snap environmental test facility - building 4024 · the sub grade test cell complex (sgtcc)...

SAMPLE AND ANALYSIS PLAN

for the

RADIOLOGICAL CHARACTERIZATION ANDCONFIRMATORY SURVEY OF TH

SNAP ENVIRONMENTAL TEST FACILITY - BUILDING 4024

MARCH 2007

REVISION 0

'3r=as te`.n? at1E)rt%F S 4an et

Peter ti!o ttley?AR VA Radiation Safety Officer

Approved bDonald Mb c ee:

Date

Date

Accepted 3V . r te .. €~ W k _ _f

; , ..`- :tats' ~ .. ., r

Boeing t'on span Manager• of Health . Safety and 1Radiad"'m Services

Prepared By :A EVA NPInc.

Federal D&D Services7207 IBM Drive

Charlotte, NC 28262

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SETF Radiological Characterization and Sample And Analysis Plan

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PREFAC E

The Boeing Company (Boeing) awarded AREVA NP Inc ., (AREVA) an Undefinitized Firm Fixed-PriceLetter Contract No . 116285 (contract) January 22, 2007 . The Scope of Work for the contract is to plan

and perform the demolition and removal of the existing SNAP Environmental Test Facility, (SETF), also

known as Building 4024 . The facility was used for the testing of small nuclear reactors and inducedradioactivity (i .e., activation products) remains within the building structure . The project is locatedwithin Area IV of the Santa Susana Field Laboratory, eastern Ventura County, California .

The project execution requirements involve facility demolition including the complete removal of thesubsurface concrete and associated utilities . The desired end state for the project consists of .

1 . Verification the site meets the established site release criteria using MARSSIM-compliantsurvey methods and techniques of the remaining soil and/or bedrock, an d

2. The excavation has been backfilled in compliance with the applicable requirements and the sitere-graded to natural contours . Note that the term "site" as used here refers to the subsurfaceexcavation and the backfilled locations .

AREVA has developed this Sample and Analysis Plan (SAP) to guide the performance of radiologicalcharacterization and con firmatory surveys prior to performance of decontamination activities . This SAPwas also developed to guide the performance of remedial action suppo rt surveys during performance ofdecontamination activities within the SETF test cells . Objectives of characterization and confirmatorysurveys include : confirming current radiological conditions at SETF clean areas as well as within theactivated test cells; and performance of a background study to assist with subsequent final status surveydata evaluations . Survey results will be used to assist with finalizing decontamination planning,environmental protection and worker health and safety evaluations, and confirm waste managementassumptions . Results of the survey and background study will also assist with remedial action suppo rtsurvey data evaluations once activated po rt ions of the test cells are removed . The remedial actionsupport survey will show that decontamination effo rts were successful and that remaining po rtions of thetest cells can be demo lished with other SETF survey units and disposed of as decommissioning materials(DM) .

A Final Status Survey Plan will be developed separately to address the sampling and analysis

requirements of a MARSSIM designed final status survey (FSS) that demonstrates successful attainmentof the end state .

SETF_SAP March 30, 2007, RevO final .docMarch 2007

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TABLE OF CONTENTS

1 . SITE INFORMATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1

1 .1 Background . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1

1 .2 SETF Facility Description . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 .2 .1 High Bay Area . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 .2 .2 General Support and Operating Area . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 51 .2 .3 Mechanical/Electrical Support Area . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 51 .2 .4 Yard Area . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 51 .2 .5 Site Lithology . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5

1 .3 Identity of Potential Contaminants . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 61 .4 Regulatory Authority and Guidance Documents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6

1 .4 .1 Facility Decommissioning . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 61 .4 .2 Decommissioned Materials . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7

2. SURVEY OVERVIEW . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 92 .1 Survey Objective . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 92 .2 Data Quality Objectives . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 92 .3 Derived Concentration Guideline Levels for Surveys . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10

2 .3 .1 DCGL for Surface Contamination . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 102 .3 .2 Gamma Exposure Rate Measurements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 122 .3 .3 DCGLs for Soil or Bulk Decommissioned Materials . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 2

2 .4 Organization and Responsibilities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 133 . SURVEY INSTRUMENTATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14

3 .1 Instrument Calibration . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 153 .2 Sources . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 163 .3 Static Measurement Minimum Detectable Concentration . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 163 .4 Scan Survey Minimum Detectable Concentration . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 7

4. SURVEY/SAMPLING DESIGN . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 184 .1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 184 .2 Survey Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 9

4 .2 .1 Number of Measurements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 204 .2 .2 Visual Sample Plan . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 214 .2 .3 Survey Package Development . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 214 .2 .4 Background Study. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 224 .2 .5 Confirmatory Survey Measurements and Samples . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 234 .2 .6 SGTCC Confirmatory Survey. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 254 .2 .7 Remedial Action Support Survey Measurements and Samples . . . . . . . . . . . . . . . . . . . . . . . . . . . . 27

4 .2 .8 Data Evaluation and Review . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 294 .2 .9 Elevated Measurement Comparison . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 314 .2 .10 Spatial Analysis and Decision Assistance . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 32

4 .3 Survey Records . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 325 . QUALITY ASSURANCE AND QUALITY CONTROL . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34

5 .1 General Provisions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 345 .1 .1 Selection of Personnel . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 345 .1 .2 Written Procedures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 345 .1 .3 Instrumentation Selection , Calibration, and Operation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 34


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5 .1 .4 Survey Documentation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 345 .1 .5 Chain of Custody . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 355 .1 .6 Independent Review of Survey Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 35

5 .2 Training . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 355 .3 Sample Analysis . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 35

6. SURVEY REPORT . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 367. REFERENCES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 378. ATTACHMENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 399. APPENDICES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 39

LIST OF TABLE S

Table 2-1, Acceptable Surface Contamination Valuesi . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11Table 2-2, Acceptable Soil and Bulk DM DCGLs and MDCs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12

Table 3-1, Portable Survey Instrumentation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15

Table 4-1, Background Reference Study . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 23

Table 4-2, Confirmatory Survey . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 24Table 4-3, SGTCC Confirmatory Survey . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 26

Table 4-4, Final Remedial Action Survey . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 8

LIST OF FIGURES

Figure 1-1, Location Map of SETF, Building 4024 at ETEC . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2Figure 1-2, SETF Site Layout . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2Figure 1-3, SETF High Bay . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3Figure 1-4, Sub Grade Test Cell Complex . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4


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LIST OF ACRONYMS AND ABBREVIATION S

ALARAAMCGCERCLACFRCOCDCGLDHS-RHBDMDOEDQOdpm/100cm2EPAICRPLBGRMDCmrem/yrNCRPNRCtCiOSHApCi/gPMPPEQAQCRCARCRARWPSETFSMLSNAPTEDETLDTSCAWBS

As Low as Reasonably AchievableAverage Member of the Critical GroupComprehensive Environmental Response, Compensation, and Liability ActCode of Federal Regulation sContaminant of ConcernDerived Concentration Guideline LevelCalifornia State Department of Health Services, Radiologic Health BranchDecommissioned Material sU.S . Department of EnergyData Quality Objectivedecays per minute per 100 square centimetersU. S. Environmental Protection AgencyInternational Council on Radiological ProtectionLower Boundary of the Gray Regio nminimum detectable concentrationmillirem per yearNational Council on Radiation ProtectionU. S. Nuclear Regulatory CommissionmicrocuriesOccupational Safety and Health Administrationpicocuries per gramproject managerpersonal protective equipmentquality assurancequality controlradiation control are aResource Conservation and Recovery Actradiation work permitSNAP Environmental Test Facility, Building 4024Sample/Measurement LocationSystem for Nuclear Auxiliary Powertotal effective dose equivalentthermo luminescent dosimeterToxic Substances Control ActWork Breakdown Structure


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1 . SITE INFORMATION

1 .1 Background

Boeing West Hills and its predecessor organizations performed nuclear research and energydevelopment activities at its Santa Susana Field Laboratory (SSFL) from about 1954 until the

end of 1998 . Activities sponsored by the Department of Energy (DOE) and its predecessoragencies , included engineering , research , development , and manufacturing operations .

The nuclear and energy development facilities, including both the Boeing West Hills and the

Energy Technology Engineering Center (ETEC) operations, were located in Area IV of the

SSFL site, which is situated in the Simi Hills of southeastern Ventura County, California, refer

to Figure 1-1, Location Map of SETF, Building 4024 at ETEC . The nuclear work concluded in

the late 1980s . The D&D of all remaining SSFL facilities associated with DOE -sponsoredactivities is currently being performed under the ETEC Closure contract with the DOE . The

SETF is owned by the U .S . DOE .

The SETF was designed and erected for testing SNAP reactors in a simulated operationalenvironment . The facility was erected in 1960 and was then enlarged in 1962 to provide a second

control room and increased operating equipment area. Four unshielded SNAP-type reactors weretested at the SETF . Following the end of testing, the reactor systems and their associatedradioactive test equipment were removed . Additional decontamination and dismantlement

operations were performed in 1978 and again in 2005 .

1 .2 SETF Facility Descriptio n

As constructed, the SETF consisted of three basic areas : the high bay, general support and

mechanical/electrical support areas . A paved yard surrounded the main building where otherabove grade support structures and below grade components such as radioactive solid, liquid,and gas storage tanks were once buried as shown in the SETF site plan (Figure 1-2) .

1 .2.1 High Bay Area

The high bay area is the section of the building built above the subsurface cell complex and

operating gallery . The high bay area is enclosed by a structural steel, mill-framed building ; see

Figure 1-3, SETF High Bay . The panels forming the siding have asbestos containing material

(ACM) in the sealant used on the panels and must be handled as ACM . Removal of ACMincluding the performance of a survey to determine the presence of asbestos containing material

is the responsibility of the contractor. To handle the cell roof plugs in the high bay floor, a still

operational 20-ton gantry crane moves on rails that extend through a high bay door to

approximately 40 feet east of the structure where outside storage cavities were constructed andstill remain .


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SETF Radiological Characterization and

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Sample And Analysis PlanPage - 2 -

Figure 1-1, Location Map of SETF, Building 4024 at ETE C

Figure 1-2, SETF Site Layou t

SETFSAP March 30, 2007, RevO final .docMarch 2007

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SETF Radiological Characterization and Sample And Analysis Pla n


Figure 1-3, SETF High Bay

The sub grade test cell complex (SGTCC) consists of the three parallel cells (two power testcells and the center transfer cell), a partial rear corridor which interconnects the cells, and the

operating gallery, see Figure 1-4, Sub Grade Test Cell Complex . To insure gas tightness, the

cells were completely lined on the inside with 3/16 inch-thick aluminum plate . This plate was

seal welded to T-bar anchors in the structural concrete . The top of the cells' 8 foot thick roof isat ground level and serves as the high bay floor. The subsurface construction of the facility

allowed advantage to be taken of the natural shielding for neutron and gamma radiation

attenuation provided by the earth and rock on four sides of the complex . The below grade

structure side and rear walls were back -filled with earthen fill materials . The floor was cast onthe bedrock. The side wall structural concrete is nominally 3 feet thick, the rear wall concrete is

2 feet thick and the floor concrete varies from 6.5 to 8 feet thick as the rock elevation varies .

Concrete walls which separate the three cells are 4-1/2 feet thick; the transfer cell's front wall is

4-1/2 feet thick ; and the front walls of the two test cells are 9 feet thick . A 3-feet-thick concretepartial wall was built across the rear of each test cell , creating a common corridor . Nine floorstorage vaults were constructed in the floor of the corridor, three at the rear of each cell .

The 4 by 7 feet access doors between the operating gallery and each cell were stepped plugs ofthe same thickness as the shield walls which they penetrate and provided for personnel orequipment access to the cells . Tracks were provided in the floor, for the self-powered plugs toroll on . Two of these doors remain in the lower operating gallery area of the facility . The roofof each cell is penetrated by a 9 feet diameter circular access port . The plugs filling this port ar e

SETFSAP March 30, 2007, RevO final .docMarch 2007

HDMSE00576740



stepped for shielding purposes . To not exceed the capacity of the 20-ton gantry crane, the plugs

are constructed in three layers to make up a total thickness of 8 feet . The center of the roof

access plugs are penetrated by a 24 inch minimum diameter port with a single shield plug in

each .

Xlk

Figure 1-4, Sub Grade Test Cell Complex

The roof, front face and walls separating cells from one another are all pierced by 8 inch and 10inch minimum diameter stepped ports . Two other types of cell penetrations were provided;these are electrical and instrumentation conduits and "through tubes ." The aluminum conduitsrun from the cell liner out through the walls or roof. Aluminum bent-design through-tubes oftwo sizes, 1-1/2 and 2 inch diameter penetrated the various walls .

The operating gallery is at two levels . The lower level is at the same elevation as the cell floors28 feet below grade. The upper level is formed by a bolted steel floor 14 feet above the lowerfloor. The west end is partitioned off by a concrete wall that extends from the lower floor to thehigh bay floor . Personnel access to the gallery floors and equipment rooms is provided by asingle stairway. Material and equipment was moved to either floor of the operating gallery by a5-ton bridge crane that is no longer operationa l


HDMSE00576741



1 .2.2 General Support and Operating Are a

Immediately north of the high bay area was the general support and operating area which

contained the reactor control rooms, change rooms, rest rooms, boiler and compressor room anda shop area . The above grade structures have been demolished and only the slab remains in this

area. The removal of the general support and operating area concrete slab is within this project

scope and will be managed as a Decommissioned Material .

1 .2.3 Mechanical/Electrical Support Are a

South of and adjacent to the high bay area was the mechanical/electrical support area containing

two rooms, the filter and radioactive gas compressor room and the electrical equipment room .The above grade building structure and all equipment was removed and only the concrete slab

remains . The removal of the mechanical/electrical support area concrete slab is within this

project scope and is expected to be managed as a Decommissioned Material .

1 .2.4 Yard Area

The yard is paved with asphalt which currently provides vehicle access to all sides of the

building. Below ground radioactive waste storage facilities were once located in the area . Tanksremoved during a 1977-78 D&D campaign were : three 6 feet diameter by 40ft long radioactive

gas holdup tanks; and two buried 500 gallon liquid radioactive waste holdup tanks located east

of the gas holdup . The D&D effort was documented in written plans and photos taken duringthe removal of these components . However, eight 3 feet diameter by 4 feet deep solidradioactive waste storage vaults, each with a 4 .5 feet thick shield block cover were provided in

the crane runway area and have not been removed . The storage vaults, vault covers, crane and

crane runway are within this project scope .

Facility water was supplied by a 12 inch diameter water line crossing the southeast corner of thesite . A looped system around the SETF was provided for fire protection, industrial demands,and domestic requirements . A sanitary sewer system collected non-radioactive sewage wastesfrom the building lavatories and carried it to the central sewer manhole in the northwest cornerof the site . All utilities are to be disconnected and blanked off by Boeing prior to start ofdemolition . Removal of the disconnected subsurface utilities within the established projectboundary is within this project scope . Asphalt, concrete foundations, etc . within the area is to besurveyed, removed and managed as a Decommissioned Material .

1 .2.5 Site Lithology

A layer of fill, weathered bedrock or native soil covers the area to variable depths . The site isunderlain by the upper cretaceous, arkosic-sandstone Chatsworth formation . Shallowgroundwater may be present at the site . The shallow groundwater has been sampled andanalyzed by Boeing and found to be free of contamination .


HDMSE00576742



1 .3 Identity of Potential Contaminant s

Radioactivity induced by testing SNAP reactors in the sub grade test cell complex was detected

as documented in Reference 7 .5, Team Product Document No : RS-00025, Building 4024Concrete Sampling, performed under the Closure of ETEC (R21-RS) Program (RS-00025

repo rt) . The RS -00025 repo rt provides the results for concrete sampling in the SETF , Building4024 conducted in 2003 . The activity of 1 inch depth cores ranged from no detectable activity

to 105 pCi/g of Europium-152 (Eu-152) and 9.4 pCi/g of Cobalt-60 (Co-60), the primarycontaminants of concern (COC) .

These results from the RS-00025 survey and were used to predict which concrete needs to be

removed with radiological controls and managed as radioactive waste and which can beremoved as decommissioning materials without radiological controls and shipped to a Class 1landfill . According to the Reference 7 .6, Historical Site Assessment of Area IV Santa Susana

Field Laboratory Ventura County, California (HSA), other potential radionuclide COCs in

addition to Co-60 and Eu- 152 include: Am-24 1, Cs-134, Cs- 137, Eu-154, Fe-55, Fe-59, H-3, K-40, Mn-54, Na-22, Ni-63, Pu-238, Pu-239, Pu-240, Pu-241, Sr-90, Th-228, Th-230, Th-232, U-

234, U-235, and U-238 . These additional COCs will also be tested for during the confirmatory

survey .

1 .4 Regulatory Authority and Guidance Document s

1 .4.1 Facility Decommissioning

The decommissioning and demolition of the SETF Building 4024 will be performed as a non

time critical removal action under the U .S. Department of Energy's (DOE's) incumbent

CERCLA authority . Use of non-time critical removals for conducting decommissioning

activities effectively integrates DOE lead agency responsibility, U . S . Environmental Protection

Agency (EPA) oversight responsibility, and stakeholder participation . The DOEDecommissioning Program will utilize DOE expertise in devising and implementingappropriate solutions to decommissioning projects . Effective EPA oversight and stakeholderparticipation will be provided in comp liance with applicable requirements . Decommissioningprojects will retain sufficient flexibility to tailor activities to meet specific site needs, andachieve risk reduction and restoration expeditiously .

Regulations and guidance documents utilized for Sample and Analysis Plan development andfor survey implementation include

1 . DOE 0 5400.5, Radiation Protection of the Public and the Environment

2. Policy on Decommissioning of Department of Energy Facilities Under theComprehensive Environmental Response, Compensation, and Liability Act (CERCLA )

3 . Multi-Agency Radiation Survey and Site Investigation Manual (MARS SIM), Revision 1,

August 2000


HDMSE00576743



4. NUREG-1501, Background as a Residual Radioactivity Criterion for Decommissioning,

NRC Draft Report for Comment, August 199 4

5 . NUREG-1506, Measurement Methods for Radiological Surveys in Support of NewDecommissioning Criteria, NRC, August 199 5

6. NUREG-1507, Minimum Detectable Concentrations With Typical Radiation Survey

Instruments For Various Contaminants And Field Conditions, NRC, Draft Report for

Comment, August 199 5

1 .4.2 Decommissioned Materials

The D&D strategy used in most prior decommissioning projects at the SSFL was to clean the

facilities and materials to radiological release criteria approved by the DOE and the NRC-

authorized California State Agency, Department of Health Services, Radiologic Health Branch

(DHS-RHB) . Decontaminated materials would then be surveyed and released for unrestricteduse or disposed of in a Class I II landfill . An alternative to this approach was for those facilities

where the labor required to clean the components or structures to release criteria, plus any

material, transportation and disposal costs, was estimated to be more costly than to size-reduce,

package, and dispose of the materials as low-level waste (LLW) at a licensed LLW disposalsite. This approach minimized both LLW waste generation and cost .

In 2002, the Governor of California issued a moratorium (Ref . 7 .3, Executive Order No . D-62-02) on the disposal of waste materials originating from former radiological facilities that passedthe approved numerical release criteria (Ref. 7 .4, N001 SRR140131) but potentially containedamounts of manmade radioactivity above background. These materials were defined as"Decommissioned Materials" (DM) and were no longer permitted to be disposed of in Class IIIor unclassified (unlined) waste disposal sites . Under the Governor's moratorium, the materialsbelow the release criteria from a demolished former radiological facility can only be disposedof at a Class I or Class II disposal waste facility when there is a potential for radioactivitypresent above background levels .

Boeing has established the following process for identifying materials that fall within thecategory of decommissioned materials : The Boeing Health, Safety and Radiation Servicesdepartment first performs surveys to assure that contamination levels are below the designatedcriteria contained in N001 SRR140131 . Documentation is then provided to the DHS-RHB . TheDHS-RHB then performs a verification survey, provides written concurrence, and the materialsare then sent to a Class I hazardous waste facility .

Boeing shall coordinate with the DHS-RHB to obtain approval to ship DM to Class I or Class IIlandfills . This will entail providing DHS-RHB with AREVA supplied survey/sampling data

showing that the remaining SETF structure is DM that meets approved cleanup standards, and

facilitate DHS/RHB to perform a verification survey of the DM . AREVA shall be responsible

for working with the DHS-RHB for the classification/confirmation of DM wastes . If the DHS-RHB decline to participate in the verification process, then the DOE will self-certify that the

material meets the DM criteria based on the AREVA survey data .


HDMSE00576744



N001 SRR140131 contains both surface contamination limits (consistent with the limits of Reg .Guide 1 .86 and DOE Order 5400 . 5) and soil concentration limits . Soil concentration limits canalso be used for volumetric contamination limits of building debris, including concrete andrebar. AREVA will implement the ALARA process in its demonstration of DM . That is to say,the DHS -RHB will more readily accept material as DM if contamination levels, both surfaceand volumetric , are ALARA .

Based on surface area, volumes and survey data, a dose analysis of the DM for a land fi llscenario will be prepared by AREVA . The dose analysis will demonstrate that the permitrequirements of the Class I hazardous waste facility are met. The permit requires that thedisposal of DM would not result in significant contamination of the environment as defined inCalifornia Health and Safety Code Part 9, Chapter 5, Article 1 .

The AREVA as the D&D contractor will encounter two categories of decommissioned

materials on this project . The SETF high bay (down to the basement area, as indicated by

survey markings on the walls) and the foundations for the General/ support and

Mechanical/electrical support areas have already been surveyed by DHS-RHB and documentedas meeting the DM criteria . The remainder of the SETF which will be managed as DM requires

contractor survey, review by the RHB-DHS and verification survey by DHS-RHB . Alternately,

the DOE will self-certify this material as DM if the DHS-RHB decline to participate .


HDMSE00576745



2. SURVEY OVERVIEW

2.1 Survey Objective

Preliminary surveys and a HSA have been conducted at the SETF facility and site . The objectiveof this Sample and Analysis Plan (SAP) is to obtain additional radiological characterization data

to guide decontamination efforts in the sub grade test cells and perform confirmatory surveys in

areas of the SETF already confirmed by DHS-RHB as decommissioned materials (DM) suitable

for disposal at Kettleman Hills Class I disposal site . An additional objective of this SAP is toobtain background data from materials of construction on surfaces and environmental soil areas

both of which are not impacted by use or storage of radioactive materials . This background data

will assist with evaluations of survey data obtained from SETF surfaces and environmental soil

areas to determine if materials are to be removed as low level radioactive waste (LLW), DMwaste, or suitable to release for unrestricted use after final status surveys are completed . By

combining characterization survey results with the results of the previous RS-00025 survey, a

complete characterization of the SETF site will be available .

The surveys will include measurements for gross total and removable surface radioactivity, dose

rate, and material sampling for isotopic analysis performed and/or collected at random and

biased locations on facility surfaces and in environ soil areas . The survey will also include core

bore sampling of the SETF test cell walls to gain further information on the depth of activation .

2.2 Data Quality Objective s

Data Quality Objectives (DQOs) were developed in accordance with the guidance providedin the MARSSIM . The DQOs for the survey are as follows :

I Background Study - Perform measurements and collect samples of sufficient quantity innon-impacted buildings of similar age and materials of construction and inenvironmental soil area portions of the Santa Susana Field Laboratory (SSFL) or otherappropriate reference area to determine the natural background radioactivity associatedwith the materials of construction and naturally occurring radioactive materials (NORM)present in soils of the environs surrounding or associated with the impacted SETF areassubject of this survey .

2. Confirmatory Survey- Perform measurements and collect samples of sufficient quantity

to confirm that residual radioactivity above natural background from former operationsat Building 4024 is not present in areas already confirmed by DHS-RHB as

decommissioned materials (DM) . Evaluate the measurements and sample results for

comparability to previous survey results .

3 . Operate instruments for background study and survey direct measurements and sampleanalysis such that measurement and/or analysis sensitivities or minimum detectableconcentrations (MDCs) are ALARA or, as a minimum less than the derivedconcentration guideline levels (DCGLs) .

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HDMSE00576746



4. SGTCC Confirmatory Survey- Perform measurements and collect samples of sufficient

quantity to confirm levels of residual radioactivity above natural background from

former operations in test cells and evaluate the measurements and sample results for

comparability to previous survey results . Perform core bore sampling of the SETF testcell walls to gain further information on the depth of activation to assist during removal

of LLW from SETF test cell walls, floor and ceiling .

5 . Remedial action support surveys (RASS) - perform RASS to provide real time datashowing that demolition and decontamination of SETF test cell walls, floor and ceilinghave been successful such that once LLW materials are removed surveys showingremaining structure surfaces of the test cells can be disposed of as DM waste .

2.3 Derived Concentration Guideline Levels for Survey s

In accordance with the guidance provided in the MARSSIM, Section 4, Preliminary Survey

Considerations, derived concentration guideline levels (DCGLs) are needed during survey

planning to provide the goal for essentially all aspects of designing, implementing, andevaluating the survey . The MARSSIM defines the DCGL as follows :

DCGL (derived concentration guideline level) : A derived, radionuclide-specific activityconcentration within a survey unit corresponding to the release criterion. The DCGL is

based on the spatial distribution of the contaminant and hence is derived differently for

the nonparametric statistical test (DCGLW) and the Elevated Measurement Comparison(DCGLEMC) . DCGLs are derived from activity/dose relationships through various

exposure pathway scenarios .

However, the MARS SIM allows for the application of limits established by regulations such as

DOE Order 5400 .5 and NRC Reg . Guide 1 .86 in addition to dose based values as contained in

Ref. 7 .4, Boeing N001 SRR140131 . N001 SRR140131 contains both surface contamination limits(consistent with the limits of Reg . Guide 1 .86 and DOE Order 5400 .5) and soil concentration

limits . Soil concentration limits can also be used for volumetric contamination limits of building

debris, including concrete and rebar . However, the ALARA process will be used to demonstrate

that structure surfaces remaining after demolition and decontamination of the test cells can be disposed ofas DM waste . That is to say these surfaces will be shown to be DM because levels of residualradioactivity, both surface and volumetric, are ALARA. DCGLs and/or background referencevalues may also be action levels as assigned by survey evaluation criteria .

2 .3 .1 DCGL for Surface Contaminatio n

To facilitate proper selection and setup of the survey instrumentation for measurements of grosssurface contamination, DCGLs (in units of dpm/l00 cm2) have been selected from Table 5 ofNOOISRR140131 ; these values meet requirements of DOE Order 5400 .5 . NOOISRR140131specifies the acceptable surface contamination limits that have been approved for use at theSSFL by the DOE and DHS-RHB ; these limits are presented in Table 2-1 . The DCGLs to beused for this survey are 100 dpm/l00 cm2 above background for direct or total alpha surfacecontamination and 20 dpm/l00 cm2 for removable alpha surface contamination. The beta-gammasurface contamination DCGL to be used for this survey is 5,000 dpm/l 00 cm2 above backgroun d


HDMSE00576747


Confirmatory Survey


for direct or total surface contamination and 1,000 dpm/100 cm2 for removable surface

contamination . These reference values will be the basis for measurement MDCs and comparison

for direct measurements to determine acceptable residual radioactivity levels once corrected for

the natural background . These values may also be used in conjunction with personnel,instruments, equipment decontamination, and free release procedure to determine suitability to

free release .

Radionuclide Average Total Maximum Total Removable(dpm/100 cmz) (dpm/100 cmz) (dpm/100 cmz) 2, 4

(Fixed + Removable z' sz, 3

(Fixed + Removable)

U-nat, U-235, U-238, and associated 5,000 (alpha) 15,000 (alpha) 1,000 (alpha)

deca productsTransuranics, Ra-226, Ra-228, Th- 100 300 20230, Th-228, Pa-231, Ac-227,1-125 ,1-129

Th-nat, Th-232, Sr-90, Ra-223, Ra- 1,000 3,000 200224, U-232,1-126,1-131,1-13 3Beta-gamma emitters (nuclides with 5,000 15,000 1,00 0

decay modes other than alphaemission or spontaneous fission )except Sr-90 and others noted above 5

Tritium and tritiated com ounds6 N/A N/A 10,000

NOTES:1 . The values in Table 2-1 are from Ref. 7 .4, Boeing document N001 SRR140131 and are consistent with

values contained in DOE 0 5400 .5 and 10 CFR Part 835, Appendix D . The values, with the exceptionnoted in footnote 5, apply to radioactive contamination deposited on, but not incorporated into the interioror matrix of, the contaminated item . Where surface contamination by both alpha-and beta-gamma-emitting

nuclides exists, the limits established for alpha-and beta-gamma-emitting nuclides apply independently .2 . As used in this table, dpm (disintegrations per minute) means the rate of emission by radioactive material

as determined by correcting the counts per minute observed by an appropriate detector for background,efficiency, and geometric factors associated with the instrumentation .3 . The levels may be averaged over one square meter provided the maximum surface activity in any area of100 cmz is less than three times the value specified . For purposes of averaging, any square meter of surfaceshall be considered to be above the surface contamination value if. (1) From measurements of arepresentative number of sections it is determined that the average contamination level exceeds theapplicable value ; or (2) it is determined that the sum of the activity of all isolated spots or particles in any100 cm2 area exceeds three times the applicable value .4. The amount of removable radioactive material per 100 cm 2 of surface area should be determined byswiping the area with dry filter or soft absorbent paper, applying moderate pressure, and then assessing theamount of radioactive material on the swipe with an appropriate instrument of known efficiency . (Note--The use of dry material may not be appropriate for tritium .) When removable contamination on objects ofsurface area less than 100 cm 2 is determined, the activity per unit area shall be based on the actual area andthe entire surface shall be wiped. It is not necessary to use swiping techniques to measure removablecontamination levels if direct scan surveys indicate that the total residual surface contamination levels arewithin the limits for removable contamination .

5 . This category of radionuclides includes mixed fission products, including the Sr-90 which is present inthem. It does not apply to Sr-90 which has been separated from the other fission products or mixtureswhere the Sr-90 has been enriched .

SETF_SAP March 30, 2007, RevO final .do c

Table 2-1, Acceptable Surface Contamination Values'

March 2007

HDMSE00576748



6 . Tritium contamination may diffuse into the volume or matrix of materials . Evaluation of surfacecontamination shall consider the extent to which such contamination may migrate to the surface in order toensure the surface contamination value provided in this appendix is not exceeded . Once this contamination

migrates to the surface, it may be removable, not fixed; therefore, a "Total" value does not apply.

2.3 .2 Gamma Exposure Rate Measurements

Gamma exposure rate measurements performed at 1 meter above surfaces will be performedduring the survey for informational purposes . A value of 5 jtR/hour above the background will

be used for reference consistent with Section 5 of NOO 1 SRR140131 . This value is one fourth of

20 gR/hour above the background as provided in DOE Order 5400 .5 and will be used to

compare gamma exposure rate measurements for the survey . DOE Order 5400 . 5 states :

"The average level of gamma radiation inside a building or habitable structure on a site tobe released without restrictions shall not exceed the background level by more than 20uR/hour and shall comply with the basic dose limit when an "appropriate-use" scenario isconsidered. This requirement shall not necessarily apply to structures scheduled fordemolition or to buried foundations . External gamma radiation levels or open lands shallalso comply with the basic limit and the ALARA process, considering appropriate-usescenarios for the area . "

2.3 .3 DCGLs for Soil or Bulk Decommissioned Material s

The DCGLs to be used to determine that decontamination of the activated SETF test cells has

been successful for the SETF contaminants of concern (COC) are 1 .9 pCi/g for Co-60, and 4 .5

pCi/g for Eu-152 . These values come from Section 3 .5 of NOOISRR140131 guidelines forresidential soil . These DCGLs with ALARA principles will also be used to show that portions of

the SETF remaining, after cell decontamination is complete, can be demolished and disposed of

as DM .

In addition to the primary COCs, other radionuclides have the potential to be present at theSETF. These potential COCs will also be analyzed for during characterization and values fromN001 SRR140131 used as DCGLs . The DCGLs for the potential radionuclide COCs and goal foranalysis minimum detectable concentrations (MDC) are as follows :

Radionuclide Symbol MDC(Ci/)

DCGL(Ci/ )

Americium-241 Am-241 0 .1 5 . 4Cobalt-60 Co-60 0 .1 1 . 9

Cesium-134 Cs-134 0 .1 3 . 3Cesium -137 Cs-137 0 .1 9 . 2

Europium-152 Eu-152 0.5 4 . 5Europium -154 Eu-154 1 4 . 1

Iron - 55 Fe - 55 20 629,000Hydrogen-3 H-3 10 31,900

Potassium -40 K-40 1 27 . 6Manganese-54 Mn-54 0 .1 6 . 1


Table 2-2, Acceptable Soil and Bulk DM DCGLs and MDCs

HDMSE00576749



Radionuclide Symbol MDC(Ci/)

DCGL(Ci/ )

Sodium-22 Na-22 0 .1 2 . 3Nickel-63 Ni-63 10 55,300

Plutonium -238 Pu-238 0 .1 37 . 2Plutonium -239 Pu-239 0.1 33 . 9Plutonium -240 Pu-240 0.1 33 . 9Plutonium -241 Pu-241 5 23 0

Strontium-90 Sr-90 0.5 36Thorium-228 Th-228 0 .1 5Thorium -232 Th-232 0 .1 5Uranium-234 U-234 0 .1 30Uranium -235 U-235 0 .1 30Uranium -238 U-238 0 .1 35

Existing dose-based DCGLs are used here because the DHS recommends a dose assessment beprepared for disposal of DM to land fills . A separate Final Status Survey Plan will be developed

to address the sampling and analysis requirements of a MARSSIM designed final status survey

(FSS) that demonstrates successful attainment of the end state . This FSS plan will includeDCGLs based on a cancer incidence risk level of 1 x 10-6 for soil areas after the SETF structure

has been removed .

2.4 Organization and Responsibilities

AREVA will implement an integrated management approach that includes project managementoversight and technical support . The AREVA Project Manager will support the onsite team toensure successful project execution and completion . The onsite survey and samp ling team,position descriptions , required training and experience is discussed in detail in Reference 7 .7,Quality Assurance Project Plan for the survey .


HDMSE00576750



3. SURVEY INSTRUMENTATIO N

Selection and use of instruments will ensure sensitivities are sufficient to detect the identifiedprimary radionuclide at the minimum detection requirements . Table 3-1 provides a list of the

instruments, types of radiation detected and calibration sources . The radionuclide Co-60 and Eu-152 emits both beta and gamma radiation, are not present in natural background radiation, and

can be measured using these field instruments . As stated in Section 1 .3 and Section 2 .3.3, Co-60,Eu-152 and other potential contaminants of concern (COC) will be tested for during the survey,

as follows: Am-241, Cs-134, Cs-137, Eu-154, Fe-55, Fe-59, H-3, K-40, Mn-54, Na-22, Ni-63,Pu-238, Pu-239, Pu-240, Pu-241, Sr-90, Th-228, Th-230, Th-232, U-234, U-235, and U-238 .

These potential COC collectively emit alpha, beta, and gamma radiation, some are and some arenot present in natural background radiation, and some can and some cannot be measured using

portable field instruments. Because some these radionuclides are also found in the natural

background radioactivity, a background study will be performed such that levels of naturally

occurring radioactivity background and residual radioactivity from SETF operations can be

properly accounted for . Further, the radionuclides not easily detected by portable fieldinstruments will be quantified through offsite laboratory analysis utilizing alpha spectrometry,

liquid scintillation counting and by gamma spectrometry, as appropriate .

AREVA will use the Ludlum Model 2350-1 Data Logger or equivalent instrument with a variety

of detectors for direct measurements of total alpha and beta surface activity as well as exposure

rate measurements . The Data Logger is a portable micro-processor computer based counting

instrument capable of operation with ZnS scintillation, plastic scintillation, GM, and NaI(Tl)gamma scintillation detectors . The Data Logger is capable of retaining in memory the survey

results and instrument/detector parameters for up to 1000 measurements . This data is then

downloaded to a personal computer for subsequent reporting and analysis .

Detector selection will depend on the survey to be performed, surface contour and survey area

size. The project team will use a 125 cm2 Zinc Sulfide (ZnS) detector for direct alpha

measurements and a 125 cm2 plastic scintillation detector for direct beta measurements . A 2" x

2" Sodium Iodide (NaI) gamma scintillation detector will be used for gamma exposure rate andcount rate measurements . Smears for removable alpha and beta activity will be analyzed using a

shielded Alpha/Beta Planchet Counter . Typical MDCs for the instrument/detector combinations

are presented in Table 3-1, Portable Survey Instrumentation .

Isotopic quantification and identification will be performed on soil , sediment, and residue/debrissamples sent offsite to the AREVA Environmental Laboratory (AREVA E-Lab) . The AREVA

E-Lab will analyze these samples using High Purity Germanium (HPGe) based gammaspectroscopy system to quantify gamma emitting radionuclides , liquid scintillation counting forquantifying beta emitting radionuclides and solid-state silicon charged pa rticle detector basedalpha spectroscopy system to quantify alpha emitting radionuclides .


HDMSE00576751


Confirmatory Survey

Table 3-1Portable Survey Instrumentatio n

I II StrUIIICnt if

I)ctector


'1'' pica!MI)( McaSurenicn t

Ludlum Model 2350-1 Plastic 600 Direct beta, staticwith 44-116, 43-89 Scintiltatordetector or equal (125 cm2) Beta 99Tc ((3) < 5,000 Beta scan .Ludlum Model 2350- 1with 43-90, 43-89 ZnS Scintillatordetector or equal (125 cm2 Alpha 230Th (a) 95 Direct alpha, staticLudlum Model 2350- 1

ith 44 40 d t t Shi ld d GM 2,300 Direct beta, static. - or o rw e ec e eequal (15 .5cm2) Beta 99Tc ((3) < 5,000 Beta scans .

Ludlum Model 2350-1 Nal (TI) Gamma exposur e

with . 44-10 detector or Scintiltator < 5 R/hr rate

equal (2" x 2") Gamma 137Cs (y) 240 MDCR Gamma scans .

Ludlum Model 2929Scaler w/Model 43-10-

1 1 Sample Counter

Dual channelShieldedPhoswichScintillator Alpha & Beta

230Th (a)

99Tc 90

Gross Alpha/Beta

Smear countin g

Note 1 : Units are dpmll00cm2 unless otherwise specified.

3.1 Instrument Calibration

Data loggers and associated detectors are calibrated on an annual basis using National Instituteof Standards and Technology (NIST ) traceable sources and calibration equipment .

The calibration includes :

• High Voltage calibration ,

• Discriminator/threshold calibration,• Window calibration,

• Alarm operation verification, and

• Scaler calibration verification .

The detector calibration includes :

• Operating voltage determination ,

• Calibration constant determination, and• Dead time correction determination .

Calibration labels showing the instrument identification number, calibration date, and calibrationdue date are attached to all portable field instruments . The user will check the instrument

calibration label before each use .

SETF_SAP March 30, 2007, RevO final .doc

I)etector Radiation Calibration

,I'} re I)ctcctcd Source

March 2007

HDMSE00576752



3.2 Sources

All sources used for calibration or efficiency determinations for the survey will be representativeof the instrument's response to the identified nuclides and are traceable to NIST .

Radiation Protection Technicians will control radioactive sources used for instrument responsechecks and efficiency determination . Sources will be stored securely and signed out whenneeded in the field . A source sign-out log will track the location of all sources when they areremoved from the AREVA field office .

3.3 Static Measurement Minimum Detectable Concentratio n

The MDC is defined as the smallest amount or concentration of radioactive material in a samplethat will yield a net positive count with a 5% probability of falsely interpreting background

responses as true activity . The MDA is dependent upon the counting time, geometry, sample

size, detector efficiency and background count rate as explained in Reference 7 .13, NUREG-

1507, Minimum Detectable Concentrations with Typical Radiation Survey Instruments forVarious Contaminants and Field Conditions . As a data quality objective, the instrument

operating parameters will be set such that static alpha and beta measurement MDCs will be onehalf the DCGL, or at a minimum less than the DCGL, according to the guidance provided in the

MARSSIM, NUREG-1575 . The equation used for calculating the static MDC for fieldinstrumentation is :

3 + 3.29Rb is (1 + ts

MDC =A

tb

RT(100) is

Where :MDC = Minimum Detectable Concentration (dpm/l00 cm2)Rb = Background Count Rate (cpm)

tb = Background Count Time (min)is = Sample Count Time (min)

A = Detector Area (cm2 )ET = Total detector efficiency (MARSSIM Section 6 .6 .1 )

And :


ETI(D

S

March 2007

HDMSE00576753



Where :

ET,

Dc

Sc

Esz

= total detector efficiency (NUREG-1507)

= net detector counts (cpm )

= source 2 7r emission rate (cpm) from source calibration certi fi cation= source efficiency, unless directed to use experimentally proven

value, use 0 .25 for alpha measurements and beta measurements(beta energies from 0 .15 to 0 .4 MeV) or 0 .5 for beta measurements(beta energies > 0.4 MeV)

If the source used for the detector efficiency determination was calibrated for total activity only(e.g., source 4ir activity in dpm), the detector efficiency would be calculated as follows :

ET2

Where :

SD

ET2 = total detector efficiency

Dc = net detector counts (cpm)

SD = source 471 activity (dpm) from source calibration certification

Est = source efficiency, unless directed to use experimentally proven

value, use 0 .5 for alpha measurements and beta measurements(beta energies from 0.15 to 0 .4 MeV) or 1 .0 for beta measurements(beta energies > 0.4 MeV)

Prior to performing measurements, the survey team may calculate preliminary MDCs prior to thefieldwork using information from the background study .

3.4 Scan Survey Minimum Detectable Concentration

The scan MDC for structure surfaces will be calculated according to the guidance provided inthe MARSSIM Section 6 .7 .2 .1, as follows :

ScanMDC =

Where :

MDCR

/ ElES( )100

MDCR = Minimum detectable count rat e

Ei = instrument efficiencyES = surface efficiencyp = surveyor efficiency

A = Detector Area (cm2 )


HDMSE00576754



4. SURVEY/SAMPLING DESIG N

4.1 Introduction

The purpose of this survey is to provide sufficient, accurate data to confirm radiological

conditions in areas of the SETF already confirmed by DHS-RHB as decommissioned materials

(DM), and obtain additional radiological characterization data to guide decontamination efforts

in the sub grade test cells . In addition to obtain background data from materials of constructionon surfaces and environmental soil areas both of which not impacted by use or storage of

radioactive materials . This background data will assist with evaluations of survey data obtained

from SETF surfaces and environmental soil areas to determine if materials are to be removed as

low level radioactive waste (LLW), DM waste, or suitable to release for unrestricted use afterfinal status surveys are completed .

The surveys will include measurements for gross total and removable surface radioactivity, dose

rate, and material sampling for isotopic analysis performed and/or collected at random andbiased locations on facility surfaces and in environ soil areas . The survey will also include core

bore sampling of the SETF test cell walls to gain further information on the depth of activation .

The project team will perform surveys according to AREVA procedures, survey packageinstructions (field sampling plans), and this Sampling and Analysis Plan . The procedures

identify survey instrument requirements, measurement and sample collection, and data reduction

and evaluation methods, while the survey package identifies specific instructions to implement

the survey protocols contained in this SAP. Implementation of this SAP will include the

following :

• A walk-down of the site to assist in the survey design . Survey units and classifications

have been established, and measurement frequency and type determined for each survey

unit .

• Survey packages (or field sampling plans) tracking mechanisms will be developed for

each of the survey units . These survey packages will provide the survey team with

specific sampling and measurement instructions .

• Samples will be collected to support DQOs for background study and for core boresampling of the activated sub grade test cell complex walls, floor and/or ceiling .

• The samples will be packaged and field screened by the project team personnel and

samples showing significant levels of radioactivity above background will be sent to theoffsite laboratory for analyses .

• The project team will perform survey measurements and collect samples for removablecontamination as defined in the survey package . Measurements will be performed usingappropriate calibrated instruments and daily instrument quality control (QC) checks wil l


HDMSE00576755



be performed before and after each day's work .

• The project team will mark or map the survey locations as applicable .

• Survey data collected during the project will be downloaded from the survey instrument

to a secure data management system for storage, analysis, and reporting .

• Supervisory personnel will review the completed survey packages to ensure that all

required surveys have been performed and that the completed survey packages containall necessary information .

4.2 Survey Requirement s

The following survey protocols consist of a mix of surface activity measurements and sampling .Samples will be shipped offsite for analyses such as alpha spectroscopy and/or gamma

spectroscopy. The current guidance contained in MARSSIM provides for the classification of a

site into either Impacted or Non-Impacted Areas . Areas with some potential for contamination

are classified as impacted. Areas that have no reasonable potential for contamination areclassified as non-impacted .

Impacted areas may be then further divided in to one of three classifications :

• Class 1 Areas: Areas that have, or had prior to remediation , a potential for radioactive

contamination (based on operating history) or known contamination (based on previoussurveys) above the DCGL .

• Class 2 Areas: Areas that have, or had prior to remediation, a potential for radioactive

contamination, but are not expected to exceed the DCGL .

• Class 3 Areas : Any impacted area that is not expected to contain any residual

radioactivity, or is expected to contain levels of residual radioactivity at a small fractionof the DCGL .

For the purpose of this survey, the site has been classified as impacted based on information

contained in Ref. 7 .5, RS-00025 report . It should be noted that MARSSIM is primarily designedfor building surfaces and surface soils, and its application to this investigation is for statistical

testing purposes . If residual radioactive material is found during this survey, the survey units

will be classified as Class 1 or 2 for final status survey planning . Should residual radioactive

material not be found, this survey is intended to serve as and support a Class 3 final status surveyfor release of the subject survey unit. Refer to Attachment 1, SETF Site Survey Areas and

Survey Units, for the initial divisions and classification .

The types of measurements and samples that may be performed may vary depending on

accessibility and sample recovery . For example, at each accessible survey location, it may be

reasonable to perform measurements for total and removable contamination, and materia l


HDMSE00576756



samples for offsite laboratory analysis on structural surfaces. However, if accessibility issuesarise, the survey (measurements and samples) would be modified as practical for the location

and specific location. In the case for collection of material samples for alpha and/or gamma

spectroscopy, the first effort for sample collection will be for 2 kg (kilograms) of material forgamma spectroscopy analysis at each accessible sample location or a 2 kg composite material

sample collected by scraping the surfaces between multiple sample locations . With the addition

of a background study, the survey requirements for the survey units at SETF are as follows :

4.2.1 Number of Measurements

For a given survey unit, MARSSIM provides direction on how to determine the minimum

number of measurement or sample locations to be collected based on the nonparametricstatistical test to be used to evaluate the data . This number is based on the desired power of thestatistical test (confidence levels), the expected variation in the sample or measurement results,

and the width of the gray region which impacts the probability of incorrectly failing to release a

survey unit that meets the criteria for release for unrestricted use . The survey results will be used

to assess the presence or absence of radiological contamination in each survey unit .

To determine the number of measurements needed in an impacted survey unit for the surveys,

settings recommended in Reference 7 .15, Appendix A, Section A .7, Volume II of the NUREG-1757 and the MARSSIM Section 5 .5 will be used. The settings to determine the number of

measurements in a survey unit will be as follows :

• The null hypothesis (Ho) will be that residual radioactivity in the survey area and/or

units exceed the release criterion .

• For the purpose of the characterization surveys, Type I error (a) will be set at 0 .05 or5 percent and Type II error ((3) will be set at 0 .05 or 5 percent.

• The lower bound of the gray region (LBGR) will be conservatively set at 50% of the

DCGL, but could be adjusted later to provide a value for the relative shift between

the range of 1 to 3 .

• The relative shift will be conservatively set to 1 .5 .

Because the survey measurements will be corrected for background and the sample analysis isradionuclide specific, the number of measurements to take is from the MARSSIM Table 5 .5 .

This will result in a value of "N" (prescribed number of samples/measurements) equal to 18 for

each survey unit, with an additional 18 samples/measurement locations (S/ML) for the referencearea. The values listed in MARSSIM Table 5 .5 have been increased by 20% to account forpotentially unusable data .

Alternately, the Visual Sample Plan (VSP) program may be employed to assist with surveyplanning and determining number of measurement locations necessary for a survey . VSP wasdeveloped by Pacific Northwest National Laboratory (PNL) and DOE to assist with surve y


HDMSE00576757



design and two dimensional modeling of environmental (land area) and for structural surfaces .VSP provides planning assistance for sampling design and uses MARSSIM based mathematical

and statistical algorithms to determine how many samples are needed for either environmental or

structural survey units and assists with survey maps and drawings to show where samples shouldbe taken.

4.2.2 Visual Sample Pla n

Alternately, the Visual Sample Plan (VSP) program may be employed to assist with survey

planning and determining number of measurement locations necessary for a survey . VSP wasdeveloped by Pacific Northwest National Laboratory (PNL) and DOE to assist with survey

design and two dimensional modeling of environmental (land area) and for structural surfaces .VSP provides planning assistance for sampling design and uses MARSSIM based mathematical

and statistical algorithms to determine how many samples are needed for either environmental or

structural survey units and assists with survey maps and drawings to show where samples should

be taken.

4.2.3 Survey Package Developmen t

For each survey unit, (e .g., background reference area, structural surfaces, and environmental

soil areas) the survey team will develop a survey package, or portfolio . The survey packages willbe the primary method of controlling and tracking the hard copy records of survey results . The

characterization survey packages will be developed according to this plan and will be provided

as a record of survey activities once the survey has been completed . Records of surveys will bedocumented and maintained in the survey packages for each survey unit . During the survey, the

project team will update the survey package(s) with the survey data and results of any surveys or

sample analyses performed on a daily basis .

Information and details regarding the history and physical survey units will be compiled during awalk-down . The survey package will contain sections for this information as follows :

1) Detailed description of the survey area and/or survey units, as applicable,

Photographs, drawing or drawings of the survey area and/or survey units, asapplicable,

3) Survey area operational history including summary data from previous surveys,

4) Survey instructions,

5) Location codes developed uniquely for the area ,

6) Types and number of survey measurements and/or samples prescribed for the survey.

7) Survey support requirements ,


HDMSE00576758



Health and safety requirements ,

9) RWP requirements ,

10) Specific survey instructions for any abnormal conditions that may be encountered

within the survey area, and

11) Survey instrument data downloads and sample analysis report hard copies .

A combination of photographs and/or drawings will be developed for each survey package

depicting each survey area or survey unit . The survey area/unit drawings will be annotated withthe location of the survey measurement locations .

4.2.4 Background Stud y

AREVA will conduct a background study to determine environmental nuclide concentrationsand direct measurement levels from areas similar but not associated with the subject survey

units . The local background determination will serve as the baseline for evaluating survey

measurement results and survey reference values . Because the background study results will beused in the evaluation of the onsite survey data , measurements , sampling , sample preparation,and sample analysis will be similar to those to be used for the onsite measurements . Basisinformation and guidance for conducting a background survey can be found in Section 4 .5 of the

MARSSIM and in Ref. 7 .15, Appendix A, Section A .3, Volume 11 of the NUREG-1757,Selection of Background Reference Areas and Background Reference Materials.

Typical nuclides found in significant levels in background materials (soil, sediments, buildingmaterials, etc .) include some of the potential COC, i .e ., from the naturally occurring uranium inaddition to naturally occurring radioactive materials (NORM) thorium, and actinium series, butnot Co-60 or Eu-152. The background study will be performed on structural surfaces andenvironmental soil areas which have common characteristics with the samples to be collectedfrom the SETF survey unit structural surfaces and environmental soil areas but which areunaffected by radioactive material storage or operations . The background soil and sedimentsamples will be analyzed by radionuclide specific analysis (e .g ., alpha and gamma spectroscopy)to determine the radionuclides and their concentration in the natural background.

Direct alpha and direct beta measurements for material background will be taken on constructionmaterials, which are expected to include : metal, painted concrete and bare concrete . Theseconstruction materials contain various amounts of NORM, as discussed above, that add to thegross activity direct alpha and direct beta measurements . The data collected during thebackground study will be reviewed for trends, and statistics performed on the various data setsfor each material surveyed. The background data will be used for evaluation of the survey datacollected from the subject survey units . Data collected from the SETF survey units will becompared to the background data to determine if it is statistically different during the dataevaluation and review described in Section 4 .2 .7 .


HDMSE00576759


Confirmatory Survey


The number of samples and measurements to be taken for the various background parameters

will be as shown in Table 4-1 below .

Table 4-1, Background Reference Study

Number of Measurements and Sample s


Survey Unit Type Surfaces and Environmental Tota l

Structures BackgroundBackground Reference Area

Reference Area

Number of Survey Units 1 1 2

Survey Measurement Typ e

Direct Beta Measurements on Bare Concrete, 54 0 5 4Painted Concrete, and Metal Surface s

Direct Alpha Measurements on Bare Concrete, 54 0 5 4Painted Concrete, and Metal Surface s

Contact Gamma Scan Measurement on 18 0 1 8Concrete Surfaces of 9 m2 at each SML

1 Meter Gamma Exposure Rate Fixed 18 18 36MeasurementSoil/material Samples for Isotopic Analysis 1 18 1 9

Total 145 36 18 1

4.2.5 Confirmatory Survey Measurements and Sample s

A confirmatory survey will be performed that consists of measurements and samples ofsufficient quantity to confirm that residual radioactivity above natural background from formeroperations at Building 4024 is not present in areas already confirmed by DHS-RHB asdecommissioned materials (DM). Measurements will also be collected in environmental areasadjacent to and around the SETF to establish as found conditions before decontamination anddemolition activities begin . The objective of the survey is to confirm with reasonable confidencethe presence or absence of radioactive material in excess of the DCGL survey reference values,and evaluate the measurements and sample results for comparability to previous survey results .This objective will be met through implementation of a combination of random and biasedsampling program, which will be based on facility layout, operational history, interviews withSETF staff, and previous Boeing sampling results from Building 4024 .

The number of measurements and samples will be sufficient to confirm the absence, or presenceof radioactive material . If radioactivity is detected at levels greater than the reference DCGLs,this condition may require further study to determine the lateral extent of radioactivecontamination. The number of measurements to be performed for the survey will beapproximately 10% of the numbers from the MARSSIM Table 5 .3 but will be performed infourteen (14) of the sixteen (16) total survey units (Attachment 1) . The number of measurementsand samples will be as shown in Table 4-2 below .


HDMSE00576760


Confirmatory Survey

Table 4-2, Confirmatory Survey

Number of Measurements and Samples



Survey Unit Type Impacted

Surfaces

an dStructures

Non-Impacted

Surfaces an d

Structures

Impacted

EnvironsNon -

Impacte d

Environs

Tota l

Number of Survey Units 9 3 1 1 1 4

Survey Measurement Typ e

Beta Scan Survey of 9 m2 at each SML 1 8

Direct Beta Measurement 18 6 2 4

Direct Alpha Measurement 18 6 2 4

Smear Sample for Removable Alpha/Beta 18 6 2 4

Contact Gamma Scan Survey of 25 m2 at

each SML

2 2 4

1 Meter Gamma Exposure Rate, FixedMeasurement

18 6 2 2 2 8

Soil/material Samples for Isotopic Analysis 2 0 2 2 6

Total 92 24 6 6 128

Survey protocols for the confirmatory survey will be as follows . These protocols and the orderperformed may vary as more is learned about the SETF site .

1 . Direct and removable measurements will be performed on the surface of each

sample/measurement location (SML) . The SMLs will be depicted on drawings locatedin the survey package instruction. The measurements will be for total beta surface

contamination and for total alpha surface contamination . Each of the detectors will bemanually positioned , placed in an appropriate geometry on the surface to be measured .The project team will mark or map the survey measurement locations as applicable . The

measurements will be performed on dry surfaces . Survey data collected during theproject will be downloaded from the survey instrument to a secure data management

system for storage, analysis , and reporting .

2 . Smear samples for removable alpha and beta contamination will be collected at each ofthe locations where direct measurements were performed . The smear samples will be

collected by applying moderate pressure and wiping approximately 100 cm2 area for the

sample .

3 . Exposure rate measurements will be performed , one meter above the SML on floor orabove environment sample locations .

4 . The project team will perform sampling as material (e.g., residue, silt, or soil) isidentified. The samples in order of priority are as follows :


HDMSE00576761



a. 2 kg Soil/Sediment Samples for Gamma Spectroscopyb. 5 to 10 g Soil/Sediment Samples for Alpha Spectroscopy, and/orc . Collect residues on smears where indication of contamination is detected .

5 . The project team will mark or map the survey sample locations as applicable .

6 . The samples will be packaged and field screened by the project team personnel, chain ofcustody forms and sample shipping paperwork completed, and sent to the offsite

AREVA E-Lab for analysis .

7 . Supervisory personnel will review the completed survey packages to ensure that all

required surveys have been performed and that the completed survey packages containall necessary information .

4.2.6 SGTCC Confirmatory Survey

A confirmatory survey of the SGTCC will be performed that consists of measurements and

samples of sufficient quantity to confirm levels of residual radioactivity above natural

background from former operations in the Test Cells B-102 and B-104 . The objective of thesurvey is to confirm with 95 percent confidence the presence of radioactive material in excess of

the DCGL survey reference values , and evaluate the measurements and sample results forcomparability to previous survey results . This objective will be met through implementation of a

combination of random and biased sampling program , which will be based on cell layout,operational history , interviews with SETF staff, and previous sampling results from Building4024. The samples will include core bores of the SETF test cell walls to gain further information

on the depth of activation to assist during removal of LLW from SETF test cell walls, floor and

ceiling. The number of measurements and samples will be sufficient to confirm the presence andlateral and vertical extent of radioactive material . The number of measurements to be performedfor the survey will be approximately 50% of the numbers from the MARSSIM Table 5 .3 but willbe performed in two (2) of the sixteen (16) total survey units (Attachment 1) . The number of

measurements and samples will be as shown in Table 4-3 below .


HDMSE00576762





Surface s

an dStructures

Tota l

Number of Survey Units 2 2

Survey Measurement Type

Beta Scan Survey of 9 m2 at each SML 18 1 8

Direct Beta Measurement 18 1 8

Direct Alpha Measurement 18 1 8

Smear Sample for Removable Alpha/Beta 18 1 8

Gamma Scan Survey of 9 m2 at each SML 18 1 8

Contact Gamma Exposure Rate FixedMeasurement of Cell Surfaces

18 1 8

Samples for Isotopic Analysis 18 1 8

Total 126 126

Survey protocols for the confirmatory survey will be as follows . These protocols and the orderperformed may vary as more is learned about the SETF site .

1 . Beta Scan Surveys will be performed on cell floor, walls and ceiling to determinelocations of highest and lowest activation products by beta emissions . The resultingSMLs will be marked on drawings located in the survey package instruction .

2 . Direct and removable measurements will be performed on the surface of eachsample/measurement location (SML) identified by the beta scan . The measurementswill be for total beta surface contamination and for total alpha surface contamination .Each of the detectors will be manually positioned , placed in an appropriate geometry onthe surface to be measured . The measurements will be performed on dry surfaces .Survey data collected during the project will be downloaded from the survey instrumentto a secure data management system for storage, analysis, and reporting .

3 . Smear samples for removable alpha and beta contamination will be collected at each of

the locations where direct measurements were performed . The smear samples will be

collected by applying moderate pressure and wiping approximately 100 cm2 area for the

sample .

4 . Gamma scan surveys will be performed on cell floor, walls and ceiling to determine

locations of highest and lowest activation products by gamma emissions . The resulting

SMLs will be marked on drawings located in the survey package instruction .


Table 4-3SGTCC Confirmatory Survey


March 2007

HDMSE00576763



5 . Contact gamma exposure rate measurements will be performed at locations identified

during the gamma scan. The detector will be manually positioned, placed in an

appropriate geometry on the surface to be measured . Survey data collected during the

project will be downloaded from the survey instrument to a secure data managementsystem for storage, analysis, and reporting.

6 . The project team will evaluate the SMLs from the beta and gamma surveys to determine

locations to perform nominal core bore sampling using a vacuum based core drill with3" diameter diamond bit . The core bores once obtained will be handled as follows :

a . Marked for location and orientation to cell wall and placed in clean plastic

wrapper

b. Moved to a low background areac. Drawing developed to depict measurements and wafer locationsd. Direct beta measurements performed on each en de . Axial gamma scan performed along length of core bore with collimated NaI(Tl)

detector to indicate depth of activation

f. Core will be sliced into approximate 1 inch thick slices (pucks )g. Pucks will be marked for location and have direct alpha and beta measurements

performed on each en dh. Step e. and f. will be repeated until direct measurement results are

indistinguishable from background level s

i. Results of data evaluations will be used to determine pucks to send to offsite

laboratory for further isotopic analysi s

7 . The samples will be packaged and field screened by the project team personnel , chain ofcustody forms and sample shipping paperwork completed , and sent to the offsiteAREVA E-Lab for analysis .

8 . Supervisory personnel will review the completed survey packages to ensure that allrequired surveys have been performed and that the completed survey packages containall necessary information .

4 .2.7 Remedial Action Support Survey Measurements and Sample s

Remedial action support surveys (RASS) will be performed that consists of measurements andsamples of sufficient quantity to confirm that residual radioactivity above natural background

from decontaminated SGTCC wall, floor and ceiling is no longer present and confirm that the

materials remaining can be demolished and disposed of as decommissioned materials (DM). The

objective of the survey is to confirm with 95 percent confidence with real time data showing thatdemolition and decontamination of SETF test cell walls, floor and ceiling have been successful

such that once LLW materials are removed surveys showing remaining structure surfaces of the test cells

can be disposed of as DM waste . This objective will be met through implementation of a

combination of random and biased sampling program, which will be based on facility layout anddecontamination operations . The number of measurements and samples will be sufficient t o


HDMSE00576764



confirm the absence, or presence of radioactive material . If radioactivity is detected at levels

greater than the reference DCGLs, this condition may require further study to determine the

lateral extent of radioactive contamination .

The measurements to be performed over the course of the decontamination of the cell walls willbe in much iteration until surfaces meet clean up goals . Once the clean up goals are achieved, afinal RAS S will be performed to document the final condition . The number of measurements to

be performed for the survey will be the same as for final status survey taken from the MARS SIM

Table 5 .5 and will be performed in the two test cell survey units listed in Attachment 1 . The

number of measurements and samples will be as shown in Table 4-4 below .

Table 4-4, Final Remedial Action Survey




Surface s

an dStructures

Tota l

Number of Survey Units 2 2

Survey Measurement Type

Beta Scan Survey, 100% of Surfaces ineach cell

2 2

Direct Beta Measurement 36 3 6

Smear Sample for Removable Alpha/Beta 36 36

Gamma Scan Survey, 100% of Surfaces in

each cell

2 2

Contact Gamma Exposure Rate FixedMeasurement of Cell Surfaces

36 3 6

Samples for Isotopic Analysis 18 1 8

Total 130 13 0

Survey protocols for the final RAS SURVEYS will be as follows . These final status surveyprotocols may be performed in a different sequence based on operations at the time and as moreis learned about the SGTCC survey units .

1 . A beta scan survey of 100% of the decontaminated SGTCC survey unit surfaces will beperformed .

2 . Direct and removable measurements wi ll be performed on the surface of eachsample/measurement location (SML). The SMLs will be depicted on drawings locatedin the survey package instruction. The measurements will be for total beta surfacecontamination . Detectors will be manually positioned, placed in an appropriategeometry on the surface to be measured . The project team will mark or map the surveymeasurement locations as applicable . The measurements will be performed on dry


HDMSE00576765



surfaces . Survey data collected during the project will be downloaded from the surveyinstrument to a secure data management system for storage, analysis , and reporting .

3 . Smear samples for removable alpha and beta contamination will be collected at each ofthe locations where direct measurements were performed . The smear samples will becollected by applying moderate pressure and wiping approximately 100 cm2 area for the

sample .

4 . A gamma scan survey of 100% of the decontaminated SGTCC survey unit surfaces willbe performed .

5 . Exposure rate measurements will be performed, one meter above the SML on floor,walls and ceiling surfaces .

6 . The project team will perform sampling as material (e .g ., residue , silt, or soil) isidentified. The samples in order of priority are as follows :

a . 2 kg Soil/Sediment Samples for Gamma Spectroscopyb. 5 to 10 g Soil/Sediment Samples for Alpha Spectroscopy, and/orc. Collect residues on smears where indication of contamination is detected .

Some of these samples may be obtained during the confirmatory survey of the SGTCC .

7 . The project team will mark or map the survey sample locations as applicable .

8 . The samples will be packaged and field screened by the project team personnel, chain of

custody forms and sample shipping paperwork completed, and sent to the offsite

AREVA E-Lab for analysis .

9 . Supervisory personnel will review the completed survey packages to ensure that allrequired surveys have been performed and that the completed survey packages containall necessary information .

4 .2.8 Data Evaluation and Review

Direct alpha and direct beta measurements collected during the characterization surveys will be

compared against the surface DCGLs . The soil sample analysis results will also be comparedagainst the soil DCGL values . A detailed background study will be performed at the beginning

of the surveys . The background study will be used to determine the contribution of naturallyoccurring radioactivity (NORM) in building materials for the direct alpha and direct beta

measurements . The study will determine the effect on the survey results for brick, concrete, and

vitrified clay tile piping materials used for construction of the storm drain and sanitary sewer

systems .


HDMSE00576766



The following equation will be used to convert direct alpha and direct beta measurement resultsto activities per unit area for comparison to the DCGL :

Cs+b Cb

is tbX =

100

Where :X, = individual measurement result in units of activity per unit area,

dpm/100 cm2CS+b = direct beta measurement result, countsCb = backgrounds, countsis = sample count time, minutestb = background count time, minutesET = total detector efficiency (MARSSIM Section 6 .6 .1)A = detector area, cm2

And :

ETI

Where :

ETIDc

Sc

EsI

total detector efficiency (NUREG-1507)net detector counts (cpm)source 2ir emission rate (cpm) from source calibration certificationsource efficiency, unless directed to use experimentally proven value,use 0 .25 for alpha measurements and beta measurements (betaenergies from 0 .15 to 0 .4 MeV) or 0 .5 for beta measurements (betaenergies > 0 .4 MeV)

If the source used for the detector efficiency determination was calibrated for total activity only,(e.g., source 4ir activity in dpm), the detector efficiency would be calculated as follows :

ET2nS

Where :

ET2 = total detector efficiency

Dc = net detector counts (cpm)SD = source 4it activity (dpm) from source calibration certification

Est = source efficiency, unless directed to use experimentally proven value,

use 0 .5 for alpha measurements and beta measurements (beta energiesfrom 0 .15 to 0.4 MeV) or 1 .0 for beta measurements (beta energies >0 .4 MeV)


c * ES2

March 2007

HDMSE00576767



The mean activity level (or mean counts) for the scan surveys and the standard deviation of the

mean activity level (or mean counts) for the scan surveys will be calculated using all availablemeasurement results for the surface surveyed, and the following equations :

X =

Where :

X = the mean activity level, dpm/100 cm2 or counts ,xi = individual measurement result i, dpm/100 cm2n = the number of measurement results, unit less .

and

sX =

n- 1

Where :SX = the standard deviation of the mean activity level, in dpm/100 cm2 or

countsX = the mean activity level, dpm/100 cm2 or counts,x; = individual measurement result i , dpm/100 cm2n = the number of measurement results, unit less .

At the completion of the surveys conducted in each survey unit, measurement results will beobtained and evaluated according to the survey DQOs. As provided by the MARS SIM guidance,the process to survey , measure, analyze data, and evaluate data according to the survey DQOswill be repeated during the characterization . Once all DQOs have been achieved, the survey willbe considered complete .

4.2.9 Elevated Measurement Comparison

The Elevated Measurement Comparison (EMC) may be performed if any measurement from thesurvey unit that is equal to or greater than a DCGL or an investigation level indicates there is anarea of relatively high concentrations that should be investigated-regardless of the outcome ofthe nonparametric statistical tests . The EMC will be performed according to the guidanceprovided in the MARSSIM Section 8 .5 .1, as follows :

DCGLEMC = A. x DCGLW

Where :


Am is the area factor for the area of the systematic grid area .

March 2007

HDMSE00576768



4.2.10 Spatial Analysis and Decision Assistance

The Spatial Analysis and Decision Assistance (SADA) program may be employed to assist withsurvey data evaluation and determining depth of contamination at measurement locations in the

activated test cells . Spatial Analysis and Decision Assistance (SADA) was developed by theUniversity of Tennessee (UT) with funding from EPA and NRC . The basis for development was

recognition that current regulatory guidance contained in the MARSSIM does not discusssubsurface contamination in environmental (soil) areas . The purpose of SADA was to addressthe need with computer based assistance for survey design and three dimensional modeling of

environmental (land area) subsurface contamination . However, SADA can also be applied to

volumetric structural contamination for thick concrete walls, floors and ceilings such as in theSETF test cells .

4.3 Survey Records

The project team will maintain records of surveys in the survey packages for each area accordingto project procedures . The survey package may include the following records depending upon

the survey design and protocols :

• Survey Package Worksheet giving the package identification, survey location

information, general survey instructions, and any specific survey instructions .

• Survey Field Notes containing comments from the survey technician regarding any

unusual situation encountered while surveying .

• The Survey Unit Diagram and/or drawings of the area to be surveyed .

• Photographs of the survey area, as necessary, to show special or unique conditions .

• Printout of laboratory analysis results .

• Ludlum Model 2350-1 data files and converted values for all radiation survey

measurements .

The survey team will take direct measurements for total alpha and beta surface activity using the

Ludlum Model 2350-1 Data Logger system. Upon completion of a survey, the contents of the

Data Logger's memory will be downloaded to a secure data management system .

AREVA will produce a survey report that presents all raw data, converted data, and information

by survey location. The survey technician and supervisor will review these reports for

completeness, accuracy, suspect entries and compare the data to the guideline values .

Any changes to the database tables such as detector efficiency and background, which could

affect survey results, will require supervisor approval . In addition, changes to data in th e


HDMSE00576769



primary table will require a written explanation on a change request . The change request will beattached to the survey report and maintained as a permanent record .

Data and document control will include the maintenance of the raw data files, translated datafiles, and documentation of all corrections made to the data . The data management system will

be backed up on a daily basis . AREVA will then turn all original survey records over to Boeing

with the final data report.


HDMSE00576770



5. QUALITY ASSURANCE AND QUALITY CONTRO L

AREVA's Quality Assurance/Quality Control (QA/QC) Programs ensure that all quality andregulatory requirements are satisfied . A ll activities affecting quality are controlled by proceduresand the Quality Assurance Project Plan for SETF Surveys, Rev 0, March 2007, AREVA(QAPP) . These documents include the following Quality Control measures as an integral part of

the survey process .

5.1 General Provision s

5.1 .1 Selection of Personnel

Project management and supervisory personnel are required to have extensive experience with

AREVA procedures and the QA/QC plan and be familiar with the requirements of this Survey

and Sampling Plan . Management must have prior experience with the radionuclide(s) of

concern and a working knowledge of the instruments used to detect the radionuclides on site .

AREVA will select supervisory personnel to direct the survey based upon their experience and

familiarity with the survey procedures and processes . Likewise, Health Physics technicians who

will perform the surveys will be selected based upon their qualifications and experience .

5 .1 .2 Written Procedure s

All survey tasks that are essential to survey data quality will be controlled by standard operating

procedures (SOPs) and this plan . A list of plans and procedures is provided in the QAPP .

5 .1 .3 Instrumentation Selection, Calibration, and Operation

AREVA has selected instruments proven to reliably detect the radionuclides present at theSETF facility . Instruments will be calibrated by AREVA qualified vendors under approvedprocedures using calibration sources traceable to the NIST . All detectors are subject to dailyresponse checks when in use .

Procedures for calibration, maintenance, accountability, operation, and quality control ofradiation detection instruments implement the guidelines established in American NationalStandard Institute (ANSI) standard ANSI N323-1978 and ANSI N42 .17A-1989 .

5 .1 .4 Survey Documentation

The survey packages will be the primary method of controlling and tracking the hard copy

records of survey results . Records of surveys will be documented and maintained in the surveypackage for each area (or survey unit) according to AREVA procedures . Each survey

measurement will be identified by the date, technician, instrument type and serial number,

detector type and serial number, location code, type of measurement, mode of instrumen t


HDMSE00576771



operation, and Quality Control (QC) sample number, as applicable .

5.1 .5 Chain of Custody

Procedures establish responsibility for the custody of samples from the time of collection untilresults are obtained . All samples shipped off site for analysis will be accompanied by a chain-of-custody record to track each sample.

5.1 .6 Independent Review of Survey Result s

The survey package and survey data from each area will receive an independent review to

verify all documentation is complete and accurate .

5.2 Training

All project personnel will receive site-specific training to identify the specific hazards present in

the work and survey areas . Training will also include a briefing and review of this Plan,AREVA procedures, the QAPP and the Site Health and Safety Plan (HASP) . Copies of all

training records will be maintained on site through the duration of on-site activities .

During site orientation and training, survey personnel will become familiar with site emergencyprocedures . In the event of an emergency, personnel will act in accordance with all applicable

site emergency procedures and the HASP .

5.3 Sample Analysi s

In order to meet the MARSSIM objective for variance and precision, the survey team will

perform quality assurance checks on 5% of all sample analyses . The QC samples will include

split samples and/or duplicate or replicate samples of each type of sampled material (e .g. soil,concrete) obtained and analyzed. Split samples will be analyzed if an ample amount of material

is collected in a sample . The sample will be homogenized and split into two separate samples

for analysis . Duplicate or replicate samples are obtained by using the same sampling procedure

at a point directly adjacent to the original sample location . The location of the samples to be

duplicated shall be chosen such that an adequate number of samples will be collected to achieverequirements. Each duplicate sample shall undergo the same analyses as the initial sample .

Bias in the sample analysis process will be determined quantitatively by the analysis of blanksamples, matrix spike sample and/or laboratory control sample (LCS) spiked by the analyticallaboratory. In order to meet the MARSSIM objective for variance in bias, the AREVAEnvironmental Laboratory will perform quality assurance checks on 5% of all sample analysesperformed for each type of sample and analytical analysis performed. The AREVA E-LabQA/QC program will be in effect for the analysis of samples .


HDMSE00576772



6. SURVEY REPORT

AREVA may begin preparing the Survey Data Report during the surveys . General informationcan be drafted early to expedite report preparation when work is completed . The report will

contain brief descriptions of the site and the surveys performed, photographs of the survey andsample locations as necessary, and survey results in tabular and graphical form .

AREVA will submit a draft data report to Boeing for comment after completing site activities

and receiving all sample analyses . The final report will be submitted the DHS-RHB following

resolution of all comments .


HDMSE00576773



7. REFERENCE S

7 .1 DOE Order 5400 .5, Radiation Protection of the Public and the Environment

7 .2 Policy on Decommissioning of Department of Energy Facilities Under the

Comprehensive Environmental Response , Compensation, and Liability Act

(CERCLA), May 22, 199 5

7 .3 Executive Order No. D-62-02, Cleanup and Abatement Order (CAO) No . R9-2002-

330 : Moratorium on Disposal of Low-Level Radioactive Wastes, Governor, State ofCalifornia, issued September 29, 200 2

7 .4 NOOISRR140131, Approved Sitewide Release Criteria for Remediation of

Radiological Facilities at the SSFL, Boeing, 199 9

7 .5 Team Product Document No : RS-00025, Building 4024 Concrete Sampling, Boeing

12/15/04

7 .6 Historical Site Assessment of Area IV Santa Susana Field Laboratory, Ventura

County, Californi a

7 .7 Quality Assurance Project Plan for the SETF Survey, Rev 0, March 2007, AREVA

7 .8 Health and Safety Plan for the SETF Decommissioning, March 2007, ARE

7 .9 Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM),

Revision 1, August 2000, EPA402-R-97-016 Revl (NUREG-1575 Rev

7 .10 Multi-Agency Radiological Laboratory Analytical Protocols Manual (MARLAP),

Part I, July 2004, EPA402-B-04-001A (NUREG-1576 )

7 .11 NUREG-1501, Background as a Residual Radioactivity Criterion forDecommissioning, NRC, Draft Report for Comment August 199 4

7 .12 NUREG-1506, Measurement Methods for Radiological Surveys in Support of NewDecommissioning Criteria, NRC, August 199 5

7 .13 NUREG-1507, Minimum Detectable Concentrations with Typical Radiation Survey

Instruments for Various Contaminants and Field Conditions, NRC, Draft Report for

Comment August 199 5

7 .14 NUREG-1757, Consolidated NMSS Decommissioning Guidance, Vol . 1,Decommissioning Process for Materials Licensees, Decommissioning Process forMaterials Licensees, Revision 2, September 200 6


HDMSE00576774



7 .15 NUREG- 1757, Consolidated NMSS Decommissioning Guidance , Vol . 2,

Decommissioning Process for Materials Licensees , Characterization , Survey, andDetermination of Radiological Criteria , Revision 1, September 200 6

7 .16 American National Standard Institute (ANSI) Standard ANSI N323-1978, Radiation

Protection Instrumentation Test and Calibration . "

7 .17 ANSI N42.17A-1989, American National Standard Performance Specifications forHealth Physics Instrumentation - Portable Instrumentation for Use in Normal

Environmental Conditions - Descriptio n


HDMSE00576775



8. ATTACHMENT S

Attachment 1 : SETF Site Survey Areas and Survey Units

Attachment 2 : SETF Site Plan

Attachment 3 : SETF First Floor Plan

Attachment 4 : SETF Sub Grade Test Cell Complex Plan

9. APPENDICES

Team Product Document No : RS-00025, Building 4024 Concrete Sampling, performed under

the Closure of ETEC (R21-RS) Program


HDMSE00576776


Confirinatory Survey

Attachment 1

SETF Site Survey Areas and Survey Units

Sample And Analysis Plan

Page A- 1 -

Survey Area Type an dClassification

SurveyArea No . Survey Area Description

SurveyUnit No . Survey Unit Description

A - Impacted Environ s

Class 1 Survey Units A4024 None NA

Class 2 Survey Units A4024 None NA

Class 3 Survey Units A4024 Environs Adjacent to SETFFacility Building 4024

301C1 Surface Soil Area s

B - Non-Impacted Environs B4024 Environs Outside Class 3 Areas 401C1 Surface Soil Area s

C - Impacted Structure s

Class 1 Survey Units C4024 Building 4024 Interior Surfaces o fTest Cell B-102

1O1C1 Floor, walls and ceiling

C4024 Building 4024 Interior Surfaces o fTest Cell B-104

102C1 Floor, walls and ceiling

Class 2 Survey Units C4024 Building 4024 Interior Surfaces o fTest Cell B-103






Class 3 Survey Units C4024 Building 4024 Interior Surfaces o fRoom 101

301C1 Floor

C4024 Building 4024 Interior Surfaces o fRoom 102 thru 108

302C1 Floor

C4024 Building 4024 Interior Surfaces o fRoom 109 and 110

303C1 Floor



C4024 Building 4024 Interior Surfaces o fRoom 113



306C1 Floor

D - Non-Impacted Structures D4024 Building 4024 Exterior Surfaces 401C1 Exterior Walls

D4024 Building 4024 Exterior Surfaces 402C1 Roof

D4024 Building 4024 Exterior Surfaces 403C1 Asphalt Drives, ConcreteSidewalk s

E - Impacted Systems None NA NA NA

F - Non-Impacted Systems None NA NA NA

G - Background Structures G4000 Background Reference Area 401B1 Building Surfaces Unaffected byRadiological Operation s

H - Background Environs H4000 Background Reference Area 401B1 Environmental Area Unaffectedby Radiological Operations


HDMSE00576777


Confirmatory Survey

Attachment 2

SETF Site Plan

SETFSAP March 30, 2007, RevO final .doc


Page A- 1 -

HDMSE00576778

-"' ----- -

VF r ,4.-0,2z " 6 1 mot)4725 (81- )

;,'-,`26


Confirmatory Survey

Attachment 3

SETF First Floor Pla n

- -- --------- ---- --------f .) \ \,,..~; f \



Page A- 1 -

---------- ------ --------

HDMSE00576779


Confirmatory Survey

Attachment 4

SETF Sub Grade Test Cell Complex Pla n



Page A- 2 -

HDMSE00576780


Confirmatory Survey Appendix Page - 1 -

Appendix A

Team Product Document No: RS-00025,

Building 4024 Concrete Sampling ,

Performed under the Closure of ETEC (R21-RS) Progra m

SETF_SAP March 30, 2007, RevO final .docMarch 200 7

HDMSE00576781

Team Product Documen t

GO Number S/A Number Page 1 of Total Pages Rev. Ltr/Chg . No. NumberSee Summary of Chg .

97055 03731 15 15 NEW RS-0002 5Program Titl eClosure of ETEC (R21-RS )Document TitleBuilding 4024 Concrete SamplingDocument Type Related DocumentsFinal ReportOriginal Issue Date Release Date Approvals Date12/15/2004 RELEASE 12/15/04 CV P. D . RutherfordPrepared By/Date Dept . Mail/Addr D . L. Konce lE . R. McGinnis 12/08/2004 641 T038 B . D . Sujata

IR&D Program? Yes ❑ No ❑

If Yes, Enter Authorization No .

Distribution AbstractName Mail Addr . This document provides the results for concrete samplin g

J . G . Barnes T038 in Building 4024 conducted in 2003 . The results are usedM . E. Lee T038 to predict which concrete needs to be removed withR . A. Marshall T038 radiological controls and buried as radioactive waste an dE . R. McGinnis T038 which can be done without radiological controls an dD . L . Koncel T038 buried in a Class 1 landfill . The criteria for determinin gP . D . Rutherford T038 this are the Derived Concentration Guideline Limit sB . D . Sujata T038 (DCGLs) which are volumetric release limits for soil . AnyR . D . Meyer T038 volume of concrete containing higher levels than th eRadiation Safety Files T057 DCGLs for soil release will require contamination contro lFacility Release Files T057 methods during removal .

Complete Document Reserved for Proprietary/Legal NoticeNo Asterisk, Title Page/Summaryor Change Page Only .

Rocketdyne Form 651-F REV . 6-99

HDMSE00576782

RS-00025 Page 2 of 1 5

Table of Contents

1 .0 Executive Summary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 32.0 Scope . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .33 .0 Sampling Methodology . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 44.0 Sample Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 55 .0 Conclusion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 126.0 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 3

List of Tables

Table 1 : Core Tracking Log . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7Table 2 : Cobalt-60 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14

Table 3 : Europium-152 Results . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 5

List of Figure s

Figure 1 : Concrete Core and Discs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4

Figure 2 : Map of General Core Locations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6Figure 3 : Concrete Removal Diagram . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12

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RS-00025 Page 3 of 1 5

1.0 Executive Summary

In June of 2003 concrete core samples were taken in Building 4024 to help determinethe safest and most cost effective method for demolishing the building . Cores weretaken in 21 locations in the reactor test cell, decon gallery and operating galleryareas . Deep cores were taken in the East and West reactor cells and 1" thick discsfor analysis were sliced off at 1", 16" and 30" depths . Shallow, 1" cores were takenin the areas outside the test cells .

These discs were analyzed by gamma spectroscopy and two of the highest activitysamples (# 54 and 57, see Table 1) were sent offsite for tritium, iron-55 and nickel-63 analysis at Eberline Services Laboratory along with 4 other concrete and bedrocksamples .

The 1" depth samples ranged from no detectable activity (NDA) in the areas outsidethe cells to a maximum of 105 pCi/g europium-152 and 9 .4pCi/g cobalt-60 in theareas inside the cells . No europium-154, tritium, iron-55 or nickel-63 was detectedin any of the samples analyzed at Eberline Services .

All 16" and 30" depth samples analyzed were NDA with the exception of onelocation, core # 21, which indicated 3 .7 pCi/g of Eu-152 at the 16" depth . The 16"

depth sample of core number 1 was counted for a long duration to lower theminimum detectable activity (MDA) . This count indicated 0 .4 pCi/g Eu-152 andNDA Co-60 . This analysis was done to determine how far below MDA for a

standard count time (~ 0 .7 pCi/g for Eu-152 and 0.2 pCi/g for Co-60) one of the16" samples actually was .

This document summarizes the results of the sampling and the conclusions drawn

from the results .

2.0 Scope

In 1978, concrete cores were taken in the East and West cells of Building 4024 toquantify the extent of activation products formed within the concrete and rebar

during the SNAP reactor experiments in the 1960s . A partial Decontamination and

Decommissioning (D&D) of facility equipment was subsequently performed(References 1 and 2) . This involved only the removal of facility equipment and

process systems. The reactor cell concrete and aluminum liner were left intact .

In 1992, further D&D was being considered, and the proposed unrestricted userelease limits required isotopic analysis of the concrete . Additional core sampleswere removed and analyzed by gamma spectroscopy . No samples were taken above8 feet on the walls or on the ceiling . Also no samples were taken outside of the tworeactor cells . The 1992 data was not used in the current analysis ; however, sampleswere taken in 2003 adjacent to the most activated locations from the 1992 sampleeffort and were used to confirm decay equations (see Tables 2 and 3) .

HDMSE00576784

RS-00025 Page 4 of 1 5

Definitive sampling was completed in 2003 to predict how much of the buildingstructure would require engineering controls to prevent workplace hazards andenvironmental releases of radioactivity if the building was demolished b yrubblization . This sampling endeavor included all surfaces of the two reactor cellsand the basement areas outside the cells .

3.0 Sampling Methodology

General areas to be sampled were pre-selected by the Radiation Safety Engineerbased on locations most likely to have become activated during reactor operations .The work crew was provided with an Engineering Work Request (EWR) procedure(Ref. 3) which included a map of the general sample locations (Figure 2) . TheRadiation Safety Technician utilized a gamma detector to pinpoint the highestsurface measurement at each location and marked each spot for concrete coring .Each location distance was measured from location 0, 0 in a two dimensional gridcoordinate system and subsequently logged .

Table 1 is the core tracking log produced by the work crew .

A three-inch diameter concrete core saw was used to remove a core at each location

to a depth of three feet. Three one-inch thick discs were sawed off of each core at 1,15 and 30 inches depth and carefully labeled and bagged (Figure 1) .

Sample 0" to 1 "

X=Core #

X-1 6

X-30 X-29 Fragment

Fragmen t

SamnIP 7A" to 'in-

Sample 15" to 16"

Figure 1 : Concrete Core and Discs

At selected locations, where possible, samples were taken of the soil or bedrock aftercoring through the wall at the sampling location . All discs and soil/bedrock weretransferred to the gamma spectroscopy laboratory for analysis . Six disc andsoil/bedrock samples with the highest radioactivity were sent to an outsidelaboratory, Eberline Services, for tritium (H-3), iron-55 (Fe-55) and nickel-63 (Ni-63) analysis .

HDMSE00576785

RS-00025 Page 5 of 1 5

4.0 Sample Results

Two gamma-emitting isotopes, cobalt-60 (Co-60) and europium-152 (Eu-152), weredetectable in the sample lot . The activity varied depending on location and depth .The samples were counted for 2000 seconds, which achieved MDAs of less than10% of the soil DCGLs for Co-60, Eu-152 and Eu-154 (Reference 4)

It became apparent that the majority of the 15 to 16" and 29" to 30" depth sampleswould be less than minimum detectable activity with a 2000 second count time . Toverify this, several of the 15 to 16" depth samples that had the highest activity at 0 to1" depth were counted for 7,000 seconds . Except for cores 1 and 21(0 .4 and 3 .7pCi/g Eu-152 respectively), all were less than MDA .

At the highest activity 1" depth location, the soil/bedrock behind the core wascounted for 50,000 seconds . It indicated no detectable activity so no further samplesof bedrock behind the cores required analysis .

The activity of 1 inch depth cores ranged from no detectable activity to 105 pCi/gEu-152 and 9.4 pCi/g Co-60 . It would take 61 .5 years for the 105 pCi/g of Eu-152 todecay to just below its Derived Concentration Guide Limit (DCGL) (release limit forsoil) of 4 .51 pCi/g . By that time, the Co-60 would have decayed to 0 .15% of itsDCGL (1 .94 pCi/g) (Reference 4) .

Tables 2 and 3 list the results of gamma spectroscopy for Co-60 and Eu-152 . No Eu-154, H-3, Fe-55 or Ni-63 was detected in any of the samples analyzed .

HDMSE00576786

RS-00025 Page 6 of 1 5

East Cell Floor RReference Locator0,0 Decon Gallery Floor Peference Locator 0, 0

Wall) 2 0

Low

(Floor) 2

3 (Ceiling) 5

Wa 11,

Wal l

East Cel l

S

6

Lo w

Wal l

Roor) I2 9

0 (Ceiling )

WestCell Floor Reference Locator 0, 0

W

oor) 1 6

E

N

all

Wall) 1

Roor) 12

1 7

14 15 'Wall ~

Roor 13

Decon Galle ry West Cel l

Operating Gallery

Operating Gallery Floor Reference Locator 0,0

Roa r

Wall 18Stairs

Wall

Wal l

Floorn I or 19

J I Wall

U-

Service Gallery

Service Gallery RoorF;bference Locator0, 0

Figure 2: Map of General Core Locations (numbers indicate core numbers)

Wall) 2

HDMSE00576787

RS-00025 Page 7 of 1 5

Table 1 : Core Tracking Log

U = U (from floor) N=North W=West R=Ri ht LOC = rid locator

Ending Depth Tracking LOC A ft LOC B ft Sample Slice dCore # Location Sample # Inches Numbers Date B Comments

East Cell, East 7' 9" R 5' 1" U Rocky1 Wall -1992 024-03-0001 1 0-1 6/19/2003 Serena

East Cell, East 7' 9" R 5' 1" U Rocky1 Wall -1992 024-03-0002 16 15 .0-16 6/19/2003 Serena

East Cell, East 7' 9" R 5' 1" U Rocky1 Wall-1992 024-03-0003 30 29-30 .0 6/19/2003 Serena

Behind East Cell, 7' 9" R 5' 1" U Rocky1 East Wall-1992 024-03-0004 38 37-38 .0 6/19/2003 Serena Bedrock/Soi l

14' 1" N 9' 1" W Rocky2 East Ce ll, Floor 024-03-0005 1 0-1 6/19/2003 Serena

14' 1"N 9' 1"W Rocky2 East Ce ll, Floor 024-03-0006 16 15 .0-16 6/19/2003 Serena

14' 1"N 9' 1"W Rocky2 East Ce ll, Floor 024-03-0007 30 29-30 .0 6/19/2003 Serena

Under East Cell, 14' 1"N 9' 1"W Rocky2 Floor 024-03-0008 92 91-92 .0 6/19/2003 Serena Bedrock/Soi l

East Cell, North 2' 3" R 11' 5" U Rocky3 Wall - High 024-03-0009 1 0-1 6/19/2003 Serena

East Cell, North 2' 3" R 11' 5" U Rocky3 Wall-High 024-03-0010 16 15 .0-16 6/19/2003 Serena

East Cell, North 2' 3" R 11' 5" U Rocky3 Wall-High 024-03-0011 29 .5 28 .5-29 .5 6/19/2003 Serena

East Cell, South 12' 7" R 7' 11" U Rocky4 Wall - Hi 024-03-0012 1 0-1 6/19/2003 Serena

East Cell, South 12' 7" R 7' 11" U Rocky4 Wall-High 024-03-0013 16 15 .0-16 6/19/2003 Serena

HDMSE00576788

RS-00025 Page 8 of 1 5

Ending Depth Tracking LOC A ft LOC B ft

Core # Location Sample # Inches Numbers Date Sampled B Comments

East Cell, South 12' 7" R 7' 11" U Rocky4 Wall - Hi 024-03-0014 30 29-30 .0 6/19/2003 Serena

15'8"N 5'7"W Rocky5 East Ce ll, Ceiling 024-03-0015 1 0-1 6/19/2003 Serena

15'8"N 5'7"W Rocky5 East Ce ll, Ceiling 024-03-0016 16 15 .0-16 6/19/2003 Serena

15'8"N 5'7"W Rocky5 East Cell, Ceiling 024-03-0017 30 29-30 .0 6/19/2003 Serena

West Cell , West 17' 7" R 4' 10" U Rocky6 Wall-1992 024-03-0018 1 0-1 6/19/2003 Serena

West Cell, West 17' 7" R 4' 10" U Rocky6 Wall-1992 024-03-0019 12 11-12 .0 6/19/2003 Serena

West Cell, West 17' 7" R 4' 10" U Rocky6 Wall -1992 024-03-0020 30 29-30 .0 6/19/2003 Serena

Behind West Cell, 17' 7" R 4' 10" U Rocky6 West Wall-1992 024-03-0021 38 37-38 .0 6/19/2003 Serena Bedrock/Soi l

11'8"N 9'8"W Rocky7 West Cell , Floor 024-03-0022 1 0-1 6/19/2003 Serena

11'8"N 9'8"W Rocky7 West Cell , Floor 024-03-0023 15 14-15 .0 6/19/2003 Serena

11'8"N 9'8"W Rocky7 West Cell , Floor 024-03-0024 30 29-30 .0 6/19/2003 Serena

,Under West Cell 11' 8" N 9' 8" W R ocky7 Floor 024-03-0025 82 81-82 .0 6/19/2003 Serena Bedrock/Soi l

West Cell, South 11' 10" R 12' 9" U Rocky8 Wall - Hi 024-03-0026 1 0-1 6/19/2003 Serena

West Cell, South 11' 10" R 12' 9" U Rocky8 Wall - High 024-03-0027 16 15 .0-16 6/19/2003 Serena

HDMSE00576789

RS-00025 Page 9 of 1 5



West Cell, South 11' 10" R 12' 9" U Rocky8 Wall - Hi 024-03-0028 30 29-30 .0 6/19/2003 Serena

West Cell, North 12' 2" R 12' 9" U Rocky9 Wall - High 024-03-0029 1 0-1 6/19/2003 Serena

West Cell, North 12' 2" R 12' 9" U Rocky9 Wall - Hi 024-03-0030 16 15 .0-16 6/19/2003 Serena

West Cell, North 12'2"R 12'9"U Rocky9 Wall - Hi 024-03-0031 30 29-30 .0 6/19/2003 Serena

West Cell, Ceiling 11' 11" 12' 5" Rocky10 Shield Plug 024-03-0032 1 0-1 6/19/2003 Serena

West Cell, Ceiling 11' 11" 12' 5" Rocky

10 Shield Plug 024-03-0033 15 14-15 .0 6/19/2003 Serena

West Cell, Ceiling 11' 11" 12' 5" Rocky10 Shield Plug 024-03-0034 29 28-29 .0 6/19/2003 Serena

Decon Gallery, 12' 5"R 10' 4"U Rocky11 South Wall 024-03-0035 1 0-1 6/19/2003 Serena

Decon Gallery, 12' 5"R 10' 4"U Rocky11 South Wall 024-03-0036 16 15 .0-16 6/19/2003 Serena

Decon Gallery, 12' 5"R 10' 4"U Rocky11 South Wall 024-03-0037 27 26-27 .0 6/19/2003 Serena

Decon Gallery, 5' 7" N 11'6" W Rocky12 Floor 024-03-0038 1 0-1 6/19/2003 Serena

Decon Gallery, 57 N 11'6" W Rocky12 Floor 024-03-0039 16 15 .0-16 6/19/2003 Serena

Decon Gallery, 5'7" N 11' 6" W Rocky12 Floor 024-03-0040 30 29-30 .0 6/19/2003 Serena

Decon Gallery, 23' 0" N 8' 0" W Rocky13 Floor 024-03-0041 1 0-1 6/19/2003 Serena

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Core # Location Sample # Inches Numbers Date Sampled By Comments

Decon Gallery, 23' 0" N 8' 0" W Rocky13 Floor 024-03-0042 15 14-15 .0 6/19/2003 Serena

Decon Gallery, 23' 0" N 8' 0" W Rocky13 Floor 024-03-0043 30 29-30 .0 6/19/2003 Serena

Decon Gallery, 20' 2"R 12' 1 "U Rocky14 East Wall 024-03-0044 1 0-1 6/19/2003 Serena

Decon Gallery, 20' 2"R 12' 1 "U Rocky14 East Wall 024-03-0045 15 14-15 .0 6/19/2003 Serena

Decon Gallery, 20' 2"R 12' 1 "U Rocky14 East Wall 024-03-0046 30 29-30 .0 6/19/2003 Serena

Decon Gallery, 19' 3"R 10' 2"U Rocky15 West Wall 024-03-0047 1 0-1 6/19/2003 Serena

Decon Gallery, 19' 3"R 10' 2"U Rocky15 West Wall 024-03-0048 15 14-15 .0 6/19/2003 Serena

Decon Gallery, 19' 3"R 10' 2"U Rocky15 West Wall 024-03-0049 30 29-30 .0 6/19/2003 Serena

Operating Gallery 14' 10" N 8' 4" W Rocky16 Floor 024-03-0050 1 0-1 6/19/2003 Serena

Operating Gallery 14' 7" N 14' 3" W Rocky17 Floor 024-03-0051 1 0-1 6/19/2003 Serena

Operating Gallery, 33' 2" R 4' 2" U Rocky18 North Wall 024-03-0052 1 0-1 6/19/2003 Serena

Service Gallery, 5' 10" N 3' 8" W Rocky19 Floor 024-03-0053 1 0-1 6/19/2003 Serena

East Cell Hallway, 7' 5"R 10' 1/2"U Rocky

20 South Wall 024-03-0054 1 0-1 6/19/2003 Serena

East Cell Hallway, 75"R 10' 1/2"U Rocky20 South Wall 024-03-0055 16 15 .0-16 6/19/2003 Serena

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East Cell Hallway, 7' 5"R 10' 1/2"U Rocky

20 South Wall 024-03-0056 27 26-27 .0 6/19/2003 SerenaWest Cell 10' 7"R 14' 3"UHallway, South Rocky

21 Wall 024-03-0057 1 0-1 6/19/2003 Serena

West Cell 10' 7"R 10' 7"UHallway, South Rocky

21 Wall 024-03-0058 16 15 .0-16 6/19/2003 Serena

West Cell 10' 7"R 10' 7"UHallway, South Rocky

21 Wall 024-03-0059 24.25 23 .25-24 .25 6/19/2003 Serena

West Cell 10' 7" R 10' 7"UHallway, South Rocky

21 Wall 024-03-0060 24.25 23 .25-24 .25 6/19/2003 Serena Soil Sample

HDMSE00576792

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5.0 Conclusio n

These conclusions are based on comparing the results to the soil DCGLs . The resultsindicate that all of the areas outside of the two cells may be rubblized in the open airwithout worker safety or environmental release concerns . The first 15" depth of thestructural surfaces in both of the cells should be removed with the building stil lstanding with portable ventilation in use or using wet removal methods . This wouldinclude the walls, ceiling and floors in these areas . The rest of the cells may bedemolished after the upper building is torn down . The shaded areas of Figure 3represent the areas that should be removed with contamination control measures inplace .

4024 Basement Activated Concrete Remova l

9iaded areas need 15" on al lwalls, floors and ceilings rubbelizedin a controlled environment becauseof EPA NEgIAF requirements. . Wet sawing

may be done in open air based on 4059experience . The rest of the building afterthatmay be rubbleized in the open air .

Figure 3 : Concrete Removal Diagram

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6.0 References

1 . A. M. Stelle, Building T024 (SETF) Facilities Dismantling Plan, 7/26/1977

2 . D. A. Speights, Radiological Survey Results-Release to Unrestricted Use,Building 024, SSFL, 11/28/197 8

3 . E . R. McGinnis, Rocketdyne Engineering Work Request # R9036358, 4024Radiation Safety Instructions for Sampling, 3/14/200 3

4 . N001 SRR140131, "Approved Site wide Release Criteria for Remediation ofRadiological Facilities at the Santa Susana Field Laboratory", February 18, 1999

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Table 2: Cobalt-60 Results

Ending Depth Activity Error MDACore Location Sample # Inches Isotope Ci/ Ci/ Ci/ Detect

1 East Cell, East Wall-1992 0024030001 1 Co-60 2 .418E+00 2.581E-C1 1 .71E-0 1East Cell, East Wall-1992 0024030001 1 Co-60 2 .460E+00 2.533E-C1 1 .31E-0 1

1 East Cell, East Wall-1992 0024030002 16 Co-60 7.050E-02 N/A 1 .41E-01 N DEast Cell, East Wall-1992 0024030003 30 Co-60 3.840E-02 N/A 7 .68E-02 N D

1 East Cell, East Wall-1992 0024030003 30 Co-60 5 .050E-02 N/A 1 .01E-01 N DBehind East Cell, East Wall-1992 0024030004 38 Co-60 2 .580E-02 N/A 5 .16E-02 N DBehind East Cell, East Wall-1992 024030004L 38 Co-60 1 .965E-03 N/A 3 .93E-03 N D

1 East Cell, East Wall-1992 0024030002 16 Co-60 6 .100E-02 N/A 1 .22E-01 N DEast Cell, East Wall-1992 0024030002 16 Co-60 2.820E-02 6.147E-C3 1 .36E-0 2

2 East Cell, Floor 0024030005 1 Co-60 2 .135E+00 1 .852E-C1 1 .19E-0 12 East Cell, Floor 0024030005 1 Co-60 3 .661E+00 3.204E-C1 1 .857E+01 N D3 East Cell, North Wall-High 0024030009 1 Co-60 1 .310E+00 1 .821E-C1 1 .559E-0 13 East Cell, North Wall-High 0024030009 1 Co-60 1 .025E+00 1 .781E-C1 1 .572E-0 14 East Cell, South Wall-High 0024030012 1 Co-60 2 .272E+00 2 .491E+00 2 .23E-0 14 East Cell, South Wall-High 0024030012 1 Co-60 2 .155E+00 2 .405E+00 2 .04E-0 15 East Cell, Ceiling 0024030015 1 Co-60 1 .069E+00 1 .565E+00 1 .58E-0 15 East Cell, Ceiling 0024030015 1 Co-60 9.332E-01 1 .489E-C1 1 .747E-0 16 West Cell, West Wall-1992 0024030018 1 Co-60 2 .792E+00 2 .78E-01 1 .88E-0 16 West Cell, West Wall-1992 0024030016 1 Co-60 2 .271E+00 0 .02467 1 .46E-0 16 Behind West Cell, West Wall-1992 0024030021 38 Co-60 3 .665E-02 N/A 7 .33E-02 N D7 West Cell, Floor 024030022A 1 Co-60 2 .276E+00 2.500E-C1 1 .518E-0 17 West Cell, Floor 0240300226 1 Co-60 1 .740E+00 2.184E-C1 1 .87E-0 18 West Cell, South Wall - High 024030026A 1 Co-60 9 .121E+00 6.138E-C1 1 .568E-0 18 West Cell, South Well - High 024030026B 1 Co-60 9 .392E+00 6 .27E-01 3 .04E+0 08 West Cell, South Wall - High 024030027 16 Co-60 1 .040E-01 N/A 2 .08E-01 N D9 West Cell, North Wall - High 024030029A 1 Co-60 5 .018E+00 4.107E-C1 2 .503E-0 19 West Cell, North Wall - High 024030029B 1 Co-60 4 .996E+00 4 .068-01 2 .255E-0 19 West Cell, North Wall - High 024030030 16 Co-60 1 .095E-01 N/A 2 .190E-01 N D10 West Cell, Ceiling Shield Plug 024030032A 1 Co-60 7.150E-02 N/A 1 .43E-01 N D11 Decon Gallery, South Wall 024030035A 1 Co-60 7 .300E-02 N/A 1 .46E-01 N D12 Decon Gallery, Floor 024030038A 1 Co-60 7 .550E-02 N/A 1 .51E-01 N D13 Decon Gallery, Floor 024030041 1 Co-60 7.000E-02 N/A 1 .40E-01 N D14 Decor Gallery, East Wall 024030044 1 Co-60 5.850E-02 N/A 1 .17E-01 N D15 Decon Gallery, West Wall 024030047 1 Co-60 7 .750E-02 N/A 1 .55E-01 N D16 Operating Gallery Floor 024030050 1 Co-60 5 .850E-02 N/A 1 .17E-01 N D17 Operating Gallery Floor 024030051 1 Co-60 8 .250E-02 N/A 1 .65E-01 N D18 Operating Gallery, North Wall 024030052 1 Co-60 7.150E-02 N/A 1 .43E-01 N D19 Service Gallery, Floor 024030053 1 Co-60 7.250E-02 N/A 1 .45E-01 N D20 East Cell Hallway, South Wall 024030054A 1 Co-60 1 .350E+00 2.055E-C1 1 .79E-0 120 East Cell Hallway, South Wall 0240300548 1 Co-60 1 .620E+00 2 .28E-01 2 .92E-0 120 East Cell Hallway, South Wall 024030055 16 Co-60 6.950E-02 N/A 1 .39E-01 N D20 East Cell Hallway, South Wall 024030056 27 Co-60 3.905E-02 N/A 7 .81E-02 N D21 West Cell Hallwa ,South Wall 024030057A 1 Co-60 3 .878E+00 3 .36E-01 1 .95E-0 121 West Cell Hallwa ,South Wall 024030057B 1 Co-60 4 .002E+00 3.413E-C1 1 .71E-0 121 West Cell Hallwa , South Wall 024030058 16 Co-60 1 .025E-01 N/A 2 .05E-01 N D21 West Cell Hallwa , South Wall 024030059 24 Co-60 8.200E-02 N/A 1 .64E-01 N D21 Behind West Cell Hallway, South Wall 024030060 30 Co-60 8 .950E-03 N/A 1 .79E-02 N D

mi nmax

average

1 .965E-03

9 .392E+0 01 .477E+00

3 .930E-0 3

2 .190E-0 11 .259E-0 1

NA in error column indicates sample was < MDA (results entered as 0.5*MDA) .

ND = Non-detect .

A = front side, B = backside . There were no significant differences between the twosides, so that method was abandoned .

LC = Long Count time .

1992 in the "Location" column indicates the sample was taken adjacent to one of thehotter 1992 samples .

Co-60 DCGL = 1 .94 pCi/g (Reference 4) . MAX MDA 10% DGGL .

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Table 3 : Europium-152 Result s

Ending Depth Activity Error MDACore Location Sample # Inches Isotope Ci/ Ci/ Ci/ Detect

1 East Cell, East Wall-1992 024030001A 1 Eu-152 3 .451E+01 1 .462E+00 7 .26E-0 11 East Cell, East Wall-1992 024030001 B 1 Eu-152 3 .231 E+01 1 .344E+00 5 .11 E-0 11 East Cell, East Wall-1992 024030002A 16 Eu-152 1 .165E-01 N/A 2 .33E-01 N D1 East Cell, East Wall-1992 024030003A 30 Eu-152 4 .390E-02 N/A 8 .78E-02 N D1 East Cell, East Wall-1992 024030003B 30 Eu-152 4 .955E-02 N/A 9 .91E-02 N D1 East Cell, East Wall-1992 024030003B 30 Eu-152 3 .615E-02 N/A 7 .23E-02 N D1 Behind East Cell, East Wall-1992 024030004 38 Eu-152 5 .700E-02 N/A 1 .14E-01 N D1 Behind East Cell, East Wall-1992 024030004LC 38 Eu-152 1 .304E-01 N/A 5 .80E-0 31 East Cell, East Wall-1992 024030002B 16 Eu-152 1 .075E-01 N/A 2 .15E-01 N D1 East Cell, East Wall-1992 024030002C 16 Eu-152 4 .113E-01 2.318E-C2 2 .54E-0 22 East Cell, Floor 024030005A 1 Eu-152 2 .260E+01 9.18E-01 4 .04E-0 12 East Cell, Floor 024030005B 1 Eu-152 3 .723E+01 1 .51 E+00 7 .72E-0 13 East Cell, North Wall-High 024030009A 1 Eu-152 1 .688E+01 8.072E-C1 4 .751E-0 13 East Cell, North Wall-High 024030009B 1 Eu-152 1 .625E+01 7.862E-C1 4 .646E-0 14 East Cell, South Well-High 024030012A 1 Eu-152 3 .023E+00 1 .281E+00 6 .11E-0 14 East Cell, South Wall-High 024030012B 1 Eu-152 2 .705E+00 1 .169E+00 7 .19E-0 15 East Cell, Ceiling 024030015A 1 Eu-152 1 .388E+01 6.857E-C1 4 .02E-0 15 East Cell, Ceiling 024030015B 1 Eu-152 1 .387E+01 6.942E-C1 4 .329E-0 16 West Cell, West Wall-1992 024030018A 1 Eu-152 2 .973E+01 1 .260E+00 6 .76E-0 16 West Cell, West Wall-1992 024030018B 1 Eu-152 2 .556E+01 1 .113E+00 5 .098E-0 16 Behind West Cell, West Wall-1992 024030021 38 Eu-152 6 .400E-02 N/A 1 .28E-01 N D7 West Cell, Floor 024030022A 1 Eu-152 2 .194E+01 9.943E-C1 5 .455E-0 17 West Cell, Floor 024030022B 1 Eu-152 1 .834E+01 8.769E-C1 5 .36E-0 1

8 West Cell, South Wall - High 024030026A 1 Eu-152 7 .4510E+01 2 .805E+00 9 .249E-0 18 West Cell, South Wall - High 024030026B 1 Eu-152 7 .758E+01 2.91E+00 1 .049E+008 West Cell, South Wall - High 024030027 16 Eu-152 1 .480E-01 N/A 2 .960E-01 N D9 West Cell, North Wall - High 024030029A 1 Eu-152 4 .566E+01 1 .830E+00 7 .460E-0 19 West Cell, North Wall - High 024030029B 1 Eu-152 4 .535E+01 1 .817E+00 7 .620E-0 19 West Cell, North Wall - High 024030030 16 Eu-152 1 .665E-01 N/A 3 .330E-01 N D10 West Cell, Ceiling Shield Plug 024030032A 1 Eu-152 6 .750E-02 N/A 1 .35E-01 N D11 Decon Gallery, South Wall 024030035A 1 Eu-152 1 .080E-01 N/A 2 .16E-01 N D12 Decon Gallery, Floor 024030038A 1 Eu-152 1 .040E-01 N/A 2 .08E-01 N D13 Decon Gallery Floor 024030041 1 Eu-152 1 .035E-01 N/A 2 .07E-01 N D

14 Decor Gallery, East Wall 024030044 1 Eu-152 9.750E-02 N/A 1 .95E-01 N D15 Decon Gallery, West Wall 024030047 1 Eu-152 1 .025E-01 N/A 2 .05E-01 N D16 Operating Gallery Floor 024030050 1 Eu-152 8 .400E-02 N/A 1 .68E-01 N D17 Operating Gallery Floor 024030051 1 Eu-152 8 .050E-02 N/A 1 .61E-01 N D18 Operating Gallery, North Wall 024030052 1 Eu-152 8.350E-02 N/A 1 .67E-01 N D19 Service Gallery, Floor 024030053 1 Eu-152 8.800E-02 N/A 1 .76E-01 N D20 East Cell Hallway, South Wall 024030054A 1 Eu-152 6 .229E+01 2.40E+00 1 .11E+0 020 East Cell Hallway, South Wall 024030054B 1 Eu-152 7 .490E+01 2.81 E+00 1 .06E+0 020 East Cell Hallway, South Wall 024030055 16 Eu-152 1 .110E-01 N/A 2 .22E-01 N D20 East Cell Hallway, South Wall 024030056 27 Eu-152 8.150E-02 N/A 1 .63E-01 N D21 West Cell Hallwa ,South Wall 024030057A 1 Eu-152 9 .452E+01 3 .406E+00 1 .09E+0 021 West Cell Hallwa South Wall 0240300576 1 Eu-152 1 .051E+02 3 .750E+00 9 .50E-0 121 West Cell Hallwa , South Wall 024030058 16 Eu-152 3 .678E+00 3.076E-C1 2 .10E-0 121 West CeII Hallwa , South Wall 024030059 24 Eu-152 1 .040E-01 N/A 2.08E-01 N D21 Behind West Cell Hallway, South Wall 024030060 30 Eu-152 2.202E-01 1 .290E-C2 2 .65E-02 2 .65E-0 2

mi nmax

average

3 .615E-021 .051E+0 2

1 .823E+01

5 .800E-0 3

3 .330E-0 1

1 .746E-0 1

NA in error column indicates sample was < MDA (results entered as 0 .5*MDA) .

ND = Non-detect .

A = front side, B = backside . There were no significant differences between the twosides, so that method was abandoned .

LC = Long Count time .

1992 in the "Location" column indicates the sample was taken adjacent to one of thehotter 1992 samples .

Eu-152 DCGL = 4 .51 pCi/g (Reference 4) . MAX MDA < 10% DCGL .

HDMSE00576796