Basin 9A and near the raw water flush valve (25V1 8) pit and runs south to the WEMS settling basin.There were approximately 880' of 36" RCP and the remains of the hydro-mat liner.* The north lateral ran east and west on the north side of the facility just inside the north fence line. This lateral connected to the main lateral east of the sludge settling basins (1153).1 2 NASA Lewis Research Center -Plum Brook Station Building Plans, NASA PBRF Records Files and Drawings CF-115330 and 115332.13 NASA PBRF Drawings PF-06006 & PF-06007.8 Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 Under Drain System: An under drain system was added to drain ground water from under the concrete pipe in Lateral A and the main lateral. This was a 6" Corrugated Metal Pipe (CMP) that ran approximately the last 275' of Lateral A and the last 350' of the main lateral emptying into the WEMS settling basin.The term "lateral" was historically applied to the original open ditch areas of the PBRF storm drainage system. 1 4 Other sub-surface storm drainage piping fed into three laterals and was not included in the "lateral" descriptions in this report. For example, there were storm drain sections north of Lateral A headwall that tied directly into Lateral A (CBs IA, 2A, 3A, 4A, 23, 24, 25, 26, 27, 28, and 33). Also, storm drainage piping south of the headwall tied into Lateral A (CBs 18, and 22 plus three field drains). The areas outside the "lateral" descriptions are addressed in this FSS report.In addition to the above laterals, there were a number of under-drains and sloped landscaping throughout the site that directed rain and ground water to catch basins.These features were to keep the grounds relatively dry. The SDS consisted of a total of 9200 ft. of pipe ranging in size from 2" to 36" and a total of 56 catch basins.A map of the SDS is provided in Exhibit 2 of Appendix A. See Exhibits 4, 5, and 9 in Appendix A for photographic documentation of Storm Drains, Pipe Trenches & Other Sub-Surface Excavations prior to remediation.
The Cold Retention Basins, Building 1154, were located east of the Fan House and the Waste Handling Building and on the east side of Line 3 road. The two CRBs were designed as a hold area for quadrant and canal water associated with the 60MW test reactor and mock-up reactor operations.
The stored water contained in the CRBs was sometimes released to Lateral D under controlled conditions, after sampling and analysis.
The basins were mostly below grade with a roof section that was about 1-2 ft. above grade. The north basin was identified as CRB-1 and the south as CRB-2.The Fan House (FH), Building 1132, was located south of the Primary Pump House (PPH) and east of the Hot Lab (HL). Primary FH functions were collection and processing of exhaust air and contaminated water from the Reactor Building and other PBRF buildings.
Air processing equipment contained in the FH included fans, pumps, compressors, a scrubber, filters, activated carbon absorbers, radiation monitor and exhaust system.The Waste Handling Building (WHB), Building 1133, was located south of the FH and east of the Hot Retention Area (HRA). The WHB contained equipment for processing contaminated water, protective clothing, miscellaneous contaminated trash, or dry active waste (DAW), equipment and experiment hardware.
Waste processing activities spanned decontamination, waste shipment and recycling.
The WHB included laundry facilities for decontaminating protective clothing.
It contained operating areas for processing and packaging radioactive waste for offsite shipment, an evaporator 14 PBRF reference drawing RF-06260.9 Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 facility for processing high-solids contaminated waste water and work areas for decontaminating reusable equipment and for packaging radioactive waste for storage and shipment.
The WHB was designed for operation in close conjunction with the FH and HRA for processing PBRF radioactive wastes.The Hot Retention Area (HRA), Building 1155, was located south of the FH and west of the HRA. The HRA was designed to provide holding capacity for large volumes of radioactively contaminated water generated in PBRF reactor operations.
It functioned as a tank farm for storage, holdup and decay of water from the hot drain system. The hot drain system collected radioactive water from hot sumps in the Reactor Building and the other PBRF buildings.
The twelve HRA tanks had a combined capacity of 512,000 gallons. Eight large (60,000 gallon) steel tanks were housed in the vault and four stainless steel, 8000 gallon tanks were buried underground north of the main HRA vault.Additionally, a large number of underground piping systems were connected to many of the buildings at PBRF including the following:
FH, PPH, WHB, Reactor Building, HL, CRBs, SEB, ROLB and the HRA. These piping systems included the following:
primary and secondary cooling, contaminated discharge lines, resin transfer lines, valve pits, sewage systems, domestic water system, ventilation system piping, vent and drain lines and utility supply lines.2.5 Storm Drains, Pipe Trenches & Other Sub-Surface Excavations Construction During the construction phase of the Reactor Facility (1956 to early 1963) prior to reactor full power operations, the lateral drainage ditches A, C, D and the main laterals were constructed as open ditches. The main lateral was open from Catch Basin 6B just north of the Precipitator (1157) and east to near the east fence line,. then south to the WEMS. Lateral A was an open ditch running south from the Reactor Security and Control Building (RSCB) to near the south fence line then east to the WEMS. A 60 foot long 43"x 27" CMP ran under Line 3 Road. The spoils from the ditching were used to fill an existing creek bed that ran through the center of the facility.
Pentolite Ditch that ran east and west from the WEMS exit to Plum Brook, was denoted as Lateral B.Lateral C was an open ditch from the Fan House along the west side of Line 3 Road south to Lateral A. Lateral D was an open ditch from CRB-1 along the east side of Line 3 Road and south to Lateral A.Piping and catch basins were eventually installed in the north and main lateral from the precipitator east and around the sludge settling basins then south to a headwall near the valve pit (25V1 8) and raw water flush line. Piping was installed in Lateral C from the Fan House south to near the Waste Storage Pad and Catch Basin 13A.10 Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 Early during the 60 MW reactor operations period, the storm drainage system laterals from the headwalls 1 5 to the WEMS were open ditches lined with a hydro-mat lining and sealed with a cold mastic sealant. The Hot Retention Area (HRA) pump out line discharged effluent into the storm drainage system adjacent to the valve pit near Cold Retention Basin (CRB) # 1. This location was just north of what was to be catch basin 7A. The headwall was visible near catch basin 7A.The floor drain system for the Hot Lab Building Room 8, Change Room, 1 6 floor drains and the Mezzanine Room 27 floor drains 1 6 exited the south end of the building at -3 foot elevation and connected to the storm drainage system toward Catch Basin 3A.The HRA and the CRB pump out lines also emptied into Lateral D near CRB-1. This water flowed (undiluted) south to Lateral A then east to the WEMS settling basin where it finally mixed with raw water from the main lateral and was diluted to meet effluent release criteria.Over time, the hydro-mat liners were prone to leakage because of weathering causing cracked joints and required significant maintenance.
It was found that the material used was not suitable for that purpose and suffered significant damage from the sun.In 1968, the bottoms of the hydro-mat liners were cut out and unstable base material removed. It is not known where this material was disposed.
The ditch bottoms were then graveled and reinforced concrete pipe (RCP) installed.
The hydro-mat liner remained in place on the ditch sides. An under drain system was installed on Lateral A and on the main lateral for a distance of about 300' from the WEMS settling basin.There was an angled comer between Lateral D and the Lateral A east -west section that was squared off also at this time. New piping was also installed for the HRA pump out system, so that the discharge went between CRB 1 and CRB 2 and into the main lateral that runs north and south along the east fence line. The pipe discharged into catch basin 8A and then into the 36" reinforced concrete pipe, which empties into the WEMS settling basin (Facility Change 67-011). This afforded a better mixing of the HRA discharge water and the raw dilution water and reduced the frequency of WEMS gate closures.
The CRB pump out discharge remained in Lateral D.The CRBs were two prism based concrete basins with a capacity of about 500,000 gallons each. The basins were 94 ft. square at the top, 22 ft. square at the bottom and 18 ft. deep. Each basin had a pump that returned stored water to the Quadrant and Canal system. This water could also be pumped to the effluent trench (lateral D of the WEMS system) or transferred between basins. Valving was done in a below grade valve pit located just west of CRB-1. The valve pit was 14.3 ft. long, 10 ft. wide and 7 ft. deep. All electrical feed was through the valve pit to control panels located on the west side of each basin.15 PBRF print number PF-65156.16 PBRF print number PF-04587.11 Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 2.6 Final Configuration and Scope of Remediation of SDPTSSE for Final Status Survey As areas became available, SDPTSSE were remediated by initially excavating the impacted soil/material 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.
Remediation continued until surveys indicated that the area was below the RAL.The final configuration of the Storm Drains, Pipe Trenches & Other Sub-Surface Excavations for FSS consisted of a ditch that was excavated and benched, if necessary, as shown in Exhibits 8,11, 12, 14, 16, 17 and 19 of Appendix A.2.6.1 Storm Drain System Dismantlement The SDS was dismantled in phases by Decommissioning Contractor in accordance with Work Execution Package (WEP) number PBRF-WEP-09-020, "Storm Drain System Dismantlement".
See Figure 1 and Exhibit 1 of Appendix A for a graphical representation of the Storm Drain, Pipe Trench and Other Sub-Surface Excavations conducted at PBRF. The phases of SDS dismantlement were as follows: Phase 1 the West Storm Drain System dismantlement consisted of the following:
o Approximately 520 linear feet (ft.) of piping between CB-28 and CB-4A, o CB-28, o CB-lA, o Roof drain line (DL) to STS-45, o (Note-STS is used for "storm system" on some PBRF data sheets to designate pipe sections.)
o Cold Sump line to STS-45, o SDS from STS-45 to CB-2A, o Roof drain line to CB-2A, o CB-27, o SDS between CB-27 and CB-4A, o CB-2A, o SDS between CB-2A and CB-4A, o Approximately 190 linear ft. of SDS piping between Hot Laboratory (HL), Building 1112 and CB-3A, o Roof DL STS-82 from southeast end of HL to south end of STS-82, o STS-1 12 from HL to STS-82, o STS-82 from south end of STS-1 12 to CB-3A, o Approximately 180 linear ft. of STS between CB-26 and CB-3A o CB-26, STS-9, CB-25, STS-24, STS-64, CB-23, STS-75, CB-3A 12 Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 o Approximately 190 linear ft. of SDS piping from CB-3A to CB-33 and from CB-4A to CB-5A, o STS-53, CB4A, STS-54, CB-33, STS-70, and CB-5A.Phase 2 dismantlement of the Storm Drain System North of Reactor Building (RxB), Building 1111, consisted of the following:
o Approximately 687 linear ft. of SDS between CB-1 and STS-72, o CB-i and STS-36, o STS-39, o CB-4 and STS-37, o STS-41, o SDS from CB-3 to west end of STS-42 and CB-3, o STS-42 from south end of Unit Sub Station 3 to CB-4, o CB-4 and the SDS between CB-4 and CB-5.* Phase 3 dismantlement of the Storm Drain System East of the RxB consisted of the following:
o Approximately 283 linear ft. of SDS between CB-10 and STS-71, o CB-10, STS-2, CB-9, STS-4, CB-8, STS-3, CB-7, and STS-71.Phase 4 dismantlement of the Storm Drain System West of the SEB consisted of the following:
o Approximately 400 linear ft. of SDS between CB-7A and STS-57, o CB-7, STS-20, CB-21, STS-23, CB-20, STS-22, CB-12, STS-59, CB-11, and STS-57.Phase 5 dismantlement of the Storm Drain System North of the North Road consisted of the following:
o Approximately 175 linear ft. of SDS between Man Hole MH-E4 and STS-73, o MH-E4, CB-B6 and STS-73, o Approximately 285 linear ft. of SDS from STS-56 to STS-65, o STS-56, MH-E5, and STS-65, o Approximately 195 linear ft. of SDS from CB-5 to STS-58, o CB-5, STS-74, CB-6A, and STS-58, o Approximately 215 linear ft. of SDS from Reactor Services and Equipment Building (SEB), Building 1131, to STS-66, o STS-78, o STS-79 from north of SEB to STS-78, o CB-6B and STS-66.Phase 6 dismantlement of the Storm Drain System East of the RxB consisted of the following:
o Approximately 460 linear ft. of SDS between Blow-off Pit through CB-12A TO CB-9A, o Blow Off Pit, STS-80, CB-12A, STS-67, CB-11A, and STS-60.13 Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 o Approximately 220 linear ft. of SDS between the Valve Pits to the intersection of STS-77 and STS-62, o Valve Pits, STS-87, CB-10A, STS-63, STS-62 up to intersection of STA-77, o Approximately 610 linear ft. of SDS from CB-14 AND CB-17 TO CB-8A, o STS-25, CB-17, STS-24, CB-15, STS-76, CB-16, STS-77, and the remains of STS-62, o Approximately 1,505 linear ft. of SDS from what remains of FH-1 10-1 to CB-8A and then to the WEMS, o FH-l 10-1, CB-8A, STS-68 to the intersection with STS-34, the remaining part of STS-68, CB-1 8A, and West Lateral-F2 to the intersection with STS-35, o STS-35 from CB-18A to West Lateral-F2, o West Lateral-F2, o STS-69 to CB-17A, CB- 17A and the remaining section of STS-69, o Approximately 850 linear ft. of SDS from CB-15A to WEMS, o CB-15A, STS-30 up to STS-81, STS-81, o STS-30, STS-46, CB-16A, and remaining SDS between CB-16A and the WEMS, o West Lateral-Fl.
Phase 7 dismantlement the Southern Storm Drain System consisted of the following:
o Approximately 60 linear ft. of SDS between FH and CB-WH5, o Cold sump line to CB-WH5, o Approximately 465 linear ft. of SDS from CB-WH5 to STS-6, o CB-WH5, STS-1 from north end of line connecting to WHB, o Remaining STS-1, o STS-13 FD from WHB to CB-WH4, o STS-14 cold sump from WHB to CB-WH4, o STS-15 roof drain from WHB to CB-WH14, o CB-WH4 and STS-5, o STS-83, o CB-WH3 and STS-5, o Approximately 240 linear ft. of SDS from west end of STS-1 1 to CB-13A, o STS-11, CB-WH2, STS-84, CB-WH11, STS-88, STS-95, and CB-13A.When each phase of the SDS was dismantled, final post remediation surveys were conducted and the excavated areas were turned over to the FSS group for isolation and control and final status survey. See Exhibits 7, 8, and 14 of Appendix A for photographic documentation of Radiological Surveys being conducted after SDS dismantlement.
Once final status surveys were completed, the excavated areas were turned over to the Decommissioning Contractor for backfill.
See Exhibit 18 of Appendix A.14 Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 NOTE; A list of the buried piping remaining shall be provided in Attachment
- 17,"Buried and Miscellaneous Piping".2.6.2 Cold Retention Basin Dismantlement The Cold Retention Basins, Building 1154, were dismantled in phases by the Decommissioning Contractor in accordance with Work Execution Package (WEP)number PBRF-WEP-09-006, "Cold Retention Basin Dismantlement".
See Figure 1 for a graphical representation of the Storm Drain, Pipe Trench and Sub Surface Excavations conducted at PBRF. The phases of CRB dismantlement was as follows:* Roof system dismantlement including the roof, joists and girders," Internal systems disassembly including the pumps, piping, ladders, etc.,* Concrete structure dismantlement,* Sub-base material excavation, and* Underlying soil survey and excavation.
Once the CRBs were dismantled in the sequence above, final post remediation surveys were conducted and the excavated areas were turned over to the FSS group for isolation and control and for final status survey. Once final status surveys were completed, the excavated areas were turned over to the Decommissioning Contractor for backfill.
See Exhibit 10 of Appendix A.2.6.3 Impacted Utility Excavations Impacted utilities were dismantled in phases by the Decommissioning Contractor in accordance with Work Execution Package (WEP) number PBRF-WEP-09-007,"Impacted Utility Excavation".
See Figure 1 for a graphical representation of the Storm Drain, Pipe Trench and Sub Surface Excavations conducted at PBRF. The utility excavation was as follows:* Utility isolation,* Sanitary Sewer System (SSS) excavation of approximately 815 linear ft. of system piping running east to west along North Road. This includes the following piping: o SanS-5, o SanS-6, o SanS-7, o SanS-4, and o SanS-8.* SSS excavation of approximately 585 linear ft. of system piping running between the FH (1132) and the WHB (1133). This includes the following piping: o SanS-lA, o SanS-1B, o SanS-2, and 15 Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 o SanS-3.* Cold Retention Area piping excavation of approximately 1,393 linear ft. of system piping running between the CRBs (1154) and the FH (1132). This includes the following piping: o CRB-5, CRB-4-1, CRB-3-1, and CRB-7-1. In addition to the valve pit outside the CRBs, o CRB-1, CRB-2, CRB-3, and CRB-4.* Hot Retention Area piping excavation of approximately 216 linear ft. of system piping running between the CRB valve pit and the FH (1132). This includes the following piping: o FH-110-1 and FH-110 sump FH-110.* Primary Pump House (PPH), Building 1132, and FH utility excavation of approximately 633 linear ft. of system piping surrounding the FH (1132) and the PPH (1134). This includes the following piping: o RxB-134, o PPH-105, PPH-106, and PPH-107, o Resin and valve pit south of PPH, RP-01, RPHD-1, and RPHD-2, o FH-103, o FH-112 and FH-113.See Exhibit 3 of Appendix A for a map of the Sanitary Sewer System, at PBRF.Once the Impacted Utilities were dismantled in the sequence stated above, final post remediation surveys were conducted and then the excavations were turned over to the FSS group for isolation and control and for final status survey. Once final status surveys were completed the excavations were turned back over to the Decommissioning Contractor for backfill.
1 7 See Exhibit 13 of Appendix A.2.6.4 Spill Area Excavation Three Spill Areas were excavated, by the Decommissioning Contractor, in accordance with Work Execution Package (WEP) number PBRF-WEP-09-009, "Spill Area Excavation".
See Figure 1 for a graphical representation of the Storm Drain, Pipe Trench and Sub-Surface Excavations conducted at PBRF. The spill areas were known low level waste spills-one near the Hot Lab Building east truck door, one in vicinity of Primary Pump House resin pits, and one adjacent to the Water Effluent Monitoring Station trench. See Exhibits 6 and 15 of Appendix A.The extents of spill area excavation were based on pre-excavation survey, which were designed to identify the area and depth of excavation necessary to remediate the spill area.Spoils from spill area excavations were segregated based on radionuclide characterization data. See Exhibit 20 of Appendix A.17 If a section of pipe was not excavated and dismantled in the manner stated above, then that pipe was not addressed in this report. The pipe will be addressed in Attachment 9, "Embedded Piping" or Attachment 17, "Buried Piping".16 Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 Once the spill areas were excavated, final post remediation surveys were conducted and then the excavations were turned over to the FSS group for isolation and control and for final status survey. Once final status surveys were completed the excavations were turned back over to Decommissioning Contractor for backfill.2.6.5 Removal of Storm Sewer South of SEB (RCRA Area Excavation)
The Storm Sewer South of SEB (Building 1131) was dismantled in phases by the Decommissioning Contractor in accordance with Work Execution Package (WEP)number PBRF-WEP-09-027, "Removal of Storm Sewer South of Building 1131 Excavation".
See Figure 1 and Exhibit 1 of Appendix A for a graphical representation of the Storm Drain, Pipe Trench and Sub-Surface Excavation and Survey Unit Location map for PBRF. The phases of the dismantlement were as follows:* Phase 1 Resource Conservation and Recovery Act (RCRA) area excavation which consisted the following:
o Approximately 60 linear ft. of storm drain system piping from CB-13 to SEB (1131), o CB-13, STS-27, and CB-14, o STS-26, o STS-25 andCB-15, o Monitoring well EB-RA-05 and underground electrical lines and conduit that serviced recovery wells, RW-01 and RW-02.* Phase 2 RCRA area excavation which consisted the following:
o SEB (1131) air intakes and monitoring well EB-RA-05, See Exhibit 19 of Appendix A for photographic documentation of the RCRA spill area excavation.
Soil from RCRA area excavations were segregated and handled separately from other site soils. See Exhibit 20 of Appendix A. Once RCRA area excavations were completed, final post remediation surveys were conducted and then the excavated areas were turned over to the FSS group for isolation and control and final status survey. Once final status surveys were completed the excavated areas were turned over to the Decommissioning Contractor for backfill.17 Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 Figure 1, Storm Drains, Pipe Trenches & Other Sub-Surface Excavation and Survey Unit Location Map[1l4 7I~tN~OUT~ DITC?1 18 Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 3.0 Storm Drains, Pipe Trenches & Other Sub-Surface Excavations History and Operations with Radioactive Materials During reactor operations, there were several areas, especially between the Primary Pump House, Hot Lab, and the Fan House, where minor spills of radioactive material occurred on the ground. During resin changes at the Primary Pump House Resin Pit, some area contamination did occur. Additionally, some area contamination occurred when the Hot Lab sump was cleaned in the general vicinity of the Hot Lab rollup door apron and the concrete sump cover. Although these areas were cleaned as much as possible, some low level of contamination found its way to the storm drainage system.Catch Basin 10, which receives run-off water from the asphalt/gravel area between the PPH and FH, was contaminated shortly after shutdown.
The catch basin was cleaned, but area contamination still existed to some degree inside the catch basin and also the 8" corrugated metal pipe which connects Catch Basin 10 to catch basin 9 and beyond. Additionally, contamination likely existed inside the 36" RCP from Catch Basin 8A to the WEMS settling basin. Low levels of contamination were likely present on the existing hydro-mat liner and under the hydro-mat liner of lateral D and beyond to the WEMS settling basin.The storm drain system at and near the Waste Handling Building south rollup door apron was impacted by several minor spills. The area inside the rollup door was a posted contaminated area and several small spills of radioactive materials occurred just outside the door.Prior to the installation of the concrete pipe, Lateral D and part of Lateral A were impacted by undiluted HRA discharges.
This represented about 650' of liner in Lateral D and about 400' of liner in Lateral A before finally mixing with raw water at the WEMS Settling Basin.After the installation of the concrete pipe, the main lateral was impacted from Catch Basin 8A to the WEMS. The Emergency Retention Basin also drained into the main lateral at Catch Basin 18A. See Exhibit 2 of Appendix A for a Map of the SDS Laterals.When the concrete pipe was installed, approximately 7700 cubic yards of earth was required to bring the ditches back up to grade. It is not known where this backfill material was obtained.3.1 Disposition of Materials in the Post-Shutdown Period Following termination of operations of the 60 MW and mock-up reactors on January 5, 1973 through June 3 0 th of 1973, the WEMS remained active and was maintained in that condition until there was no radiological release hazard. The final end condition was that the WEMS was deactivated and the gates opened to the Pentolite Ditch. Prior to deactivation, the following conditions were met: , No liquid radioactive waste discharges had occurred for two months, 19 Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0* 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 lxil-7 O Ci/ml beta-gamma and 3x10 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 slit and sand. Unnecessary loose equipment was removed from the WEMS Butler Building, as were scrap materials inside and outside; electrical heaters and other equipment were shutdown after a WEMS test and the building closed and locked.Subsequent to July 1 st of 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 federal regulations.
Reports to the NRC provide the details of significant events or changes in status during the period between 1973 and the approval of the PBRF Decommissioning Plan in 2002.Radiological characterization information to support decommissioning of PBRF was developed in the 1985 Teledyne Isotopes Characterization Survey and the 1998 GTS Duratek Confirmation Survey. The 1985 study indicated that the accumulated silt in catch basins had gross beta activity ranging from 7 to 330 pCi/g, with an average of 44 pCi/g. Depths and areas of contamination were not reported.The catch basins were reexamined in the 1998 survey. The beta survey showed that one sample had a maximum concentration of 5,000 dpm/100-cm 2 , and the remaining 2 samples had an average concentration of less than 1,200 dpmrl00-cm
.The 1998 gross beta gamma activity measurements were on the order of 15 to 20 pCi/g, similar to the 1985 measurements (44 pCi/g). The 1998 sampling effort also showed that the activity in the catch basins is predominately naturally occurring K-40 at concentrations from 7 to 14 pCi/g. The concentration of Cs-137 and Co-60 ranged from 1 to 11 pCi/g and from 1 to 5 pCi/g, respectively.
Following termination of reactor operations in early 1973, the storm drains, pipe trenches & other sub-surface systems remained active and were to be maintained in acceptable condition for effluent flows from the operable building groundwater sump pumps and storm drainage.Before and after July 1 st of 1973, the storm drains, pipe trenches & other sub-surface systems were controlled according to AEC/NRC licenses.
Periodic effluent sampling for radioactivity was conducted as part of the PBRF facility environmental monitoring program to demonstrate compliance with AEC/NRC regulations for effluent discharges.
3.2 Decommissioning In general, the Storm Drains, Pipe Trenches and Other Sub-Surface Excavations were remediated in the following manner: 20 Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0* Geographical boundaries of the area of excavation were marked, flagged or identified in some manner.* Utilities were identified and de-energized.
- Area was cleaned and grubbed of vegetation.
- SDPTSSE was excavated and safety boundaries were established.
- Excavations were inspected periodically." Areas remediated based on contamination levels.* Excavation was guided by walkover scan surveys and excavated soil was segregated." The soil >DCGL was shipped to an approved waste disposal facility." Soil < DCGL was transported to the soil farming area, within the PBRF Restricted Area, for FSS.Most of the soil < DCGL was surveyed and sorted using the MACTEC Development Corporation SS-Series Conveyor Soil Survey and 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 action level was 50% of the DCGL. Rejected materials were staged for shipment to an approved waste disposal facility.
18 Post remediation surveys were performed to ensure that the remediation was complete.
Results were compared to the scan action level which was set at 50% of the applicable DCGL. 1 9 This Final Post Remediation (FPR) surveys and samples established that no further remediation was necessary prior to commencing Final Status Survey for the SDPTSSE. The Storm Drain, Pipe Trench and Sub-Surface Excavations were prepared for FSS and surveyed in accordance with the FSSP[NASA 2007].4.0 Survey Design and Implementation for Storm Drains, Pipe Trenches & Other Sub-Surface Excavations The survey design and implementation for SDPTSSE is as follows:* Section 4.1 discusses 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.
18 FSS of Excavated Materials is reported in the FSSR Attachment 18.19 Investigation levels are established for 2"x2" NaI detector with Ludlum Model 2350-1 that is set up with either the Cesium-137 window or the Cobalt-60 window depending on the radionuclide distribution identified.
21 Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0" 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 mrern/yr plus ALARA.The NRC dose limit applies to residual radioactivity that is distinguishable from background.
The DCGL values established in 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 3 of this report. The DCGL values are the volumetric activity concentrations 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 3, 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, the Resident Farmer exposure scenario was implemented in RESRAD Version 6.0.Section 7.3.1 of the FSSP [NASA 2007] states that sub-surface survey units that have had remediation performed, shall have FSS performed and results compared to surface soil DCGLs.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-8.22 Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 4.1.2 DCGL for Other Media In accordance with the FSS Plan [NASA 2007], the DCGL for sediment 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, and FSS of the PBRF". Current and representative sample data were used to determine the final radionuclide mixtures for FSS.Per NUREG-1757
[USNRC 2006], 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 is 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 mremnyr is reviewed for compliance with the unrestricted use limit.4.1.4 Surrogate DCGL and the Unity Rule There are two distinct types of surrogate DCGLs, at PBRF. The first surrogate DCGL is for surface soil scanning with Nal detector model 44-10 and the second is for surface and sub-surface soil sample analysis.
Technical Basis Document TBD-PBRF-09-001, "Radionuclide Distributions and Adjusted DCGLs for Site Soils"[PBRF 2009] developed a surrogate DCGL value (DCGLsuR) for the hard-to-detect (HTD) radionuclide of concern, Sr-90, using Cs-137 or Co-60. Table 2-1 of Technical Basis Document TBD-PBRF-09-001 provides the DCGLs for surface soil, based on analysis of numerous characterization sample results. Furthermore, NUREG- 1757 allows for the de-selection of radionuclides that contribute no greater than 10% of the 25 mrem/yr dose criteria.For PBRF soils, the dose from all radionuclides other than Co-60, Sr-90 and Cs-137 totaled 0.5 mrem/yr. Because this dose is only 2% of the 25 mrem/yr. limit, all radionuclides, other than Co-60, Sr-90, and Cs-137, were eliminated from further consideration.
To ensure the 25 mrem/yr. criterion is met, the maximum allowable dose for Open Land Survey Units, at PBRF, shall be: Maximum allowable dose for Open Land Survey Unit, at PBRF =23 Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 25 mrem/yr. (annual dose limit) -0.5 mrem/yr. (the maximum dose from de-selected radionuclides)
= 24.5 mrem/yr.Table 5-2 of PBRF-09-001 provides the values for surrogate DCGLs for each open land area at PBRF. The values were derived from characterization sample analysis that was used to determine the isotopic mix of Co-60, Sr-90, and Cs-137 for that area. Based on the characterization data, the predominant radionuclide was determined to be either Co-60 or Cs- 137, and the other radionuclides were surrogated to the predominant radionuclide.
During scanning activities, the Nal detector is set up in the "windowed mode" to detect the predominant radionuclide for that area, either Cs-137 or Co-60. The other radionuclides are surrogated to the predominant radionuclide and the DCGLsUR are provided in Table 5-2 of Technical Basis Document TBD-PBRF-09-001.
During soil sample analysis, both Cs- 137 and Co-60 can be easily detected by gamma spectroscopic analysis.
Therefore, only Sr-90 needs to be surrogated to the predominant radionuclide.
These soil sample DCGLsUR are determined in the survey design for that survey unit.See Table 4 for the Surrogate DCGLs that were used for SDPTSSE FSS.Table 4, Surrogate DCGLs for Soil FSS Scan Soil Location Activity Fractions Surrogate Survey Sample Radionuclide DCGLsuR DCGLsUR Cs-137 Co-60 Sr-90 (pCi/g) (pCi/g)Default for PBRF site and 0.912 0.007 0.081 Cs-137 11.55 11.82(1)Spill Areas 4, 5& 6 Spill Areas 1, 2 0.201 0.714 0.085 Co-60 3.28 3.50(2)Emergency 0.878 0.037 0.085 Cs-137 10.31 11.40)Retention Basin Table 4 Notes: 1. Co-60 soil sample DCGL is 3.8 pCi/g, per Survey Designs 30, 33, 37 and 44.2. Cs-137 soil sample DCGL is 14.7 pCi/g, per Survey Design 39.3. Co-60 soil sample DCGL is 3.7 pCi/g, per Survey Design 46.A unity rule calculation was performed on the sample results to quantify the total activity for each sample.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: 24 Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 S u r r o g a t e ,, .= I) ( -)[(DCGLs,)
+(DCGL 2 _DCGL 3 DCGL.)] (Equation 1)Where: DCGLsuR = Surrogate radionuclide DCGL DCGL 2, 3.. .n = DCGL for radionuclides to be represented by the surrogate Rn = 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: C1 + C 2 Cn <+ -+....... -<DCGLI DCGL 2 DCGL. (Equation 2)Where: C, = concentration of radionuclide n and DCGLn = DCGL of radionuclide n.4.1.4.3 Area Factors The area factor is the multiple of the DCGL that is permitted in an area of elevated residual radioactivity without requiring remediation and still be in compliance with the release criteria.
It 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 calculated as the ratio of dose per unit area or volume for the default surface area for the applicable dose modeling scenario to the dose calculated using the area of elevated residual radioactivity, AEMC. Area factors for surface soil are provided in Table 3-4 of the FSSP [NASA 2007] and are shown in Table 5.Area factor assumptions and calculations are provided in Attachment B of the FSSP [NASA 2007].25 Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 Table 5, Surface Soil Area Factors Elevated Area 1 2 3 5 10 15 25 100 250 2,000 m2)(in 2)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 6. Note that the maximum survey unit size for Class 1 surface soils is 2,000 in 2.Table 6, Recommended Survey Unit Area Size Requirements for FSS Class Land 1 up to 2000 m2 2 up to 10,000 M 2 3 Up to 100,000 in 2 4.1.4.5 Scan Coverage for Class 1 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.
No Class 2 or Class 3 survey units were identified within the SDPTSSE. Minimum scan survey coverage requirements for the PBRF are provided in Table 5-1 of the FSSP [NASA 2007] and Table 7 below.Table 7, Minimum Scan Survey Coverage By Classification Scan Survey Coverage Class 1 Class 2 Class 3 Scan Coverage 100% 10 tol100% Minimnum ofl10%26 Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 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 SDPTSSE areas were not fully characterized or remediated.
The only reference to SDPTSSE areas identified in the FSSP is provided in Table 2-2 and states that Drainage Systems (Storm Sewers) are Class 1 areas. Therefore, based on the information provided in the FSSP and that remediation was conducted in the SDPTSSE areas, all SDPTSSE are considered Class 1 areas.Refer to Figure 1 and Exhibit 1 of Appendix A for a location map of each survey unit. Table 6 provides the current classification of the area and the corresponding FSSP [NASA 2007] classification for the area. See Appendix B for a map of each specific survey unit contained within this report.Table 8 was reviewed to ensure that no areas were classified "downward" from classifications assigned in the FSS Plan [NASA 2007]. "OL" refers to "Open Land".Table 8, Storm Drains, Pipe Trenches and Sub-Surface Excavations Survey Unit Classification Comparison to FSSP Survey FSSP Unit Class Description"l)
FssP (2)UnitClassification(2 OL-1-1 1 Storm Drains -Section 2-1 1 OL-1-2 1 Storm Drains -Section 2-2 1 OL- 1-3 1 Cold Retention Basin North 1 OL-1-4 1 Cold Retention Basin South 1 OL- 1-5 1 Cold Retention Basin East West Ramp 1 OL-1-6 1 Storm Drains Phase #1 1 OL-1-7 1 Storm Drains Phase 2, Section 1 1 OL-1-8 1 Storm Drains Phase 2, Section 2 1 OL-1-9 1 Storm Drains W, NW & N of SEB 1 OL- 1-10 1 Storm Drains SE of PPH 1 OL-I-1I 1 Phase 4, Section 1 1 OL-1-12 1 Storm Drains, Lateral D, North Section 1 OL-1-13 1 Storm Drains, Lateral D, North Section 1 OL-i-14 1 Storm Drains, South & East of SEB 1 OL-1-15 1 Storm Drains, Main Lateral, South of FH-110 1 OL-1-16 1 Storm Drains, Lateral A, East of Line 3 Road 1 OL-1-17 1 Storm Drains, Lateral D, South Section & STS46 Trench 1 27 Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 Table 8, Storm Drains, Pipe Trenches and Sub-Surface Excavations Survey Unit Classification Comparison to FSSP Survey FSSP Unit Class Description(1 C)laSSi (2)UnitClassification(2 OL-1-18 1 SANS Trenches South of HL Building 1 OL- 1-19 1 RCRA Trenches South of SEB 1 OL-1-20 1 Northeast Corner of FH/WHB Footprint 1 OL-1-21 1 Southeast Corner of FH/WHB Footprint 1 OL-1-22 1 Western Sections of FH/WHB Footprint 1 OL-1-23 1 UST Excavations 1 OL-1-24 1 Evaporator Pit 1 OL-1-25 1 Phase 7 North of Haul Road, South of FH/WHB 1 OL-1-26 1 ERB Sump Drain Line Excavation 1 OL-1-33 1 Storm Drain Excavation-MacTec Crossover 1 OL-1-34 1 Storm Drain Excavation-Crossover south of SEB 1 OL-1-35 1 Storm Drain Excavation-Crossover at Line 3 1 Road/Driveway E Storm Drain Excavation-Line 3 Road North Crossover OL-1-37 1 Storm Drain Excavation-Line 3 Road South 1 Crossover OL-1-38 1 Storm Drain Excavation-Haul Road Crossover 1 OL-1-39 1 Storm Drain Excavation
-Trench South of Sludge 1 Basins, East of SEB OL-1-40 1 Storm Drain Excavation
-CB- 18 Excavation 1 OL-1-41 1 Storm Drain Excavation
-CB-5A Excavation 1 OL-1-42 1 Resin Pits Excavation South of PPH 1 01-1-43 1 Storm Drain Excavation-Lateral C South Excavation 1 01-1-44 1 Storm Drain Excavation-Lateral C North Excavation 1 01-1-45 1 Excavations South of Waste Storage Pad 1 Table 8 Notes: 1. The data provided in the description are provided in the Survey Unit Log and the Survey Unit Release Records. See Figure 1 for a map of SDPTSSE that identifies the survey unit locations.
- 2. The FSSP Classifications are based on Table 2-2 of the FSSP which identifies Drainage Systems (Storm Sewers) as being Class 1.Table 9 provides the survey unit breakdown, by MARSSIM classification
[USNRC 2000].28 Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 Table 9, Storm Drains, Pipe Trenches and Other Sub-Surface Excavations Survey Unit Breakdown by MARSSIM Classification No. of Surface % of % of Surface Average Area of Class Survey Area Survey Areac Suveyag Unt (o)Units (M 2) Units Area Survey Units 1 39 25268 100 100 648 4.2 Number of Measurements and Samples The Final Status Survey for SDPTSSE was covered by several Survey Design and Survey Request (SR) documents.
See Appendix B for specific sample locations within each survey unit. Table 10 identifies the Survey Design that was implemented for each SDPTSSE survey unit. The following Survey Requests (SRs) were used for SDPTSSE survey units: Survey Request Numbers 164, 165, 169, 176, 204, 237, 242, 244, 277 and 279.The number of measurements and samples for each SDPTSSE survey unit was determined using the MARSSIM [USNRC 2000] 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 [3 =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 SDPTSSE.2° When the Sign Test is selected, the VSP software uses MARSSIM [USNRC 2000] Equation 5-2 to calculate the number of measurements.
Equation 3 of this report is Equation 5.2 from the MARSSIM and is shown below: 1+ (Equation 3)N =1.2 (la+Z-l)Where: a -1.2 = adjustment factor to add 20% to the calculated number of samples, per a MARSSIM requirement to provide a margin for measurement sufficiency, N = Number of measurements or samples, 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.p = proportion of standard normal distribution
< 1 -P3 (1.2816 for P3 = 0.1), (D (A/a) = value of cumulative standard normal distribution over the interval -o0, A/a, 20 The FSS Plan (Section 5.2.4) states that a qualified software product, such as Visual Sample Planc [PNL 2010], may be used in the survey design process.29 Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 A = the "relative shift", defined as the DCGL -the Lower Bound of the Gray Region (LGBR), and C = the standard deviation of residual contamination in the area to be surveyed (or a similar area).The MARSSIM module of VSP [PNL 2010] requires user inputs for the following parameters:
a, P3, A, a and the DCGLw. The number of measurements, N, for the 39 SDPTSSE survey units were calculated in six survey designs. Table 10 summarizes the survey design calculations and lists the values of the key VSP input parameters.
Table 10, Storm Drains, Pipe Trenches & Other Sub-Surface Excavations Survey Design Summary Design LGBR/ (5) (5)No.(1)(2)(3)
Survey Units(4) Class DCGL(s) LGBR(-) DCGL A) A/C N OL-1-1, OL-1-2 and 30 OL-1-6 1 11.55 11.26 0.975 0.29 0.11 2.64 11 33 OL-1-3 and OL-1-4 1 11.55 11.26 0.975 0.29 0.15 1.93 11 37 OL-1-3 and OL-1-5 1 11.55 11.26 0.975 0.29 0.15 1.93 11 OL-I-10, 1 3.577- 3.05 0.87 0.45 0.15 3.0 11 39 OL-1-42, and 1 3.5(6) 3.05 0.87 0.45 0.15 3.0 11 OL-1-45 1 3.5(6) 3.05 0.87 0.45 0.15 3.0 11 OL-1-7, OL-1-8, OL-1-9, OL-1-11 through OL- 1-25, 44 OL-1-33 through 1 11.55 11.26 0.975 0.29 0.10 2.90 11 OL-1-41, OL-1-43 and OL- 1-44 46 OL-1-26 1 10.31 5.7 0.5 5.7 2.28 2.5 11 Table 10 Notes: 1. The data reported in Table 10 is taken from the Survey Design reports listed. They are maintained in the PBRF Document Control System.2. Small differences in the values in this table and the values documented in the Survey Design reports are due to spreadsheet rounding and significant figures.3. Values provided in the table are typical values for the survey units within that specific design.4. Survey Units OL-1 -27 through OL-1-32 are located in the ERB and are covered in the FSSR Att. 10.5. Units are in pCi/g.6. Co-60 DCGL.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 [PNL 2010] 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 [PNL 2010] report for survey unit OL-1-26 in Design No. 46 (with modifications).
The sensitivity of N is explored by varying the standard deviation from 2.28 to 4.56 pCi/g (an increase of 100%), with the lower bound of gray region from ranging from 50 to 70 % of the DCGL. The value of beta, probability of mistakenly concluding that the survey units mean concentration is greater than the DCGL is varied 30 Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 from 0.05 to 0.15. While the VSP [PNL 2010] sensitivity analysis also varies the value of a, the sensitivity of N to changes in a is not evaluated here.Table 11 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 70% of the DCGL. This range corresponds to A/a ranging from 1.5 to 2.5. The sensitivity of N to expected measurement variability is examined first. With the LBGR* set to 60%, a = 0.05 and 03 = 0.10, a 100 % increase in a increases N from 12 to 23. At this LBGR value, N is sensitive to measurement variability.
With the LBGR set to 50% of the DCGL, the sensitivity of N to a is decreased; a 100 % increase in a increases N from 11 to 17.However, in contrast, the sensitivity of N to an incorrect conclusion that the survey unit will pass (owner's risk) is low. With the LBGR set at 60 %, of the DCGL (holding a and a constant) and increasing 03 from 0.10 to 0.15, decreases the number of measurements from 12 to 10. With the LBGR set at 50 %, of the DCGL, (holding a and a constant) and increasing 03 from 0.10 to 0.15, decreases the number of measurements from 11 to 9. These results show that N = 11 represents a reasonable number of measurements for FSS of the SDPTSSE, in view of parameter values applied to the designs.Table 11, Sensitivity Analysis for OL-1-26 Design Number of Samples DCGL = 11.55 =0.05 12) ct=0.10 a7=0.15 a =4.56 1) 3) a = 2.28 a = 4.56 a = 2.28 a = 4.56 a = 2.28 LBGR=70% (1)(4) 13=0.05 44 18 35 14 29 12 13=0.10 35 14 27 11 22 9 P 13=0.15 29 12 22 9 18 7 LBGR=60% 13=0.05 28 15 23 12 19 10 13=0.10 23 12 17 9 14 8 13=0.15 19 10 14 8 12 6 LBGR=50% 13=0.05 21 14 17 11 14 9 13=0.10 17 11 13 9 11 7 13=0.15 14 9 11 7 9 6 Table 11 Notes: 1. Units of DCGL, a 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). f3 = 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 survey units) and to display the measurement locations on survey unit maps drawn to scale.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 solely by the Sign Test. If the scan sensitivity was not below the DCGLw, the number of 31 Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 measurements was increased as determined by the Elevated Measurement Comparison.
2 1 4.3 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 [USNRC 2000] class of each survey unit.Scan sensitivities for detectors used for walkover gamma scans of soil are determined using the method referenced in the PBRF FSS Plan and described in NUREG- 1507 [NRC 1998]. Scan sensitivities for the Ludlum Model 44-10 Nal detectors used in FSS of soils at PBRF were developed in a technical basis document[PBRF 2009a]. The method is summarized and the key equations presented.
The scan MDC is calculated using the following equations adapted from NUREG-1507
[USNRC 1998] for gamma scanning with Nal detectors:
MDCRSURV = d' 60) (Equation 4)MDCscan -_ dMCRID Conv
- MSo (Equation 5)Where: MDCsuRv = the minimum detectable count rate in cpm that can be reliably detected by the "surveyor" d'= index of sensitivity, unit less (MARSSIM default value of 1.38 is assigned), bi= background counts observed in the interval i, i = observation interval (s), p = surveyor efficiency, unit less (MARSSIM default value of 0.5 is assigned), MDCscan = the scan MDC, here in units of pCi/g, Conv = instrument response conversion factor, units of cpm per gR/h, MS, = instrument response in units of jsR/h per pCi/g (determined empirically or with a shielding algorithm).
Site-specific parameter values for the MDCscan equation are obtained from the technical basis document [PBRF 2009a]. The most conservative instrument response conversion factor for detectors in the PBRF LMI 44-10 inventory is 232.39 cpm per 2' As discussed in the next section, the scan sensitivities of instruments used in the FSS of the SDPTSSE were below the DCGLw, and no increase in the number of measurements calculated using the Sign Test was required.32 Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 jtR/h for Cs-137 and 262.21 for Co-60. The instrument response factors for Cs-137 and Co-60 respectively are 0.138 and 0.667 jtRih per pCi/g.In accordance with the FSSP [NASA 2007], gamma scanning was performed over land surfaces to identify locations of residual surface activity.
NaI 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 SDPTSSE is provided in Table 12. Measurement sensitivities provided in this section relate both to the gamma scan sensitivities and the static measurement sensitivities.
Table 12, Typical Detection Sensitivities of 44-10 for Co-60 and Cs-137 Co-60(1) Cs- 137(4(5)Background MDCR(2) MDCscan MDCR1 2 1 MDCscan(4)(cpm) (ncpm){3) (pCi/g) (ncpm){3) (pCi/g)50 50.3 1.50 71.2 3.13 100 71.2 2.13 100.6 4.43 150 87.1 2.61 123.2 5.42 200 100.6 3.01 142.3 6.26 250 112.5 3.36 159.1 7.00 Table 12 Notes: 1. Per SR-39, the scan action level is 150 ncpm for Co-60. This value applies to survey units OL-I-10, OL-1-42, and OL-1-45.2. MDCR = Minimum Detectable Count Rate.3. ncpm = net counts per minute=gross counts per minute -background counts per minute.4. Per SRs 30, 33, 37, and 44 the scan action level is 250 ncpm for Cs-137. This value applies to all remaining survey units contained within the SDPTSSE Attachment to the FSSR.5. Per SR-46, the scan action level is 241 ncpm for Cs-137. This value applies to survey unit OL-1 -26.33 Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 5.0 Storm Drains, Pipe Trenches & Other Sub-Surface Excavations Survey Results Results of the SDPTSSE 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 SDPTSSE 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., MDCSCa, investigation levels, soil sample number and location, statistical tests, and EMC tests).5.1 Surveys and Investigations 5.1.1 Scan Surveys Scan surveys were performed in accordance with the FSS requirements contained in the following Survey Requests:* SR-164 (survey unit OL-1-1),* SR-165 (survey unit OL-1-2),* SR-169 (survey units OL-1-3 and OL-1-4),* SR-176 (survey units OL-1-3 and OL-1-5),* SR-204 (survey units OL-1-6),* SR-237 (survey units OL-1-9, OL-I-11 through OL-1-25, OL-1-33 through OL-1-41, OL-1-43, and OL-1-44),* SR-242 (survey units OL-1-9 through OL-1-25, and OL-1-33 through OL-1-45)* SR-244 (survey units OL-I-10, OL-1-42, and OL-1-45),* SR-277 (survey unit OL-1-26), and* SR-279 (survey unit OL-1-26).100% of all Class 1 survey units were scanned with the Ludlum 2350-1 with the 44-10 detector setup with a window for either Cs-137 or Co-60 energies.
A scan action 34 Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 level of 250 ncpm, for Cs-137, was established, per the SR (Except for those survey units covered by SR-244 which provided a scan action level of 150 ncpm, (for Co-60) and the survey unit covered by SR-277 (OL- 1-26), which had an action level of 241 ncpm (for Cs- 137). The scan action levels were determined by estimating a background count rate for the area and establishing an action level at a value less than the DCGL, typically 75% of the DCGL.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 SDPTSSE scan surveys are compiled in Table 13. See Exhibits 7, 8 and 14 of Appendix A for a photograph of radiological surveys being conducted after SDS disassembly.
Table 13, Scan Survey Results CSurface Area Surface Area I of Survey Unit of Survey Unit Scan QC Replicate Investigation Survey a SR # Survey Scan Coverage Level Unit s (in Square (in Square Coverage (%)(2) Exceeded Meters) Feet) (%)OL-1-1 1 164 1323 14246 100 5.99 No OL-1-2 1 165 1834 19738 100 5.7 Yes(3)OL-1-3 1 169/176 1193 12843 100 5.5 Yes7 3 T OL-1-4 1 169 1329 14306 100 7.0 No7T-OL-1-5 1 176 190 2049 100 13.4 Yes7 3 T OL-1-6 1 204 1166 12548 100 7.1 No OL-1-7 1 237 801 8619 100 6.0 No OL-1-8 1 237 537 5777 100 7.8 No OL-1-9 1 237/242 1954 21036 100 5.7 No OL-1-10 1 244 221 2380 100 8.4 No OL-1-11 1 237/242 222 2385 100 6.3 No OL-1-12 1 237/242 1175 12647 100 6.3 No OL-1-13 1 237/242 1175 12653 100 7.6 No OL-1-14 1 237/242 1377 14818 100 7.5 No OL-1-15 1 237/242 1691 18199 100 5.8 No OL-1-16 1 237/242 1332 14333 100 7.5 No OL-1-17 1 237/242 805 8670 100 5.9 No OL-1-18 1 237/242 362 3900 100 15.4 No OL-1-19 1 237/242 202 2171 100 5.5 No OL-1-20 1 237/242 885 9527 100 6.3 No OL-1-21 1 237/242 895 9637 100 7.0 No OL-1-22 1 237/242 549 5912 100 30.4 No OL-1-23 1 237/242 255 2747 100 27.3 No OL-1-24 1 237/242 222 2386 100 6.7 No OL-1-25 1 237/242 956 10287 100 6.7 No 35 Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 Table 13, Scan Survey Results CSurface Area Surface Area C of Survey Unit of Survey Unit Scan QC Replicate Investigation Survey a SR # Survey Scan Coverage Level Unit s Coverage (%) (2) Exceeded s(in Square (in Square(% ()s Meters) Feet)OL-1-26 1 277/279 118 1268 100 6.3 No OL-1-33 1 237/242 93 998 100 5.0 No OL-1-34 1 237/242 61 660 100 5.3 No OL-1-35 1 237/242 77 827 100 5.4 No OL-1-36 1 237/242 97 1041 100 9.6 No OL-1-37 1 237/242 82 879 100 5.7 No OL-1-38 1 237/242 88 947 100 10.6 No OL-1-39 1 237/242 267 2877 100 7.0 No OL-1-40 1 237/242 74 796 100 21.1 No OL-1-41 1 237/242 151 1622 100 6.8 No OL-1-42 1 242/244 171 1844 100 5.4 No OL-1-43 1 237/242 518 5579 100 5.4 No OL-1-44 1 237/242 675 7268 1 100 5.2 No OL-1-45 1 242/244 146 1571 100 15.3 No Table 13 Notes: 1. The % scan coverage is given as the % of the area scanned in the initial survey. For Class 1 areas, 100% scan is required per Table 5-1 of the FSSP and Table 7 of this report.2. Obtained from Survey Unit Release Records.3. Refer to Section 5.1.2 of this report for an explanation of these survey unit investigation levels.The results provided in Table 13 show that scan coverage requirements were satisfied for all survey units. Table 13 results also shows that scan investigation levels were exceeded in only 3 out of 39 survey units.5.1.2 Investigative Measurements and Judgmental Soil Samples As identified in Table 13, three survey units (OL-1-2, OL-1-3 and OL-1-5) were documented to have investigative measurements or judgmental soil samples collected within their boundaries.
A description of the additional surveys and sampling conducted in each of the four survey units is as follows: Survey Unit OL-1-2 is located in the southern section of the protected area, north of Pentolite Road and East of Line 2 Road. During scanning of the survey unit, one area of elevated activity, > the scan investigation level, was identified in the far eastern portion of the survey unit. The area was identified as IM-I and was approximately 1 ft 2 of surface area. The scan indicated 322 ncpm at location IM-1. Surface (0-6") and sub-surface (6"-12") sampling was performed at this location, under SR-165. The sample results indicated that the surface (0-6") soil sample contained measured Cs-137 activity of 4.22 pCi/g and no detectable Co-60 activity.
The subsurface (6"-12") sample at location IM-1 indicated Cs-137 activity of 0.747 pCi/g and no detectable Co-60 activity.
No further action was taken.36 Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 Survey Unit OL-1-3 is located where the North Cold Retention Basin (CRB-1) resided. This survey unit originally encompassed the North CRB and the area between the North and South CRBs.However, elevated activity was identified on the area between the North and South CRBs. FSS performed under Survey Design #33 indicated that the Survey Unit needed additional remediation.
Surveys confirmed that broken piping in the south side of survey unit OL-1-3 was contaminated with activity levels > 50,000 dpmr/100 cm 2 , beta. All piping found was removed for disposal.
Investigative surveys were performed after FSS was suspended on OL-1-3 and indicated that the area of elevated activity was limited to the ramp separating the North and South Retention Basins. Volumetric samples of the pipe scrapings/pieces yielded 622 pCi/g Cs-137 and 61 pCi/g Co-60 .The area of elevated activity was separated from OL-1-3 and a new survey unit was created, OL- 1-5.Four additional samples were collected within OL-1-3 and identified as IM-1 through IM-4. The samples were collected from the bottom of the North CRB excavation.
The reason for the samples being collected was because during scanning, there was some standing water present and the FSS Lead Engineer requested soil samples to ensure that the scan results were representative of the conditions present in the excavation.
The results of the soil sampling indicated no detectable Cs-137 or Co-60 activity was present in any of the four samples.Survey Unit OL-1-4 is located where the South Cold Retention Basin (CRB-2) resided. Four additional samples were collected within OL- 1-4 and identified as IM-I through IM-4. The samples were collected from the bottom of the South CRB excavation.
The reason for the samples being collected was because during scanning, there was some standing water present and the FSS Lead Engineer requested soil samples to ensure that the scan results were representative of the conditions present in the excavation.
The results of the soil sampling indicated no detectable Cs-137 or Co-60 activity was present in any of the four samples. No further action was taken.* Survey Unit OL-1-5 is located between where the North and South CRBs resided. There were three areas prompting investigations in survey unit OL-1-5: o One area, that was 2.5' x 4', was located on the west side of OL-1-5 near a partially buried radioactive pipe. Three soil samples (SR-176-25 through SR-176-27) and three static measurements (N-1 through IM-3) were obtained in this area.o The average Cs-137 and Co-60 activity of the soil samples taken in this area was 24.9 pCi/gm Cs-137 and 4.9 pCi/gm Co-60. These average values are well below the calculated DCGLEMc based on an area factor of 10.4 as found in Table 4, and utilizing the following equation from Procedure CS-09, step 4.5.2 where: 37 Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0" AFi= 10.4* DCGLw = 11.82 (Cs-137 DCGLsuR for Cs-137 and Sr-90)* DCGLEMC = 122.9 DCGLEMc = AFi x DCGLw o Compliance with soil DCGLEMC was determined using the gamma spectroscopy results for SR-176-25 through SR-176-27 and a unity rule calculation performed utilizing the following equation from CS-09, step 4.5.3 where:* Cs-137 = 24.9 pCi/gm* Cs-137DCGLEMC=
122.9 pCi/gm* Co-60 = 4.9 pCi/gm* Co-60DCGLEMC
= 39.52 pCi/gm (Cs-137 / Cs-137DCGLEMc)
-# (Co-60 / Co-60 DCGLEMC)* The product of this calculation (unity fraction) is 0.327 and is < 1.0.o An elevated measurement test was performed utilizing the following equation from Procedure CS-09, Section 4.2 where:* 6 = the average residual activity in the survey unit = 1.16 pCi/gm* DCGLw = 11.55 (Cs-137 DCGLsuR for Cs-137, Sr-90 & Co-60)a average concentration in the elevated area -8 = 23.7 pCi/gm* Area Factor = 10.4 35 + (average concentration in elevated area -)<' 1.0 DCGLw (Area Factor)(DCGLw)
- The result of this calculation is 0.29 and is < 1.0.Since the calculated value is determined to be < 1.0, the area passes the EMC determination and no further action is required.The other two elevated areas were both small in surface area, < 100 cm 2.The highest Cs-137 soil sample activity from these two elevated locations was 7.1 38 Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 pCi/g, which is < the DCGLw value (for Cs-137, and all Co-60 activities were < MDA. Therefore, no further actions were taken on these areas.5.1.3 Systematic Soil Sampling 5.1.3.1 Soil Sampling for Class I Areas Systematic soil sampling was conducted within each of the 39 survey units that constitute the SDPTSSE in accordance with the FSSP [NASA 2007] and the applicable Survey Request.Systematic soil samples were identified in each survey unit, by VSP, in accordance with procedure CS-08, Final Status Survey Design.As stated in Table 4, the DCGLsuR for soil sampling is 11.82 pCi/g for Cs-137 and the DCGLw is 3.8 pCi/g for Co-60 in accordance with Survey Design #'s 30, 33, 37, and 44. The DCGLw for soil sampling is 14.7 pCi/g for Cs-137 and the DCGLSUR is 3.5 pCi/g for Co-60 in accordance with Survey Design # 39. The DCGLsUR for soil sampling is 11.4 pCi/g for Cs-137 and the DCGLw is 3.7 pCi/g for Co-60 in accordance with Survey Design # 46. Compliance with the DCGL is demonstrated through the use of the unity rule. The results are as follows: " Four hundred and seventy-one (471) samples, including 40 QC samples, from 431 sample locations were processed and analyzed.* Of the 471 original samples collected and analyzed, 48 were > MDA for Cs-137 and 1 sample was >MDA for Co-60.* The highest Cs-137 activity was in Survey Unit OL-1-25 at location Sample Point (SP)-2. The Cs-137 activity at this location was 8.80E-01 pCi/g +/- 2.22 E-01 pCi/g. The measured Co-60 activity at this location was <MDA. The highest Co-60 activity measured was in Survey Unit OL-1 -4 at location SP-5.The Co-60 activity at this location was and 1.00E+00 pCi/g +/- 1.76E-01 pCi/g. This is the only sample result > the Co-60 MDA. The Cs-137 activity measured at this location was 5.83E-01 pCi/g +/- 1.76E-01 pCi/g." The average activity for all systematic soil samples, collected within Class 1 areas,'was 1.06E-01 pCi/g for Cs-137 and 1.14E-01 pCi/g for Co-60.2 2 Refer to Table 14 of this report for a summary, by survey unit, of the average and maximum Cs-137 and Co-60 systematic soil sample results. Additionally, refer to Appendix B of this report for systematic soil sample locations, by survey unit. Also, refer to Appendix C of this report for all systematic soil sample results, by survey unit.22 The average activity was determined by using the MDA value if the activity was determined by quantitative analysis to be at or below the MDA.39 Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 5.1.3.2 Quality Control Sample Analysis The SRs required splitting 5% of samples for QC purposes.
Forty (40) of the 431 samples, or 9.3 %, were split for QC analysis.Forty Quality Control (QC) samples were collected and analyzed in Class 1 areas.All 40 samples were analyzed and the results compared to the original sample results. The comparison was in accord with the method in the FSS Plan, Section 12.7.2 [NASA 2007]. In this method the sample resolution is calculated as the quotient of the original sample one-sigma uncertainty and the sample result. Then the ratios of QC to original sample results are compared to acceptance values specified for each range of resolution given in FSS Plan Table 12.2. The ratios were all within the acceptable range provided in Table 12.2. See Appendix C for QC Comparison results.40 Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 Table 14, Storm Drains, Pipe Trenches & Other Sub-Surface Excavations Systematic Soil Sample Results By Survey Unit Cs-137, DCGLw = 11.82 pCi/g() Co-60, DCGLw = 3.80 pCi/gd 1)Maximum Test Average Test Maximum Test Average Test Maximum Result: Result: Maximu Result: (pCi/g) Result: Average Survey No. of (pCi/g) Maximum (pCig) Average < (pCi/g) (2) Unity Aeae<Maximum Average < Unt Unit ID Measurements
< DCGLw DCGLw < DCGLw DCGLw Fraction (2)OL-1-1 11 0.162 Yes 0.060 Yes 0.076 Yes 0.060 Yes 0.021 OL-1-2 11 0.428 Yes 0.428 Yes 0.076 Yes 0.054 Yes 0.050 OL-1-3 11 0.190 Yes 0.077 Yes 0.134 Yes 0.119 Yes 0.038 OL-1-4 11 0.583 Yes 0.125 Yes 1.000 Yes 0.191 Yes 0.061 OL-1-5 11 0.303 Yes 0.100 Yes 0.129 Yes 0.114 Yes 0.039 OL-1-6 11 0.102 Yes 0.080 Yes 0.137 Yes 0.117 Yes 0.038 OL-1-7 11 0.112 Yes 0.070 Yes 0.128 Yes 0.104 Yes 0.033 OL-1-8 11 0.087 Yes 0.073 Yes 0.120 Yes 0.110 Yes 0.035 OL-1-9 11 0.112 Yes 0.077 Yes 0.141 Yes 0.120 Yes 0.038 OL-I-10(3) 11 0.205 Yes 0.085 Yes 0.136 Yes 0.116 Yes 0.039 OL-1-11 11 0.150 Yes 0.080 Yes 0.133 Yes 0.120 Yes 0.038 OL-1-12 12 0.179 Yes 0.085 Yes 0.138 Yes 0.115 Yes 0.038 OL-1-13 11 0.209 Yes 0.082 Yes 0.117 Yes 0.108 Yes 0.035 OL-1-14 11 0.275 Yes 0.115 Yes 0.139 Yes 0.118 Yes 0.041 OL-1-15 11 0.293 Yes 0.110 Yes 0.130 Yes 0.110 Yes 0.038 OL-1-16 11 0.369 Yes 0.113 Yes 0.122 Yes 0.113 Yes 0.039 OL-1-17 11 0.262 Yes 0.122 Yes 0.149 Yes 0.117 Yes 0.041 OL-1-18 11 0.111 Yes 0.076 Yes 0.131 Yes 0.114 Yes 0.037 OL-1-19 11 0.183 Yes 0.107 Yes 0.119 Yes 0.105 Yes 0.037 OL-1-20 11 0.092 Yes 0.077 Yes 0.145 Yes 0.122 Yes 0.039 OL-1-21 11 0.236 Yes 0.075 Yes 0.137 Yes 0.116 Yes 0.037 OL-1-22 11 0.116 Yes 0.085 Yes 0.143 Yes 0.128 Yes 0.041 OL-1-23 11 0.183 Yes 0.077 Yes 0.135 Yes 0.108 Yes 0.035 OL-1-24 11 0.295 Yes 0.095 Yes 0.125 Yes 0.118 Yes 0.039 41 Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 Table 14, Storm Drains, Pipe Trenches & Other Sub-Surface Excavations Systematic Soil Sample Results By Survey Unit Cs-137, DCGLW = 11.82 pCi/g(1) Co-60, DCGLw = 3.80 pCi/g(1)Maximum Test Average Test Maximum Test Average Test Result: No. of Result: Result: (pCi/g) Result: Average Survey No. of (pCi/g) Maximum Average < (pCi/g) Maximum (2) Average < Unity Unit ID Measurements
< DCGLw DCGLw < DCGLw DCGLw Fraction (2)OL-1-25 11 0.880 Yes 0.204 Yes 0.144 Yes 0.130 Yes 0.052 OL- 1-26 (4 12 0.112 Yes 0.079 Yes 0.140 Yes 0.118 Yes 0.039 OL-1-33 11 0.167 Yes 0.084 Yes 0.136 Yes 0.115 Yes 0.037 OL-1-34 11 0.191 Yes 0.072 Yes 0.137 Yes 0.115 Yes 0.036 OL-1-35 11 0.159 Yes 0.088 Yes 0.146 Yes 0.123 Yes 0.040 OL-1-36 11 0.310 Yes 0.105 Yes 0.150 Yes 0.127 Yes 0.042 OL-1-37 11 0.130 Yes 0.089 Yes 0.143 Yes 0.116 Yes 0.039 OL-1-38 11 0.676 Yes 0.164 Yes 0.140 Yes 0.112 Yes 0.043 OL-1-39 11 0.271 Yes 0.124 Yes 0.137 Yes 0.124 Yes 0.043 OL-1-40 11 0.133 Yes 0.085 Yes 0.133 Yes 0.115 Yes 0.037 OL-1-41 11 0.126 Yes 0.091 Yes 0.146 Yes 0.117 Yes 0.039 OL-1-42(3) 11 0.105 Yes 0.082 Yes 0.139 Yes 0.112 Yes 0.038 OL-1-43 11 0.392 Yes 0.112 Yes 0.129 Yes 0.106 Yes 0.037 OL- 1-44 11 0.816 Yes 0.155 Yes 0.150 Yes 0.109 Yes 0.042 OL-1-45()
11 0.395 Yes 0.128 Yes 0.133 Yes 0.108 Yes 0.040 Total 431 -- --Maximum -0.880 0.428 1.000 -0.191 0.061 Grand Mean -0.106 -0.114 0.039 Table 14 Notes: 1.2.3.4.The soil sample DCGLs for survey units covered by Survey Designs 30, 33, 37 and 44 was 11.82 pCi/g for Cs-137 and 3.80 pCi/g for Co-60.Calculation of average values and unity fractions substitution of MDA values in sample results reported as <MDA.The soil sample DCGLs for survey units covered by Survey Design 39 was 3.50 pCi/g for Co-60 and 14.7 pCi/g for Cs-137.The soil sample DCGLs for survey units covered by Survey Design 46 is 11.40 pCi/g for Cs-137 and 3.7 pCi/g for Co-60.42 Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 5.2 ALARA Evaluation It is shown that residual contamination in the SDPTSSE 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." 2 3 Applicable NRC surface soil screening values are: Co-60, 3.8; Sr-90, 1.7 and Cs-137, 11 (all in pCi/g)2 4.From Appendix C, the highest Cs-137 activity was in Survey Unit OL-1-25 at location SP-2. The activity at this location was 8.80E-01 +/- 2.22E-01 pCi/g and <MDA for Co-60. The highest Co-60 activity measured was in Survey Unit OL-1-4 at location SP-5. The activity at this location was 1.00E+00 +/- 1.76E-01 pCi/g. The Cs-137 activity at this location was 5.83E-01 +/- 1.76E-01 pCi/g. 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 0.081/0.912=0.08925, the activity concentration of Sr-90 is also well below the screening level.The average activity for all systematic soil samples collected within all Class 1 areas, was 1.06E-01 pCi/g for Cs-137 and 1.14E-01 pCi/g 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: 23 This guidance was initially published in Draft Regulatory Guide DG-4006, but has been reissued in NUREG-1757 Volume 2[USNRC 2006].24 Soil Screening Levels from NUREG-1757 Volume 2, Appendix H, Table H-2 [USNRC 2006].25 The Sr-90:Cs-137 activity ratio for Survey Units OL-1-10, OL-1-42 and OL-1-45 is 0.085/0.201=0.423, per Survey Design 39 and Table 5-2 of the PBRF-TBD-09-001
[PBRF 2009].43 Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0" Co-60, 4 pCi/g," Sr-90 (plus daughter activity), 23 pCi/g and* Cs-137 (plus daughter activity), 6 pCi/g.As reported in Section 5.1.3.1 above, the average and maximum activity values for all systematic soil samples collected are as follows:* 1.06E-01 pCi/g (average value for Cs-137),* 8.80E-01 pCi/g (maximum value for Cs-137),* 1.14E-01 pCi/g (average value for Co-60), and* 1.00E+00 pCi/g (maximum value for Co-60).Therefore, all systematic soil sample results are below the EPA Trigger Levels stated above.Since Cs-137 is the surrogate for Sr-90 and the Sr-90: Cs-137 activity ratio is only 0.017, the activity concentration of Sr-90 is also well below the trigger level.5.4 Conclusions The results presented above demonstrate that the SDPTSSE 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 39 survey units with scan coverage equal to (100%for Class 1 areas) the percentage requirements stated in the FSSP." While standing water was present in the two CRB survey units (OL- 1-3 & OL- 1-4)during scanning activities, the presence of water in the survey units did not adversely impact the performance of required 100% scan surveys. Furthermore, additional sampling conducted within these survey units indicated that no detectable Cs- 137 or Co-60 activity was present in the samples." Residual surface soil contamination above scan investigation levels was detected in only three survey units. Soil sample results indicated that the activity present was well below the DCGLw or DCGLEMc, as applicable (in one survey unit).* All 431 systematic soil sample results were less than the applicable DCGLw values for Cs-137 and Co-60." Forty (40) QC soil sample (split samples) results were less than the applicable DCGLw values for Cs-137 and Co-60.* Residual surface activity and 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 units were compared to, and found to be less than EPA trigger levels.* No changes in area classification from what was proposed in the FSS Plan were made and any area not identified in the FSS Plan was given a classification of 1.44 Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 There were no changes from initial assumptions (in the FSS Plan) regarding the extent of residual activity in the SDPTSSE.6.0 References Bowles 2006 Hagelin 2010 MWH 2005 MWH 2005a NACA 1956 NASA 1959 NASA 2006 NASA 2007 NASA 2007a NASA 2010 PBRF 2009 PBRF 2009a PBRF 2009b Mark D. Bowles, Science in Flux, NASA's Nuclear Program at Plum Brook station 1955 -2005, The NASA History Series, June 2006.Karl W. Hagelin, Bremba K. Jones and Associates, NASA Plum Brook Reactor Facility Coordinates, Personal Communication, December 20, 2010.MWH Constructors, Soil Characterization Report, Plum Brook Reactor Facility, Feb. 14, 2005.MWH Constructors, PBRF Decommissioning Project Memorandum from Bruce Mann to Greg Fiscus, Re: Guidance for Soil Remediation
-Action Levels, February 24, 2005.National Advisory Committee on Aeronautics, NA CA Nuclear Reactor Plot Plan and Soil Boring Data, Drawing No. PFOO 101, Plot Plan and Soil Boring Data, Dec.4, 1956.NASA, Final Hazards Summary Part II, Appendix D, Memorandum on the Geology and Hydrology of a Proposed Reactor site Near Sandusky, Ohio, 1959 NASA Safety and Mission Assurance Directorate, Plum Brook Reactor Facility, Decommissioning Project Quality Assurance Plan, QA-0 1, Revision 2, February 2006.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.NASA Glenn Mapping System, Plum Brook Station Reactor Area, Coordinates at Centerline Intersection of Line 2 Road and Pentolite Road, 12/16/2010.
Plum Brook Reactor Facility Technical Basis Document, Radionuclide Distributions and Adjusted DCGLs for Site Soils, PBRF-TBD-09-001, June 2009.Plum Brook Reactor Facility Technical Basis Document, 44-10 NaI Detector MDCscan Values for Various Survey Conditions, PBRF-TBD-09-002, June 2009.Plum Brook Reactor Facility, Memorandum to Project File, J. L. Crooks, Don Young, FSS Final Report Background Information
-Storm Drain System (SDS), December 15, 2009.45 PNL 2010 SNL 1999 TELE 1987 USACE 2004 USEPA 2002 USNRC 1998 USNRC 2000 USNRC 2006 Plum Brook Reactor Facility FSSR Attachment 7, Rev. 0 Battelle Pacific Northwest Laboratories (PNL), Visual sample Plan, Version 5.9, 2010.Sandia National Laboratories (SNL), for US Nuclear Regulatory Commission, Residual Radioactive Contamination From Decommissioning, Parameter Analysis, NUREG/CR-5512, Vol.3, Oct. 1999.Teledyne Isotopes, An Evaluation of the Plum Brook Reactor Facility and Documentation of Existing Conditions, Prepared for NASA Lewis Research Center, December 1987.US Army Corps of Engineers Louisville District, Hydrological Report Plum Brook Reactor Facility Sandusky, Ohio, November 17, 2004.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.US Nuclear Regulatory Commission, Minimum Detectable Concentrations with Typical Radiation Survey Instruments for Various Contaminants and Field Conditions, NUREG-1507, June 1998.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, Characterization, Survey and Determination of Radiological Criteria, NUREG 1757, Vol. 2, Rev.1, September 2006.7.0 Appendices Appendix A -Exhibits Appendix B -Survey Unit Maps and Tables Showing Measurement Locations Appendix C -Final Status Survey Soil Sample Results 46 Plum Brook Reactor Facility Final Status Survey Report Attachment 7 Storm Drains, Pipe Trenches & Other Sub-Surface Excavations Revision 0 Appendix A Exhibits Plum Brook Reactor Facility FSSR, Attachment 7 Appendix A Rev.0, Page 2 of 22 List of Exhibits Exhibit 1, Storm Drain, Pipe Trenches & Other Sub-Surface Excavations Survey Unit Breakdown
... 3 Exhibit 2, Storm Drain System Laterals ............................................................................................
4 Exhibit 3, Sanitary System Piping Location M ap .............................................................................
5 Exhibit 4, Excavation of SDS Piping in Phase 4 ................................................................................
6 Exhibit 5, Excavation of SDS Piping in Phase 4 ................................................................................
7 Exhibit 6, Phase 6 of SDS Dismantlement
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8 Exhibit 7, Phase 7 of SDS Dismantlement
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9 Exhibit 8, Radiological Survey of Storm Drain Trenching
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10 Exhibit 9, Excavation of SDS Piping ...................................................................................................
11 Exhibit 10, CRB Dismantlement
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12 Exhibit 11, CRB Disassembly
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13 Exhibit 12, CRB Excavations
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14 Exhibit 13, Excavations of Piping ...................................................................................................
15 Exhibit 14, Excavation South of W HB ...........................................................................................
16 Exhibit 15, Spill Area Excavation
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17 Exhibit 16, Lateral "A" Disassembly
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18 Exhibit 17, Hot Lab Drain Line Excavation
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19 Exhibit 18, Backfill after SDS Disassembly
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20 Exhibit 19, Excavation of RCRA Soil ...........................................................................................
21 Exhibit 20, Soil Staging .......................................................................................................................
22 Plum Brook Reactor Facility FSSR, Attachment 7 Appendix A Rev.0, Page 3 of 22 Exhibit 1, Storm Drain, Pipe Trenches & Other Sub-Surface Excavations Survey Unit Breakdown OL 7lrOL I 8 J-a 41 OL I ý2 OL- 1 3!CN iOLITt DITC-1 Plum Brook Reactor Facility FSSR, Attachment 7 Appendix A Rev.0, Page 4 of 22 Exhibit 2, Storm Drain System Laterals 7 Plum Brook Reactor Facility FSSR, Attachment 7 Appendix A Rev.0, Page 5 of 22 Exhibit 3, Sanitary System Piping Location Map'-a--,AW.am w 0 1 tu-u:, I$ ~m!~ ~I I I I Plum Brook Reactor Facility FSSR, Attachment 7 Appendix A Rev.0, Page 6 of 22 Exhibit 4, Excavation of SDS Piping in Phase 4 SDS West of CRB and East of Line 3 Road N~zl -~SDS piping removal Plum Brook Reactor Facility FSSR, Attachment 7 Appendix A Rev.0, Page 7 of 22 Exhibit 5, Excavation of SDS Piping in Phase 4 Excavation of Lateral "D" South and West of CRB-2 Plum Brook Reactor Facility FSSR, Attachment 7 Appendix A Rev.0, Page 8 of 22 Exhibit 6, Phase 6 of SDS Dismantlement Radiological Survey of East SDS of SDS trench after FSS Survey Plum Brook Reactor Facility FSSR, Attachment 7 Appendix A Rev.0, Page 9 of 22 Exhibit 7, Phase 7 of SDS Dismantlement Cr1C in I-rkl h .-,f ID-n+^'n;#ý ID^ýA)logical Survey of SDS Trench Plum Brook Reactor Facility FSSR, Attachment 7 Appendix A Rev.0, Page 10 of 22 Exhibit 8, Radiological Survey of Storm Drain Trenching Trench Located Inside Protected Area Fence near Intersection of Pentolite and Line 2 Roads Plum Brook Reactor Facility FSSR, Attachment 7 Appendix A Rev.0, Page 11 of 22 Exhibit 9, Excavation of SDS Piping SDS piping located west of ERB N al Plum Brook Reactor Facility FSSR, Attachment 7 Appendix A Rev.0, Page 12 of 22 Exhibit 10, CRB Dismantlement Removal of Roof Structure on North C Plum Brook Reactor Facility FSSR, Attachment 7 Appendix A Rev.0, Page 13 of 22 Exhibit 11, CRB Disassembly Contaminated CRB Piping Removal Excavation of North CRB Plum Brook Reactor Facility FSSR, Attachment 7 Appendix A Rev.0, Page 14 of 22 Exhibit 12, CRB Excavations North and South Excavations-I Plum Brook Reactor Facility FSSR, Attachment 7 Appendix A Rev.0, Page 15 of 22 Exhibit 13, Excavations of Piping Pipe # FH-103 and Sleeve from West Wall of WHB.
Plum Brook Reactor Facility FSSR, Attachment 7 Appendix A Rev.0, Page 16 of 22 Exhibit 14, Excavation South of WHB Concrete Pad Removal Plum Brook Reactor Facility FSSR, Attachment 7 Appendix A Rev.0, Page 17 of 22 Exhibit 15, Spill Area Excavation Concrete Pad South of WHB and West of Line 3 Road Plum Brook Reactor Facility FSSR, Attachment 7 Appendix A Rev.0, Page 18 of 22 Exhibit 16, Lateral "A" Disassembly Excavation of SDS Piping Plum Brook Reactor Facility FSSR, Attachment 7 Appendix A Rev.0, Page 19 of 22 Exhibit 17, Hot Lab Drain Line Excavation West of Hot Lab and South of Reactor Security Building Drain Line Piping Removal I Plum Brook Reactor Facility FSSR, Attachment 7 Appendix A Rev.0, Page 20 of 22 Exhibit 18, Backfill after SDS Disassembly Lateral "A" Plum Brook Reactor Facility FSSR, Attachment 7 Appendix A Rev.0, Page 21 of 22 Exhibit 19, Excavation of RCRA Soil South of SEB Plum Brook Reactor Facility FSSR, Attachment 7 Appendix A Rev.0, Page 22 of 22 Exhibit 20, Soil Staging RCRA Area Soil being staged Soil from SDS Excavations Plum Brook Reactor Facility Final Status Survey Report Attachment 7 Storm Drains, Pipe Trenches & Other Sub-Surface Excavations Revision 0 Appendix B Survey Unit Maps and Tables Showing Measurement Locations Plum Brook Reactor Facility FSSR, Attachment 7 Appendix B Rev. 0, Page 2 of 41 Index of Storm Drains, Pipe Trenches and Other Sub-Surface Excavations (OL-1) Survey Unit Maps and Tables of Coordinates Survey Unit Description Page Number Number of Pages OL-1-1 Storm Drains -Section 2-1 3 1 OL-1-2 Storm Drains -Section 2-2 4 1 OL-1-3 Cold Retention Basin North 5 1 OL-1-4 Cold Retention Basin South 6 1 OL-1-5 Cold Retention Basin East West Ramp 7 1 OL-1-6 Storm Drains Phase #1 8 1 OL-1-7 Storm Drains Phase 2, Section 1 9 1 OL-1-8 Storm Drains Phase 2, Section 2 10 1 OL-1-9 Storm Drains W, NW & N of SEB 11 1 OL-1-10 Storm Drains SE of PPH 12 1 OL-1-11 Phase 4, Section 1 13 1 OL-1-12 Storm Drains, Lateral D, North Section 14 1 OL-1-13 Storm Drains, Lateral D, North Section 15 1 OL- 1-14 Storm Drains, South & East of SEB 16 1 OL-1-15 Storm Drains, Main Lateral, South of FH- 110 17 1 OL- 1-16 Storm Drains, Lateral A, East of Line 3 Road 18 1 OL-1-17 Storm Drains, Lateral D, South Section & STS46 Trench 19 1 OL-1-18 SANS Trenches South of HL Building 20 1 OL-1-19 RCRA Trenches South of SEB 21 1 OL-1-20 Northeast Comer of FH/WHB Footprint 22 1 OL-1-21 Southeast Comer of FH/WHB Footprint 23 1 OL-1-22 Western Sections of FH/WHB Footprint 24 1 OL-1-23 UST Excavations 25 1 OL-1-24 Evaporator Pit 26 1 OL-1-25 Phase 7 North of Haul Road, South of FH/WHB 27 1 OL-1-26 ERB Sump Drain Line Excavation 28 1 OL-1-33 Storm Drain Excavation-MacTec Crossover 29 1 OL-1-34 Storm Drain Excavation-Crossover south of SEB 30 1 OL-1-35 Storm Drain Excavation-Crossover at L3 Road/Driveway E 31 1 OL-1-36 Storm Drain Excavation-Line 3 Road North Crossover 32 1 OL-1-37 Storm Drain Excavation-Line 3 Road South Crossover 33 1 OL-1-38 Storm Drain Excavation-Haul Road Crossover 34 1 OL-1-39 Storm Drain Excavation
-Trench South of Sludge Basins, East of 351 SEB OL-1-40 Storm Drain Excavation
-CB-18 Excavation 36 1 OL-1-41 Storm Drain Excavation
-CB-5A Excavation 37 1 OL-1-42 Resin Pits Excavation South of PPH 38 1 01-1-43 Storm Drain Excavation-Lateral C South Excavation 39 1 01-1-44 Storm Drain Excavation-Lateral C North Excavation 40 1 01-1-45 Excavations South of Waste Storage Pad 41 1 Plum Brook Reactor Facility FSSR, Attachment 7 Appendix B Rev. 0, Page 3 of 41 Survey Unit OL-1-1 Survey Unit OL-1-1 Area: NorthlSouth Storm Drain & East/West Lateral Trenches, Class I Measurement Locations X Coord Y Coord Label Type 79 9.8 SP-1 Systematic 117 9.2 SP-2 Systematic 2.5 16.5 SP-3 Systematic 21.2 50.0 SP-4 Systematic 2.2 83.5 SP-5 Systematic 21.9 117 SP-6 Systematic 2.8 150.5 SP-7 Systematic 22.2 184 SP-8 Systematic 0.7 217.4 SP-9 Systematic 18.4 250.9 SP-10 Systematic 19.5 317.9 SP-11 Systematic The Y coordinate for samples SP-1 & SP-2 are from the south edge of the east west lateral excavation.
The X coordinate is from the southwest comer of the east west dogleg excavation.
The Y coordinate for samples SP-3 to SP-1 1 are from the southwest corner of the trench south of CB-5A excavation.
The X coordinate is from the west edge of the trench south of CB-5A excavation.
Plum Brook Reactor Facility FSSR, Attachment 7 Appendix B Rev. 0, Page 4 of 41 Survey Unit OL-1-2 (T Survey Unit OL-1-2 Area: East/West Storm Drain, North/South Lateral, &West/North Bend Trenches, Class I Measurement Locations X Coord Y Coord Label Type-93.4 -13.2 SP-1 Systematic
-49.8 2.7 SP-2 Systematic
-4.1 3.6 SP-3 Systematic 41.3 1.9 SP-4 Systematic 86.7 1.0 SP-5 Systematic 132.1 1.9 SP-6 Systematic 177.5 2.8 SP-7 Systematic 222.9 3.1 SP-8 Systematic 268.3 3.5 SP-9 Systematic
-136 -3.1 SP-10 Systematic
-214 2.3 SP-11 Systematic The sample Y coordinates are measured from the centerline of the bottom of the excavation, which is shown by the inner lines on the map. Positive measurements are to the north/east of the bottom, while negative values are measured to the south/west of the bottom.The X coordinates are measured from a point that is the intersection of 2 lines drawn from: (1) the center of the bottom of the east-west excavation and (2) the center of the bottom of the small north-south excavation that extends from the southem edge of the east-west trench Plum Brook Reactor Facility FSSR, Attachment 7 Appendix B Rev. 0, Page 5 of 4l Survey Unit OL-1-3 Survey Unit OL-1-3 Area: North Cold Retention Basin, Class I Measurement Locations X Coord Y Coord Label Type 0.0 -0.0 SP-1 Systematic 37 -0.0 SP-2 Systematic 110 -0.0 SP-3 Systematic
-18 32 SP-4 Systematic 55 32 SP-5 Systematic 0.0 63 SP-6 Systematic 74 63 SP-7 Systematic 110 63 SP-8 Systematic 19 95 SP-9 Systematic 55 95 SP-10 Systematic 92 95 SP-1 1 Systematic All measurements are taken from the closest adjacent surface.
Plum Brook Reactor Facility FSSR, Attachment 7 Appendix B Rev. 0, Page 6 of 41 Survey Unit OL-1-4 Survey Unit OL-1-4 Area: South Cold Retention Basin, Class 1 Measurement Locations X Coord Y Coord Label Type 6 13 SP-1 Systematic 4 5 SP-2 Systematic 1 21 SP-3 Systematic 8 22 SP-4 Systematic 5 1 SP-5 Systematic 29 5 SP-6 Systematic 4 4 SP-7 Systematic 22 6 SP-8 Systematic 8 24 SP-9 Systematic 9 2 SP-10 Systematic 2 18 SP-11 Systematic All measurements are taken from the closest adjacent surface.
Plum Brook Reactor Facility FSSR, Attachment 7 Appendix B Rev. 0, Page 7 of 41 Survey Unit OL-1-5 OL 1-5 Area: Cold Retention Basin Center Area, Class I Measurement Locations X Coord Y Coord Label Type 0.0 -0.0 SP-1 Systematic 15 -0.0 SP-2 Systematic 74 -0.0 SP-3 Systematic 89 -0.0 SP-4 Systematic 103 -0.0 SP-5 Systematic 8 12 SP-6 Systematic 23 12 SP-7 Systematic 37 12 SP-8 Systematic 52 12 SP-9 Systematic 67 12 SP-10 Systematic 81 12 SP-1 1 Systematic The X-Y coordinates for samples SP-2 thru SP-1 1 are from SP-1, placement of SP-1 is in the southwest corner of the survey unit.
Plum Brook Reactor Facility FSSR, Attachment 7 Appendix B Rev. 0, Page 8 of 41 Survey Unit OL-1-6 OL 1-6 Area: Storm Drains Phase #1, Class I Measurement Locations X Coord Y Coord Label Type 4' east of west trench edge 7' south of north trench edge SP-1 Systematic 40' east of west trench edge 9' south of north trench edge SP-2 Systematic 76' east of west trench edge 9' south of north trench edge SP-3 Systematic 4' east of west trench edge 44' north of south trench edge SP-4 Systematic 4' east of west trench edge 106' north of south trench edge SP-5 Systematic 15' west of east trench edge 83' south of north trench edge SP-6 Systematic 14' west of east trench edge 20' south of north trench edge SP-7 Systematic 14' east of west trench edge 143' south of north trench edge SP-8 Systematic 10' east of west trench edge 81' south of north trench edge SP-9 Systematic 29' east of west trench edge 48' south of north trench edge SP-1 0 Systematic 12' east of west trench edge 18' south of north trench edge SP-1 1 Systematic The X, Y coordinates for samples SP-1 thru SP-1 1 are as listed Plum Brook Reactor Facility FSSR, Attachment 7 Appendix B Rev. 0, Page 9 of 41 Survey Unit OL-1-7 OL 1-7 Area: Storm Drains Phase 2, Section 1, Class I Measurement Locations X Coord Y Coord Label Type 3' east of west trench edge 19' north of south trench edge SP-1 Systematic 12' east of west trench edge 12' north of south trench edge SP-2 Systematic 29' east of west trench edge 5' south of north trench edge SP-3 Systematic 26' east of west trench edge 7' north of south trench edge SP-4 Systematic 56' east of west trench edge 7' north of south trench edge SP-5 Systematic 86' west of east trench edge 7' south of north trench edge SP-6 Systematic 116' west of east trench edge 5' south of north trench edge SP-7 Systematic 146' east of west trench edge 5' south of north trench edge SP-8 Systematic 176' east of west trench edge 6' south of north trench edge SP-9 Systematic 206' east of west trench edge 5' south of north trench edge SP-1 0 Systematic 236' east of west trench edge 7' south of north trench edge SP-1 1 Systematic The X, Y coordinates for samples SP-1 thru SP-1 1 are as listed Plum Brook Reactor Facility FSSR, Attachment 7 Appendix B Rev. 0, Page 10 of 41 Survey Unit OL-1-8.-1 -11.I~J OL 1-8 Area: Storm Drains Phase 2, Section 2, Class I Measurement Locations and results X Coord Y Coord Label Type 16' east of west trench edge 10' north of south trench edge SP-1 Systematic 4' east of west trench edge 40' north of south trench edge SP-2 Systematic 12' west of SP-2 3' north of south trench edge SP-3 Systematic 24' east of SP-3 5' north of south trench edge SP-4 Systematic 2' east of west trench edge 23' north of south trench edge SP-5 Systematic 4' west of east trench edge 82' north of south trench edge SP-6 Systematic 24' east of SP-3 4' north of south trench edge SP-7 Systematic 12' east of SP-7 4' north of south trench edge SP-8 Systematic 12' east of SP-8 3' north of south trench edge SP-9 Systematic 12' east of SP-9 6' north of south trench edge SP-10 Systematic 1' east of west trench edge 65' north of south trench edge SP-1 1 Systematic The X, Y coordinates for samples SP-1 thru SP-1 1 are as listed Plum Brook Reactor Facility FSSR, Attachment 7 Appendix B Rev. 0, Page 11 of 41 Survey Unit OL-1-9 OL 1-9 Area: Storm Drains West, Northwest, and North of SEB, Class 1 Measurement Locations X Coord Y Coord Label Type 5' west of east trench edge 55' north of south trench edge SP-1 Systematic 5' west of east trench edge 135' north of south trench edge SP-2 Systematic 64' west of east trench edge 1' north of southwest trench edge SP-3 Systematic 17' west of east trench edge 20' north of south trench edge SP-4 Systematic 3' west of east trench edge 117' north of south trench edge SP-5 Systematic 105' west of east trench edge 5' north of south trench edge SP-6 Systematic 58' west of east trench edge 62' north of south trench edge SP-7 Systematic 11' west of east trench edge 2' north of south trench edge SP-8 Systematic 138' west of east trench edge 2' north of south trench edge SP-9 Systematic 92' west of east trench edge 2' north of south trench edge SP-1 0 Systematic 46' west of east trench edge 2' north of south trench edge SP-1 1 Systematic The X, Y coordinates for samples SP-1 thru SP-1 1 are as listed Plum Brook Reactor Facility FSSR, Attachment 7 Appendix B Rev. 0, Page 12 of 41 Survey Unit OL-1-10 OL 1-10 Area: Storm Drains Southeast of PPH, Class 1 Measurement Locations X Coord Y Coord Label Type 7' from west edge of trench (A) 1' south of trench edge SP-1 Systematic 22' from west edge of trench (A) 4' south of trench edge SP-2 Systematic 37' from west edge of trench (A) 11' south of trench edge SP-3 Systematic 44' from west edge of trench (A) 1' south of trench edge SP-4 Systematic 7' from east edge of trench 8' north of trench edge SP-5 Systematic 1' from east edge of trench 14' north of SP-5 SP-6 Systematic 4' from west edge of trench 28' north of SP-5 SP-7 Systematic 1' from east edge of trench 42' north of SP-5 SP-8 Systematic 4' from west edge of trench 56' north of SP-5 SP-9 Systematic 3' from west edge of trench 84' north of SP-5 SP-10 Systematic 2' from west edge of trench 112' north of SP-5 SP-1 1 Systematic The X, Y coordinates for samples SP-1 thru SP-1 1 are as listed Plum Brook Reactor Facility FSSR, Attachment 7 Appendix B Rev. 0, Page 13 of 41 Survey Unit OL-1-1 1 U OL 1-11 Area: Phase 4, Section 1, Class I Measurement Locations X Coord Y Coord Label Type 30' west of east trench edge 5' north of south trench edge SP-1 Systematic 15' west of east trench edge 4' north of south trench edge SP-2 Systematic 6' west of east trench edge 17' north of south trench edge SP-3 Systematic 6' east of west trench edge 31' north of south trench edge SP4 Systematic 22' east of west trench edge 2' north of south trench edge SP-5 Systematic 38' east of west trench edge 1' north of south trench edge SP-6 Systematic 54' east of west trench edge 1' north of south trench edge SP-7 Systematic 70' east of west trench edge 3' north of south trench edge SP-8 Systematic 86' east of west trench edge 1' north of south trench edge SP-9 Systematic 1' west of east trench edge 44' north of south trench edge SP-1 0 Systematic 10' west of east trench edge 59' north of south trench edge SP-1 1 Systematic The X, Y coordinates for samples SP-1 thru SP-1 1 are as listed Plum Brook Reactor Facility FSSR, Attachment 7 Appendix B Rev. 0, Page 14 of 41 Survey Unit OL-1-12 7-OL 1-12 Area: Storm Drains, Lateral D, North Section, Class I Measurement Locations X Coord Y Coord Label Type 42 ft from west end of trench 4.6 ft from north bank of trench SP-1 Systematic 57 ft from SP-1 5.7 ft from north bank of trench SP-2 Systematic 57 ft from SP-2 4.6 ft from north bank of trench SP-3 Systematic 57 ft from SP-3 2.9 ft from north bank of trench SP-4 Systematic 57 ft from SP-4 3.3 ft from north bank of trench SP-5 Systematic 56 ft from west end of trench 0.5 ft from south bank of trench SP-6 Systematic 57 ft from SP-6 1 ft from south bank of trench SP-7 Systematic 6 ft from west end of trench 8 ft from north bank of trench SP-8 Systematic 56 ft from SP-8 2 ft from south bank of trench SP-9 Systematic 56 ft from SP-9 3 ft from south bank of trench SP-1 0 Systematic 56 ft from SP-10 5 ft from south bank of trench SP-1 1 Systematic 56 ft from SP-1 1 6 ft from south bank of trench SP-12 Systematic The X, Y coordinates for samples SP-1 thru SP-12 are as listed Plum Brook Reactor Facility FSSR, Attachment 7 Appendix B Rev. 0, Page 15 of 41 Survey Unit OL-1 -13 SP-I1 sp.1 W-SP SP SF-I OL 1-13 Area: Storm Drains, Lateral D, North Section, Class I Measurement Locations X Coord Y Coord Label Type 12 ft from east edge of trench 26 SP-1 Systematic 9 ft from east edge of trench 89 SP-2 Systematic 0.4 ft from west edge of trench 121 SP-3 Systematic 8 ft from east edge of trench 153 SP4 Systematic 1.4 ft from west edge of trench 184 SP-5 Systematic 7 ft from east edge of trench 216 SP-6 Systematic 2.4 ft from west edge of trench 247 SP-7 Systematic 7 ft from east edge of trench 279 SP-8 Systematic 1.7 ft from west edge of trench 310 SP-9 Systematic 14 ft from east edge of trench 342 SP-10 Systematic 12 ft from east edge of trench 405 SP-1 1 Systematic The X coordinates for samples SP-1 thru SP-1 1 are as listed. The Y coordinate is measured from the center of the southern-most point of the survey unit.
Plum Brook Reactor Facility FSSR, Attachment 7 Appendix B Rev. 0, Page 16 of 41 Survey Unit OL-1-14 t,.a% A ISP-Il ISP-2 ISP-3 ISP-A ISP-S ISP6 ISP-7 OL 1-14 Area: Storm Drains, South & East of SEB, Class I Measurement Locations X Coord Y Coord Label Type 5' east of west trench edge 1' north of south trench edge SP-1 Systematic 55' east of west trench edge 5' north of south trench edge SP-2 Systematic 105' east of west trench edge 6' north of south trench edge SP-3 Systematic 155' east of west trench edge 3' north of south trench edge SP-4 Systematic 205' east of west trench edge 3' north of south trench edge SP-5 Systematic 255' east of west trench edge 4' north of south trench edge SP-6 Systematic 305' east of west trench edge 1' north of south trench edge SP-7 Systematic 11' east of west trench edge 270' south of concrete wall edge SP-8 Systematic 12' east of dam edge edge 182' south of concrete wall edge SP-9 Systematic 11' east of west trench edge 94' south of concrete wall edge SP-10 Systematic 17' east of west trench edge 6' south of concrete wall edge SP-1 1 Systematic The X, Y coordinates for samples SP-1 thru SP-1 1 are as listed.
Plum Brook Reactor Facility FSSR, Attachment 7 Appendix B Rev. 0, Page 17 of 41 Survey Unit OL-1-15 OL 1-15 Area: Storm Drains, Main Lateral, South of FH-110, Class I Measurement Locations X Coord Y Coord Label Type 12' west of east trench edge 10' north of south trench edge (WEMS wall) SP-1 Systematic 13' west of east trench edge 85' north of south trench edge (WEMS wall) SP-2 Systematic 14' west of east trench edge 160' north of south trench edge (WEMS wall) SP-3 Systematic 12' west of east trench edge 235' north of south trench edge (WEMS wall) SP-4 Systematic 13' west of east trench edge 310' north of south trench edge (WEMS wall) SP-5 Systematic 12' west of east trench edge 385' north of south trench edge (WEMS wall) SP-6 Systematic 12' west of east trench edge 460' north of south trench edge (WEMS wall) SP-7 Systematic 8' east of west trench edge 6' south of north trench edge SP-8 Systematic 50' east of west trench edge 7' south of north trench edge SP-9 Systematic 92' east of west trench edge 8' south of north trench edge SP-10 Systematic 11' west of east trench edge 535' north of south trench edge (WEMS wall) SP-1 1 Systematic The X, Y coordinates for samples SP-1 thru SP-1 1 are as listed.
Plum Brook Reactor Facility FSSR, Attachment 7 Appendix B Rev. 0, Page 18 of 41 Survey Unit OL-1-16 OL 1-16 Area: Storm Drains, Lateral A, East of Line 3 Road, Class1 Measurement Locations X Coord Y Coord Label Type 28' east of west trench edge 10' north of south trench edge SP-1 Systematic 66' east of west trench edge 11' north of south trench edge SP-2 Systematic 104' east of west trench edge 10' north of south trench edge SP-3 Systematic 142' east of west trench edge 10' north of south trench edge SP-4 Systematic 181' east of west trench edge 10' north of south trench edge SP-5 Systematic 220' east of west trench edge 11' north of south trench edge SP-6 Systematic 259' east of west trench edge 11' north of south trench edge SP-7 Systematic 298' east of west trench edge 11' north of south trench edge SP-8 Systematic 337' east of west trench edge 12' north of south trench edge SP-9 Systematic 376' east of west trench edge 12' north of south trench edge SP-10 Systematic 415' east of west trench edge 12' north of south trench edge SP-11 Systematic The X, Y coordinates for samples SP-1 thru SP-1 1 are as listed.
Plum Brook Reactor Facility FSSR, Attachment 7 Appendix B Rev. 0, Page 19 of 41 Survey Unit OL-1-17 OL 1-17 Area: Storm Drains, Lateral D, South Section & STS Trench, Class I Measurement Locations X Coord Y Coord Label Type 5 ft from east side of trench 23 ft from the southern end of the trench SP-1 Systematic 5.7 ft from southwest side of trench 7 ft from the southern end of the trench SP-2 Systematic 5.2 ft from west side of trench 49 ft from the southern end of the trench SP-3 Systematic Center of trench 34 ft from the southern end of the trench SP-4 Systematic 12 ft from east side of trench 75 ft from the southern end of the trench SP-5 Systematic 5.1 ft from west side of trench 101 ft from the southern end of the trench SP-6 Systematic 10 ft from east side of trench 127 ft from the southern end of the trench SP-7 Systematic 5.2 ft from west side of trench 153 ft from the southern end of the trench SP-8 Systematic 13 ft from east side of trench 179 ft from the southern end of the trench SP-9 Systematic 2.6 ft from west side of trench 205 ft from the southern end of the trench SP-10 Systematic 3 ft from west side of trench 9 ft from the southern end of the trench SP-1 1 Systematic The X, Y coordinates for samples SP-1 thru SP-1 1 are as listed.
Plum Brook Reactor Facility FSSR, Attachment 7 Appendix B Rev. 0, Page 20 of 41 Survey Unit OL-1-18 OL 1-18 Area: SANS Trenches South of HL Building, Class I Measurement Locations X Coord Y Coord Label Type 176' east of west trench edge 4' north of south trench edge SP-1 Systematic 4' east of west trench edge 13' north of south trench edge SP-2 Systematic 24' east of west trench edge 12' north of south trench edge SP-3 Systematic 44' east of west trench edge 11' north of south trench edge SP-4 Systematic 64' east of west trench edge 9' north of south trench edge SP-5 Systematic 84' east of west trench edge 11' north of south trench edge SP-6 Systematic 104' east of west trench edge 12' north of south trench edge SP-7 Systematic 124' east of west trench edge 11' north of south trench edge SP-8 Systematic 144' east of west trench edge 12' north of south trench edge SP-9 Systematic 164' east of west trench edge 14' north of south trench edge SP-10 Systematic 184' east of west trench edge 14' north of south trench edge SP-1 1 Systematic The X, Y coordinates for samples SP-1 thru SP-1 1 are as listed.
Plum Brook Reactor Facility FSSR, Attachment 7 Appendix B Rev. 0, Page 21 of 41 Survey Unit OL-1 -19 OL 1-19 Area: RCRA Trenches South of SEB, Class I Measurement Locations X Coord Y Coord Label Type 105' west of east trench edge 17' south of north trench edge SP-1 Systematic 88' west of east trench edge 17' south of north trench edge SP-2 Systematic 54' west of east trench edge 17' south of north trench edge SP-3 Systematic 37' west of east trench edge 17' south of north trench edge SP-4 Systematic 20' west of east trench edge 17' south of north trench edge SP-5 Systematic 3' west of east trench edge 17' south of north trench edge SP-6 Systematic 85' west of east trench edge 3' south of north trench edge SP-7 Systematic 68' west of east trench edge 3' south of north trench edge SP-8 Systematic 51' west of east trench edge 3' south of north trench edge SP-9 Systematic 34' west of east trench edge 3' south of north trench edge SP-10 Systematic 17' west of east trench edge 3' south of north trench edge SP-1 1 Systematic The X, Y coordinates for samples SP-1 thru SP-1 1 are as listed.
Plum Brook Reactor Facility FSSR, Attachment 7 Appendix B Rev. 0, Page 22 of 41 Survey Unit OL-1-20 OL 1-20 Area: Northeast Corner of FH/WHB Footprint, Class I Measurement Locations X Coord Y Coord Label Type 3' east of west trench edge 2' north of south trench edge SP-1 Systematic 34' east of west trench edge 2' north of south trench edge SP-2 Systematic 65' east of west trench edge 2' north of south trench edge SP-3 Systematic 7' east of west trench edge 30' north of south trench edge SPA Systematic 48' east of west trench edge 30' north of south trench edge SP-5 Systematic 23' east of west trench edge 57' north of south trench edge SP-6 Systematic 54' east of west trench edge 57' north of south trench edge SP-7 Systematic 13' east of west trench edge 16' north of south trench edge SP-8 Systematic 44' east of west trench edge 16' north of south trench edge SP-9 Systematic 75' east of west trench edge 85' north of south trench edge SP-10 Systematic 106' east of west trench edge 85' north of south trench edge SP-1 1 Systematic The X, Y coordinates for samples SP-1 thru SP-1 1 are as listed.
Plum Brook Reactor Facility FSSR, Attachment 7 Appendix B Rev. 0, Page 23 of 41 Survey Unit OL-1-21 OL 1-21 Area: Southeast Comer of FH/WHB Footprint, Class I Measurement Locations X Coord Y Coord Label Type 16' east of west trench edge 12' north of south trench edge SP-1 Systematic 48' east of west trench edge 12' north of south trench edge SP-2 Systematic 80' east of west trench edge 12' north of south trench edge SP-3 Systematic 32' east of west trench edge 38' north of south trench edge SP-4 Systematic 64' east of west trench edge 38' north of south trench edge SP-5 Systematic 16' east of west trench edge 66' north of south trench edge SP-6 Systematic 48' east of west trench edge 66' north of south trench edge SP-7 Systematic 80' east of west trench edge 66' north of south trench edge SP-8 Systematic 25' east of west trench edge 94' north of south trench edge SP-9 Systematic 8' east of west trench edge 2' south of north trench edge SP-1 0 Systematic 26' east of west trench edge 120' north of south trench edge SP-1 1 Systematic The X, Y coordinates for samples SP-1 thru SP-1 1 are as listed.
Plum Brook Reactor Facility FSSR, Attachment 7 Appendix B Rev. 0, Page 24 of 41 S1141 Survey Unit OL-1-22 OL 1-22 Area: Western Sections of FH/WHB Footprint, Class 1 Measurement Locations X Coord Y Coord Label Type 4' west of east trench edge 188' south of north trench edge SP-1 Systematic 16' west of east trench edge 167' south of north trench edge SP-2 Systematic 4' west of east trench edge 145' south of north trench edge SP-3 Systematic 17' west of east trench edge 124' south of north trench edge SP-4 Systematic 4' west of east trench edge 102' south of north trench edge SP-5 Systematic 17' west of east trench edge 80' south of north trench edge SP-6 Systematic 30' west of east trench edge 58' south of north trench edge SP-7 Systematic 4' west of east trench edge 58' south of north trench edge SP-8 Systematic 18' west of east trench edge 37' south of north trench edge SP-9 Systematic 6' west of east trench edge 16' south of north trench edge SP-10 Systematic 7' west of east trench edge 10' north of south trench edge SP-1 1 Systematic The X, Y coordinates for samples SP-1 thru SP-1 1 are as listed.
Plum Brook Reactor Facility FSSR, Attachment 7 Appendix B Rev. 0, Page 25 of 41 Survey Unit OL-1-23 OL 1-23 Area: UST Excavations, Class 1 Measurement Locations X Coord Y Coord Label Type 6' east of southwest comer 3' north of south trench edge SP-1 Systematic 23' east of southwest corner 3' north of south trench edge SP-2 Systematic 40' east of southwest corner 3' north of south trench edge SP-3 Systematic 15' east of southwest corner 18' north of south trench edge SP-4 Systematic 32' east of southwest corner 18' north of south trench edge SP-5 Systematic 49' east of southwest corner 18' north of south trench edge SP-6 Systematic 6' east of southwest corner 33' north of south trench edge SP-7 Systematic 23' east of southwest corner 33' north of south trench edge SP-8 Systematic 40' east of southwest corner 33' north of south trench edge SP-9 Systematic 15' east of southwest corner 47' north of south trench edge SP-1 0 Systematic 32' east of southwest corner 47' north of south trench edge SP-1 1 Systematic The X, Y coordinates for samples SP-1 thru SP-11 are measured from the survey unit's southwest corner.
Plum Brook Reactor Facility FSSR, Attachment 7 Appendix B Rev. 0, Page 26 of 41 Survey Unit OL-1-24 OL 1-24 Area: Evaporator Pit, Class I Measurement Locations and results X Coord Y Coord Label Type 15' east from southwest wall 5' down from top of pit SP-1 Systematic 30' east from southwest wall 5' down from top of pit SP-2 Systematic 44' east from southwest wall 1' down from top of pit SP-3 Systematic 15' east of west wall 19' down from top of pit SP4 Systematic 30' east of west wall 16' down from top of pit SP-5 Systematic 54' east from southwest wall 5' down from top of pit SP-6 Systematic 6' east of west wall 25' down from top of pit SP-7 Systematic 16' east of west wall 21' down from top of pit SP-8 Systematic 44' east from northwest wall 11' down from top of pit SP-9 Systematic 15' east from northwest wall 10' down from top of pit SP-10 Systematic 30' east from northwest wall 6' down from top of pit SP-1 1 Systematic The X, Y coordinates for samples SP-1 thru SP-1 1 are measured from the survey unit's identified wall edge and the top of the evaporator pit.
Plum Brook Reactor Facility FSSR, Attachment 7 Appendix B Rev. 0, Page 27 of 41 Survey Unit OL-1-25 OL 1-25 Area: Phase 7 North of Haul Road, South of FH/WHB, Class I Measurement Locations X Coord Y Coord Label Type 30' 1.0' SP-1 Systematic 63' 1.0' SP-2 Systematic 14' 29' SP-3 Systematic 47' 29' SP-4 Systematic 80' 29' SP-5 Systematic 113' 29' SP-6 Systematic 30' 58' SP-7 Systematic 63' 58' SP-8 Systematic 96' 58' SP-9 Systematic 129' 58' SP-10 Systematic 47' east of survey units west edge 4' south of trenches north edge SP-1 1 Systematic The X, Y coordinates for samples SP-1 thru SP-1 0 are measured from the survey unit's southwest comer.The X, Y coordinates for sample SP-1 1 are as delineated Plum Brook Reactor Facility FSSR, Attachment 7 Appendix B Rev. 0, Page 28 of 4l Survey Unit OL-1-26 OL 1-26 Area: ERB Sump Drain Line Excavation, Class I Measurement Locations X Coord Y Coord Label Type 9.5 -12.2 SP-1 Systematic 22.1 -12.2 SP-2 Systematic 34.7 -12.2 SP-3 Systematic 47.3 -12.2 SP4 Systematic 3.2 -1.3 SP-5 Systematic 15.8 -1.3 SP-6 Systematic 28.4 -1.3 SP-7 Systematic 41.0 -1.3 SP-8 Systematic 9.5 9.6 SP-9 Systematic 22.1 9.6 SP-10 Systematic 34.7 9.6 SP-1 1 Systematic All sample points are measured from the point shown on the map Plum Brook Reactor Facility FSSR, Attachment 7 Appendix B Rev. 0, Page 29 of 41 Survey Unit OL-1-33 OL 1-33 Area: Storm Drain Excavation-MacTec Crossover, Class I Measurement Locations X Coord Y Coord Label Type-11.3 5.2 SP-1 Systematic
-1.1 5.2 SP-2 Systematic 9.1 5.2 SP-3 Systematic
-6.2 14.0 SP-4 Systematic 4.0 14.0 SP-5 Systematic
-11.3 22.9 SP-6 Systematic
-1.1 22.9 SP-7 Systematic 9.1 22.9 SP-8 Systematic
-6.2 31.7 SP-9 Systematic 4.0 31.7 SP-10 Systematic 14.3 31.7 SP-11 Systematic All sample points are measured from the point shown on the map.
Plum Brook Reactor Facility FSSR, Attachment 7 Appendix B Rev. 0, Page 30 of 41 Survey Unit OL-1-34 OL 1-34 Area: Storm Drain Excavations-Crossover South of SEB, Class I Measurement Locations X Coord Y Coord Label Type 4.8 -7.4 SP-1 Systematic 3.2 6.7 SP-2 Systematic 8.1 0 SP-3 Systematic 13.2 -6.6 SP-4 Systematic 11.4 8.0 SP-5 Systematic 16.4 1.1 SP-6 Systematic 21.2 -5.5 SP-7 Systematic 19.8 8.8 SP-8 Systematic 24.7 1.9 SP-9 Systematic 29.7 -4.5 SP-10 Systematic 32.9 3.0 SP-1 1 Systematic All sample points are measured from the point shown on the map.
Plum Brook Reactor Facility FSSR, Attachment 7 Appendix B Rev. 0, Page 31 of 41 Survey Unit OL-1-35 OL 1-35 Area: : Storm Drain Excavations-Crossover at Line 3 Road/Driveway E, Class 1 Measurement Locations X Coord Y Coord Label Type-0.5 7.1 SP-1 Systematic 8.8 7.1 SP-2 Systematic
-5.2 15.2 SP-3 Systematic 4.1 15.2 SP4 Systematic
-9.8 23.3 SP-5 Systematic
-0.5 23.3 SP-6 Systematic 8.8 23.3 SP-7 Systematic
-5.2 31.3 SP-8 Systematic 4.1 31.3 SP-9 Systematic
-0.5 39.4 SP-10 Systematic 8.8 39.4 SP-1 1 Systematic All sample points are measured from the point shown on the map.
Plum Brook Reactor Facility FSSR, Attachment 7 Appendix B Rev. 0, Page 32 of 41 Survey Unit OL-1-36 OL 1-36 Area: Storm Drain Excavation-Line 3 Road North Crossover, Class I Measurement Locations X Coord Y Coord Label Type 11.2 -10.8 SP-1 Systematic 21.7 -10.8 SP-2 Systematic 32.1 -10.8 SP-3 Systematic 6.0 -1.7 SP4 Systematic 16.5 -1.7 SP-5 Systematic 26.9 -1.7 SP-6 Systematic 37.4 -1.7 SP-7 Systematic 0.8 7.3 SP-8 Systematic 11.2 7.3 SP-9 Systematic 21.7 7.3 SP-10 Systematic 32.1 7.3 SP-11 Systematic All sample points are measured from the point shown on the map.
Plum Brook Reactor Facility FSSR, Attachment 7 Appendix B Rev. 0, Page 33 of 41 Survey Unit OL-1-37 OL 1-37 Area: Storm Drain Excavation-Line 3 Road South Crossover, Class I Measurement Locations X Coord Y Coord Label Type 11.4 -10 SP-1 Systematic 6.6 -1.7 SP-2 Systematic 16.2 -1.7 SP-3 Systematic 25.8 -1.7 SP-4 Systematic 35.4 -1.7 SP-5 Systematic 1.6 2.9 SP-6 Systematic 1.7 6.7 SP-7 Systematic 11.4 6.7 SP-8 Systematic 21.0 6.7 SP-9 Systematic 30.6 6.7 SP-10 Systematic 40.2 6.7 SP-1 1 Systematic All sample points are measured from the point shown on the map.
Plum Brook Reactor Facility FSSR, Attachment 7 Appendix B Rev. 0, Page 34 of 4l Survey Unit OL-1-38 OL 1-38 Area: Storm Drain Excavation-Haul Road Crossover, Class I Measurement Locations X Coord Y Coord Label Type-8.8 1.9 SP-1 Systematic 1.2 1.9 SP-2 Systematic 11.2 1.9 SP-3 Systematic
-3.8 10.6 SP-4 Systematic 6.2 10.6 SP-5 Systematic
-8.8 19.2 SP-6 Systematic 1.2 19.2 SP-7 Systematic 11.2 19.2 SP-8 Systematic
-3.8 27.8 SP-9 Systematic 6.2 27.8 SP-10 Systematic 11.2 36.5 SP-1 1 Systematic All sample points are measured from the point shown on the map.
Plum Brook Reactor Facility FSSR, Attachment 7 Appendix B Rev. 0, Page 35 of 41 Survey Unit OL-1-39 OL 1-39 Area: Storm Drain Excavation-Trench South of Sludge Basins, East of SEB, Class I Measurement Locations X Coord Y Coord Label Type 7' east of SP-2 15' south SP-2 SP-1 Systematic 100' east of west trench edge 15' south of SP-6 SP-2 Systematic 40' east of west trench edge 2' north of south trench edge SP-3 Systematic 57' east of west trench edge 2' north of south trench edge SP-4 Systematic 74' east of west trench edge 4' north of south trench edge SP-5 Systematic 91' east of west trench edge 20' north of south trench edge SP-6 Systematic 15' east of west trench edge 14' north of south trench edge SP-7 Systematic 32' east of west trench edge 17' north of south trench edge SP-8 Systematic 49' east of west trench edge 17' north of south trench edge SP-9 Systematic 66' east of west trench edge 19' north of south trench edge SP-10 Systematic 83' east of west trench edge 15' north of SP-5 SP-1 1 Systematic All sample points are measured from the point shown on the map.
Plum Brook Reactor Facility FSSR, Attachment 7 Appendix B Rev. 0, Page 36 of 41 Survey Unit OL-1-40 OL 1-40 Area: Storm Drain Excavation
-CB-18 Excavation, Class I Measurement Locations and results X Coord Y Coord Label Type 1.0 1.0 SP-1 Systematic 10 1.0 SP-2 Systematic 19 1.0 SP-3 Systematic 28 1.0 SP-4 Systematic 38 1.0 SP-5 Systematic 47 1.0 SP-6 Systematic 6 9.0 SP-7 Systematic 15 9.0 SP-8 Systematic 24 9.0 SP-9 Systematic 33 9.0 SP-10 Systematic 42 9.0 SP-1 1 Systematic All sample points are measured from the point shown on the map.
Plum Brook Reactor Facility FSSR, Attachment 7 Appendix B Rev. 0, Page 37 of 4l Survey Unit OL-1-41 SW comer C OL-1-41 Area: Storm Drain Excavation
-CB-5A Excavation, Class I Measurement Locations X Coord Y Coord Label Type as per note b as per note b SP-1 Systematic 9 0.6 SP-2 Systematic 22 0.6 SP-3 Systematic 35 0.6 SP-4 Systematic 2 12 SP-5 Systematic 15 12 SP-6 Systematic 28 12 SP-7 Systematic 9 23 SP-8 Systematic 22 23 SP-9 Systematic 15 34 SP-10 Systematic 28 34 SP-1 1 Systematic"The X, Y coordinates for samples SP-2 thru SP-1 1 are measured from the designated SW comer of the excavation.
b The coordinates for sample SP-1 are 5' south of north edge A, 6' NW of SE edge B, and 9.5' east of west edge C.
Plum Brook Reactor Facility FSSR, Attachment 7 Appendix B Rev. 0, Page 38 of 41 Survey Unit OL-1-42 OL 1-42 Area: Resin Pits Excavation South of PPH, Class I Measurement Locations X Coord Y Coord Label Type 1' down from top of pit 4' north of SW pit corner SP-1 Systematic 4' down from top of pit 10' east of SW pit corner SP-2 Systematic 4' down from top of pit 24' east of SW pit corner SP-3 Systematic 4' down from top of pit 4' west of SE pit corner SP-4 Systematic 7' down from top of pit 16' south of NW pit corner SP-5 Systematic 2' up from bottom of pit 5' east of SW pit corner SP-6 Systematic 2' up from bottom of pit 4' west of SE pit corner SP-7 Systematic 1' down from top of pit 7' south of NW pit corner SP-8 Systematic 4' up from bottom of pit 1' south of NW pit corner SP-9 Systematic 1' up from bottom of pit 11' west of NE pit corner SP-1 0 Systematic 4' up from bottom of pit 2' south of NE pit corner SP-1 1 Systematic The X, Y coordinates for samples SP-1 thru SP-1 1 are as listed.
Plum Brook Reactor Facility FSSR, Attachment 7 Appendix B Rev. 0, Page 39 of 41 Survey Unit OL-1-43 SW comer OL-1-43 Area: Storm Drain Excavations
-Lateral C South Excavation, Class I Measurement Locations X Coord Y Coord Label Type 2 11 SP-1 Systematic 26 11 SP-2 Systematic 14 32 SP-3 Systematic 2 53 SP-4 Systematic 26 53 SP-5 Systematic 14 74 SP-6 Systematic 2 95 SP-7 Systematic 26 95 SP-8 Systematic 14 115 SP-9 Systematic 2 136 SP-10 Systematic 26 136 SP-1 1 Systematic The X, Y coordinates for samples SP-1 thru SP -11 are measured from the designated SW comer of the excavation.
Plum Brook Reactor Facility FSSR, Attachment 7 Appendix B Rev. 0, Page 40 of 41 Survey Unit OL-1-44 SW comer OL-1-44 Area: Storm Drain Excavation-Lateral C North Excavation, Class I Measurement Locations X Coord Y Coord Label Type 26 9 SP-1 Systematic 12 33 SP-2 Systematic 26 57 SP-3 Systematic 12 81 SP-4 Systematic 40 81 SP-5 Systematic 26 105 SP-6 Systematic 12 129 SP-7 Systematic 40 129 SP-8 Systematic
-1 153 SP-9 Systematic 26 153 SP-10 Systematic 19' west of excavation 5' south of excavation SP-1 1 Systematic east edge north edge T he X, Y coordinates tor samples SP--1 tmru SP -1U are measured trom me designatea Sw comer of me excavation (unit of measurement
= feet).The X, Y coordinates for sample SP-11 are as described below (unit of measurement
= feet).
Plum Brook Reactor Facility FSSR, Attachment 7 Appendix B Rev. 0, Page 41 of 41 Survey Unit OL-1-45 SW comer #1 a The X, Y coordinates for samples SP-1 thru SP-8 are measured from SW corer #1.b The X, Y coordinates for samples SP-1 thru SP-1 1 are measured from SW corner #2.C unit of measurement
= feet OL-1-45 Area: Excavations South of Waste Storage Pad, Class 1 Measurement Locations X Coord Y Coord Label Type 4 3 SP-1 Systematic 17 3 SP-2 Systematic 30 3 SP-3 Systematic 43 3 SP-4 Systematic 11 14 SP-5 Systematic 24 14 SP-6 Systematic 36 14 SP-7 Systematic 50 14 SP-8 Systematic 10 3 SP-9 Systematic 22 3 SP-10 Systematic 16 13 SP-11 Systematic Plum Brook Reactor Facility Final Status Survey Report Attachment 7 Storm Drains, Pipe Trenches & Other Sub-Surface Excavations Revision 0 Appendix C Soil Sample Results Plum Brook Reactor Facility FSSR, Attachment 7 Appendix C Rev. 0, Page 2 of 17 Table of Contents Description Page Number Number of Pages Soil Sample Results for Class 1 Survey Units 3 12 Summary of Soil Sample Results for Class 1 Survey Units 15 1 QC Soil Sample Comparison for Class 1 Areas 16 2 APPENDIX C FINAL STATUS SURVEY SOIL SAMPLE RESULTS Plum Brook Reactor Facility FSSR, Attachment 7 Appendix C, Rev. 0, Page 3 of 17 CLASS 1 SOIL SAMPLE RESULTS Cs-1 37 Co-60 DCGLtO) 11.4 DCGL 3.7 DCGL~2) 14.7 DCGL 3.5 Cs-1 37 Co-60 DCGLr 3) 11.82 DCGL 3.8 MDA MDA Location Sample Log # Sample # Weight (g) pCi/g 2cy pClIg 2 % Unity Cs:Co pCilg pCilg OL-1-1 SP-1 PB09-00998 SR-164-1 363.3 <MDA <MDA <MDA <MDA 0% N/A 3.93E-02 5.98E-02 OL-1-1 SP-2 PB09-00999 SR-164-2 364.7 <MDA <MDA <MDA <MDA 0% N/A 3.91E-02 5.96E-02 OL-1-1 SP-3 PB09-01001 SR-164-3 387.0 1.10E-01 4.70E-02 <MDA <MDA 1% N/A 5.62E-02 OL-1-1 SP-4 PB09-01002 SR-164-4 382.5 <MDA <MDA <MDA <MDA 0% N/A 3.92E-02 6.14E-02 OL-1-1 SP-5 PB09-01003 SR-164-5 349.7 <MDA <MDA <MDA <MDA 0% N/A 4.08E-02 6.22E-02 OL-1-1 SP-6 PB09-01004 SR-164-6 384.4 <MDA <MDA <MDA <MDA 0% N/A 5.59E-02 6.10E-02 OL-1-1 SP-7 PB09-01005 SR-164-7 371.1 <MDA <MDA <MDA <MDA 0% N/A 4.99E-02 5.86E-02 OL-1-1 SP-8 PB09-01006 SR-164-8 390.5 <MDA <MDA <MDA <MDA 0% N/A 5.85E-02 6.01E-02 OL-1-1 SP-9 PB09-01007 SR-164-9 382.9 1.62E-01 5.74E-02 <MDA <MDA 1% NfA 5.68E-02 OL-1-1 SP-10 PB09-01008 SR-164-10 454.1 <MDA <MDA <MDA <MDA 0% N/A 3.14E-02 7.56E-02 OL-1-1 SP-11 PB09-01009 SR-164-11 507.9 <MDA <MDA <MDA <MDA 0% N/A 3.83E-02 4.62E-02 OL-1-2 SP-1 PB09-01116 SR-165-1 406.2 <MDA <MDA <MDA <MDA 0% N/A 5.05E-02 5.78E-02 OL-1-2 SP-2 PB09-01117 SR-165-2 398.6 <MDA <MDA <MDA <MDA 0% N/A 5.80E-02 5.65E-02 OL-1-2 SP-3 PB09-01118 SR-165-3 390.5 <MDA <MDA <MDA <MDA 0% N/A 3.65E-02 5.57E-02 OL-1-2 SP-4 PB09-01119 SR-165-4 488.2 9.59E-02 4.01E-02 <MDA <MDA 1% N/A 4.81E-02 OL-1-2 SP-5 PB09-01120 SR-165-5 503.0 <MDA <MDA <MDA <MDA 0% N/A 4.37E-02 4.48E-02 OL-1-2 SP-6 PB09-01122 SR-165-6 459.6 4.28E-01 1.05E-01 <MDA <MDA 4% N/A 4.73E-02 OL-1-2 SP-7 PB09-01123 SR-165-7 412.4 <MDA <MDA <MDA <MDA 0% N/A 3.64E-02 5.69E-02 OL-1-2 SP-8 PB09-01124 SR-165-8 404.5 <MDA <MDA <MDA <MDA 0% N/A 4.43E-02 5.57E-02 OL-1-2 SP-9 PB09-01125 SR-165-9 388.6 <MDA <MDA <MDA <MDA 0% N/A 3.67E-02 5.59E-02 OL-1-2 SP-10 PB09-01126 SR-165-10 482.0 <MDA <MDA <MDA <MDA 0% N/A 3.11E-02 4.86E-02 OL-1-2 SP-11 PB09-01127 SR-165-11 461.0 <MDA <MDA <MDA <MDA 0% N/A 5.10E-02 4.86E-02 OL-1-3 SP-1 PB09-02115 SR-176-196 350.2 <MDA <MDA <MDA <MDA 0% N/A 8.57E-02 1.34E-01 OL-1-3 SP-2 PB09-02116 SR-176-197 408.1 <MDA <MDA <MDA <MDA 0% N/A 6.95E-02 1.10E-01 OL-1-3 SP-3 PB09-02117 SR-176-198 379.5 <MDA <MDA <MDA <MDA 0% N/A 7.91E-02 1.24E-01 OL-1-3 SP-4 PB09-02118 SR-176-199 393.3 <MDA <MDA <MDA <MDA 0% N/A 7.21E-02 1.15E-01 OL-1-3 SP-5 PB09-02119 SR-176-200 376.7 <MDA <MDA <MDA <MDA 0% N/A 7.96E-02 1.25E-01 OL-1-3 SP-6 PB09-02120 SR-176-201 426.0 <MDA <MDA <MDA <MDA 0% N/A 6.66E-02 1.08E-01 OL-1-3 SP-7 P809-02122 SR-176-203 384.8 1.90E-01 8.99E-02 <MDA <MDA 2% N/A 1.22E-01 OL-1-3 SP-8 PB09-02123 SR-176-204 428.9 <MDA <MDA <MDA <MDA 0% N/A 6.99E-02 1.09E-01 OL-1-3 SP-9 PB09-02124 SR-176-205 397.7 <MDA <MDA <MDA <MDA 0% N/A 7.13E-02 1.33E-01 OL-1-3 SP-10 PB09-02125 SR-1 76-206 375.8 <MDA <MDA <MDA <MDA 0% N/A 8.76E-02 1.25E-01 OL-1-3 SP-11 PB09-02126 SR-1 76-207 363.8 <MDA <MDA <MDA <MDA 0% N/A 7.59E-02 1.24E-01 APPENDIX C FINAL STATUS SURVEY SOIL SAMPLE RESULTS Plum Brook Reactor Facility FSSR, Attachment 7 Appendix C, Rev. 0, Page 4 of 17 CLASS I SOIL SAMPLE RESULTS Cs-137 Co-60 DCGL(1) 11.4 DCGL 3.7 DCGLT'7 14.7 DCGL 3.5 Cs-137 Co-60 DCGL t 3 7 11.82 DCGL 3.8 MDA MDA Location Sample Log # Sample # Weight (g) pCilg 2. pCilg 2 % Unity Cs:Co pCi/g pCilg OL-1-4 SP-1 PB09-01376 SR-169-13 369.1 <MDA <MDA <MDA <MDA 0% N/A 6.82E-02 6.36E-02 OL-1-4 SP-2 PB09-01377 SR-169-14 376.8 <MDA <MDA <MDA <MDA 0% N/A 7.57E-02 1.15E-01 OL-1-4 SP-3 PB09-01379 SR-169.-6 374.4 <MDA <MDA <MDA <MDA 0% N/A 7.62E-02 1.16E-01 OL-1-4 SP-4 PB09-01380 SR-169-17 410.4 <MDA <MDA <MDA <MDA 0% N/A 8.662E-02 1.14E-01 OL-1-4 SP-5 PB09-01382 SR-169-18 375.1 5.83E-01 1.76E-01 1.00E+00 1.762-01 31% N/A _ _ _ _ _ _ _ _OL-1-4 SP-6 PB09-01383 SR-169-19 396.5 <MDA <MDA <MDA <MDA 0% N/A 1.01E2-01 1.18E-01 OL-1-4 SP-7 PB09-01384 SR-169-20 387.7 <MDA <MDA <MDA <MDA 0% N/A 8.36E-02 1.12E-01 OL-1-4 SP-8 PB09-01385 SR-169-21 402.0 <MDA <MDA <MDA <MDA 0% N/A 7.46E-02 1.17E-01 OL-1-4 SP-9 PB09-01386 SR-169-22 400.8 <MDA <MDA <MDA <MDA 0% N/A 7.12E-02 1.092-01 OL-1-4 SP-10 PB19-01387 SR-169-23 381.3 <MDA <MDA <MDA <MDA 0% N/A 8.64E-02 1.23E-01 OL-1-4 SP-11 PB09-01388 SR-169-24 390.1 <MDA <MDA <MDA <MDA 0% N/A 7.31E-02 1.12E-01 OL-1-5 SP-1 PB09-02057 SR-176-1 402.1 <MDA <MDA <MDA <MDA 0% N/A 7.09E-02 1.08E-01 OL-1-5 SP-2 PB09-02058 SR-176-2 363.0 3.03E-01 1. 17E-01 <MDA <MDA 3% N/A 7.46E _0 1.29E-01 OL-1-4 SP-3 PB09-02059 SR-176-3 399.9 <MDA <MDA <MDA <MDA 0% N/A 7.792E-02 1.13E-01 OL-1-5 SP-A PB09-02060 SR-1769- 380.8 <MDA <MDA <MDA <MDA 0% N/A 9.99E-02 1.14E-01 OL-1-5 SP-5 PB09-02062 SR-1976-5 397.6 <MDA <MDA <MDA <MDA 0% N/A 1.13E-01 1.182E-01 OL-1-5 SP-6 PB09-02063 SR-176-6 405.0 <MDA <MDA <MDA <MDA 0% N/A 7.00E-02 1.11E-01 OL-1-5 SP-7 PB09-02064 SR-176-7 436.7 <MDA <MDA <MDA <MDA 0% N/A 6.87E-02 1.072E-01 OL-1-5 SP-8 PB09-02065 SR-176-8 383.9 <MDA <MDA <MDA <MDA 0% N/A 7.43E-02 1.13E-01 OL-1-5 SP-9 PB09-02066 SR-176-9 366.8 <MDA <MDA <MDA <MDA 0% N/A 7.78E-02 1.19E-01 OL-1-5SP-10 PB09-02067 SR-176-10 404.4 <MDA <MDA <MDA <MDA 0% N/A 7.42E-02 1.16E-01 OL-1-5 SP-11 PB09-02068 SR-176-11 415.9 <MDA <MDA <MDA <MDA 0% N/A 6.82E-02 1.08E-01 OL-1-6 SP-1 PB09-04922 SR-204-1 427.5 <MDA <MDA <MDA <MDA 0% N/A 6.67E-02 1.02E-01 OL-1-6 SP-2 PB09-04923 SR-204-2 345.1 <MDA <MDA <MDA <MDA 0% N/A 8.27E-02 1.26E-01 OL-1-6 SP-3 PB09-04924 SR-204-3 441.0 <MDA <MDA <MDA <MDA 0% N/A 6.47E-02 9.86E-02 OL-1-6 SP-A PB09-04925 SR-2041- 312.1 <MDA <MDA <MDA <MDA 0% N/A 9.092E-02 1.44E-01 OL-1-6 SP-5 PB09-04926 SR-204-5 375.8 <MDA <MDA <MDA <MDA 0% N/A 7.592E-02 1.16E-01 OL-1-6 SP-6 PB09-04927 SR-204-6 341.5 <MDA <MDA <MDA <MDA 0% N/A 8.78E-02 1.372E-01 OL-1-6 SP-7 PB09-04928 SR-204-7 424.6 <MDA <MDA <MDA <MDA 0% N/A 1.02E-01 1.02E-01 OL-1-6 SP-8 PB09-04929 SR-204-8 457.3 <MDA <MDA <MDA <MDA 0% N/A 7.20E-02 1.03E-01 OL-1-6 SP-9 PB09-04930 SR-204-9 384.9 <MDA <MDA <MDA <MDA 0% N/A 7.41E-02 1.13E-01 OL-1-6SP-10 PB09-04931 SR-204-10 357.5 <MDA <MDA <MDA <MDA 0% N/A 8.39E-02 1.31E-01 OL-1-6 SP-11 PB09-04932 SR-204-11 378.0 <MDA <MDA <MDA <MDA 0% N/A 7.55E-02 1.15E-01 APPENDIX C FINAL STATUS SURVEY SOIL SAMPLE RESULTS Plum Brook Reactor Facility FSSR, Attachment 7 Appendix C, Rev. 0, Page 5 of 17 CLASS I SOIL SAMPLE RESULTS Cs-1 37 Co-60 DCGL t 1 t 11.4 DCGL 3.7 DCGL(2) 14.7 DCGL 3.5 Cs-137 Co-60 DCGL7 3 T 11.82 DCGL 3.8 MDA MDA Location Sample Log # Sample # Weight (g) pCi/g 2a pCilg % Unit, Cs:Co pCilg pCi/g OL-1-7 SP-1 PB10-01504 SR-237-1 380.3 <MDA <MDA <MDA <MDA 0% N/A 7.46E-02 1.19E-01 OL-1-7 SP-2 PB10-01505 SR-237-2 456.1 <MDA <MDA <MDA <MDA 0% N/A 6.03E-02 9.67E-02 OL-1-7 SP-3 PB10-01506 SR-237-3 458.7 <MDA <MDA <MDA <MDA 0% N/A 6.19E-02 9.83E-02 OL-1-7 SP-4 PB10-01507 SR-237-4 383.9 <MDA <MDA <MDA <MDA 0% N/A 7.17E-02 1.15E-01 OL-1-7 SP-5 PB10-01508 SR-237-5 427.5 <MDA <MDA <MDA <MDA 0% N/A 6.64E-02 1.06E-01 OL-1-7 SP-6 PB10-01509 SR-237-6 450.8 <MDA <MDA <MDA <MDA 0% N/A 4.27E-02 4.89E-02 OL-1-7 SP-7 PB10-01510 SR-237-7 433.8 <MDA <MDA <MDA <MDA 0% N/A 6.54E-02 1.04E-01 OL-1-7 SP-8 PB10-01511 SR-237-8 451.5 <MDA <MDA <MDA <MDA 0% N/A 6.09E-02 9.77E-02 OL-1-7 SP-9 PB10-01512 SR-237-9 352.1 <MDA <MDA <MDA <MDA 0% N/A 8.06E-02 1.28E-01 OL-1-7 SP-10 PB10-01513 SR-237-10 380.9 <MDA <MDA <MDA <MDA 0% N/A 1.12E-01 1.16E-01 OL-1-7 SP-11 PB10-01514 SR-237-11 398.7 <MDA <MDA <MDA <MDA 0% N/A 7.12E-02 1.13E-01 OL-1-8 SP-1 PB10-01519 SR-237-13 403.7 <MDA <MDA <MDA <MDA 0% N/A 6.81E-02 1.09E-01 OL-1-8 SP-2 PB10-01522 SR-237-15 440.7 <MDA <MDA <MDA <MDA 0% N/A 8.74E-02 1.00E-01 OL-1-8 SP-3 PB10-01523 SR-237-16 439.3 <MDA <MDA <MDA <MDA 0% N/A 8.15E-02 1.03E-01 OL-1-8 SP-4 PB10-01524 SR-237-17 380.3 <MDA <MDA <MDA <MDA 0% N/A 7.23E-02 1.16E-01 OL-1-8 SP-5 PB10-01525 SR-237-18 464.3 <MDA <MDA <MDA <MDA 0% N/A 6.11E-02 9.71E-02 OL-1-8 SP-6 PB10-01526 SR-237-19 375.9 <MDA <MDA <MDA <MDA 0% N/A 7.32E-02 1.17E-01 OL-1-8 SP-7 PB10-01527 SR-237-20 422.9 <MDA <MDA <MDA <MDA 0% N/A 6.71E-02 1.07E-01 OL-1-8 SP-8 PB10-01528 SR-237-21 398.7 <MDA <MDA <MDA <MDA 0% N/A 6.90E-02 1.11E-01 OL-1-8 SP-9 PB10-01529 SR-237-22 375.0 <MDA <MDA <MDA <MDA 0% N/A 7.57E-02 1.20E-01 OL-1-8SP-10 PB10-01530 SR-237-23 378.0 <MDA <MDA <MDA <MDA 0% N/A 7.28E-02 1.17E-01 OL-1-8 SP-11 PB10-01531 SR-237-24 411.0 <MDA <MDA <MDA <MDA 0% N/A 6.90E-02 1.10E-01 OL-1-9SP-1 PB10-01576 SR-237-25 329.9 <MDA <MDA <MDA <MDA 0% N/A 8.60E-02 1.37E-01 OL-1-9SP-2 PB10-01577 SR-237-26 339.8 <MDA <MDA <MDA <MDA 0% N/A 8.10E-02 1.30E-01 OL-1-9 SP-3 PB10-01579 SR-237-28 336.2 <MDA <MDA <MDA <MDA 0% N/A 8.18E-02 1.31E-01 OL-1-9 SP-4 PB10-01580 SR-237-29 319.8 <MDA <MDA <MDA <MDA 0% N/A 1.12E-01 1.41E-01 OL-1-9 SP-5 PB10-01582 SR-237-30 420.7 <MDA <MDA <MDA <MDA 0% N/A 6.54E-02 1.05E-01 OL-1-9 SP-6 PB10-01583 SR-237-31 345.9 <MDA <MDA <MDA <MDA 0% N/A 8.20E-02 1.30E-01 OL-1-9 SP-7 PB10-01584 SR-237-32 325.7 <MDA <MDA <MDA <MDA 0% N/A 8.45E-02 1.35E-01 OL-1-9 SP-8 PB10-01585 SR-237-33 464.8 <MDA <MDA <MDA <MDA 0% N/A 6.10E-02 9.71E-02 OL-1-9SP-9 PB10-01586 SR-237-34 420.2 <MDA <MDA <MDA <MDA 0% N/A 6.55E-02 1.05E-01 OL-1-9 SP-10 PB10-01587 SR-237-35 420.0 <MDA <MDA <MDA <MDA 0% N/A 6.76E-02 1.07E-01 OL-1-9 SP-11 PB10-01588 SR-237-36 444.2 <MDA <MDA <MDA <MDA 0% N/A 6.192-02 9.93E-02 APPENDIX C FINAL STATUS SURVEY SOIL SAMPLE RESULTS Plum Brook Reactor Facility FSSR, Attachment 7 Appendix C, Rev. 0, Page 6 of 17 CLASS 1 SOIL SAMPLE RESULTS Cs-1 37 Co-60 DCGL 1) 11.4 DCGL 3.7 DCGL(2) 14.7 DCGL 3.5 Cs-137 Co-60 DCGL T 3 t 11.82 DCGL 3.8 MDA MDA Location Sample Log # Sample # Weight (a) pCig 2 pClFg 20 % Unity Cs:Co pCllg pCllg OL-1-10 SP-1 PB10-01869 SR-244 363.8 2.05E-01 9.19E-02 <MDA <MDA 1% N/A 1.21 E-01 OL-1-10 SP-2 PB10-01870 SR-244 384.2 1.80E-01 8.74E-02 <MDA <MDA 1% N/A 1.23E-01 OL-1-10 SP-3 PB10-01871 SR-244 331.6 <MDA <MDA <MDA <MDA 0% N/A 8.56E-02 1.36E-01 OL-1-10 SP-4 PB10-01872 SR-244 430.8 <MDA <MDA <MDA <MDA 0% N/A 6.39E-02 1.02E-01 OL-1-10 SP-5 PB10-01873 SR-244 367.4 <MDA <MDA <MDA <MDA 0% N/A 8.16E-02 1.28E-01 OL-1-10 SP-6 PB10-01874 SR-244 380.6 1.62E-01 8.1OE-02 <MDA <MDA 1% N/A 1.18E-01 OL-1-10SP-7 PB10-01875 SR-244 401.1 <MDA <MDA <MDA <MDA 0% N/A 6.86E-02 1.10E-01 OL-1-10 SP-8 PB10-01876 SR-244 412.8 <MDA <MDA <MDA <MDA 0% N/A 7.26E-02 1.14E-01 OL-1-10SP-9 PB10-01877 SR-244 457.2 <MDA <MDA <MDA <MDA 0% N/A 6.21E-02 9.86E-02 OL-1-10 SP-10 PB10-01878 SR-244 396.4 <MDA <MDA <MDA <MDA 0% N/A 6.94E-02 1.11E-01 OL-1-10 SP-11 PB10-01879 SR-244 421.8 <MDA <MDA <MDA <MDA 0% N/A 7.11E-02 1.12E-01 OL-1-11 SP-1 PB10-01925 SR-237-37 425.0 <MDA <MDA <MDA <MDA 0% N/A 6.47E-02 1.04E-01 OL-1-11 SP-2 PB10-01926 SR-237-38 432.6 1.50E-01 7.53E-02 <MDA <MDA 1% N/A 1.09E-01 OL-1-11 SP-3 PB10-01927 SR-237-39 407.0 <MDA <MDA <MDA <MDA 0% N/A 6.97E-02 1.11E-01 OL-1-11 SP-4 PB10-01928 SR-237-40 375.3 <MDA <MDA <MDA <MDA 0% N/A 7.33E-02 1.18E-01 OL-1-11 SP-5 PB10-01929 SR-237-41 373.1 <MDA <MDA <MDA <MDA 0% N/A 8.03E-02 1.27E-01 OL-1-11 SP-6 PB10-01930 SR-237-42 387.4 <MDA <MDA <MDA <MDA 0% N/A 7.32E-02 1.16E-01 OL-1-11 SP-7 PB10-01931 SR-237-43 331.3 <MDA <MDA <MDA <MDA 0% N/A 1.42E-01 1.33E-01 OL-1-11 SP-8 PB10-01932 SR-237-44 376.0 <MDA <MDA <MDA <MDA 0% N/A 7.97E-02 1.26E-01 OL-1-11 SP-9 PB10-01933 SR-237-45 354.4 <MDA <MDA <MDA <MDA 0% N/A 8.01 E-02 1.27E-01 OL-1-11 SP-10 PB10-01934 SR-237-46 382.6 <MDA <MDA <MDA <MDA 0% N/A 7.19E-02 1.15E-01 OL-1-11 SP-11 PB10-01935 SR-237-47 372.6 <MDA <MDA <MDA <MDA 0% N/A 8.05E-02 1.27E-01 OL-1-12 SP-1 PB10-01977 SR-237-49 400.4 <MDA <MDA <MDA <MDA 0% N/A 9.92E-02 1.13E-01 OL-1-12 SP-2 PB10-01979 SR-237-51 433.1 <MDA <MDA <MDA <MDA 0% N/A 6.55E-02 1.04E-01 OL-1-12 SP-3 PB10-01980 SR-237-52 448.6 <MDA <MDA <MDA <MDA 0% N/A 7.33E-02 1.05E-01 OL-1-12 SP-4 PB10-01982 SR-237-53 390.9 <MDA <MDA <MDA <MDA 0% N/A 7.63E-02 1.15E-01 OL-1-12 SP-5 PB10-01983 SR-237-54 420.7 <MDA <MDA <MDA <MDA 0% N/A 7.12E-02 1.12E-01 OL-1-12 SP-6 PB10-01984 SR-237-55 402.0 <MDA <MDA <MDA <MDA 0% N/A 8.18E-02 1.17E-01 OL-1-12 SP-7 PB10-01985 SR-237-56 440.6 <MDA <MDA <MDA <MDA 0% N/A 6.44E-02 1.02E-01 OL-1-12 SP-8 PB10-01986 SR-237-57 420.7 <MDA <MDA <MDA <MDA 0% N/A 7.12E-02 1.12E-01 OL-1-12 SP-9 PB10-01987 SR-237-58 366.6 1.79E-01 8.67E-02 <MDA <MDA 2% N/A 1.23E-01 OL-1-12 SP-10 P810-01988 SR-237-59 393.9 <MDA <MDA <MDA <MDA 0% N/A 7.61E-02 1.20E-01 OL-1-12 SP-11 P810-01989 SR-237-60 377.5 <MDA <MDA <MDA <MDA 0% N/A 7.52E-02 1.19E-01 OL-1-12 SP-12 PB10-01990 SR-237-61 342.8 <MDA <MDA <MDA <MDA 0% N/A 8.74E-02 1.38E-01 APPENDIX C FINAL STATUS SURVEY SOIL SAMPLE RESULTS Plum Brook Reactor Facility FSSR, Attachment 7 Appendix C, Rev. 0, Page 7 of 17 CLASS 1 SOIL SAMPLE RESULTS Cs-137 Co-6O DCGL(') 11.4 DCGL 3.7 DCGL(z) 14.7 DCGL 3.5 Cs-137 Co-60 DCGL t 3) 11.82 DCGL 3.8 MDA MDA Location Sample Log # Sample # Weight (a) pCI/g pCilg 2y % Unity Cs:Co pCi pCig OL-1-13 SP-1 PB10-02052 SR-237-62 436.3 <MDA <MDA <MDA <MDA 0% N/A 6.31E-02 1.01E-01 OL-1-13 SP-2 PB10-02053 SR-237-63 402.6 <MDA <MDA <MDA <MDA 0% N/A 7.44E-02 1.17E-01 OL-1-13 SP-3 PB10-02054 SR-237-64 386.1 2.09E-01 9.15E-02 <MDA <MDA 2% N/A 1.17E-01 OL-1-13 SP-4 PB10-02055 SR-237-65 418.3 <MDA <MDA <MDA <MDA 0% N/A 6.58E-02 1.05E-01 OL-1-13 SP-5 PB10-02056 SR-237-66 454.3 <MDA <MDA <MDA -<MDA 0% N/A 6.60E-02 1.04E-01 OL-1-13 SP-6 PB10-02057 SR-237-67 403.2 <MDA <MDA <MDA <MDA 0% N/A 8.04E-02 1.12E-01 OL-1-13 SP-7 PB10-02059 SR-237-69 440.6 <MDA <MDA <MDA <MDA 0% N/A 6.80E-02 1.07E-01 OL-1-13 SP-8 PB10-02060 SR-237-70 405.7 <MDA <MDA <MDA <MDA 0% N/A 6.99E-02 1.11E-01 OL-1-13 SP-9 PB10-02062 SR-237-71 414.7 <MDA <MDA <MDA <MDA 0% N/A 7.23E-02 1.14E-01 OL-1-13 SP-10 PB1O-02063 SR-237-72 446.3 <MDA <MDA <MDA <MDA 0% N/A 6.36E-02 1.01E-01 OL-1-13 SP-11 PB10-02064 SR-237-73 445.5 <MDA <MDA <MDA <MDA 0% N/A 7.31E-02 9.89E-02 OL-1-14 SP-1 PB10-02151 SR-237-74 360.8 2.65E-01 1.28E-01 <MDA <MDA 2% N/A 1.31 E-01 OL-1-14 SP-2 PB10-02152 SR-237-75 420.8 <MDA <MDA <MDA <MDA 0% N/A 1.04E-01 1.12E-01 OL-1-14 SP-3 PB10-02154 SR-237-77 440.6 <MDA <MDA <MDA <MDA 0% N/A 7.47E-02 1.07E-01 OL-1-14 SP-4 PB10-02155 SR-237-78 397.2 <MDA <MDA <MDA <MDA 0% N/A 7.55E-02 1.19E-01 OL-1-14 SP-5 PB10-02156 SR-237-79 350.1 <MDA <MDA <MDA <MDA 0% N/A 8.56E-02 1.35E-01 OL-1-14 SP-6 PB10-02157 SR-237-80 410.2 <MDA <MDA <MDA <MDA 0% N/A 7.31 E-02 1.15E-01 OL-1-14 SP-7 PB10-02158 SR-237-81 339.8 2.75E-01 1.15E-01 <MDA <MDA 2% N/A 1.39E-01 OL-1-14 SP-8 PB10-02136 SR-237-82 427.5 <MDA <MDA <MDA <MDA 0% N/A 7.01 E-02 1.11E-01 OL-1-14 SP-9 PB10-02137 SR-237-83 447.4 <MDA <MDA <MDA <MDA 0% N/A 9.60E-02 1.06E-01 OL-1-14 SP-10 PB10-02138 SR-237-84 428.3 <MDA <MDA <MDA <MDA 0% N/A 7.OOE-02 1.10E-01 OL-1-14 SP-11 PB10-02140 SR-237-85 405.7 <MDA <MDA <MDA <MDA 0% N/A 7.39E-02 1.17E-01 OL-1-15 SP-1 PB10-02185 SR-237-86 368.5 <MDA <MDA <MDA <MDA 0% N/A 1.49E-01 1.20E-01 OL-1-15 SP-2 PB10-02186 SR-237-87 418.4 <MDA <MDA <MDA <MDA 0% N/A 8.09E-02 1.09E-01 OL-1-15 SP-3 PB1O-02187 SR-237-88 448.8 <MDA <MDA <MDA <MDA 0% N/A 6.68E-02 1.05E-01 OL-1-15 SP-4 PB10-02188 SR-237-89 411.3 <MDA <MDA <MDA <MDA 0% N/A 6.95E-02 1.11E-01 OL-1-15 SP-5 PB10-02189 SR-237-90 433.5 2.93E-01 1.01E-01 <MDA <MDA 2% N/A 1.02E-01 OL-1-15 SP-6 PB10-02190 SR-237-91 380.9 1.92E-01 9.07E-02 <MDA <MDA 2% N/A 1.24E-01 OL-1-15 SP-7 PB10-02191 SR-237-92 401.2 <MDA <MDA <MDA <MDA 0% N/A 7.13E-02 1.14E-01 OL-1-15 SP-8 PB10-02192 SR-237-93 340.7 <MDA <MDA <MDA <MDA 0% N/A 8.07E-02 1.29E-01 OL-1-15 SP-9 PB10-02193 SR-237-94 362.5 <MDA <MDA <MDA <MDA 0% N/A 8.27E-02 1.30E-01 OL-1-15 SP-10 PB1O-02194 SR-237-95 377.9 <MDA <MDA <MDA <MDA 0% N/A 5.05E-02 6.03E-02 OL-1-15, SP-11 PB10-02196 SR-237-97 430.1 <MDA <MDA <MDA <MDA 0% N/A 6.97E-02 1.10E-01 APPENDIX C FINAL STATUS SURVEY SOIL SAMPLE RESULTS Plum Brook Reactor Facility FSSR, Attachment 7 Appendix C, Rev. 0, Page 8 of 17 CLASS I SOIL SAMPLE RESULTS Cs-137 Co-60 DCGL(j ) 11.4 DCGL 3.7 DCGL72) 14.7 DCGL 3.5 Cs-137 Co-60 DCGLr 3 T 11.82 DCGL 3.8 MDA MDA Location Sample Loa # Sample # Weight (g) pCi/g 2 pCi/g 2 % Unity Cs:Co pCl/g pCi/g OL-1-16 SP-1 PB10-02371 SR-237-98 391.9 <MDA <MDA <MDA <MDA 0% N/A 7.65E-02 1.20E-01 OL-1-16 SP-2 PB10-02372 SR-237-99 419.5 <MDA <MDA <MDA <MDA 0% N/A 6.82E-02 1.09E-01 OL-1-16 SP-3 PB10-02373 SR-237-100 410.8 <MDA <MDA <MDA <MDA 0% N/A 6.96E-02 1.11E-01 OL-1-16 SP-4 PB10-02374 SR-237-101 378.3 <MDA <MDA <MDA <MDA 0% N/A 7.56E-02 1.21E-01 OL-1-16 SP-5 PB10-02375 SR-237-102 449.1 <MDA <MDA <MDA <MDA 0% N/A 6.37E-02 1.02E-01 OL-1-16 SP-6 PB10-02376 SR-237-103 401.0 2.45E-01 1.20E-01 <MDA <MDA 2% N/A 1.18E-01 OL-1-16 SP-7 PB10-02377 SR-237-104 453.3 <MDA <MDA <MDA <MDA 0% N/A 6.31E-02 1.01E-01 OL-1-16 SP-8 PB10-02378 SR-237-105 438.3 <MDA <MDA <MDA <MDA 0% N/A 6.84E-02 1.08E-01 OL-1-16 SP-9 PB10-02379 SR-237-106 431.3 <MDA <MDA <MDA <MDA 0% N/A 6.63E-02 1.06E-01 OL-1-16 SP-10 PB10-02380 SR-237-107 385.7 3.69E-01 1.25E-01 <MDA <MDA 3% N/A 1.22E-01 OL-1-16 SP-11 PB10-02382 SR-237-108 379.9 <MDA <MDA <MDA <MDA 0% N/A 7.53E-02 1.20E-01 OL-1-17 SP-1 PB10-02826 SR-237-110 399.3 <MDA <MDA <MDA <MDA 0% N/A 7.51E-02 1.18E-01 OL-1-17 SP-2 PB10-02828 SR-237-112 407.5 <MDA <MDA <MDA <MDA 0% N/A 7.36E-02 1.16E-01 OL-1-17 SP-3 PB10-02829 SR-237-113 316.5 <MDA <MDA <MDA <MDA 0% N/A 9.47E-02 1.49E-01 OL-1-17 SP-4 PB1O-02830 SR-237-114 385.0 <MDA <MDA <MDA <MDA 0% N/A 1.02E-01 1.19E-01 OL-1-17 SP-5 PB10-02831 SR-237-115 390.2 2.40E-01 1.OOE-01 <MDA <MDA 2% N/A 1.21E-01 OL-1-17 SP-6 PB10-02832 SR-237-116 360.1 <MDA <MDA <MDA <MDA 0% N/A 7.94E-02 1.27E-01 OL-1-17 SP-7 PB10-02833 SR-237-117 450.0 2.62E-01 9.76E-02 <MDA <MDA 2% N/A 1.05E-01 OL-1-17 SP-8 PB10-02834 SR-237-118 314.2 <MDA <MDA <MDA <MDA 0% N/A 1.21E-01 1.45E-01 OL-1-17 SP-9 PB10-02835 SR-237-119 445.6 <MDA <MDA <MDA <MDA 0% N/A 6.73E-02 1.06E-01 OL-1-17 SP-10 PB10-02836 SR-237-120 394.9 1.87E-01 8.58E-02 <MDA <MDA 2% N/A 1.161-01 OL-1-17 SP-11 PB10-02837 SR-237-121 398.8 <MDA <MDA <MDA <MDA 0% N/A 3.76E-02 5.93E-02 OL-1-18 SP-1 PB10-03300 SR-237-146 399.5 <MDA <MDA <MDA <MDA 0% N/A 7.50E-02 1.18E-01 OL-1-18 SP-2 PB10-03302 SR-237-147 439.9 <MDA <MDA <MDA <MDA 0% N/A 6.50E-02 1.04E-01 OL-1-18 SP-3 PB10-03304 SR-237-149 414.7 <MDA <MDA <MDA <MDA 0% N/A 6.90E-02 1.10E-01 OL-1-18 SP-4 PB10-03305 SR-237-150 424.6 <MDA <MDA <MDA <MDA 0% N/A 7.06E-02 1.11E-01 OL-1-18 SP-5 PB10-03306 SR-237-151 429.1 <MDA <MDA <MDA <MDA 0% N/A 6.66E-02 1.06E-01 OL-1-18 SP-6 PB10-03307 SR-237-152 418.1 <MDA <MDA <MDA <MDA 0% N/A 1.11E-01 1.13E-01 OL-1-18 SP-7 PB10-03308 SR-237-153 402.8 <MDA <MDA <MDA <MDA 0% N/A 7.10E-02 1.13E-01 OL-1-18 SP-8 PB10-03309 SR-237-154 349.4 <MDA <MDA <MDA <MDA 0% N/A 8.18E-02 1.31E-01 OL-1-18 SP-9 PB10-03310 SR-237-155 381.5 <MDA <MDA <MDA <MDA 0% N/A 7.86E-02 1.24E-01 OL-1-18SP-10 PB10-03311 SR-237-156 377.3 <MDA <MDA <MDA <MDA 0% N/A 7.58E-02 1.21E-01 APPENDIX C FINAL STATUS SURVEY SOIL SAMPLE RESULTS Plum Brook Reactor Facility FSSR, Attachment 7 Appendix C, Rev. 0, Page 9 of 17 CLASS I SOIL SAMPLE RESULTS Cs-137 Co-60 DCGL 11.4 DCGL 3.7 DCGL(') 14.7 DCGL 3.5 Cs-137 Co-60 DCGL3 11.82 DCGL 3.8 MDA MDA Location Sample Log # Sample # Weight () pCi/g 2a pCi/g 2a % Unity Cs:Co pCilg pCiIg OL-1-18 SP-11 PB1O-03312 SR-237-157 442.5 <MDA <MDA <MDA <MDA 0% N/A 6.77E-02 1.07E-01 OL-1-19SP-1 PB10-03106 SR-237-122 402.1 <MDA <MDA <MDA <MDA 0% N/A 1.36E-01 1.17E-01 OL-1-19SP-2 PB10-03107 SR-237-123 429.0 <MDA <MDA <MDA <MDA 0% N/A 6.67E-02 1.06E-01 OL-1-19SP-3 PB10-03109 SR-237-125 441.4 <MDA <MDA <MDA <MDA 0% N/A 6.48E-02 1.03E-01 OL-1-19SP-4 PB10-03110 SR-237-126 432.1 <MDA <MDA <MDA <MDA 0% N/A 6.94E-02 1.09E-01 OL-1-19 SP-5 PB10-03111 SR-237-127 422.8 1.56E-01 7.58E-02 <MDA <MDA 1% N/A 1.08E-01 OL-1-19 SP-6 PB10-03112 SR-237-128 415.8 1.66E-01 8.08E-02 <MDA <MDA 1% N/A 1.14E-01 OL-1-19 SP-7 PB10-03113 SR-237-129 383.2 <MDA <MDA <MDA <MDA 0% N/A 1.33E-01 1.19E-01 OL-1-19 SP-8 PB10-03114 SR-237-130 434.4 1.83E-01 5.87E-02 <MDA <MDA 2% N/A 5.44E-02 OL-1-19SP-9 PB10-03115 SR-237-131 429.7 <MDA <MDA <MDA <MDA 0% N/A 6.66E-02 1.06E-01 OL-1-19SP-10 PB10-03116 SR-237-132 428.3 <MDA <MDA <MDA <MDA 0% N/A 6.68E-02 1.07E-01 OL-1-19 SP-11 PB10-03117 SR-237-133 440.3 <MDA <MDA <MDA <MDA 0% N/A 6.81E-02 1.07E-01 OL-1-20 SP-1 PB10-03259 SR-237-134 377.6 <MDA <MDA <MDA <MDA 0% N/A 7.29E-02 1.17E-01 OL-1-20 SP-2 PB10-03260 SR-237-135 348.0 <MDA <MDA <MDA <MDA 0% N/A 8.61 E-02 1.36E-01 OL-1-20 SP-3 PB1O-03263 SR-237-137 320.6 <MDA <MDA <MDA <MDA 0% N/A 8.58E-02 1.37E-01 OL-1-20 SP-4 PB10-03264 SR-237-138 405.7 <MDA <MDA <MDA <MDA 0% N/A 7.39E-02 1.16E-01 OL-1-20 SP-5 PB10-03265 SR-237-139 388.2 <MDA <MDA <MDA <MDA 0% N/A 3.68E-02 5.87E-02 OL-1-20 SP-6 PB10-03266 SR-237-140 380.5 <MDA <MDA <MDA <MDA 0% N/A 7.23E-02 1.16E-01 OL-1-20 SP-7 PB10-03267 SR-237A141 326.1 <MDA <MDA <MDA <MDA 0% N/A 9.19E-02 1.45E-01 OL-1-20 SP-8 PB10-03268 SR-237-142 423.8 <MDA <MDA <MDA <MDA 0% N/A 7.07E-02 1.11E-01 OL-1-20 SP-9 PB10-03269 SR-237-143 359.4 <MDA <MDA <MDA <MDA 0% N/A 8.34E-02 1.31 E-01 OL-1-20 SP-10 PB10-03270 SR-237-144 345.3 <MDA <MDA <MDA <MDA 0% N/A 8.68E-02 1.37E-01 OL-1-20 SP-11 PB10-03271 SR-237-145 339.6 <MDA <MDA <MDA <MDA 0% N/A 8.83E-02 1.39E-01 OL-1-21 SP-1 PB10-03511 SR-237-158 436.9 <MDA <MDA <MDA <MDA 0% N/A 6.54E-02 1.04E-01 OL-1-21 SP-2 PB10-03512 SR-237-159 353.3 <MDA <MDA <MDA <MDA 0% N/A 8.55E-02 1.25E-01 OL-1-21 SP-3 PB10-03514 SR-237-161 348.7 <MDA <MDA <MDA <MDA 0% N/A 9.34E-02 1.26E-01 OL-1-21 SP-4 PB10-03515 SR-237-162 396.4 <MDA <MDA <MDA <MDA 0% N/A 7.21E-02 1.15E-01 OL-1-21 SP-5 PB10-03516 SR-237-163 438.0 <MDA <MDA <MDA <MDA 0% N/A 6.28E-02 1.01E-01 OL-1-21 SP-6 PB10-03517 SR-237-164 360.7 <MDA <MDA <MDA <MDA 0% N/A 7.93E-02 1.26E-01 OL-1-21 SP-7 PB10-03518 SR-237-165 393.1 <MDA <MDA <MDA <MDA 0% N/A 7.OOE-02 1.12E-01 OL-1-21 SP-8 PB10-03519 SR-237-166 331.8 <MDA <MDA <MDA <MDA 0% N/A 8.62E-02 1.37E-01 OL-1-21 SP-9 P810-03520 SR-237-167 395.3 2.36E-01 9.46E-02 <MDA <MDA 2% N/A 1.11E-01 OL-1-21 SP-10 PB10-03522 SR-237-168 450.8 <MDA <MDA <MDA <MDA 0% N/A 6.34E-02 1.01E-01 OL-1-21 SP-11 PB10-03523 SR-237-169 368.9 <MDA <MDA <MDA <MDA 0% N/A 7.46E-02 1.19E-01 APPENDIX C FINAL STATUS SURVEY SOIL SAMPLE RESULTS Plum Brook Reactor Facility FSSR, Attachment 7 Appendix C, Rev. 0, Page 10of 17 CLASS I SOIL SAMPLE RESULTS Cs-137 Co-60 DCGL(') 11.4 DCGL 3.7 DCGL(2' 14.7 DCGL 3.5 Cs-137 Co-60 DCGL73) 11.82 DCGL 3.8 MDA MDA Location Same Log # Sample# Weight (g) pCI/g 2 pCl/g % Unity Cs:Co pCilg pCilg OL-1-22 SP-1 PB10-03700 SR-237-194 329.5 <MDA <MDA <MDA <MDA 0% N/A 9.10E-02 1.43E-01 OL-1-22 SP-2 PB1O-03711 SR-237-195 332.9 <MDA <MDA <MDA <MDA 0% N/A 8.59E-02 1.37E-01 OL-1-22 SP-3 PBI0-03712 SR-237-196 381.0 <MDA <MDA <MDA <MDA 0% N/A 7.51E-02 1.20E-01 OL-1-22 SP-4 PB10-03713 SR-237-197 404.0 <MDA <MDA <MDA <MDA 0% N/A 7.08E-02 1.13E-01 OL-1-22 SP-5 PB10-03715 SR-237-199 392.1 <MDA <MDA <MDA <MDA 0% N/A 7.64E-02 1.20E-01 OL-1-22 SP-6 PB10-03716 SR-237-200 353.3 <MDA <MDA <MDA <MDA 0% N/A 8.09E-02 1.29E-01 OL-1-22 SP-7 PB10-03717 SR-237-201 372.9 <MDA <MDA <MDA <MDA 0% N/A 8.04E-02 1.27E-01 OL-1-22 SP-8 PB10-03718 SR-237-202 355.0 <MDA <MDA <MDA <MDA 0% N/A 806E-02 1.28E-01 OL-1-22 SP-9 PB10-03719 SR-237-203 376.5 <MDA <MDA <MDA <MDA 0% N/A 1.16E-01 1.25E-01 OL-1-22 SP-10 PBIO-03720 SR-237-204 322.9 <MDA <MDA <MDA <MDA 0% N/A 1.01E-01 1.41E-01 OL-1-22 SP-11 PB1O-03722 SR-237-205 347.5 <MDA <MDA <MDA <MDA 0% N/A 7.92E-02 1.27E-01 OL-1-23, SP-1 PB10-03609 SR-237-170 446.6 <MDA <MDA <MDA <MDA 0% N/A 6.16E-02 9.88E-02 OL-1-23, SP-2 PB1O-03610 SR-237-171 399.9 <MDA <MDA <MDA <MDA 0% N/A 7.50E-02 1.18E-01 OL-1-23, SP-3 PB10-03611 SR-237-172 337.8 <MDA <MDA <MDA <MDA 0% N/A 1.83E-01 1.35E-01 OL-1-23, SP-4 PB10-03612 SR-237-173 452.5 <MDA <MDA <MDA <MDA 0% N/A 6.08E-02 9.75E-02 OL-1-23, SP-5 PB10-03613 SR-237-174 419.6 <MDA <MDA <MDA <MDA 0% N/A 7.14E-02 1.13E-01 OL-1-23, SP-6 PB10-03614 SR-237-175 415.3 <MDA <MDA <MDA <MDA 0% N/A 6.89E-02 1.1OE-01 OL-1-23, SP-7 PB10-03615 SR-237-176 434.9 <MDA <MDA <MDA <MDA 0% N/A 6.33E-02 1.01E-01 OL-1-23, SP-8 PB10-03616 SR-237-177 463.8 <MDA <MDA <MDA <MDA 0% N/A 6.46E-02 1.02E-01 OL-1-23, SP-9 PB10-03617 SR-237-178 392.2 <MDA <MDA <MDA <MDA 0% N/A 7.29E-02 1.16E-01 OL-1-23, SP-10 PB10-03618 SR-237-179 436.4 <MDA <MDA <MDA <MDA 0% N/A 6.31E-02 1.01E-01 OL-1-23, SP-11 PB10-03620 SR-237-181 441.9 <MDA <MDA <MDA <MDA 0% N/A 6.23E-02 9.98E-02 OL-1-24-SP-1 PB10-03675 SR-237-182 389.6 <MDA <MDA <MDA <MDA 0% N/A 7.69E-02 1.21E-01 OL-1-24-SP-2 PB10-03676 SR-237-183 391.0 <MDA <MDA <MDA <MDA 0% N/A 7.31E-02 1.17E-01 OL-1-24-SP-3 PB10-03678 SR-237-185 392.2 <MDA <MDA <MDA <MDA 0% N/A 7.29E-02 1.16E-01 OL-1-24-SP-4 PB10-03679 SR-237-186 380.1 1.71E-01 8.57E-02 <MDA <MDA 1% N/A 1.24E-01 OL-1-24-SP-5 PB10-03680 SR-237-187 421.4 2.95E-01 1.30E-01 <MDA <MDA 2% N/A 1.08E-01 OL-1-24-SP-6 PB10-03682 SR-237-188 386.0 <MDA <MDA <MDA <MDA 0% N/A 7.76E-02 1.22E-01 OL-1-24-SP-7 PB10-03683 SR-237-189 450.5 <MDA <MDA <MDA <MDA 0% N/A 6.35E-02 1.01E-01 OL-1-24-SP-8 PB10-03684 SR-237-190 379.1 <MDA <MDA <MDA <MDA 0% N/A 7.91E-02 1.25E-01 OL-1-24-SP-9 PB10-03685 SR-237-191 366.9 <MDA <MDA <MDA <MDA 0% N/A 7.79E-02 1.24E-01 OL-1-24-SP-10 PB10-03686 SR-237-192 390.0 <MDA <MDA <MDA <MDA 0% N/A 7.68E-02 1.21E-01 OL-1-24-SP-11 PB10-03687 SR-237-193 383.5 <MDA <MDA <MDA <MDA 0% N/A 7.46E-02 1.19E-01 APPENDIX C FINAL STATUS SURVEY SOIL SAMPLE RESULTS Plum Brook Reactor Facility FSSR, Attachment 7 Appendix C, Rev. 0, Page 11 of 17 CLASS I SOIL SAMPLE RESULTS Cs-1 37 Co-60 DCGL 1ý 11.4 DCGL 3.7 DCGLW 2) 14.7 DCGL 3.5 Cs-I37 Co-60 DCGL 3) t11.82 DCGL 3.8 MDA MDA Location Sample Log # Sample # Weight (a pCil/ % unity Cs:Co pCilg OL-1-25 SP-1 PB10-03800 SR-237-206 322.8 <MDA <MDA <MDA <MDA 0% N/A 1.51E-01 1.41E-01 OL-1-25 SP-2 PB1O-03802 SR-237-207 341.1 8.80E-01 2.22E-01 <MDA <MDA 7% N/A 1.34E-01 OL-1-25 SP-3 PB10-03803 SR-237-208 332.4 <MDA <MDA <MDA <MDA 0% N/A 8.60E-02 1.37E-01 OL-1-25 SP-4 PB10-03804 SR-237-209 325.9 <MDA <MDA <MDA <MDA 0% N/A 8.77E-02 1.40E-01 OL-1-25 SP-5 PB10-03806 SR-237-211 425.6 4.01E-01 1.24E-01 <MDA <MDA 3% N/A 1.11E-01 OL-1-25 SP-6 PB10-03807 SR-237-212 317.0 <MDA <MDA <MDA <MDA 0% N/A 9.90E-02 1.44E-01 OL-1-25 SP-7 PB10-03808 SR-237-213 355.9 <MDA <MDA <MDA <MDA 0% N/A 8.42E-02 1.33E-01 OL-1-25 SP-8 PB10-03809 SR-237-214 348.7 <MDA <MDA <MDA <MDA 0% N/A 8.20E-02 1.31E-01 OL-1-25 SP-9 PB10-03810 SR-237-215 349.2 <MDA <MDA <MDA <MDA 0% N/A 8.58E-02 1.35E-01 OL-1-25 SP-10 PB10-03811 SR-237-216 368.7 2.21E-01 9.66E-02 <MDA <MDA 2% N/A 1.24E-01 OL-1-25 SP-11 PB10-03812 SR-237-217 453.9 <MDA <MDA <MDA <MDA 0% N/A 6.60E-02 1.04E-01 OL-1-26SP-1 PB10-04146 SR-279-1 375.3 <MDA <MDA <MDA <MDA 0% N/A 7.33E-02 1.17E-01 OL-1-26 SP-2 PB10-04147 SR-279-2 382.6 <MDA <MDA <MDA <MDA 0% N/A 7.83E-02 1.23E-01 OL-1-26 SP-3 PB10-04149 SR-279-4 384.1 <MDA <MDA <MDA <MDA 0% N/A 7.80E-02 1.23E-01 OL-1-26 SP-4 PB10-04150 SR-279-5 400.0 <MDA <MDA <MDA <MDA 0% N/A 8.68E-02 1.10E-01 OL-1-26 SP-5 PB10-04151 SR-279-6 461.7 <MDA <MDA <MDA <MDA 0% N/A 6.49E-02 1.02E-01 OL-1-26 SP-6 PB10-04152 SR-279-7 417.3 <MDA <MDA <MDA <MDA 0% N/A 6.59E-02 1.06E-01 OL-1-26 SP-7 PB10-04153 SR-279-8 424.0 <MDA <MDA <MDA <MDA 0% N/A 7.07E-02 1.11E-01 OL-1-26 SP-8 PB10-04154 SR-279-9 447.5 <MDA <MDA <MDA <MDA 0% N/A 6.15E-02 9.85E-02 OL-1-26 SP-9 PB10-04155 SR-279-10 383.1 <MDA <MDA <MDA <MDA 0% N/A 7.82E-02 1.23E-01 OL-1-26 SP-10 PB10-04156 SR-279-11 340.7 <MDA <MDA <MDA <MDA 0% N/A 8.39E-02 1.34E-01 OL-1-26 SP-11 PB10-04157 SR-279-12 342.1 <MDA <MDA <MDA <MDA 0% N/A 9.52E-02 1.29E-01 OL-1-26 SP-12 P810-04158 SR-279-13 338.0 <MDA <MDA <MDA <MDA 0% N/A 1.12E-01 1.40E-01 OL-1-33 SP-1 PB10-04193 SR-237-230 399.8 <MDA <MDA <MDA <MDA 0% N/A 6.88E-02 1.10E-01 OL-1-33SP-2 PB10-04194 SR-237-231 391.7 <MDA <MDA <MDA <MDA 0% N/A 7.65E-02 1.21E-01 OL-1-33 SP-3 PB10-04195 SR-237-232 336.0 <MDA <MDA <MDA <MDA 0% N/A 8.51E-02 1.36E-01 OL-1-33 SPA PB10-04196 SR-237-233 384.3 <MDA <MDA <MDA <MDA 0% N/A 9.03E-02 1.15E-01 OL-1-33 SP-5 PB10-04197 SR-237-234 368.6 <MDA <MDA <MDA <MDA 0% N/A 8.13E-02 1.28E-01 OL-1-33 SP-6 PB10-04198 SR-237-235 460.4 <MDA <MDA <MDA <MDA 0% N/A 6.21 E-02 9.90E-02 OL-1-33 SP-7 PB10-04199 SR-237-236 460.4 <MDA <MDA <MDA <MDA 0% N/A 6.51E-02 1.03E-01 OL-1-33 SP-8 PB10-04200 SR-237-237 367.3 <MDA <MDA <MDA <MDA 0% N/A 7.49E-02 1.20E-01 OL-1-33SP-9 PB10-04202 SR-237-238 416.9 <MDA <MDA <MDA <MDA 0% N/A 7.53E-02 1.09E-01 OL-1-33 SP-10 PB10-04203 SR-237-239 424.0 1.67E-01 7.69E-02 <MDA <MDA 1% N/A 1.04E-01 OL-1-33 SP-11 PB10-04204 SR-237-240 387.1 <MDA <MDA <MDA <MDA 0% N/A 7.74E-02 1.22E-01 APPENDIX C FINAL STATUS SURVEY SOIL SAMPLE RESULTS Plum Brook Reactor Facility FSSR, Attachment 7 Appendix C, Rev. 0, Page 12 of 17 CLASS I SOIL SAMPLE RESULTS Cs-I 37 Co-60 DCGL t 1 t 11.4 DCGL 3.7 DCGLW2) 14.7 DCGL 3.5 Cs-137 Co-60 DCGLr 3 7 11.82 DCGL 3.8 MDA MDA Location Sample Log # Sample # Weight ,g) pCl/g 2<* pCl/ 2 % Un Cs:Co pCilg PCi OL-1-34 SP-1 PB1O-04168 SR-237-218 352.7 1.91E-01 8.99E-02 <MDA <MDA 2% N/A 1.25E-01 OL-1-34 SP-2 PB10-04169 SR-237-219 335.1 <MDA <MDA <MDA <MDA 0% N/A 8.53E-02 1.36E-01 OL-1-34SP-3 PB10-04171 SR-237-221 453.9 <MDA <MDA <MDA <MDA 0% N/A 6.30E-02 1.OOE-01 OL-1-34 SP-4 PB10-04172 SR-237-222 321.4 <MDA <MDA <MDA <MDA 0% N/A 8.56E-02 1.37E-01 OL-1-34 SP-5 PB10-04173 SR-237-223 406.7 <MDA <MDA <MDA <MDA 0% N/A 7.03E-02 1.12E-01 OL-1-34 SP-6 PB10-04174 SR-237-224 462.0 <MDA <MDA <MDA <MDA 0% N/A 5.95E-02 9.54E-02 OL-1-34 SP-7 PB10-04175 SR-237-225 388.2 <MDA <MDA <MDA <MDA 0% N/A 7.37E-02 1.17E-01 OL-1-34 SP-8 PB10-04176 SR-237-226 332.1 <MDA <MDA <MDA <MDA 0% N/A 8.28E-02 1.33E-01 OL-1-34 SP-9 PB10-04177 SR-237-227 453.8 <MDA <MDA <MDA <MDA 0% N/A 6.30E-02 1.O0E-01 OL-1-34 SP-10 PB1O-04178 SR-237-228 422.2 <MDA <MDA <MDA <MDA 0% N/A 6.52E-02 1.04E-01 OL-1-34 SP-1 1 PB1O-04179 SR-237-229 456.5 <MDA <MDA <MDA <MDA 0% N/A 6.26E-02 9.99E-02 OL-1-35 SP-1 PB10-04180 SR-237-242 394.4 <MDA <MDA <MDA <MDA 0% N/A 6.98E-02 1.12E-01 OL-1-35SP-2 PB10-04182 SR-237-243 343.1 <MDA <MDA <MDA <MDA 0% N/A 1.33E-01 1.38E-01 OL-1-35 SP-3 PB10-04183 SR-237-244 447.9 <MDA <MDA <MDA <MDA 0% N/A 6.38E-02 1.02E-01 OL-1-35 SP-4 PB10-04184 SR-237-245 395.4 <MDA <MDA <MDA <MDA 0% N/A 6.96E-02 iI.E-01 OL-1-35 SP-5 PB10-04185 SR-237-246 354.1 <MDA <MDA <MDA <MDA 0% N/A 8.46E-02 1.33E-01 OL-1-35SP-6 PB10-04186 SR-237-247 364.7 <MDA <MDA <MDA <MDA 0% N/A 7.84E-02 1.25E-01 OL-1-35 SP-7 PB10-04187 SR-237-248 386.1 <MDA <MDA <MDA <MDA 0% N/A 7.13E-02 1.14E-01 OL-1-35 SP-8 PBIO-04188 SR-237-249 397.4 <MDA <MDA <MDA <MDA 0% N/A 7.54E-02 1.19E-01 OL-1-35 SP-9 PB1O-04189 SR-237-250 366.3 <MDA <MDA <MDA <MDA 0% N/A 7.81 E-02 1.24E-01 OL-1-35SP-10 PB10-04190 SR-237-251 339.9 <MDA <MDA <MDA <MDA 0% N/A 8.09E-02 1.30E-01 OL-1-35 SP-11 PB10-04191 SR-237-252 322.6 <MDA <MDA <MDA <MDA 0% N/A 1.59E-01 1.46E-01 OL-1-36 SP-1 PB10-04235 SR-237-254 317.5 <MDA <MDA <MDA <MDA 0% N/A 8.67E-02 1.39E-01 OL-1-36 SP-2 PB10-04236 SR-237-255 330.4 <MDA <MDA <MDA <MDA 0% N/A 9.07E-02 1.43E-01 OL-1-36SP-3 PB10-04237 SR-237-256 337.9 <MDA <MDA <MDA <MDA 0% N/A 8.14E-02 1.31E-01 OL-1-36 SP-4 PB10-04238 SR-237-257 392.6 1.76E-01 8.55E-02 <MDA <MDA 1% N/A 1.20E-01 OL-1-36 SP-5 PB10-04239 SR-237-258 456.9 <MDA <MDA <MDA <MDA 0% N/A 1.15E-01 9.65E-02 OL-1-36 SP-6 PB10-04240 SR-237-259 391.4 <MDA <MDA <MDA <MDA 0% N/A 7.66E-02 1.21E-01 OL-1-36 SP-7 PB10-04242 SR-237-260 389.5 <MDA <MDA <MDA <MDA 0% N/A 7.06E-02 1.13E-01 OL-1-36 SP-8 PB10-04243 SR-237-261 314.4 3.10E-01 1.27E-01 <MDA <MDA 3% N/A 1.50E-01 OL-1-36 SP-9 PB I0-04244 SR-237-262 420n 6<MIJA I<MUA<MDA<MUA 0%N/A.1A1--02 1.12E-01 OL-1-36 SP-10 PB10-04245
[SR-, OL-1-36SP-11 PB10-04246 JSR-, 338.8 <MDA <MDA <MDA <MDA 0% N/A 8.85E-021 1.39E-01 357.4 <MDA <MDA <MDA <MDA 0% N/A 8.39E-02 1.32E-01 APPENDIX C FINAL STATUS SURVEY SOIL SAMPLE RESULTS Plum Brook Reactor Facility FSSR, Attachment 7 Appendix C, Rev. 0, Page 13 of 17 CLASS I SOIL SAMPLE RESULTS Cs-137 Co-60 DCGL(1 t 11.4 DCGL 3.7 DCGL" 2' 14.7 DCGL 3.5 Cs-137 Co-60 DCGLT 3 7 11.82 DCGL 3.8 MDA MDA Location Sample Log # Sample # Weight (g) pCi/g 20 pCi/g 2 % Unity Cs:Co pCi/g pCilg OL-1-37 SP-1 PBIO-04248 SR-237-266 358.1 <MDA <MDA <MDA <MDA 0% N/A 1.12E-01 1.23E-01 OL-1-37 SP-2 PB10-04249 SR-237-267 438.5 <MDA <MDA <MDA <MDA 0% N/A 8.37E-02 1.01E-01 OL-1-37 SP-3 PB10-04251 SR-237-269 464.7 <MDA <MDA <MDA <MDA 0% N/A 5.92E-02 9.49E-02 OL-1-37 SP-4 PB10-04252 SR-237-270 436.0 <MDA <MDA <MDA <MDA 0% N/A 7.96E-02 1.01E-01 OL-1-37 SP-5 PB10-04253 SR-237-271 444.2 <MDA <MDA <MDA <MDA 0% N/A 7.33E-02 9.93E-02 OL-1-37 SP-6 PB10-04254 SR-237-272 349.2 <MDA <MDA <MDA <MDA 0% N/A 9.94E-02 1.26E-01 OL-1-37 SP-7 PB10-04255 SR-237-273 309.5 <MDA <MDA <MDA <MDA 0% N/A 1.30E-01 1.43E-01 OL-1-37 SP-8 PB10-04256 SR-237-274 329.0 <MDA <MDA <MDA <MDA 0% N/A 1.00E-01 1.08E-01 OL-1-37 SP-9 PB10-04257 SR-237-275 351.9 <MDA <MDA <MDA <MDA 0% N/A 8.58E-02 1.25E-01 OL-1-37 SP-10 PB10-04258 SR-237-276 363.3 <MDA <MDA <MDA <MDA 0% N/A 8.25E-02 1.30E-01 OL-1-37 SP-11 PB10-04259 SR-237-277 357.5 <MDA <MDA <MDA <MDA 0% N/A 7.70E-02 1.23E-01 OL-1-38SP-1 PB10-04260 SR-237-278 377.1 1.88E-01 8.64E-02 <MDA <MDA 2% N/A _ 1.17E-01 OL-1-38 SP-2 PB10-04262 SR-237-279 445.0 <MDA <MDA <MDA <MDA 0% N/A 6.74E-02 1.06E-01 OL-1-38 SP-3 PBIO-04263 SR-237-280 371.7 <MDA <MDA <MDA <MDA 0% N/A 1.35E-01 1.19E-01 OL-1-38 SP-4 PB10-04264 SR-237-281 378.9 <MDA <MDA <MDA <MDA 0% N/A 7.91 E-02 1.25E-01 O1--1-38 SP-5 PB10-04266 SR-237-283 406.4 <MDA <MDA <MDA <MDA 0% N/A 7.38E-02 1.16E-01 OL-1-38 SP-6 PB10-04267 SR-237-284 454.8 <MDA <MDA <MDA <MDA 0% N/A 6.05E-02 9.70E-02 OL-1-38 SP-7 PB10-04268 SR-237-285 428.9 6.76E-01 1.72E-01 <MDA <MDA 6% N/A 1.10E-01 OL-1-38SP-8 PB10-04269 SR-237-286 315.5 <MDA <MDA <MDA <MDA 0% N/A 8.72E-02 1.40E-01 OL-1-38 SP-9 PB10-04270 SR-237-287 430.2 <MDA <MDA <MDA <MDA 0% N/A 6.97E-02 1.10E-01 OL-1-38 SP-10 PB10-04271 SR-237-288 465.0 2.81E-01 9.53E-02 <MDA <MDA 2% N/A 9.49E-02 OL-1-38 SP-1 1 PB10-04272 SR-237-289 456.3 <MDA <MDA <MDA <MDA 0% N/A 8.82E-02 9.67E-02 OL-1-39 SP-1 PB10-04426 SR-237-290 361.1 2.07E-01 9.26E-02 <MDA <MDA 2% N/A 1.22E-01 OL-1-39 SP-2 PB10-04427 SR-237-291 345.6 <MDA <MDA <MDA <MDA 0% N/A 8.67E-02 1.37E-01 OL-1-39SP-3 PB10-04429 SR-237-293 418.7 <MDA <MDA <MDA <MDA 0% N/A 7.16E-02 1.13E-01 OL-1-39 SP-4 PB10-04430 SR-237-294 382.9 <MDA <MDA <MDA <MDA 0% N/A 7.47E-02 1.19E-01 OL-1-39 SP-5 PB10-04431 SR-237-295 353.7 <MDA <MDA <MDA <MDA 0% N/A 7.78E-02 1.25E-01 OL-1-39 SP-6 PB10-04432 SR-237-296 436.4 <MDA <MDA <MDA <MDA 0% N/A 6.87E-02 1.08E-01 OL-1-39SP-7 PB10-04433 SR-237-297 371.9 2.71E-01 1.07E-01 <MDA <MDA 2% N/A 1.23E-01 OL-1-39 SP-8 PB10-04434 SR-237-298 357.6 <MDA <MDA <MDA <MDA 0% N/A 1.10E-01 1.23E-01 OL-1-39 SP-9 PB10-04435 SR-237-299 351.9 <MDA <MDA <MDA <MDA 0% N/A 1.25E-01 1.34E-01 OL-1-39 SP-10 PB10-04436 SR-237-300 352.0 <MDA <MDA <MDA <MDA 0% N/A 1.92E-01 1.30E-01 OL-1-39 SP-11 PB10-04437 SR-237-301 349.2 1.82E-01 8.83E-02 <MDA <MDA 2% N/A 1.26E-01 APPENDIX C FINAL STATUS SURVEY SOIL SAMPLE RESULTS Plum Brook Reactor Facility FSSR, Attachment 7 Appendix C, Rev. 0, Page 14 of 17 CLASS 1 SOIL SAMPLE RESULTS Cs-1 37 Co-60 DCGL('t 11.4 DCGL 3.7 DCGL(2) 14.7 DCGL 3.5 Cs-137 Co-60 DCGL0 3 7 11.82 DCGL 3.8 MDA MDA Location Sample Lo # Sample # Welht g pCi/g 2 pCIlg 2a % Unity Cs:Co pCilg pCilg OL-1-40 SP-1 PB10-04520 SR-237-302 451.9 <MDA <MDA <MDA <MDA 0% N/A 6.09E-02 9.75E-02 OL-1-40 SP-2 PB10-04523 SR-237-303 344.6 <MDA <MDA <MDA <MDA 0% N/A 6.52E-02 1.03E-01 OL-1-40SP-3 PB10-04524 SR-237-304 377.9 <MDA <MDA <MDA <MDA 0% N/A 7.57E-02 1.21E-01 OL-1-40SP-4 PB10-04525 SR-237-305 358.3 <MDA <MDA <MDA <MDA 0% N/A 7.68E-02 1.23E-01 OL-1-40 SP-5 PB1O-04526 SR-237-306 356.0 <MDA <MDA <MDA <MDA 0% N/A 1.33E-01 1.33E-01 OL-1-40 SP-6 PB10-04527 SR-237-307 384.7 <MDA <MDA <MDA <MDA 0% N/A 1.06E-01 1.19E-01 OL-1-40 SP-7 PB10-04528 SR-237-308 410.4 <MDA <MDA <MDA <MDA 0% N/A 9.64E-02 8.05E-02 OL-1-40 SP-8 PB10-04529 SR-237-309 376.6 <MDA <MDA <MDA <MDA 0% N/A 7.96E-02 1.25E-01 OL-1-40 SP-9 PB10-04530 SR-237-310 382.6 <MDA <MDA <MDA <MDA 0% N/A 7.47E-02 1.19E-01 OL-1-40 SP-10 PB10-04531 SR-237-311 393.3 <MDA <MDA <MDA <MDA 0% N/A 8.28E-02 1.12E-01 OL-1-40 SP-11 PB10-04532 SR-237-312 352.2 <MDA <MDA <MDA <MDA 0% N/A 8.12E-02 1.29E-01 OL-1-41, SP-1 PB10-04650 SR-237-314 401.8 <MDA <MDA <MDA <MDA 0% N/A 7.26E-02 1.10E-01 OL-1-41, SP-2 PB10-04651 SR-237-315 402.5 <MDA <MDA <MDA <MDA 0% N/A 7.45E-02 1.17E-01 OL-1-41, SP-3 PB10-04652 SR-237-316 425.8 <MDA <MDA <MDA <MDA 0% N/A 9.82E-02 1.07E-01 OL-1-41, SPA PB10-04654 SR-237-318 373.2 <MDA <MDA <MDA <MDA 0% N/A 1.13E-01 1.26E-01 OL-1-41, SP-5 PB10-04655 SR-237-319 400.2 <MDA <MDA <MDA <MDA 0% N/A 7.97E-02 1.14E-01 OL-1-41, SP-6 PB10-04656 SR-237-320 414.8 <MDA <MDA <MDA <MDA 0% N/A 8.52E-02 1.06E-01 OL-1-41, SP-7 PB10-04657 SR-237-321 324.1 <MDA <MDA <MDA <MDA 0% N/A 9.25E-02 1.46E-01 OL-1-41, SP-8 PB10-04658 SR-237-322 403.6 <MDA <MDA <MDA <MDA 0% N/A 8.62E-02 1.13E-01 OL-1-41, SP-9 PB10-04659 SR-237-323 401.7 <MDA <MDA <MDA <MDA 0% N/A 1.26E-01 1.10E-01 OL-1-41, SP-10 PB10-04660 SR-237-324 375.8 <MDA. <MDA <MDA <MDA 0% N/A 1.02E-01 1.26E-01 OL-1-41, SP-11 PB10-04662 SR-237-325 411.5 <MDA <MDA <MDA <MDA 0% N/A 6.95E-02 1.11E-01 OL-1-42, SP-1 PB11-00002 SR-244-13 387.9 <MDA <MDA <MDA <MDA 0% N/A 9.11E-02 1.14E-01 OL-1-42, SP-2 PB11-00004 SR-244-15 423.6 <MDA <MDA <MDA <MDA 0% N/A 9.26E-02 1.04E-01 OL-1 42, SP-3 PB11-00005 SR-244-16 422.8 <MDA <MDA <MDA <MDA 0% N/A 7.09E-02 1.12E-01 OL-1-42, SPA PB11-00006 SR-244-17 434.7 <MDA <MDA <MDA <MDA 0% N/A 6.33E-02 1.01 E-01 OL-1-42, SP-5 PB11-00007 SR-244-18 340.0 <MDA <MDA <MDA <MDA 0% N/A 8.81 E-02 1.39E-01 OL-1-42, SP-6 PB11-00008 SR-244-19 422.0 <MDA <MDA <MDA <MDA 0% N/A 6.52E-02 1.04E-01 OL-1-42, SP-7 PB11-00009 SR-244-20 444.6 <MDA <MDA <MDA <MDA 0% N/A 6.74E-02 1.06E-01 OL-1-42, SP-8 PB11-00010 SR-244-21 393.2 <MDA <MDA <MDA <MDA 0% N/A 7.OOE-02 1.12E-01 OL-1-42, SP-9 PB11-00011 SR-244-22 380.3 <MDA <MDA <MDA <MDA 0% N/A 1.03E-01 1.24E-01 OL-1-42, SP-10 PB11-00012 SR-244-23 424.3 <MDA <MDA <MDA <MDA 0% N/A 8.33E-02 1.04E-01 OL-1-42, SP-11 PB11-00013 SR-244-24 419.2 <MDA <MDA <MDA <MDA 0% N/A 1.05E-01 1.13E-01 APPENDIX C FINAL STATUS SURVEY SOIL SAMPLE RESULTS Plum Brook Reactor Facility FSSR, Attachment 7 Appendix C, Rev. 0, Page 15 of 17 CLASS 1 SOIL SAMPLE RESULTS Cs-1 37 Co-60 DCGL___ 11.4 DCGL 3.7 DCGL(2) 14.7 DCGL 3.5 Cs-137 Co-60 DCGL T 3 T 11.82 DCGL 3.8 MDA MDA Location Sample Log # Sample # Weight L pCi/ý pCig 2a % Unity Cs:Co pCIIg pCi/g OL-1-43, SP-1 PB11-00071 SR-237-326 382.7 <MDA <MDA <MDA <MDA 0% N/A 8.74E-02 1.15E-01 OL-1-43, SP-2 PB11-00072 SR-237-327 365.3 <MDA <MDA <MDA <MDA 0% N/A 1.05E-01 1.29E-01 OL-1-43, SP-3 PB11-00073 SR-237-328 380.3 <MDA <MDA <MDA <MDA 0% N/A 7.23E-02 1.16E-01 OL-1-43, SP-4 PB11-00075 SR-237-330 392.2 <MDA <MDA <MDA <MDA 0% N/A 7.01 E-02 1.12E-01 OL-1-43, SP-5 PB11-00076 SR-237-331 423.9 <MDA <MDA <MDA <MDA 0% N/A 1.30E-01 1.11E-01 OL-1-43, SP-6 PB11-00077 SR-237-332 402.1 <MDA <MDA <MDA <MDA 0% N/A 6.84E-02 1.10E-01 OL-1-43, SP-7 PB11-00078 SR-237-333 439.0 <MDA <MDA <MDA <MDA 0% N/A 6.83E-02 1.08E-01 OL-1-43, SP-8 PB11-00079 SR-237-334 436.7 <MDA <MDA <MDA <MDA 0% N/A 6.55E-02 1.04E-01 OL-1 -43, SP-9 PB11-00080 SR-237-335 454.7 <MDA <MDA <MDA <MDA 0% N/A 9.68E-02 9.69E-02 OL-1-43, SP-10 PB11-00082 SR-237-336 438.2 3.92E-01 1.03E-01 <MDA <MDA 3% N/A 5.39E-02 OL-1-43, SP-11 PB11-00083 SR-237-337 386.8 <MDA <MDA <MDA <MDA 0% N/A 7.24E-02 1.09E-01 OL-1-44, SP-1 PB11-00084 SR-237-338 389.9 <MDA <MDA <MDA <MDA 0% N/A 7.44E-02 1.29E-01 OL-1-44, SP-2 PB11-00085 SR-237-339 423.9 <MDA <MDA <MDA <MDA 0% N/A 7.07E-02 1.11E-01 OL-1-44, SP-3 PB11-00087 SR-237-341 428.3 <MDA <MDA <MDA <MDA 0% N/A 6.57E-02 1.17E-01 OL-1-44, SP-4 P811-00088 SR-237-342 457.7 <MDA <MDA <MDA <MDA 0% N/A 8.69E-02 1.03E-01 OL-1-44, SP-5 PB11-00089 SR-237-343 415.7 1.52E-01 6.94E-02 <MDA <MDA 1% N/A 4.70E-02 OL-1-44, SP-6 PB11-00090 SR-237-344 437.2 <MDA <MDA <MDA <MDA 0% N/A 1.13E-01 1.15E-01 OL-1-44, SP-7 PB11-00091 SR-237-345 448.6 <MDA <MDA <MDA <MDA 0% N/A 6.68E-02 1.05E-01 OL-1 -44, SP-8 PB1 1-00092 SR-237-346 427.9 <MDA <MDA <MDA <MDA 0% N/A 7.09E-02 1.07E-01 OL-1-44, SP-9 PB11-00093 SR-237-347 383.7 8.16E-01 1.88E-01 <MDA <MDA 7% N/A 1.50E-01 OL-1-44, SP-10 PB11-00094 SR-237-348 451.8 <MDA <MDA <MDA <MDA 0% N/A 9.70E-02 1.04E-01 OL-1-44, SP-11 PB11-00095 SR-237-349 433.7 <MDA <MDA <MDA <MDA 0% N/A 9.15E-02 1.05E-01 OL-1-45, SP-1 PB11-00106 SR-244-25 408.0 <MDA <MDA <MDA <MDA 0% N/A 8.95E-02 1.08E-01 OL-1-45, SP-2 PB11-00107 SR-244-26 431.2 <MDA <MDA <MDA <MDA 0% N/A 1.02E-01 1.17E-01 OL-1-45, SP-3 PB11-00108 SR-244-27 377.3 3.95E-01 1.29E-01 <MDA <MDA 3% N/A 1.33E-01 OL-1-45, SP-4 PB11-00109 SR-244-28 374.7 <MDA <MDA <MDA <MDA 0% N/A 9.08E-02 8.OOE-02 OL-1-45, SP-5 PB11-00110 SR-244-29 400.4 2.03E-01 6.11E-02 <MDA <MDA 1% N/A 7.46E-02 OL-1-45, SP-6 PB11-00111 SR-244-30 403.7 <MDA <MDA <MDA <MDA 0% N/A 6.97E-02 1.25E-01 OL-1-45, SP-7 PB11-00112 SR-244-31 411.7 <MDA <MDA <MDA <MDA 0% N/A 1.07E-01 1.22E-01 OL-1-45, SP-8 PB11-00113 SR-244-32 415.5 <MDA <MDA <MDA <MDA 0% N/A 5.31E-02 6.05E-02 OL-1-45, SP-9 P81-001-14 SR-244-33 392.6 <MDA <MDA <MDA <MDA 0% N/A 7.17E-02 1.28E-01 OL-1-45, SP-10 PB1 -00115 SR-244-34 433.9 <MDA <MDA <MDA <MDA 0% N/A 1.27E-01 1.16E-01 OL-1-45, SP-11 PB11-00117 SR-244-36 393.1 <MDA <MDA <MDA <MDA 0% N/A 9.94E-02 1.28E-01 Total Number 431 46 46 1 1 431 N/A 385 430 Maximum Value 507.9 8.80E-01 2.22E-01 1.OOE+00 1.76E-01 31% N/A 1.92E-01 1.50E-01 Average Value 395.8 2.74E-01 1.01E-01 1.00E+00, 176E-01 0% N/A 7.84E-02 1.12E-01 Standard Deviation 38.71 1.68E-01 3.52E-02 N/A N/A 2% N/A 2.OOE-02 1.99E-02 Notes: 1. Denotes DCGLs used for Survey Unit OL-1-26, per Survey Design #46 2. Denotes DCGLs used for Survey Units OL-1 -10, OL-1-42, and OL-1-45, per Survey Design #39 3. Denotes DCGLs used for all remaining Suvey Units within SDPTSSE, per Survey Designs #30, 33, 37, and 44 APPENDIX C FINAL STATUS SURVEY SOIL SAMPLE QC COMPARISON Plum Brook Reactor Facility FSSR, Attachment 7 Appendix C, Rev. 0, Page 16 of 17 QC SOIL SAMPLE
SUMMARY
DATA Weight Location HPGe Log # Sample # (g) Cs-1 37 Co-60 % Unity Cs:Co Cs-137 Co-6O MDA MDA pCl/g 2a pCil/g 2u pCi/g pCi/g OL-1-35 SP-11 QC PB10-04192 SR-237-253 381.8 <MDA <MDA <MDA <MDA 0% N/A 7.49E-02 1.19E-01 OL-1-36 SP-11 QC PB10-04247 SR-237-265 378.1 <MDA <MDA <MDA <MDA 0% N/A 7.93E-02 1.25E-01 OL-1-37 SP-2 QC PB10-04250 SR-237-268 422.2 <MDA <MDA <MDA <MDA 0% N/A 1.21E-01 1.04E-01 OL-1-38 SP-4 QC PB10-04265 SR-237-282 383.6 <MDA <MDA <MDA <MDA 0% N/A 7.17E-02 1.15E-01 OL-1-33 SP-11 QC PB10-04205 SR-237-241 424.5 1.67E-01 7.68E-02 <MDA <MDA 1% N/A 1.04E-01 OL-1-34 SP-2 QC PB10-04170 SR-237-220 406.4 <MDA <MDA <MDA <MDA 0% N/A 6.77E-02 1.08E-01 OL-1-26 SP-2 QC PB10-04148 SR-279-3 429.4 <MDA <MDA <MDA <MDA 0% N/A 6.41E-02 1.03E-01 OL-1-19 SP-2 QC PB10-03108 SR-237-124 443.6 <MDA <MDA <MDA <MDA 0% N/A 6.76E-02 1.06E-01 OL-1-25 SP-4 QC PB10-03805 SR-237-210 360.5 <MDA <MDA <MDA <MDA 0% N/A 7.93E-02 1.26E-01 OL-1-22 SP4 QC PB10-03714 SR-237-198 431 <MDA <MDA <MDA <MDA 0% N/A 6.63E-02 1.06E-01 OL-1-21 SP-2 QC PB10-03513 SR-237-160 423.8 <MDA <MDA <MDA <MDA 0% N/A 6.75E-02 1.08E-01 OL-1-24 SP-2 0C PB10-03677 SR-237-184 387.4 <MDA <MDA <MDA <MDA 0% N/A 7.74E-02 1.22E-01 OL-1-7 SP-11 QC PB10-01515 SR-237-12 312.4 <MDA <MDA <MDA <MDA 0% N/A 8.81E-02 1.41E-01 OL-1-8 SP-1 QC PB10-01520 SR-237-14 433.9 <MDA <MDA <MDA <MDA 0% N/A 6.54E-02 1.04E-01 OL-1-9 SP-2 QC PB10-01578 SR-237-27 356.8 <MDA <MDA <MDA <MDA 0% N/A 7.95E-02 1.26E-01 OL-1-12 SP-3 QC PB10-01981 SR-237-52 448.6 <MDA <MDA <MDA <MDA 0% N/A 7.49E-02 1.OOE-01 OL-1-10SP-11 QC PB10-01881 SR-244 396.7 <MDA <MDA <MDA <MDA 0% N/A 7.55E-02 1.19E-01 OL-1-15 SP-1 QC PB10-02127 SR-242-4 375.7 <MDA <MDA <MDA <MDA 0% N/A 7.97E-02 1.25E-01 OL-1-13 SP-6 QC PB10-02058 SR-237-68 387.7 <MDA <MDA <MDA <MDA 0% N/A 7.10E-02 1.14E-01 OL-1-15 SP-10 QC PB10-02195 SR-237-96 366.6 <MDA <MDA <MDA <MDA 0% N/A 8.24E-02 1.20E-01 OL-1-17 SP-1 QC PB10-02827 SR-237-111 397 <MDA <MDA <MDA <MDA 0% N/A 7.55E-02 1.19E-01 OL-1-20 SP-2 QC PB10-03262 SR-237-136 395.1 <MDA <MDA <MDA <MDA 0% N/A 7.24E-02 1.15E-01 OL-1-18 SP-2 QC PB10-03303 SR-237-148 397.2 <MDA <MDA <MDA <MDA 0% N/A 7.54E-02 1.19E-01 OL-1-39 SP-2 QC PB10-04428 SR-237-292 368.1 <MDA <MDA <MDA <MDA 0% N/A 7.48E-02 1.29E-01 OL-1-40 SP-11 QC PB10-04533 SR-237-313 404.9 <MDA <MDA <MDA <MDA 0% N/A 6.79E-02 1.09E-01 OL-1-41, SP-3 QC PB10-04653 SR-237-317 403.8 <MDA <MDA <MDA <MDA 0% N/A 6.81E-02 1.09E-01 OL-1-43, SP-3 QC PB11-00074 SR-237-329 389.0 <MDA <MDA <MDA <MDA 0% N/A 9.89E-02 1.21E-01 OL-1-44, SP-2 QC PB11-00086 SR-237-340 447.9 <MDA <MDA <MDA <MDA 0% N/A 6.38E-02 1.02E-01 OL-1-11 SP-11 QC PB10-01936 SR-237-48 394.7 <MDA <MDA <MDA <MDA 0% N/A 9.30E-02 1.12E-01 j)L-1-116 SP-11 Q0 PB10-02383 SR-237-109 399.6 <MDA <MDA <MDA <MDA 0% N/A 1.12E-01 1.18E-01 OL-1-14, SP-2 QC PB10-02153 SR-237-76 427.0 <MDA <MDA <MDA <MDA 0% N/A 1.40E-01 1.08E-01 ,5L-1-23, SP-10 Q PB10-03619 SR-237-180 437.5 <MDA <MDA <MDA <MDA 0% N/A 6.86E-02 1.08E-01 OL-1-42, SP-1 QC PB11-00003 SR-244-14 341.8 <MDA <MDA <MDA <MDA 0% N/A 8.77E-02 1.38E-01)L-1-45, SP-10 QC PB11-00116 SR-244-35 423.9 <MDA <MDA <MDA <MDA 0% N/A 1.35E-01 1.19E-01 0L-1-2, SP-11 QC PB09-01128 SR-165-12 430.0 1.11E-01 5.13E-02 <MDA <MDA 1% N/A 5.06E-02 OL-1-3, SP-11 QC PB09-02127 SR-176-24 412.4 <MDA <MDA <MDA <MDA 0% N/A 7.27E-02 1.14E-01 0L-1-4 SP-2, QC PB09-01378 SR-169-15 394.5 <MDA <MDA <MDA <MDA 0% N/A 7.61E-02 1.19E-01 OL-1-1, SP-11, 0 P809-01010 SR-164-12 494.5 <MDA <MDA <MDA <MDA 0% N/A 4.71E-02 4.40E-02 OL-1-5, SP-11,: PB09-02069 SR-176-12 401.8 <MDA <MDA <MDA <MDA 0% 'N/A 7.84E-02 1.17E-01 OL-1-6, SP-11, QC PB09-04933 SR-204-12 384 <MDA <MDA <MDA <MDA 0% N/A 7.81E-02 1.22E-01 Total Number 40_1 2 [ 2 0 1 0 1 40 0 38 40 Maximum Value [494.5 1.67E01 768E-02 1<MDA J <MDA 1% N/A 1 4E-01 1.4E-01 Average Value 4024 1 39E-01 M 641E-02 <MDA <MDA 0% N/A 8E-E-02 1.1E-01 Standard Deviation 33.14 13.96E-02 1.80E-021 N/A I N/A 1 0% N/A I 1.90E-02 1.78E-02 APPENDIX C FINAL STATUS SURVEY SOIL SAMPLE QC COMPARISON Plum Brook Reactor Facility FSSR, Attachment 7 Appendix C, Rev. 0, Page 17 of 17 I I~,,I a ...IO , Ir Ioa.t w omp. "sonJdl~l Ir ec: o Otll.JI I .I /Original Replicate Original 2 Location HPGe Log # Sample # Result Result Sigma H-lnt, Resolution Ratio Pass OL-1-35 SP-11 QC PB10-04192 SR-237-253
<MDA <MDA YES OL-1-36 SP-11 QC PB10-04247 SR-237-265
<MDA <MDA YES OL-1-37 SP-2 QC PB10-04250 SR-237-268
<MDA <MDA YES OL-1-38 SP-4 QC PB10-04265 SR-237-282
<MDA <MDA YES OL-1 -33 SP-1 1 QC PB10-04205 SR-237-241 1.67E-01 7.74E-02 7.68E-02 4 0.5 YES OL-1-34 SP-2 QC PB10-04170 SR-237-220
<MDA <MDA YES OL-1-26 SP-2 QC PB10-04148 SR-279-3 <MDA <MDA YES OL-1-19 SP-2 OC PB10-03108 SR-237-124
<MDA <MDA YES OL-1-25 SP-4 QC PB10-03805 SR-237-210
<MDA <MDA YES OL-1-22 SP-4 QC PB10-03714 SR-237-198
<MDA <MDA YES OL-1-21 SP-2 QC PB10-03513 SR-237-160
<MDA <MDA YES OL-1-24 SP-2 QC PB10-03677 SR-237-184
<MDA. <MDA YES OL-1-7SP-11 OC PB10-01515 SR-237-12
<MDA <MDA YES OL-1-8 SP-1 QC PB10-01520 SR-237-14
<MDA <MDA YES OL-1-9 SP-2 QC PB10-01578 SR-237-27<MDA <MDA YES OL-1-12 SP-3 QC PB10-01981 SR-237-52
<MDA <MDA YES Acceptance Criteria OL-1-10 SP-11 QC PB10-01881 SR-244 <MDA <MDA YES ResolunYES Ratio OL-1-15 SP-1 QC PB10-02127 SR-242-4 <MDA <MDA YES I OL-1 -13 SP-6 QC PB10-02058 SR-237-68
<MDA <MDA YES < 4 0.4-2.5 OL-1-15 SP-10 QC PB10-02195 SR-237-96
<MDA <MDA YES 4-7 0.5-2.0 OL-1-17 SP-1 QC PB10-02827 SR-237-111
<MDA <MDA YES 8-15 0.6-1.66 OL-1-20 SP-2 QC P810-03262 SR-237-136
<MDA <MDA YES 16-50 0.75-1.33 OL-1-18 SP-2 QC PB10-03303 SR-237-148 39<MDA <MDA YES St -200 0.8-1.25 OL-1-39 SP-2 QC PB10-04428 SR-237-292
<MDA <MDA YES > 200 0.85 -1.18 OL-1-40 SP-11 QC PB100453 SR-3731 <MDA <M 1 4 YES -111 If both results are< MDA, they are in agreement.
OL-1-41. SP-30 0 P1IO-04653 SR-237-317
<MDA<MDA YES OL-1-43, SP-3 QC PB11-00074 SR-237-329
<MDA <MDA YES OL-1-44, SP-2 QC PB11-00086 SR-237-340
<MDA <MDA YES OL-1-11 SP-11 QC PB10-01936 SR-237-48
<MDA <MDA YES OL-1-16, SP-1 1 QC PB10-02383 SR-237-109
<MDA <MDA YES OL-1-14, SP-2 QC PB10-02153 SR-237-76
<MDA <MDA YES OL-1-23, SP-10 QC PB10-03619 SR-237-180
<MDA <MDA YES OL-1-42, SP-1 QC PB11-00003 SR-244-14
<MDA <MDA YES OL-1-45, SP-10 Q0 PB11-00116 SR-244-35
<MDA <MDA I I YES OL-1-2, SP-11 QC PB09-01128 SR-165-12 1.11E-01 5.10E-02 5.13E-02 4 0.5 YES OL-1-3, SP-11 QC PB09-02127 SR-176-24
<MDA <MDA YES OL-1-4 SP-2, QC PB09-01378 SR-169-15
<MDA <MDA YES OL-1-1, SP-11, QC PB09-01010 SR-164-12
<MDA <MDA YES OL-1-5, SP-11, QC PB09-02069 SR-176-12
<MDA <MDA YES OL-1 -6, SP-1 1, QC PB09-04933 SR-204-12
<MDA <MDA YES Total Number 2 2 2 2 2 N/A Total Number "YES" T -40 Total Number "NO" 0 2. When comparing a positive result to a <MDA result, assume that the sample result is positive at the MDA and use the MDA value to determine the ratio.