NG-15-0135, 2014 Annual Radiological Environmental Operating Report
| ML15138A131 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold |
| Issue date: | 05/14/2015 |
| From: | Vehec T NextEra Energy Duane Arnold |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NG-15-0135 | |
| Download: ML15138A131 (99) | |
Text
NEXTera EN ERGY
ý;ý ARNOLD May 14, 2015 NG-1 5-0135 TS 5.6.2 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 Duane Arnold Energy Center Docket No. 50-331 Renewed Op. License No. DPR-49
Subject:
2014 Annual Radiological Environmental Operating Report Please find as Enclosure 1 to this letter, a copy of NextEra Energy Duane Arnold, LLC's, (hereafter, NextEra Energy Duane Arnold) 2014 Annual Radiological Environmental Operating Report for the Duane Arnold Energy Center, pursuant to the requirements of ODAM Section 8.2.2 and Technical Specification Section 5.6.2.
This letter contains no new commitments nor does it revise any existing commitments.
Should you have any questions regarding this matter, please contact David Olsen at (319) 851-8129.
Sincerely, T. A. Vehec Vice President, Duane Arnold Energy Center NextEra Energy Duane Arnold, LLC Enclosure cc:
Regional Administrator, USNRC, Region III Resident Inspector, USNRC, Duane Arnold Energy Center Project Manager, USNRC, Duane Arnold Energy Center NextEra Energy Duane Arnold, LLC, 3277 DAEC Road, Palo, IA 52324 to NG-15-0135 Duane Arnold Energy Center 2014 Annual Radiological Environmental Operating Report 97 Pages to follow
MWMMWý NEXTera ENERGY701, ARNOLD 2014 Annual Radiological Environmental Operating Report Duane Arnold Energy Center Cedar Rapids, Iowa Docket No. 50-331 January 1, 2014 through December 31, 2014
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2014 Annual Radiological Environmental Operating Report Duane Arnold Energy Center DOCKET NUMBER. 50-331 Prepared By:
Date: 01-Alct
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1 A-Environmental, Inc.
/10 TI Midwest Laboratory 700 Landwehr Road Northbrook. IL 60062-2310 pho-e f8471 564-0700 - f- (847) 564-4517 DUANE ARNOLD ENERGY CENTER CEDAR RAPIDS, IOWA Docket No. 50-331 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)
ANNUAL REPORT - PART II DATA TABULATIONS AND ANALYSES January 1 to December 31, 2014 Prepared by ATI ENVIRONMENTAL, Inc.
Midwest Laboratory Project No. 8001 Reviewed and Approved
PREFACE Staff members of the Environmental, Inc., Midwest Laboratory were responsible for the acquisition of data presented in this report; with the exception of Appendices D and E which were completed by DAEC personnel. All environmental samples, with the exception of aquatic, were collected by personnel of DAEC.
Aquatic samples were collected by the University of Iowa Hygienic Laboratory.
The report was prepared by Environmental, Inc., Midwest Laboratory, with the exception of Appendices D and E, which were prepared by DAEC personnel.
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TABLE OF CONTENTS PART I No Page P R E F A C E.....................................................................................................................
ii L ist o f T a b le s..........................................................................................................
.. v L ist o f F ig u re s.......................................................................................................
v i
1.0 INTRODUCTION
1 2.0
SUMMARY
2 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM..........................
3 3.1 Program Design and Data Interpretation................................................................
3 3.2 Program Description.........................................................................................
4 3.2.1 Environmental Monitoring...............................................................................
4 3.2.2 Ground W ater Protection Program......................................................................
5 3.3 Program Execution...........................................................................................
5 3.4 Laboratory Procedures......................................................................................
6 3.5 Program Modifications......................................................................................
6 4.0 RESULTS AND DISCUSSION...............................................................................
7 4.1 Atmospheric Nuclear Detonations and Nuclear Accidents................................
7 4.2 Program Findings.............................................................................................
7 5.0 TABLES AND FIGURES.........................................................................................
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6.0 REFERENCES
CITED...........................................................................................
25 APPENDICES A
Interlaboratory Comparison Program Results......................................................
A-1 B
Data Reporting Conventions...............................................................................
B-1 C
Effluent Concentration Limits for Radioactivity in Air and Water Above Background in Unrestricted Areas.................................................................
C-1 D
Summary of the Land Use Census......................................................................
D-1 E
Annual Radiation Dose Assessment....................................................................
E-1 iii
TABLE OF CONTENTS (continued)
Page Data Tabulations and Analyses......................................................................................
i PART II iv
LIST OF TABLES No.
Paqe 5.1 Characteristic Properties of Isotopes Quantified in Gamma-spectroscopic A n a ly s e s.........................................................................................................
1 1 5.2 Sample Collection and Analysis Program..............................................................
12 5.3 Sampling Locations, DAEC....................................................................................
14 5.4 Type and Frequency of Collections........................................................................
16 5.5 Sample Codes for Tables 5.4 and 5.6....................................................................
17 5.6 P ro g ra m D ev iatio ns.....................................................................................................
18 5.7 Radiological Environmental Monitoring Program Summary......................................
19 In addition, the following tables are included in the Appendices:
Appendix A A -0 A tta c hm e nt A............................................................................................................
A O -2 A-1 Environmental Resource Associates (EPA DW substitute program)....................... Al-1 A-2 Interlaboratory Comparison Program
- Results, Thermoluminescent A-3 A-4 A-5 A-6 A-7 Appendix C C-1 Dosimeters (TLDs)......................................................................................
A2-1 In-house Spiked Samples........................................................................................
A3-1 In-house "Blank" Samples........................................................................................
A4-1 In-house "Duplicate" Samples.............................................................................
A5-1 Department of Energy MAPEP comparison results.................................................
A6-1 Environmental Resource Associates (EML substitute program)..............................
A7-1 Effluent Concentration Limits for Radioactivity in Air and Water Above Background in Unrestricted Areas..............................................................
C-2 v
LIST OF FIGURES No.
Pacie 5.1 Radiological Environmental Monitoring Program Sampling Stations near the Duane Arnold Energy Center...................................................................
23 5.2 Radiological Environmental Monitoring Program Sampling Stations Outside 0.5 M ile s.........................................................................................................
2 4 vi
1.0 INTRODUCTION
This report summarizes and interprets results of the Radiological Environmental Monitoring Program (REMP) conducted by Environmental, Inc., Midwest Laboratory at the Duane Arnold Energy Center, Palo, Iowa, during the period January - December, 2014.
This Program monitors the levels of radioactivity in the air, terrestrial, and aquatic environments in order to assess the impact of the plant on its surroundings.
The REMP fulfills the requirements of Sections IV.B.2 and IV.B.3 of Appendix I to 10 CFR 50 for the operation of the plant. The REMP also fulfills the requirements of 10 CFR 72.44(d)(2) for operation of the ISFSI.
Tabulations of individual analyses made during the year are included in Part II of this report.
The Duane Arnold Energy Center (DAEC) is a boiling water reactor, located in LinnCounty, Iowa, on the Cedar River, and owned and operated by NextEra Energy Resources. Initial criticality was attained on March 23, 1974. The reactor reached 100% power on August 12, 1974. Commercial operation began on February 1, 1975.
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2.0
SUMMARY
The Radiological Environmental Monitoring Program, as required by the U.S. Nuclear Regulatory Commission (NRC) Technical Specifications for the Duane Arnold Energy Center, is herein described.
Results for the year 2014 are summarized and discussed.
Program findings show only background levels of radioactivity in the environmental samples collected in the vicinity of the Duane Arnold Energy Center.
No effect on the environment is indicated in the areas surrounding the site of the Duane Arnold Energy Center.
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3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 3.1 Program Desiqn and Data Interpretation The purpose of the Radiological Environmental Monitoring Program at the Duane Arnold Energy Center (DAEC) is to assess the impact of the plant on its environment. For this purpose, samples are collected from the air, terrestrial, and aquatic environments and analyzed for radioactive content.
In addition, ambient gamma radiation levels are monitored by thermoluminescent dosimeters (TLDs).
Sources of environmental radiation include the following:
(1)
Natural background radiation arising from cosmic rays and primordial radionuclides; (2)
Fallout from atmospheric nuclear detonations; (3)
Releases from nuclear power plants; and (4)
Industrial and medical radioactive waste.
In interpreting the data, effects due to the DAEC operation must be distinguished from those due to other sources.
A major interpretive aid in assessment of these effects is the design of the monitoring program at the DAEC which is based on the indicator-control concept. Most types of samples are collected both at indicator locations (nearby, downwind, or downstream) and at control locations (distant, upwind, or upstream).
A station effect would be indicated if the radiation level at an indicator location was significantly larger than that at the control location. The difference would have to be greater than could be accounted for by typical fluctuations in radiation levels arising from other sources.
An additional interpretive technique involves analyses for specific radionuclides present in the environmental samples collected from the DAEC site. The DAEC's monitoring program includes analyses for strontium-90 and iodine-131, which are fission products, and tritium, which is produced by cosmic rays, atmospheric nuclear detonations, and also by nuclear power plants.
Most samples are also analyzed for gamma-emitting isotopes with results for the following groups quantified:
zirconium-95, cesium-137, and cerium-144.
These three gamma-emitting isotopes were selected as radiological impact indicators because of the different characteristic proportions in which they appear in the fission product mix produced by a nuclear reactor and that produced by a nuclear detonation. Each of the three isotopes is produced in roughly equivalent amounts by a reactor: each constitutes about 10% of the total activity of fission products ten (10) days after reactor shutdown. On the other hand, ten (10) days after a nuclear explosion, the contributions of zirconium-95, cerium-144, and cesium-137 to the activity of the resulting debris are in the approximate ratio 4:1:0.03 (Eisenbud,1963). The other group quantified consists of niobium-95, ruthenium-103 and -106, cesium-134, barium-lanthanum-140, and cerium-141.
These isotopes are released in small quantities by nuclear power plants, but to date their major source of injection into the general environment has been atmospheric nuclear testing. Nuclides of the next group, manganese-54, cobalt-58 and-60, and zinc-65, are activation products and arise from activation of corrosion products. They are typical components of nuclear power plant effluents, but are not produced in significant quantities by nuclear detonations. Nuclides of the final group, beryllium-7, which is of cosmogenic origin, and potassium-40, a naturally-occurring isotope, were chosen as calibration monitors and provide a comparison between levels of naturally occurring radionuclides and radionuclides that could be attributed to the operation of the plant.
Characteristic properties of isotopes quantified in gamma-spectroscopic analysis are presented in Table 5.1. Other means of distinguishing sources of environmental radiation can be employed in interpreting the data. Current radiation levels can be compared with previous levels, including those measured before the Plant became operational. Results of the DAEC's Monitoring Program can be related to those obtained in other parts of the world.
Finally, results can be related to events known to cause elevated levels of radiation in the environment, e.g., atmospheric nuclear detonations.
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3.2 Pro-gram Description 3.2.1 Environmental Monitoring The sampling and analysis schedule for the Radiological Environmental Monitoring Program (REMP) at the DAEC is summarized in Table 5.2 and is briefly reviewed below. Table 5.3 defines the sampling location codes used in Table 5.2 and specifies for each location its distance, direction, and sector relative to the reactor site. The types of samples collected at each location and the frequency of collections are presented in Table 5.4 using codes defined in Table 5.5.
To monitor the air environment, airborne particulates are collected on membrane filters by continuous pumping at nine locations. Airborne iodine is collected by continuous pumping through charcoal filters. Eight of the nine locations are indicators and one is a control (D-13). Filters are changed and counted weekly. Particulate filters are analyzed for gross beta activity. If gross beta activity exceeds ten times the yearly mean of the control samples, gamma isotopic analysis is performed.
Quarterly composites of airborne particulates from each location are analyzed for gamma emitting isotopes. Charcoal filter samples are analyzed weekly for iodine-1 31.
Ambient gamma radiation is monitored at a total of 50 locations. A TLD is placed at each location and exchanged and analyzed quarterly. The TLD locations are distributed as follows:
Two on-site locations Eighteen in a circle within a 0.5 mi. radius from the DAEC stack.
Six in 22.50 sectors within 1 mi. from the DAEC stack.
Ten in 22.50 sectors between 1 and 3 miles from the DAEC stack.
Ten control locations greater than 3 miles from the DAEC stack.
Four along sections of the Independent Spent Fuel Storage Installation (ISFSI) fenceline.
Surface water is collected monthly from four river locations, D-49 (Lewis Access, Control, 4 mi.
upstream), D-50 (Inlet), D-51 (Discharge) and D-61 (downstream of Discharge) and also from Pleasant Creek Lake (D-99). The monthly samples are analyzed for tritium and gamma-emitting isotopes. Additional analyses are performed on samples collected from the control and indicator locations, D-49 and D-61. Analyses for low-level iodine-131 are performed on monthly collections and quarterly composites are prepared and analyzed for strontium-89 and strontium-90.
The aquatic environment is also monitored by upstream and downstream (D-49 and D-61) semiannual collections of fish.
River bottom sediment is collected semiannually at the plant's intake and discharge (D-50 and D-51) and the site's north drainage ditch (D-107a). The samples are analyzed for gamma-emitting isotopes.
Potable ground water is collected quarterly from a treated municipal water system (D-53), the inlet to the municipal water treatment system (D-54), three indicator locations (D-55, D-57, D-58) and one control location (D-72). The samples are analyzed for.tritium and gamma emitting isotopes.
Any positive identification of a reactor by-product material initiates analyses for hard to detect isotopes of Ni-63, Sr-89, Sr-90, Fe-55 and gross alpha. Beginning in the fourth quarter of 2014 all samples were analyzed to a lower MDA of 2 pCi/L for 1-131.
Milk is collected monthly from one indicator and one control location during the non-grazing season, October through April, and biweekly during the grazing season, May 1 through September
- 30. The samples are analyzed for iodine-131 and gamma-emitting isotopes.
For additional monitoring of the terrestrial environment, grain, hay and broad leaf vegetation samples are collected annually, as available, from nine locations: one control (D-138) and eight indicators (D-16, D-57, D-58, D-72, D-96, D-109 and D-118). Grain, hay and broad leaf (green leafy) vegetation samples are analyzed for gamma-emitting isotopes and at least two broad leaf vegetation samples are analyzed for iodine-1 31.
If any of the cattle grazing on-site are slaughtered for home use, a meat sample is collected. The sample is analyzed for gamma-emitting isotopes.
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3.2.2 Ground Water Protection Proqram Environmental, Inc., Midwest Laboratory provides laboratory services for the Duane Arnold Energy Center Ground Water Protection Program. For results from these analyses, refer to the Duane Arnold Energy Center, 2014 Annual Radioactive Material Release Report.
3.3 Procqram Execution The program was executed as described in the preceding section with the following exceptions:
(1) Airborne Particulates /Airborne Iodine:
A partial air particulate / air iodine sample (165 M3) at location D-13, for the week ending 02/07/14. Lower volume suspected due to power outage.
A partial air particulate / air iodine sample (214 M3) and the week ending 02/13/14.
Lower volume suspected due to power outage.
A partial air particulate / air iodine sample (140 M3) was collected at location D-15, for the week ending 04/16/14 due to a power outage.
A partial air particulate / air iodine sample (103 M3) was collected at location D-15, for the week ending 05/16/14 due to a power outage.
A partial air particulate / air iodine sample (310 M3) was collected at location D-1 5, for the week ending 07/11/14, due to a power outage..
No Air particulate / air iodine sample at location D-13, for the weeks ending 07/17/14 and the week ending 07/24/14 due to power outage at the sampler.
(2) Thermoluminescent Dosimetry The fourth quarter, 2014 TLD at location D-17 was missing in the field. The TLD was replaced.
(3) Vegetation Vegetation samples were not readily available from locations D-58, D-72 and D-138 for 2014.
(4) Surface Water Surface water was not available at locations D49 and D-99 for both the 1/22/14 and 2/4/14 collections due to frozen water conditions.
Surface water was not available at location D-99 for the 12/20/14 collection due to frozen water conditions.
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3.4 Laboratory Procedures The Iodine-1 31 analyses in milk and water were made using a sensitive radiochemical procedure involving separation of iodine using an ion-exchange rnmethod, solvent extraction and subsequent beta counting. Levels of iodine-131 in vegetation and concentrations of airborne iodine-131 in charcoal samples were determined by gamma spectroscopy.
Gamma-spectroscopic analyses are performed using high-purity germanium (HPGe) detectors.
The gamma isotopic analysis provides a spectrum with an energy range from 80 to 2048 KeV.
Specific isotopes included in the gamma library are Mn-54, Fe-59, Co-58, Co-60, Zn-65, Zr-95, Nb-95, Ru-103, Ru-106, 1-131, Ba-La-140, Cs-134, Cs-137, Ce-141, and Ce-144. Naturally occurring gamma-emitters, such as Be-7, K-40 and Ra daughters, are frequently detected but may not be listed.
Tritium was measured by liquid scintillation spectrometry.
Analytical Procedures used by Environmental, Inc. are on file and are available for inspection.
Procedures are based on those prescribed by the Health and Safety Laboratory of the U.S. Dep't of Energy, Edition 28, 1997, U.S. Environmental Protection Agency for Measurement of Radioactivity in Drinking Water, 1980, and the U.S. Environmental Protection Agency, EERF, Radiochemical Procedures Manual, 1984.
Environmental, Inc., Midwest Laboratory has a comprehensive quality control/quality assurance program designed to assure the reliability of data obtained.
Details of the QA Program are presented elsewhere (Environmental, Inc., Midwest Laboratory, 2014). The QA Program includes participation in Interlaboratory *Comparison (crosscheck) Programs.
Results obtained in crosscheck programs are presented in Appendix A.
3.5 Program Modifications Starting in the fourth quarter of 2014, REMP well water samples were analyzed for low level 1-131 (MDA < 2 pCi/L).
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4.0 RESULTS AND DISCUSSION All collections and analyses were made as scheduled, except for those listed in Table 5.6.
Results are summarized in Table 5.7 as recommended by the Nuclear Regulatory Commission.
For each type of analysis and sample medium, the table lists the mean and range of all indicator and control locations, as well as that location with the highest mean and range.
Tabulated results of measurements are not included in this section, although reference to these results will be made in discussion. A complete tabulation of results for 2014 is contained in Part II of the Annual Report on the Radiological Environmental Monitoring Program for the Duane Arnold Energy Center.
4.1 Atmospheric Nuclear Detonations and Nuclear Accidents There were no reported accidents involving significant release to the environment at nuclear reactor facilities in 2014. The Fukushima Daiichi nuclear accident occurred March 11, 2011.
There were no reported atmospheric nuclear tests in 2014. The last reported test was conducted on October 16, 1980 by the People's Republic of China.
4.2 Program Findings Results obtained show background levels of radioactivity in the environmental samples collected outside of the Owner Controlled Area in 2014. The trace levels of strontium-90 and cesium-137, still measurable in soil and sediments are attributed to deposition of fallout from previous decades.
Airborne Particulates The average annual gross beta concentrations in airborne particulates were almost identical at indicator and control locations (0.026 and 0.025 pCi/m 3, respectively) and similar to levels observed from 1995 through 2012. The results are tabulated below.
Year Indicators Controls Year Indicators Controls Concentration (pCi/m 3)
Concentration (pCi/m3) 1999 0.026 0.027 2007 0.031 0.031 2000 0.026 0.027 2008 0.029 0.029 2001 0.026 0.026 2009 0.031 0.030 2002 0.027 0.027 2010 0.028 0.028 2003 0.029 0.029 2011 0.030 0.029 2004 0.028 0.028 2012 0.030 0.029 2005 0.031 0.031 2013 0.028 0.025 2006 0.0.29 0.027 2014 0.026 0.025 Average annual gross beta concentrations in airborne particulates.
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4.2 Proaram Findinas. Airborne Particulates (continued)
Gamma spectroscopic analysis of quarterly composites of air particulate filters yielded similar results for indicator and control locations.
Beryllium-7, produced continuously in the upper atmosphere by cosmic radiation (Arnold and AI-Salih, 1955), was detected in all samples, with an average activity of 0.068 pCi/m3 for indicator locations and 0.063 pCi/m3 for the control location.
No reactor by-product radionuclides were identified. All samples met required lower limits of detection as specified in the DAEC Offsite Dose Assessment Manual.
Airborne Iodine 3
Levels of airborne iodine-1 31 measured below the required limit of 0.030 pCi/m for all samples.
Ambient Radiation (TLDs)
At ten control locations, thermoluminescent dosimeter (TLD) readings averaged 14.6 mR/quarter.
At locations within a half mile, one mile and three mile radius of the stack, the measurements averaged 16.3, 16.8 and 14.1 mR/quarter, respectively. The two on-site locations D-15 and D-16 averaged 14.7 and 13.5 mR/quarter respectively. These average measurements are similar to the estimated average natural background radiation for Middle America, 19.5 mR/quarter, which is based on data on Pages 71 and 108 of the report, "Natural Background Radiation in the United States" (National Council on Radiation Protection and Measurements, 1975).
The terrestrial absorbed dose (uncorrected for structural and body shielding) ranges from 8.8 to 18.8 mrad/quarter and averages 11.5 mrad/quarter for Middle America.
Cosmic radiation and cosmogenic radionuclides contribute 8.0 mrad/quarter for a total average of 19.5 mrad/quarter. No plant effect is indicated.
ISFSI Facility Operations Monitoring Four TLDs, placed directionally along the ISFSI fenceline, averaged 29.9 mR/quarter. The TLD site D-30, located between the nearest residence and the ISFSI site averaged 16.5 mR/qtr.
Calculated dose rates indicate the site is in compliance with 10 CFR 72.104 and 40 CFR 190.
Milk There was no iodine-1 31 activity detected in milk samples. Iodine-1 31 measured below a detection limit of 0.5 pCi/L.
No gamma-emitting isotopes, excepting naturally occurring potassium-40, were detected in any milk samples. This is consistent with findings that most radiocontaminants in feed do not find their way into milk due to the selective metabolism of the cow.
The Common exceptions are radioisotopes of potassium, cesium, strontium, barium, and iodine (National Center for Radiological Health, 1968).
No reactor by-product radionuclides were identified. All samples met required lower limits of detection as specified in the DAEC Offsite Dose Assessment Manual.
Ground Water (potable)
No measurable tritium activity was detected above an LLD of 176 pCi/L. Gamma-emitting isotopes were below detection limits.
No reactor by-product radionuclides Could be identified. All samples met required lower limits of detection as specified in the DAEC Offsite Dose Assessment Manual.
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4.2 Program Findings (continued)
Vegetation Iodine-131 concentrations in broadleaf vegetation were below the LLD level of 0.030 pCi/g wet weight in all samples.
With the exception of potassium-40, which was observed in all vegetation samples (broadleaf, grain, and forage), all other gamma-emitting isotopes were below detection limits. No reactor by-product radionuclides were identified. All samples met required lower limits of detection as specified in the DAEC Offsite Dose Assessment Manual.
Surface Water Surface water was tested for tritium and gamma emitting isotopes in sixty samples from five locations. No measurable tritium activity was detected above an LLD of 183 pCi/L.
1-131 was detected in two samples collected in February at locations D-50 (control) at 11.2 pCi/L and D-61 (0.5 mile downstream, indicator) at 7.9 pCi/L. Since the 1-131 was detected at both the plant intake and the downstream locations, there is no indication of a plant origin.
Analyses for 1-131 were performed on samples from locations D-49 (control) and D-61 (0.5 mi.
downstream, indicator). The February 1-131 chemistry result for location D-61 showed a positive result of 9.3 pCi/L which was consistent with the gamma result on that same sample. There was no sample available at location D-49 in February due to frozen conditions (see table 5.6 page 18).
Quarterly composites were also prepared from the samples collected at locations D-49 and D-61 and tested for strontium-89 and strontium-90. All samples tested below detection limits.
No plant effect on surface water is indicated.
Fish Fish were collected in June and September, 2014, and analyzed for gamma-emitting isotopes.
With the exception of naturally-occurring potassium-40, no gamma-emitting isotopes were identified in edible portions of fish. The potassium-40 level was similar at both the indicator and control locations (3.42 and 3.38 pCi/g wet, respectively).
No reactor by-product radionuclides were identified. All samples met required lower limits of detection as specified in the DAEC Offsite Dose Assessment Manual.
River Sediments River sediments were collected in May and November, 2014, and analyzed for gamma-emitting isotopes. Potassium-40 activity ranged from 5.45 to 8.29 pCi/g dry weight and averaged 7.16 pCi/g dry weight.
No reactor by-product radionuclides were identified. All samples met required lower limits of detection as specified in the DAEC Offsite Dose Assessment Manual.
Ground Water Protection Program Environmental, Inc., Midwest Laboratory provides laboratory services for the Duane Arnold Energy Center Ground Water Protection Program. For results from these analyses, refer to the Duane Arnold Energy Center, 2014 Annual Radioactive Material Release Report.
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5.0 TABLES AND FIGURES 10
Table 5.1 Characteristic properties of isotopes quantified in gamma-spectroscopic analyses.
Designation Naturally Occurring A. Cosmogenic B. Terrestrial I1. Fission Products b A. Short-lived B. Other than Short-lived Ill. Activation Products Comment Produced by interaction with atmosphere of cosmic rays Primordial Nuclear accidents and detonations constitute the major environmental source.
Typically found in nuclear power plant effluents Isotope Be-7 K-40 1-131 Ba-140 Nb-95 Zr-95 Ru-103 Ru-106 Cs-134 Cs-137 Ce-141 Ce-144 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Half-life a 53.2 d 1.26 x 109 y 8.04 d 12.8 d 35.15 d 65 d
- 39.35 d 368.2 d 2.061 y 30.174 y 32.5 d 284.31 d 312.5 d 45.0 d 70.78 d 5.26 y 245 d a
Half-lives are taken from Appendix E of Environmental Quarterly, 1 January 1978, b Energy, 1978).
Includes fission-product daughters.
EML-334 (U. S. Department of 11
Table 5.2 Sample collection and analysis program.
Sampling Location a Exposure Sample Description Sampling and Collection Type and Frequency Pathway and/or Point Frequency of Analysis b Sample Type Airborne 3
Hiawatha Continuous operation of Analyze for gross beta activity Particulates 5
Palo sampler with sample more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after filter 6
Center Point collection at least once per change.
Perform gamma 7
Shellsburg week or as required isotopic analysis on each 11 Toddville by dust loading sample having gross beta 13 Alburnett (C) activity greater than ten times 15 On-site North the yearly mean of the control 16 On-site South samples.
40 Wickiup Hill Composite weekly samples to form a quarterly composite (by location).
Analyze quarterly composite for gamma isotopic.
Airborne 3
Hiawatha Continuous operation of Analyze each cartridge for Iodine 5
Palo sampler with sample iodine-131.
6 Center Point collection at least once per 7
Shellsburg week.
11 Toddville 13 Alburnett (C) 15 On-site North 16 On-site South 40 Wickiup Hill Ambient 1-3, 5-8 (Controls)
One dosimeter continuously Read gamma radiation dose Radiation 10, 11, 13 (Indicators) at each location, quarterly.
15-23, Within 0.5 mile of Dosimeters are changed at 28-32, Stack least quarterly.
33-42 Within 3.0 miles of Stack 43-48 Within 1.0 mile of 82-86, 91 Stack 161-164 ISFSI Fence line Surface Water 49 Lewis Access (C)
Once per month.
Gamma isotopic and tritium 50 Plant Intake analysis for each sample (by 51 Plant Discharge locayion).
61
- % mi. downstream location).
from Plant Discharge Locations 49 and 61, analyses 99 Pleasant Creek Lake for low-level 1-131. Quarterly composites for Sr-89, Sr-90.
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Table 5.2 Sample collection and analysis program, (continued).
Sampling Location a Exposure Sample Description Sampling and Collection Type and Frequency Pathway and/or Point Frequency of Analysis Sample Type Ground 53 Treated Municipal Grab sample at least Analysis gamma emitting Water 54 Water once per quarter isotopes, iodine-131 and tritium on Inlet to Municipal Wate quarterly samples. Iodine-131 55 Treatment System analyzed to an MDA of < 2 pCi/L.
57, 58 On-site well 72 (C)
Wells off-site and If reactor by-product gamma within 4 km of DAEC emitters are identified, or if tritium concentrations measure > MDA, then analyze for Ni-63, Sr-89, Sr-90 and alpha emitters.
River 50 Plant Intake (C)
At least once every six Gamma isotopic analysis of each Sediment 51 Plant Discharge months.
sample 107a North Drainage Ditch (on-site)
Vegetation 16,57 Farms raising food Annually at harvest Gamma isotopic analysis, 58,72, crops time. Two samples of including iodine-131, on each 96,109 each: grain, green leafy, sample.
118 and forage.
138 (C)
Fish 49 Cedar River upstream One sample per 6 Gamma isotopic analysis on of DAEC not months (once during edible portions.
influenced by effluent January through June (C) and once during July 61 through December).
Downstream of DAEC in influence of effluent Milk c 138 (C)
Farm near Newhall, IA At least once per two During the grazinng season:
weeks during the Gamma isotopic and iodine-131 110 Dairy Farm within 7.8 grazing season.
analyses of each sample.
miles from Site At least once per month During the non-grazing season:
during the non-grazing Gamma isotopic and iodine-131 season.
analyses of each sample.
Meat d On-site Annually Gamma Isotopic a (C) denotes control location. All other locations are indicators.
Gamma isotopic analysis and analysis for gamma-emitting nuclides refer to~high resolution gamma ray spectrum analysis.
cThe grazing season is considered to be May 1 through September 30.
d Only sampled when meat is butchered for home use.
13
Table 5.3 Sampling locations, Duane Arnold Energy Center.
Sampling Location Code Location Description Distance and Direction from Site Stack D-1 Cedar Rapids 20,800 meters SE D-2 Marion 16,900 meters ESE D-3 Hiawatha 10,800 meters SE D-5 Palo 4,500 meters SSW D-6 Center Point 9,660 meters N D-7 Shellsburg 7,950 meters W D-8 Urbana 15,000 meters NNW D-10 Atkins 13,600 meters SSW D-1 1 Toddville 4,980 meters E D-13 Alburnett 14,500 meters ENE D-15 On-site, North-Northwest 1,050 meters NNW D-16 On-site, South-Southeast 520 meters SSE D-17 On-site, N 1,050 meters N D-18 On-site, NNE 630 meters NNE D-19 On-site, NE 590 meters NE D-20 On-site, ENE 550 meters ENE D-21 On-site, ENE 515 meters ENE D-22 On-site, ESE 535 meters ESE D-23 On-site, SE 490 meters SE D-28 On-site, WSW 730 meters WSW D-29 On-site, W 630 meters W D-30 On-site, WNW 640 meters WNW D-31 On-site, NW 1,020 meters NW D-32 On-site, NNW 1,110 meters NNW D-33 3 mile ring 4,340 meters N D-34 3 mile ring 3,930 meters NNE D-35 3 mile ring 2,800 meters NE D-36 3 mile ring 3,500 meters ENE D-37 3 mile ring 2,960 meters E D-38 3 mile ring 3,180 meters ESE D-39 3 mile ring 2,510 meters SE D-40 3 mile ring 2,430 meters SSE D-41 3 mile ring 5,680 meters S D-42 3 mile ring 4,380 meters SSE D-43 1 mile ring 1,590 meters SSW D-44 1 mile ring 1,580 meters WSW D-45 1 mile ring 1,420 meters W D-46 1 mile ring 1,580 meters WNW D-47 1 mile ring 1,760 meters NW D-48 1 mile ring 1,680 meters NNW 14
Table 5.3 Sampling locations, Duane Arnold Energy Center (continued).
Samolina Location Code Location Description Distance and Direction from Site Stack D-49 Lewis Access, upstream of DAEC 6,750 meters NNW D-50 Plant Intake 560 meters SE D-51 Plant Discharge 600 meters SE D-53 Treated Municipal Water 13,900 meters SE D-54 Inlet, Municipal Water Treatment System 13,900 meters SE D-55 Production Well D-57 Farm (Off-site Well) 805 meters W D-58 Farm (Off-site Well) 974 meters WSW-SW D-61 Downstream of plant discharge 670 meters SSE D-72 Farm 3,200 meters SSW D-82 On-site, SSE 660 meters SSE D-83 On-site, SSE 620 meters SSE D-84 On-site, S 610 meters S D-85 On-site, SSW 660 meters SSW D-86 On-site, SW 850 meters SW D-91 On-site, NNW 1,090 meters NNW D-96 Farm 11,400 meters SSW D-99 Pleasant Creek Lake 3,880 meters WNW D-107a North Drainage Ditch D-109 Farm 5,890 meters SW D-110 Farm 12,700 meters SW D-118 Farm 2,230 meters NW D-138 Farm 21,600 meters WSW D-161 ISFSI Fence East On-site D-162 ISFSI Fence South On-site D-163 ISFSI Fence West On-site D-164 ISFSI Fence North On-site 15
Table 5.4 Type and Frequency of collection.
Location Weekly l
Quarterly Semiannually Annually D-1 TLD D-2 TLD D-3 AP, Al TLD D-5 AP, Al TLD D-6 AP, Al TLD D-7 AP, Al TLD D-8 TLD D-10 TLD D-1 1 AP, Al TLD D-13 AP, Al TLD D-15 AP, Al TLD D-16 AP, Al TLD G
D-17 to D-23 TLD D-28 to D-39 TLD D-40 AP, Al TLD D-41 to D-48 TLD D-49 SW F
D-50 SW BS D-51 SW BS D-53 WW D-54 WW D-55 WW D-57 WW G
D-58 WW G
D-61 SW F
D-72 WW G
D-82 to D-86 TLD D-91 TLD D-96 G
D-99 SW D-107A BS D-109 G
D-110 MI*
D-118 G
D-138 MI*
G D-161 to D-164 TLD On-site ME
- Biweekly during the grazing season.
16
Table 5.5. Sample codes used in Table 5.4 and Table 5.6.
Code Description AP Airborne Particulates Al Airborne Iodine TLD Thermoluminescent Dosimeter MI Milk WW Well Water G
Vegetation ME Meat SW Surface Water F
Fish BS River Sediment 17
Table 5.6. Program Deviations, Duane Arnold Energy Center.
Sample Collection Date Type Analysis Location(s) or Period Comments SW H-3/ 1-131/Gamma SW H-3 / Gamma SW H-3 / 1-131/Gamma SW H-3 /Gamma SW H-3/Gamma AP/AI Gross Beta /1-131 AP/AI Gross Beta /1-131 AP/AI Gross Beta /1-131 AP/AI Gross Beta / 1-131 AP/AI Gross Beta / 1-131 AP/AI Gross Beta / 1-131 AP/AI Gross Beta / 1-131 TLD Ambient Gamma G
Gamma G
Gamma G
Gamma D-49 D-99 D-49 D-99 D-99 D-13 D-13 D-15 D-1 5 D-1 5 D-1 3 D-13 D-1 7 D-58 D-72 01-22-14 01-22-14 02-04-14 02-04-14 12-20-14 02-07-14 02-13-14 04-16-14 05-16-14 07-11-14 07-17-14 07-24-14 Water frozen.
Water frozen.
Water frozen.
Water frozen.
Water frozen.
Low volume due to power outage Low volume due to power outage Low volume due to power outage Low volume due to power outage Low volume due to power outage.
Power off to sampler.
Power off to sampler.
TLD missing in the field, TLD replaced.
Vegetation not readily available.
Vegetation not readily available.
Vegetation not readily available.
4th Qtr. 2014 2014 2014 2014 D-138 In no instance did missed analyses affect minimum sampling requirements as specified in the ODAM.
18
Table 5.7 Radiological Environmental Monitoring Program Summary.
Name of Facility Location of Facility Duane Arnold Energy Center Linn, Iowa Docket No.
50-331 Reporting Period January-December, 2014 (County, State)
Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLD b Mean (F) c Mean (F) c.
Mean (F) c Routine (Units)
Analyses a Range c Location d Rangec Range c Results e Airborne Pathway Airborne Particulates (pCi/m 3)
GB 4661 0.003 0.026 (416/416)
D-3, Hiawatha 0.028 (52/52)
(0.002-0.060) 7 mi. SE (0.014-0.060)
GS Be-7 36 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 Ru-1 03 Ru-1 06 Cs-134 Cs-137 Ce-141 Ce-144 0.020 0.0011 0.0027 0.0011 0.0012 0.0019 0.0018 0.0021 0.0019 0.0103 0.0012 0.0015 0.0028 0.0075 0.063 (32/32)
(0.038-0.084)
" LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
" LLD
" LLD
" LLD
" LLD
< LLD
<LLD D-40, Toddville' 3.0 mi. SSE 0.068(4/4)
(0.056-0.080) 0.025 (50/50)
(0.011-0.064) 0.063 (4/4)
(0.039-0.089)
< LLD
" LLD
< LLD
< LLD
< LLD
< LLD
< LLD
< LLD
" LLD
" LLD
< LLD
< LLD
< LLD 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
Airborne Iodine 1-131 466 0.030
< LLD
< LLD 0
(pCi/m3)
Direct Radiation TLDs (mR/quarter)
Control Locations Gamma 40 1.0 None D-8,Urbana 17.0 (4/4) 14.6 (40/40) 0 10 mi. NW (11.7-17.7)
(10.5-18.9)
Within 0.5 mi.
Gamma 79 1.0 1.6.3 (79/79)
D-29,On-site 20.6 (4/4)
None 0
of Stack (9.3-22.5) 0.5 mi. W (17.7-22.5)
Within 1.0 mi.
Gamma 24 1.0 16.8 (24/24)
D-46, 19.3 (4/4)
None 0
of Stack (11.7-23.3) 1 mi. WNW (16.2-23.3)
Within 3.0 mi.
Gamma 40 1.0 14.1 (40/40)
D-41, 17.3 (4/4)
None 0
of Stack (10.3-21.0) 3.5 mi. S (15.8-20.0)
ISFSI border Gamma 16 1.0 29.9 (16/16)
D-161 47.9(4/4)
None 0
(11.3-53.2)
ISFSI Fence (42.5-53.2) 19
Table 5.7 Radiological Environmental Monitoring Program Summary.
Name of Facility Location of Facility Duane Arnold Energy Center Linn, Iowa Docket No.
50-331 Reporting Period January-December, 2014 (County, State)
Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLD b Mean (F) c Mean (F)
Mean (F)
Routine (Units)
Analyses a Range c Location d Range Range '
Results e Waterborne Pathway Surface Water H-3 55 183
< LLD
< LLD 0
(pCi/L) 1-131 24 0.5 9.3 (1/12)
D-61,
< LLD 0
0.5 mi., Downstream Sr-89 8
0.9
< LLD
< LLD 0
Sr-90 8
0.8
< LLD
< LLD 0
GS 55 Mn-54 5.1
< LLD
< LLD 0
Fe-59 6.9
< LLD
< LLD 0
Co-58 4.0
< LLD
< LLD 0
Co-60 4.5
< LLD
< LLD 0
Zn-65 7.3
< LLD
< LLD 0
Nb-95 4.9
< LLD
< LLD 0
Zr-95 6.9
< LLD
< LLD 0
1-131 8.5 7.9 (1/33)'
D-50, 11.2 (1/22)'
11.2 (1/2 2 )'
0 Plant Intake Cs-134 4.6
< LLD
< LLD 0
Cs-137 4.8
< LLD
< LLD 0
Ba-140 19.6
< LLD
< LLD 0
La-140 4.1
< LLD
< LLD 0
Sediments GS 6
(pCi/g dry)
K-40 1.0 6.76 (4/4)
D-50, 7.97 (2/2) 7.97 (2/2) 0 (5.45-8.03)
Plant Intake (7.65-8.29)
(7.65-8.29)
Mn-54 0.018
< LLD
< LLD 0
Fe-59 0.039
< LLD
< LLD 0
Co-58 0.016
< LLD
< LLD 0
Co-60 0.011
< LLD
< LLD 0
Zn-65 0.033
< LLD
< LLD 0
Nb-95 0.024
< LLD
< LLD 0
Zr-95 0.026
< LLD
< LLD 0
Ru-103 0.018
< LLD
< LLD 0
Ru-106 0.115
< LLD
< LLD 0
Cs-134 0.012
< LLD
< LLD 0
Cs-137 0.015
< LLD
< LLD 0
Ce-141 0.043
< LLD
< LLD 0
Ce-144 0.094
< LLD
< LLD 0
20
Table 5.7 Radiological Environmental Monitoring Program Summary.
Name of Facility Location of Facility Duane Arnold Energy Center Docket No.
50-331 Reporting Period January-December, 2014 Linn, Iowa (County, State)
Indicator Location with Highest Control Number Sample Type and Locations Annual(Mean Locations Non-Type Number of LLD Mean (F) c Mean (F)
Mean(F)c Routine (Units)
Analyses a Range C Location Rangec Rangec Results Waterborne Pathway Ground Water, H-3 24 176
< LLD
< LLD 0
potable (pCi/L) 1-131 6
0.5
< LLD
< LLD 0
GS 24 Mn-54 2.9
< LLD
< LLD 0
Fe-59 5.5
< LLD
< LLD 0
Co-58 3.7
< LLD
< LLD 0
Co-60 2.0
< LLD
< LLD 0
Zn-65 5.7
< LLD
< LLD 0
Nb-95 3.8
< LLD
< LLD 0
Zr-95 5.3
< LLD
< LLD 0
1-131 10.3
< LLD
< LLD 0
Cs-134 3.3
< LLD
< LLD 0
Cs-137 3.2
< LLD
< LLD 0
Ba-140 22.6
< LLD
< LLD 0
La-140 3.6
< LLD
< LLD 0
Ingestion Pathway Milk 1-131 38 0.5
< LLD
< LLD 0
(pCi/L)
GS 38 K-40 100 1382 (19/19)
D-110, Farm 1382 (19/19) 1362 (19/19) 0 (1161-1644) 7.9 mi. SW (1161-1644)
(1088-1764)
Cs-134 5
< LLD
< LLD 0
Cs-137 5
< LLD
< LLD 0
Ba-140 60
< LLD
< LLD 0
La-140 5
< LLD
< LLD 0
Broadleaf GS 3
Vegetation K-40 0.5 4.18 (3/3)
D-15 6.69 (1/1) none 0
(pCi/g wet)
(1.81 -6.69)
On-site D-15, on-site Mn-54 0.014
< LLD none 0
Fe-59 0.038
< LLD none 0
Co-58 0.013
< LLD none 0
Co-60 0.018
< LLD none 0
Zn-65 0.049
< LLD none 0
Nb-95 0.018
< LLD none 0
Zr-95 0.032
< LLD none 0
Ru-103 0.019
< LLD none 0
Ru-106 0.121
< LLD none 0
1-131 0.033
< LLD none 0
Cs-134 0.016
< LLD none 0
Cs-137 0.017
< LLD none 0
Ce-141 0.046
< LLD none 0
Ce-144 0.176
< LLD none 0
21
Table 5.7 Radiological Environmental Monitoring Program Summary.
Name of Facility Location of Facility Duane Arnold Energy Center Docket No.
Reporting Period Linn, Iowa (County, State) 50-331 January-December, 2014 Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLD b Mean (F)c Mean (F)
Mean (F) c Routine (Units)
Analyses a Range' Location d Range c Range' Results e Ingestion Pathway (cont.)
Vegetation GS 8
(Grain and Forage) K-40 0.5 5.31 (7/7)
D-96 8.6 (2/2) none 0
(pCi/g wet)
(2.61-14.59)
< LLD none 0
Fe-59 0.063
< LLD none 0
Co-58 0.023
< LLD none 0
Co-60 0.025
< LLD none 0
Zn-65 0.047
< LLD none 0
Nb-95 0.033
< LLD none 0
Zr-95 0.055
< LLD none 0
Ru-103 0.023
< LLD none 0
Ru-106 0.234
< LLD none 0
1-131 0.051
< LLD none 0
Cs-134 0.025
< LLD none 0
Cs-1i37 0.030
< LLD none 0
Ce-141 0.047
< LLD none 0
Ce-144 0.171
< LLD none 0
Fish GS 8
(pCi/g wet)
K-40 1.0 3.42 (4/4)
D-61, 3.42 (4/4) 3.38 (4/4) 0 (3.26-3.64)
Downstream (3.26-3.64)
(3.08-3.94)
Mn-54 0.021
< LLD
< LLD 0
Fe-59 0.073
< LLD
< LLD 0
Co-58 0.028
< LLD
< LLD 0
Co-60 0.016
< LLD
< LLD 0
Zn-65 0.040
< LLD
< LLD 0
Nb-95 0.040
< LLD
< LLD 0
Zr-95 0.049
< LLD
< LLD 0
Ru-103 0.042
< LLD
< LLD 0
Ru-106 0.163
< LLD
< LLD 0
Cs-134 0.022
< LLD
< LLD 0
Cs-137 0.019
< LLD
< LLD 0
Ce-141 0.060
< LLD
< LLD 0
Ce-144 0.133
< LLD
< LLD 0
GB = Gross beta; GS = Gamma spectroscopy b LLD = Nominal lower limit of detection based on 4.66 sigma counting error for the background sample.
Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (F).
d Locations are specified by: (1) Name and code (Table 5.3); and (2) distance, direction and sector relative to reactor site.
e Non-routine results are those which exceed ten times the control station value for the location. If a control station value is not available, the result is considered non-routine if it exceeds ten times the preoperational value for the location.
f See section 4.2 page 9 for a discussion of 1-131 in surface water.
22
Figure 5.1 Radiological Environmental Monitoring Program Sampling Stations near the Duane Arnold Energy Center.
4 N
57 I---------- - - j 32 31 30 2
n m
19I 18 19 1078 86 GATE 58 2000 feet See Table 5.3 for sampling locations and Table 5.4 for Type and Frequency of collection.
23
Figure 5.2. Radiological Environmental Monitoring Program Sampling Stations Outside 0.5 Miles.
See Table 5.3 for sampling locations and Table 5.4 for Type and Frequency of collection.
24
6.0 REFERENCES
CITED Arnold, J. R. and H. A. AI-Salih. 1955. Beryllium-7 Produced by Cosmic Rays. Science 121: 451-453.
Eisenbud, M. 1963. Environmental Radioactivity, McGraw-Hill, New York, New York, pp. 213, 275-276.
Environmental, Inc., Midwest Laboratory.
2001 through 2014. Environmental Radiological Monitoring Program for the Duane Arnold Energy Center, Annual Report - Part II, Data Tabulations and Analyses, January - December, 2001 - 2014.
1984 to 2000. (formerly Teledyne Brown Engineering, Environmental Services, Midwest Laboratory)
Environmental Radiological Monitoring Program for the Duane Arnold Energy
- Center, Annual Report - Part II, Data Tabulations and Analyses, January - December, 1983 - 1999.
1982 to 1984.
(formerly Hazleton Environmental Sciences Corporation) Environmental Radiation Monitoring for the Duane Arnold Energy Center, Annual Report - Part II, Data Tabulations and Analyses, January - December 1981 - 1983.
2012.
Quality Assurance Program Manual, Rev. 3, 14 November 2012.
2009.
Quality Control Procedures Manual, Rev. 2, 08 July 2009.
2009.
Quality Control Program, Rev. 2, 12 November 2009.
Gold, S., H. W. Barkhau, B. Shlein, and B. Kahn, 1964. Measurement of Naturally Occurring Radionuclides in Air, in the Natural Environment, University of Chicago Press, Chicago, Illinois, 369-382.
National Center for Radiological Health, 1968. Radiological Health and Data Reports, Vol. 9, Number 12, 730-746.
U.S. Department of Energy. 1978.
Environmental Quarterly, Appendix E. Half-Life Tables, 1 January 1978, EML-334.
U. S. Nuclear Regulatory Commission. 1977.
Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I.
Wilson, D. W., G. M. Ward and J. E. Johnson.
1969.. In Environmental Contamination by Radioactive Materials, International Atomic Energy Agency. p. 125.
25
Environmental, Inc.
Midwest Laboratory 700 Londweh, Road - Northbrook. IL 60062-2310 phone (847) 564-0700 f fax (847) 564-4517 APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS NOTE:
Environmental Inc., Midwest Laboratory participates in intercomparison studies administered by Environmental Resources Associates, and serves as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada. Results are reported in Appendix A. TLD Intercomparison results, in-house spikes, blanks, duplicates and mixed analyte performance evaluation program results are also reported. Appendix A is updated four times a year; the complete Appendix is included in March, June, September and December monthly progress reports only.
January, 2014 through December, 2014
Appendix A Interlaboratory Comparison Program Results Environmental, Inc., Midwest Laboratory has participated in interlaboratory comparison (crosscheck) programs since the formulation of it's quality control program in December 1971. These programs are operated by agencies which supply environmental type samples containing concentrations of radionuclides known to the issuing agency but not to participant laboratories. The purpose of such a program is to provide an independent check on a laboratory's analytical procedures and to alert it of any possible problems.
Participant laboratories measure the concentration of specified radionuclides and report them to the issuing agency. Several months later, the agency reports the known values to the participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used.
Results in Table A-1 were obtained through participation in the environmental sample crosscheck program administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada.
Table A-2 lists results for thermoluminescent dosimeters (TLDs), via International Intercomparison of Environmental Dosimeters, when available, and internal laboratory testing.
Table A-3 lists results of the analyses on in-house "spiked" samples for the past twelve months. All samples are prepared using NIST traceable sources. Data for previous years available upon request.
Table A-4 lists results of the analyses on in-house "blank" samples for the past twelve months. Data for previous years available upon request.
Table A-5 lists REMP specific analytical results from the in-house "duplicate" program for the past twelve months. Acceptance is based on the difference of the results being less than the sum of the errors.
Complete analytical data for duplicate analyses is available upon request.
The results in Table A-6 were obtained through participation in the Mixed Analyte Performance Evaluation Program.
Results in Table A-7 were obtained through participation in the environmental sample crosscheck program administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurement Laboratory Quality Assessment Program (EML).
Attachment A lists the laboratory precision at the 1 sigma level for various analyses. The acceptance criteria in Table A-3 is set at +/- 2 sigma.
Out-of-limit results are explained directly below the result.
AO-1
Attachment A ACCEPTANCE CRITERIA FOR "SPIKED" SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSESa Analysis Gamma Emitters Level 5 to 100 pCi/liter or kg
> 100 pCi/liter or kg One standard deviation for single determination 5.0 pCi/liter 5% of known value Strontium-89b Strontium -90b Potassium-40 Gross alpha Gross beta Tritium Radium-226,-228 Plutonium Iodine-131, Iodine-1 2 9 b Uranium-238, Nickel-63b Technetium
-99b Iron-55b 5 to 50 pCi/liter or kg
> 50 pCi/liter or kg 2 to 30 pCi/liter or kg
> 30 pCi/liter or kg
> 0.1 g/liter or kg
< 20 pCi/liter
> 20 pCi/liter
< 100 pCi/liter
> 100 pCi/liter
< 4,000 pCi/liter
> 4,000 pCi/liter
> 0.1 pCi/liter
> 0.1 pCi/liter, gram, or sample
< 55 pCi/liter
> 55 pCi/liter
<35 pCi/liter
> 35 pCi/liter 50 to 100 pCi/liter
> 100 pCi/liter 5.0 pCi/liter 10% of known value 5.0 pCi/liter 10% of known value 5% of known value 5.0 pCi/liter 25% of known value 5.0 pCi/liter 5% of known value
+10 169.85 x (known)0,933 10% of known value 15% of known value 10% of known value 6 pCi/liter 10% of known value 6 pCi/liter 15% of known value 10 pCi/liter 10% of known value 20% of known value Other Analyses b 8 From EPA publication, "Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.
b Laboratory limit.
AO-2
TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.
Concentration (pCi/L)
Lab Code Date Analysis Laboratory ERA Control Result b Result c Limits Acceptance ERW-1384 4/7/2014 Sr-89 40.29 +/- 5.76 36.70 27.50 +/- 43.60 Pass ERW-1384 4/7/2014 Sr-90 24.08 +/- 2.35 26.50 19.20 +/- 30.90 Pass ERW-1385 4/7/2014 Ba-1 33 78.23 +/- 3.93 87.90 74.00 +/- 96.70 Pass ERW-1385 4/7/2014 Co-60 62.75 +/- 3.53 64.20 57.80 +/- 73.10 Pass ERW-1385 4/7/2014 Cs-134 44.97 +/- 3.99 44.30 35.50 +/- 48.70 Pass ERW-1385 4/7/2014 Cs-137 88.54 +/- 4.93 89.10 80.20 +/- 101.00 Pass ERW-1385 4/7/2014 Zn-65 249.1 +/- 10.4 235.0 212.0 - 275.0 Pass ERW-1388 4/7/2014 Gr. Alpha 56.70 +/- 2.47 61.00 31.90 +/- 75.80 Pass ERW-1388 4/7/2014 Gr. Beta 32.10 +/- 1.20 33.00 21.40 +/- 40.70 Pass ERW-1391 4/7/2014 1-131 25.52 +/- 1.12 25.70 21.30 +/- 30.30 Pass ERW-1394 4/7/2014 Ra-226 12.30 +/- 0.61 12.40 9.26 +/- 14.30 Pass ERW-1394 4/7/2014 Ra-228 5.08 +/- 1.16 4.26 2.46 +/- 5.86 Pass ERW-1394 4/7/2014 Uranium 10.76 +/- 0.74 10.20 7.95 +/- 11.80 Pass ERW-1397 4/7/2014 H-3 8982 +/- 279 8770 7610 -9650 Pass ERW-5382 10/6/2014 Sr-89 29.40 +/- 5.32 31.40 22.80 +/- 38.10 Pass ERW-5382 10/6/2014 Sr-90 19.19 +/- 1.85 21.80 15.60 +/- 25.70 Pass ERW-5385 10/6/2014 Ba-133 43.54 +/- 4.54 49.10 40.30 +/- 54.50 Pass ERW-5385 10/6/2014 Cs-134 81.95 +/- 7.49 89.80 73.70 +/- 98.80 Pass ERW-5385 10/6/2014 Cs-137 95.76 +/- 5.50 98.80 88.90 +/- 111.00 Pass ERW-5385 10/6/2014 Co-60 90.25 +/- 2.77 92.10 82.90 +/- 104.00 Pass ERW-5385 10/6/2014 Zn-65 327.4 +/- 23.3 310.0 279.0 - 362.0 Pass ERW-5388 10/6/2014 Gr. Alpha 30.88 +/- 8.05 37.60 19.40 +/- 46.10 Pass ERW-5388 10/6/2014 G. Beta 20.47 +/- 4.75 27.40 17.30 +/- 35.30 Pass ERW-5392 10/6/2014 1-131 19.58 +/- 2.35 20.30 16.80 +/- 24.40 Pass ERW-5394 10/6/2014 Ra-226 15.10 +/- 1.81 14.70 11.00 +/- 16.90 Pass ERW-5394 10/6/2014 Ra-228 4.42 +/- 0.86 4.31 2.50 +/- 5.92 Pass ERW-5394 10/6/2014 Uranium 5.51 +/- 0.37 5.80 4.34 +/- 6.96 Pass ERW-5397 10/6/2014 H-3 6876 +/- 383 6880 5940 -7570 Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).
b Unless otherwise indicated, the laboratory result is given as the mean +/- standard deviation for three determinations.
c Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA.
Al-1
TABLE A-2. Thermoluminescent Dosimetry, (TLD, CaSO4: Dy Cards).
mR Lab Code Date Known Lab Result Control Description Value
+/- 2 sigma Limits Acceptance Environmental, Inc.
2014-1 2014-1 2014-1 2014-1 2014-1 2014-1 2014-1 2014-1 2014-1 2014-1 2014-1 2014-1 2014-1 5/15/2014 50 cm.
5/15/2014 5/15/2014 5/15/2014 5/15/2014 5/15/2014 5/15/2014 5/15/2014 5/15/2014 5/15/2014 5/15/2014 5/15/2014 5/15/2014 60 cm.
70 cm.
75 cm.
80 cm.
90 cm.
100 cm.
110 cm.
120 cm.
135 cm.
150 cm.
165 cm.
180 cm.
26.83 18.63 13.69 11.93 10.48 8.28 6.71 5.54 4.66 3.68 2.98 2.46 2.07 34.43 +/- 3.76 22.20 +/- 1.16 14.74 +/- 0.80 12.68 +/- 1.05 11.81 +/- 0.91 7.72 +/- 0.71 6.46 +/- 0.71 5.25 +/- 1.03 4.76 +/- 0.48 2.87 +/- 0.46 2.30 +/- 0.15 2.09 +/- 0.28 1.75 +/- 0.21 18.78 - 34.88 13.04 - 24.22 9.58 - 17.80 8.35 - 15.51 7.34 - 13.62 5.80 - 10.76 4.70 - 8.72 3.88 -7.20 3.26 - 6.06 2.58 -4.78 2.09 - 3.87 1.72 -3.20 1.45 - 2.69 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Environmental, Inc.
2014-2 2014-2 2014-2 2014-2 2014-2 2014-2 2014-2 2014-2 2014-2 2014-2 2014-2 2014-2 2014-2 12/9/2014 12/9/2014 12/9/2014 12/9/2014 12/9/2014 12/9/2014 12/9/2014 12/9/2014 12/9/2014 12/9/2014 12/9/2014 12/9/2014 12/9/2014 30 cm.
30 cm.
60 cm.
60 cm.
120 cm.
120 cm.
150 cm.
150 cm.
150 cm.
180 cm.
180 cm.
180 cm.
180 cm.
77.04 77.04 19.26 19.26 4.82 4.82 3.08 3.08 3.08 2.14 2.14 2.14 2.14 84.03 +/- 8.47 83.74 +/- 12.02 20.39 +/- 2.37 20.33 +/- 1.19 5.15 +/- 0.20 5.20 +/- 0.45 3.84 +/- 0.61 3.17 +/- 0.38 3.31 +/- 0.32 2.27 +/- 0.51 2.23 +/- 0.12 2.74 +/- 0.48 1.97 +/- 0.41 53.90 - 100.20 53.90 - 100.20 13.50 - 25.00 13.50 - 25.00 3.40 -6.30 3.40 - 6.30 2.20 -4.00 2.20 -4.00 2.00 -4.00 1.50 -2.80 1.50 -2.80 1.50 -2.80 1.50 -2.80 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A2-1
TABLE A-3. In-House "Spiked" Samples Concentration (pCi/L)a Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 C Activity Limits d Acceptance SPW-1011 SPAP-103 SPAP-105 SPAP-105 SPW-107 SPW-129 SPW-129 SPW-129 SPW-1 30 SPW-133 SPMI-1 35 SPMI-1 35 W-12014 W-12014 SPW-297 SPW-657 SPW-1 127 SPW-1 917 1/13/2014 1/13/2014 1/13/2014 1/13/2014 1/13/2014 1/15/2014 1/15/2014 1/15/2014 1/15/2014 1/15/2014 1/15/2014 1/15/2014 1/20/2014 1/20/2014 1/29/2014 2/25/2014 3/26/2014 3/28/2014 4/25/2014 5/21/2014 5/21/2014 5/21/2014 5/21/2014 5/21/2014 5/21/2014 5/21/2014 5/21/2014 6/18/2014 6/18/2014 6/30/2014 6/30/2014 6/30/2014 Ra-228 Gr. Beta Cs-1 34 Cs-1 37 H-3 Cs-1 34 Cs-1 37 Sr-90 Ni-63 C-14 Cs-1 34 Cs-1 37 Gr. Alpha Gr. Beta Tc-99 Ra-226 U-238 Pu-238 Tc-99 Cs-1 34 Cs-1 37 Sr-89 Sr-90 Cs-1 34 Cs-1 37 Sr-89 S r-90 U-238 C-14 Co-60 Cs-137 H-3 35.47 + 2.55 43.91 +/- 0.34 2.46 + 0.67 102.4 +/-2.7 62,380 +/-707 69.90 + 3.71 84.36 + 7.06 39.48 +/- 1.52 255.8 +/- 3.8 3153 +/- 15 76.80 +/- 4.04 80.44 +/- 6.63 19.69 +/- 0.41 30.35 +/- 0.33 104.2 +/- 1.7 15.84 +/- 0.45 43.28 +/- 2.56 27.37 +/-2.13 531.1 +/- 8.7 70.90 +/- 5.81 79.72 +/- 6.49 83.35 +/- 5.05.
33.37 +/- 1.52 64.15 +/- 4.93 76.21 +/- 6.91 65.82 +/- 4.89 40.90 +/- 1.59 44.80 +/- 1.54 3495 +/- 9 131.8 +/-6.9 143.8 +/- 9.1 6220 +/- 238 30.85 44.82 2.82 99.9 62,246 78.00 75.77.
39.20 204.0 4737 78.00 75.80 20.00 30.90 107.8 16.70 41.72 23.80 21.60 -40.11.
26.89 -62.75 1.69 - 3.95 89.9 - 109.9 49,797 - 74,695 68.00 - 88.00 65.77 - 85.77 31.36 -47.04 142.8 -265.2 2842 - 6632 68.00 - 88.00 65.80 - 85.80 10.00 -30.00 20.90 - 40.90 75.5 - 140.2 11.69 - 21.71 29.20 - 54.24 14ý28 - 33.32 377.41 - 700.90 59.50 - 79.50 65.17 -85.17 58.28 -87.42 31.10 -46.64 59.50 - 79.50 65.17 -85.17 58.28 - 87.42 31.10 - 46.64 29.19 - 54.21 2,842 -6632 126.81 - 154.99 131.04 -160.16 5,089 - 7633 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass SPW-1786 SPW-2168 SPW-2168 SPW-2168 SPW-2168 SPMI-2170 SPMI-2170 SPMI-2170 SPMI-2170 SPW-2792 SPW-2796 WW-2836 WW-2836 WW-2836 539.15 69.50 75.17 72.85 38.87 69.50 75.17 72.85 38.87 41.70 4,737 140.90 145.60 6,361 A3-1
TABLE A-3. In-House "Spiked" Samples Concentration (pCi/L)a Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 c Activity Limits d Acceptance SPW-3486 SPW-080714 SPW-080714 SPW-081214 SPW-4093 SPW-4093 SPW-4093 SPMI-4095 SPMI-4095 SPW-4104 SPW-4106 SPW-4108 SPW-4108 SPAP-41 10 SPF-4112 SPF-4112 SPF-4112 SPW-081414 W081614 W082614 SPW-090414 SPW-090414 SPW-5124 W100714 W100714 W111014 W111014 W112514 W120814 W120814 SPW-7149 7/17/2014 8/7/2014 8/7/2014 8/12/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/14/2014 8/16/2014 8/26/2014 9/4/2014 9/4/2014 9/29/2014 10/7/2014 10/7/2014 11/10/2014 11/10/2014 11/25/2014 12/8/2014 12/8/2014 12/26/2014 Fe-55 Gr. Alpha Gr. Beta Pu-238 1-131 (G)
Sr-90 Sr-89 1-131 (G) 1-131 Ni-63 H-3 Cs-1 34 Cs-1 37 Gr. Beta 1-131 Cs-1 34 Cs-1 37 H-3 Ra-226 Ra-228 Gr. Alpha Gr. Beta Ra-228 Gr. Alpha Gr. Beta Gr. Alpha Gr. Beta Ra-226 Gr. Alpha Gr. Beta Ni-63 2211 +/-72 18.42 +/- 0.40 31.70 +/- 0.40 22.59 +/- 2.15 59.95 +/- 6.17 39.46 +/- 1.55 105.5 +/- 4.9 59.92 +/- 6.17 60.05 +/- 0.72 200.1 +/- 3.4 59,597 +/- 695 2.45 +/- 0.81 90.20 +/- 3.74 43.65 +/- 0.11 2.64 +/- 0.38 0.91 +/- 0.03 2.61 +/- 0.06 14,663 +/- 788 14.30 +/- 0.37 27.18 +/- 2.13 17.85 +/- 0.39 30.03 +/- 0.33 32.93 +/- 2.38 18.56 +/- 0.40 27.71 +/- 0.32 17.84 +/- 0.38 30.12 +/- 0.33 16.63 +/- 0.41 19.29 +/- 0.41 27.93 +/- 0.32 217.53 +/- 3.25 2319 20.10 32.40 22.70 59.62 38.65 115.0 59.62 59.62 203.2 60,261 2.32 98.56 44.19 2.86 1.03 2.39 17,700 16.70 30.49 20.10 30.90 31.94 20.10 30.90 20.10 30.90 16.70 20.10 30.90 203.10 1855 -2783 10.05 -30.15 22.40 - 42.40 18.16 -27.24 49.62 - 69.62 28.65 - 48.65 92.0 - 149.5 49.62 - 69.62 47.70 -71.54 142.2 -264.1 48209:- 72313 0.00 - 12.32 88.56 - 108.56 34.19 -54.19 0.00 - 12.86 0.00 -11.03 0.00 -12.39 14160 -21240 11.69 - 21.71 20.49 - 40.49 10.05 -30.15 20.90 - 40.90 21.94 -41.94 10.05 -30.15 20.90 - 40.90 10.05 -30.15 20.90 - 40.90 11.69 -21.71 10.05 -30.15 20.90 -40.90 142.17 -264.03 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass a Liquid sample results are reported in pCi/Liter, air filters( pCi/m3), charcoal (pCi/charcoal canister), and solid samples (pCi/kg).
b Laboratory codes: W (Water), MI (milk), AP (air filter), SO (soil), VE (vegetation), CH (charcoal canister), F (fish), U (urine).
' Results are based on single determinations.
d Control limits are established from the precision values listed in Attachment A of this report, adjusted to +/- 2s.
NOTE: For fish, Jello is used for the spike matrix. For vegetation, cabbage is used for the spike matrix.
A3-2
TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)a Lab Code Sample Date Analysisb Laboratory results (4.66a)
Acceptance Type LLD Activityc Criteria (4.66 av)
SPW-1001 SPAP-102 SPAP-104 SPAP-104 SPW-106 SPW-128 SPW-128 SPW-1 28 SPW-130 SPW-133 SPMI-134 SPMI-134 W-12014 W-12014 SPW-297 SPW-656 SPW-1 126 SPW-1 127 SPW-1 127 SPW-1917 SPW-1 785 SPW-1 831 SPW-2167 SPW-2167 SPW-2167 SPW-2167 SPW-2167 SPMI-2169 SPMI-2169 SPMI-2169 SPMI-2169 SPMI-2169 SPW-2793 Water Air Particulate Air Particulate Air Particulate Water Water Water Water Water Water Milk Milk Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Milk Milk Milk Milk Milk Water 1/13/2014 1/13/2014 1/13/2014 1/13/2014 1/13/2014 1/15/2014 1/15/2014 1/15/2014 1/15/2014 1/15/2014 1/15/2014 1/15/2014 1/20/2014 1/20/2014 1/29/2014 2/25/2014 3/26/2014 3/26/2014.
3/26/2014 3/28/2014 4/25/2014 4/30/2014 5/21/2014 5/21/2014 5/21/2014 5/21/2014 5/21/2014 5/21/2014 5/21/2014 5/21/2014 5/21/2014 5/21/2014 6/18/2014 Ra-228 Gr. Beta Cs-134 Cs-137 H-3 Cs-134 Cs-137 Sr-90 Ni-63 C-14 Cs-134 Cs-137 Gr. Alpha Gr. Beta Tc-99 Ra-226 U-238 U-233/234 U-238 Pu-238 Tc-99 1-131 Cs-1 34 Cs-1 37 1-131(G)
Sr-89 Sr-90 Cs-134 Cs-1 37 1-131(G)
Sr-89 Sr-90 U-238 0.74 0.003 0.006 0.004 151.0 2.85 2.52 0.61 10.85 13.51 4.43 1.92 0.48 0.78 5.63 0.03 0.13 0.13 0.00 0.02 5.61 0.21 2.29 2.46 2.77 0.81 0.52 4.45 3.91 4.31 0.98 0.61 0.08 0.39 +/- 0.39 0.015 +/- 0.003 0.005 +/- 0.005
-0.002 +/- 0.005 115.0 +/- 97.0 0.59 +/- 1.46 0.68 +/- 1.64 0.74 +/- 0.36 1.57 +/- 6.60 3.10 +/- 8.27 0.14 +/- 2.46
-2.07 +/- 2.48
-0.31 +/- 0.31
-0.24 +/- 0.54
-4.42 +/- 3.34 0.01 +/- 0.02 0.08 +/- 0.12 0.11 +/- 0.13 0.08 +/- 0.12 0.01 +/- 0.01
-4.33 +/- 3.33 0.07 +/- 0.12
-0.79 +/- 1.35 0.36 +/- 1.48 0.25 +/- 1.53 0.01 +/- 0.62 0.03 +/- 0.24
-0.55 +/- 2.39
-0.52 +/- 2.60 2.57 +/- 2.21
-0.02 +/- 0.83 0.35 +/- 0.32 0.02 +/- 0.06 2
0.01 0.05 0.05 200 10 10 1
20 200 10 10 2
4 10 1
1 1
1 1
10 0.5 10 10 20 5
1 10 10 20 5
1 1
A4-1
TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)a Lab Code Sample bate Analysisb Laboratory results (4.66a)
Acceptance Type LLD Activityc Criteria (4.66 c)
SPW-3485 SPW-4092 SPW-4092 SPW-4092 SPW-4092 SPW-4092 SPMI-4094 SPMI-4094 SPMI-4094 SPMI-4094 SPMI-4094 SPMI-4094 SPW-4103 SPW-4105 SPW-4107 SPW-4107 SPW-4107 SPAP-4109 SPF-4 111 SPF-4111 SPF-4111 W-081614 W-082614 W-092314 W-5123 W-100714 W-100714 W-111014 W-111014 W-112514 W-120814 W-120814 SPW-7148 Water Water Water Water Water Water Milk Milk Milk Milk Milk Milk Water Water Water Water Water Air Particulate Fish Fish Fish Water Water Water Water Water Water Water Water Water Water Water Water 7/17/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/16/2014 8/16/2014 9/23/2014 9/29/2014 10/7/2014 10/7/2014.
11/10/2014 11/10/2014 11/25/2014 12/8/2014 12/8/2014 12126/2014 Fe-55 1-131(G)
Cs-134 Cs-137 Sr-89 Sr-90 1-131 1-131(G)
Cs-134 Cs-137 Sr-89 Sr-90 Ni-63 H-3 1-131(G)
Cs-1 34 Cs-1 37 Gr. Beta Cs-1 34 Cs-1 37 Co-60 Ra-226 Ra-228 Ra-226 Ra-228 Gr. Alpha Gr. Beta Gr. Alpha Gr. Beta Ra-226 Gr. Alpha Gr. Beta Ni-63 597.6 3.59 3.71 2.71 0.89 0.52 0.35 4.50 4.30 3.45 0.80 0.47 0.12 138.1 3.21 2.72 2.56 0.004 0.01 0.01 0.01 0.04 0.62 0.02 0.70 0.39 0.76 0.39 0.75 0.05 0.42 0.74 10.80 10.3 +/- 363.3 0.91 +/- 1.95
-0.31 +/- 1.77
-2.20 +/- 1.98 0.11 +/-0.63
-0.05 +/- 0.23 0.03 +/- 0.20
-0.41 +/- 2.44
-0.84 +/- 2.02 0.96 +/- 2.51
-0.19 +/- 0.79 0.71 +/- 0.30 0.02 +/- 0.07 104.1 +/- 78.1
-3.68 +/- 1.33
-0.62 +/- 1.49 0.75 +/- 1.62
-0.003 +/- 0.00 0.00 +/- 0.01
-0.01 +/- 0.01 0.00 +/- 0.01 0.05 +/- 0.03 0.29 +/- 0.40 0.04 +/- 0.02 0.43 +/- 0.38 0.04 +/- 0.28
-0.06 +/- 0.53 0.01 +/- 0.28
-0.25 +/- 0.52 0.02 +/- 0.03 0.04 +/- 0.30
-0.42 +/- 0.51
-1.80 +/- 6.50 1000 20 10 10 5
1 0.5 20 10 10 5
1 20 200 20 10 10 0.01 100 100 100 1
2 1
2 2
4 2
4 2
2 4
20 a Liquid sample results are reported in pCi/Liter, air filters(pCi/m3), charcoal (pCi/charcoal canister), and solid samples (pCi/kg).
b 1-131(G); iodine-1 31 as analyzed by gamma spectroscopy.
' Activity reported is a net activity result.
A4-2
TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance AP-7829, 7830 AP-7913, 7914 AP-7871, 7872 S-43, 44 SG-64, 65 SG-64, 65 SG-64, 65 S-136, 137 S-136,137 WW-220,221 WW-262,263 WW-346, 347 SWU-367, 368 F-409, 410 F-409, 410 AP-7829, 7830 AP-7913, 7914 AP-7871, 7872 S-43, 44 SG-64, 65 SG-64, 65 SG-64, 65 S-136,137 S-136,137 WW-220, 221 WW-262, 263 WW-346, 347 SWU-367, 368 F-409, 410 F-409, 410 WW-491,492 WW-575, 576 W-617, 618 SWU-743, 744 S-700,701 S-806, 807 SG-928, 929 SG-928, 929 SG-928, 929 SG-928,929 SG-928, 929 SG-928, 929 SG-928,929 1/2/2014 112/2014 1/3/2014 1/9/2014 1/9/2014 1/9/2014 1/9/2014 1/13/2014 1/13/2014 1/13/2014 1/21/2014 1/24/2014 1/29/2014 2/2/2014 2/2/2014 1/2/2014 1/2/2014 1/3/2014 1/9/2014 1/9/2014 1/9/2014 1/9/2014 1/13/2014 1/13/2014 1/13/2014 1/21/2014 1/24/2014 1/29/2014 2/2/2014 2/2/2014 2/6/2014 2/13/2014 2/14/2014 2/25/2014 2/26/2014 3/4/2014 3/11/2014 3/11/2014 3/11/2014 3/11/2014 3/11/2014 3/11/2014 3/11/2014 Be-7 Be-7 Be-7 K-40 Gr. Alpha Ra-226 Ra-228 Be-7 K-40 H-3 H-3 H-3 Gr. Beta Cs-1 37 Gr. Beta Be-7 Be-7 Be-7 K-40 Gr. Alpha Ra-226 Ra-228 Be-7 K-40 H-3 H-3 H-3 Gr. Beta Cs-137 Gr. Beta H-3 H-3 H-3 Gr. Beta K-40 K-40 Ac-228 Bi-214 K-40 Pb-212 Pb-214 Th-228 TI-208 0.08 +/- 0.02 0.07 +/- 0.01 0.05 +/- 0.02 19.28 +/- 0.57 686.08 +/- 69.97 97.30 +/- 9.78 91.90 +/- 9.30 14.90 +/- 0.39 3.29 +/- 0.36 231.85 +/- 80.45 294.80 +/- 89.80 934.97 +/- 118.47 0.74 +/- 0.38 0.05 +/- 0.02 3.60 +/- 0.07 0.08 +/- 0.02 0.07 +/- 0.01 0.05 +/- 0.02 19.28 +/- 0.57 686.08 +/- 69.97 97.30 +/- 9.78 91.90 +/- 9.30 14.90 +/- 0.39 3.29 +/- 0.36 231.85 +/- 80.45 294.80 +/- 89.80 934.97 +/- 118.47 0.74 +/- 0.38 0.05 +/- 0.02 3.60 +/- 0.07 474.00 +/- 101.10 196.69 +/- 82.94 526.29 +/- 97.65 1.61 +/- 0.65 21.32 +/- 0.64 24.79 +/- 0.57 6.78 +/- 0.34 5.32 +/- 0.20 4.79 +/- 0.80 2.70 +/- 0.09 5.39 +/- 0.17 6.10 +/- 2.07 0.92 +/- 0.06 0.06 +/- 0.01 0.06 +/- 0.01 0.06 +/- 0.01 19.24 +/- 0.57 642.46 +/- 65.59 92.20 +/- 9.27 97.10 +/- 9.87 14.88 +/- 0.38 3.93 +/- 0.36 273.46 +/- 82.47 265.00 +/- 88.47 965.59 +/- 119.52 1.31 +/- 0.42 0.05 +/- 0.02 3.72 +/- 0.07 0.06 +/- 0.01 0.06 +/- 0.01 0.06 +/- 0.01 19.24 +/- 0.57 642.46 +/- 65.59 92.20 +/- 9.27 97.10 +/- 9.87 14.88 +/- 0.38 3.93 +/- 0.36 273.46 +/- 82.47 265.00 +/- 88.47 965.59 +/- 119.52 1.31 +/- 0.42 0.05 +/- 0.02 3.72 +/- 0.07 583.10 +/- 105.30 154.68 +/- 80.89 579.51 +/- 99.77 1.73 +/- 0.71 21.15 + 0.59 24.17 +/- 0.59 6.94 +/- 0.35 5.34 +/- 0.22 6.24 +/- 1.01 2.75 +/- 0.09 5.53 +/- 0.17 4.76 +/- 1.93 0.91 +/- 0.06 0.07 +/- 0.01 0.06 +/- 0.01 0.06 +/- 0.01 19.26 +/- 0.40 664.27 +/- 47.95 94.75 +/- 6.74 94.50 +/- 6.78 14.89 +/- 0.27 3.61 +/- 0.25 252.66 +/- 57.60 279.90 +/- 63.03 950.28 +/- 84.14 1.02 +/- 0.28 0.05 +/- 0.01 3.66 +/- 0.05 0.07 +/- 0.01 0.06 +/- 0.01 0.06 +/- 0.01 19.26 +/- 0.40 664.27 +/- 47.95 94.75 +/- 6.74 94.50 +/- 6.78 14.89 +/- 0.27 3.61 +/- 0.25 252.66 +/- 57.60 279.90 +/- 63.03 950.28 +/- 84.14 1.02 +/- 0.28 0.05 +/- 0.01 3.66 +/- 0.05 528.55 +/- 72.99 175.69 +/- 57.93 552.90 +/- 69.80 1.67 +/- 0.48 21.24 +/- 0.44 24.48 +/- 0.41 6.86 +/- 0.24 5.33 +/- 0.15 5.52 +/- 0.64 2.73 +/- 0.06 5.46 +/- 0.12 5.43 +/- 1.42 0.92 +/- 0.04 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A5-1
TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance S-2119, 2120 S-2119, 2120 S-2119, 2120 S-2119, 2120 F-1594, 1595 SO-1115, 1116 SO-1115, 1116 SO-1115, 1116 SO-1115, 1116 SO-1115, 1116 S-1033, 1034 S-1033, 1034 S-1033, 1034 S-1033, 1034 S-1033, 1034 S-1033, 1034 W-1094, 1095 W-1094, 1095 AP-1197, 1198 AP-1698, 1699 E-1218, 1219 E-1218, 1219 SWU-1260, 1261 AP-1615, 1616 AP-1657, 1658 AP-1804, 1805 P-1489, 1490 BS-1531, 1532 S-1909, 1910 SWU-1867, 1868 AP-1930, 1931 SL-1888, 1889 SL-1888, 1889 SL-1888, 1889 SL-1888, 1889 SO-1 972, 1973 SO-1972, 1973 SO-1972, 1973 SO-1972, 1973 W-617, 618 AP-2077, 2078 3/12/2014 3/12/2014 3/12/2014 3/12/2014 3/16/2014 3/18/2014 3/18/2014 3/18/2014 3/18/2014 3/18/2014 3/19/2014 3/19/2014 3/19/2014 3/19/2014 3/19/2014 3/19/2014 3/23/2014 3/23/2014 3/27/2014 3/31/2014 4/1/2014 4/1/2014 4/1/2014 4/1/2014 4/2/2014 4/3/2014 4/7/2014 4/16/2014 4/22/2014 4/29/2014 5/1/2014 5/1/2014 5/1/2014 5/1/2014 5/11/2014 5/1/2014 5/1/2014 5/1/2014 5/1/2014 5/8/2014 5/8/2014 Ac-228 Cs-137 K-40 Pb-214 Cs-137 Cs-137 Gr. Beta K-40 U-233/4 U-238 Ac-228 Bi-214 Cs-137 K-40 Pb-214 TI-208 Ra-226 Ra-228 Be-7 Be-7 Gr. Beta K-40 Gr. Beta Be-7 Be-7 Be-7 H-3 K-40 K-40 Gr. Beta Be-7 Be-7 Cs-137 Gr. Beta K-40 Cs-137 Gr. Alpha Gr. Beta K-40 H-3 Be-7 0.76 +/- 0.20 0.13 +/- 0.05 17.48 +/- 1.48 0.73 +/- 0.18 0.02 +/- 0.01 0.06 +/- 0.01 23.30 +/- 2.10 12.63 +/- 0.18 0.11 +/- 0.02 0.13 +/- 0.02 0.99 +/- 0.20 1.02 +/- 0.18 0.15 +/- 0.04 15.39 +/- 1.19 1.09 +/- 0.13 0.36 +/- 0.05 0.30 +/- 0.20 1.10 +/- 0.79 0.17 +/- 0.08 0.06 +/- 0.02 1.57 +/- 0.04 1.26 +/- 0.14 2.81 +/- 0.51 0.07 +/- 0.01 0.07 +/- 0.01 0.05 +/- 0.02 582.31 +/- 101.85 0.51 +/- 0.19 14.71 +/- 0.54 2.28 +/- 0.40 0.16 +/- 0.09 0.80 +/- 0.04 0.01 +/- 0.00 11.57 +/- 0.72 1.04 +/- 0.05 0.12 +/- 0.03 7.51 +/- 3.24 29.89 +/- 3.25 20.45 +/- 0.85 175.13 +/- 83.82 0.23 +/- 0.11 0.73 +/- 0.21 0.11 +/- 0.05 18.39 +/- 1.53 0.63 +/- 0.12 0.03 +/- 0.02 0.06 +/- 0.00 24.40 +/- 2.20 12.84 +/- 0.15 0.12 +/- 0.02 0.14 +/- 0.02 1.13 +/- 0.26 0.98 +/- 0.16 0.14 +/- 0.04 15.13 +/- 1.19 0.88 +/- 0.17 0.31 +/- 0.05 0.70 +/- 0.20 1.13 +/- 0.86 0.14 +/- 0.08 0.07 +/- 0.02 1.57 +/- 0.04 1.31 +/- 0.18 2.94 +/- 0.50 0.07 +/- 0.02 0.08 +/- 0.01 0.06 +/- 0.01 505.07 +/- 98.72 0.58 +/- 0.23 14.78 +/- 0.53 1.67 +/- 0.35 0.19 +/- 0.11 0.76 +/- 0.08 0.01 +/- 0.00 12.67 +/- 0.78 1.00 +/- 0.09 0.10 +/- 0.02 9.09 +/- 3.63 31.42 +/- 3.04 20.88 +/- 0.76 177.17 +/- 83.92 0.18 +/- 0.11 0.75 +/- 0.15 0.12 +/- 0.04 17.94 +/- 1.06 0.68 +/- 0.11 0.03 +/- 0.01 0.06 +/- 0.00 23.85 +/- 1.52 12.74 +/- 0.12 0.12 +/- 0.01 0.14 +/- 0.01 1.06 +/- 0.16 1.00 +/- 0.12 0.15 +/- 0.03 15.26 +/- 0.84 0.99 +/- 0.11 0.34 +/- 0.04 0.50 +/- 0.14 1.12 +/- 0.58 0.15 +/- 0.05 0.07 +/- 0.01 1.57 +/- 0.03 1.29 +/- 0.11 2.88 +/- 0.36 0.07 +/- 0.01 0.07 +/- 0.01 0.06 +/- 0.01 543.69 +/- 70.92 0.54 +/- 0.15 14.75 +/- 0.38 1.98 +/- 0.27 0.17 +/- 0.07 0.78 +/- 0.05 0.01 +/- 0.00 12.12 +/- 0.53 1.02 +/- 0.05 0.11 +/- 0.02 8.30 +/- 2.43 30.66 +/- 2.23 20.66 +/- 0.57 176.15 +/- 59.31 0.20 +/- 0.08 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A5-2
- TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance S-2205, 2206 S-2205, 2206 VE-2184, 2185 VE-2184, 2185 DW-50102, 50103 DW-50102, 50103 SW-2226, 2227 DW-50087, 50088 DW-50090, 50091 DW-50090, 50091 DW-50098, 50099 AP-2289, 2290 PM-3174, 3175.
G-2415,2416 G-2415, 2416 G-2415,2416 WW-2541, 2542 SW-2817, 2818 SS-2943, 2944 S-3048, 3049 SWT-3216, 3217 AP-3699,3700 S-3300, 3301 S-3300,3301 S-3300, 3301 VE-3237,3238 CF-3384,3385 S-3447,3448 WW-3573,3574 VE-3594,3595 WW-3762,3763 SWT-3867, 3868 S-3804, 3805 S-3804, 3805 LW-3931, 3932 5/15/2014 5/15/2014 5/19/2014 5/19/2014 5/20/2014 5/20/2014 5/21/2014 5/21/2014 5/21/2014 5/21/2014 5/21/2014 5/22/2014 5/28/2014 6/2/2014 6/2/2014 6/2/2014 6/4/2014 6/16/2014 6/24/2014 6/27/2014 7/1/2014 7/3/2014 7/8/2014 7/8/2014 7/8/2014 7/8/2014 7/14/2014' 7/16/2014 7/18/2014 7/22/2014 7/25/2014 7/29/2014 7/30/2014 7/30/2014 7/31/2014 Be-7 K-40 Be-7 K-40 Ra-226 Ra-228 H-3 Gr. Alpha Ra-226 Ra-228 Gr. Alpha Be-7 K-40 Be-7 Gr. Beta K-40 H-3 H-3 K-40
.K-40 Gr. Beta Be-7 K-40 Ac-228 Ra-226 K-40 K-40 K-40 H-3 K-40 H-3 Gr. Beta Ac-228 Pb-214 Gr. Beta 0.50 +/- 0.19 33.60 +/- 0.79 0.62 +/- 0.18 5.30 +/- 0.44 7.07 +/- 0.76 5.44 +/- 0.85 14318.00 +/- 347.00 1.76 +/- 1.09
- 0.61 +/- 0.09 0.97 +/- 0.41 13.04 +/- 1.36 0.14 +/- 0.08 30.68 +/- 1.30 0.73 +/- 0.16 5.89 +/- 0.09 5.30 +/- 0.49 5107.00 +/- 223.00 13303.00 +/- 336.00 11.49 +/- 0.79 42.51 +/- 1.31 2.27 +/- 0.94 0.06 +/- 0.01 4.85 +/- 0.97 10.23 +/- 0.43 70.14 +/- 2.37 2.54 +/- 0.27 11.10 +/- 0.58 19.63 +/- 0.64 381.58 +/- 85.76 3.04 +/- 0.19 315.47 +/- 87.02 1.10 +/- 0.53 0.67 +/- 0.11 0.56 +/- 0.05 1.04 +/- 0.40 0.70 +/- 0.18 33.52 +/- 0.70 0.53 +/- 0.17 5.14 +/- 0.44 8.31 +/- 0.90 6.02 +/- 0.67 14350.00 +/- 347.00 2.67 +/- 1.01 0.47 +/- 0.09 1.26 +/- 0.52 10.76 +/- 1.26 0.24 +/- 0.10 32.64 +/- 1.24 0.62 +/- 0.28 5.90 +/- 0.09 5.19 +/- 0.65 5029.00 +/- 222.00 13130.00 +/- 334.00 11.81 +/- 0.70 40.04 +/- 1.39 2.53 +/- 1.05 0.07 +/- 0.02 5.91 +/- 1.17 10.18 +/- 0.32 72.01 +/- 2.38 2.63 +/- 0.24 10.69 +/- 0.60 21.03 +/- 0.96 401.30 +/- 86.67 3.21 +/- 0.15 327.30 +/- 87.56 1.51 +/- 0.58 0.61 +/- 0.10 0.51 +/- 0.04 0.95 +/- 0.41 0.60 +/- 0.13 33.56 +/- 0.53 0.58 +/- 0.12 5.22 +/- 0.31 7.69 +/- 0.59 5.73 +/- 0.54 14334.00 +/- 245.37 2.22 +/- 0.74 0.54 +/- 0.06 1.12 +/- 0.33 11.90 +/- 0.93 0.19 +/- 0.06 31.66 +/- 0.90 0.68 +/-0.16 5.89 +/- 0.06 5.25 +/- 0.41 5068.00 +/- 157.33 13216.50 +/- 236.88 11.65 +/- 0.53 41.28 +/- 0.95 2.40 +/- 0.70 0.07 +/- 0.01.
5.38 +/- 0.76 10.21 +/- 0.27 71.08 +/- 1.68 2.59 +/- 0.18 10.90 +/- 0.42 20.33 +/- 0.58 391.44 +/- 60.96 3.13 +/- 0.12 321.39 +/- 61.72 1.31 +/- 0.39 0.64 +/- 0.07 0.54 +/- 0.03 1.00 +/- 0.29 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A5-3
TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance G-3952,3953 G-3952,3953 G-3952,3953 G-3952,3953 WW-4036, 4037 VE-4204,4205 WW-4394,4395 VE-4183,4184 AV-4455, 4456 AV-4455, 4456 WW-4500, 4501 AP-090214A/B SG-5089, 5090 SG-5089, 5090 SG-5194,5 SG-5194,5 SG-5194,5 S-5632,3 S-5632,3 S-5632,3 S-5632,3 S-5632,3 S-5632,3 S-5632,3 DW-50243,4 AP-101414A/B SG-5590,1 SG-5590,1 DW-50251,2 U-5842,3 CF-6074,5 CF-6074,5 8/4/2014 8/4/2014 8/4/2014 8/4/2014 8/5/2014 8/11/2014 8/13/2014 8/14/2014 8/22/2014 8/22/2014 8/26/2014 9/2/2014 9/19/2014 9/19/2014 10/11/2014 10/1/2014 10/1/2014 10/8/2014 10/8/2014 10/8/2014 10/8/2014 10/8/2014 10/8/2014 10/8/2014 10/13/2014 10/14/2014 10/15/2014 10/15/2014 10/16/2014 10/20/2014 10/21/2014 10/21/2014 K-40 Be-7 Gr. Beta H-3 H-3 K-40 H-3 K-40 Be-7 K-40 H-3 Gr. Beta Ac-228 Bi-214 Gr. Alpha Pb-214 Ac-228 K-40 Cs-137 TI-208 Pb-212 Pb-214 Bi-212 Ac-228 Gr. Alpha Gr. Beta Pb-214 Ac-228 Ra-226 H-3 H-3 K-40 5.42 +/- 0.42 1.29 +/- 0.19 8.53 +/- 0.20 140.16 +/- 93.50 190.60 +/- 82.60 6.28 +/- 0.38 1540.26 +/- 136.52 5.70 +/- 0.41 286.67 +/- 102.30 2547.90 +/- 255.70 347.00 +/- 100.00 5.35 +/- 0.34 1.24 +/- 0.16 8.63 +/- 0.20 127.25 +/- 92.99 164.70 +/-.81.30 6.60 +/- 0.37 1499.15 +/- 135.43 5.73 +/- 0.34 251.99 +/- 98.94 2201.40 +/- 203.90 321.00 +/- 98.00 0.03 +/- 0.04 8.26 +/- 0.63 4.71 +/- 0.29 0.03 +/- 0.04 9.48 +/- 0.68 4.41 +/- 0.31 276.20 +/- 9.51 43.56 +/- 0.73 59.90 +/- 1.37 19.28 +/- 0.88 0.15 +/- 0.03 0.32 +/- 0.03 0.92 +/- 0.05 1.25 +/- 0.08 1.25 +/- 0.29 1.08 +/- 0.14 2.99 +/- 0.94 0.02 +/- 0.00 80.30 +/- 8.08 64.50 +/- 1.87 0.55 +/- 0.13 7376 +/- 949 7509 +/- 283 3.09 +/- 0.31 258.60 +/- 9.26 43.94 +/- 0.78 62.80 +/- 1.73 17.94 +/- 0.89 0.13 +/- 0.03 0.34 +/- 0.03 0.92 +/- 0.05 1.09.+/- 0.09 1.34 +/- 0.47 1.10 +/- 0.14 4.98 + 1.17 0.02 +/- 0.00 73.40 +/- 7.51 62.80 - 1.15 0.32 _ 0.10 7342 +/- 947 7969 +/- 291 3.30 +/- 0.38 5.38 +/- 0.27 1.27 +/- 0.13 8.58 +/- 0.14 133.70 +/- 65.94 177.65 +/- 57.95 6.44 +/- 0.27 1519.71 +/- 96.15 5.72 +/- 0.27 269.33 +/- 71.16.
2374.65 +/- 163.52 334.00 +/- 70.01 0.03 +/- 0.00 8.87 +/- 0.46 4.56 +/- 0.21 267.40 +/- 6.64 43.75 +/- 0.53 61.35 +/- 1.10 18.61 +/- 0.63 0.14 +/- 0.02 0.33 +/- 0.02 0.92 +/- 0.03 1.17 +/- 0.06 1.29 +/- 0.27 1.09 +/- 0.10 3.99 +/- 0.75 0.02 +/- 0.00 76.85 +/- 5.52 63.65 +/- 1.10 0.44 +/- 0.08 7359 +/- 670 7739 +/- 203 3.20 +/- 0.25 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A5-4
TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance VE-6269,70 VE-6269,70 SO-6500,1 SO-6500,1 SO-6500,1 SO-6500,1 SO-6500,1 SO-6500,1 SO-6500,1 SO-6500,1 SO-6500,1 SO-6500,1 SO-6500,1 SO-6500,1 DW-50262,3 DW-50264,5 DW-50264,5 AP-120214A/B AP-120814A/B SG-7068,9 SG-7068,9 S-7152,3 11/3/2014 11/3/2014 11/5/2014 11/5/2014 11/5/2014 11/5/2014 11/5/2014 11/5/2014 11/5/2014 11/5/2014 11/5/2014 11/5/2014 11/5/2014 11/5/2014 11/10/2014 11/10/2014 11/10/2014 12/2/2014 12/8/2014 12/19/2014 12/19/2014 12/25/2014 K-40 Be-7 Sr-90 Gr. Alpha Gr. Beta.
U-233/4 U-238 Th-228 Th-230 Th-232 Bi-214 Pb-214 Ac-228 Cs-137 Gr. Alpha Ra-226 Ra-228 Gr. Beta Gr. Beta Pb-214 Ac-228 K-40 6.25 +/- 0.54 0.81 +/- 0.28 0.07 +/- 0.03 11.77 +/- 1.73 26.69 +/- 1.62 0.14 +/- 0.04 0.18 +/- 0.05 0.47 +/- 0.11 0.38 +/- 0.07 0.41 +/- 0.08 0.75 +/- 0.02 0.78 +/- 0.08 1.02 +/- 0.11 0.40 +/- 0.01 8.95 +/- 1.26 3.89 +/- 0.24 2.96 +/- 0.63 0.03 +/- 0.00 0.03 +/- 0.01 4.27 +/- 0.23 2.72 +/- 0.36 20.83 +/- 0.88 6.56 +/- 0.49 0.74 +/- 0.18 0.07 +/- 0.02 12.18 +/- 1.62 24.19 +/- 1.13 0.14 +/- 0.05 0.13 +/- 0.04 0.34 +/- 0.06 0.29 +/- 0.05 0.41 +/- 0.06 0.78 +/- 0.02 0.86 +/- 0.09 1.13 +/- 0.13 0.39 +/- 0.01 7.84 +/- 1.24 3.71 +/- 0.20 2.33 +/- 0.59 0.03 +/- 0.00 0.03 +/- 0.01 4.38 +/- 0.33 3.27 +/- 0.49 20.16 +/- 0.62 6.41 +/- 0.36 0.77 +/- 0.17 0.07 +/- 0.02 11.98 +/- 1.19 25.44 +/- 0.99 0.14 +/- 0.03 0.15 +/- 0.03 0.41 +/- 0.06 0.34 +/- 0.04 0.41 +/- 0.05 0.77 +/- 0.01 0.82 +/- 0.06 1.08 +/- 0.09 0.39 +/- 0.01 8.40 +/- 0.88 3.80 +/- 0.16 2.65 +/- 0.43 0.03 +/- 0.00 0.03 +/- 0.00 4.33 +/- 0.20 3.00 +/- 0.30 20.49 +/- 0.54 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A5-5
TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP).
Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MAW-1140 2/1/2014 Gr. Alpha MAW-1 140 2/1/2014 Gr. Beta MAW-1 142 2/1/2014 1-129 0.77 +/- 0.06 4.31 +/- 0.08
-0.01 +/- 8.00 0.85 4.19 0.00 0.26 - 1.44 2.10 -6.29 NA MAW-i 184 MAW-i 184 MAW-i 184 MAW-1 184 f MAW-1 184 f MAW-i 184 MAW-i 184 MAW-i 184 MAW-i 184 MAW-i 184 MAW-1184 MAW-1184 MAW-i 184 MAW-1184 MAW-1184 MAW-1184 MAVE-1 148 MAVE-1 148 MAVE-1 148 MAVE-1 148 MAVE-1 148 MAVE-1 148 MAAP-1151 MAAP-1151 d MAAP-1 151 MAAP-1151 MAAP-1 151 MAAP-1151 MAAP-1151 f MAAP-1 151 MAAP-1151 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 Fe-55 H-3 Ni-63 Pu-238 Pu-239/240 Sr-90 Tc-99 U-233/234 U-238 Co-57 Co-60 Cs-1 34 Cs-1 37 K-40 Mn-54 Zn-65 Co-57 Co-60 Cs-1 34 Cs-137 Mn-54 Zn-65 Am-241 Co-57 Co-60 Cs-1 34 Cs-137 Mn-54 Pu-238 Pu-239/240 Zn-65 0.40 +/- 3.20 345.10 +/- 10.60 32.40 +/- 3.20 1.28 +/- 0.12 0.91 +/- 0.10 7.00 +/- 0.70 8.10 +/- 0.60 0.20 +/- 0.07 1.25 +/- 0.18 27.86 +/- 0.38 15.99 +/- 0.27 21.85 +/- 0.54 28.74 +/- 0.49 1.80 +/- 2.00 14.06 +/- 0.40 0.00 +/- 0.19 11.63 +/- 0.19 7.28 +/- 0.18 6.29 +/- 0.29 5.18 +/- 0.20 9.22 +/- 0.26 8.59 +/- 0.40 0.09 +/- 0.02 1.60 +/- 0.05 1.38 +/- 0.08 1.75 +/- 0.11 1.81 +/- 0.10 0.01 +/- 0.03 0.08 +/- 0.02 0.10 +/- 0.02
-0.24 +/- 0.09 0.00 321.00 34.00 0.83 0.68 8.51 10.30 0.23 1.45 27.50 16.00 23.10 28.90 0.00 13.90 0.00 10.10 6.93 6.04 4.74 8.62 7.86 0.09 0.00 1.39 1.91 1.76 0.00 0.00 0.08 0.00
-0.01 - 2.00 225.00 - 417.00 23.80 - 44.20 0.58-1.08 0.47 - 0.88 5.96 -11.06 7.20 - 13.40 0.16 -0.29 1.02 -1.89 19.30 - 35.80 11.20 -20.80 16.20 - 30.00 20.20 - 37.60 0.00 - 10.00 9.70 -18.10
-0.01 - 0.00 7.10 -13.10 4.85 - 9.01 4.23 - 7.85 3.32 -6.16 6.03-11.21 5.50 - 10.22 0.06 -0.12 NA 0.97 - 1.81 1.34 -2.48 1.23 -2.29 NA NA 0.05 -0.10
-0.50 - 1.00 Pass Pass Pass Pass Pass Pass Fail Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Fail Pass Pass A6-1
TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP).
Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MAAP-1151 MAAP-1151 MAAP-1151 MAAP-1 154 MAAP-1 154 MASO-1 146 MASO-1 146 MASO-1 146 9 MASO-1 146 MASO-1 146 MASO-1 146 MASO-1 146 MASO-1 146 MASO-1 146 MASO-1 146 MASO-1 146 f MASO-1 146 MASO-1 146 MASO-1 1 4 6 h MASO-1 146h MASO-4439 MASO-4439 MASO-4439 MASO-4439 MASO-4439 MASO-4439 MASO-4439 MASO-4439 MASO-4439 MASO-4439 MAW-4431 MAW-4431 MAW-4431 MAW-4431 MAW-4431 MAW-4431i MAW-4431 MAW-4431 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 8/1/2014 8/1/2014 8/1/2014 8/1/2014 8/1/2014 8/1/2014 8/1/2014 8/1/2014 8/1/2014 8/1/2014 8/1/2014 8/1/2014 8/1/2014 8/1/2014 8/1/2014 8/1/2014 8/1/2014 8/1/2014 U-233/234 U-238 Sr-90 Gr. Alpha Gr. Beta Co-57 Co-60 Cs-134 Cs-137 K-40 Mn-54 Zn-65 Am-241 Ni-63 Pu-238 Pu-239/240 Sr-90 Tc-99 U-233/234 U-238 Am-241 Ni-63 Pu-239/240 Sr-90 Tc-99 Cs-134 Co-57 Co-60 Mn-54 Zn-65 Am-241 Cs-137 Co-57 Co-60 H-3 Fe-55 Mn-54 Zn-65 0.03 +/- 0.01 0.13 +/- 0.02 1.11 +/- 0.14 0.56 +/- 0.06 0.98 +/- 0.06 0.02 0.13 1.18 1.77 0.77 0.01 - 0.03 0.09 -0.17 0.83 - 1.53 0.53 - 3.01 0.39-1.16 1064.50 +/- 3.60 1.70 +/- 0.50 6.10 +/- 1.80 1364.30 +/- 5.30 728.90 +/- 15.90 1588.00 +/- 6.00 763.50 +/- 6.80 68.20 +/- 9.00 4.80 +/- 15.30 140.60 +/- 15.50 102.00 +/- 13.10 1.23 +/- 1.37
-0.30 +/- 12.00 22.90 +/- 3.00 32.00 +/- 3.60 65.90 +/- 6.70 771.62 +/- 23.29 55.63 +/- 5.81 778.34 +/- 17.82 458.20 +/- 9.20 520.60 +/- 7.09 1135.00 +/- 7.40 768.20 +/- 7.70 1050.70 +/- 12.60 407.89 +/- 15.03 0.79 +/- 0.08 18.62 +/- 0.54 24.85 +/- 0.42 12.27 +/- 0.38 207.20 +/- 10.60 55.10 +/- 14.80 14.36 +/- 0.53 11.46 +/- 0.78 966.00 1.22 0.00 1238.00 622.00 1430.00 695.00 68.00 0.00 96.00 76.80 0.00 0.00 81.00 83.00 85.50 980.00 58.60 858.00 589.00 622.00 1116.00 779.00 1009.00 541.00 0.88 18.40 24.70 12.40 208.00 31.50 14.00 10.90 676.00 - 1256.00 NA' NA 867.00 - 1609.00 435.00 - 809.00 1001.00 - 1859.00 487.00 - 904.00 47.60 - 88.40 NA 67.00 - 125.00 53.80 - 99.80 NA NA 57.00 - 105.00 58.00 - 108.00 59.90 - 111.20 686.00 - 1274.00 41.00 - 76.20 601.00 - 1115.00 412.00 - 766.00 435.00 - 809.00 781.00 - 1451.00 545.00 - 1013.00 706.00 - 1312.00 379.00 - 703.00 0.62 -1.14 12.90 - 23.90 17.30 - 32.10 8.70 -16.10 146.00 - 270.00 22.10 - 41.00 9.80 - 18.20 7.60 - 14.20 Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Fail Fail Pass Pass Fail Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass A6-2
TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP).
Concentration "
Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MAW-4431 8/1/2014 Tc-99 6.10 +/- 0.50 6.99 4.89 -9.09 Pass MAW-4431 8/1/2014 Pu-238 0.59 +/- 0.07 0.62 0.43 -0.80 Pass MAW-4431 8/1/2014 U-233/234 0.22 +/- 0.04 0.21 0.14 -0.27 Pass MAW-4431 8/1/2014 U-238 1.25 +/- 0.10 1.42 0.99 -1.85 Pass MAW-4493 8/11/2014 Gr. Alpha 0.93 +/- 0.07 1.40 0.42 -2.38 Pass MAW-4493 8/1/2014 Gr. Beta 6.31 +/- 1.35 6.50 3.25 -9.75 Pass MAAP-4433 8/1/2014 Am-241 0.06 +/- 0.02 0.07 0.05 - 0.09 Pass MAAP-4433 8/1/2014 Pu-238 0.10 +/- 0.03 0.11 0.08 -0.14 Pass MAAP-4433 8/1/2014 Pu-239/240 0.04 +/- 0.02 0.05 0.03 - 0.06 Pass MAAP-4433 8/1/2014 Sr-90 0.74 +/- 0.10 0.70 0.49 -0.91 Pass MAAP-4433 8/1/2014 U-233/234 0.03 +/- 0.01 0.04 0.03 -0.05 Pass MAAP-4433 8/1/2014 U-238 0.21 +/- 0.03 0.25 0.18 -0.33 Pass MAAP-4444 8/1/2014 Sr-89 7.82 +/- 0.52 9.40 6.60 - 12.20 Pass MAAP-4444 8/1/2014 Sr-90 0.76 +/- 0.10 0.76 0.53 -0.99 Pass MAVE-4436 8/1/2014 Cs-134 7.49 +/- 0.18 7.38 5.17 -9.59 Pass MAVE-4436 8/1/2014 Co-57 11.20 +/- 0.19 9.20 6.40-12.00 Pass MAVE-4436 8/1/2014 Co-60 6.84 +/- 0.17 6.11 4.28 -7.94 Pass MAVE-4436 8/1/2014 Mn-54 8.11 +/- 0.26 7.11 4.97 -9.23 Pass MAVE-4436 8/1/2014 Zn-65 7.76 +/- 0.43 6.42 4.49 -8.35 Pass a Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).
b Laboratory codes as follows: MAW (water), MAAP (air filter), MASO (soil), MAVE (vegetation).
0MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and control limits as defined by the MAPEP. A known value of "zero" indicates an analysis was included in the testing series as a "false positive". MAPEP does not provide control limits.
d Interference from Eu-152 resulted in misidentification of Co-57.
' Provided in the series for "sensitivity evaluation". MAPEP does not provide control limits.
f The high bias on the plutonium crosscheck samples was traced to contamination from a newly purchased standard.
The results of reanalysis with replacement tracer purchased from NIST:
MAW-1184 Pu-238 0.68 +/- 0.10 Bq/ L MAW-1184 Pu-239/240 0.66 +/- 0.10 Bq / L MASO-1146 Pu-238 95.15 +/- 8.98 Bq / kg MASO-1 146 Pu-239/240 67.21 +/- 7.54 Bq / kg Insufficient sample remained to reanalyze the Air filter sample(MAAP-1151). High bias results due to same contaminated tracer a False positive test. Long sample counting time lead to interference from naturaling occuring Bi-214 in sample matrix with a close spectral energy.
h80% of participating laboratories were outside the acceptable range.
Parallel reanalysis was run on ERA spiked sample with acceptable results.
Result of reanalysis Fe-55 32.63 +/- 16.30 Bq / L A6-3
TABLE A-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.
Concentration (pCi/L) b Lab Code b Date Analysis Laboratory ERA Control Result C Result d Limits Acceptance
.ERAP-1044 ERAP-1044 ERAP-1044 ERAP-1044 ERAP-1044 ERAP-1044 ERAP-1044 ERAP-1044 ERAP-1044 ERAP-1 044 ERAP-1044 ERAP-1044 ERAP-1044 ERAP-1 044 ERAP-1 044 ERSO-1050 ERSO-1050.
ERSO-1050 ERSO-1050 ERSO-1 050 ERSO-1 050 ERSO-1050 ERSO-1050 ERSO-1050 ERSO-1050 ERSO-1050 ERSO-1050 e ERSO-1050 e ERSO-1050 ERSO-1050 ERSO-1050 ERSO-1050.
ERSO-1050 ERSO-1050 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 Am-241 Co-60 Cs-134 Cs-1 37 Fe-55 Gr. Alpha Gr. Beta Mn-54 Pu-238 Pu-239/240 Sr-90 U-233/234 U-238 Uranium Zn-65 Am-241 Ac-228 Bi-212 Bi-214 Co-60 Cs-1 34 Cs-137 K-40 Mn-54 Pb-212 Pb-214 Pu-238 Pu-239/240 Sr-90 Th-234 U-233/234 U-238 Uranium Zn-65 54.2 +/- 3.0 1177.9 +/- 14.3 1010.5 +/- 15.8 938.3 +/- 45.7 142.3 +/- 87.3 52.3 +/- 0.5 64.4 +/- 2.6
<4.9 63.0 +/- 2.6 52.8 +/- 1.9 81.4 +/- 1.6 30.4 +/- 1.7 30.4 +/- 1.4 62.0 +/- 3.5 852.2 +/- 26.1 426.6 +/- 155.5 1260.0 +/- 107.0 1331.9 +/- 309.7 1804.5 +/- 50.4 6738.8 +/- 167.6 3262.9 +/- 108.8 8538.6 +/- 55.0 11241.3 +/- 296.6
< 21.6 1119.6 +/- 26.1 1861.7 +/- 54.9 1085.5 +/- 167.7 681.6 +/- 128.6 2338.0 +/- 144.0 3474.9 +/- 226.0 3319.5 +/- 250.2 3375.6 +/- 252.6 6810.6 +/- 551.1 5968.0 +/- 226.1 59.7 1120.0 1010.0 828.0 240.0 46.0 53.8 0.0 56.3 48.6 78.9 36.4 36.1 74.3 667.0 399.0 1240.0 1240.0 1960.0 6830.0 3390.0 8490.0 10500.0 0.0 1240.0 2070.0 578.0 471.0 2780.0 3360.0 2780.0 3360.0 6910.0 5400.0 36.8 - 80.8 867.0 - 1400.0 643.0 - 1250.0 622.0 - 1090.0 74.4 - 469.0 15.4 -71.4 34.0 - 78.4 NA 38.6 - 74.0 35.2 - 63.5 38.6 -118.0 22.6 - 54.9 23.3 - 49.9 41.1 -113.0 478.0 -921.0 233.0 - 518.0 795.0 - 1720.0 330.0 - 1820.0 1180.0 -2820:0 4620.0 - 9400.0 2220.0 - 4070.0 6510.0 - 10900.0 7660.0 - 14100.0 NA 812.0 - 1730.0 1210.0 - 3090.0 348.0 - 797.0 308.0 -651.0 1060.0 - 4390.0 1060.0 - 6320.0 1060.0 - 4390.0 2080.0 -4260.0
.3750.0 - 9120.0 4300.0 - 7180.0 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass
- Pass Pass Pass Pass Pass Pass Pass Pass Pass.
Pass Fail Fail Pass Pass Pass Pass Pass Pass A7-1
TABLE A-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.
Concentration (pCi/L) b Lab Code b Date Analysis Laboratory ERA Control Result c Result d Limits Acceptance ERVE-1051 ERVE-1051 ERVE-1051 ERVE-1051 ERVE-1051 ERVE-1051 ERVE-1051 ERVE-1051 ERVE-1051 ERVE-1051 ERVE-1051 ERVE-1051 ERVE-1051 ERVE-1051 ERW-1054 ERW-1054 ERW-1054 ERW-1054 ERW-1054 ERW-1054 ERW-1054 ERW-1054 ERW-1054 ERW-1054 ERW-1054 ERW-1055if ERW-1055 ERW-1055 ERW-1055 ERW-1060 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 Am-241 Cm-244 Co-60 Cs-1 34 Cs-1 37 K-40 Mn-54 Pu-238 Pu-239/240 Sr-90 U-233/234 U-238 Uranium Zn-65 Am-241 Co-60 Cs-134 Cs-1 37 Mn-54 Pu-238 Pu-239/240 U-233/234 U-238 Uranium Zn-65 Fe-55 Gr. Alpha Gr. Beta Sr-90 H-3 1532.0 +/- 149.5 519.8 +/- 94.6 981.2 +/- 41.8 701.4 +/- 58.6 961.9 +/- 46.3 32789.7 +/- 758.2
< 25.9 2724.1 +/- 259.4 4361.4 +/- 323.4 2405.7 +/- 263.2 1612.2 +/- 162.0 1574.3 +/- 159.6 3255.4 +/- 356.7 1124.1 +/- 101.2 104.6 +/- 3.4 1195.2 +/- 18.9 1474.9 +/- 47.5 2591.0 +/- 23.4
<4.3 54.1 +/- 3.6 185.9 +/- 17.6 74.8 +/- 6.3 76.4 +/- 7.8 154.3 +/- 14.6 1818.5 +/- 56.4 636:3 +/- 176.0 120.9 +/- 3.5 141.6 +/- 2.3 873.9 +/- 56.9 5818.0 +/- 230.0 1490.0 516.0 926.0 646.0 880.0 31900.0 0.0 2110.0 3740.0 2580.0 1760.0 1750.0 3580.0 919.0 114.0 1270.0 1660.0 2690.0 0.0 44.1 160.0 82.4 81.8 168.0 1800.0 1200.0 133.0 174.0 890.0 5580.0 911.0 - 1980.0 253.0 - 804.0 639.0- 1290.0 415.0 - 839.0 638.0 - 1220.0 23000.0 - 44800.0 NA 1260.0 - 2890.0 2300.0 - 5150.0 1470.0 - 3420.0 1160.0 - 2260.0 1170.0 - 2220.0 2430.0 - 4460.0 663.0 - 1290.0 76.8 - 153.0 1100.0 - 1490.0 1220.0 - 1910.0 2280.0 - 3220.0 NA 32.6 - 54.9 124.0 -202.0 61.9 - 106.0 62.4 - 100.0 123.0 -217.0 1500.0 - 2270.0 716.0 - 1630.0 47.2 - 206.0 99.6 - 258.0 580.0 -1180.0 3740.0 - 7960.0 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assessment Program (EML).
b Laboratory codes as follows: ERW (water), ERAP (air filter), ERSO (soil), ERVE (vegetation). Results are reported in units of pCi/L, except for air filters (pCi/Filter), vegetation and soil (pCi/kg).
Unless otherwise indicated, the laboratory result is given as the mean +/- standard deviation for three determinations.
d Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA. A known value of "zero" indicates an analysis was included in the testing series as a "false positive". Control limits are not provided.
e The high bias on the plutonium crosscheck samples was traced to contamination from a newly purchased standard.
The results of reanalysis with replacement tracer purchased from NIST:
ERSO-1050 Pu-238 634.7 +/- 98.50 Bq / kg ERSO-1050 Pu-239/240 451.8 +/- 82.80 Bq / kg An error in the efficiency calculation was found. The result of recalculation was 932 pCi/L.
The sample was repeated, result of reanalysis, 1066 pCi/L.
A7-2
APPENDIX B.
DATA REPORTING CONVENTIONS Data Reporting Conventions 1.0. All activities, except gross alpha and gross beta, are decay corrected to collection time or the end of the collection period.
2.0. Single Measurements Each single measurement is reported as follows:
x +/- s where:
x = value of the measurement; s = 2a counting uncertainty (corresponding to the 95% confidence level).
In cases where the activity is less than the lower limit of detection L, it is reported as: < L, where L = the lower limit of detection based on 4.66cr uncertainty for a background sample.
3.0. Duplicate analyses If duplicate analyses are reported, the convention is as follows.
3.1 Individual results: For two analysis results; x1 +/- s1 and x 2 +/- s2 Reported result:
x +/- s; where x = (1/2) (xi + x2) and s = (1/2)
+2s 3.2.
Individual results:
< Li,
< L2 Reported result: < L, where L = lower of Li and L2 3.3.
Individual results:
x +/- s, < L Reported result:
x +/- s if x - L; < L otherwise.
4.0. Computation of Averages and Standard Deviations 4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements over the period averaged; for example, an annual standard deviation would not be the average of quarterly standard deviations.
The average and standard deviation "s" of a set of n numbers x1, x2... xn are defined as follows:
I~ x n-nn-4.2 Values below the highest lower limit of detection are not included in the average.
4.3 If all values in the averaging group are less than the highest LLD, the highest LLD is reported.
4.4 If all but one of the values are less than the highest LLD, the single value x and associated two sigma error is reported.
4.5 In rounding off, the following rules are followed:
4.5.1. If the number following those to be retained is less than 5, the number is dropped, and the retained numbers are kept unchanged. As an example, 11.443 is rounded off to 11.44.
4.5.2.
If the number following those to be retained is equal to or greater than 5, the number is dropped and the last retained number is raised by 1. As an example, 11.445 is rounded off to 11.45.
B-1
APPENDIX C Table C-1.
Maximum permissible concentrations of radioactivity in air and water above natural a
background in unrestricted areas Air (pCi/mi)
Water (pCi/L)
Gross alpha Gross beta b
Iodine-1 31
-3 1 x 10 1
-1 2.8 x 10 Strontium-89 Strontium-90 Cesium-1 37 Barium-140 Iodine-1 31 Potassium-40 Gross alpha Gross beta Tritium 8,000 500 1,000 8,000 1,000 4,000 2
10 6
1 x 10 Taken from Table 2 of Appendix B to Code of Federal Regulations Title 10, Part 20, and appropriate footnotes.
Concentrations may be averaged over a period not greater than one year.
b Value adjusted by a factor of 700 to reduce the dose resulting from the air-grass-cow-milk-child pathway.
C A natural radionuclide.
C-1
APPENDIX D
SUMMARY
OF THE LAND USE CENSUS D-1
Appendix D Summary of the 2014 Land Use Census The Duane Arnold Energy Land Use Census for 2014 was completed during August and September of 2014. All residences, milk animals, cattle and gardens greater than 500 square feet were identified within three miles for each of the 16 meteorological sectors. If none were identified within the three mile range, additional surveys were performed out to a distance of five miles.
There were 154 vegetable gardens identified during the performance of the 2014 Census. This number is more than the number of gardens found in the 2013 survey by 6. The distance to the nearest vegetation receptor did not change.
There was one change in the location of the nearest resident. In 2013, the "Franz Cottage" located at 4318 Power Plant Road was vacant. That house was inhabited in 2014.
There were two changes to the nearest animal receptors:
A cattle herd 3870 meters to the SE was discontinued in 2014.
A farm 2910 meters to the ENE raising goats in 2013 switched to Cattle in 2014.
Since the last performance of the land use census, no new drinking water wells have been identified within a two mile radius of the site.
The Cedar River was surveyed by boat on September 18th of 2014 for water use downstream of the DAEC to Cedar Rapids. This survey identified no new usages of river water from previous surveys. Recreational fishing is the only identified food pathway use of Cedar River water between the DAEC and the City of Cedar Rapids eight miles down-river.
D-2
In accordance with the DAEC's Environmental Sampling Procedure ESP 4.4, "Land Use Census", no changes in land use were identified that would adversely affect the safe operation of the DAEC, or that would warrant an update of the DAEC Updated Final Safety Analysis Report (UFSAR). Examples of land use that would warrant an UFSAR update include new hazards near the DAEC such as new gas pipelines or new installations utilizing toxic gases.
NextEra Energy Resources, Duane Arnold has committed to compliance with NEI 07-07, "Nuclear Energy Institute's Industry Ground Water Protection Initiative".
Per NEI 07-07, the following information is presented:
N No radioactive reactor by-product material was identified in samples collected by the DAEC's Radiological Environmental Monitoring Program (REMP) or the site Ground Water Protection Program (GWPP) above the threshold concentration levels for reporting.
0 Ground Water Protection Program results are detailed in the-site's Annual Radioactive Material Release Report.
D-3
APPENDIX E ANNUAL RADIATION DOSE ASSESSMENT E-1
Appendix E Annual Radiation Dose Assessment The annual offsite radiation dose to a member of the public was determined by assessment of environmental dosimetry results and by calculations based on monitored effluent releases.
Section A.
Dose Contribution from Direct Radiation Direct radiation dose from the operation of the DAEC was reported by TLDs placed at locations in the surrounding environment as described in the Offsite Dose Assessment Manual (ODAM).
- 1. Pre-operational and 2014 TLD results were evaluated with a paired difference statistical test.
The evaluation concluded that there were no significant differences in the TLD populations for the 0.5 mile and 1 mile TLD populations.
- 2. As stated in Part 1 of this report, no plant effect was indicated by the TLDs when dose results were compared to the estimated average natural background for Middle America.
Section B.
Estimated Offsite Dose from Effluent Releases
-1. The contribution of dose to a member of the public most likely to be exposed from liquid and gaseous effluent releases was calculated using the Meteorological Information and Dose Assessment System (MIDAS) computer program in accordance with the ODAM. The calculation methods follow those prescribed by Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I".
- 2. Following calculation of offsite doses, the appropriateness of REMP sampling station types and locations was reviewed. The current sampling scheme was determined to be adequate for the identified receptors.
Results of the MIDAS dose calculations are displayed below.
1.) There were no releases of radioactive material to liquid effluents in 2014.
2.) The maximum dose to air at the site boundary from noble gases released was 0.0000940 mrad from gamma radiation at 588 meters towards the South-East.
3.) The maximum dose to air at the site boundary from noble gases released was 0.0000285 mrad beta radiation at 2416 meters towards the South-East.
4.) The whole body dose equivalent to the hypothetical maximally exposed individual from noble gases was 0.000150 mrem, at 1620 meters towards the North-North-West.
5.) The skin dose equivalent to the hypothetical maximally exposed individual from noble gases was 0.000150 mrem, at 1620 meters towards the North-North-West.
E-2
6.) The hypothetical maximally exposed organ due to airborne iodines and particulates with half-lives greater than eight days (excluding carbon-14) was the lungs of a child at 2450 meters towards the East-South-East, with an estimated dose equivalent of 0.00658 mrem.
7.) The hypothetical maximally exposed organ due to airborne carbon-14 was the bone of a child located 2500 meters to the East-North-East of the site. The dose was 0.071 mrem.
Conclusion No measurable dose due to the operation of the DAEC or the DAEC ISFSI was detected by environmental TLDs in 2013. The calculated doses are below the regulatory limits stated in Appendix I to 10CFR50, 40CFR190 and 10 CFR 72.104.
Estimated Maximum Offsite Individual Doses for 2014 Type Age Distance Direction Dose or Dose Equivalent Annual 10 CFR 50, Grou (meters)
(mrem)
Appendix I "Limit" Direct Radiation None (as measured by TLDs)
Liquid Releases Whole Body Dose Child S
0.000000 mrem 3 mrem Organ Dose Child -
S 0.000000 mrem 10 mrem Liver Noble Gas Gamma Air Dose 588 SE 0.0000940 mrad 10 mrad Beta Air Dose 2416 SE 0.0000285mrad 20 mrad Whole Body All 1620 NNW 0.000150 mrem 5 mrem Skin Child 1620 NNW 0.000150 mrem 15 mrem Particulates & lodines Organ Dose Child -
2450 ESE 0.00658 mrem 15 mrem Lungs Carbon 14 Organ Dose Child -
2500 ENE 0.071 mrem 15 mrem Bone There is no Appendix I limit for direct radiation. It is listed here to demonstrate compliance with 40 CFR 190 limits of 25 mrem whole body and 75 mrem thyroid.
E-3
4 ATI Environmental, Inc.
- 7ýi I Midwest Laboratory 700 Landwehr Pod
- Nodhb-ook. IL 60062-23 10 phone (847) 564.0700
- fa, (847) 564-4517 DUANE ARNOLD ENERGY CENTER CEDAR RAPIDS, IOWA Docket No. 50-331 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)
ANNUAL REPORT - PART II DATA TABULATIONS AND ANALYSES January 1 to December 31, 2014 Prepared by ATI ENVIRONMENTAL, Inc.
Midwest Laboratory Project No. 8001 Reviewed and Approved
TABLE OF CONTENTS Section Page List of Tables...............................................................................................................
iii 1.0 INTRODUCTIO N.........................................................................................................
iv 2.0 PROG RAM DEVIATIO NS........................................................................................
v 3.0 DATA TABLES.............................................................................................................
vi ii
- LIST OF TABLES No.
Title Page 1
2 3
4 5
6 7
8 9
10 11 12 13 14 15 16 17 18 19 Airborne particulates and iodine, Airborne particulates and iodine, Airborne particulates and iodine, Airborne particulates and iodine, Airborne particulates and iodine, Airborne particulates and iodine, Airborne particulates and iodine, Airborne particulates and iodine, Airborne particulates and iodine, Location D-3, analyses for gross betaand iodine-1 31.......... 1-1 Location D-5, analyses for gross beta and iodine-1 31.......... 2-1 Location D-6, analyses for gross beta and iodine-1 31.......... 3-1 Location D-7, analyses for gross beta and iodine-1 31.......... 4-1 Location D-11, analyses for gross beta and iodine-131......... 5-1 Location D-13, analyses for gross beta and iodine-1 31......... 6-1 Location D-1 5, analyses for gross beta and iodine-1 31......... 7-1 Location D-1 6, analyses for gross beta and iodine-1 31......... 8-1 Location D-40, analyses for gross beta and iodine-1 31......... 9-1 Airborne particulate composite samples, analysis for gamma-emitting isotopes.................... 10-1 Ambient gamma radiation by thermoluminescent dosimeters (TLD), quarterly exposure......... 11-1 Milk samples, analysis for iodine-1 31 and gamma emitting isotopes.................................. 12-1 Ground water, Area wells, analysis for gross beta, gamma emitting isotopes a nd tritium...............................................................................
13-1 Vegetation samples (broadleaf), analysis for iodine-131 and gamma-emitting isotopes........... 14-1 Vegetation samples (hay and grain), analysis for gamma-emitting isotopes.......................... 15-1 Surface water samples, analysis for tritium and gamma-emitting isotopes............................
16-1 Surface water composites, analysis for strontium-89 and strontium-90................................
17-1 Fish samples, analysis for gamma-em itting isotopes...................................................... 18-1 River sediment samples, analysis for gamma-emitting isotopes.........................................
19-1 iii
1.0 INTRODUCTION
The following constitutes a supplement to the Annual Report for the Radiological Environmental Monitoring Program conducted at the Duane Arnold Energy Center, Palo, Iowa in 2013. Results of completed analyses are presented in the attached tables.
For information regarding sampling locations, type and frequency of collection, and sample codes, please refer to Part I, Tables 5.3 - 5.5 and Figures 5.1 and 5.2.
All concentrations, except gross beta and airborne iodine, are decay corrected to the time of collection. Airborne 1-131 is decayed to the midpoint of the collection period.
The required values for lower limits of detection (LLD) for gamma emitting isotopes are established through the Offsite Dose Assessment Manual (ODAM). Naturally occurring radioisotopes, such as Be-7, K-40 and Ra daughters, are frequently detected, but may not be listed for every sample medium.
iv
2.0 PROGRAM DEVIATIONS Sample Collection Date Type Analysis Location(s) or Period Comments SW H-3/ 1-131/ Gamma SW H-3/ Gamma SW H-3 /1-131/Gamma SW H-3/ Gamma SW H-3/ Gamma AP/AI Gross Beta/ 1-131 AP/AI Gross Beta/ 1-131 AP/AI Gross Beta/ 1-131 AP/AI Gross Beta/ 1-131 AP/AI Gross Beta/ 1-131 AP/AI Gross Beta/ 1-131 AP/AI Gross Beta/ 1-131 TLD Ambient Gamma G
Gamma G
Gamma G
Gamma D-49 D-99 D-49 D-99 D-99 D-13 D-13 D-1 5 D-15 D-15 D-13 D-13 D-17 D-58 D-72 D-138 01-22-14 01-22-14 02-04-14 02-04-14 12-20-14 02-07-14 02-13-14 04-16-14 05-16-14 07-11-14 07-17-14 07-24-14 4 th Qtr 2014 Water frozen.
Water frozen.
Water frozen.
Water frozen.
Water frozen.
Low volume due to power outage.
Low volume due to power outage.
Low volume due to power outage.
Low volume due to power outage.
Low volume due to power outage.
Power off to sampler.
Power off to sampler.
TLD missing in the field, TLD replaced.
Vegetation not readily available.
Vegetation not readily available.
Vegetation not readily available.
2014 2014 2014 In no instance did missed analyses affect minimum sampling requirements as specified in the ODAM.
v
3.0 DATA TABLES vi
Table 1. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-1 31 a.
Location: D-3 (Hiawatha)
Units: pCi/m 3
Collection: Continuous, weekly exchange.
Date Collected Required LLD Volume (m')
Gross Beta 0.010 Date Collected Required LLD Volume (m*)
Gross Beta 0.010 01-08-14 01-17-14 01-24-14 02-01-14 02-07-14 02-13-14 02-19-14 02-27-14 03-07-14 03-14-14 03-22-14 03-28-14 04-03-14 204 376 290 331 251 248 250 329 334 290 331 238 237 0.042 +/- 0.005 0.033 +/- 0.003 0.023 +/- 0.003 0.022 +/- 0.003 0.029 +/- 0.004 0.041 +/- 0.005 0.042 +/- 0.005 0.039 +/- 0.004 0.033 +/- 0.004 0.031 +/- 0.004 0.017 +/- 0.003 0.029 +/- 0.004 0.032 +/- 0.004 07-11-14 07-17-14 07-24-14 08-01-14 08-09-14 08-14-14 08-22-14 08-27-14 09-06-14 09-11-14 09-19-14 09-27-14 10-02-14 311 240 277 317 316 200 313 199 390 177 236 297 196 0.025 +/- 0.003 0.020 +/- 0.004 0.032 +/- 0.004 0.026 +/- 0.004 0.040 +/- 0.004 0.027 +/- 0.005 0.041 +/- 0.004 0.022 +/- 0.005 0.024 +/- 0.003 0.025 +/- 0.005 0.035 +/- 0.005 0.036 +/- 0.004 0.042 +/- 0.005 1st Quarter Mean +/- s.d.
0.032 +/- 0.008 3rd Quarter Mean +/- s.d.
0.030 +/- 0.008 04-11-14 04-16-14 04-23-14 05-01-14 05-09-14 05-16-14 05-22-14 05-30-14 06-04-14 06-13-14 06-19-14 06-26-14 07-03-14 320 193 277 315 316 278 239 316 198 353 244 277 270 0.021 +/- 0.003 0.022 +/- 0.005 0.027 +/- 0.004 0.014 +/- 0.003 0.015 +/- 0.003 0.017 +/- 0.003 0.027 +/- 0.004 0.020 +/- 0.003 0.020 +/- 0.005 0.023 +/- 0.003 0.020 +/- 0.004 0.018 +/- 0.003 0.016 +/- 0.003 10-09-14 10-17-14 10-23-14 10-30-14 11-07-14 11-13-14 11-21-14 11-28-14 12-04-14 12-12-14 12-17-14 12-26-14 01-02-15 268 308 225 258 236 236 307 268 232 306 191 360 274 0.022 +/- 0.004 0.018 +/- 0.003 0.022 +/- 0.004 0.031 +/- 0.004 0.025 +/- 0.004 0.017 +/- 0.004 0.028 +/- 0.003 0.031 +/- 0.004 0.041 +/- 0.005 0.060 +/- 0.005 0.051 +/- 0.006 0.029 +/- 0.003 0.033 +/- 0.004 2nd Quarter Mean +/- s.d.
0.020 +/- 0.004 4th Quarter Mean +/- s.d.
Cumulative Average 0.031 +/- 0.013 0.028 a Iodine-131 concentrations are < 0.03 pCi/m3 unless noted otherwise.
1-1
Table 2. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-1 31 a Location: D-5 (Palo)
Units: pCi/m 3
Collection: Continuous, weekly exchange.
Date Volume Date Volume Collected (m")
Gross Beta Collected (m")
Gross Beta Required LLD 0.010 Required LLD 0.010 01-08-14 01-17-14 01-24-14 02-01-14 02-07-14 02-13-14 02-19-14 02-27-14 03-07-14 03-14-14 03-22-14 03-28-14 04-03-14 203 369 285 325 246 244 245 328 323 285 324 243 250 0.042 +/- 0.005 0.027 +/- 0.003 0.023 +/- 0.003 0.024 +/- 0.003 0.031 +/- 0.004 0.039 +/- 0.005 0.035 +/- 0.005 0.033 +/- 0.004 0.036 +/- 0.004 0.033 +/- 0.004 0.021 +/- 0.003 0.029 +/- 0.004 0.020 +/- 0.004 07-11-14 07-17-14 07-24-14 08-01-14 08-09-14 08-14-14 08-22-14 08-27-14 09-06-14 09-11-14 09-19-14 09-27-14 10-02-14 328 251 290 336 333 209 329 210 412 208 333 322 202 0.024 +/- 0.003 0.024 +/- 0.004 0.032 +/- 0.004 0.026 +/- 0.003 0.045 +/- 0.004 0.009 +/- 0.004 0.037 +/- 0.004 0.023 +/- 0.005 0.020 +/- 0.003 0.022 +/- 0.004 0.020 +/- 0.003 0.032 +/- 0.004 0.046 +/- 0.006 0.028 +/- 0.010 1st Quarter Mean +/- s.d.
0.030 +/- 0.007 3rd Quarter Mean +/- s.d.
04-11-14 04-16-14 04-23-14 05-01-14 05-09-14 05-16-14 05-22-14 05-30-14 06-04-14 06-13-14 06-19-14 06-26-14 07-03-14 318 201 283 322 323 283 242 325 200 360 248 291 252 0.022 0.021 0.025 0.011 0.016 0.014 0.025 0.022
+/- 0.003
+/- 0.005
+/- 0.004
+/- 0.003
+/- 0.003
+/- 0.003
+/- 0.004
+/- 0.003 10-09-14 10-17-14 10-23-14 10-30-14 11-07-14 11-13-14 11-21-14 11-28-14 12-04-14 12-12-14 12-17-14 12-26-14 01-02-15 277 335 253 299 343 267 351 315 238 360 234 366 282 0.018 +/- 0.003 0.022 +/- 0.003 0.020 +/- 0.004 0.029 +/- 0.004 0.020 +/- 0.003 0.017 +/- 0.003 0.022 +/- 0.003 0.024 +/- 0.003 0.043 +/- 0.005 0.042 +/- 0.004 0.043 +/- 0.005 0.031 +/- 0.003 0.037 +/- 0.004 0.018 +/- 0.005 0.018 +/- 0.003 0.020 +/- 0.004 0.021 +/- 0.004 0.017 +/- 0.004 2nd Quarter Mean +/- s.d.
0.019 +/- 0.004 4th Quarter Mean +/- s.d.
Cumulative Average 0.028 +/- 0.010 0.026 a Iodine-131 concentrations are < 0.03 pCi/mi3 unless noted otherwise.
2-1
Table 3. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131a.
Location: D-6 (Center Point)
Units: pCi/m 3
Collection: Continuous, weekly exchange.
Date Volume Date Volume Collected (mi)
Gross Beta Collected (mi)
Gross Beta Required LLD 0.010 Required LLD 0.010 01-08-14 01-17-14 01-24-14 02-01-14 02-07-14 02-13-14 02-19-14 02-27-14 03-07-14 03-14-14 03-22-14 03-28-14 04-03-14 197 357 276 319 241 238 240 317 321 280 318 240 246 0.046 +/- 0.006 0.034 +/- 0.003 0.032 +/- 0.004 0.019 +/- 0.003 0.033 +/- 0.005 0.033 +/- 0.004 0.040 +/- 0.005 0.043 +/- 0.004 0.035 +/- 0.004 0.029 +/- 0.004 0.019 +/- 0.003 0.019 +/- 0.004 0.033 +/- 0.004 07-11-14 07-17-14 07-24-14 08-01-14 08-09-14 08-14-14 08-22-14 08-27-14 09-06-14 09-11-14 09-19-14 09-27-14 10-02-14 317 238 278 323 321 200 316 201 397 201 323 323 197 0.022 +/- 0,003 0.023 +/- 0,004 0.033 +/- 0,004 0.026 +/- 0,004 0.041 +/- 0,004 0.033 +/- 0,005 0.040 +/- 0,004 0.022 +/- 0.005 0.025 +/- 0.003 0.024 +/- 0.005 0.027 +/- 0.003 0.028 +/- 0.003 0.041 +/- 0.005 1st Quarter Mean +/- s.d.
0.032 +/- 0.009 3rd Quarter Mean +/- s.d.
0.029 +/- 0.007 04-11-14 04-16-14 04-23-14 05-01-14 05-09-14 05-16-14 05-22-14 05-30-14 06-04-14 06-13-14 06-19-14 06-26-14 07-03-14 317 199 280 325 326 286 245 328 203 356 246 280 280 0.022 +/- 0.003 0.021 +/- 0.005 0.027 +/- 0.004 0.011 +/- 0.003 0.017 +/- 0.003 0.016 +/- 0.003 0.026 +/- 0.004 0.023 +/- 0.003 10-09-14 10-17-14 10-23-14 10-30-14 11-07-14 11-13-14 11-21-14 11-28-14 12-04-14 12-12-14 12-17-14 12-26-14 01-02-15 279 320 240 278 318 244 318 284 248 328 209 390 300 0.015 +/- 0.003 0.017 +/- 0.003 0.019 +/- 0.004 0.028 +/- 0.004 0.018 +/- 0.003 0.020 +/- 0.004 0.030 +/- 0.003 0.035 +/- 0.004 0.039 +/- 0.005 0.044 +/- 0.004 0.042 +/- 0.005 0.027 +/- 0.003 0.032 +/- 0.004 0.021 0.021 0.022 0.020 0.010
+/- 0.005
+/- 0.003
+/- 0.004
+/- 0.004
+/- 0.003 2nd Quarter Mean +/- s.d.
0.020 +/- 0.005 4th Quarter Mean +/- s.d.
Cumulative Average 0.028 +/- 0.010 0.027 a lodine-131 concentrations are < 0.03 pCi/m 3 unless noted otherwise.
3-1
Table 4. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-1 31 a.
Location: D-7 (Shellsburg)
Units: pCi/mr 3
Collection: Continuous, weekly exchange.
Date Volume Date Volume Collected (me)
Gross Beta Collected (me)
Gross Beta Required LLD 01-08-14 01-17-14 01-24-14 02-01-14 02-07-14 02-13-14 02-19-14 02-27-14 03-07-14 03-14-14 03-22-14 03-28-14 04-03-14 203 369 284 325 246 244 245 328 333 294 334 253 259 0.010 0.043 +/- 0.005 0.034 +/- 0.003 0.024 +/- 0.004 0.024 +/- 0.003 0.034 +/- 0.005 0.036 +/- 0.004 0.035 +/- 0.005 0.017 +/- 0.003 0.033 +/- 0.004 0.027 +/- 0.004 0.017 +/- 0.003 0.028 +/- 0.004 0.033 +/- 0.004 Required LLD 0.010 07-11-14 07-17-14 07-24-14 08-01-14 08-09-14 08-14-14 08-22-14 08-27-14 09-06-14 09-11-14 09-19-14 09-27-14 10-02-14 343 257 299 345 340 197 307 195 383 196 315 313 191 0.021 0.020 0.025 0.023 0.034 0.030 0.017 0.018
+/- 0.003
+/- 0.004
+/- 0.004
+/- 0.003
+/- 0.004
+/- 0.005
+/- 0.003
+/- 0.005 0.010 +/- 0.002 0.022 +/- 0.005 0.022 +/- 0.003 0.025 +/- 0.003 0.037+/-. 0.005 1st Quarter Mean +/- s.d.
0.030 +/- 0.008 3rd Quarter Mean +/- s.d.
0.024 +/- 0.007 04-11-14 04-16-14 04-23-14 05-01-14 05-09-14 05-16-14 05-22-14 05-30-14 06-04-14 06-13-14 06-19-14 06-26-14 07-03-14 327 209 294 335 342 300 257 344 214 385 264 255 285 0.020 +/- 0.003 0.022 +/- 0.005 0.024 +/- 0.004 0.012 +/- 0.003 0.018 +/- 0.003 0.014 +/- 0.003 0.024 +/- 0.004 0.021 +/- 0.003 0.020 +/- 0.004 0.010 +/- 0.002 0.019 +/- 0.004 0.023 +/- 0.004 0.015 +/- 0.003 0.019 +/- 0.005 10-09-14 10-17-14 10-23-14 10-30-14 11-07-14 11-13-14 11-21-14 11-28-14 12-04-14 12-12-14 12-17-14 12-26-14 01-02-15 268 310 232 271 308 246 327 298 258 344 224 406 311 0.017 +/- 0.003 0.015 +/- 0.003 0.019 +/- 0.004 0.022 +/- 0.004 0.013 +/- 0.003 0.013 +/- 0.003 0.026 +/- 0.003 0.027 +/- 0.003 0.036 +/- 0.004 0.048 +/- 0.004 0.032 +/- 0.005 0.011 +/- 0.002 0.029 +/- 0.003 2nd Quarter Mean +/- s.d.
4th Quarter Mean +/- s.d.
Cumulative Average 0.024 +/- 0.011 0.024 a lodine-131 concentrations are < 0.03 pCi/mi3 unless noted otherwise.
4-1
Table 5. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131a.
Location: D-11 (Toddville)
Units: pCi/m 3
Collection:
Continuous, weekly exchange.
Date Volume Date Volume Collected (me)
Gross Beta Collected (ma)
Gross Beta Required LLD 01-08-14 01-17-14 01-24-14 02-01-14 02-07-14 02-13-14 02-19-14 02-27-14 03-07-14 03-14-14 03-22-14 03-28-14 04-03-14 197 358 276 315 239 236 238 338 344 300 340 257 261 0.010 0.044 +/- 0.006 0.038 +/- 0.004 0.025 +/- 0.004 0.023 +/- 0.003 0.033 +/- 0.005 0.035 +/- 0.005 0.021 +/- 0.004 0.038 +/- 0.004 0.030 +/- 0.003 0.029 +/- 0.004 0.017 +/- 0.003 0.027 +/- 0.004 0.028 +/- 0.004 Required LLD 0.010 07-11-14 07-17-14 07-24-14 08-01-14 08-09-14 08-14-14 08-22-14 08-27-14 09-06-14 09-11-14 09-19-14 09-27-14 10-02-14 320 243 280 326 322 202 316 200 394 204 315 323 197 0.019 +/- 0.003 0.019 +/- 0.004 0.028 +/- 0.004 0.022 +/- 0.003 0.036 +/- 0.004 0.025 +/- 0.005 0.037 +/- 0.004 0.021 +/- 0.005 0.019 +/- 0.003 0.023 +/- 0.005 0.030 +/- 0.004 0.032 +/- 0.004 0.036 +/- 0.005 1st Quarter Mean +/- s.d.
0.030 +/- 0.008 3rd Quarter Mean +/- s.d.
0.027 +/- 0.007 04-11-14 04-16-14 04-23-14 05-01-14 05-09-14 05-16-14 05-22-14 05-30-14 06-04-14 06-13-14 06-19-14 06-26-14 07-03-14 342 208 300 341 342 283 242 325 202 361 248 283 244 0.020 +/- 0.003 0.012 +/- 0.004 0.020 +/- 0.003 0.013 +/- 0.003 0.016 +/- 0.003 0.015 +/- 0.003 0.014 +/- 0.004 0.017 +/- 0.003 0.019 +/- 0.005 0.019 +/- 0.003 0.022 +/- 0.004 0.017 +/- 0.003 0.014 +/- 0.004 10-09-14 10-17-14 10-23-14 10-30-14 11-07-14 11-13-14 11-21-14 11-28-14 12-04-14 12-12-14 12-17-14 12-26-14 01-02-15 281 320 240 278 318 244 322 292 252 332 211 391 302 0.020 0.013 0.016 0.027 0.021 0.016 0.027 0.027
+/- 0.003
+/- 0.003
+/- 0.003
+/- 0.004
+/- 0.003
+/- 0.004
+/- 0.003
+/- 0.004 0.038 +/- 0.004 0.037 +/- 0.004 0.043 +/- 0.005 0.027 +/- 0.003 0.036 +/- 0.004 2nd Quarter Mean +/- s.d.
0.017 +/- 0.003 4th Quarter Mean +/- s.d.
Cumulative Average 0.027 +/- 0.010 0.025 a Iodine-131 concentrations are < 0.03 pCi/m 3 unless noted otherwise.
5-1
Table 6. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-1 31 a.
Location: D-13 (Alburnett)
Units: pCi/m 3
Collection: Continuous, weekly exchange.
Date Volume Date Volume Collected (m")
Gross Beta Collected (mi)
Gross Beta Required LLD 01-08-14 01-17-14 01-24-14 02-01-14 02-07-14 02-13-14 02-19-14 02-27-14 03-07-14 03-14-14 03-22-14 03-28-14 04-03-14 216 376 290 315 165 214 242 317 312 283 326 247 251 0.010 0.046 +/- 0.005 0.035 +/- 0.003 0.025 +/- 0.004 0.017 +/- 0.003 0.042 +/- 0.006 0.037 +/- 0.005 0.033 +/- 0.005 0.034 +/- 0.004 0.030 +/- 0.004 0.030 +/- 0.004 0.017 +/- 0.003 0.028 +/- 0.004 0.030 +/- 0.004 b
b Required LLD 0.010 07-11-14 07-17-14 07-24-14 08-01-14 08-09-14 08-14-14 08-22-14 08-27-14 09-06-14 09-11-14 09-19-14 09-27-14 10-02-14
- 79.
0.011 +/- 0.009 NDd NDd 312 0.023 +/- 0.003 317 191 306 184 329 124 247.
316 197 0.036 +/- 0.004 0.025 +/- 0.005 0.033 +/- 0.004 0.024 +/- 0.005 0.027 +/- 0.003 0.035 +/- 0.007 0.032 +/- 0.004 0.028 +/- 0.003 0.034 +/- 0.005 1st Quarter Mean +/- s.d.
0.031 +/- 0.008 3rd Quarter Mean +/- s.d.
0.028 +/- 0.007 04-11-14 04-16-14 04-23-14 05-01-14 05-09-14 05-16-14 05-22-14 05-30-14 06-04-14 06-13-14 06-19-14 06-26-14 07:03-14 328 205 289 328 329 278 237 318 198 352 244 274 277 0.022 +/- 0.003 0.017 +/- 0.004 0.019 +/- 0.003 0.011 +/- 0.003 0.015 +/- 0.003 0.013 +/- 0.003 0.019 +/- 0.004 0.019 +/- 0.003 0.019 +/- 0.005 0.017 +/- 0.003 0.019 +/- 0.004 0.022 +/- 0.004 0.016 +/- 0.003 10-09-14 10-17-14 10-23-14 10-30-14 11-07-14 11-13-14 11-21-14 11-28-14 12-04-14 12-12-14 12-17-14 12-26-14 01-02-15 280 319 240 278 318 249 203 285 339 257 304 350 273 0.016 +/- 0.003 0.015 +/- 0.003 0.020 +/- 0.004 0.023 +/- 0.004 0.018 +/- 0.003 0.012 +/- 0.003 0.042 +/- 0.005 0.021 +/- 0.003 0.024 +/- 0.003 0.064 +/- 0.005 0.015 +/- 0.003 0.025 +/- 0.003 0.037 +/- 0.004 2nd Quarter Mean +/- s.d.
0.017 +/- 0.003 4th Quarter Mean +/- s.d.
Cumulative Average 0.026 +/- 0.014 0.025 a Iodine-131 concentrations are < 0.03 pCi/m 3 unless noted otherwise.
b Low volume due to possible power outage.
c Low volume due to power outage from storms; Iodine-1 31 concentration < 0.034 pCi/mr due to low volume.
d "ND" = No data; see Table 2.0, Listing of Missed Samples.
6-1
Table 7. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131a Location: D-15 (On-site, north)
Units: pCi/m 3
Collection:
Continuous, weekly exchange.
Date Collected Required LLD Volume (ms)
Gross Beta 0.010 Date Collected Required LLD Volume (m6)
Gross Beta 0.010 01-08-14 01-17-14 01-24-14 02-01-14 02-07-14 02-13-14 02-19-14 02-27-14 03-07-14 03-14-14 03-22-14 03-28-14 04-03-14 198 344 272 308 234 238 226 340 334 291 333 257 259 0.047 +/- 0.006 0.037 +/- 0.004 0.029 +/- 0.004 0.022 +/- 0.003 0.032 +/- 0.005 0.034 +/- 0.004 0.043 +/- 0.005 0.036 +/- 0.004 0.029 +/- 0.003 0.032 +/- 0.004 0.021 +/- 0.003 0.028 +/- 0.004 0.027 +/- 0.004 07-11-14 07-17-14 07-24-14 08-01-14 08-09-14 08-14-14 08-22-14 08-27-14 09-06-14 09-11-14 09-19-14 09-27-14 10-02-14 310 241 275 319 314 199 311 198 392 193 314 315 202 0.017 +/- 0.003 0.002 +/- 0.003 0.025 +/- 0.004 0.024 +/- 0.003 0.040 0.029 0.025 0.029 0.020 0.020 0.028 0.030 0.034
+/- 0.004
+/- 0.005
+/- 0.004
+/- 0.005
+/- 0.003
+/- 0.005
+/- 0.004
+/- 0.003
+/- 0.005 1st Quarter Mean +/- s.d.
0.032 +/- 0.008 3rd Quarter Mean +/- s.d.
0.025 +/- 0.009 04-11-14 04-16-14 04-23-14 05-01-14 05-09-14 05-16-14 05-22-14 05-30-14 06-04-14 06-13-14 06-19-14 06-26-14 07-03-14 325 140 293 344 333 103 232 319 195 263 244 277 138 0.023 0.024 0.027 0.011
+/- 0.003
+/- 0.006
+/- 0.004
+/- 0.002 b
0.015 +/- 0.003 0.025 +/- 0.008 0.021 +/- 0.004 0.019 +/- 0.003 0.020 +/- 0.005 0.018 +/- 0.004 0.006 +/- 0.003 0.015 +/- 0.003 0.019 +/- 0.006 C
d e
10-09-14 10-17-14 10-23-14 10-30-14 11-07-14 11-13-14 11-21-14 11-28-14 12-04-14 12-12-14 12-17-14 12-26-14 01-02-15 265 314 235 282 314 240 322 279 253 319 198 360 280 0.018 +/- 0.003 0.016 +/- 0.004 0.021 +/- 0.003 0.036 +/- 0.004 0.043 +/- 0.005 0.058 +/- 0.004 0.045 +/- 0.006 0.035 +/- 0.003 0.037 +/- 0.004 0.015 0.016 0.018 0.022
+/- 0.003
+/- 0.003
+/- 0.004
+/- 0.003 2nd Quarter Mean +/- s.d.
0.019 +/- 0.006 4th Quarter Mean +/- s.d.
Cumulative Average 0.029 +/- 0.014 0.026 a Iodine-131 concentrations are < 0.03 pCi/mi3 unless noted otherwise.
b Low volume due to power outage.
c Low volume due to power outage; Iodine-131 concentration <0.037pCi/m 3 due to low volume.
d Filter light.
e Low volume due to ground fault trip; Iodine-1 31 concentration <0.031 pCi/m3 due to low volume..
f Filter light.
7-1
Table 8. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-1 31 a Location: D-16 (On-site)
Units: pCi/m 3
Collection: Continuous, weekly exchange.
Date Volume Date Volume Collected (mi)
Gross Beta Collected (mi)
Gross Beta Required LLD 01-08-14 01-17-14 01-24-14 02-01-14 02-07-14 02-13-14 02-19-14 02-27-14 03-07-14 03-14-14 03-22-14 03-28-14 04-03-14 202 348 273 332 251 256 249 332 330 287 330 255 255 0.010 0.048 +/- 0.006 0.039 +/- 0.004 0.031 +/- 0.004 0.017 +/- 0.003 0.032 +/- 0.004 0.038 +/- 0.004 0.037 +/- 0.005 0.039 +/- 0.004 0.035 +/- 0.004 0.027 +/- 0.004 0.021 +/- 0.003 0.030 +/- 0.004 0.029 +/- 0.004 Required LLD 07-11-14 07-17-14 07-24-14 08-01-14 08-09-14 08-14-14 08-22-14 08-27-14 09-06-14 09-11-14 09-19-14 09-27-14 10-02-14 320 248 285 311 309 197 306 196 388 191 312 312 201 0.010 0.025 +/- 0.003 0.019 +/- 0.004 0.033 +/- 0.004 0.026 +/- 0.004 0.043 +/- 0.004 0.030 +/- 0.005 0.038 +/- 0.004 0.023 +/- 0.005 0.010 +/- 0.002 0.026 +/- 0.005 0.025 +/- 0.003 0.036 +/- 0.004 0.042 +/- 0.005 1st Quarter Mean +/- s.d.
0.033 +/- 0.008 3rd Quarter Mean +/- s.d.
0.029 +/- 0.009 04-11-14 04-16-14 04-23-14 05-01-14 05-09-14 05-16-14 05-22-14 05-30-14 06-04-14 06-13-14 06-19-14 06-26-14 07-03-14 325 208 291 334 323 285 240 328 202 367 249 285 285 0.022 +/- 0.003 0.008 +/- 0.004 0.024 +/- 0.004 0.007 +/- 0.002 0.019 +/- 0.003 0.015 +/- 0.003 0.024 +/- 0.004 0.021 +/- 0.003 0.021 +/- 0.005 0.020 +/- 0.003 0.018 +/- 0.004 0.020 +/- 0.004 0.013 +/- 0.003 0.018 +/- 0.006 10-09-14 10-17-14 10-23-14 10-30-14 11-07-14 11-13-14 1.1-21-14 11-28-14 12-04-14 12-12-14 12-17-14 12-26-14 01-02-15 262 310 232 290 318 239 320 275 250 315 198 356 277 0.017 +/- 0.003 0.017 +/- 0.003 0.018 +/- 0.004 0.029 +/- 0.004 0.020 +/- 0.003 0.016 +/- 0.004 0.033 +/- 0.004 0.024 +/- 0.004 0.037 +/- 0.004 0.057 +/- 0.005 0.045 +/- 0.006 0.027 +/- 0.003 0.042 +/- 0.004 0.029 +/- 0.013 2nd Quarter Mean +/- s.d.
4th Quarter Mean +/- s.d.
Cumulative Average 0.027 a Iodine-131 concentrations are < 0.03 pCi/m3 unless noted otherwise.
8-1
Table 9. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131.
Location: D-40 Units: pCi/m3 Collection: Continuous, weekly exchange.
Date Volume Date Volume Collected (ms)
Gross Beta Collected (mi)
Gross Beta Required LLD 01-08-14 01-17-14 01-24-14 02-01-14 02-07-14 02-13-14 02-19-14 02-27-14 03-07-14 03-14-14 03-22-14 03-28-14 04-03-14 193 369 284 325 247 242 246 352 326 288 353 215 247 0.010 0.047 +/- 0.006 0.030 +/- 0.003 0.022 +/- 0.003 0.024 +/- 0.003 0.024 +/- 0.004 0.037 +/- 0.005 0.041 +/- 0.005 0.032 +/- 0.004 0.037 +/- 0.004 0.008 +/- 0.003 0.015 +/- 0.003 0.033 +/- 0.005 0.029 +/- 0.004 Required LLD 07-11-14 07-17-14 07-24-14 08-01-14 08-09-14 08-14-14 08-22-14 08-27-14 09-06-14 09-11-14 09-19-14 09-27-14 10-02-14 317 239 272 317 324 202 306 195 381 199 312 308 195 0.010 0.021 +/- 0.003 0.018 +/- 0.004 0.024 +/- 0.004 0.021 +/- 0.003 0.035 +/- 0.004 0.026 +/- 0.005 0.036 +/- 0.004 0.023 +/- 0.005 0.024 +/- 0.003 0.021 +/- 0.005 0.027 +/- 0.004 0.034 +/- 0.004 0.034 +/- 0.005 b
1st Quarter Mean +/- s.d.
0.029 +/- 0.011 3rd Quarter Mean +/- s.d.
04-11-14 04-16-14 04-23-14 05-01-14 05-09-14 05-16-14 05-22-14 05-30-14 06-04-14 06-13-14 06-19-14 06-26-14 07-03-14 327 200.
285 329 322 286 236 318 199 353 244 275 237 0.023 +/- 0.003 0.021 +/- 0.005 0.024 +/- 0.004 0.012 +/- 0.003 0.016 +/- 0.003 0.015 +/- 0.003 0.026 +/- 0.004 0.023 +/- 0.003 0.011 +/- 0.004 0.022 +/- 0.003 0.022 +/- 0.004 0.015 +/- 0.003 0.012 +/- 0.004 10-09-14 10-17-14 10-23-14 10-30-14 11-07-14 11-13-14 11-21-14 11-28-14 12-04-14 12-12-14 12-17-14 12-26-14 01-02-15 270 314 232 272 305 239 327 293 249 325 204 372 284 0.027 +/- 0.006 0.008 +/- 0.003 0.017 +/- 0.003 0.021 +/- 0.004 0.031 +/- 0.004 0.025 +/- 0.003 0.022 +/- 0.004 0.027 +/- 0.003 0.034 +/- 0.004 0:037 +/- 0.004 0..056 +/- 0.004 0.042 +/- 0.005 0.032 +/- 0.003 0.041 +/- 0.004 0.030 +/- 0.012 2nd Quarter Mean +/- s.d.
0.018 +/- 0.005 4th Quarter Mean +/- s.d.
Cumulative Average 0.026 a Iodine-1 31 concentrations are < 0.03 pCi/mi3 unless noted otherwise.
b Filter light.
9-1
Table 10.
Airborne particulates, analyses for gamma-emitting isotopes.
Collection: Quarterly Composite Units: pCi/mrn Location D-3 Quarter Lab Code Volume (mi)
Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-106 Cs-134 Cs-137 Ce-141 Ce-144 1st Quarter DAP-1799 3710 2nd Quarter DAP-3693 3595 3rd Quarter DAP-5989 3468 0.050 +/- 0.013
< 0.0008
< 0.0011
< 0.0006
< 0.0006
< 0.0013
< 0.0011
< 0.0013
< 010007
< 0.0069
< 0.0007
< 0.0005
< 0.0018
< 0.0032 0.084 + 0.013 0.0007 0.0007 0.0007 0.0007 0.0006 0.0010 0.0018 0.0008 0.0054 0.0006 0.0005 0.0011 0.0040 0.075 +/- 0.014 0.0006 0.0014 0.0006 0.0006 0.0018 0.0008 0.0015 0.0008 0.0059 0.0007 0.0005 0.0015 0.0036 4th Quarter DAP-7430 3469 0.052 +/- 0.014
< 0.0005
< 0.0009
< 0.0007
< 0.0007
< 0.0013
< 0.0007
< 0.0002
< 0.0005
< 0.0005
< 0.0008
< 0.0004
< 0.0002
< 0.0041 Location D-5 Lab Code Volume (m')
Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-1 06 Cs-134 Cs-137 Ce-141 Ce-144 DAP-1800 3670 DAP-3694 3646 0.063 +/- 0.014 0.0006 0.0010 0.0008 0.0005 0.0009 0.0014 0.0014 0.0013 0.0102 0.0009 0.0010 0.0020 0.0056 0.075 +/- 0.015 0.0007 0.0012 0.0006 0.0008 0.0007 0.0011 0.0013 0.0006 0.0049 0.0007 0.0008 0.0013 0.0036 DAP-5991 3762 0.076 +/- 0.016
< 0.0010
< 0.0023
< 0.0009
< 0.0007
< 0.0017
< 0.0013
< 0.0018
'< 0.0013
< 0.0072
< 0.0010
< 0.0008
< 0.0018
< 0.0054 DAP-7431 3921 0.052 +/- 0.013
< 0.0009
< 0.0012
< 0.0005
< 0.0001
< 0.0007
< 0.0009
< 0.0013
< 0.0004
< 0.0053
< 0.0006
< 0.0007
< 0.0013
< 0.0013 Location D-6 Lab Code Volume (mi)
Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-1 06 Cs-1 34 Cs-137 Ce-141 Ce-144 DAP-1801 3590 0.055 +/- 0.015
< 0.0009
< 0.0022
< 0.0009
< 0.0007
< 0.0009
< 0.0015
< 0.0012
< 0.0019
< 0.0103
< 0.0011
< 0.0009
< 0.0025
< 0.0069 DAP-3695 3670 0.073 +/- 0.012
< 0.0009
< 0.0015
< 0.0007
< 0.0008
< 0.0010
< 0.0015
< 0.0014
< 0.0013
< 0.0060
< 0.0009
< 0.0006
< 0.0023
< 0.0046 DAP-5992 3636 0.064 +/- 0.014
'< 0.0008
< 0.0014
< 0.0006
< 0.0003
< 0.0006
< 0.0015
< 0.0013
< 0.0009
< 0.0062
< 0.0007
< 0.0009
< 0.0020
< 0.0038 DAP-7432 3756 0.048 +/- 0.016 0.0005 0.0012 0.0004 0.0007 0.0009 0.0008.
0.0013 0.0001 0.0057 0.0007 0.0004 0.0015 0.0028 10-1
Table 10.
Airborne particulates, analyses for gamma-emitting isotopes.
Collection: Quarterly Composite Units: pCi/mrn Location D-7 Quarter Lab Code Volume (m")
Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 Ru-1 03 Ru-1 06 Cs-1 34 Cs-137 Ce-141 Ce-144 1st Quarter DAP-1802 3717 2nd Quarter DAP-3696 3810 3rd Quarter DAP-5993 3681 4th Quarter DAP-7433 3802 0.056 + 0.017 0.0008 0.0019 0.0007 0.0010 0.0012 0.0012 0.0013 0.0011 0.0091 0.0011 0.0015 0.0022 0.0059 0.063 + 0.011 0.0004 0.0009 0.0005 0.0006 0.0010 0.0008 0.0009 0.0007 0.0055 0.0006 0.0006 0.0012 0.0022 0.065 + 0.012 0.0004 0.0009 0.0004 0.0006 0.0007 0.0008 0.0015 0.0009 0.0038 0.0005 0.0006 0.0012 0.0027 0.044 +/- 0.015 0.0006 0.0008 0.0008 0.0007 0.0007 0.0014 0.0014 0.0009 0.0074 0.0009 0.0008 0.0013 0.0049 Location D-11 Lab Code Volume (ms)
Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-106 Cs-134 Cs-137 Ce-141 Ce-144 DAP-1803 3699 DAP-3697 3721 DAP-5994 3642 DAP-7434 3782 0.064 +/- 0.013 0.0006 0.0011 0.0008 0.0005 0.0011 0.0007 0.0013 0.0008 0.0070 0.0008 0.0004 0.0013 0.0031 0.066 +/- 0.013 0.0008 0.0006 0.0006 0.0004 0.0008 0.0012 0.0013 0.0008 0.0074 0.0008 0.0006 0.0018 0.0048 0.067 +/- 0.016 0.0009 0.0013 0.0008 0.0008 0.0012 0.0015 0.0011 0.0010 0.0070 0.0009 0.0009 0.0018 0.0053 0.046 +/- 0.011 0.0004 0.0011 0.0011 0.0003 0.0017 0.0014 0.0017 0.0007 0.0048 0.0009 0.0008 0.0013 0.0051 Location D-1 3 Lab Code Volume (m)
Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-106 Cs-1 34 Cs-1 37 Ce-141 Ce-144 DAP-1804 3555 0.055 +/- 0.016
< 0.0008
< 0.0027
< 0.0010
< 0.0010
< 0.0012
< 0.0012
< 0.0017
< 0.0016
< 0.0051
< 0.0010
< 0.0008
< 0.0028
< 0.0064 DAP-3698 3655 0.068 +/- 0.015
< 0.0010
< 0.0008
< 0.0006
< 0.0009
< 0.0012
< 0.0010
< 0.0016
< 0.0012
< 0.0078
< 0.0010
< 0.0009
< 0.0013
< 0.0057 DAP-5995 2602 DAP-7435 3695 0.089 +/- 0.022 0.0010 0.0024 0.0007 0.0006 0.0009 0.0018 0.0019 0.0009 0.0085 0.0011 0.0008 0.0025 0.0069 0.040 +/- 0.013 0.0008 0.0016 0.0005 0.0006 0.0011 0.0012 0.0014 0.0011 0.0077 0.0012 0.0006 0.0016 0.0051 10-2
Table 10.
Airborne particulates, analyses for gamma-emitting isotopes.
Collection: Quarterly Composite Units: pCi/ms Location Quarter D-1 5 1st Quarter DAP-1806 3635 2nd Quarter DAP-3699 3206 3rd Quarter DAP-5996 3583 Lab Code Volume (m*)
Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-106 Cs-1 34 Cs-137 Ce-141 Ce-144 0.068 + 0.016 0.0004 0.0018 0.0003 0.0009 0.0014 0.0013 0.0012 0.0015 0.0089 0.0007 0.0007 0.0015 0.0053 0.068 + 0.016 0.0008 0.0021 0.0008 0.0012 0.0008 0.0011 0.0016 0.0015 0.0057 0.0010 0.0006 0.0020 0.0030 0.062 +/- 0.016 0.0008 0.0012 0.0004 0.0009 0.0009 0.0005 0.0011 0.0010 0.0068 0.0007 0.0010 0.0012 0.0050 4th Quarter DAP-7436 3661 0.038 +/- 0.011
< 0.0007
< 0.0009
< 0.0006
< 0.0008
< 0.0007
< 0.0012
< 0.0014
< 0.0004
< 0.0053
< 0.0007
< 0.0006
< 0.0011
< 0.0044 Location D-16 Lab Code Volume (ms)
Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-106 Cs-134 Cs-1 37 Ce-141 Ce-144 DAP-1807 3700 DAP-3701 3721 0.062 +/- 0.018 0.0008 0.0014 0.0006 0.0004 0.0011 0.0012 0.0013 0.0008 0.0065 0.0009 0.0003 0.0014 0.0050 0.079 +/- 0.018 0.0011 0.0016 0.0007 0.0008 0.0011 0.0009 0.0013 0.0007 0.0038 0.0010 0.0008 0.0018 0.0058 DAP-5997 3575 0.062 +/- 0.014
< 0.0009
< 0.0019
< 0.0006
< 0.0010
< 0.0012
< 0.0006
< 0.0010
< 0.0014
< 0.0043
< 0.0010
< 0.0005
< 0.0014
< 0.0049 DAP-7437 3642 0.056 +/- 0.015
< 0.0011
< 0.0019
< 0.0008
< 0.0005
< 0.0008
< 0.0007
< 0.0012
< 0.0007
< 0.0098
< 0.0010
< 0.0006
< 0.0016
< 0.0045 Location D-40 Lab Code Volume (ms)
Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 Ru-1 03 Ru-1 06 Cs-134 Cs-1 37 Ce-141 Ce-144 DAP-1808 3686 0.059 +/- 0.016
< 0.0008
< 0.0010
< 0.0005
< 0.0004
< 0.0007
< 0.0004
< 0.0011
< 0.0009
< 0.0047
< 0.0008
< 0.0006
< 0.0013
< 0.0037 DAP-3702 3611 0.075 +/- 0.017
< 0.0008
< 0.0016
< 0.0003
< 0.0008
< 0.0007
< 0.0010
< 0.0011
< 0.0012
< 0.0031
< 0.0008
< 0.0011
< 0.0017
< 0.0030 DAP-5998 3568 0.080 +/- 0.017
< 0.0009
< 0.0015
< 0.0006
< 0.0004
< 0.0006
< 0.0010
< 0.0017
< 0.0013
< 0.0074
< 0.0008
< 0.0009
< 0.0021
< 0.0047 DAP-7438 3686 0.040 +/- 0.013
< 0.0006
< 0.0015
< 0.0006
< 0.0007
< 0.0014
< 0.0006
< 0.0016
< 0.0011
< 0.0069
< 0.0008
< 0.0010
< 0.0015
< 0.0056 10-3
Table 11. Ambient gamma radiation as measured by thermoluminescent dosimeters (TLD).
Quarterly collection.
Units: mR/91 days Control Locations 1st Qtr.
2nd Qtr.
3rd Qtr.
4th Qtr.
D-1 D-2 D-3 D-5 D-6 D-7 D-8 D-10 D-1 1 D-13 16.4 +/- 0.9 14.0 +/- 0.9 15.5 +/- 1.4 13.4 +/- 0.8 13.6 +/- 0.7 12.6 +/- 0.7 17.9 +/- 0.9 17.7 +/- 1.0 13.0 +/- 1.2 11.4 +/- 0.6 14.6 +/- 2.2 12.7 +/- 1.6 10.8 +/- 1.1 10.5 +/- 0.9 14.6 +/- 1.5 14.8 +/- 1.3 12.4 +/- 1.1 14.3 +/- 1.4 11.7 +/- 1.3 12.8 +/- 1.8 13.7 +/- 1.1 12.9 +/- 1.5 14.7 +/- 0.9 13.0 +/- 0.9 17.4 +/- 1.0 12.9 +/- 1.1 13.7 +/- 0.9 13.6 +/- 0.7 18.2 +/- 1.0 15.8 +/- 0.9 12.8 +/- 1.2 11.7 +/- 0.7 14.4 +/- 2.1 16.8 +/- 1.3 14.6 +/- 1.2 13.7 +/- 0.6 18.9 +/- 1.5 18.3 +/- 0.9 16.3 +/- 0.9 17.6 +/- 1.6 16.0 +/- 0.9 16.2 +/- 1.5 17.5 +/- 1.0 16.6 +/- 1.6 Mean +/- s.d.
Within 0.5 mi. of Stack D-1 5 D-16 D-17 D-18 D-19 D-20 D-21 D-22 D-23 D-28 D-29 D-30 D-31 D-32 D-82 D-83 D-84 D-85 D-86 D-91 13.9 +/- 1.0 12.4 +/- 0.8 16.6 +/- 0.8 14.6 +/- 1.2 14.4 +/- 0.8 14.4 +/- 1.0 18.0 +/- 1.2 15.5 +/- 0.8 10.8 +/- 0.8 16.1 +/- 1.2 17.7 +/- 0.7 14.6 +/- 0.9 16.4 +/- 1.2 18.9 +/- 0.9 15.3 +/- 0.8 13.0 +/- 0.6 14.7 +/- 0.8 14.9 +/- 0.7 15.2 +/- 1.4 14.5 +/- 0.9 15.1 +/- 1.9 12.2 +/- 0.9 14.3 +/- 1.7 19.7 +/- 1.9 18.9 +/- 1.1 12.8 +/- 1.4 19.5 +/- 2.1 15.8 +/- 1.0 13.2 +/- 1.0 9.3 +/- 1.0 14.8 +/- 1.0 19.9 +/- 1.1 14.2 +/- 1.6 15.7 +/- 1.4 14.4 +/- 1.2 17.3 +/- 1.2 12.7 +/- 0.9 11.8 +/- 1.2 15.9 +/- 1.1 16.3 +/- 1.4 13.6 +/- 1.5 15.1 +/- 2.9 13.3 +/- 1.1 12.0 +/- 0.8 19.7 +/- 1.0 14.8 +/- 1.2 14.8 +/- 1.0 19.1 +/- 0.8 17.8 +/- 0.7 17.8 +/- 0.7 10.3 +/- 0.9 18.0 +/- 1.7 22.5 +/- 1.0 15.6 +/- 0.9 17.0 +/- 1.2 22.0 +/- 0.7 16.4 +/- 0.8 13.3 +/- 0.6 18.5 +/- 1.2 15.5 +/- 0.6 19.2 +/- 1.2 15.5 +/- 0.9 16.6 +/- 3.1 19.6 +/- 0.7 15.2 +/- 1.3 NDa 21.0 +/- 0.9 14.4 +/- 1.1 18.8 +/- 1.9 16.0 +/- 1.0 14.3 +/- 0.8 15.6 +/- 0.8 17.2 +/- 0.8 22.2 +/- 1.0 21.4 +/- 1.7 18.4 +/- 1.6 22.4 +/- 1.7 18.8 +/- 0.9 19.2 +/- 1.1 12.8 +/- 1.0 22.0 +/- 0.9 17.9 +/- 1.3 18.2 +/- 1.7 18.2 +/- 2.9 Mean +/- s.d.
a8 NDO = No data; see Table 2.0, Listing of Missed Samples.
11-1
Table 11. Ambient gamma radiation as measured by thermoluminescent dosimeters (TLD).
Quarterly collection.
Units: mR/91 days Within 1.0 mi. of Stack 1st Qtr.
2nd Qtr.
3rd Qtr.
D-43 D-44 D-45 D-46 D-47 D-48 14.2 +/- 0.9 16.1 +/- 0.8 14.6 +/- 0.6 16.2 +/- 1.0 17.1 +/- 0.8 16.7 +/- 0.8 15.8 + 1.2 12.4 +/- 1.5 15.5 +/- 1.0 11.7 +/- 1.5 19.8 +/- 1.4 17.3 +/- 1.5 15.9 +/- 1.6 15.4 + 3.0 14.9 +/- 0.9 17.4 +/- 0.8 14.4 +/- 0.7 17.9 +/- 0.8 21.0 +/- 0.9 18.2 +/- 0.8 17.3 + 2.4 4th Qtr.
14.1 +/- 1.0 18.0 +/- 0.6 14.1 +/- 1.0 23.3 +/- 1.2 20.3 +/- 1.2 21.2 +/- 1.3 18.5 + 3.8 Mean + s.d.
Within 3.0 mi. of Stack D-33 D-34 D-35 D-36 D-37 D-38 D-39 D-40 D-41 D-42 Mean +/- s.d.
ISFSI Fenceline 10.7 +/- 0.7 13.0 +/- 0.9 14.0 +/- 0.8 13.9 +/- 0.7 16.9 +/- 1.6 14.5 +/- 0.9 14.6 +/- 0.7 11.9 +/- 0.9 15.8 +/- 0.7 11.5 +/- 0.7 13.7 +/- 1.9.
10.7 +/- 0.9 11.1 +/- 1.2 13.3 +/- 0.9 11.9 +/- 1.0 16.1 +/- 1.0 11.7 +/- 1.2 14.6 +/- 1.2 10.3 +/- 1.0 17.7 +/- 1.7 12.4 +/- 1.1 13.0 +/-2.4 10.7 +/- 0.8 13.3 +/- 0.7 13.7 +/- 0.8 13.8 +/- 0.9 15.1 +/- 1.2 15.3 +/- 0.9 14.7 +/- 0.8 11.5 +/- 1.0 15.8 +/- 0.8 11.1 +/-0.7 13.5 +/- 1.8 13.7 +/- 0.7 14.0 +/- 0.9 16.2 +/- 1.0 15.2 +/- 1.0 21.0 +/- 0.7 14.3 +/- 1.2 20.7 +/- 1.1 12.8 +/- 0.9 20.0 +/- 1.1 14.8 +/- 1.0 16.3 +/- 3.1 D-161 D-162 D-163 D-164 50.3 +/- 2.1 16.5 +/- 0.9 48.6 +/- 1.2 13.6 +/- 0.8 32.2 +/- 19.9 42.5 +/- 3.4 14.2 +/- 1.2 42.1 +/-2.7 11.3 +/- 1.1 27.5 +/- 17.1 53.2 +/- 1.6 19.7 +/- 0.8 34.4 +/- 1.0 14.1 +/- 0.7 30.4 +/- 17.5 45.6 +/- 2.5 20.5 +/- 1.4 39.9 +/- 1.9 12.0 +/- 0.8 29.5 +/- 15.9 Mean +/- s.d.
11-2
Table 12.
Milk samples, analyses for iodine-131 and gamma emitting isotopes.
Collection: Monthly during non-grazing season (October 1 through April 30): biweekly during grazing season (May 1 through September 30)
Location D-110 Date Lab Concentration (pCi/L)
Collected Code 1-131 K-40 Cs-134 Cs-137 Ba-140 La-140 01-23-14 DM1-280
<0.4 1644 +/- 116
<4.3
<4.1
< 16.3
<2.8 02-11-14 DMI-509
<0.4 1424 +/-96
< 3.1
< 3.7
< 10.7
<2.2 03-28-14 DMI-1189
<0.4 1363 +/-99
<3.6
<3.8
< 11.9
<2.5 04-22-14 DMI-1631
< 0.3 1359 +/- 106
< 3.2
< 3.8
< 12.5
< 2.2 05-08-14 DMI-2059
<0.5 1309 +/-81
<2.6
<3.0
< 11.1
<2.1 05-21-14 DMI-2207
<0.3 1352 +/-_116
<4.0
<2.4
< 13.6
<2.2 06-04-14 DMI-2514
<0.3 1415 +/--116
<4.1
<3.8
<8.1
<2.4 06-17-14 DMI-2808
< 0.3 1440 +/- 90
< 2.6
. < 2.7
< 10.6
< 2.1 07-03-14 DMI-3166
< 0.4 1421 +/- 100
< 3.8
< 2.9
< 18.3
< 1.9 07-11-14 DMI-3368
<0.2 1268 +/- 108
<4.1
<4.3
<12.8
<2.1 07-22-14 DMI-3603
< 0.3 1390 +/- 101
< 2.8
< 2.5
< 9.9
< 1.1 08-09-14 DMI-4157
<0.5
.1321 +/- 106
<3.2
<2.9
<10.6
<1.3 08-22-14 DMI-4375
< 0.4, 1400 +/- 112
< 4.3
< 2.5
< 10.1
< 1.3 09-05-14 DMI-4722
<0.3 1412 +/- 112
<4.0
<3.0
<17.5
<1.8 09-18-14 DMI-4969
<0.4 1460 +/-115
<4.1
<3.4
<16.1
<2.3 09-29-14 DMI-5164
<0.3 1422 +/- 115
<4.2
<3.9
<17.1
<1.7 10-21-14 DMI-5879
< 0.5 1406 +/- 85
< 2.4
< 2.5
< 11.3
< 1.6 11-18-14 DMI-6543
< 0.4 1298 +/- 104
< 3.8
< 3.1
< 16.0
< 1.1 12-16-14 DMI-7061
< 0.2 1161 +/- 86
< 3.1
< 2.7
< 14.3
< 1.8 Location D-138 Date Lab Concentration (pCi/L)
Collected Code 1-131 K-40 Cs-134 Cs-1 37 Ba-140 La-140 01-23-14 DMI-281
< 0.5 1764 +/- 121
< 3.3
< 3.6
< 14.5.
< 1.2 02-11-14 DMI-510
<0.4 1362 +/- 107
<3.2
<3.9
< 12.2
<2.5 03-28-14 DMI-1190
<0.3 1374 +/-97
<2.8
<3.0
<9.9
<3.1 04-22-14 DMI-1632
< 0.4 1471 +/- 105
< 3.3
< 3.8
< 15.6
< 1.8 05-08-14 DMI-2060
< 0.4 1432 +/- 95
< 2.9
< 2.3
< 9.9
< 1.5 05-21-14 DMI-2208
<0.4 1314 +/- 115
<3.5
<3.9
< 11.3
<2.1 06-04-14 DMI-2515
<0.4 1467 +/--116
<3.2
<2.8
<9.4
< 1.7 06-17-14 DMI-2809
< 0.3 1589 +/- 106
< 2.7
< 2.9
< 10.5
< 2.8 07-03-14 DMI-3167
< 0.5 1089 +/- 93
< 3.0
< 3.6
< 12.3
< 2.9 07-11-14 DMI-3369
<0.2 1377 +/- 114
<3.6
<3.0
< 17.6
<4.0 07-22-14 DMI-3604
< 0.3 1331 +/- 88
< 2.9
< 3.5
< 8.2
< 2.3 08-09-14 DMI-4158
< 0.5 1307 +/- 101
< 2.9
< 2.4
< 14.3
< 2.4 08-22-14 DMI-4376
< 0.3 1088 +/- 107
< 3.2
< 2.9
< 13.4
< 1.4 09-05-14 DMI-4723
< 0.3 1435 +/- 108
< 3.5
< 2.9
< 9.9
< 3.0 09-18-14 DMI-4970
< 0.3 1337 +/- 102
< 3.2
< 3.3
< 10.2
< 2.7 09-29-14 DMI-5165
<0.5 1173 +/- 100
<3.6
<2.3
< 14.3
<2.3 10-21-14 DMI-5880
< 0.2 1394 +/- 107
< 3.1
< 3.8
< 9.6
< 3.0 11-18-14 DMI-6544
<0.4 1280 +/- 108
<3.0
<3.0
< 13.2
<2.3 12-16-14 DMI-7062
< 0.2 1295 +/- 107
< 3.1
< 2.9
< 12.8
< 2.1 12-1
Table 13. Well water samples, analyses for gamma emitting isotopes iodine-I 31 a and tritium.
Collection: Quarterly Units: pCi/L Location D-53 Treated Municipal Water Lab Code Date Collected DWW-690 02-24-14 H-3 1-131 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140
< 138
< 1.9
<5.1
< 1.1
< 2.0
< 4.0
< 1.7
< 5.3
< 3.9
< 2.5
< 1.5
< 9.4
< 2.1 DWW-2610 06-09-14
< 140
< 1.7
<4.7
< 2.0
< 1.4
< 4.6
< 2.4
< 4.3
<6.1
< 2.7
< 1.6
< 14.2
< 1.6 DWW-3936 08-01-14
< 131
< 1.8
< 5.5
< 2.3
< 2.0
< 2.7
< 3.8
<4.0
< 10.3
< 2.8
< 2.5
< 22.6
< 3.6
< 176
< 0.4
< 2.9
< 3.9
< 3.7
< 1.6
< 5.7
< 2.6
< 3.6
< 5.5
< 3.3
< 3.2
< 16.8
< 3.4 DWW-7017 12-15-14 Location D-54 Inlet to Municiral Water Lab Code Date Collected H-3 1-131 DWW-691 02-24-14
< 138 DWW-2611 06-09-14
< 140 DWW-3937 08-01-14
< 131 DWW-7018 12-15-14
< 176 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140
< 2.5
< 2.2
<2.1
< 1.6
<5.1
< 3.1
<4.3
< 3.2
< 2.8
< 2.7
< 7.5
< 2.8
< 2.7
<4.9
< 3.6
< 1.6
< 4.0
< 2.6
< 2.7
< 7.2
< 3.3
< 3.6
< 15.0
<2.3
< 1.3
< 2.6
< 2.0
< 1.9
< 4.3
< 3.2
<4.7
< 8.9
< 2.8
<3.1
< 20.2
< 4.0
< 0.5
<2.1
< 4.5
< 1.9
< 1.9
<6.1
< 3.0
<4.8
< 9.7
< 2.8
< 3.3
< 15.0
< 3.4 a 1-131 by chemistry analysis added in fourth quarter.
14-1
Table 13. Well water samples, analyses for gamma emitting isotopes iodine-131a and tritium.
Collection: Quarterly Units: pCi/L Location D-55 On-site Well Lab Code Date Collected DWW-692 02-24-14 H-3 1-131 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-1 34 Cs-1 37 Ba-140 La-140
< 138
< 3.7
< 8.7
< 2.6
< 2.9
< 8.4
< 2.0
< 5.2
< 4.8
< 4.4
< 3.5
< 21.0
< 4.2 DWW-2612 06-09-14
< 140
<2.5
< 3.3
< 2.5
< 1.9
< 3.0
< 3.0
< 5.6
< 7.8
< 3.3
< 2.6
< 18.3
< 3.3 DWW-3938 08-01-14
< 131
< 3.9
<4.0
< 2.2
< 1.3
< 5.6
< 4.2
< 6.3
< 13.5
< 4.0
< 3.8
< 26.5
< 5.0
< 176
< 0.5
< 2.6
< 5.8
< 3.2
<2.3
< 3.6
< 3.9
< 5.8
< 7.4
< 3.6
< 2.7
< 16.7
< 6.6 DWW-7019 12-15-14 Location D-57 Bull Farm Lab Code DWW-693 DWW-2613 DWW-3939 DWW-7020 Date Collected 02-24-14 06-09-14 08-01-14 12-15-14 H-3
< 138
< 140
< 131
< 176 1-131
< 0.4 Mn-54
< 2.6
< 1.5
< 2.5
< 4.0 Fe-59
< 4.1
< 4.0
< 3.7
< 3.2 Co-58
< 2.5
< 1.7
< 1.6
< 2.3 Co-60
< 2.4
< 2.4
< 2.3
< 1.3 Zn-65
< 5.9
< 3.9
< 2.7
< 2.5 Nb-95
< 3.2
< 2.5
< 3.1
< 2.9 Zr-95
< 5.4
< 3.9
< 5.5
< 3.5 1-131
< 4.1
< 8.0
< 10.2
< 6.2 Cs-134
< 2.8
< 2.6
< 2.7
< 3.2 Cs-137
< 2.8
< 2.8
< 3.2
< 3.2 Ba-140
< 12.7
< 18.0
< 26.2
< 15.5 La-140
< 2.6
< 2.9
< 4.6
< 5.3 a 1-131 by chemistry analysis added in fourth quarter.
14-1
Table 13. Well water samples, analyses for gamma emitting isotopes iodine-1 31 a and tritium.
Collection: Quarterly Units: pCi/L Location D-58 Franz Farm Lab Code Date Collected H-3 DWW-694 02-24-14
< 138 DWW-2614 06-09-14
< 140 DWW-3940 08-01-14 DWW-7021 12-15-14
< 176 1-131 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140
.< 2.6
<2.5
< 3.3
< 1.5
< 4.2
< 2.4
< 5.0
<4.1
< 2.6
< 3.8
< 11.9
< 1.6
< 2.2
< 6.2
< 1.4
< 2.6
< 4.6
< 1.5
< 3.4
<6.1
<3.1
< 2.0.
< 15.4
< 2.5
< 131
<2.1
< 5.1
< 2.5
< 1.4
< 1.5
< 3.0
< 5.2
< 11.6
< 2.6
< 1.5
< 22.6
< 3.5
< 0.5
< 2.4
< 3.6
<2.3
< 2.6
< 3.5
<4.1
<5.1
< 6.4
< 3.0
<3.1
< 20.1
< 4.5 Location D-72(C) Van Note Farm Lab Code DWW-695 DWW-2615 DWW-3941 DWW-7022 Date Collected 02-24-14 06-09-14 08-01-14 12-15-14 H-3
< 138
< 140
< 131
< 176 1-131.
< 0.5 Mn-54
< 2.5
< 4.1
< 2.2
< 3.6 Fe-59
< 6.2
< 6.8
< 3.9
< 5.2 Co-58
< 2.6
< 3.0
< 1.9
< 2.1 Co-60
< 2.0
< 1.3
< 2.8
< 1.8 Zn-65
< 2.8
< 4.2
< 2.2
< 3.4 Nb-95
< 2.0
< 4.4
< 2.7
< 2.7 Zr-95
< 3.1
< 7.4
< 3.4
< 2.9 1-131
< 4.2
< 8.4
< 9.6
< 8.5 Cs-134
< 2.9
< 4.0
< 2.7
< 3.0 Cs-137
< 1.9
< 4.6
< 3.1
< 2.9 Ba-140
< 11.0
< 18.0
< 21.7
< 19.5 La-140
< 2.6
< 3.2
< 5.6
< 1.9 a 1-131 by chemistry analysis added in fourth quarter.
14-1
Table 14. Vegetation (broadleaf), analyses for iodine-131 and other gamma-emitting isotopes.
Collection: Annually Units: pCi/g wet Location D-15 D-57 D-118 Lab Code DVE-5168 DVE-3371 DVE-5016 Date Collected 09-27-14 07-10-14 09-10-14 Sample Type Broadleaf Broadleaf Cabbage K-40 6.69 +/- 0.52 4.04 +/- 0.42 1.81 +/- 0.15 Mn-54
< 0.009
< 0.014
< 0.003 Fe-59
< 0.038
< 0.022
< 0.007 Co-58
< 0.011
< 0.013
< 0.005 Co-60
< 0.010
< 0.018
< 0.005 Zn-65
< 0.049
< 0.034
< 0.006 Nb-95
< 0.018
< 0.018
< 0.004 Zr-95
< 0.032
< 0.021
< 0.007 Ru-103
< 0.016
< 0.019
< 0.004 Ru-106
< 0.085
< 0.12
< 0.037 1-131
< 0.021
< 0.033
< 0.015 Cs-134
< 0.016
< 0.015
< 0.004 Cs-137
< 0.017
< 0.014
< 0.005 Ce-141
< 0.046
< 0.023
< 0.010 Ce-144
< 0.18
< 0.094
< 0.039 14-1
Table 15. Vegetation (hay and grain), analyses for gamma-emitting isotopes.
Collection:
Annually Units:
pCi/g wet Location D-16 D-57 D-57 D-15 D-57 Lab Code DVE-5166 DVE-3370 DVE-3372 DVE-5167 DVE-6635 Date Collected 09-27-14 07-10-14 07-10-14 09-27-14 11-20-14 Sample Type Forage Clover Wheat Forage Corn K-40 3.46 +/- 0.44 5.98 +/- 0.63 4.70 +/- 0.60 4.91 +/- 0.43 2.75 +/- 0.21 Mn-54
< 0.023
< 0.021
< 0.020
< 0.017
< 0.006 Fe-59
< 0.027
< 0.031
< 0.063
< 0.014
< 0.013 Co-58
< 0.016
< 0.023
< 0.021
< 0.010
< 0.004 Co-60
< 0.023
< 0.025
< 0.022
< 0.015
< 0.007 Zn-65
< 0.018
< 0.032
< 0.047
< 0.022
< 0.013 Nb-95
< 0.015
< 0.024
< 0.033
< 0.019
< 0.008 Zr-95
< 0.023
< 0.040
< 0.055
< 0.029
< 0.012 Ru-103
< 0.015
< 0.022
< 0.023
< 0.016
< 0.004 Ru-106
< 0.21
< 0.15
< 0.23
< 0.16
< 0.036 1-131
< 0.031
< 0.048
< 0.051
< 0.036
< 0.011 Cs-134
< 0.020
< 0.021
< 0.025
< 0.018
< 0.006 Cs-137
< 0.022
< 0.021
< 0.030
< 0.017
< 0.005 Ce-141
< 0.028
< 0.025
< 0.047
< 0.039
< 0.012 Ce-144
< 0.15
< 0.17
< 0.16
< 0.16
< 0.044 Location D-96 D-96 D-109 Lab Code DVE-6636 DVE-6637 DVE-6638 Date Collected 11-18-14 11-18-14 11-18-14 Sample Type Corn Beans Corn K-40 2.61 +/- 0.21 14.59 +/- 0.45 3.05 +/- 0.21 Mn-54
< 0.006
< 0.009
< 0.006 Fe-59
< 0.011
< 0.026
< 0.014 Co-58
< 0.004
< 0.007
< 0.004 Co-60
< 0.004
< 0.010
< 0.006 Zn-65
< 0.008
< 0.027
< 0.015 Nb-95
< 0.008
< 0.009
< 0.005 Zr-95
< 0.008
< 0.013
< 0.007 Ru-103
< 0.006
< 0.008
< 0.005 Ru-106
< 0.060
< 0.062
< 0.069 1-131
< 0.011
< 0.018
< 0.010 Cs-1 34
< 0.007
< 0.007
< 0.006 Cs-137
< 0.007
< 0.009
< 0.006 Ce-141
< 0.010
< 0.016
< 0.013 Ce-144
< 0.043
< 0.059
< 0.038 15-1
Table 16. Surface water samples, analyses for iodine-131, tritium and gamma-emitting isotopes.
Collection:
Monthly Units:
pCi/L Location:
D-49 Lab Code Date Collected H-3 1-131 (Chemistry)
DSW-1071 DSW-1647 DSW-2220 DSW-2958 03-19-14 04-22-14 05-22-14 06-25-14 01-22-14 NDa 02-04-14 N Da
< 150
< 0.4 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140
< 1.9
< 3.9
< 1.5
- 2.3
- 5.2
< 2.9
< 3.2
.< 2.6
< 2.8
< 3.0
< 10.1
< 1.7
< 146
<0.3.
<2.3
<4.9
< 3.0
< 1.9
<2.8
< 2.8
< 4.2
<3.5
< 3.0
< 2.3
< 14.8
< 2.2
< 145
<0.3
< 3.0
- 3.8
< 2.6
< 2.5
< 4.4
<3.1
<4.2
< 5.0
< 3.2
< 2.9
< 10.9
< 2.2
< 142
< 0.4
< 0.9
< 3.8
< 1.6
<2.1
< 5.5
< 1.8
<4.2
<4.8
< 2.6
< 2.7
< 10.7
<3.1 Lab Code Date Collected H-3 DSW-3543 DSW-4377 DSW-4971 DSW-5939 07-16-14 08-21-14 09-18-14 10-22-14 DSW-6733 DSW-7091 11-26-14 12-20-14
< 137 1-131 (Chemistry)
Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140
< 0.3
< 2.9
<4.3
- 2.3
< 2.6
<4.5
< 2.6
< 5.2
< 7.1
<4.2
< 3.8
< 16.6
< 3.6
< 143
< 0.3
- 1.5
< 5.7
<2.1
< 2.2
< 2.6 1 1.7
< 3.4
< 4.7
< 3.0
- 3.0
< 12.0
<2.7
< 151
< 0.3
< 2.9
< 4.3
< 2.7
< 1.5
< 3.6
< 3.8
<4.1
< 5.1
< 3.7
< 4.5
< 7.4
< 1.9
< 148
< 0.2
< 3.3
< 3.7
<2.1
< 2.2
<4.7
< 3.3
<6.9
< 4.6
< 3.7
<3.1
< 14.6
< 1.4
< 179
< 0.3
< 2.5
< 3.6
< 1.4
< 2.1
<4.3
< 3.8
< 5.4
< 5.6
< 3.8
<2.6
< 8.6
< 2.2
< 183
< 0.5
< 3.3
< 5.9
< 1.9
< 2.6
< 5.9
< 2.4
< 2.9
< 4.4
<3.3
<3.1
< 14.6
< 2.5 a ND = No data; see Table 2.0, Listing of Missed Samples.
16-1
Table 16. Surface water samples, analyses for tritium and gamma-emitting isotopes.
Collection:
Monthly Units:
pCi/L Location:
D-50 Lab Code Date Collected DSW-282 01-22-14 H-3 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140
< 144
< 2.4
< 4.9
< 3.0
< 1.7
< 4.9
<2.1
< 3.9
<4.1
< 2.7
<2.1
< 13.4
< 2.6 DSW-392 02-04-14
< 152
< 3.5
< 5.2
< 1.5
< 2.9
<'3.3
< 3.2
<5.1 11.2 +/- 5.8
< 3.6
< 2.4
< 12.3
< 2.6 b
DSW-1072 03-19-14
< 150
<4.0
< 6.9
< 1.2
<3.1
< 5.4
< 1.4
< 5.4
< 2.4
< 4.0
< 3.5
< 15.5
< 1.8 DSW-1648 04-22-14
< 146
<4.5
<6.1
< 2.4
<2.1
< 3.6
< 3.6
< 5.0
< 3.7
< 3.9
< 3.4
< 19.3
<2.3
< 145
< 4.5
< 2.5
< 1.6
< 3.6
< 3.3
< 5.6
<7.1
<4.1
< 4.0
< 18.6
<2.1
< 142
< 2.8
<2.8
<2.5
- 1.8
<2.8
<2.1
< 4.8
<6.3
< 3.2
< 3.6
< 16.6
< 3.7 DSW-2221 DSW-2959 05-21-14 06-25-14 Lab Code Date Collected DSW-3544 07-16-14 DSW-4378 DSW-4972 DSW-5940 DSW-6734 DSW-7092 08-21-14 09-18-14 10-22-14 11-26-14 12-20-14 H-3
< 137 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140
< 2.8
< 2.8
< 2.5
< 2.7
< 2.7
< 3.2
< 5.1
< 6.4
< 3.4
< 2.9
< 17.9
< 2.9
< 143
< 1.6
< 5.2
< 1.5
< 1.9
<4.1
< 1.9
<4.8
< 5.0
<2.1
< 2.0
< 10.9
< 3.5
< 151
< 3.2
<4.5
<2.1
< 1.8
< 4.4
< 3.1
< 5.5
< 7.0
<4.2
< 3.3
< 16.2
< 1.6
< 148
< 3.4
< 5.7
< 1.7
<3.1
< 5.8
<4.1
< 5.7
< 3.6
< 3.2
< 3.9
< 16.3
< 2.9
< 179
< 2.2
< 3.8
< 2.3
< 1.6
< 2.3
< 2.5
< 3.9
< 5.3
< 2.7
< 3.8
< 14.8
< 2.3
< 183
< 1.7
< 3.7
< 2.6
< 2.0
<5.3
< 1.9
< 4.0
< 3.6
< 2.8
< 3.3
< 10.4
< 1.1 a Sample analyzed for 1-131 (by chemistry) per client request, result = 0.9+/-0.3 pCi/L.
b Sample analyzed for 1-131 (by chemistry) per client request, result = 8.8+/-0.3 pCi/L.
16-2
Table 16. Surface water samples, analyses for tritium and gamma-emitting isotopes.
Collection:
Monthly Units:
pCi/L Location:
D-51 Lab Code Date Collected DSW-283 DSW-393 DSW-1073 DSW-1649 DSW-2222 DSW-2960 01-22-14 02-04-14 a
03-19-14 04-22-14 05-21-14 06-25-14 H-3 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Lab Code Date Collected
< 144
<2.1
<4.1
< 1.4
<2.1
< 1.2
< 1.5
< 3.2
<4.3
< 2.9
< 2.9
< 9.6
< 1.6
< 152
< 1.8
< 3.0
< 1.7
< 1.9
< 5.5
<4.5
<4.0
< 4.4
< 3.2
<3.5
< 11.9
< 2.7
< 150
< 2.2
< 5.6
< 2.4
< 1.9
< 3.1
< 2.7
< 3.4
< 4.8
< 3.7
<2.1
< 11.5
< 2.9
< 146
< 2.3
< 3.3
< 1.4
< 1.9
<2.8
<2.3
< 5.8
< 3.7
< 2.7
< 1.8
< 12.4
<2.1
< 145
< 3.0
< 3.2
< 1.2
< 2.8
< 3.5
< 3.7
< 3.7
< 8.5
< 3.9
< 2.2
< 17.6
<4.0
< 142
< 2.5
<2.1
< 1.5
< 1.9
< 3.8
< 3.1
< 3.2
<4.8
< 2.6
< 3.3
< 13.1
< 1.5 DSW-3545 DSW-4379 DSW-4973 DSW-5941 DSW-6735 DSW-7093 07-16-14 08-21-14 09-18-14 10-22-14 11-26-14 12-20-14 H-3 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140
< 137
< 2.7
< 3.1
< 2.0
<2.1
< 3.5
< 2.6
< 3.2
< 3.5
< 2.7
< 2.0
< 15.9
<2.5
< 143
< 2.3
< 6.2
< 2.5
< 1.4
<5.1
<4.0
< 3.2
< 8.2
< 2.5
< 2.2
< 18.4
< 3.2
< 151
< 3.9
< 6.5
<4.0
< 3.1
< 5.6
< 4.9
< 5.2
< 7.3
<4.3
< 4.8
< 14.0
< 4.0
< 148
<2.6
< 4.0
< 1.6
< 2.6
< 3.7
< 3.8
<5.1
< 3.5
< 3.3
< 2.2
< 10.4
<2.9
< 179
< 3.9
< 4.9
<3.1
< 3.5
< 5.8
< 3.5
< 5.4
<6.3
<4.3
< 3.3
< 16.3
< 2.7
< 183
< 2.5
<4.1
< 3.0
< 1.4
<2.3
<3.1
< 4.0
< 2.5
<2.1
< 2.7
< 9.6
< 1.7 a Sample analyzed for 1-131 (by chemistry) per client request. Result = 8.9+/-0.3 pCi/L.
16-3
Table 16. Surface water samples, analyses for iodine-1 31, tritium and gamma-emitting isotopes.
Collection:
Monthly Units:
pCi/L Location:
D-61 Lab Code Date Collected DSW-285 01-22-14 H-3 1-131 (Chemistry)
Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140
< 144
<0.5
< 2.8
<4.8
< 2.5
< 2.5
< 5.6
< 3.2
< 3.5
< 5.4
< 3.0
< 3.3
< 16.4
< 2.5 DSW-394 02-04-14
< 152 9.3 +/- 0.3
<2.8
< 3.9
< 1.8
<2.6
< 7.3
< 3.9
<6.5 7.9 +/- 4.3
< 3.0
< 2.8
< 13.6
< 2.7
< 150
<0.5
< 2.8
< 6.0
< 2.8
<2.5
<6.1
< 3.2
< 5.3
< 3.9
<3.1
< 2.7
< 14.6
< 2.6
< 146
<0.3
<2.9
< 3.0
<2.0
< 1.3
<2.0
<2.2
<5.3
<2.5
<3.1
< 3.4
<6.5
< 1.6
< 145
<0.3
< 2.2
< 2.3
< 2.4
< 2.5
< 1.9
< 3.4
< 2.8
< 3.2
< 3.0
< 1.7
< 8.9
< 3.0 DSW-1075 DSW-1650 DSW-2223 DSW-2961 03-19-14 04-22-14 05-22-14 06-25-14
< 142
< 0.4
< 1.2
<5.1
< 1.4
< 1.8
<3.1
< 2.9
<4.1
<4.8
<3.1
< 2.0
< 17.1
< 2.6 Lab Code Date Collected DSW-3546 DSW-4380 DSW-4974 DSW-5942 DSW-6736 DSW-7094 07-16-14 08-21-14 09-18-14 10-22-14 11-26-14 12-20-14 H-3 1-131 (Chemistry)
Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-1 34 Cs-137 Ba-140 La-140
< 137
< 0.4
< 1.1
< 5.2
< 1.9
< 3.0
< 3.6
< 3.4
< 3.3
- < 4.9
< 3.2
< 2.8
< 14.6
< 2.9
< 143
< 0.3
< 2.6
< 3.9
< 3.0
< 2.5
< 2.3
<2.9
- <3.5
<5.3
< 2.7
< 3.2
< 15.7
<2.0
< 151
<0.3
< 3.1
<4.5
< 2.3
< 2.6
< 6.2
< 3.4
< 4.4
< 4.7
< 2.5
< 2.8
< 11.1
< 2.3
< 148
<0.3
< 3.8
< 6.8
<2.6
<4.5
<4.1
< 2.6
< 5.2
<4.8
< 4.6
<4.5
< 12.9
<4.1
< 179
<0.3
< 2.3
<4.6
<2.1
<2.1
< 5.0
<2.5
<2.5
< 4.7
< 2.9
< 2.9
< 8.8
< 1.8
< 183
< 0.2
< 3.3
<6.0
< 2.9
< 1.4
< 5.0
< 3.2
<2.9
<4.1
< 3.3
< 3.5
< 10.6
<3.1 16-4
Table 16. Surface water samples, analyses for tritium and gamma-emitting isotopes.
Collection:
Monthly Units:
pCi/L Location:
D-99 Lab Code Date Collected DSW-1076 DSW-1651 DSW-2224 DSW-2962 03-19-14 04-22-14 05-22-14 06-25-14 01-22-14 H-3 NDa Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140
< 150
<2.1
< 3.8
< 0.9
< 2.1
< 3.8
<2.5
< 3.9
< 3.5
< 2.8
< 3.2
< 10.8
< 3.2
< 146
<3.1
< 1.5
<2.3
<2.3
<2.5
<2.1
< 3.3
<5.1
<2.9
< 3.0
< 13.5
< 1.6
< 145
- 3.6
< 3.7
< 2.0
< 1.1
< 2.7
< 3.0
< 5.9
<7.1
< 4.0
<4.0
< 17.2
- 1.9
< 142
< 1.8
< 3.3
< 2.8
< 2.6
<4.3
< 2.9
<4.5
< 4.9
<2.8
<2.6
< 13.4
< 3.7 12-20-14 N Da Lab Code Date Collected DSW-3547 DSW-4381 DSW-4975 DSW-5943 DSW-6737 07-16-14 08-21-14 09-18-14 10-22-14 11-26-14 H-3 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 1-131 Cs-134 Cs-137 Ba-140 La-140
< 137
< 2.7
< 4.7
- 1.9
< 2.4
< 5.6
< 3.8
< 5.7
< 7.6
< 4.2
< 3.7
< 17.4
- 1.8
< 143
< 1.9
< 3.9
<2.0
< 2.4
< 3.4
< 3.4
< 3.8
< 6.7
< 2.6
<2.2
< 18.6
<4.1
< 151
<2.5
< 4.2
- 1.6
< 3.0
< 2.4
< 2.8
< 3.9
< 5.4
< 3.1
< 2.8
< 14.3
< 2.2
< 148
< 2.8
< 4.2
<2.5
< 1.8
< 5.8
< 2.3
< 3.4
< 3.2
< 2.5
<2.8
< 11.5
- 1.7
< 179
< 4.0
< 4.6
< 2.8
< 3.2
< 7.3
< 2.8
< 6.9
<5.3
< 3.9
< 3.9
< 19.6
< 2.6 a ND = No data; see Table 2.0, Listing of Missed Samples.
16-5
Table 17. Surface water, analysis for strontium.
Collection: Quarterly composites of monthly samples.
Units: pCi/L Location D-49 Period 1st Qtr.
2nd Qtr.
3rd Qtr.
4th Qtr.
Lab Code DSW-1 107 DSW-3052 DSW-5017 DSW-7167 Sr-89
< 0.93
< 0.74
< 0.63
< 0.69 Sr-90
< 0.80
< 0.63
< 0.53
< 0.54 Location D-61 Period 1st Qtr.
2nd Qtr.
3rd Qtr.
4th Qtr.
Lab Code DSW-1108 DSW-3053 DSW-5018 DSW-7168 Sr-89
< 0.66
< 0.59
< 0.63
< 0.78 Sr-90
< 0.52
< 0.47
< 0.50
< 0.56 17-1
Table 18. Fish, analyses of edible portion for gamma-emitting isotopes.
Collection:
Semiannually Units: pCi/g wet Location Upstream, D-49 Lab Code Date Collected Sample Type K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-106 Cs-134 Cs-137 Ce-141 Ce-144 DF-2599 06-04-14 DF-2600 06-04-14 DF-4832 09-02-14 DF-4833 09-02-14 Cyprinus Carpio 3.23 +/- 0.38
< 0.014
< 0.024
< 0.012
< 0.012
< 0.039
< 0.016
< 0.017
< 0.009
< 0.062
< 0.010
< 0.009
< 0.019
< 0.069 Carpiodes Sp.
3.08 +/- 0.43
< 0.011
< 0.029
< 0.008
< 0.014
< 0.028
< 0.013
< 0.026
< 0.015
< 0.14
< 0.015
< 0.017
< 0.029
< 0.054 Carpiodes Sp.
3.28 +/- 0.46
< 0.017
< 0.044
< 0.024
< 0.016
< 0.040
< 0.030
< 0.037
< 0.042
< 0.16
< 0.021
< 0.017
< 0.060
< 0.12 Moxostoma 3.94 +/- 0.48
< 0.012
< 0.033
< 0.012
< 0.013
< 0.027
< 0.025
< 0.027
< 0.015
< 0.15
< 0.016
< 0.014
< 0.051
< 0.11 Location Downstream, D-61 Lab Code Date Collected Sample Type K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-1 06 Cs-1 34 Cs-137 Ce-141 Ce-144 DF-2601 06-04-14 DF-2602 06-04-14 DF-4834 09-02-14 DF-4835 09-02-14 Ictiobus Sp.
3.26 +/- 0.41
< 0.013
< 0.035
<0.012
< 0.010
< 0.015
< 0.013
< 0.015
< 0.012
< 0.12
< 0.012
< 0.008
< 0.025
< 0.10 Carpiodes Sp.
3.64 +/- 0.41
< 0.011
< 0.024
< 0.009
< 0.010
< 0.019
< 0.012
< 0.009
< 0.013
< 0.15
< 0.018
< 0.015
< 0.021
< 0.079 Moxostoma Carpiodes Sp.
3.32 +/- 0.36
< 0.017
< 0.030
< 0.012
< 0.014
< 0.022
< 0.031
< 0.031
< 0.023
< 0.12
< 0.015
< 0.014
< 0.039
< 0.083 3.44 +/- 0.55
< 0.021
< 0.073
< 0.028
< 0.009
< 0.038
< 0.040
< 0.049
< 0.028
< 0.12
< 0.022
< 0.019
< 0.048
< 0.13 18-1
Table 19. River sediment, analysis for gamma-emitting isotopes.
Collection: Semiannually Units: pCi/g dry Location D-50 (Plant Intake, Control)
Lab Code Date Collected K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 Ru-103 Ru-106 Cs-134 Cs-1 37 Ce-141 Ce-144 DBS-2266 05-21-14 8.29 +/- 0.53
< 0.015
< 0.032
< 0.016
< 0.011
< 0.026
< 0.019
< 0.023
< 0.017
< 0.049
< 0.010
< 0.015
< 0.043
< 0.094 DBS-6729 11-26-14 7.65 +/- 0.49
< 0.015
< 0.029
< 0.014
< 0.010
< 0.025
< 0.014
< 0.015
< 0.018
< 0.11
< 0.010
< 0.013
< 0.032
< 0.066 Location D-51 (Discharge)
Lab Code DBS-2267 DBS-6730 Date Collected 05-21-14 11-26-14 K-40 8.03 +/- 0.48 7.31 +/- 0.43 Mn-54
< 0.012
< 0.012 Fe-59
< 0.032
< 0.029 Co-58
< 0.016
< 0.010 Co-60
< 0.009
< 0.008 Zn-65
< 0.030
< 0.021 Nb-95
< 0.024
< 0.006 Zr-95
< 0.016
< 0.014 Ru-103
< 0.017
< 0.013 Ru-106
< 0.054
< 0.059 Cs-134
< 0.010
< 0.009 Cs-1 37
< 0.011
< 0.010 Ce-141
< 0.041
< 0.013 Ce-144
< 0.059
< 0.075 19-1
Table 19. River sediment, analysis for gamma-emitting isotopes.
Collection: Semiannually Units: pCi/g dry Location D-107A (North Drainaae Ditch)
Lab Code Date Collected K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Zr-95 Ru-1 03 Ru-1 06 Cs-1 34 Cs-1 37 Ce-141 Ce-144 DBS-2268 05-21-14 6.23 +/- 0.41
< 0.018
< 0.039
< 0.008
< 0.010
< 0.033
< 0.020
< 0.026
< 0.012
< 0.11
< 0.012
< 0.011
< 0.043
< 0.072 DBS-6731 11-26-14 5.45 +/- 0.42
< 0.015
< 0.016
< 0.011
< 0.009
< 0.026
< 0.008
< 0.023
< 0.016
< 0.098
< 0.012
< 0.010
< 0.030
< 0.089 19-2