ML14160A815
| ML14160A815 | |
| Person / Time | |
|---|---|
| Site: | University of Buffalo |
| Issue date: | 06/05/2014 |
| From: | Vasbinder D University of Buffalo |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| GEW-P14-008 | |
| Download: ML14160A815 (22) | |
Text
University -at Buffalo The State University ofNew York Environment, Health & Safety Services June 5, 2014 Docket 50-57 License R-77 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 -0001
Dear Sir or Madam:
This submission is in follow up to our submission, dated May 22, 2014, detailing supplemental information and data to address comments provided by ORISE and the N.R.C. regarding building release surveys performed at the University at Buffalo's Buffalo Materials Research Center to prepare the building for demolition.
A conference call was held on June 2, 2014 during which several items were identified that required further clarification.
Attached is a letter and data firom the University's Decommissioning Management Contractor, Enercon to Mr. 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 1 Inspector, Steve Hammann as well as to ORISE.
If you have any questions or wish further information, please contact me at (716) 829-3301 or dvasbind@buffalo.edu.
Sme~Y,
,6/
David R. Vasbinder Director, Buffalo Materials Research Center Cc: Ted Smith, U.S.N.R.C. Project Manager Steve Hammann, NRC Region I Nick Altic, ORISE A (ýý t,tzz
ENERCON Excellence-Every proiecO. Ever~y .()Y.
June 5, 2014 GEW-P 14-008 Mr. Dave Vasbinder Associate Director, Environment, Health, and Safety Services BMRC The State University of New York University at Buffalo 220 Winspear Avenue Buffalo, NY 14215-1034 Re: Response to June 2, 2014 Comments Mr. Vasbinder; This letter provides discussion of the technical issues addressed in our discussion June 2, 2014 with NRC and ORISE. Each of the key items identified as requiring clarification are addressed in the following sections.
Selection of Release Criteria For this project, the surface release criteria for building materials were based on the use of Regulatory Guide 1.86, "Termination of Operating Licenses for Nuclear Reactors" Table 1. This table provides average and maximum values for surface measurements and removable contamination limits. These criteria are acceptable for unrestricted release of buildings, materials, and equipment. The criteria were stated in the NRC approved decommissioning plan.
Since the average limits provided in Reg Guide 1.86 were followed, the concept of using a developed area factor following MARSSIM for elevated measurement comparison of individual survey measurements that exceed the DCGL value is not directly applicable. Reg Guide.1.86 Table I average values were selected as a conservative measure and to eliminate the need to derive site-specific DCGLs and area factors.
Statistical Analysis of Survey Units 2
Three survey units were assessed during scans and surveys using the release criteria of 1,000 dpm/100cm because SR-90 was the radionuclide of concern in that survey unit. The remainder of the survey units used the average release criteria of 5,000 dpm/1OOcm 2.
The survey package units using 1,000 dpm/1OOcm 2 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 exceed 1,000 dpm/1OOcm 2 (two measurements for RBC-200-1 and four measurements for ADM-000-5). The third survey unit (RBC-201-1) had no individual reading that exceeded 1,000 dpm/1OOcm 2. None of these six locations exceed the maximum surface concentration level of 3,000 dpm/100cm 2 in Table 1 of Reg Guide 1.86 for Sr-90.
For the six locations with measurements above 1,000 dpm/1OOcm 2, the areas were determined during the survey to be less that 1-meter square using the process described in this letter. The average concentration limit for these survey units was less than 1,000 dpm/1OOcm 2. No reading exceeded the maximum 44.9001WhI ifwr Penn F hvio7' May. vI~ PA 7,ý3368* 1 74,32 S160.3 n co ccn
June 5, 2014 GEW-P 14-008 Page 2 of 4 concentration limit of 3,000 dpm/1OOcm 2 . Thus, these survey units met the levels established in the NRC approved decommissioning plan.
At the request of NRC and ORISE, statistical analysis for RBC-200-1 and ADM-000-5 was completed based on the Sign Test and submitted for review. Use of the Sign Test is appropriate under MARSSIM because the radionuclide in question (Sr-90) is not present in the background. Statistical analysis documentation added to each survey package unit and provided to NRC and ORISE showed that the survey units passed the Sign Test. Each of these statistical analyses included a note that the Sign Test was based on an assumed area factor of 2.
Technical clarification and justification has been requested to support this assumption as stated on the statistical 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 an area 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 published area factor for Sr-90 is much higher than the very conservatively selected assumed factor of 2 used in the Sign Test.
- 2. As a further demonstration that the assumed area factor value of 2 used in the Sign Test is extremely conservative, area factor calculations for Sr-90 have been made using the NRC's DandD code. This code is widely recognized as extremely conservative. The results in the table below provide area factors for Sr-90 for various area sizes. The factor for a 1-meter square area is 10. This calculated value is much higher than the very conservatively selected factor of 2 used in the Sign Test. Supporting code output reports forthese analyses are provided in Attachment 2.
Table 1 - Area Factors for Sr-90 Size of Area above Release Limit Area Factor (square meters) 125 1 10 1 5 2 3 3.3 1 10 Assessment of Areas Exceeding the Investigation Limit NRC and ORISE have requested a description of the evaluation process for the individual survey measurements that exceeded the investigation limit.
As part of the survey process, an investigation limit was administratively selected to ensure that areas exceeding a specified value were appropriately evaluated regardless of whether the area exceeded the Mrqwlhv 4490OidWifiam~nn PA.7568 ighoy 1foy
June 5, 2014 GEW-P 14-008 Page 3 of 4 average release limit. For the BMRC surveys, this value was selected to be 75% of the average release limit. Thus, survey units with an average release limit of 5,000 dpm/1OOcm 2 had an investigation limit of 3,750 dpmi/lOOcm 2, while survey units with an average release limit of 1,000 dpm/1OOcmM 2 had an 2
investigation limit of 750 dpm/1OOcm .
Areas identified during the survey with having activity greater than the investigation limits were evaluated 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 release limit.
- If the re-scan confirmed a reading exceeded the maximum release limit, the area was remediated and re-scanned.
- If the re-scan confirmed a reading exceeded the average release limit and the area was less than 1-meter square, a direct one-minute measurement was taken at the location of the highest activity and recorded, then survey activities were continued.
- If the re-scan confirmed a reading exceeded the investigation limit but not the release limit within the 1-meter square area, a direct one-minute measurement was taken at the location of the highest activity and recorded, then survey activities were continued. 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 in survey units RBC-200-1 and ADM-000-5 but are below the maximum release limit. These six measurements were part of the Sign Test evaluations (two measurements for RBC-200-1 and four measurement 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 comments section that the measurements were part of a structurally significant location that will be removed and disposed as low-level radioactive waste (LLRW) during demolition. These two measurements are included in the total of 14.
The remaining six locations were evaluated using the investigation process described above. No readings above the average release limit were found at these locations.
Assessment of Number of Sampling Points NRC and ORISE requested confirmation that the number of sampling points met the requirements for building release for demolition. Each survey unit was individually evaluated for the number of sampling points prior to starting the field survey. The "General Instructions" section identified the number of static measurements for that specific survey unit based on statistical assessment. Maps were prepared for each survey area using the Visual Sample Plan. These maps were provided to the staff during the data collection process. Measurement locations were recorded during the survey process, and were provided in the survey unit package documentation.
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June 5, 2014 GEW-P 14-008 Page 4 of 4 Following the MARSSIM protocol, an additional 10% allowance was included for quality control along with an additional 20% allowance to account for any inaccessibility issues, data collection issues, or unanticipated issues with data collection. This information is provided in Attachment 3.
Conclusions In summary, none of the survey data exceeded the maximum release limit. Only 14 survey points exceeded, 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 but were less than the maximum release limit. The two survey units with these six data points passed the average release limit. No points exceeded the maximum release limit of Reg Guide 1.86 stated in the NRC approved decommissioning plan. The two survey units were proven to pass the Sign Test using an extremely conservative area factor assumption.
Two of the 14 points represented a known activated structural component that will be removed and disposed as LLRW during demolition.
The remaining six points exceeding the investigation limit were assessed to confirm that no material exceeded the average release limit.
In concurrence with the Reg Guide 1.86 criteria, no measurement of the surface reading was averaged over more than 1-meter square. In concurrence with Reg Guide 1.86 criteria, no measurement of the maximum surface reading was greater than 100 cm 2 since no measurement exceeded the maximum value.
Three survey units had less actual survey points than planned. During planning, each survey unit was designed with an excess number of survey points beyond the MARSSIM requirements. The actual number of survey points for these survey units, although less than planned, was still confirmed to meet the MARSSIM requirements.
We continue to believe that the building has met the release criteria in the FSS plan, the decommissioning plan, 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 Brown Manager, Environmental Services Group Project Manager Attachments cc: Robert Weller 4490.0-0d Willioi.rPTe . Highw.ay ~ r~ile:> v766 7;4;_.,33*..'
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GEW-PI4-008 Attachment 1 Table 8.2 Example Indoor Area Factors 36 m 2 25 m 2 16 m 2 9m 2 4m 2 I m2 NNuclide Co-60 1.0 1.2 1.6 2.5 5.5 22.7 Cs-137 1.0 1.2 1.7 2.6 5.7 23.5 H-3 1.0 1.4 2.3 4.0 9.0 36.0 Ni-63 1.0 1.4 2.3 4.0 9.0 36.0 Pu-239 1.0 1.4 2.3 4.0 9.0 36.0 Ra-226 1.0 1.4 2.1 3.6 8.0 32.2 Sr-90 1.0 1.4 2.2 4.0 8.9 35.7 Th-232 1.0 1.4 2.3 4.0 9.0 36.0 U-235 1.0 1.4 2.2 4.0 9.0 35.8 Zn-65 1.0 1.2 1.6 2.5 5.4 22.3
GEW-P14-008 Attachment 2 Page 1 of 15 DandD Building Occupancy Scenario Page I of 3 RE0 DandD Building Occupancy Scenario DandD Version: 2.1.0 Run Date/Time: 6/2/2014 12:32:13 PM Site Name: Sr-90 AF CaIcs
Description:
Calculation of Sr-90 Area Factors FiteName:C:\Users~ajnardi\Docutnents\DandD\Sr-90 Area Factors.ncd Options:
Implicit progeny doses NOT included with explicit parent doses Nuclide concentrations are distributed among all progeny Number of simulations: 10 Seed for Random Generation: 8718721 Averages used forbehavioral type parameters External Pathway is ON Inhalation Pathway is ON Secondary Ingestion Pathway is ON Initial Activities:
Area of Nuclide. ( ) Distributionn 190Sr 111-25 EcoNS'rANr(dpm/l 00 cm" 2)
- Jutficafi~n.
. i for conceniraion; Sr-90 Unit Value ,aioe L.OOE+00 Chain Data:
Number of chains: I Chain No. 1: 90Sr Nuclides.in chain: 2 Ingestion Inhalation Surface 15 cm Chan. HafFrs Facionl ecndFractional CEDE CEDE Dose Rate Dose Rate Puleosition Life Parent Yield Parent ield Factor Factor Factor 2 Factor 3 (Sv/Bq) (Sv/Bq) ((Sv/d)/(Bq/m )) ((Sv/d)/(Bq/m ))
9OSr t90" 13.2.11E-1II 1.06E÷04 1! 1.7-oo1 I
I.
I ZI .,'.85E:0s1I3.5IE-07
. ~ "29E012.28E-09 112.46EI 4 14.60E- 13 16 11.03E-14 Initial Concentrations:
Note: All reported values are the upper bound ofthe symmetric 95% confidence interval for the 0.9 quantile value F90Sr* ]
Surface Concentration (d pm/100 cm**2) 90Y 0o,oOE+oo Model Parameters:
file:///C:AUsers/ajinardi/Documents/DandD/Sr-90%20Area%2OFactors bidDetail..htm 6/2/2014
GEW-P14-008 Attachment 2 Page 2 of 15 DandD Building Occupancy Scenario Page 2 of 3 General Parameters:
Parameter Name Description Distribution To:im i
~
Biling-
-T Ifý ýnThe time in the building during the oecupnnlcy period LONISTANT(hr~week) oDetau vs e.ed .Vlue 4.50E++Jt 7-cyhe duration of the occupancy exposure C I [period CONSTANT(days)
Default value used \,alue 3.6512+02 VIrheaverage vohlunetric breathing rate during ONSTANT 3hr)
Vbuildingoccupancy for an 8-hourw'vork day Default value used 0E+00 I .Val4e RFo*:Resuspension Effective resuspension factor during tle DERIVED(l/m)
Factor occupancvyperiod = RFo
- Fl
,lefuttvalue used,, 7 Effective secondary ingestion transfer rate of G GO*'lngetionRate
- Ingestion Rate surfaces removahle to the mouth surface dur'ingfrom activity building building. DERIVED(im*2,lr) occupancy = GO Fl Default value used Tstart:Start Time Trhe strt time of-tle scenario indays ICONSANr(days)
Defaul value used -Iaue o.O01+00 ITend:End Time IThe ending time of the scenario in days ']IONSTANT(days)
Default value used [Value 3.65E+02 Idt:Time Step Size IThe time step size .CONSTANT(days)
Default value used - !Value 3.65E+02 The time steps for the history tile. Doses sill Pstep:Print Step Size be written to the history file every n time CONSTANT(nonc) steps Defaul, value used Value 1.ttOE+00 AOExt:External Minimum surface area to which occupant is external radiation during CONSTANTftm*2)
IExposure Area eEposed oce anc:viaperiod Default value used ,,00EValue I ,OO lAOInh:Inhalation exposed viasurface Minimum area to inhalation which occupant is during oceupancy CONSTANT(int2)
Exposure Area period Default value used .[Value 1,00E+01 AOing:Seconday =Mininusmsurface area to which occupwit is Oe:St onEposre Ar exposed via secondars ingestion during.. CONS'IANT(mn*'2)
Ingestion Exposure A occupaney period "
EDfault \aluc used Value I.OOE+01 Minimum surface area to which oceupant is DERIVED~ m*'2)
.O:Exposure Area exZpsed during the occupancy period rDefaull value used']
Fraclion of surface contamination available IFI:ose Fraeti.= o]i, forrcsresuspension and ingestion CONS'IANTtsssne)
"Defaul value used ]Value,00E-01 I Rfo:Loose Res o Ruspension factor for loose contamination CONTINIIOUS LOGARITHMICI,/m)
IFactor Default value used Value Probbilit 9.12E-06 0.O0E-f00 1.101E-0-4 7.67E-01 1.46E-04 9.09E.01 1.6213-04 9.50..-01 1.85E-04 9.90E-[ I I.9012-04 1.001E+00 file'///C:/Users/ajnardi/Documents/DandD/Sr-90%2OArea%20Factors bidDetail.him 6/12/2 01.4
GEW-P14-008 Attachment 2 Page 3 of 15 DandD Building Occupancy Scenario Page 3 of 3 The secondary ingestion transfer rate Of GO:Loose Ingestion loose rernovable surfiace activity from Rate building surfaces to the mouth during *~21br)
[ONSTAN'r(ni building occupancy Defeult value... ed .. . .1. iOE-04 Correlation Coefficients:
None Summary 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/year Detailed Results:
Note: All reported values are the upper hound of the synnmetric 95% confidence interval for the0.9 quantile value Concentration at Time of Peak Dose:
Surface Concentration (dpm/100 cn/ mt*2)
!lO0Sr 119.88E-0I 90Y 9.78E-01 Pathway Dose from All Nuclides (mrem)
All Pathways Exera a I7d Dose Inhalation Ingetion 13.26E-03 117.70E-06 713.07E-03 lll.75E-04 Radionuclide Dose through All Active Pathways (mrem)
Nuclide. All Pathways 1 11 Done
[9OSr 13.22E-03, Sm 113.91E-05 All Nuclides = 13.26E-03 Dose from Each Nuclide through Each Active Pathway (mrem) file:///C:/Users/ajnardilDocuments!DandD/Sr-90%2OArea%20Factors bidDetail.htm 6/2/2 014
GEW-P14-008 Attachment 2 Page 4 of 15 DandD Building Occupancy Scenario Page 1 of.3
- 0 DandD Building Occupancy Scenario DandDl Version: 2.1.0 Run Date/Tihiie: 6/2/2014 12:25:31 PM Site Name: Sr-90 AF Calcs
==
Description:==
Calculation, of Sr-90 Area Factors FileNanae:C:AUsers',ajnardi\Documents\DandD\Sr-90 Area Factors.med Options:
Implicit progeny doses NOT included with explicit parent doses Nuclide concentrations are distributed among all progeny Number of simulations: 100 Seed for Random Generation: 8718721 Averages used for behavioral type parameters External Pathway is ON Inhalation Pathway.is ON SecondaryIngestion Pathway is ON Initial Activities:
Nuclide Area of IContamination (in) Di-rbIiF 19I0SrI FCO NSTAN1'(dpmiIOO crnfl2)_
caon orcnentrafiow Sr-90 Unit Valtue luo Volne LOOD0E00 Chain Data:
Number of chains: I Chain No. i: 90Sr Nuclides in chain: 2 Chain Nuclide P~sit { Half Life First Fractional Second Fractional Parent Yield Parent~ Yield ingestion Inhalation CEDE Factor (Sv/Bq)
CEDE Factor (Sv/Bq)
Surface Dose Rate Factor 2
15 cm Dose Rate Factor 3
((Sv/d)/(Bq/m )) ((Sv/d)/(Bq/m ))
, .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 value Nuclide Surface Concentration (dpm/100 cm**2)
[90Y ]IO.OOE+00 I9oy 10.00&-00 Model Parameters:
file:/i/C:/Users/ajnardi/Documents/DandD/Sr-90%2OArea%20Factors bidDetail.htm 6/212014
0 1, .
GEW-P14-008 Attachment 2 Page 5 of 15 DandD Building Occupancy Scenario Page 2 of3 General Parameters:
Parameter Name Description. Distribution ih =i ui the building during the CONS'AN'lhr/seek) o TI me I .B i d n occ up an cy'p e riod!
efanh value u1ed Vlu.e 4.515E-N It:euanyPro TP periodI he duratin of the occupancy exposure CONSTANT(days)
DeSfault value used Jalue 3.65E÷,02 iVo:Breathing Rate= "t vlnicr breathing I'f, avrgFouterebet t raeduig aedr ngOSANTIm-~3/hr
...... ,s ..
use ilding occupancy for an 8-hour work day4 +
t~tatl value used Valu l.4oE+oO+
RFo**:Resuspension Effective resuspeosion. factor durino h DERIVED(I:m)
Factor 11occupancy period = RVO* F1 D)efault value used _ _ _ _ _ _
Effecive secondary ingestion transfer rate of GW neto Rat e n ovbl surfaee activity fronmbuilding c EIV.:., n"2,. hr)-
SUrfaCs 10 the mouth during building.
Defauti value ased I I.00E"O) atrtend:End Time
,lDefaudt valute used ..
IThe ending time ofthe scenarioit days kC'ONSTANT(days)
- l Valsue 3(6XE+02O Default vatue used Value-T _ 3.65E+02 Idt:Time Step Size lthe titestep size t- CONSTANT(davs)
Default value used IValu 3.65E+02 The lime steps for the history rile. Doses will Pstep:Print Step Size be written to the history file every n time CONSTANT(nunei steps Defullt valtue sued Vu 1.00E1+00 AOExt:External Minimum surface area to which occupant is Exposurerea exposed via external radiation during CONSTANTim-2)
Exposure Area occupancy period value tsed.
ekfaflrt Valise I.OOE+÷1 AO :Inhalat Minimum surlface area to which occupant is ExosurenAreao Exposure Area exposed period" via inhalation during occupancy CONSTANT~ t-2) I
- fauht valsue used _lOlJE40 Pal AOngSeondMinimum surface area to which occupansis exposed via secondary ingestion during ONSIANT(ns2)
Ingestion Exposure Area occupne period Delault value used [Value . .t0E-i+li area to whtich occupant is DERIVED(m**2)
AnExour ,rea exoe usurface Minimtnt gteocpnyper. od (*
D13fault value tsed Fraction of surface contamination available n FI seFrtion Ifor resuspensiou and ingestion CONSTANT(nonel t)efaNlt value used tOO,-Ill
,Valu tRfo.LooseResuspension Resuspensio factor l)rlose contamination CONTINUOUS LOGARITHMIC(I/rn)
Defaultuvalue used Value Pmba"ilitv 9.12E-06 0.o0(E+00 1.1OE-0t4 7.67E-01 1.46E-04 9.09E-01 1.62E-(14 9.50E-01 1.85E-04 9.90E-01 1.90E-04 L.OO10E÷0) file:/I/C:/IJsers/ajnardifDocumentS!DandDISr-90%2OArea%20Factors bid Detail.hti6/ 6/2/2014
GEW-P14-008 Attachment 2 Page 6 of 15 DandD Building Occupancy Scenario Page 3 of 3 The secondary ingestion transfer rate of GO:Loose Ingestion loose removable surface activity from . 0N.STAN\T(mn*2/tthr)
Rate building surfaces to the mouth during lbuilding occupanev iD6efault value used value 1.10E-04 Correlation Coefficients:
None Summary 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/year Detailed Results:
Note: All reported values are the npper bound of the symmetric. 95% confidence interval for the 0.9 quantile 'alue Concentration at Time of Peak Dose:
Surface Concentration
((90Sr
[0Y
. 91S9E-01 19.78E-0I (dpm/100 cm**2)
Pathway Dose from All Nuclides (mrem)
All Pathway External nhalati Secondary IDoseI11 neto 13.26E-03 j-j-O]1770130 13.07E-01 F7511-04 Radionuclide Dose through All Active Pathways (mrem) uclide All Pathways Nucl 77 Dose 19OSr F-2-2E-03 19n, 113.91E-05 AIlNuclides 113.26E-03 Dose 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. ý GEW-P14-008 Attachment 2 Page 7 of 15 DandD Building Occupancy Scenario Page ] of3 It
~.tp~n~
DandD Building Occupancy Scenario DandD Version: 2.1.0 Run DatelTime: 6/2/2014 12:29:47 PM Site Name: Sr-90 AF Caics
Description:
Calculation of Sr-90 Area Factors FileNam e:C:AUsers\,ajnardi\Docurnents\DandDf\Sr-90 Area Factors.mcd Options:
Implicit progeny doses NOT included with explicit parent doses Nuclide concentrations. are distributed among all progeny Number of simulations: 100 Seed for Random Generation: 8718721 Averages used for behavioral type parameters External Pathway is ON Inhalation Pathway is ON Secondary Ingestion Pathway is ON
'Initial Activities:
Area of Nuclide Contamination (m2 ) Distribution
[90Sr lF5ICoNSTANT~dprni00 cm**2) busitifcation for concentratioii: Sr-90 Unift Vale alu 1.0017+00).
Chain Data:
Number of chains: 1 Chain No. 1: 90Sr Nuclides in chain: 2 Ingestion Inhalation Surface 15 cm Chain Half First Fractional Second Fractional CEDE CEDE Dose Rate Dose Rate PoSition Life Parent Yield Parent Yield Factor Factor Factor Factor (Sv/Bq) ((Sv/d)/(Bg/m 2)) ((Sv/d)/(Bg/m 3 ))
[90r i~t I J it.o6E+o 4I[ Ij ... (( j1jV E(Sv/Bq)
[.s -08 T3.51 E-07 I2,46E- 14 ]3.21E-16 I9oY ]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 value Surface Concentration (dpmn/i00 cm**2) gOSr l5.OOE-01 90 ý 0.00E+00 Model Parameters:
file:///C:/Users!ajnardi/DocUmentSIDandD/Sr-90%20Area%20Factors bidDetail.him 6,1/2014
I II "
GEW-P14-008 Attachment 2 Page 8 of 15 DandD Building Occupancy Scenario Page 2"of 3 General Parameters:
Parameter Name Description Distribution T ToTm* meInBeInBlding time in he building during the CONSTAN'{hr/week)
Ioccupancy pe~riod 1NSAThwek De~fult vlue uaed Value 4.50E4 01
[Tto:Oceupancy :Pe~riod e duration of th.Cu
,period Thri he,.occupancy c.cexposureMc CONs'rANT(days'J IDeffult value used Value 3,65E+02 3
Vo'VBo e thing in Ra211te a e Tte. average vlumetric breathing rateduriug CONSANm
[builIding Occupancy for an 8-hour .. rkdayl C N 'A T~m *13 "hr.)
DQefaiullvalaue sd -- ]I VaZlu 1.40E+00 RFo*:Resuspension lFffective resuspension factor during the Factor occupancy period-, RFo
- Fl Default value used __
Eflective secondary ingestion transfer rate of 5 Rate GW~ngesti removable surface activity from building Dl)RlVEDlm 2/l GO*:ingestio Rate surfaces to the mouth during building
.ocupancy =GO
- Fl IDefaulh value used 1!
Tstart:Start Time. ithe start time of the scenario in days ICONSýTI.A NT(davs)
EDefault valuteused Vle0.001:'+00 jTend:End Time Tlthe ending time of the scenario in days 11CONSTANT(days)
Oefan,,alueu.sed IValae 3.65.E'-02 IdtITXime Step Size JThe titmes tepOsize CON.STANT(day )
Default valu used. ,Value 3.653+02 he time steps for the history tile. Doses will Pstep:Print Step Size bewritten o thhisio, file every n time C ONSTANT(none)
'Default value used .00E+00
,Vaue A Et:Externaiimu surce area to which occupant is eeposed via external radiation during CONSTANT(m*12)
Exposure Area occupancyperiod
)efustltvalue sused Val+e l.01F-0l AOlnh:lahahation 4minimun e.xposed viasurface inhalation to wthich occupant is area during ,_,,_,
occupancy CONSTANT(m**2)
Exposure Area period Detfault value used .. Value 1.00F.+01 AOIng-Secondary Minimum surface area to which.occupanr is expotsd via secondary ingestion during CONSTANT(ns*2J ingestn xposre Area c period Default yalte used Value 1.001L+01 ejj j Minimum surface area to which occupant is AO:,:E::poure Area expused during the.occupancy period DERIVED(at'2)
DQefault value used jI:
o s F aaoon Fh Looe ti ] Fraeiion ing es tio n s ion a, ndcontaminati r re sus pofe nsurface available C N T N oe~
CONSTANT~none.
Defaul value used ][Volue 1.00E-01 Rfo:Loose Resuspension Resuspensionfactor for loose contamination CONTINUOUS LOGARITHMIC(l/nt)
Default value used Valueprobailit 9.12E-06 0.00E+00
- 1. 0OE-04 7.67E-0 I 1.46E-04 9.091-0flI 1.62E-04 9.50E.-01 1.85H-04 9.901-01 1.90r-04 1.00E+00 file:/'IC:/Users/ajnardi/Documents/DandD/Sr-90%2OArea%20Factors bidDetail.htm 6/2/2014
GEW-P14-008 Attachment 2 Page 9 of 15 DandD Building Occupancy Scenario Page 3-of 3 The secondary ingestion transfer rate of GO:Loose Ingestion loome removable surface activity frorn CONSTANTlmi2'11ur Rate building surlfces to the inoutshduring
[bailding oecup,'ucy
[1Default value used SValue 1.1OE-04 Correlation Coefficients:
None Summary 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/year Detailed Results:
Note: All reported values are the upper bound of the symmetric 95% confidence interval fto the 0.9 quanolie value Concentration at Time of Peak Dose:
n ., .1 Surface Concentration (dptn/100 cm**2) j j9O~r 4.94E-01 ]
190Y a
114.89E-01 ~1 Pathway Dose from All Nuclides (mrem)
- All Pathways Etra I InatinSecondary [
l[ .Dose Exera Inhaaioe'stion 11.63E-03 11l3.85E-06 :]11.54E-03 [--18.77E-05 Radionuclide Dose through All Active Pathways (mrem)
Nuclide All Pathways Dose .,
I .
1[90Sr .111.61E-0-1
[90Y ]11.96E-05 JAII Nuclides [1.63E-03 Dose from Each Nuclide through Each Active Pathway (nirem) 190Sr If NEaxterF~ Il.97E-07 na~l 11.53E-03 Inhalation 18.16E-05 Seonarv 190Y _ 3Z.65E-06 F89.S1-06 6.IOE-06 file://!C:!Users/ajnardi/Documents/DandD/Sr-90%2OArea%20FactorsbidDetail.htm 6/2/2014
GEW-P14-008 Attachment 2 Page 10 of 15 DandD Building Occupancy Scenario Page I of 3 "0101%
R&Q,4 DandD Building Occupancy Scenario t
DandD Version: 2.1.0 Run Date/Time: 6/2/2014 12:30:07 PM Site Name: Sr-90 AF Calcs
==
Description:==
Calculation of Sr-90 Area Factors FileName:C:\Uscrs\ajnardi\Documents\DandD\Sr-90 Area Factors.mcd Options:
Implicit progeny doses NOT. included with explicit parent doses Nuclide concentrations are distributed among all progeny Number of simulations: 100 Seed for Random Generation: 8718721 Averages used for behavioral type parameters External Pathway is ON Inhalation Pathway is ON Secondary Ingestion Pathway is ON Initial Activities:
Area of Contamination (m 2 ) D u 1 m90Sr 113 .. . ICONSTANT(dpn/,oo c 2) coneoraion: Sr-9( Unit' Vuc ustification for*b I0 ooF*oo Chain Data:
Number of chains: I Chain No. 1: 90Sr Nuclides in chain: 2 K9 K44 Ingestion Inhalation Surface 15 cm Chain Half First Fractional Second Fractional CEDE CEDE Dose Rate Dose Rate NUclide Position Life Parent Yield Parent Yield Factor Factor Factor Factor 2 3 (Sv/Bq) (Sv/Bq) I((Sv/d)/(Bq/m )) ((Sv/d)/(Bq/m ))
[90Sr Illj[t,06E+04 L j[
3.00~0l~
j[j8E-0 [3.51 E-07 11.0E 3.21 E-16 Initial Concentrations:
Note: All reported values are the upper bound of the symmetric 95% confidence interval for the0.9 quantile value Surface Concentration
[ ucid (dpm/i 00 cm**2) 19oSr 13.00E-01 190Y 110.ooE0300 Model Parameters:
file:///C:/Users/ajnardi/Documents/DandD/Sr-90%2OArea%2OFactors bidDetail.htm. 6/2!2014
GEW-P14-008 Attachment 2
.Page 11 of 15 DandD Building Occupancy Scenario Page 2of3 General Parameters:
Parameter Name Description Distribution
File time in the building.during tire To:Tie In Building occupancy period T Default value used Value 4.50E+01 o p The duration of the occupancy exposure CONSTANT(davsl jTtoOcnep en od period foeffult value used Value 3.(i0EF02 bude 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+00 RFO.:Resuspension lEffe.tivcresuspcnsion factor during the LR'IVED(t/mt Factor - [occupancy period -RFo
- 1D1 fDntauic value used GO'1t-etio Rte E.ffective secondary ingestion transfer rate removable surface activity fi'om building ofiIDE'RIVEfDm**2/hri surfaces to the mouth during building I r" Ioccupancy =(o *Ft 1L Iet'ult vatue used ITtart:Start Time The start time of the scenario in days ' CONSTANT(days)
Default valu used ]Value 0o.E+OO ITend:End Time *lThe ending time 6f the scenario indays CONSTANT(davs)
Efaul_ , value used vue 1.65E:+02 dt:Time Step Size Irhe time step size ]CONSTANT(days) egfaultvalue used Value 3.651+02 The time steps for the history file. Doses will Pstep:Print Step Size be written to the history file every n trmic CONSTANT(nonar step5S . I t)efault value used .alue 1.0011+00 AOExt:External Minimum surface areat. which occupant is I exposed via external radiation during CONSTANT(ns*2)
Exposure Area 1]occupancy period, Default.value used 0Value 0.t(E4+(0 is AOInihalatii Minimum surface area to which occupant Exposure Ia Areali exposed viAinhalation during occupancy period CONSTANT(m**2) efault. value used ((Value 1.00E+01 Aolng-Seconda Minimum surface area to which occupant is A* lg"econdy exposed vis secondary ingestion during CONSTANT(m*2)I ingestion ~xposu7reArea ioccupancy period DefaultI value used Valu._.._e 1.00F,01 lAMinimum surface area to which occupant is. IE Vr,"D(n**2)
IAOexposuI e Aea Issed during the occupancy period Dlfault vaue ued ]
Fractinn of surface contarmination available CNTN~oe FhLooseFraction to espesionand ingestion Default anle used Vaue toQE.Ol fo:LooseResuspenson Resuspension factor for loose contamination CONTINUOUS LOGARITIIMIC(iu)
Deaault value used VYauk Probbiltv 9.12E-06 ().OOE+00 S.I OE-OJ 7.67E-01 1.46E-04 9.09E-01 1.62E-04 9.S0E-01 1.g8E-()4 9.90E-01 1.90E-04 I.OOE+O0 file'J//C:/Users/ajnardi/Documents/DandD!Sr-90%2OArea%20Factors bidDetail.htm 6/2/2014
- 1. 1 , ý,
GEW-P14-008 Attachment 2 Page 12 of 15 DandD Building Occupancy Scenario Page 3 of 3 lTIhe swcund'ry ingestion *ransfcr rate (if GO:Loose Ingestion loose removable surface activily from Rate building surticevs to the mouth during
.. ý'bailding occupancy 1CONSlAW,(m.*2,br)
-1
. Ilnefault valuc used hLiY-,' 1.10E-04 11 Correlation Coefficients:
None Summary 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/year Detailed Results:
Note: All reported values are the upper bound of the symmetric 95% confidence interval for the 0.9 quantile value Concentration at Time of Peak Dose:
Surface Concentration (rn/! 0 cm* "2)
(ii
. tgI12.96E-0I 90Y .93E-01 Pathway Dose from All Nuclides (mrem) 9.-77E-041 = 12.3 1E-06 ]1]9.22E-04 ]ISý1.26E-05
.Radionuclide Dose through All Active Pathways (mrem)
All Pathways Nuclide Dos 190Sr 119.65E-04
[90Y 111.17E-05 JAil Nuclides 119.77E-04 Dose from Each Nuclide through Each Active. Pathway. (mrem)
External Inhalation Secodary 190Sr 1l. 18E-07 .19.16E-04 - 114.90E-05 19Y 12.19E-06 = 15.89E-06 113.66E-06 file:/tlC:/Users/ajnardi!Documents/DandD/Sr-90%2OArea%2OFactors bidDetail.htm 6/2/2014
GEW-P14-008 Attachment 2 Page 13 of 15.
DandD Building Occupancy Scenario Page ]of3 4-41 Ov. .9r, 1..
41 DandD Building Occupancy Scenario DandD Version: 2.1.0 Run Daterl'ime: 6/2,'2014 12:31:14 PM Site Name: .Sr-90 AF Calcs
==
Description:==
Calculation of Sr-90 Area Factors FileName:C:\Users\ajnardi\Documents\DandD\Sr-90 Area Factors.mcd Options:
Implicit progeny doses NOT included with expkicit parent doses Nuclide concentrations are distributed among all progeny Number of simulations: 100 Seed for Random Generation: 8718721 Averages used.for behavioral type parameters External Pathway is ON Inhalation Pathway is ON Secondary Ingestion Pathway is ON Initial Activities:
Area of Nncldo I Contamination(m2 Distribution 190Sr ' III " IlCoNSANT-dPnlbooom-2)
U-1sti-fiestionfor eonmnstrtion: Sr-9t1Unit Value -VaLue: LO0(,40o.
Chain Data:
Number ofchains:.1 Chain No..1 : 90Sr Nuclides in chain:.2
[_
Chain iaif First Fractional Second Fractional CEDE CEDE Dose Rate Dose Rate ePosition Life Parent Yield Parent Yield Factor Factor Factor Factor 2 3 (Sv/Bq) (Sv/Bq) ((Svid)/(Bqlm )) ((Svld)t(Bq/m ))
!9OSr !l!
19r 12 111.06E+0411 2l.67E+OO00 J[ .I
,1W 3.1 10 E-0'°8 3.5'1E-07 12.46E-14 I2.91 E-09,2..I28E-09" 14:60E- 13 I13.21E-16
]1 .03E- 14 Initial Concentrations:
Note: All reported values are the upper bound of the syrnmetric.95% confidence interval for the 0.9 quantlte value Nuclide Surface Concentration 9u r '
ý9or l .0 oE- o]
iI1o.OOE-OD Model Parameters:
file:/i/C:/Users/ajnardilDocuments/DandD/Sr-90%2OArea%20Factors bidDetail~htm 6/2/2014
.,I I , 1, GEW-P14-008 Attachment 2 Page 14 of 15 DandD Building Occupancy Scenario Page 2 of 3 General Parameters:
Parameter Name 11 Description J7 Distributiont ITo:Tme In Buildinig ,.:occupancyinperiod . FCO-STANT(hriweek)
I thetime the building during ti Itefub value used Value 4.50E+01 rIoO Tto: upny..
OccupancyP Period
'The ACNTN~as duration of the occupancy exposure FeONSTANTldasI)
FDe'aull value used V.65E+02 3'jl The average volumetric breathing rate during CONSTANTin*'3/hr)
,VoBreathing Rate building occupancy for an8-hour work day
ýDefault value used JValue 1.40E+O0)
RFo*1 Resuspension Efrective resuspension factor during the RIVED301n)
Factor occupancy period = RFo
- Ft D (
L'efault value used Effective secondary ingestion transfer raueof GO*:lngestion Rate& removable surfact activity from buildinig IlERIVED m2Thr) surfaces to the mouth during building occupancy = GO
- Fl Default value used I rYstart:Start Time -he start timneofr'e scenario indays ICONSTANT(days)
De0fault value ured Value O.OOE+.oo Tend:End Time I~he ending time of the scenario in days CONSTANI(days)
Default value used alue 3.65E-02 Step Size the time step size
]t:Time CONSTANT(days)
IDefault value used L aiLie 3.65E102 The tiesteps for the history file. Doses will see
~Pstep:Print Step Sie be written to the history file every ntine CONSTANT(none) steps Defaul valuetur :.00ro+0,, al°ue AOExV:External . Minimumsurfacu area to which occupant is exposed via external radiation during FCONSTIAN]'im**2)
Exposure Area 2ecupanc period Default value used Value 1 e,.0'-OI AOInh:inhalation Minimum surface area to whdich occupant is exposed via.inhalation during occupancy 1pried CONSTANT(m**2)
!Exposure Area.
[Default value used value 1.00E+01 iA0lg:Secondary Minimum surface area to wthich occupant is ingestion during IONS'I'ANT(m *2) r Are lngestionEExposure I!!ngestion uccupenc*via secondary Area exposed eriod ,,______,.______,,,,______
efau9*ltvateused 1-u-e .00E+0 .
,Minimuussurface sreais hich occupmat i AO:ExPosure Area J exposed during the ocEu ancy period V DERtVEDlni*2I eFtFracion vfasurlccoustaeinationvavailable for rcsuspensiou and ingestion I hefauli value used Valuei t OOLF-Ot Rfo:Loose Resuspension Resuspension factor for loose contamination CONTINUOUS I.OGARITHMIC(tim) lFactor Default value used Value Pobabilitv
- 9. 12E-06 0.00E*00
.l10E.04. 7.67E-0I 1.46E-04 9.09E-01 1.62E4l4 9.50E-01 1.85E-04 9,90E-01 1.90E-04 .00F+O0 file:///C:/Users/ajnardi/Documents!DandD/Sr-90%2OArea%2OFactors bidDetail.htm 6/2/2014
GEW-P14-008 Attachment 2 Page 15 of 15 DandD BuildingOccupancy Scenario Page 3 of 3 The secondary jloosecremiovableingestion snirl'ace transifer activity rate from of GO:Loose Ingestion Rate. ]building surfaces to the mouth during Nt, *I21hr)
( mn 1C7ON'STA
((building OCCUpaIncy 1rDefault value mqed "v -alue l.ioE-0o4 Correlation Coefficients:
None Summary 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/year Detailed Results:
Note: All reported values are the upper bound of the symmetric 95% confidence interval fur the 0.9 quontile value Concentration at Time of Peak Dose:
Surface Concentration 909.88-2 n/I cm*2) 9oY19.7E-02 Pathway. Dose from All Nuclides (m remn)
AloPthayExternal Secondary Doe in[gestion,I '
13.26E-04 117.70E-07 :]3.07E-04 .75E-05 Radionuclide: Dose through All Active Pathways (mrem) r Nuclide NucIi
[ All Pathways Dose 3.22E-04 90Y j13.91E-06 JAH Nuclides J13.26E-04 Dose from Each Nuclide through Each Active Pathway (mrem) file://!C:/Users/ajnardi/Documenls/DandD/Sr-9.0%'2OArea%20Factors bidDetail.htm 6 6/2/2014
I. r, I I.
GEW-P14-008 Attachment 3 Planned Survey Points Survey Point Survey Package Number of Actual Number Exceeding the Exceeding the Identificationu e o of Survey Points Investigation Average Release Survey Points Level Level RCD-001 15 15 0 0 RCD-002 15 15 0 0 RGD-001 15 15 0 0 RGD-002 15 15 0 0 RND-001 19 19 0, 0 RND-002 16 16 0 0 ADM-IOK-001 23 23 0 0 ADM-BR-001 20 20 0 0 ADM-100 14 14 0 0 ADM-115 14 14 0 0 ADM-IK-001 14 14 0 0 RBC-201 14 14 0 0 ADM-000-4 14 14 0 0 ADM-000-5 28 28 2 4 (1)
ADM-001-1 14 14 0 0 ADM-001-2 14 14 0 0 ADM-201 14 14 0 0 RBC-200-1 14 14 2 2 (2)
RBC-201-1 14 14 2 0 RBE-401 14 13 0 0 RBG-101 14 14 0 0 RBN-000-1 14 11 0 2(3)
RBN-001 14 14 0 0 RBN-001-1 14 11 0 0 ADM-200 14 14 0 0 ADM-101 14 14 0 0 RBR-301 14 14 0 0 ADM-301 14 14 0 0 ADM-401 14 14 0 0 Notes:
(1) Four points each less than 1-meter square exceed the average release limit but not the maximum release limit 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 release limit 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 structural component to be removed during demolition and disposed as LLRW.