ATTACHMENT 4 CONSUMERS ENERGY BIG ROCKPOINT

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ATTACHMENT 4CONSUMERS ENERGYBIG ROCKPOINTDOCKET NUMBERS 50-155 AND 72-043TRANSMITTAL OF RELOCATED SOIL SURVEY PACKAGES IN SUPPORT OF BIG ROCKPOINT PHASED LICENSE TERMINATIONCLASS 1 FINAL STATUS SURVEY RELEASE RECORD, 09C1 1,NORTH EAST PROTECTED AREAOctober 13, 200637 Pages

Class I Final Status SurveyRelease Record 09CllNorth East Protected AreaSURVEY PACKAGE CLOSUREFinal Status Survey Documentation is authorized for closure. All required reviews arecomplete and the evaluation of data results have satisfied the criteria established forunrestricted release.Date:Signed.tLo t-I 0(10I(EsSigned:IDate:/dc'V. J-Date:/-o(E'S Su-perintendent)Signed:(AP & ES Manager)'(-

.ASurvey Area RequirementsFinal Status Survey, Release Record 09C 11North East Protected AreaSurvey DescriptionFinal Status Survey 09C, 1 encompasses 1989 m2 at or below the grade elevation presentduring plant power operations in the north east section of the Protected Area. No materials ofplant origin remain in the survey area.HistoryDuring power operations the Protected Area supported the components and systems necessaryfor electrical generation. The location of Survey Unit 9 is adjacent to the transport route used tomove spent resin and filter media for radiological survey and offsite removal. Structures andenclosures formerly located in this area were once used for the storage of contaminatedmaterials. A detailed review of the history and radiological characterization of survey Unit 9 isprovided in Appendix 2B and 2E of the LTP (License Termination Plan).Current Radiological StatusScoping measurements and supporting surveys performed in the Protected Area followingremoval of subsurface components and demolition debris do not indicate the presence ofelevated levels of residual radioactivity in this survey area. Based on operational history andformer locations of radioactive systems and material transport pathways, the radiological statusof this survey unit is Class 1.Post-Construction ExpectationsFinal Status Survey 09C1 1 will be performed in the following activity sequence:1. Walkdown: Environmental Services Survey Group (ESSG) personnel will perform awalkdown assessment to ensure survey area preparations are complete and confirmthat the following post-construction expectations have been satisfied as applicable:" Groundwater and Surface water control is adequate" All construction debris has been removed from the survey area* The survey location status meets all applicable safety requirements2. Survey Area Isolation and Control: Control measures will be established to ensure thatany potential ongoing decommissioning activities in adjacent locations do not impact thecurrent survey area status. Isolation and control measures include postings, barriers,access points, and the evaluation of ongoing work activities in adjacent areas.Survey Area RequirementsFSS 09Ci 1Page 1 of 2

3. Survey Design and Execution: Survey design and execution will follow the Data QualityObjectives for 09C, 1 in accordance with the survey requirements established inprocedures RM-76, Final Status Survey Design and RM-77, Final Status SurveyImplementation, and LTP, Chapter 5. Survey size will be based on the statisticalrequirements of the Sign Test for Class 1 areas with soil samples collected in randomstart, systematic data point locations. Surface scanning will be performed with 100%survey area coverage. This survey will be conducted in accordance with approved BRPprocedures and follow the guidance of NUREG 1575.4. Data Quality Assessment: Isolation and control of the survey area will be maintaineduntil the survey Data Quality Assessment demonstrates that the regulatory requirementsfor unrestricted site release have been satisfied.Survey Area RequirementsFSS 09Ci 1Page 2 of 2

DATA QUALITY OBJECTIVESFinal Status Survey, Release Record 09C1 1North East Protected AreaSTATE THE PROBLEMThe Problem:To demonstrate that the level of residual radioactivity in Class 1 Survey Unit 09 does notexceed the release criteria of 25 mrem/year Total Effective Dose Equivalent (TEDE) asspecified in the License Termination Plan (LTP).Stakeholders:The primary stakeholders interested in the answer to this problem are ConsumersEnergy Co., and the general public as represented by the Michigan Department ofEnvironmental Quality (MDEQ), and the US Nuclear Regulatory Commission (USNRC).The Planning Team:The planning team consists of members of the BRP Environmental Services SurveyGroup (ESSG). The primary decision maker will be the Final Status Survey Supervisor.The Final Status Survey Supervisor will obtain input from the site Construction Groupand Scheduling Group for issues relating to schedule and costs.Schedule:Approximately five (5) working days are projected to implement the survey and to collectand analyze field data.Resources:The primary resources needed to determine the answer to the problem are two (2)technicians to perform fieldwork, one (1) technician to prepare the samples and conductlaboratory analyses, and two (2) survey team members to prepare and review thedesign, generate maps, coordinate field activities and evaluate data.2.IDENTIFY THE DECISIONSeveral decisions need to be defined to address the stated problem.PrincipalStudy Question (1):Does the mean concentration of residual radioactivity in the survey unit exceed therelease criteria stated above?Decision (1):Determine whether the mean concentration of residual radioactivity in the surveyexceeds the release criteria stated in the problem.Actions (1):Alternative actions include failure of the survey unit, remediation, or no action required.Data Quality ObjectivesFSS 09C I1Page 1 of 5

PrincipalStudy Question (2):Do any areas of elevated activity in the survey unit exceed the release criteria?The Decision (2):Determine if any areas of elevated activity in the survey unit exceed the release criteria.Actions (2):Alternative actions include confirmation and investigation, performing the elevatedmeasurement comparison (EMC), remediation, or no action required.PrincipalStudy Question (3):Is the potential dose from residual radioactivity in the survey unit ALARA as stated?The Decision (3):Determine if the potential dose from residual radioactivity in the survey unit is ALARA.ALARA requirements for soil remediation are defined in Chapter 4 of the LTP.Actions (3):Alternative actions include remediation or no action required.3.IDENTIFY INPUTS TO THE DECISIONInformation Needed:Characterization measurements are required to define the radionuclides present anddetermine the extent and variability of residual radioactivity in the survey area for designand implementation of the survey. Survey area classification, ALARA analysis, potentialradionuclides of interest, and site-specific DCGL values are also required inputs to thedecision process. The primary information required for evaluation is the analyticalresults of survey measurements.Source of the Information:The soil sample data to be used for survey development are the radionuclide-specificmeasurements of representative soil samples collected for radiological characterizationand excavated soil surveys conducted to determine suitability for transport of excavatedsoil to the SVA. The soil samples obtained were judgmentally selected as a result ofmultiple surveys conducted during the excavation and transport process. The ALARAanalysis for potential soil remediation is provided in LTP, Section 4.4. Site-specificDCGL values and BRP radionuclides of interest are defined in LTP Chapter 5, Table 5-1and Procedure RM-76, FinalStatus Survey Design.The survey will be conducted in accordance with applicable regulatory guidance asestablished in LTP Chapter 5 for Class 1 areas. Soil samples will be utilized forradionuclide-specific measurements in this evaluation.4.BOUNDARIES OF THE STUDYBoundaries of the Survey:The target population for this survey is the total thickness of prepared soil in the surveyarea of 1989 M 2 .Data Quality ObjectivesFSS 09C11Page 2 of 5

Temporal Boundaries:Scanning and sampling in this survey unit will only be performed during daylight hoursunder dry weather conditions. Surface soils must be free of significant snow cover andstanding water prior to surface scanning. Soils must be in a non-frozen state orfragmented for collection to satisfy BRP procedural sampling requirements. Theanticipated start date for the survey is September 13, 2006.Constraints:Cold weather or rainy conditions may effect the operation of electronic equipment.Adverse weather conditions that include accumulations of rain or snow may limit areaaccess and delay survey efforts.5.DEVELOP A DECISION RULEThe following decision rules have been developed to define a logical process forchoosing among alternative actions for the principal study questions associated with thissurvey area.Decision Rule (1):If all reported concentrations for residual radioactivity are less than the site-specificDCGL's and the unity rule has been satisfied for each sample, then the survey unitmeets release criteria. No further action is required.Decision Rule (2):If the mean value of activity in the survey unit is greater than the DCGL, then the surveyunit fails to meet the release criteria.1 Remediate, resurvey, and evaluate the resultsrelative to the decision rule.Decision Rule (3):If the mean activity in the survey unit is less than the DCGL and any individual samplemeasurement exceeds this value, conduct the Sign Test and the elevated measurementcomparison (EMC) per LTP, Chapter 5 and Procedure RM-76, Final Status SurveyDesign. If the EMC and the Sign Test have been satisfied then the survey unit meetsthe release criteria and no further action is required. If the EMC or the Sign Test has notbeen satisfied then remediate the area(s) of elevated activity, resurvey as appropriate,and evaluate the results relative to the decision rule.Decision Rule (4):If the potential dose from residual radioactivity in the survey unit is ALARA, then nofurther action is necessary. If the potential dose from residual radioactivity in the surveyunit is not ALARA, then remediate and resurvey.6.SPECIFY TOLERABLE LIMITS ON DECISION ERRORSThe Null Hypothesis:It is assumed that residual radioactivity in the survey unit exceeds the release criterion.multiple radionuclides are present the mean activity value is determined as the average of theweighted sum. The DCGL of the weighted sum is 1.1 WhenData Quality ObjectivesFSS 09C11Page 3 of 5

Type I Error(a):The a error is the maximum probability of rejecting the null hypotheses when it is true.Thea error is defined in the LTP at a value of 0.05 (5%) and cannot be changed to aless restrictive value unless prior approval is granted by the USNRC. The a error valueof 0.05 will be used for survey planning and data assessment for this survey area.Type II Error(/3):The 83 error is the probability of accepting the null hypothesis when it is false. A valueof 0.05 (5%) will be used for survey planning and data assessment for this survey area.The Lower Bound of the Gray Region (LBGR):The LBGR is initially set at one-half the DCGLw for this survey unit. The LBGR may beadjusted during survey design to achieve an optimum relative shift between 1.0 and 3.0.Relative Shift (A/a):The relative shift will be maintained within the range of 1.0 and 3.0 by adjusting theLBGR as appropriate.7.OPTIMIZE DESIGN FOR OBTAINING DATAStatistical TestSign Test:Radionuclides of potential plant origin also present in soil as background activityresulting from fallout constitute only a small fraction of the DCGL. Therefore, the SignTest will be used where applicable in the survey evaluation to determine if the surveyarea meets the requirements for unrestricted release.Number of Samples Determined:The number of samples required for this survey will be determined based on the relativeshift as defined by the requirements of the Sign Test (LTP, Chapter 5.) and ProcedureRM-76, Final Status Survey Design. The LBGR is initially set at one-half the DCGLw andmay be adjusted as necessary for optimizing the survey design to achieve a relative shiftbetween 1.0 and 3.0. Sample point locations are to be determined using a random start,systematic square grid spacing.Judgmental Sampling:Co-60 is the most limiting radionuclide for identification by surface scanning; judgmentalsurface and subsurface core samples will be collected in any location that exceeds thescan investigation level.Scan Coverage:Scanning for this survey area will provide 100% coverage.Number of Samples for Quality Control:A minimum of 5% of the sample population will be collected for quality evaluation.These samples may include sample splits, sample recounts, or third party sampleData Quality ObjectivesFSS 09C1 1Page 4 of 5

analysis. Quality analyses will be conducted as defined in LTP, Chapter 5 andProcedure RM-79, FinalStatus Survey Quality Control.Additional Sample Analysis Requirements:The area of soil excavation intersects the identified waterborne pathway for Tritiummigration and shall require Tritium in soil analyses for a minimum of 10% of the samplepopulation. Soil samples will be collected in the same random locations as thoseselected for QA/QC evaluation and sent to an independent laboratory for Tritiumanalysis. Data results will be provided in the survey package.Investigation Levels:Investigation levels defined in LTP, Chapter 5 and BRP Procedure RM-76, FinalStatusSurvey Design, shall be conservatively established for this survey as shown below:for Survey 09C11Soil Sample AnalysisThe investigation levels for soil sample measurements are meant to include anyindividual radionuclide result greater than the site-specific DCGL or where the combinedradionuclide values exceed the unity rule. Co-60 is the most limiting radionuclide foridentification by surface scanning; further investigation will be initiated at any locationthat exceeds the Co-60 Scan DCGL of 1818 CPM above background as detailed in thesurvey design.Data Quality ObjectivesFSS 09C11Page 5 of 5

FINAL STATUS SURVEY DESIGNRelease Record 09C1 lNorth East Protected AreaSurvey Unit DescriptionSurvey 09C,1 encompasses an area of 1989 m2 in the north east section of the Protected Area.No materials of plant origin exist in this survey unit.Soil Sample DesignScoping DataScoping measurements and supporting surveys performed in the Protected Area followingremoval of subsurface components and demolition'debris do not indicate the presence ofelevated levels of residual radioactivity in this survey area. Input data for survey design wereconservatively estimated based on supporting surveys of excavated soils resulting fromsubsurface structure and component removal within the Protected Area.Table 1Input Data for Survey Design (pCi/g)RadionuclidesCs-1370.524DCGL11.93*Survey data detailed inAttachment 1Co-600.2553.21Sample RequirementsThe number of sample data points for this survey is based on the requirements of the Sign Test.The Unity Rule is used for the presence of multiple radionuclides. The Standard Deviation ofthe weighted sum is described by the following:j(ac132 DCG SI37C/0.524 2 V,11.93)oCOsOOt(DC61-coeo)( 0.255 )23.21')a 0.091Relative ShiftRelative Shift DCGLw-LBGRaRelative Shift1-0.8180.091Relative Shift 2.0With oa and p error levels set at 0.05 and the relative shift of 2.0, the Sign Test requires 15sample data points (Table 5.5 NUREG 1575).Survey DesignFSS 09C11Page 1 of 7

Sample LocationsSample locations are selected in a random start, systematic square grid pattern with thesouthwest corner of the survey unit as origin (X 0, Y 0). Two numbers between 0 and 1 havebeen randomly selected and then applied to the survey unit maximum X and Y dimensions todetermine the random start location as shown below:Table 2Random NumbersRandom #, Y Axis0.939078Random #, X Axis0.373169Survey Unit Dimensions:X 41.6 metersY 49.0 metersRandom Start LocationWith SW Corner Origin:X (0.373169)(41.6) 15.5 metersY (0.939078)(49.0) 46.0 metersSample SpacinaAs a conservative measure sample spacing will be calculated based on 18 samples for thissurvey. Samples are located in a systematic square grid pattern with sample spacingdetermined by the following:LAnWhere: A area of survey unit, andn - number of samples.L t198998 9L1810.5metersWith sample spacing established at 10.5 meters, 20 data points are available for this survey.Data point locations are identified in Attachment 2.QAIQC SamplingA minimum of 5% of the sample population and 5% ofthe scan survey area are required to beselected for QA/QC verification in accordance with BRP Procedure RM-79, Final Status SurveyQuality Control. As a conservative measure, three (3) soil samples and 10% of the scan surveyarea will be selected for QA/QC evaluation. Data point locations for soil samples will bedetermined by random number selection.The QA/QC scan starting point and track direction are also determined by random numberselection. The first random data point selected will identify the scanning start point and thesecond random data point will determine the direction in which the scan will track. QA/QClocation results are provided in Table 3 below:Survey DesignFSS 09CllPage 2 of-7.

Table 3Random Numbers Generated for QA/QCSoilQAIQCSamplesSplit Sample:Sample Recount:Sample Recount:RandomSampleNumber51113Verification ScanRandomSampleNumberStart Point:Scan Toward:Scan Area Requirement:189199 m2Surface ScanningThe coverage requirement for surface scanning in this Class 1 area is 100%. The Scan MDC hasbeen established at fractional values of the DCGLw for typical background activity levels at BigRock Point. Scan MDC values for varying backgrounds are provided in Attachment 3. Theinvestigation level for identification of potential areas of elevated activity in this survey area willbe the Scan DCGL as defined by the following:Scan DCGL Detector Rating CPM . Exposure Model uR/hr . DCGLwpCi/guR/hrScan DCGL for Co-60 1818 CPMScan DCGL for Cs-137 3518 CPMWhere:1Detector Rating 1200 CPM Cs - 137 and 565 CPM Co - 60uR/hruR/hrExposure Model .2u/rCs-137 and 509u/rCo-605 pCi/g5 pCi/gDCGLw 11.93 pCi/g Cs-1 37 and 3.21 pCi/g Co-60The DCGLW for Co-60 is the most limiting value for scanning measurements performed to identifyareas of potentially elevated activity. Scanning conducted for this survey will assume all residualradioactivity to originate from Co-60 and the instrument response at the Co-60 DCGLw.(1818 cpm)will be used as the scanning investigation level for FSS 09C 11.1These values established in EA-BRP-SC-0201, Nal Scanning Sensitivity for Open Land Survey.Survey DesignFSS 09c 1 1IPage 3 of 7

Attachment IDesign Data - FSS 09C 11Protected Area Supporting SurveysSurvey 5SequenceNo.165381653916540167551675616774Mean:Std *0.310.3520.255* Measurement system MDA - Co-60 not identified in this sampleSurvey DesignFSS 09C1 lPage 4 of 7

Attachment 2Soil Sample Locations - Survey 09C1 1North East Protected Area#Y49 0 m*i 8016019eO*14*10.7*I*11X 41 6 mLIII]Su eyUn 5 0mic1020Meters ni yIe Loc 17175156157505 645.05O0556.06.5556006.060Sample spacing10 5 rnetertSurvey DesignFSS 09C,1Page 5 of 7

Attachment 3Scan MDC In Varying 00145002.482.484475.7777.111,607.221 2000d'2.48300035004000%ý.78,Z 'ýf'17;a63.Survey Design09C 11Page 6 of 72.

Attachment 4Area Factors for Open Land Survey EvaluationContaminatedArea (M2 )H-3Mn-54Calculated Area Factors at Time of Peak DoseEu-154Cs-137 715.630.559.9117230452887Survey Design09C1 1Page 7 of .141.231.391.632.143.194.907.88

RM-76FINAL STATUS SURVEY DESIGNRevision 1Page 19 of 19RM-76-5FINAL STATUS SURVEY APPROVALAND AUTHORIZATION FOR IMPLEMENTATIONISurvey Code09C011Survey Area Description:'Final Status Survey 09C01 encompasses 1989 m 2 at or below the grade elevationpresent durinn plant power operations in the north east section of the ProtectedArea. No materials of plant origin remain in the survey area.The survey area is authorized for Final Status Survey Implementation.Designei byTechnical Review byRM-76.docDateDate

Revision 2Page 8 of 12RM-77FINAL STATUS SURVEY IMPLEMENTATIONRM-77-1SURVEY IMPLEMENTATION CHECKLISTPage 1 of 3Step( )1.01.1InitialPREPARATION FOR SURVEYDateoqC ,tSurvey #Survey Area Status:a. Final Status Survey Design has been approved forimplementation (see RM-76-5, Final Status SurveyApproval and Authorization for Supplementation).1.2.3.4.Survey area walkdown completeSurvey area determined ready for FSSDecommissioning activities that may impact theenvironmental status of the survey area have beencompleted.Survey area environment is controlled by barriersand postings or other approved method to restrictaccess./b. Survey area has been turned over to the EnvironmentalServices Survey Group (ESSG) in acceptable conditionfor FSS.AS -GQgý&6'1ý8SG1.22%&/0ý0Field Preparation:a.77b.v1c.d.e.RM-77.docSurvey unit boundaries delineated (Step 6.1.1)Statistical soil samples predetermined in the surveydesign are located and marked within the survey unit.(Step 6.1.2)Soil sample locations verified (Step 6.1.2.c)Instruments and equipment have been collected andcalibrated for data measurement and collection(Step 6.1.3)Field documentation is prepared (Step 6.1.4)QAýASSG10

RM-77FINAL STATUS SURVEY IMPLEMENTATIONRevision 2Page 9 of 12RM-77-1SURVEY IMPLEMENTATION CHECKLISTPage 2 of 3Initial2.0DATA COLLECTION2.1Soil Survey:All soil samples collected and controlled (Step 6.2.1).d&rESSG2.34k444Surface Scan:2.2DateSurface Scan complete. Action response requirements havebeen conducted on any identified areas exceeding theinvestigation level (Step 6.3).JSSGJudgmental Soil Samples:a.b.Judgmental soil samples have been collected andcontrolled (Step 6.2.3).Deep core profiles performed in areas identified tocontain elevated residual activity (Step 6.2.3).&SS-G-3.0SAMPLE PREPARATION AND LABORATORY ANALYSIS3.1Sample Preparation (Step 6.4.1):V 7a.b.C.d.Soil samples are homogenousSoil samples are visibly dry prior to packingNon-soil materials have been removed from sampleSoil samples have been transferred to one-literMarinelli containers and are labeled and sealed.LIECESSG,RM-77.docA4i4

Revision 2Page 10 of 12RM-77FINAL STATUS SURVEY IMPLEMENTATIONRM-77-1SURVEY IMPLEMENTATION CHECKLISTPage 3 of 3Initial.,3.2z3.3'-XLaboratory Analysis:Isotopic analyses are complete. The spectroscopy reportrequires a signature of completion by the laboratory analystand a signature of evaluation documenting that a secondlevel review has been performed (Step 6.4.2).Sample Control and Documentation:Chain of custody documentation exhibits control of soilsamples (Step 6.4.3).Reviewed byRM-77.docDateSSGDate

Revision 11Page 7 of 13RM-59SAMPLING AND ANALYSIS OF OPEN LANDAREAS FOR SITE CHARACTERIZATION SURVEYSATTACHMENT RM-59-1SAMPLING AND ANALYSIS REPORTTime: 1600Date: 09-13-2006Location: 09C,1T¶Soer,,.SURVEY IDENTIFICATION / DESCRIPTIONSurvey 09C11 encompasses 1989 m2 at or below the grade elevation present during plant Power operationsin the north east section of the Protected Area. No materials of plant origin remain in this area.SURVEY TYPE'Survey Type:XXCharacterizationRemediationFinalScan (Motive)Scan (Static)Trenching and Digging (use RM-59-4)SURVEY DESIGNSample Collection:Scan Coverage:Judgmental. RandomXSystematicLarge Container Assay100%ANALYSISInst.SN/Cal Due 201195/02-10-07Inst.SN/Cal Due 186185/09-23-06Inst.SN/Cal Due 189086/01-26-07Inst.SN/Cal Due Det. # 6Inst.SN/Cal DueInvestigation of Unidentified Peaks:DAILYDAILYDAILYDAILYDAILYMinimum Detectable Activity (Section SATSATSATXSATUNSATUNSATUNSATUNSATUNSATUNSATINIT: SSOINIT: SSOINIT: SSOINIT: SSOINIT:INIT: JLRUNSATINIT: JLRCOMMENTSSurvey 09C 1l was performed in a random start, square grid, systematic samplingq oattern with samplescollected at 20 data point locations. Laboratory analyses did not identify residual radioactivity above trace levels ofthe DCGL value. Surface scanning identified no areas of elevated residual radioactivity. The results of the QA/QCverification scan 110%)) were consistent with the scan values identified in the survey.Technician Si nature:Second Level Review:Signature:RM-59.docDate:--;"-01Date:,-OI'

Surface Scan SummaryRelease Record 09C 1lNorth East Protected AreaN@17S 4,0 4,601653 5,24265.34 5 5ý2@13@14@154846242 rvey Unit 09C1 10484 73747@12o11@104620105MetersSample LocationBLUEVtIt iAvrqoalAtea Activity (kcpm)Mobittl Sa (:;ttiVerifieatiun Scatt General Area Activity (kcpm)I ;[lee: I: kqrePrimary Scan :!, ITechnician Signature.md Area Activity (kcprm)%Date: XI.LtTime:QC Verification Scan:Technician Signature:ILDate:Time:id/z

Soil Sample Activity SummaryRelease Record 09C1 1North East Protected AreaY 49.0 m4-Y 49.0 401X 41.6 m0Survey Unit 09C1 1SSample51020MetersSample 1 0*0.01400.053163402.76.4*0.0448783393382.31.96. 46.4*0.02680,0578No.1235Grid #353521.92.76.06.0Cs-137 (pCilg)Co-60 (pCig)*-0.00300.0557*0,0263 480 0634*.0014"0-0594*0,00170.05270.0506*0ý0234 80.0451* *-0.0108*0 017417315183141931320312*Forced-count values**Coordinate location relative"" *-0.0014 048*-0.0092'0.0218*-0.0033to SW corner of survey unit where X O m. and Y O m.0.04470.06080.04540.04840.06670.0541

RM-72SAMPLE CHAIN-OF-CUSTODYRevision 0Page 4of 509C,1RM-72-1CHAIN-OF-CUSTODY RECORDSampling LocationSample NumberDateTime1Grid# 194(5.0) (4.0)09-13-0612402Grid # 195(5.5) (4.0)09-13-0612453Grid # 196(6.0)(4.0)09-13-0612484Grid # 197(6.5) (4.0)09-13-0612505Grid # 178(6.5) (4.5)09-13-061254Grid # 178(6.5) (4.5)09-13-0612546Grid # 177(6.0) (4.5)09-13-0613057Grid # 176(5.5) (4.5)09-13-0613078Grid # 175(5.0) (4.5)09-13-0613589Grid # 156(5.0) (5.0)09-13-06135410Grid # 157(5.5)(5.0)09-13-061310Grid # 158(6.0) (5.0)09-13-061325Grid # 159(6.5)(5.0)09-13-061320Grid # 140(6.5)(5.5)09-13-06133514Grid # 139(6.0)(5.5)09-13-06140315Grid # 138(5.5) (5.5)09-13-06140016Grid.# 137(5.0) (5.5)09-13-06135017Grid #61(5.0)(6.0)09-13-06134118Grid # 62(5.5)(6.0)09-13-06134619Grid # 63(6.0)(6.0)09-13-06134220Grid # 64(6.5)(6.0)09-13-061340QA Split5()1121'(R)Final Disposition of Sample/(Samples may be analyzed and stored, shipped for offsite evaluation or analyzed and disposed of.)1. Requ hby:TimeDateq3v0(L.-1Received in good condition by:S1 L)'31.je2. Relinq ii-ed by:DateTimeReceived in good condition by:3. RelinquisheDaTimeReceived in good condition by:4.ReAdy:Date4. Relinquished by:RM-72.doc;720Date6/5ReevdngodcnitTimeReceived in good condition by:

Revision 2Page 19 of 26RM-78FINAL STATUS SURVEY ASSESSMENTRM-78-3DATA ASSESSMENT REPORTPage 1 of 8FINAL STATUS SURVEY:1.0DATA VERIFICATION1.1Data Acceptance/699Y?C,/Review the Implementation Checklist (RM-77-1) to verify that survey isolationand control measures were executed prior to FSS and are being maintained.z.Review RM-77, Final Status Survey Implementation, to verify that methods,techniques, and survey activities required for FSS have been applied inaccordance with the appropriate procedures.1.2Field QC Records:Review all assessments, Condition Reports and audits to ensure thatidentified issues have been resolved.Comments:/Verify scan instrumentation was in calibration and the QC source checkswere performed prior to and after surveys.Verify daily QC source checks for Canberra gamma spectroscopy detectorproperly logged prior to soil sample analysis.1.3Review Verification:Verify that the Data Quality Objectives are complete.Verify that the survey design has been technically reviewed.RM-78.doc

RM-78FINAL STATUS SURVEY ASSESSMENTRevision 2Page 20 of 26RM-78-3DATA ASSESSMENT REPORTPage 2 of 8Verify that gamma spectroscopy results have received a technical review.VVerify the Sample and Analysis Report (RM-59-1) is completed and

established in LTP Chapter 5 for Class 1 areas. Soil samples will be utilized for radionuclide-specific measurements in this evaluation. 4. BOUNDARIES OF THE STUDY Boundaries of the Survey: The target population for this survey is the total thickness of prepared soil in the survey area