ML15245A525
| ML15245A525 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 08/31/2015 |
| From: | Bailey E Oak Ridge Institute for Science & Education |
| To: | John Hickman Reactor Decommissioning Branch |
| References | |
| DCN 5271-SR-01-0, RFTA No.15-005 | |
| Download: ML15245A525 (33) | |
Text
August 31, 201"5 Mm* John Hickman.
US. Nuclear Regulatory Colnmission Office of Nu~clear MVateriaj Safety, anrd Safeguards Division of Decomrtissiornhng, .Uran*i'um Recovery,* and Waste Progarams.
Reactor Decoinn-issioning Branch 1154:5 Rockvillc Pike
.Rockville, MD 20852
SUBJECT:
FINAL REPORT--INDEPENDENT CONFIRMATORY SURVEY
SUMMARY
AND RESULTS FOR THE CRIB HOUSE AND NON-IMPACTED OPEN LAND AREAS AT THE ZION NUCLEAR POWER STATION, ZION, ILLINOIS (RFTA NO.15-005); DCN 5271-SR-01-0
Dear Mr. Hickman:
ORAU is pleased to provide the enclosed final report detailing thae independent .confifrnatoi-y surv~ey activities of the Crib House and the nonimpacted open land areas at. the Zion Nuclear Power Station in Zion, Illinois. This report, provides the sumnuaryantd results of activities performed by ORAL, under the Oak. Ridge Thsdtute for Science and Education (ORlSE) c~ntract, during the period of July 6-9, 2015.
You may contact me at 865.576.6659 or Tim Vitkus at 865.576.5073 if you ha*,e ,any qu~estions.
Sicerely-,
Eri-ka N. Bailey Survey Prtijects Manager, Health. Physicist OIRAU ENB:EMH:fs Enclosure electronic distribution: R. Edwards, NRC RLin, NRC T. Carter, NRC B. Watson; NftC S. Roberts, ORAU 'T. Vitkus, ORAU File/5!271 I * * ... . . . .
TechnicallGrou Man~ er Review Laboratory Review - I I Quali Review P.O. Boxc 117,Oak Ridge, TN 37:831
- W\vw.orau.0rg
INDEPENDENT CONFIRMATORY SURVEY
SUMMARY
AND RESULTS FOR THE CRIB HOUSE AND NON-IMPACTED OPEN LAND AREAS AT THE ZION NUCLEAR POWER STATION, ZION, ILLINOIS FINAL REPORT ORAU Further Together Prepared by Erika N. Bailey AUGUST 2015 Ptepared for the U.S. Nuclear Regulatory Commission Prepared by ORAU under the Oak Ridge Institute for Science and Education contract, number DE-AC05-06OR23100, with the U.S. Department of Energy under interagency agreement (NRC FIN No. F-1244) between the U.S. Nuclear Regulatory Commission and the U.S. Department of Energy.
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ORAU INDEPENDENT CONFIRMATORY SURVEY
SUMMARY
AND RESULTS FOR THE CRIB HOUSE AND NON-IMPACTED OPEN LAND AREAS AT THE ZION NUCLEAR POWER STATION, ZION, ILLINOIS
- 1. INTRODUCTION The Zion Nuclear Power Station (ZNPS) was operated by Exelon Generation Company (Exelon) and is currently being decommissioned by a division of EnergySolrntions called ZionSolz,/ions, LLC (ZS). The ZNPS operated commercially from 1973 to 1997. Cessation of nuclear operations was certified in 1998 after both reactor units had been defueled and the fuel assemblies had been placed in the spent fuel pools. Both units were then placed in a SAFSTOR condition until final decommissioning and dismantlement began in 2010. At that time, the U.S. Nuclear Regulatory Cormmission (NRC) operating license was transferred from Exelon to the decommissioning company, ZS. Decommissioning activities are expected to be completed by 2020. Upon successful completion of decommissioning activities, control and responsibility for the site will be transferred back to Exelon (EC 2015).
The NRC is responsible for oversight of permitted license activities that are currently being conducted at the ZNPS. The NRC requested that ORAU, under the Oak Ridge Institute for Science and Education (ORISE) contract, perform confirmatory surveys of the remaining portions of the Crib House and assess the radiological status of the non-impacted open land areas.
- 2. SITE DESCRIPTION The ZNPS is located in Lake County, Illinois on the easternmost portion of the city of Zion. It is approximately 40 miles north of Chicago, Illinois and 42 miles south of Milwaukee, Wisconsin (Figure A-i). The overall site is comprised of approximately 200 acres and is situated between the northern and southern parts of Illinois Beach State Park on the western shore of Lake Michigan (EC 2015 and ZS 2014).
While ZNPS was operational, the Crib House contained the pump housings for six circulatory pumps that provided cooling water, drawn from Lake Michigan, to Turbine Building heat exchangers and condensers, as well as sumps and sump system components. The majority of the Crib House has already undergone dismantlement. The remaining portion of the Crib House Zion Confirmatory Survey Report157 1 5271-SR-01-0
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o -RAL; consists of the below-grade structure (i.e., basement) which spans between 588 feet and 532 feet above sea level. Historical contamination was not identified in the remaining structures and based upon use and the historical results, ZS designated the sub-grade structures as Class 3 for final status survey.
A large majority of the site footprint is comprised of open land areas that have been classified as non-impacted. Most of the non-impacted land area survey units are located to the west of Radiologically Restricted Area (RRA) fence, although there are small areas north and southwest of the fence. Lake Michigan forms the eastern boundary to the RRA fence. Figure 2.1 shows the non-impacted land area survey units as green-shaded areas.
1vigure L.I. LrNP* LancU Area survey Uflts
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ORAU3. OBJECTIVES The objectives of the confirmatory survey activities were to provide independent contractor field data reviews and to generate independent radiological data for use by the NRC in evaluating the accuracy and adequacy of the licensee's procedures and results.
- 4. APPLICABLE SITE GUIDELINES The primary radlionuclides of concern (ROCs) at the ZNPS are beta-gamma emitters--fission and activation products--resulting from reactor operation. Licensee documentation states that five specific ROCs accounted for 99.5%/ of the total activity at ZNPS (ZS 2015). Specific building surface activity guidelines are not applicable for the Crib House because the above-grade structure has been demolished and the debris will not remain on site. Instead, the remaining building surfaces were evaluated based on maximum inventory levels per square meter area that corresponded to a total dose of 25 rmillirem per year (mrem/year). Table 4.1 provides the per square meter maximum inventories for each of the five ROCs.
S S - S - -
ROC Inventory (pCi/mn Limit 2)
Co-60 9.28E+07 Cs-134 3.58E+07 Cs-I137 4.95E+07 Ni-63 5.64E+09 Sr-90 1.94E+06 The volumetric soil and buried pipe derived concentration guideline levels (DCGLw\~s) for impacted areas of the site are listed in Table 4.2. However, ORAU notes that these DCGLws are not applicable to survey units assigned a non-impacted designation--the focus of ORAU's confirmatory activities during this site visit. Any positive identification of site ROCs not expected to be present in background in a non-impacted area would require reclassification as impacted.
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ORAU
. .* , . es
- si RCSurface Soil Subsurface Soil Buried Pipe (pCi/g) (pCi/g) (dpm/1O0 cm 2)
Co-60 4.7 3.8 3.60E+04 Cs-134 7.5 4.9 6.33E+04 Cs-137 15.7 8.5 1.50E+05 Ni-63 3988 847 1.31E+08 Sr-90 14.3 1.8 3.49E+/-05
'From Chap)ter 5 in the license termination plan (ZS 2014b)
Each radionuclide-specific DCGL\v represents the concentration above background of a residual radionucdide that would result in a radiological dose of 25 intrnm/yr to the average member of the critical group. Because each individual*DCGLw, represents 25 mrem/yr, the sum-of-the-fractions (SOF) approach is used to demonstrate compliance with the dose limit for impacted areas of the site. SOF calculations are performed as follows:
n SOFToTAL = SOFj = DCG-Lw,J j=O0 Where Ciis the concentration of COG "j," and DCGL~v 1 is the DCGLWv for COG "j." Note that gross concentrations are considered here for conservatism. The analytical results presented in Tables B-2 and B-3 were evaluated and compared to the applicable DCGL~vs presented in Table 4.2.
SOF calculations are not applicable to samples from the non-impacted areas of the site and due to the extremely low radionuclide concentrations in the samples from impacted areas and only a few values being above the analytical minimum detectable concentrations (MDCs), ORAU did not perform SOF calculations.
- 5. PROCEDURES The confirmatory survey activities were conducted during the period of July 6-9, 2015, in accordance with the project-specific confirmatory survey plan, the ORAU Radiological and Environmental Survey ProcedureManual and the ORAU EnvironmentalServices and Radiation Training
~Qual4'y Program Manual (ORAU 2015a, 2015b, and 2015c).
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5.1 SURFACE SCANS ORAU ORAU performed high-density gamma radiation scans of the accessible lower surfaces inside the Crib House. Five random locations were also selected for high-density beta scans where ZS had performed in situ gamma spectroscopy measurements on remaining structural surfaces of the Crib House. Beta scans were performed using Ludlum Model 44-142 plastic scintillation detectors and gamma scans using Ludium Model 44-10 sodium iodide (NaI) detectors coupled to Ludlum Model 2221 ratemeter-scalers with audible indicators. Gamma scans were also performed on accessible exterior portions of the roof of the Crib House where the gamma detector/ratemeter pairs were coupled to global positioning systems (GPS) that enabled real-time gamma count rate and spatial data capture (Figure A-2).
In addition to randomly selected locations for the non-impacted open land areas, gamma radiation surface scans were also planned for low-lying regions, accumulation points, high-traffic pathways, and drainage paths. However, many of these areas were impacted by standing water during the time of the confirmatory survey which prevented ORAU personnel from collecting useful scan data.
Therefore, ORAU only performed scans in the vicinity of seven randomly selected locations.
Figures A-3 through A-9 present the gamma walkover survey data for the open land areas as well as the surface soil sample locations from each area.
5.2 DIRECT SURFACE ACTIVITY MEASUREMENTS Qualitative and quantitative surface activity measurements were collected from within the Crib House to assess residual activity levels within each of the five randomly selected ZS in situ gamma spectroscopy measurement locations. The ZS in situ measurements were made such that the detector field-of-view (FOV) covered an area of 28 in-. The five randomly selected locations corresponded to the ZS location IDs of RWC-004-1, RWC-009-1, RWC-003-1, RWC-014-1, and RWC-005-1. Since there were no elevated radiation levels of concern detected during scans, ORAU collected five evenly spaced beta direct measurements spanning the FOV for each selected in situ location with the exception of two floor measurement locations. In these two locations, the FOVs overlapped with the remaining water pump components and wall locations where ORAU was unable to collect the two measurements above three meters (scaffolding was not available). Figure 5.1 shows the Zion Confirmatory Survey Report552 5 -RO-5271-SR-01-0
ORAU measurement/numbering format used to collect the direct measurements within the selected in situ measurement locations.
/{ ( 5
/ \
Figure 5.1. Beta Measurement and Concrete Sampling Illustration 5.3 MISCELLANEOUS MATERIAL AND SOIL SAMPLING Concrete sampling followed the same approach described for direct surface activity measurements within the Crib House. An incremental concrete sample was collected from each of the five direct measurement locations (following the collection of the surface activity measurements) from each of the randomly selected ZS in situ measurement areas. The five increments associated with one in si/u measurement location were packaged separately in the field and then homogenized and combined into one composite sample (using equal weights from each increment) at the Radiological and Environmental Analytical Laboratory (REAL) in Oak Ridge, Tennessee. In total, ORAU collected 25 increments which resulted in five composite samples from the Crib House.
In addition to concrete samples, the NRC requested that two judgmental samples be collected of the residual sediment materials observed inside the remaining pump components. The NRC and ORAU identified two pumps (lB and 2B) containing enough sediment material to be sampled.
Zionl ConfirmatoU Survey Report652-S-O-( 6 5271-SR-01-0
ORAU Seven surface soil samples were collected from non-impacted open land area survey units, as presented in Figures A-3 through A-9. These locations were randomly generated using Visual Sample Plan (VSP) Version 7.4 software.
- 6. SAMPLE ANALYSIS AND DATA INTERPRETATION Samples and data collected on site were delivered to the ORAU/ORISE facility for analysis and interpretation. Sample custody was transferred to the REAL in Oak Ridge, Tennessee. Sample analyses were performed in accordance with the OIRAU Radiologicaland EnvironmentalAna~y/ical Laborato~y ProceduresManual (ORAU 201 5d). Concrete and soil samples were analyzed by gamma spectroscopy for gamma-emitting ROCs and results were reported in units of picocuries per gram (pCi/g). Analyses for the remaining pure beta-emitting radionuclides (Ni-63 and Sr-90) were not performed at the NRC's request.
- 7. FINDINGS AND RESULTS The results of the confirmatory survey are discussed in the subsections below.
7.1 OBSERVATIONS During survey activities within the Crib House, ORAU technicians noted that the maps for the in si/u flOOr measurement locations they were provided did not correspond to the locations where ZS staff indicated they collected some of the in si/u floor measurements. ORAU conveyed this information to the NRC to request that ZS resolve the discrepancy; however, at the issuance of this report ORAU has not been informed of a resolution. ORAU referenced measurement locations based on the in situ floor measurement location map initially provided.
7.2 SURFACE SCANS The majority of the confirmatory gamma scan results exhibited radiation levels within the detector background range. For the non-impacted areas, elevated gamma radiation count rates were observed when approaching the Independent Spent Fuel Storage Installation (ISFSI) along the eastern edge of SU 10305 (Figure A-5) and near loaded railroad cars over the western berm of SU 10303 Zion Confirmatory Survey Report752 5271-SR-01-0
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ORAU (Figure A-7). These increased count rates are expected and are not indicative of contamination.
Scans did not identify any areas for further investigation.
7.3 SURFACE ACTIVITY MEASUREMENTS The majority of the direct beta radiation activity results were consistent with typical background levels. Surface activity for the confirmatory measurement locations ranged from -300 to 2,200 dpm/100 cm 2. Three of the confirmatory measurement locations exhibited residual beta activity above the detector's MDC. The highest direct beta radiation activity for a confirmatory measurement was 2,200 dpm/100 cm 2 on the floor of the Crib House at ZS location ID RWC-004-1. Table B.1 provides a summary of the confirmatory measurement data for each location addressed during the survey.
7.4 RADIONUCLIDE CONCENTRATIONS IN MISCELLANEOUS MATERIAL AND SOIL Analytical results for the Crib House and open land area samples are provided in Tables B-2 and B-3, respectively. All five composite concrete samples from th'e Crib House exhibited ROC concentrations below the respective analytical MDCs for Co-60, Cs-134, and Cs-137 (Table B-2). A few confirmatory sediment and soil samples exhibited ROC concentrations above the respective analytical MDCs for Co-60 and Cs-137 (Tables B.2 and B.3); however, the Co-60 and Cs-137 concentrations represent a small fraction of the respective DCGL \s~. Due to the extremely low radionuclide concentrations in the samples and only a few values being above the analytical MDCs, ORAU did not perform SOP calculations. For the non-impacted land area samples, only Cs-i137 was present above the analytical MDC. Cs-137 is expected in low concentrations, therefore confirming the non-impacted designation.
- 9.
SUMMARY
At the NRC's request, ORAU conducted confirmatory survey activities within the remaining portions of the Crib House and the non-impacted open land areas at the ZNPS during the period of July 6-9, 2015. The survey activities included visual inspections, gamma and beta radiation surface scans, gamma and beta radiation measurements, and soil and miscellaneous sampling.
Zion Confirmatory Survey Report852 8 5271-SR-01-0 SROO
ORAU The majority of gamma surface scans and total surface activity measurements were not distinguishable from background. The two sediment samples collected from the pumps within the Crib House contained radionuclide concentrations above analytical MDCs for both Co-60 and Cs-137, but all sample concentrations were well below the respective DCGL~1 s. Six of the seven surface soil samples collected from the non-impacted land areas contained Cs-i137 concentrations above the analytical MDCs but were also well below the Cs-137 DCGLw; low concentrations of Cs-137 is expected in background samples.
The only potential documentation issue identified was the in situ floor measurement location discrepancy between the maps provided to ORAU and where ZS staff indicated the measurements were performed. However, based on the results of the confirmatory survey activities, ORAU is of the opinion that the Crib House and non-impacted open land areas satisfy the site criteria for release from radiological controls.
Zion Confirmatory Survey Report 9 957-RO- 5271-SR-01-0
ORAU 10. REFERENCES EC 2015. The Future of Zion. Webpage: http: / / www.exeloncorp.com /P owerPlants / zion /Pages /
aboutdecommissioning.aspx. Exelon Corporation. Chicago, Illinois. Accessed June 30.
ORAU/ORISE 2014. Radiation ProtectionManual. Prepared by ORAU under thae Oak Ridge Institute for Science and Education contract. Oak Ridge, Tennessee. October.
ORAU 201 5a. Project-SpecijicPlanfor the Confirmatory Survejy Activities at the Zion Nuclear Power Station, Crib House and Non-Impacted Open LandAreas, Zion Illinois. 5271-PL-01-0. Oak Ridge Institute for Science and Education, managed by Oak Ridge Associated Universities. Oak Ridge, Tennessee.
July 2.
ORAU 2015b. ORAU Radiologicaland EnvironmentalSurvey ProceduresManual. Oak Ridge Institute for Science and Education, managed and operated by ORAU. Oak Ridge, Tennessee. August 6.
ORAU 2015c. ORAU EnvironmentalServices and Radiation Training~Quali~yProgramManual.ORAU.
Oak Ridge, Tennessee. August 7.
O RAU 2015d. ORAU Radiologicaland EnvironmentalAnalyticalLaboratoryProceduresManual.Oak Ridge Institute for Science and Education, managed and operated by ORAU. Oak Ridge, Tennessee.
May 7.
ORAU 2.015e. Health and Safety Manual. ORAU. Oak Ridge, Tennessee. June.
ZS 2014. Zion Station Restoration Project License Termination Plan: Chapter2 Site Characteriz<ation,Rev. 0.
ZionSolutions, LLC. Chicago, Illinois. December 19.
ZS 2015. STS Package Zion Crib House: STS Sample Plan B3-O81OIA-F. ZionSolutions, LLC. Chicago, Illinois. June 25.
Zion Confirmatory Survey Report1057-R10 10 5271-SR-01-0
APPENDIX A FIGURES Zion Confirmatory Survey Report52 5271-SR-01-0
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Figure A-i. Location of the Zion Nuclear Power Station, Zion, Illinois Zion Confirmatory Survey Report ,\-1 5271I-SR-01 -0
A CPM 6211 -6749 *
- 4951 5370 4531 --4950 LJBoundary U Random Samples Zion NPS Top of Crib 5791 -6210 4111 -4530 Gamma Walkover 5371 - 5790 * <4110
- _
0 2.5 5 ORAU (C'ssts" by: A. Kirtb~nk D.¢: Ju.Iis. 2015 Meters Y ilx*V GIS *! Zg*tl Figure A-2. Top of Crib House-Gamma Walkover Scan Zion Confirmatorx Survey Report 5271 -SR-01-O)
CPM 7501 -
9265 4351 - 5050 3651 - 4350 I.....
U Boundary Random Sampl Zion NPS Random Sample 6451 - 7500 2951 - 3650 Location 5751 - 6450 2251 - 2950 f"lRAI ! 5271S0008 5051 - 5750 <2250 o 8o 160 I v
- an Creatd by: A. Kirthlnk Date:July 15. 0L Meters V *LW\ GIS 52 I I.,n, Figure A-3. Non-Impacted Land Area, SU10215-Gamma Walkover Scan and Sample Location 5271S0008 Zion Confirmatory" Survey Report 527 1-SR-01-4)
A CPM 7501 - 9265 4351 3651 -
5050 4350 LJ U
Boundary Random Sampi Zion NPS Random Sample 64l51 -7500 BB2951 -3650 Location 5751 - 6450 2251 - 2950 5271S0009
(~DAI U 5051 - 5750 <2250 o 80 160 ______________"_______
Created hby:A. Khrthink Date: JuIy 15,2015 Meters Figure A-4. Non-Impacted Land Area, SU10216v--Gamma Walkover Scan and Sample Location 5271S0009 Zion Confirmatory Survey Report 5271-~SR-01 -0
A CPM 4351 - 5050 LJ Boundary Zion NPS Random Sample
- 7501 6451 -9265
-7500 3651 -4350 2951 -3650 U Random Samples Location 5751 - 6450 2251 - 2950 5271S0010
(~DAI I 5051 - 5750 <2250 0 ir--60 Created by: A. Kierthink Date: July 15, 2015 Meer V SEX'(45 I Figure A-5. Non-Impacted Land Area, SU10305--Gamma Walkover Scan and Sample Location 5271S0010 Zion Confirmatory Survey Report 5271 -SR-01 -0
A CPM 7501 - 9265 4351 - 5050 3651 - 4350 L..U Boundary Random Sampl Zion NPS Random Sample 64m51 -7500 2951_-3650 L.ocation 5751 - 6450 2251 - 2950 5271S0011
(~RAI I 5051 -5750 <2250 o 80 160 v-. t ,=~
I C~reed by: A. KinrhLnk Date: July ISg,2015 Meters Figure A-6.Non-Impacted Land Area, SU10402-Gamma Walkover Scan and Sample Location 5271S0011 Zion Confirmatory Survey Report 527 1-SR-01-0
CPM 7501 - 9265 4351 3651 5050 4350 LJ U
Boundary Random Samples I 6451 -7500 II 2951 -3650 5751 -6450 2251 - 2950 5051 - 5750 <2250 0 8 160 Cxcated by: A. ]Krnhlink Date: July t5, 2015 Mete, N 1E~AN(.P,Sit.,,,
Figure A-7. Non-Impacted Land Area, SU10303--Gamma Walkover Scan and Sample Location 5271S0012
/ion Confirmatory Survey Report A-7 5271 -SR-01 -(
A CPM 7501 - 9265 4351 5050 L=J 3651 -- 4350 U Boundary Random Sampi Zion NPS Random Sample 6451 - 7500 2951 - 3650 Location 5751 - 6450 2251- 2950 5271S0013 5051 - 5750 <2250
~ U I re e by: A. Kirthlnk Date July 15, 2015 Meters XF%(L*
(.15 * '
Figure A-8. Non-Impacted Land Area, SU10303--Gamma Walkover Scan and Sample Location 5271S0013 Zion Confirmatory Survey Report 5271 -SR-(01-0)
Figure A-9. Non-Impacted Land Area, SU10305--Gamma Walkover Scan and Sample Location 5271S0014 Zion Contirmatory Survey Report 5271 -SR-)01-i
APPENDIX B DATA TABLES Zion Confirmatory Survey Report52 -ROO 5271-SR-01-0
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- a * . a Gross Gamma Gross Beta INet Ileta *urtace Iqet Jieta 3urtace ZS Location ID LocationlID ORAU Order of, Count Rate Count Rate Activity Activity Surface Measurements 2 )a (cpm) (cpm) S(dpm/1O0 cru (pCi/m 2)a RWC-004-1 5271M0001 Floor 1 5,624 613 1046 4.71E+04 Floor 2 5,801 582 728 3.28E+04 Floor 3 5,768 544 338 1.52E+04 Floor 4 5,801 726 2205 9.93E+04
_______ _______ Floor 5 5,869 616 1077 4.85E+04 RWC-009-1 5271M0002 Floor 1 5,721 534 236 1.06E+04 Floor 2 5,416 543 328 1.48E+04 Floor 3 5,689 506 -51 -2.31E+03 Floor 4 5,939 517 62 2.77E+03
_______ _______ Floor 5 5,732 496 -154 -6.93E+03 RWC-003-1 5271M0003 East Wall 1 5,233 206 -297 -1.34E+04 East Wall 2 4,956 254 195 8.78E+03 East Wall 3 5,150 225 -103 -4.62E+03 East Wall 4 5,231 249 144 6.47E+03
______________ East Wall 5 5,502 237 21 9.24E+02 RWC-014-1 5271M0004 North Wall 1 5,449 256 215 9.70E+03 North Wall 2 5,463 247 123 5.54E+03 North Wall 3 5,398 227 -82 -3.70E+/-03 North Wall 4 5,733 231 -41 -1.85E+/-03
______________ North Wall 5 5,664 257 226 1.02E+04 RWC-005-1 5271M0005 West Wall 1 4,824 223 -123 -5.54E+03 West Wall 2 4,688 215 -205 -9.24E+/-03 West Wall 3 4,673 221 -144 -6.47E+/-03 West Wall 4 4,629 235 0 0.00E+00
______________ West Wall 5 4,736 256 215 9.70E+03 Detectors calibrated to Tc-99.
Zion Confirmatory Survey Report B-1 B-I 527l-SR-01-0
SampleTypeDataor ORAU IDSample Zi s tu'
- Location ID Co-00 (pCi/g)
I (pCi/g) t...S-1 I, Concrete Samples from the Crib House Random 5271M0001 RWC-004- 0.002 + 0.041, 0.088 0.021 -_-0.038, 0.088 0.016 +/- 0.037, 0.084 5271M0002 RWC-009-1 0.010 + 0.027, 0.064 0.031 + 0.027, 0.071 -0.001 + 0.031, 0.068 5271M0003 RWC-003-1 -0.005 _+0.016, 0.032 0.009 _+0.015, 0.035 0.006 +/-+0.0088, 0.0207 5271M0004 RWC-014-1 0.002 +_ 0.014, 0.032 0.003 __0.015, 0.033 0.000 +/-+0.014, 0.032 5271M0005 RWC-005-1 0.020 + 0.019, 0.047 0.008 +/-+0.021, 0.047 0.005 +/-_0.016, 0.036
___________Sediment Samples collected from select pumps within the Crib House Judgmental 5271S0006 Pump lB J0.052 + 0.022, 0.041 ] 0.021 _+0.020, 0.048 [0.044 +/-+0.016, 0.029 5271S0007 Pump 2B 0.363 +/-+0.047, 0.053 0.030 _+0.029, 0.067 0.151 +/-_0.028, 0.042 aUncertainties represent the 95% confidence level, based on total propagated uncertainties.
bMDC =minimum detectable concentration; these are the values after the comma c=zero value due to rounding
.3r me a - . i 6
/- )Zs. .
- Soil Samn1es from the Non-Imnacted Onen Land Areas 527180008 10215 0.005 + 0.020, 0.045 0.002 _+0.019, 0.042 0.136 + 0.022, 0.027 5271S0009 10216 -0.009 + 0.010, 0.041 -0.007 + 0.013, 0.046 0.255 +/-+0.031, 0.025 5271S0010 10305 -0.003 + 0.017, 0.040 0.021 + 0.016, 0.040 0.253 +/-_0.030, 0.025 5271S0011 10402 0.002 + 0.017, 0.037 -0.0039 + 0.0088, 0.0340 0.040 +/-_0.012, 0.022 5271S0012 10303 -0.023 _+0.030, 0.055 0.025 _+0.021, 0.053 0.264 +/- 0.036, 0.034 5271S0013 10303 0.014 _+0.027, 0.060 0.019 _+0.023, 0.054 0.063 +/-_0.020, 0.036 527180014 10305 -0.006 + 0.021, 0.044 -0.0059 _+0.0062, 0.0462 0.013 _+/-0.011, 0.026
'Uncertainties rep*resent the 95% confidence level, based on total propagated uncertaintics.
bMDC =minimum detectable concentration; these are the values after the comma Zion Confirmatory Survey Report B-2 B257-RO- 5271-SR-01-0
APPENDIX C SURVEY AND ANALYTICAL PROCEDURES Zion Confirmatory Survey Report57 5271-SR-01-0
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C.1 PROJECT HEALTH AND SAFETY ORAU performed all survey activities in accordance with the OIRAU/ORI[SE Radiation Protection Manual, the OR~AU Health and Safety Manual,and the ORAU Radiological and EnvironmentalSurvey ProceduresManual (ORAU/ORISE 2014, ORAU 2015e, and ORAU 2015b). Prior to on-site activities, a work-specific hazard checklist was completed for the project and discussed with field personnel. The planned activities were thoroughly discussed with site personnel prior to implementation to identify hazards present. Additionally, prior to performing work, a pre-job briefing and walk down of the Crib House were completed with field personnel to identify hazards present and discuss safety concerns. Should ORAU have identified a hazard not covered in the ORAU Radiologicaland EnvironmentalSurvejy ProceduresManual or the project's work-specific hazard checklist for the planned survey and sampling procedures, work would not have been initiated or continued until it was addressed by an appropriate job hazard analysis and hazard controls.
C.2 CALIBRATION AND QUALITY ASSURANCE Calibration of all field instrumentation was based on standards/sources, traceable to National Institute of Standards and Technology (NISTF).
Field survey activities were conducted in accordance with procedures from the following ORAU documents:
- ORAU Radiologicaland EnvironmentalSurve~y ProceduresManual (ORAU 201 5b)
- ORAU Radiological and EnvironmentalAna~yticalLaborato{yProceduresManual (ORAU 2015c)
- OR/lU Environmental Services and Radiation TrainingQuality ProgramManual (ORAU 201 5d)
The procedures contained in these manuals were developed to meet the requirements. of U.S. Department of Energy (DOE) Order 414.1D and the U.S. Nuclear Regulatory Commission (NRC) ~Qualily Assurance Manualfor the Office of Nuclear MaterialSafety and Safeguards and contain measures to assess processes during their performance.
Zion Confirmatory Survey ReportC-52 C-1 SRO-5271-SR-01-0
Quality control procedures include:
- Daily instrument background and check-source measurements toconfirm that equipment operation is within acceptable statistical fluctuations
- Participation in Mixed-Analyte Performance Evaluation Program, NIST Radiochemistry Intercomparison Testing Program, and Intercomparison Testing Program Laboratory Quality Assurance Programs
- Training and certification of all individuals performing procedures
- Periodic internal and external audits C.3 SURVEY PROCEDURES C.3.1 SURFACE SCANS Scans for elevated gamma radiation were performed by passing the detector slowly over the surface.
The distance between the detector and surface was maintained at a minimum. Specific scan mini~mum detectable concentration (MDCs) for the sodium iodide scintillation detectors (NaI) were not determined as the instruments w~ere used solely as a qualitative means to identify elevated gamma radiation levels in excess of background. Identifications of elevated radiation levels that could exceed the site criteria were determined based on an increase in the audible signal from the indicating instrument.
Beta scans were performed using small, hand-held scintillation detectors with a 1.2 mg cm 2 window.
Identification of elevated radiation levels was based on increases in the audible signal from the indicating instrument. Beta surface scan MD)Cs were estimated using the approach described in NUREG-1507. The scan MDC is a function of many variables, including the background level.
Additional parameters selected for the calculation of scan MDCs included a two-second observation interval, a specified level of performance at the first scanning stage of 95%/ true positive and 25%/
false positive rate, which yields a d' value of 2.32 (NUREG-1 507, Table 6.1), and a surveyor efficiency of 0.5. The beta total efficiency was 0.10 for Co-60 (calibrated with Tc-99). The detector used had a general background of 300 cpm. The minimum detectable count rate (MDCR) and scan MVDC was calculated as:
Bi- (300)(2 s)(1 main/60 s) =10 counts Zion Confirmatory Survey ReportC-52 C-2 -ROO 5271-SR-01-0
MDCR =(2.32)(10 counts)l/2 [(60 s/min)/2s] =220 cpm M[DCRsurvcyor = 220/(0.5)I/2 =311 cpm Scan MDC =(311)/(.10) =3,110 dpm/100 cm2 C.3.2 SURFACE ACTIVITY MEASUREMENTS Measurements of total beta surface activity levels were performed using hand-held scintillation detectors coupled to portable ratemeter-scalers. Count rates (cpm), which were integrated over one minute with the detector held in a static position, were converted to activity levels (dpm/ 100 cm2 )
by dividing the count rate by the total static efficiency (siX~s) and correcting for the physical area of the detector (not required for these detectors). ORAU did not determine construction material-specific background for each surface type encountered for determining net count rates. Instead, ORAU took the conservative approach followed by the licensee and subtracted instrument's ambient background for the area (varied, 235 cpm used in the example below) when determining surface activity. An example aprioriMD C for beta activity is given by:
3 + (4.65s-B)
MDC =
G Etot Where:
B = background Eto*= total efficiency G = geometry correction factor (1.0)
The a priori beta static MDC was approximately 743 dpm/100 cm 2 for Co-60.
C.3.3 MISCELLANEOUS MATERIAL AND SOIL SAMPLING Soil and sediment samples (approximately 0.5 kilogram each) were collected using a clean garden trowel, then transferred into a new sample container by ORAU personnel. The five concrete increments associated with one in situ measurement location from within the Crib House were packaged separately in the field and then homogenized and combined into one composite sample (using equal weights from each increment) at the REAL in Oak Ridge, Tennessee. In total, ORAU collected 25 concrete increments which resulted in five composite samples from within the Crib House. ORAU personnel labeled each sample in accordance with ORAU survey procedures and completed the required custody documentation.
Zion Confirmatory Survey ReportC-57 C-3 5271-SR-01-0 SROO
C.4 RADIOLOGICAL ANALYSIS C.4.1 GAMMA SPECTROSCOPY Samples were analyzed as received, mixed, crushed, and/or homogenized as necessary, and a portion sealed in a 0.5-liter Marinelli beaker. The quantity placed in the beaker was chosen to reproduce the calibrated counting geometry. Net material weights were determined and the samples counted using intrinsic, high purity, germanium detectors coupled to a pulse h~eight analyzer system. Background and Compton stripping, peak search, peak identification, and concentration calculations were performed using the computer capabilities inherent in the analyzer system. All total absorption peaks (TAPs) associated with the ROCs were reviewed for consistency of activity. Spectra were also reviewed for other identifiable TAPs. TAPs used for determining the activities of ROCs and the typical associated MDCs for a one-hour count time were:
- i- .** . a v an ~l1 Co-60 { 1.173 0.05 Cs-134 0.796 { 0.05 Cs-137 0.662 0.04
- Spectra were also reviewed for other identifiable TAPs.
C.5 DETECTION LIMITS Detection limits, referred to as M~DCs, were based on 95%/ confidence level via the NUREG-1 507 method. Because of variations in background levels, measurement efficiencies, and contributions from other radlionuclides in samples, the detection limits differ from sample to sample and instrument to instrument.
Zion Confirmatory Survey Report C-4 C457-RO- 5271-SR-01-0
APPENDIX D MAJOR INSTRUMENTATION Zion Confirmatory Survey Report57 5271-SR-01-0
-ROO
The display of a specific product is not to be construed as an endorsement of the product or its manufacturer by the author or his employer.
D.1 SCANNING AND MEASUREMENT INSTRUMENT/DETECTOR COMBINATIONS D.1.1 GAMMA Ludlum NaI Scintillation Detector Model 44-10, Crystal: 5.1 cm X 5.1 cm (Ludilum Measurements, Inc., Sweetwater, Texas) coupled to:
Ludlum Ratemeter-scaler Model 2221 (Ludlum Measurements, Inc., Sweetwater, Texas) coupled to:
Trimble Data Logger (Trimble Navigation Limited, Sunnyvale, California)
D.1.2 BETA Ludlum Plastic Scintillation Detector Model 44-142, 100 cm2- physical area coupled to:
Ludlum Ratemeter-scaler Model 2221 (ILudlum Measurements, Inc., Sweetwater, Texas) coupled to:
Trimble Data Logger (Trimble Navigation Limited, Sunnyvale, California)
D.2 LABORATORY ANALYTICAL INSTRUMENTATION High-Purity, Extended Range Intrinsic Detector CANBERRA/Tennelec Model No: ERVDS30-25 195 (Canberra, Meriden, Connecticut)
Used in conjunction with:
Lead Shield Model G-I11 (Nuclear Lead, Oak Ridge, Tennessee) and Multichannel Analyzer Canberra's Gamma Software Dell Workstation (Canberra, Meriden, Connecticut)
High-Purity, Intrinsic Detector Model No. GIVX-45200-5 CANBERRA Model No: GC4020 (Canberra, Meriden, Connecticut)
Zion Confirmatory Survey Report D-1 Dl57-RO- 5271-SR-01-0
Used in conjunction with:
Lead Shield Model G-1 1 Lead Shield Model SPG-1 6-1K8 (Nuclear Data)
Multichannel Analyzer Canberra's Gamma Software Dell Workstation (Canberra, Meriden, Connecticut)
Zion Confirmatory Survey Report D-2 D257-RO- 5271-SR-01-0