ML14160A815

University of Buffalo, Submittal of Supplemental Information Regarding Building Release Surveys to Prepare the Building for Demolition

ML14160A815
Person / Time
Site:	University of Buffalo
Issue date:	06/05/2014
From:	Vasbinder D R University of Buffalo
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
GEW-P14-008
Download: ML14160A815 (22)

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{{#Wiki_filter:University -at BuffaloThe State University of New YorkEnvironment, Health & Safety ServicesJune 5, 2014Docket 50-57License R-77U.S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, D.C. 20555 -0001

Dear Sir or Madam:

This submission is in follow up to our submission, dated May 22, 2014, detailing supplementalinformation and data to address comments provided by ORISE and the N.R.C. regarding building releasesurveys performed at the University at Buffalo's Buffalo Materials Research Center to prepare the buildingfor demolition.A conference call was held on June 2, 2014 during which several items were identified that required furtherclarification.Attached is a letter and data firom the University's Decommissioning Management Contractor, Enercon toMr. Dave Vasbinder detailing supplemental information addressing those items that were identified.We have also provided courtesy copies of this information to our Project Manager, Ted Smith and Region 1Inspector, Steve Hammann as well as to ORISE.If you have any questions or wish further information, please contact me at (716) 829-3301 ordvasbind@buffalo.edu.Sme~Y,,6/David R. VasbinderDirector, Buffalo Materials Research CenterCc: Ted Smith, U.S.N.R.C. Project ManagerSteve Hammann, NRC Region INick Altic, ORISEA (ýýt, tzz ENERCONExcellence-Every proiecO. Ever~y .()Y.June 5, 2014GEW-P 14-008Mr. Dave VasbinderAssociate Director, Environment, Health, and Safety Services BMRCThe State University of New YorkUniversity at Buffalo220 Winspear AvenueBuffalo, NY 14215-1034Re: Response to June 2, 2014 CommentsMr. Vasbinder;This letter provides discussion of the technical issues addressed in our discussion June 2, 2014 with NRCand ORISE. Each of the key items identified as requiring clarification are addressed in the followingsections.Selection of Release CriteriaFor this project, the surface release criteria for building materials were based on the use of RegulatoryGuide 1.86, "Termination of Operating Licenses for Nuclear Reactors" Table 1. This table providesaverage and maximum values for surface measurements and removable contamination limits. Thesecriteria are acceptable for unrestricted release of buildings, materials, and equipment. The criteria werestated in the NRC approved decommissioning plan.Since the average limits provided in Reg Guide 1.86 were followed, the concept of using a developed areafactor following MARSSIM for elevated measurement comparison of individual survey measurementsthat exceed the DCGL value is not directly applicable. Reg Guide.1.86 Table I average values wereselected as a conservative measure and to eliminate the need to derive site-specific DCGLs and areafactors.Statistical Analysis of Survey UnitsThree survey units were assessed during scans and surveys using the release criteria of 1,000 dpm/100cm2because SR-90 was the radionuclide of concern in that survey unit. The remainder of the survey unitsused the average release criteria of 5,000 dpm/1OOcm2.The survey package units using 1,000 dpm/1OOcm2 as the average release limit were RBC-200-1,RBC-201-1, and ADM-000-5. Two of these survey package units have individual readings that exceed1,000 dpm/1OOcm2 (two measurements for RBC-200-1 and four measurements for ADM-000-5). Thethird survey unit (RBC-201-1) had no individual reading that exceeded 1,000 dpm/1OOcm2.None ofthese six locations exceed the maximum surface concentration level of 3,000 dpm/100cm2 in Table 1 ofReg Guide 1.86 for Sr-90.For the six locations with measurements above 1,000 dpm/1OOcm2, the areas were determined during thesurvey to be less that 1-meter square using the process described in this letter. The average concentrationlimit for these survey units was less than 1,000 dpm/1OOcm2.No reading exceeded the maximum44.9001WhI ifwr Penn F hvio7 ' May. vI~ PA 7,ý3368* 1 74,32 S160.3 n co ccn June 5, 2014GEW-P 14-008Page 2 of 4concentration limit of 3,000 dpm/1OOcm2.Thus, these survey units met the levels established in the NRCapproved decommissioning plan.At the request of NRC and ORISE, statistical analysis for RBC-200-1 and ADM-000-5 was completedbased on the Sign Test and submitted for review. Use of the Sign Test is appropriate under MARSSIMbecause the radionuclide in question (Sr-90) is not present in the background. Statistical analysisdocumentation added to each survey package unit and provided to NRC and ORISE showed that thesurvey units passed the Sign Test. Each of these statistical analyses included a note that the Sign Testwas based on an assumed area factor of 2.Technical clarification and justification has been requested to support this assumption as stated on thestatistical summary sheet. Since Reg Guide 1.86 release criteria were selected rather than calculating site-specific DCGLs, area factors were not calculated. Supporting justification for as the assumption that anarea factor of 2 is a conservative selection for the Sign Test comparison is as follows:1. Radionuclide-specific area factors are published in NUREG-1505 Table 8.2 (see Attachment 1)for indoor building surfaces. The 1-meter square area factor for Sr-90 is 35.7. This publishedarea factor for Sr-90 is much higher than the very conservatively selected assumed factor of 2used in the Sign Test.2. As a further demonstration that the assumed area factor value of 2 used in the Sign Test isextremely conservative, area factor calculations for Sr-90 have been made using the NRC'sDandD code. This code is widely recognized as extremely conservative. The results in the tablebelow provide area factors for Sr-90 for various area sizes. The factor for a 1-meter square areais 10. This calculated value is much higher than the very conservatively selected factor of 2 usedin the Sign Test. Supporting code output reports forthese analyses are provided in Attachment 2.Table 1 -Area Factors for Sr-90Size of Area aboveRelease Limit Area Factor(square meters)125 110 15 23 3.31 10Assessment of Areas Exceeding the Investigation LimitNRC and ORISE have requested a description of the evaluation process for the individual surveymeasurements that exceeded the investigation limit.As part of the survey process, an investigation limit was administratively selected to ensure that areasexceeding a specified value were appropriately evaluated regardless of whether the area exceeded the4490OidWifiam~nn ighoy Mrqwlhv PA.7568 1foy June 5, 2014GEW-P 14-008Page 3 of 4average release limit. For the BMRC surveys, this value was selected to be 75% of the average releaselimit. Thus, survey units with an average release limit of 5,000 dpm/1OOcm2 had an investigation limit of3,750 dpmi/lOOcm2, while survey units with an average release limit of 1,000 dpm/1OOcmM2 had aninvestigation limit of 750 dpm/1OOcm2.Areas identified during the survey with having activity greater than the investigation limits wereevaluated using the following process:* A 1-meter square area at the location of the reading exceeding the investigation limit was re-scanned. The purpose of the re-scan was to determine if any area exceeded the average releaselimit.* If the re-scan confirmed a reading exceeded the maximum release limit, the area was remediatedand re-scanned.* If the re-scan confirmed a reading exceeded the average release limit and the area was less than1-meter square, a direct one-minute measurement was taken at the location of the highest activityand recorded, then survey activities were continued.* If the re-scan confirmed a reading exceeded the investigation limit but not the release limit withinthe 1-meter square area, a direct one-minute measurement was taken at the location of the highestactivity and recorded, then survey activities were continued.Attachment 3 provides a summary table of survey data collected for the 29 BMRC survey units. Overall,only 14 survey points exceeded the investigation limit in the combined data from all survey units.Of these 14 measurements, six measurements are those values that exceeded the average release limit insurvey units RBC-200-1 and ADM-000-5 but are below the maximum release limit. These sixmeasurements were part of the Sign Test evaluations (two measurements for RBC-200-1 and fourmeasurement for ADM-000-5) requested by and provided to NRC and ORISE.An additional two measurements in survey unit RBN-000-1 were reported, but noted in the commentssection that the measurements were part of a structurally significant location that will be removed anddisposed as low-level radioactive waste (LLRW) during demolition. These two measurements areincluded in the total of 14.The remaining six locations were evaluated using the investigation process described above. No readingsabove the average release limit were found at these locations.Assessment of Number of Sampling PointsNRC and ORISE requested confirmation that the number of sampling points met the requirements forbuilding release for demolition. Each survey unit was individually evaluated for the number of samplingpoints prior to starting the field survey. The "General Instructions" section identified the number of staticmeasurements for that specific survey unit based on statistical assessment. Maps were prepared for eachsurvey area using the Visual Sample Plan. These maps were provided to the staff during the datacollection process. Measurement locations were recorded during the survey process, and were provided inthe survey unit package documentation.4:49 , Old Wifliatr:Penn. gYihway A.utrysvillh.PA- 5"S £66 p .pte: 7.2?4.W.911 ' 0 ,U .4,32S,638j enccomccnm June 5, 2014GEW-P 14-008Page 4 of 4Following the MARSSIM protocol, an additional 10% allowance was included for quality control alongwith an additional 20% allowance to account for any inaccessibility issues, data collection issues, orunanticipated issues with data collection. This information is provided in Attachment 3.ConclusionsIn summary, none of the survey data exceeded the maximum release limit. Only 14 survey pointsexceeded, the investigation limit of 75% of the average release limit.Of these 14 survey points, six points each less than 1-meter square exceeded the average release limit butwere less than the maximum release limit. The two survey units with these six data points passed theaverage release limit. No points exceeded the maximum release limit of Reg Guide 1.86 stated in theNRC approved decommissioning plan. The two survey units were proven to pass the Sign Test using anextremely conservative area factor assumption.Two of the 14 points represented a known activated structural component that will be removed anddisposed as LLRW during demolition.The remaining six points exceeding the investigation limit were assessed to confirm that no materialexceeded the average release limit.In concurrence with the Reg Guide 1.86 criteria, no measurement of the surface reading was averagedover more than 1-meter square. In concurrence with Reg Guide 1.86 criteria, no measurement of themaximum surface reading was greater than 100 cm2 since no measurement exceeded the maximum value.Three survey units had less actual survey points than planned. During planning, each survey unit wasdesigned with an excess number of survey points beyond the MARSSIM requirements. The actualnumber of survey points for these survey units, although less than planned, was still confirmed to meetthe MARSSIM requirements.We continue to believe that the building has met the release criteria in the FSS plan, the decommissioningplan, and the methodology specified in MARSSIM. Accordingly, the building demolition needs to be.initiated, and NRC approval to proceed is required.Sincerely,Gerald E. Williams, P.E. Frank BrownManager, Environmental Services Group Project ManagerAttachmentscc: Robert Weller4490.0-0d Willioi.rPTe .Highw.ay ~ r~ile:> v766 7;4; J3'7 7,,24 .ýO3?..J eerolc , GEW-PI4-008Attachment 1Table 8.2 Example Indoor Area FactorsNNuclide 36 m2 25 m2 16 m2 9 m2 4 m2 I m2Co-60 1.0 1.2 1.6 2.5 5.5 22.7Cs-137 1.0 1.2 1.7 2.6 5.7 23.5H-3 1.0 1.4 2.3 4.0 9.0 36.0Ni-63 1.0 1.4 2.3 4.0 9.0 36.0Pu-239 1.0 1.4 2.3 4.0 9.0 36.0Ra-226 1.0 1.4 2.1 3.6 8.0 32.2Sr-90 1.0 1.4 2.2 4.0 8.9 35.7Th-232 1.0 1.4 2.3 4.0 9.0 36.0U-235 1.0 1.4 2.2 4.0 9.0 35.8Zn-65 1.0 1.2 1.6 2.5 5.4 22.3 GEW-P14-008Attachment 2Page 1 of 15DandD Building Occupancy ScenarioPage I of 3RE0DandD Building Occupancy ScenarioDandD Version: 2.1.0Run Date/Time: 6/2/2014 12:32:13 PMSite Name: Sr-90 AF CaIcsDescription: Calculation of Sr-90 Area FactorsFiteName:C:\Users~ajnardi\Docutnents\DandD\Sr-90 Area Factors.ncdOptions:Implicit progeny doses NOT included with explicit parent dosesNuclide concentrations are distributed among all progenyNumber of simulations: 10Seed for Random Generation: 8718721Averages used forbehavioral type parametersExternal Pathway is ONInhalation Pathway is ONSecondary Ingestion Pathway is ONInitial Activities:Area ofNuclide. Distributionn ( )190Sr 111-25 EcoNS'rANr(dpm/l 00 cm" 2)-.i Jutficafi~n. for conceniraion; Sr-90 Unit Value ,aioe L.OOE+00Chain Data:Number of chains: IChain No. 1: 90SrNuclides.in chain: 2Ingestion Inhalation Surface 15 cmChan. Haf Frs Facionl ecndFractional CEDE CEDE Dose Rate Dose RatePuleosition Life Parent Yield Parent ield Factor Factor Factor Factor(Sv/Bq) (Sv/Bq) ((Sv/d)/(Bq/m2)) ((Sv/d)/(Bq/m3))9OSr 1II 1 .06E÷04 I I ZI .,'.85E:0s1I3.5IE-07 112.46EI 4 13.2.11E- 16t90" 1! 1.7-oo1 I ..~ "29E012.28E-09 14.60E- 13 11.03E-14Initial Concentrations:Note: All reported values are the upper bound ofthe symmetric 95% confidence interval for the 0.9 quantile valueSurface ConcentrationF90Sr ] (d pm/100 cm**2)90Y 0o,oOE+ooModel Parameters:file:///C:AUsers/ajinardi/Documents/DandD/Sr-90%20Area%2OFactors bidDetail..htm6/2/2014 GEW-P14-008Attachment 2Page 2 of 15DandD Building Occupancy ScenarioPage 2 of 3General Parameters:Parameter Name Description Distribution-T ý ýn ~ If The time in the building during theTo:im i Biling- oecupnnlcy period LONISTANT(hr~week)oDetau vs e.ed .Vlue 4.50E++Jt 7-cyhe duration of the occupancy exposure CI [period CONSTANT(days)Default value used \,alue 3.6512+02VIrhe average vohlunetric breathing rate during ONSTANT 3hr)Vbuildingoccupancy for an 8-hourw'vork dayDefault value used .Val4e I 0E+00RFo*:Resuspension Effective resuspension factor during tle DERIVED(l/m)Factor occupancvyperiod = RFo

• Fl,lefutt value used,, 7Effective secondary ingestion transfer rate ofG :Ingestion Rate removahle surface activity from building. DERIVED(im*2,lr)surfaces to the mouth dur'ing buildingoccupancy = GO FlDefault value usedTstart:Start Time Trhe strt time of-tle scenario in days ICONSANr(days)Defaul value used -Iaue o.O01+00ITend:End Time IThe ending time of the scenario in days ']IONSTANT(days)Default value used [Value 3.65E+02Idt:Time Step Size IThe time step size .CONSTANT(days)Default value used -! Value 3.65E+02The time steps for the history tile. Doses sillPstep:Print Step Size be written to the history file every n time CONSTANT(nonc)stepsDefaul, value used Value 1 .ttOE+00AOExt:External Minimum surface area to which occupant iseEposed via external radiation during CONSTANTftm*2)IExposure Area oce anc: periodDefault value used ,,00EValue I ,OOlAOInh:Inhalation Minimum surface area to which occupant isexposed via inhalation during oceupancy CONSTANT(int2)Exposure Area periodDe fault value used .[Value 1,00E+01AOing:Seconday =Mininusmsurface area to which occupwit isOe:St onEposre Ar exposed via secondars ingestion during.. CONS'IANT(mn*'2)Ingestion Exposure A occupaney period "EDfault \aluc used Value I.OOE+01Minimum surface area to which oceupant is DERIVED~ m*'2).O:Exposure Area exZpsed during the occupancy periodrDefaull value used']Fraclion of surface contamination availableI FI:ose Fraeti.= o rcs ]i,for resuspension and ingestion CONS'IANTtsssne)"De faul value used ]Value I ,00E-01Rfo:Loose Res o Ruspension factor for loose contamination CONTINIIOUS LOGARITHMICI,/m)IFactorDefault value used Value Probbilit9.12E-06 0.O0E-f001.101E-0-4 7.67E-011.46E-04 9.09E.011.6213-04 9.50..-011.85E-04 9.90E-[ II .9012-04 1.001E+00file'///C:/Users/ajnardi/Documents/DandD/Sr-90%2OArea%20Factors bidDetail.him6/12/2 01.4 GEW-P14-008Attachment 2Page 3 of 15DandD Building Occupancy ScenarioPage 3 of 3GO:Loose IngestionRateThe secondary ingestion transfer rate Ofloose rernovable surfiace activity frombuilding surfaces to the mouth duringbuilding occupancy[ONSTAN'r(ni *~21br)Defeult value ... ed .. ..1. iOE-04Correlation Coefficients:NoneSummary Results:90.00% of the 100 calculated TEDE values are < 2.88E-03 mrem/year.The 95 %.Confidence Interval for the 0.9 quantile value of TEDE is 2.59E-03 to 3.26E-03 mnrem/yearDetailed Results:Note: All reported values are the upper hound of the synnmetric 95% confidence interval for the0.9 quantile valueConcentration at Time of Peak Dose:Surface Concentration(dpm/100 cn/ mt*2)!lO0Sr 119.88E-0I90Y 9.78E-01Pathway Dose from All Nuclides (mrem)All Pathways Exera I7d aDose Inhalation Ingetion13.26E-03 117.70E-06 713.07E-03 lll.75E-04Radionuclide Dose through All Active Pathways (mrem)Nuclide .All Pathways1 11 Done[9OSr 13.22E-03,Sm 113.91E-05All Nuclides = 13.26E-03Dose from Each Nuclide through Each Active Pathway (mrem)file:///C:/Users/ajnardilDocuments!DandD/Sr-90%2OArea%20Factors bidDetail.htm6/2/2 014 GEW-P14-008Attachment 2Page 4 of 15DandD Building Occupancy ScenarioPage 1 of.3*0DandD Building Occupancy ScenarioDandDl Version: 2.1.0Run Date/Tihiie: 6/2/2014 12:25:31 PMSite Name: Sr-90 AF CalcsDescription: Calculation, of Sr-90 Area FactorsFileNanae:C:AUsers',ajnardi\Documents\DandD\Sr-90 Area Factors.medOptions:Implicit progeny doses NOT included with explicit parent dosesNuclide concentrations are distributed among all progenyNumber of simulations: 100Seed for Random Generation: 8718721Averages used for behavioral type parametersExternal Pathway is ONInhalation Pathway.is ONSecondaryIngestion Pathway is ONInitial Activities:Nuclide Area ofIContamination (in) Di-rbIiF19I0SrI FCO NSTAN1'(dpmiIOO crnfl2)_luo caon orcnentrafiow Sr-90 Unit Valtue Voln e LOOD0E00Chain Data:Number of chains: IChain No. i: 90SrNuclides in chain: 2ingestion Inhalation Surface 15 cmChain Half First Fractional Second Fractional CEDE CEDE Dose Rate Dose RateNuclide P~sit { Life Parent Yield Parent~ Yield Factor Factor Factor Factor(Sv/Bq) (Sv/Bq) ((Sv/d)/(Bq/m2)) ((Sv/d)/(Bq/m3)), .l l.06-04ý I 385E-08l3.51 E-07 2.46E-14 13.21'E-16.Initial Concentrations:Note: All reported value. arc the upper bound of the symmetric 95% confidence interval.or the 0.9 quantile valueNuclide Surface Concentration(dpm/100 cm**2)[90Y ]IO.OOE+00I9oy 10.00&-00Model Parameters:file:/i/C:/Users/ajnardi/Documents/DandD/Sr-90%2OArea%20Factors bidDetail.htm6/212014 0 1 , .GEW-P14-008Attachment 2Page 5 of 15DandD Building Occupancy ScenarioGeneral Parameters:Page 2 of 3Parameter Name Description. Distributionih =i ui the building during the CONS'AN'lhr/seek)o TI m e I .B i d n o c c u p an c y' p e ri o d!efanh value u1ed Vlu. e 4.515E-NTP he duratin of the occupancy exposure CONSTANT(days)It:euanyPro periodIDeSfault value used Jalue 3.65E÷,02" t vlnicr breathing raeduig OSANTIm-~3/hriVo:Breathing Rate= I'f, avrgFouterebet t aedr ng ......,s ..use ilding occupancy for an 8-hour work day4 +t~tatl value used Valu l.4oE+oO+Effective resuspeosion. factor durino h DERIVED(I:m)Factor 11occupancy period = RVO
• F1D)efault value used _ _ _ _ _ _Effecive secondary ingestion transfer rate ofGW neto Rat e n ovbl surfaee activity fronm building c EIV.:. , n"2,. hr)-SUrfaCs 10 the mouth during building.Defauti value ased I I.00E"O)atrtend:End Time IThe ending time ofthe scenario it days kC'ONSTANT(days),lDefaudt valute used ..*l Valsue 3(6XE+02ODefault vatue used Value-T _ 3.65E+02Idt:Time Step Size lthe titestep size t- CONSTANT(davs)Default value used IValu 3.65E+02The lime steps for the history rile. Doses willPstep:Print Step Size be written to the history file every n time CONSTANT(nuneistepsDefullt valtue sued Vu 1 .00E1+00AOExt:External Minimum surface area to which occupant isExposurerea exposed via external radiation during CONSTANTim-2)Exposure Area occupancy periodekfaflrt value tsed. Valise I.OOE+÷1AO :Inhalat Minimum surlface area to which occupant isExosurenAreao exposed via inhalation during occupancy CONSTANT~ t-2)Exposure Area period" I:fauht valsue used Pal _lOlJE40AOngSeondMinimum surface area to which occupansisexposed via secondary ingestion during ONSIANT(ns2)Ingestion Exposure Area occupne periodDelault value used [Value ..t0E-i+liMinimtnt surface area to whtich occupant is DERIVED(m**2)AnExour ,rea exoe u gteocpnyper. od (*D13fault value tsedFraction of surface contamination available nFI seFrtion Ifor resuspensiou and ingestion CONSTANT(nonelt)efaNlt value used ,Valu tOO,-IlltRfo.LooseResuspension Resuspensio factor l)rlose contamination CONTINUOUS LOGARITHMIC(I/rn)Defaultuvalue used Value Pmba"ilitv9.12E-06 0.o0(E+001.1 OE-0t4 7.67E-011.46E-04 9.09E-011.62E-(14 9.50E-011.85E-04 9.90E-011.90E-04 L.OO10E÷0)file:/I/C:/IJsers/ajnardifDocumentS!DandDISr-90%2OArea%20Factors bid Detail.hti6/6/2/2014 GEW-P14-008Attachment 2Page 6 of 15DandD Building Occupancy ScenarioPage 3 of 3GO:Loose IngestionRateThe secondary ingestion transfer rate ofloose removable surface activity frombuilding surfaces to the mouth duringlbuilding occupanev.0N.STAN\T(mn*2/tthr)iD6efault value used value 1.10E-04Correlation Coefficients:NoneSummary Results:90.00% of the 100 calculated TEDE values are < 2.88E&03 mrem/year.The 95 % Confidence Interval for the 0.9 quantile value of TEDE is 2.59E-03 to 3.26E-03 mree/yearDetailed Results:Note: All reported values are the npper bound of the symmetric. 95% confidence interval for the 0.9 quantile 'alueConcentration at Time of Peak Dose:Surface Concentration(dpm/100 cm**2)[[90Sr .91S9E-01[0Y 19.78E-0IPathway Dose from All Nuclides (mrem)All Pathway External nhalati SecondaryIDoseI11 neto13.26E-03 j-j-O]1770130 13.07E-01 F7511-04Radionuclide Dose through All Active Pathways (mrem)uclide All PathwaysNucl 77 Dose19OSr F-2-2E-0319n, 113.91E-05AIlNuclides 113.26E-03Dose from Each Nuclide through Each Active Pathway (mrem)file:///C:!Users/ajnardi/Documents/DandD/Sr-90%2OArea%2OFactors bidDetail.htm..6/2/2014

ý I .ýGEW-P14-008Attachment 2Page 7 of 15DandD Building Occupancy ScenarioPage ] of3~.tp~n ~ItDandD Building Occupancy ScenarioDandD Version: 2.1.0Run DatelTime: 6/2/2014 12:29:47 PMSite Name: Sr-90 AF CaicsDescription: Calculation of Sr-90 Area FactorsFileNam e:C:AUsers\,ajnardi\Docurnents\DandDf\Sr-90 Area Factors.mcdOptions:Implicit progeny doses NOT included with explicit parent dosesNuclide concentrations. are distributed among all progenyNumber of simulations: 100Seed for Random Generation: 8718721Averages used for behavioral type parametersExternal Pathway is ONInhalation Pathway is ONSecondary Ingestion Pathway is ON'Initial Activities:Area ofNuclide Contamination (m2) Distribution[90Sr lF5ICoNSTANT~dprni00 cm**2)busitifcation for concentratioii: Sr-90 Unift Vale alu 1.0017+00).Chain Data:Number of chains: 1Chain No. 1: 90SrNuclides in chain: 2Ingestion Inhalation Surface 15 cmChain Half First Fractional Second Fractional CEDE CEDE Dose Rate Dose RatePoSition Life Parent Yield Parent Yield Factor Factor Factor Factor(Sv/Bq) (Sv/Bq) ((Sv/d)/(Bg/m2)) ((Sv/d)/(Bg/m3))[90r i~t I J it.o6E+o 4I[ Ij ... [[ j1jV [.s E -08 T3.51 E-07 I 2,46E- 14 ]3.21E-16I9oY ]1 1.7+01 ll Io Io [29E0 ]2.28E-09 [4.60E-13 1[I03.E-14 .Initial Concentrations:Note: All reported values:are the upper bound of the symmetric 95% confidence interval for the 0.9 quantile valueSurface Concentration(dpmn/i00 cm**2)gOSr l5.OOE-0190 ý 0.00E+00Model Parameters:file:///C:/Users!ajnardi/DocUmentSIDandD/Sr-90%20Area%20Factors bidDetail.him6,1/2014 I I I "GEW-P14-008Attachment 2Page 8 of 15DandD Building Occupancy ScenarioGeneral Parameters:Page 2" of 3Parameter Name Description DistributionT meInBe time in he building during the CONSTAN'{hr/week)ToTm* InB lding Ioccupancy pe~riod 1NSAThwekDe~fult vlue uaed Value 4.50E4 01Thri e duration of he occupancy exposureM c[Tto:Oceupancy :Pe~riod ,period ,. of th.Cu c.c CONs'rANT(days'JIDeffult value used Value 3,65E+02Vo' hing 3 Ra211te Tte average .vlumetric breathing rateduriug CONSANmV o B e t in a e [builIding Occupancy for an 8-hour .. rk dayl C N 'A T~m *13 "hr.)DQefaiull valaue sd -- ]I VaZlu 1.40E+00RFo*:Resuspension lFffective resuspension factor during theFactor occupancy period-, RFo

• FlDefault value used __Eflective secondary ingestion transfer rate ofGW~ngesti Rate removable surface activity from building Dl)RlVEDlm52/lGO*:ingestio Rate surfaces to the mouth during building.ocupancy =GO
• FlIDefaulh value used 1!Tstart:Start Time. ithe start time of the scenario in days ICONSýTI.A NT(davs)EDefault valute used Vle0.001:'+00jTend:End Time Tlthe ending time of the scenario in days 11CONSTANT(days)Oefan,,alueu.sed IValae 3.65.E'-02IdtITXime Step Size JThe titmes tepOsize CON.STANT(day )Default valu used. ,Value 3.653+02he time steps for the history tile. Doses willPstep:Print Step Size be written o thhisio, file every n time C ONSTANT(none)'Default value used ,Vaue .00E+00A Et:Externaiimu surce area to which occupant iseeposed via external radiation during CONSTANT(m*12)Exposure Area occupancyperiod)efustlt value sused Val+e l.01F-0lAOlnh:lahahation 4minimun surface area to wthich occupant is ,_,,_,e.xposed via inhalation during occupancy CONSTANT(m**2)Exposure Area periodDetfault value used ..Value 1.00F.+01AOIng-Secondary Minimum surface area to which.occupanr isexpotsd via secondary ingestion during CONSTANT(ns*2Jingestn xposre Area c periodDefault yalte used Value 1.001L+01ejj j Minimum surface area to which occupant isAO:,:E::poure Area expused during the.occupancy period DERIVED(at'2)DQefault value usedjI: ooe ati Fraeiion of surface contaminati available CONSTANT~none.F h L o s F aoon ] r re s u s p e n s io n , a n d in g e s tio n C N T N ~ o eDefaul value used ][Volue 1.00E-01Rfo:Loose Resuspension Resuspensionfactor for loose contamination CONTINUOUS LOGARITHMIC(l/nt)Default value used Valueprobailit9.12E-06 0.00E+001. 0OE-04 7.67E-0 I1.46E-04 9.091-0flI1.62E-04 9.50E.-011.85H-04 9.901-011.90r-04 1.00E+00file:/'IC:/Users/ajnardi/Documents/DandD/Sr-90%2OArea%20Factors bidDetail.htm6/2/2014 GEW-P14-008Attachment 2Page 9 of 15DandD Building Occupancy ScenarioPage 3- of 3GO:Loose IngestionRateThe secondary ingestion transfer rate ofloome removable surface activity frornbuilding surlfces to the inoutshduring[bailding oecup,'ucyCONSTANTlmi2'11ur[1Default value used SValue 1.1OE-04Correlation Coefficients:NoneSummary Results:90.00% of the 100 calculated TEDE values are < 1.44E-03 mresr/year,The 95 % Confidence Interval for the 0.9 quantile value of TEDE is 1.29E-03 to 1.63E-03 mrem/yearDetailed Results:Note: All reported values are the upper bound of the symmetric 95% confidence interval fto the 0.9 quanolie valueConcentration at Time of Peak Dose:n ., .1j9O~r 4.94E-01190Y 114.89E-01Surface Concentration(dptn/100 cm**2)j]~1aPathway Dose from All Nuclides (mrem)*All Pathways Etra I InatinSecondary [l[ .Dose Exera Inhaaioe'stion11.63E-03 11l3.85E-06 :]11.54E-03 [--18.77E-05Radionuclide Dose through All Active Pathways (mrem)Nuclide All PathwaysI .Dose .,1[90Sr .111.61E-0-1[90Y ]11.96E-05JAII Nuclides [1 .63E-03Dose from Each Nuclide through Each Active Pathway (nirem)If NEaxterF~ na~l Inhalation Seonarv190Sr Il .97E-07 11.53E-03 18.16E-05190Y _ 3Z.65E-06 F89.S1-06 6.IOE-06file://!C:!Users/ajnardi/Documents/DandD/Sr-90%2OArea%20FactorsbidDetail.htm6/2/2014 GEW-P14-008Attachment 2Page 10 of 15DandD Building Occupancy ScenarioPage I of 3"01 01% R&Q, 4tDandD Building Occupancy ScenarioDandD Version: 2.1.0Run Date/Time: 6/2/2014 12:30:07 PMSite Name: Sr-90 AF CalcsDescription: Calculation of Sr-90 Area FactorsFileName:C:\Uscrs\ajnardi\Documents\DandD\Sr-90 Area Factors.mcdOptions:Implicit progeny doses NOT. included with explicit parent dosesNuclide concentrations are distributed among all progenyNumber of simulations: 100Seed for Random Generation: 8718721Averages used for behavioral type parametersExternal Pathway is ONInhalation Pathway is ONSecondary Ingestion Pathway is ONInitial Activities:Area ofContamination (m2) D u1 m90Sr 113 .. .ICONSTANT(dpn/,oo c 2)ustification coneoraion: Sr-9( Unit' Vuc I0 Chain Data:Number of chains: IChain No. 1: 90SrNuclides in chain: 2Ingestion Inhalation Surface 15 cmChain Half First Fractional Second Fractional CEDE CEDE Dose Rate Dose RateNUclide Position Life Parent Yield Parent Yield Factor Factor Factor Factor(Sv/Bq) (Sv/Bq) I((Sv/d)/(Bq/m2)) ((Sv/d)/(Bq/m3))[90Sr Illj[t,06E+04 L j[ j[j8E-0 [3.51 E-07 3.21 E-163.00~0l~ K 911.0E K 44Initial Concentrations:Note: All reported values are the upper bound of the symmetric 95% confidence interval for the 0.9 quantile valueSurface Concentration[ ucid (dpm/i 00 cm**2)19oSr 13.00E-01190Y 110.ooE0300Model Parameters:file:///C:/Users/ajnardi/Documents/DandD/Sr-90%2OArea%2OFactors bidDetail.htm.6/2!2014 GEW-P14-008Attachment 2.Page 11 of 15DandD Building Occupancy ScenarioPage 2of3General Parameters:Parameter Name Description DistributionFile time in the building.during tireTo:Tie In Building occupancy period TDefault value used Value 4.50E+01o p The duration of the occupancy exposure CONSTANT(davsljTtoOcnep en od periodfoeffult value used Value 3.(i0EF02bude agvege volumetric breathing rate during CON...... *--VI Brea g =.te lbuilding occupancy r a 8-hour work day IOItArT m .3lr)DelAQul, a,,o used \[amte 1.40E+00RFO.:Resuspension lEffe.tivcresuspcnsion factor during the LR'IVED(t/mtFactor -[occupancy period -RFo
• 1D1fDntauic value usedE.ffective secondary ingestion transfer rate ofiGO'1t-etio Rte removable surface activity fi'om building IDE'RIVEfDm**2/hrisurfaces to the mouth during building I r"Ioccupancy = (o
• Ft 1LIet'ult vatue usedITtart:Start Time The start time of the scenario in days ' CONSTANT(days)Default valu used ]Value 0o.E+OOITend:End Time *lThe ending time 6f the scenario in days CONSTANT(davs)Efaul_ , value used vue 1.65E:+02dt:Time Step Size Irhe time step size ]CONSTANT(days)egfault value used Value 3.651+02The time steps for the history file. Doses willPstep:Print Step Size be written to the history file every n trmic CONSTANT(nonars t e p S .I 5t)efault value used .alue 1.0011+00AOExt:External Minimum surface areat. which occupant is Iexposed via external radiation during CONSTANT(ns*2)Exposure Area 1]occupancy period,Default.value used 0Value 0.t(E4+(0AOInihalatii Minimum surface area to which occupant isIa li exposed viA inhalation during occupancy CONSTANT(m**2)Exposure Area period ___________________efault. value used {{Value 1.00E+01Aolng-Seconda Minimum surface area to which occupant isA* lg" econdy exposed vis secondary ingestion during CONSTANT(m*2)Iingestion ~xposu7reArea ioccupancy periodDefault value used I Valu._.._e 1.00F,01lAMinimum surface area to which occupant is. IE Vr,"D(n**2)IAOexposuI e Aea Issed during the occupancy periodDlfault vaue ued ]Fractinn of surface contarmination available CNTN~oeFhLooseFraction to espesionand ingestionDefault anle used Vaue toQE.Olfo:LooseResuspenson Resuspension factor for loose contamination CONTINUOUS LOGARITIIMIC(iu)Deaault value used VYauk Probbiltv9.12E-06 ().OOE+00S. I OE-OJ 7.67E-011.46E-04 9.09E-011.62E-04 9.S0E-011 .g8E-()4 9.90E-011.90E-04 I.OOE+O0file'J//C:/Users/ajnardi/Documents/DandD!Sr-90%2OArea%20Factors bidDetail.htm6/2/2014

1. 1 , ý,GEW-P14-008Attachment 2Page 12 of 15DandD Building Occupancy ScenarioPage 3 of 3GO:Loose IngestionRatelTIhe swcund'ry ingestion rate (ifloose removable surface activily frombuilding surticevs to the mouth duringý'bailding occupancy1CONSlAW,(m.*2,br)........... ..-1.Ilnefault valuc usedhLiY-,'1.10E-0411Correlation Coefficients:NoneSummary Results:90.00% of the 100 calculated TEDE values are < 8.64.E-04 mrem/year.The 95 0% Confidence Interval for the 0.9 quantile value of TEDE is 7.76E-04 to 9.77E-04 mrem/yearDetailed Results:Note: All reported values are the upper bound of the symmetric 95% confidence interval for the 0.9 quantile valueConcentration at Time of Peak Dose:Surface Concentration(ii (rn/! 0 cm* "2).tgI12.96E-0I90Y .93E-01Pathway Dose from All Nuclides (mrem)9.-77E-041 = 12.3 1 E-06 ]1]9.22E-04 ]ISý1.26E-05.Radionuclide Dose through All Active Pathways (mrem)All PathwaysNuclide Dos190Sr 119.65E-04[90Y 111.17E-05JAil Nuclides 119.77E-04Dose from Each Nuclide through Each Active. Pathway. (mrem)External Inhalation Secodary190Sr 1l. 1 8E-07 .19.16E-04 -114.90E-0519Y 12.19E-06 = 15.89E-06 113.66E-06file:/tlC:/Users/ajnardi!Documents/DandD/Sr-90%2OArea%2OFactors bidDetail.htm6/2/2014 GEW-P14-008Attachment 2Page 13 of 15.DandD Building Occupancy ScenarioPage ] of34-41 Ov. .9r, 41 1..DandD Building Occupancy ScenarioDandD Version: 2.1.0Run Daterl'ime: 6/2,'2014 12:31:14 PMSite Name: .Sr-90 AF CalcsDescription: Calculation of Sr-90 Area FactorsFileName:C:\Users\ajnardi\Documents\DandD\Sr-90 Area Factors.mcdOptions:Implicit progeny doses NOT included with expkicit parent dosesNuclide concentrations are distributed among all progenyNumber of simulations: 100Seed for Random Generation: 8718721Averages used.for behavioral type parametersExternal Pathway is ONInhalation Pathway is ONSecondary Ingestion Pathway is ONInitial Activities:Area ofNncldo I Contamination(m2 Distribution190Sr ' III " IlCoNSANT-dPnlbooom-2)U-1sti-fiestion for eonmnstrtion: Sr-9t1 Unit Value -VaLue: LO0(,40o.Chain Data:Number ofchains:.1Chain No..1 : 90SrNuclides in chain:.2Chain iaif First Fractional Second Fractional CEDE CEDE Dose Rate Dose RateePosition Life Parent Yield Parent Yield Factor Factor Factor Factor[_ (Sv/Bq) (Sv/Bq) ((Svid)/(Bqlm2)) ((Svld)t(Bq/m3))!9OSr !l! 111.06E+0411 J[ ,1W 1 3. E-0'°8 3.5'1E-07 1 2.46E-14 I13.21E-1619r 12 2l.67E+OO00 .I 10 I2.91 E-09,2..I28E-09" 14:60E- 13 ]1 .03E- 14Initial Concentrations:Note: All reported values are the upper bound of the syrnmetric.95% confidence interval for the 0.9 quantlte valueNuclide Surface Concentrationý 9 u r ' i l .0 o E -o ]9or I1o.OOE-ODModel Parameters:file:/i/C:/Users/ajnardilDocuments/DandD/Sr-90%2OArea%20Factors bidDetail~htm6/2/2014

.,I I , 1,GEW-P14-008Attachment 2Page 14 of 15DandD Building Occupancy ScenarioPage 2 of 3General Parameters:Parameter Name 11 Description J7 DistributiontI the time in the building during ti .ITo:Tme In Buildinig ,.:occupancy period FCO-STANT(hriweek)Itefub value used Value 4.50E+01Tto: OccupancyP 'The duration of the occupancy exposure ONSTANTldasI)rIoO upny.. Period Fe ACNTN~asFDe'aull value used 3'jl V.65E+02The average volumetric breathing rate during CONSTANTin*'3/hr),VoBreathing Rate building occupancy for an 8-hour work dayýDefault value used JValue 1.40E+O0)RFo*1 Resuspension Efrective resuspension factor during the RIVED301n)Factor occupancy period = RFo

• Ft D (L'efault value usedEffective secondary ingestion transfer raue ofGO*:lngestion Rate& removable surfact activity from buildinig IlERIVED m2Thr)surfaces to the mouth during buildingoccupancy = GO
• FlDefault value used IrYstart:Start Time -he start timneof r'e scenario in days ICONSTANT(days)De0fault value ured Value O.OOE+.ooTend:End Time I~he ending time of the scenario in days CONSTANI(days)Default value used alue 3.65E-02]t:Time Step Size the time step size CONSTANT(days)IDefault value used L aiLie 3.65E102see The tiesteps for the history file. Doses will~Pstep:Print Step Sie be written to the history file every n tine CONSTANT(none)stepsDefaul valuetur al°ue :.00ro+0,,AOExV:External .Minimumsurfacu area to which occupant isexposed via external radiation during FCONSTIAN]'im**2)Exposure Area 2ecupanc periodDefault value used 1 Value e,.0'-OIAOInh:inhalation Minimum surface area to whdich occupant isexposed via.inhalation during occupancy CONSTANT(m**2)!Exposure Area. 1pried[Default value used value 1.00E+01iA0lg:Secondary Minimum surface area to wthich occupant isI lngestionE r Are exposed via secondary ingestion during IONS'I'ANT(m *2)!!ngestion Exposure Area eriod ,,______,.______,,,,______1-u-e .00E+0 .,Minimuussurface sreai s hich occupmat i VAO:ExPosure Area J exposed during the ocEu ancy period DERtVEDlni*2IeFtFracion vfasurlccoustaeinationvavailablefor rcsuspensiou and ingestion Ihefauli value used Valuei t OOLF-OtRfo:Loose Resuspension Resuspension factor for loose contamination CONTINUOUS I.OGARITHMIC(tim)lFactorDefault value used Value Pobabilitv9. 12E-06 0.00E*00.l10E.04. 7.67E-0I1.46E-04 9.09E-011.62E4l4 9.50E-011.85E-04 9,90E-011.90E-04 .00F+O0file:///C:/Users/ajnardi/Documents!DandD/Sr-90%2OArea%2OFactors bidDetail.htm6/2/2014 GEW-P14-008Attachment 2Page 15 of 15DandD BuildingOccupancy ScenarioPage 3 of 3GO:Loose IngestionRate.The secondary ingestion transifer rate ofjloosec remiovable snirl'ace activity from]building surfaces to the mouth during[[building OCCUpaIncy1C 7ON'STA Nt, ( mn *I21hr)1rDefault value mqed "v -alue l.ioE-0 o4Correlation Coefficients:NoneSummary Results:90.00% of the 100 calculated TEDE values are < 2.88E-04 mrem/year.The 95 %.Confidence Interval for the 0.9 quantile value of TEDE is 2.59E-04 to 3.26E-04 mrem/yearDetailed Results:Note: All reported values are the upper bound of the symmetric 95% confidence interval fur the 0.9 quontile valueConcentration at Time of Peak Dose:Surface Concentration909.88-2 n/I cm*2)9oY19.7E-02Pathway. Dose from All Nuclides (m remn)AloPthayExternal SecondaryDoe I in[gestion, '13.26E-04 117.70E-07 :]3.07E-04 .75E-05Radionuclide: Dose through All Active Pathways (mrem)r Nuclide [ All PathwaysNucIi Dose3.22E-0490Y j13.91E-06JAH Nuclides J13.26E-04Dose from Each Nuclide through Each Active Pathway (mrem)file://!C:/Users/ajnardi/Documenls/DandD/Sr-9.0%'2OArea%20Factors bidDetail.htm 66/2/2014 I .r, I I .GEW-P14-008Attachment 3Planned Survey Points Survey PointSurvey Package Number of Actual Number Exceeding the Exceeding theIdentificationu e o of Survey Points Investigation Average ReleaseSurvey Points Level LevelRCD-001 15 15 0 0RCD-002 15 15 0 0RGD-001 15 15 0 0RGD-002 15 15 0 0RND-001 19 19 0, 0RND-002 16 16 0 0ADM-IOK-001 23 23 0 0ADM-BR-001 20 20 0 0ADM-100 14 14 0 0ADM-115 14 14 0 0ADM-IK-001 14 14 0 0RBC-201 14 14 0 0ADM-000-4 14 14 0 0ADM-000-5 28 28 2 4 (1)ADM-001-1 14 14 0 0ADM-001-2 14 14 0 0ADM-201 14 14 0 0RBC-200-1 14 14 2 2 (2)RBC-201-1 14 14 2 0RBE-401 14 13 0 0RBG-101 14 14 0 0RBN-000-1 14 11 0 2(3)RBN-001 14 14 0 0RBN-001-1 14 11 0 0ADM-200 14 14 0 0ADM-101 14 14 0 0RBR-301 14 14 0 0ADM-301 14 14 0 0ADM-401 14 14 0 0Notes:(1) Four points each less than 1-meter square exceed the average release limit but not the maximum releaselimit specified in Reg Guide 1.86 Table 1. The survey unit passes the Sign Test.(2) Two points each less than 1-meter square exceed the average release limit but not the maximum releaselimit specified in Reg Guide 1.86 Table 1. The survey unit passes the Sign Test.(3) Two points exceed the average release limit. The location is part of a recognized activated structuralcomponent to be removed during demolition and disposed as LLRW.}}