ML18255A017
| ML18255A017 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 12/23/2015 |
| From: | Bailey E Oak Ridge Associated Universities |
| To: | John Hickman Division of Decommissioning, Uranium Recovery and Waste Programs, US Dept of Energy (DOE) |
| References | |
| Download: ML18255A017 (33) | |
Text
December 23, 2015 Mr. Jqhn Hick¢an OR.ifil.
F11t//1er. 1i1ye/her U.S,Nudear R<<:!gulat0111 Commission Office of Nuclear Matei-ial.Safocy and Safeguards Division of Decommissioning, Uranium Recovew, and Waste Programs Reacte>~ Decommissioning Branch 1vfai1Stop: TSFS 11545, Rockville Pike*
Rockville,.Nil) 20852
SUBJECT:
REVISED *FINAL REPORT-INDEPENDENT CONFIRMATORY
- stJRVEY.
SUMMARY
ANO RESULTS FOR THE :CRIB HOUSE AND NON-IMPACTED.OPEN LAND AREAS AT THE ZION NUCLEAR
. POWER STAtION, ZION, ILLINOIS (RFTA NO.15-005); DCN5271;.,SR-01-1
Dear Mr. Hickman:
QRAU is, pleased to provide thc,ci1dosed re,,ised.final* report detailing the mdependem*confumatoq1
~urvey activities: of the Crib House and the non-it:npactcd open fandru:eas* at the Zion Nuclear Pow<!t Station in Zion, Illinois. This rep<:>rt.provides the si.lmmary ru'l.d results of:activities performed by ORAU, u~der the Oak Ridge'Irtstitute. for Science and Educati0n (9RlSE)_coritiac~ during the pcri<Jd of]uly,6-9, 20'15. The final repm;t has.been.revised to include strooi:iuin-90.results for the open land area* samples; as rcqu~st~d-by the U.S. Nuclear: Regulatory Commission.
You may concact.me*at 865:576.6659 or Tim Vit1...1s at865.576;5073 if you ha,re any questions.
Sincerely,
{_;vb_~
Erilm N. Bailey SurYe}' Projects Manager, Hcalrh'llhysicfat ORAU
'ENn:EMH:fs
- Enclosure electronic distcibutiorii R. Ed,vru:ds; NRt T. Carter, NRC
- S. Roberts, ORAU File/5271 B.Lin,NRC R Watson, NRC T. Vitkus, ORA U P.O. Box 117 Oak Ridge, TN 37831, *.www.orau.org,
INDEPENDENT CONFIRMATORY SURVEY
SUMMARY
AND RESULTS FOR TI:IE CRIB HOUSE AND NON-IMPACTED OPEN LAND AREAS AT THE ZION NUCLEAR POWER STATION, ZION, ILLINOIS
- REVISED.FINAL REPORT QR-4\\IJ.
Further. Together.
Prepared by Erika N. Bailey DECEMBER 2015 Prepared for the U.S. Nuclear Regulatory Commission Prepared by ORAU under the Oak Ridge Institute for Science and Education contract, number DE-ACOS-060R23100, 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.
Zion Confirmatory Survey Report 5271-SR-01-1
0&-4\\l.J 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 Energy Solutions called ZionSolutions, LLC (ZS). The ZNPS operated commercially from 1973 to 1997. Cessation of nuclear 0perations 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 Commission (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 ORAD, 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-1). 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 Report 1
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OAAU 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.
Figure 2.1. ZNPS Land Area Survey Units Zion Confirmatory Survey Report 2
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ORi\\U
- 3. 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 i:he licensee's procedures and results.
- 4. APPLICABLE SITE GUIDELINES The primary radionuclides 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 millirem per year (mrem/year). Table 4.1 provides the per square meter maximum inventories for each of the five ROCs.
- ,;*Roe.*
.Co-60 Cs-134 Cs-137 Sr-90 Jnyentqry Limit *
(pCi/m2): *:
9.28E+07 3.58E+07 4.95E+07 5.64E+09 1.94E+06
- :,~'
- The volumetric soil and buried pipe derived concentration guideline levels (DCGLws) 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 si.te visit. Any positive identification of site ROCs not expected to be present in background in a non-impacted area would require reclassification as impacted.
Zion Confirmatory Survey Report 3
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0&.11.JJ Surface Soil Subsurface Soil *
- Buried Pjpe.**.
pCi/ ).
,* (pCi/g
( dpm/100 c1p.2j*: ;
. ROC.
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 Chapter 5 in the license termination plan (ZS 2014b)
Each radionuclide-specific DCGLw represents the concentration above background of a residual radionuclide that would result in a radiological dose of 25 mrem/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 n
L C*
SOFTOTAL = I SOFj =
DCG~.
j=O W,J j=O Where C; is the concentration of COC "j," and DCG~v,; is the DCGLw for COC "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 DCG~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 Surory Procedure Manual and the ORAU Environmental Services and Radiation Training Quality Program Manual (ORAU 2015a, 2015b, and 2015c).
Zion Confirmatory Survey Report 4
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ORiID 5.1 SURFACE SCANS ORAU performed high-density gamma radiation scans of the accessible lower surfaces inside the Crib House. Five random locations were als~ 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 Ludlum Model 44-10 sodium iodide (Na!) 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 I
pairs were coupled to global positioning systems (GPS) that enabled real-time gamma count rate and spatial data capture (Figure A-2).
In additjon 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.
Figur~s 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 m2* The five randomly selected locations corresponded to the ZS location IDs ofRWC-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 FOV s 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 Report 5271-SR-01-1
ORA.U measurement/ numbering format used to collect the direct measurements within the selected in situ measurement locations.
~---------t, m--------,,
0 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 sele~ted ZS in situ measurement areas. The five increments associated with one in situ 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 (1B and 2B) containing enough sediment material to be sampled.
Zion Confirmatory Survey Report 6
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ORi\\.D
. 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 ORAURadiological and EnvironmentalAnajytical Laboratory Procedures Manual (ORAU 2015d). 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). Per NRC's request, soil samples for the open land areas were analyzed for Sr-90 via low background proportional counting and reported in units of pCi/ g. All Sr-90 results were below the DCGLs and MDCs. Analysis for the remaining pure beta-emitting radionuclide (Ni-63) was not performed per NRC's direction.
- 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 tec_hnicians noted that the maps for the in situ floor measurement locations they were provided did not correspond to the locations where ZS staff indicated they collected some of the in situ 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 floo'r 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 Zion Confirmatory Survey Report 7
5271-SR-01-1
ORi~"U SU 10305 (Figure A-5) and near loaded railroad cars over the western berm of SU 10303 (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 a~tivity results were consistent with typical background levels. Surface activity for the confirmatory measurement locations ranged from -300 to 2,200 dpm/100 cm2* 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 cm2 on the floor of the Crib House at ZS location ID RWC-004-1. Table B. l 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 the 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 DCGLws. Select soil sample results for the Crib House and open land areas were analyzed for Sr-90 and were below the MDC for Sr-90.
Due to the extremely low *radionuclide concentrations in the samples and only a few values being n
above the analytical MDCs, ORAU did not perform SOP calculations. For the non-impacted land area samples, only Cs-137 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 Zion Confirmatory Survey Report 8
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OR!\\U 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.
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_vs. Six of the seven surface soil samples collected from the non-impacted land areas contained Cs-137 concentrations above the analytical MDCs but were also well below the Cs-137 DCGL_v; 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.
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ORAU
- 10. REFERENCES EC 2015. The Future efZion. Webpage: http://www.exeloncorp.com/PowerPlants/zion/Pages/
aboutdecommissioning.aspx. Exelon Corporation. Chicago, Illinois. Accessed June 30.
ORAU/ORISE 2014. Radiation Protection Manual. Prepared by ORAU under the Oak Ridge Institute for Science and Education contract. Oak Ridge, Tennessee. October.
ORA U 2015a. Prqject-Specific Plan for the Confirmatory S urory Activities at the Zion Nuclear Power Station, Crib House and Non-Impacted Open Land Areas, 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 Radiological and Environmental Surory Procedures Manual Oak Ridge Institute for Science and Education, managed and operated by ORAU. Oak Ridge, Tennessee. August 6.
ORAU 2015c. ORAU Environmental Services and Radiation TrainingQuali!J Program Manual. ORAU.
Oak Ridge, Tennessee. August 7.
ORAU 2015d. ORAU Radiological and Environmental Anafytical Laboratory Procedures Manual. Oak Ridge Institute for Science and Education, managed and operated by ORAU. Oak Ridge, Tennessee.
May 7.
- oRAU 2015e. Health and Saft!)! Manual. ORAU. Oak Ridge, T~nnessee. June.
ZS 2014. Zion Station fustoration Prqject License Termination Plan: Chapter 2 Site Characterization, Rev. 0.
ZionS olutions, LLC. Chicago, Illinois. December 19.
ZS 2015. STS Package Zion Crib House: STS Sample Plan B3-081D1A-F. ZionSolutions, LLC. Chicago, Illinois. June 25.
Zion Confirmatory Survey Report 10 5271-SR-01-1
Zion Confirmatory Survey Report APPENDIXA FIGURES 5271-SR-01-1
t ~~
o 1,1004,200 ORAU
-=::i Meters Crcau:d by, A, Kirthlink
\\ ~\\IE.A\\' GlS\\ 527 1 Lon Zion NPS Zion, Illinois Oo1.tc1 July 15, 2015 Figure A-1. Location of the Zion Nuclear Power Station, Zion, Illinois Zion Confirmatory Survey Report A-1 5271-SR-01-1
4951 - 5370 c:::J Boundary 6211 -6749 -
4531 -4950 Random Samples 5791 - 6210 -
41 11 - 4530 5371 - 5790 -
<4110 0
Me te rs ZionNPS Top of Crib Gamma Walkover Ueatcd by1 A. Kir1hlink Datei July 15, 2015 Y*\\IEA\\' GIS\\527 1 Zaon Figure A-2. Top of Crib House-Gamma Walkover Scan Zion Confirmatory Survey Report A-2 5271-SR-01-1
4351 - 5050 c:::J Boundary 7501 - 9265 -
3651 - 4350 Random Samples 6451 - 7500 -
2951 - 3650 5751 - 6450 -
2251 - 2950 5051 - 5750 -
<2250 0 t ~~
so 160 ORAU ZionNPS Random Sample Location 5271S0008 Meters Created by1 A. Ki.rtblink 0-.ue;July 15, 2015
\\ '\\IE.A\\' GIS\\WI Lea Figure A-3. Non-Impacted Land Area, SU10215-Gamma Walkover Scan and Sample Location 5271S0008 Zion Confirmatory Survey Report A -3 5271-SR-01-1
4351 - 5050 c:::J Boundary 7501 - 9265 -
3651 - 4350 Random Samples 6451 - 7500 -
2951 - 3650 5751 - 6450 -
2251 - 2950 5051 - 5750 -
<2250 0 t.4~
so 160 ORAU Zion NPS Random Sample Location 5271S0009 Meters Crea1cd by1 A. Kirthlink Do1.tc:JuJy 1S, 201.S
\\ ~\\IE.\\\\' ClS\\ S271 Loa Figure A-4. Non-Impacted Land Area, SU10216-Gamma Walkover Scan and Sample Location 5271S0009 Zion Confirmatory Survey Report A-4 5271-SR-01-1
4351 - 5050 c:::J Boundary 7501 - 9265 -
3651 - 4350 Random Samples 6451 - 7500 -
2951 - 3650 5751 - 6450 -
2251 - 2950 5051 - 5750 -
<2250 0 t ~~
so 160 ORAU Zion NPS Random Sample Location 1 5271S0010 Mete rs Created by: A. Kirthlink Ooltc:July 1S, 2015
\\":\\lf_o\\\\' GIS\\ SZil Ukl Figure A-5. N on-Impacted Land Area, SU10305-Gamma Walkover Scan and Sample Location 5271S0010 Zion Confirmatory Survey Report A-5 5271-SR-01-1
CPM 4351 - 5050 c:::J Boundary 7501 - 9265 -
3651 - 4350 Random Samples 6451 - 7500 -
2951 - 3650 5751 - 6450 -
2251 - 2950 5051 - 5750 -
<2250 0 t ~~
so 160 ORAU ZionNPS Random Sample Location 5271S0011 Meters Created by: A. IGrthlink Date: July 15, 2015
'\\~\\IE,\\\\' GIS\\517 1 Lou Figure A-6.Non-Impacted Land Area, SU10402-Gamma Walkover Scan and Sample Location 5271S0011 Zion Confirmatory Survey Report
.c\\-6 5271-SR-01-1
4351 - 5050 CJ Boundary 7501 - 9265 -
3651 - 4350 Random Samples 6451 - 7500 -
2951 - 3650 5751 - 6450 -
2251 - 2950 5051 - 5750 -
<2250 0 t.4~
so 160 ORAU Zion NPS Random Sample Location 5271S0012 Meters Created by1 A. Ki.rth.link D.atc:July 15, 2015
\\: \\IE.-\\\\' G1S\\5.z'71 Z-Figure A-7. Non-Impacted Land Area, SU10303-Gamma Walkover Scan and Sample Location 5271S0012 Zion Confirmatory Survey Report A-7 5271-SR-01-1
CPM 4351 - 5050 c:::J Boundary 7501 - 9265 -
3651 - 4350 Random Samples 6451 - 7500 -
2951 - 3650 5751 - 6450 -
2251 - 2950 5051 - 5750 -
<2250 0 t ~~
so 160 ORAU Zion NPS Random Sample Location 5271S0013 Mete rs Created by, A. Kirthlink O.uc: JuJy 1S, 20 15
\\ ': \\I.E.,\\\\' GlS\\WI Loa Figure A-8. Non-Impacted Land Area, SU10303-Gamma Walkover Scan and Sample Location 5271S0013 Zion Confirmatory Survey Report A-8 5271-SR-01-1
4351 - 5050 c::::J Boundary 7501 - 9265 -
3651 - 4350 Random Samples 6451 - 7500 -
2951 - 3650 5751 - 6450 -
2251 - 2950 5051 - 5750 -
<2250 0 t ~~
so 160 ORAU Zion NPS Random Sample Location 5271S0014 Meters Created by: A. K.irthlink Dr.ate: July 15, 2015
)!\\ IE.-\\\\' GIS\\SZ? l :U0.1 Figure A-9. Non-Impacted Land Area, SU10305-Gamma Walkover Scan and Sample Location 5271S0014 Zion Confirmatory Survey Report A-9 5271-SR-01-1
Zion Confirmatory Survey Report APPENDIXB DATA TABLES 5271-SR-01-1
Gross Gamma Gross Beta Net Beta Surface Net Beta Surface ZS Location ID QRAU Surface Order of Count Rate Count Rate
- . Activity.
Activity Location.ID Measurements (cpm)
(cpm)
(dpm/100 cm2}a (pCi/m2}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
O.OOE+OO West wall 5
4,736 256 215 9.70E+03
- Detectors calibrated to Tc-99.
Zion Confirmatory Survey Report B-1 5271-SR-01-1
Location Ip
- Concrete: Samples:from the Crib ifJo*use <
Random 5271M0001 RWC-004-1 0.002 +/- 0.041, 0.088 0.021 +/- 0.038, 0.088 5271M0002 RWC-009-1 0.010 +/- 0.027, 0.064 0.031 +/- 0.027, 0.071 5271M0003 RWC-003-1
-0.005 +/- 0.016, 0.032 0.009 +/- O.G15, 0.035 5271M0004 RWC-014-1 0.002 +/- 0.014, 0.032 0.003 +/- O.G15, 0.033 5271M0005 RWC-005-1 0.020 +/- 0.019, 0.047 0.008 +/- 0.021, 0.047
. Sedirij.ent Sam les:Collectt:ofrom Select Pum s within.the Crib.House Judgmental 5271S0006 Pump 1B 0.052 +/- 0.022, 0.041 0.021 +/- 0.020, 0.048 5271S0007 Pump2B 0.363 +/- 0.047, 0.053 0.030 +/- 0.029, 0.067
- uncertainties 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 n/a = not applicable
~oil Saniples;from tb-e:Noii~In1pa~tedOpenLaiid Are*11s * ***
Random 5271S0008 10215 0.005 +/- 0.020, 0.045 5271S0009 10216
-0.009 +/- 0.010, 0.041 5271S0010 10305
-0.003 +/- 0.017, 0.040 5271S0011 10402 0.002 +/- 0.017, 0.037 5271S0012 10303
-0.023 +/- 0.030, 0.055 5271S0013 10303 0.014 +/- 0.027, 0.060 5271S0014 10305
-0.006 +/- 0.021, 0.044
- uncertainties represent the 95% confidence levei based on total propagated uncertainties.
bMDC = minimum detectable concentration; these are the values after the comma Zion Confirmatory Survey Report B-2 0.002 +/- 0.019, 0.042
-0.007 +/- 0.013, 0.046 0.021 +/- 0.016, 0.040
-0.0039 +/-0.0088, 0.0340 0.025 +/- 0.021, 0.053 0.019 +/- 0.023, 0.054
-0.0059 +/- 0.0062, 0.0462 0.016 +/- 0.037, 0.084 n/a
-0.001 +/- 0.031, 0.068 n/a 0.006 +/- 0.0088, 0.0207 n/a 0.000 +/- 0.014, 0.032 n/a 0.005 +/- 0.016, 0.036 n/a 0.044 +/- 0.016, 0.029 0.04 +/- 0.17, 0.30 0.151 +/- 0.028, 0.042
-0.02 +/- 0.11, 0.21 0.136 +/- 0.022, 0.027
-0.05 +/- 0.16, 0.31 0.255 +/- 0.031, 0.025 0.07 +/- 0.17, 0.30 0.253 +/- 0.030, 0.025 0.03 +/- 0.19, 0.34 0.040 +/- 0.012, 0.022
-0.03 +/- 0.16, 0.30 0.264 +/- 0.036, 0.034 0.10 +/- 0.18, 0.32 0.063 +/- 0.020, 0.036
-0.03 +/- 0.17, 0.31 0.013 +/- 0.011, 0.026
-0.04 +/- 0.16, 0.31 5271-SR-01-1
APPENDIXC SURVEY AND ANALYTICAL PROCEDURES Zion Confirmatory Survey Report 5271-SR-01-1
C.1 PROJECT HEALTH AND SAFETY ORAU performed all survey activities in accordance with the ORAU / ORISE Radiation Protection Manual, the ORAU Health and Sqfefy Manual, and the ORAUR.adiological andEnvironlftental Suroey Procedures Manual (ORAU/ORISE 2014, ORAU 2015e, and ORAU 2015b). Prior to oh-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 Radiological and Environmental Suroey Procedures Manual 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 (NIST). _
Field survey activities were conducted in acc~rdance with procedures from the following ORAU documents:
ORAUR.adiological and Environmental Suroey Procedures Manual (ORAU 2015b)
- -ORAU Radiological and EnvironmentalAnafytical Laboratory Procedures Manual (ORAU 2015c)
ORAU Environmental Services and Radiation Training Qualify Program Manual (ORAU 2015d)
- The procedures contained in these manuals were developed to meet the requirements of U.S. Department of Energy (DOE) Order 414.lD and the U.S. Nuclear Regulatory Commission (NRC) Qualify Assurance Manual for the Office of Nuclear Material S qfefy and S qfeguards and contain measures to assess processes during their performance.
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Quality control procedures include:
Daily instrument background and check-source measurements to confirm 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 minimum detectable concentration (MDCs) for the sodium iodide scintillation detectors (NaI) were not determined as the instruments were 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 aJ.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 MDCs 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 ad' value of 2.32 (NUREG-1507, Table 6.1), and a surveyor efficiency of 0.5. The beta total efficiency was 0.10 for C:o-60 (calibrated with Tc-99). The detector used had a general background of 300 cpm. The minimum detectable count rate (MDCR) and scan MDC was calculated as:
B; = (300)(2 s)(l min/60 s) = 10 counts Zion Confirmatory Survey Report C-2 5271-SR-01-1
C.3.2
- MDCR = (2.32)(10 counts)112[(60 s/min)/2s] = 220 cpm
- MDCR.urreyor = 220/(0.5) 112 = 311 cpm Scan:MDC = (311)/(.10) = 3,110 dpm/100 cm 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 cmj by dividing the count rate by the total static efficiency (eiXe.) 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 a pr,iori :MDC for beta activity is given by:
3 + ( 4.65\\/B)
MDC=
G Etot Where:
B background Etot
- total efficiency G
geometry correction factor (1.0)
The a priori beta static MDC was approximately 7 43 dpm/ 100 en/ for Co-6.0.
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 res:ulted 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.
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C.4 RADIOLOGICAL ANALYSIS C.4.1 GAMMA SPECTROSCOPY Samples were analyzed as i;eceived, 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 height 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:
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.4.2 SR-90ANALYSIS Soil samples were dissolved by a combination of potassium hydrogen fluoride and pyrosulfate fusions. The fusion cake was dissolved and strontium was co-precipitated on lead sulfate. The strontium was separated from residual calcium and lead by precipitating strontium sulfate from ethylenediaminetetraacetic acid at a pH of 4.0. Strontium was separated from barium by complexing the strontium in diethylenetriaminepentaacetic acid while precipitating barium as barium chromate.
The strontium was ultimately converted to strontium carbonate and counted on a low-background gas proportional counter. The typical MDC of the procedure is 0.4 pCi/ g for a one hour count time.,
C.5 DETECTION LIMITS Detection limits, referred to as MDCs~ were based on 95% confidence level via the NUREG-1507 m,ethod. Because of variations in background levels, measurement efficiencies, and contributions from other radionuclides in samples, the detection limits differ from sample to sample and instrument to instrument.
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APPENDIXD MAJOR INSTRUMENTATION Zion Confirmatory Survey Report 5271-SR-01-1
The display of a specific* product is not to be construed as an endorsement of the product or its manufacturer by the author cir 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 (Ludlum 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 Mod~l 44-142, 100 cm2 physical area coupled to:
Ludlum Ratemeter-scaler Model 2221 (Ludlum 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: ERVDS30-25195 (Canberra, Meriden, Connecticut)
Used in conjunction with:
Lead Shield Model G-11 (Nuclear Lead, Oak Ridge, Tennessee) and Multichannel Analyzer Canberra's Gamma Software Dell Workstation (Canberra, Meriden, Connecticut)
High-Purity, Intrinsic Detector Model No. GMX-45200-5 CANBERRA Model No: GC4020 (Canberra, Meriden, Connecticut)
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Used in conjunction with:
Lead Shield Model G-11 Lead Shield Model SPG-16-K8 (Nuclear Data)
Multichannel Analyzer Canberra's Gamma Software Dell Workstation (Canberra, Meriden, Connecticut)
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