ML041260044
| ML041260044 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 04/30/2004 |
| From: | Peifer M Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NG-04-0323 | |
| Download: ML041260044 (61) | |
Text
NMC Committed to Nuclear Excele Duane Arnold Energy Center Operated by Nuclear Management Company, LLC April 30, 2004 NG-04-0323 10 CFR 50.4 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Duane Arnold Energy Center Docket 50-331 License No. DPR49 2003 Annual Radiological Environmental Operating Report Please find attached one (1) copy of the 2003 Annual Radiological Environmental Operating Report for the Duane Arnold Energy Center (DAEC). This report is transmitted in accordance with the DAEC Offsite Dose Assessment Manual (Section 6.4.2) and Technical Specifications (Section 5.6.2) reporting requirements.
Mark A. Peifer Site Vice President, Duane Arnold Energy Center Nuclear Management Company, LLC
Enclosure:
2003 Annual Radiological Environmental Operating Report cc:
D. Beaulieu (NRC-NRR)(w/a)
J. Caldwell (Region l1l) (w/a)
NRC Resident Office (w/a)
K. Erickson (Linn Co. Health Dept.) (w/a)
Drs. J. Floyd/J. Hess (w/a)
Radiochemistry Supervisor (University of Iowa) (w/a)
K. Larson (ANI) (w/a)
W. Nestel (INPO) (wla)
IRMS (w/a) 26 3277 DAEC Road
- Palo, Iowa 52324-9785 Telephone: 319.851.7611
Environmental, Inc.
Midwest Laboratory an Anegheny TednhorWes Co.
700 Landwehr Road
- Northook, IL 60062-2310 ph. (847) 564-0700
- fax (847) 564-4517 DUANE ARNOLD ENERGY CENTER CEDAR RAPIDS, IOWA DOCKET NO. 50-331 ANNUAL REPORT TO THE NUCLEAR REGULATORY COMMISSION UNITED STATES Radiation Environmental Monitoring Program January 1 to December 31, 2003 Prepared and submitted by ENVIRONMENTAL, Inc.
Midwest Laboratory Project No. 8001 Approved:
Br nia C d 'M.S.
Lorato anager
i 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.
ii
TABLE OF CONTENTS No.
PREFACE..............................................
ii List of Tables................................................
v List of Figures..............................................
vi
1.0 INTRODUCTION
1I 2.0
SUMMARY
2 3.0 ENVIRONMENTAL RADIOLOGICAL MONITORING PROGRAM
.............................. 3 3.1 Program Design and Data Interpretation............................
3 3.2 Program Description............................
4 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..............................................
10
6.0 REFERENCES
CITED..............................................
27 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)
PART 11 Page Data Tabulations and Analyses.......................
iv
No.
5.1 5.2 5.3 5.4 5.5 5.6 5.7 LIST OF TABLES Page Characteristic Properties of Isotopes Quantified in Gamma-spectroscopic Analyses........................................
II Sample Collection and Analysis Program........................................
12 Sampling Locations, DAEC........................................
15 Type and Frequency of Collections........................................ 17 Sample Codes Used in Table 5.4........................................
18 Missed Collections and Analyses........................................
19 Radiological Environmental Monitoring Program Summary....................................... 20 In addition, the following tables are in the Appendices:
Appendix A A-1 A-2 A-3 A-4 A-5 A-6 A-7 Appendix C C-1 Interlaboratory Comparison Program Results................................. Al-I Interlaboratory Comparison Program
- Results, Thermoluminescent 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 Measurements Laboratory Quality (EML) Assessment Program comparison results.......................................................
A7-1 Attachment A: Acceptance criteria for spiked samples............................................ A-2 Effluent Concentration Limits for Radioactivity in Air and Water Above Background in Unrestricted Areas.......................................................
C-2 v
LIST OF FIGURES No.
Paae 5.1 Radiological Environmental Monitoring Program Sampling Stations near the Duane Arnold Energy Center...................
25 5.2 Radiological Environmental Monitoring Program Sampling Stations Outside 0.5 Miles....
26 vi
1.0 INTRODUCTION
This report summarizes and interprets results of the Radiological Environmental Monitoring Program conducted by Environmental, Inc., Midwest Laboratory at the Duane Arnold Energy Center, Palo, Iowa, during the period January - December, 2003. 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.
Tabulation of the individual analyses made during the year are included in Part II of this report.
Duane Arnold Energy Center (DAEC) is located in Linn County, Iowa, on the Cedar River, owned by IES Utilities, Inc and operated by Nuclear Management Corporation. The Duane Arnold Energy Center is a 565.7 MW(e) boiling water reactor. Initial criticality was attained on March 23, 1974. The reactor reached 100% power on August 12, 1974. Commercial operation began on February 1, 1975.
I
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 2003 are summarized and discussed.
Program findings show background levels of radioactivity In the environmental samples collected in the vicinity of the Duane Arnold Energy Center.
No effect on the environment due to the operation of the Duane Arnold Energy Center is indicated.
2
3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 3.1 Program Design 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 should not be considered radiological impact indicators.
3
3.1 Program Design and Data Interpretation (continued)
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.
3.2 Program Description The sampling and analysis schedule for the environmental radiological monitoring program 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 type (indicator or control) and 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 twelve locations. Also, airborne iodine is collected by continuous pumping through charcoal filters at six of these locations. Nine of the twelve locations are indicators and three are controls (D-1, D-2, and 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 from six locations (D-2, D-5, D-7, D-8, D-11 and D-1 5) are analyzed weekly for iodine-131.
Ambient gamma radiation is monitored at twelve air sampling locations. In addition, gamma radiation is monitored at thirty-four special locations: eighteen in a circle within a 0.5 mi. radius of the DAEC stack; six in 22.58 sectors within I mi. of the DAEC stack; and ten in 22.5° sectors between I and 3 miles of the DAEC stack. Two TLDs are placed at each location and are exchanged and analyzed quarterly.
Precipitation is collected monthly from one location and analyzed for gamma-emitting isotopes.
Quarterly composites are analyzed for tritium.
Milk samples were collected monthly from four locations during the non-grazing season, October through April, and biweekly during the grazing season, May 1 through September 30.
One location (D-108) is a control, the rest are indicators. All 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 seven locations: one control (D-108) and six indicators (D-16, D-57, D-58, D-72, D-96, and D-109). Grain, hay and broad leaf (green leafy) vegetation samples are analyzed for gamma-emitting isotopes and at least one broad leaf vegetation is analyzed for iodine-131. If cattle are slaughtered for home use, a meat sample is collected annually, during or immediately following a grazing period from animals grazing on-site.
The sample is analyzed for gamma-emitting isotopes. Also, potable ground water is collected quarterly from a treated municipal water system (D-53), the inlet to the municipal water treatment system (D-54) and four additional ground water locations (D-55, D-57, D-58, and D-72). The samples are analyzed for gross beta and tritium. If gross beta activity exceeds ten times the yearly mean of the control samples, gamma isotopic, strontium-89 and strontium-90 analyses are performed.
4
Program Description (continued)
Soil samples are collected once per year at two indicator locations (D-15 and D-16). The samples are analyzed for strontium-90 and gamma-emitting isotopes.
Surface water is collected monthly from five river, pond and sewage effluent locations, one control (D-49) and four indicators (D-50, D-51, D-99, and D-107). All monthly samples are analyzed for gamma-emitting isotopes. Tritium analyses are performed on quarterly composites from each location. In addition, samples from Location D-107 (plant sewage discharge) are analyzed for potassium (ICP analysis).
The aquatic environment is also monitored by upstream and downstream (D-49 and D-61) semiannual collections of fish. River bottom sediment is also collected semiannually at the plant's intake and discharge (D-50 and D-51) and downstream of the sewage plant (D-107). The samples are analyzed for gamma-emitting isotopes.
3.3 Program Execution The program was executed as described in the preceding section with the following exceptions.
In no instance did missed analyses affect the minimum sampling requirements as specified in the ODAM.
(1)
Milk:
Milk was not available from location D-101, January through May, November and December of 2003. Goats were dry.
(2)
Air particulates / Air Iodine:
No AP/AI sample was available at location D-15 for the week ending June 5, 2003. No power was available at the sampler site.
No AP/AI sample was available at location D-7 for the week ending June 19, 2003. Power was not available at the sampler site.
5
3.4 Laboratory Procedures The iodine-131 analyses in milk were made using a sensitive radiochemical procedure involving separation of the iodine using an ion-exchange method, solvent extraction and subsequent beta counting.
Gamma-spectroscopic analyses were performed with HPGe detectors. Levels of iodine-131 in vegetation were determined by gamma spectroscopy. Concentrations of airborne iodine-131 in charcoal samples were also determined by gamma spectroscopy.
Tritium was determined by liquid scintillation.
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, 2003 ). The QA Program includes participation in Interlaboratory Comparison (crosscheck) Programs.
Results obtained in crosscheck programs are presented in Appendix A.
3.5 Program Modifications A new indicator location (D-109) was added to the environmental monitoring program in 2003.
Milk and vegetation samples were collected from the Beatty farm (3.6 mi. SW); first collection, January, 2003.
6
4.0 RESULTS AND DISCUSSION All collections and analyses were made as scheduled, except for the listing 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.
The tabulated results of all measurements are not included in this section, although references to these results will be made in the discussion. A complete tabulation of results for 2003 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 atmospheric nuclear tests in 2003.
4.2 Program Findings Results obtained show background levels of radioactivity in the environmental samples collected In 2003.
Airborne Particulates The average annual gross beta concentrations in airborne particulates were identical at both indicator and control locations (0.029 pCVm 3) and similar to levels observed from 1988 through 2002. The results are tabulated below.
Year j Indicators jControls Year Indicators Controls Concentration ( pCi/M3)
Concentration ( pCVm 3) 1988 0.026 0.028 1996 0.024 0.023 1989 0.026 0.029 1997 0.023 0.023 1990 0.022 0.024 1998 0.024 0.024 1991 0.023 0.022 1999 0.026 0.027 1992 0.022 0.023 2000 0.026 0.027 1993 0.022 0.023 2001 0.026 0.026 1994 0.023 0.024 2002 0.027 0.027 1995 0.025 0.024
=
2003 0.029 0.029 L__
I I Z...
_L Average annual gross beta concentrations in airborne particulates.
Gamma spectroscopic analysis of quarterly composites of air particulate filters yielded similar results for indicator and control locations. Beryllium-7, which is produced continuously in the upper atmosphere by cosmic radiation (Arnold and Al-Salih, 1955), was detected in all samples.
All other gamma-emitting isotopes were below their respective LLD limits. No effect from plant operation is indicated.
7
Airborne Iodine Weekly levels of airborne iodine-131 were below the lower limit of detection (LLD) of 0.07 pCi/m3 in all samples.
Ambient Radiation (TLDs)
At twelve air sampling locations, the TLD readings averaged 17.3 and 15.4 mRlquarter for indicator and control locations, respectively. At locations within a half mile, one mile and three mile radius of the stack, measurements averaged 18.3 mR/quarter, 19.6 mR/quarter and 16.5 mR/quarter, respectively. The average for all locations was 17.7 mR/quarter. This is lower than 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.
Precipitation Concentration of tritium in precipitation was below the LLD of 330 pCi/L in all samples. No gamma-emitting isotopes were detected. No plant effect is indicated.
Milk lodine-1 31 results were below the detection limit of 1.0 pCi/L in all samples.
No gamma-emitting isotopes, except naturally occurring potassium-40, were detected in any milk samples. This is consistent with the finding of the National Center for Radiological Health 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).
In summary, milk data for 2003 show no radiological effects of plant operation.
Ground Water The annual mean for gross beta activity measured 3.5 pCVL, similar to levels observed from 1988 through 2002. The location with the highest mean (6.1 pCIL) was D-58, a farm 1.0 mile distant from the plant. Tritium activity measured below the LLD of 330 pCiYL in all samples. No effect from plant operation is indicated.
Vegetation lodine-131 concentrations in broadleaf vegetation were below the LLD level of 0.24 pCig wet weight in all samples.
Except for potassium-40, which was observed in all vegetation samples ( broadleaf, grain, and forage ), all other gamma-emitting isotopes were below detection limits. No effect from plant operation is indicated.
8
Soil Strontium-90 was not detected in soil samples above the LLD level of 0.028 pCVg dry weight.
Cesium-137 activity averaged 0.14 pCVg dry weight. Both strontium-90 and cesium-137 activities are similar to or less than levels observed from 1988 through 2002, these levels are generally attributable to deposition of fallout from previous decades.
Naturally-occurring potassium-40 averaged 10.75 pCi/g dry weight. No effect from the plant operation is indicated.
Surface Water Concentrations of tritium measured below the LLD level of 330 pCVL in all samples. All gamma-emitting isotopes were below their respective LLDs.
Potassium-40 was measured at one location, D-107 (sewage effluent). The concentration ranged from 16.4 to 34.6 pCVL and averaged 22.5 pCVL.
No plant effect on surface water is indicated.
Fish All gamma-emitting isotopes, except naturally-occurring potassium-40, in edible portions were below detection limits. The potassium-40 level was similar at both indicator and control locations (2.93 and 3.10 pCVg wet, respectively). No plant effect on fish is indicated.
River Sediments River sediments were collected in May and September, 2003, and analyzed for gamma-emitting isotopes. Cs-1 37 was detected in samples from both the upstream and downstream locations at a concentration of 0.056 and 0.057 pCVg dry weight, respectively. Potassium-40 activity ranged from 7.16 - 10.79 pCVg dry weight and averaged 9.31 pCVg dry weight.
All other gamma-emitting isotopes were below detection limits.
9
5.0 TABLES AND FIGURES 10
Table 5.1 Characteristic properties of isotopes quantified in gamma-spectroscopic analyses.
J Designation Comment Isotope Half-lifea I. Naturally Occurring A. Cosmogenic Produced by interaction of cosmic Be-7 53.2 d rays with atmosphere B. Terrestrial Primordial K-40 1.26 x 109 y
- 11. Fission Productsb Nuclear detonations constitute the major environmental source A. Short-lived 1-131 8.04d Ba-140 12.8 d B. Other than Short-lived Nb-95 35.15 d Zr-95 65 d Ru-103 39.35 d Ru-1 06 368.2 d Cs-1 34 2.061 y Cs-137 30.174 y Ce-141 32.5 d Ce-144 284.31 d 1ll. Activation Products Typically found in nuclear power plant Mn-54 312.5 d effluents Fe-59 45.0 d Co-58 70.78 d Co-60 5.26 y Zn-65 245 d a Half-lives are taken from Appendix E of Environmental Quarterly. 1 January 1978. EML-334 (U. S. Department of Energy. 1978).
b Includes fission-product daughters.
11
Table 5.2 Sample collection and analysis program.
Sampling Location Exposure Pathway and/or Sample Description Sampling and Collection Type and Frequency Sample Type Point Frequency of Analysis" Airborne 1
Cedar Rapids (C)
Continuous operation of Analyze for gross beta activity Particulates 2
Marion (C) sampler with sample more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after filter 3
Hiawatha collection at least once per change. Perform gamma 5
Palo week or as required by dust isotopic analysis on each sample 6
Center Point loading having gross beta activity greater 7
Shellsburg than ten times the yearly mean 8
Urbana of the control samples.
10 Atkins 11 Toddville Composite weekly samples to 13 Albumett (C) form a quarterly composite (by 15 On-site North location). Analyze quarterly 16 On-site South composite for gamma isotopic.
Airborne Iodine 2 Marion (C)
Continuous operation of Analyze each cartridge for 5
Palo sampler with sample iodine-131.
7 Shellsburg collection at least once per 8
Urbana week.
11 Toddville 15 On-site North Ambient 1-2 (C) Air Particulate Two dosimeters Read gamma radiation dose Radiation 3, 5-8 Locations continuously at each quarterly.
10, 11 location. Both dosimeters 13 (C) are changed at least 15, 16 quarterly.
17-23, s 0.5 mi. of Stack 28-32, 82-86, 91 43-48 s 1.0 mi. of Stack 33-42 s 3.0 mi. of Stack Surface Water 49 Lewis Access (C)
Once per month.
Gamma isotopic analyses of 50 Plant Intake (C) each sample (by location).
51 Plant Discharge 99 Pleasant Creek Composite monthly samples to 107 Plant Sewage form quarterly composite (by Dischange location). Analyze quarterly composite for tritium.
(C) denotes control location. All other locations are Indicators.
12
Table 5.2 Sample collection and analysis program, (continued).
Sampling Location Exposure Pathway and/or Sample Description Sampling and Collection Type and Frequency Sample Type Point Frequency of Analysis' Ground 53 Treated Municipal Grab sample at least Gross beta and tritium activity Water Water once per quarter analysis on quarterly sample.
(potable) 54 Inlet to Municipal If gross beta is greater than Water Treatment ten times the yearly mean of System control samples, perform gamma isotopic and Sr-89 and 55 On-site well Sr-90 analyses.
57, 58 Wells off-site and 72 within 4 km of DAEC River 50 Plant Intake (C)
At least once every Gamma isotopic analysis of each Sediment 51 Plant Discharge six months.
sample.
107 Sewage Effluent Canal (on-site)
Vegetation 16, 57 Farms that raise food Annually at harvest Gamma isotopic analysis of 58, 72, crops time. One sample of edible portions.
94, 96, each: grain, green 109 leafy, and forage. At 1-131 analysis on broadleaf least one sample vegetation.
108 (C) should be broadleaf vegetation.
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 July (C) and once during Downstream of DAEC August through 61 in influence of effluent December).
Milkb 108 (C) Control Farm At least once per two Durina the grazing season:
weeks during the Gamma isotopic and iodine-131 grazing season.
analyses of each sample.
96,101 Dairy Farms within 10 At least once per Durina the non-arazing season:
109 miles of Site month during the Gamma isotopic and iodine-131 non-grazing season.
analyses of each sample.
(C) denotes control location. All other locations are indicators.
13
Table 5.2 Sample collection and analysis program, (continued).
Sampling Location Exposure Pathway and/or Sample Description Sampling and Collection Type and Frequency Sample Type Point Frequency of Analysis' Precipitation On-site Monthly Gamma isotopic on all samples.
Tritium on quarterly composites.
MeatC On-site Annually Gamma Isotopic Soil 15,16 On-site Annually Gamma Isotopic and Sr-90.
a Gamma isotopic analysis and analysis for gamma-emitting nuclides refer to high resolution gamma ray spectrum analysis. Any radionuclide detected at a concentration greater than the lower limit of detection (LLD) should be reported quantitatively; conversely, any radionuclide concentration less than the LLD should not be reported.
b The grazing season is considered to be May 1 through September 30.
c Meat was not collected in 2003; no animals slaughtered for home use.
14
Table 5.3 Sampling locations, Duane Arnold Energy Center.
Sampling Location Code Type Sampling Location Description Distance and Direction Point from Site Stack D-1 D-2 D-3 D-5 D-6 D-7 D-8 D-10 D-11 D-13 D-15 D-16 D-17 D-1 8 D-19 D-20 D-21 D-22 D-23 D-28 D-29 D-30 D-31 D-32 D-33 D-34 D-35 D-36 D-37 D-38 D-39 D-40 D-41 D-42 D-43 D-44 D-45 D-46 C
C C
I 2
3 5
6 7
8 10 11 13 15 16 17 18 19 20 21 22 23 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 Cedar Rapids Marion Hiawatha Palo Center Point Shellsburg Urbana Atkins Toddville Albumett On-site, Northwest On-site, South On-site, N On-site, NNE On-site, NE On-site, ENE On-site, ENE On-site, E On-site, ESE On-site, WSW On-site, W On-site, WNW On-site, NW On-site, NNW 3 miles N 3 miles NNE 3 miles NE 3 miles ENE 3 miles E 3 miles ESE 3 miles SE 3 miles SSE 3 miles S 3 miles SSE 1 mile SSw 1 mile WSW I mile W I mile WNW 11 mi @ 135° 11 mi @1250 7 mi @ 130° 3 mi @ 2000 7mi@0 0 6mi@255 0 10 mi @ 345° 9 mi@ 210° 4 mi @ 90' 9 mi @ 70' 0.5 mi @ 3050 0.5 mi @ 1900 0.5 miN 0.5 miNNE 0.5 mi NE 0.5 mi ENE 0.5 mi ENE 0.5 miE 0.5 mi ESE 0.5 mi WSW 0.5 miW 0.5 mi WNW 0.5 mi NW 0.5 mi NNW 3.0 mi N 3.0 mi NNE 3.0 miNE 3.0 mi ENE 3.0 mi E 3.0 mi ESE 3.0 mi SE 3.0 mi SSE 3.0 miS 3.0 mi SSE 1.0 mi SSW 1.0 mi WSW 1.0 miW 1.0 miWNW SE ESE SE SSW N
W NW SSW E
ENE NW SSE 15
Table 5.3 Sampling locations, Duane Arnold Energy Center (continued).
Sampling Location Code Type Sampling Location Description Distance and Direction Point from Site Stack D-47 47 1 mile WNW 1.0 miWNW D-48 48 1 mile NW 1.0 mi NW D-49 C
49 Lewis Access, upstream of DAEC 4.0 mi NNW D-50 C
50 Plant Intake D-51 51 Plant Discharge D-53 53 Treated Municipal Water D-54 54 Inlet, Municipal Water Treatment System D-55 55 On-site Well D-57 57 Farm (Off-site Well) 1.0 mi WSW D-58 58 Farm (Off-site Well) 0.5 mi WSW-SW D-61 61 0.5 mi downstream of plant discharge D-72 72 Farm 2.0 mi SSW D-82 82 On-site, SE 0.5 mi SE D-83 83 On-site, SSE 0.5 mi SSE D-84 84 On-site, S 0.5 mi S D-85 85 On-site, SSW 0.5 mi SSW D-86 86 On-site, SW 0.5 mi SW D-91 91 On-site, N 0.5 mi N D-94 94 Farm 2.7 mi N D-96 96 Farm 8.0 mi SSW D-99 99 Pleasant Creek Lake 2.5 mi WNW D-101 101 Farm 4.0 mi E D-106 106 Farm 4.5 mi SE D-107 107 Sewage Effluent Canal On-site D-108 C
108 Farm 17.3 mi. SW D-109 109 Farm 3.6 mi. SW "C" denotes control location. All other locations are indicators.
16
Table 5.4 Type and Frequency of collection.
Location D-1 D-2 D-3 D-5 D-6 D-7 D-8 D-1 0 D-11 D-13 D-15 D-16 D-17 to D-23 D-28 to D-42 D-43 to D-48 D-49 D-50 D-51 D-53 D-54 D-55 D-57 D-58 D-61 D-63 D-72 D-82 to D-86 D-91 D-94 D-96 D-99 D-101 D-106 D-107 D-108 D-109 On-site Location Type Weekly Monthly C
C AP AP, Al AP AP, Al AP AP, Al AP, Al AP AP, Al AP AP, Al AP Quarterly TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD Semiannually Annually C
SO SO, G C
RS RS G
G F
M WW G
G TLD TLD G
M SW M
M SW M
M P
G RS C
G G
ME "C" denotes control location. All other locations are indicators.
17
Table 5.5. Sample codes used in 5.4.
Code Description AP Airborne Particulates Al Airborne Iodine TLD Thermoluminescent Dosimeter P
Precipitation M
Milk WW Well Water G
Vegetation ME Meat SO Soil SW Surface Water F
Fish BS River Sediment 18
Table 5.6. Missed collections and analyses, Duane Arnold Energy Center.
Sample Collection Date Type Analysis Location(s) or Period Comments ml 1-131. Gamma D-1 01 01-02-03 Sample not available; goat dry.
Ml 1-131, Gamma D-101 02-04-03 Sample not available; goat dry.
Ml 1-131, Gamma D-101 03-04-03 Sample not available; goat dry.
Ml 1-131, Gamma D-101 04-01-03 Sample not available; goat dry.
Ml 1-131, Gamma D-101 05-06-03 Sample not available; goat dry.
AP/AI Gross Beta, D-1 5 06-05-03 No power to sampler.
1-131 AP/AI Gross Beta, D-07 06-19-03 No power to sampler, run-time 1-131 only 21.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
Ml 1-131, Gamma D-101 11-14-03 Sample not available; goat dry.
Ml 1-131, Gamma D-101 12-02-03 Sample not available; goat dry.
In no instance did missed analyses affect minimum sampling requirements as specified in the ODAM.
19
Table 5.7 Radiological Environmental Program Summary.
Name of Facility Location of Facility Duane Arnold Energy Center Llnn. Iowa (County. State)
Docket No.
Reporting Period 50-331 January-December, 2003 Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)
Mean (F)c Routine (Units)
Analysesa Rangec Locationo Rangec Range' Results' Airbome GB 622 0.002 0.029 (466/466)
D-1, Cedar Rapids 0.029 (52/52) 0.029 (156/156) 0 Particulates (0.006-0.054) 11 mi. SE (0.018-0.045)
(0.013-0.053)
(pCi/m")
GS 48 Be-7 0.020 0.069 (36/36)
D-7, Shellsburg 0.078 (414) 0.071 (12/12) 0 (0.044-0.099) 6 mi. W (0.050-0.097)
(0.042-0.102)
Nb-95 0.0018
< LLD
<LLD 0
Zr-95 0.0025
< LLD
< LLD 0
Ru-103 0.0014
< LLD
< LLD 0
Ru-1 06 0.0099
< LLD
< LLD 0
Cs-134 0.0009
< LLD
< LLD 0
Cs-137 0.0058
< LLD
< LLD 0
Ce-141 0.0025
< LLD
< LLD 0
Ce-144 0.0054
< LLD
<LID 0
Airbome Iodine 1-131 310 0.030
< LLD
< LLD 0
(pCI/mi)
TLD, AP Locations Gamma 48 1.0 17.3 (36/36)
D-8, Urbana 20.9 (414) 15.4 (12/12) 0 (mR/quarter)
(13.1-23.0) 10 mi. NW (17.9-23.0)
(10.2-18.5)
TLD, within 0.5 mi. of Stack Gamma 72 1.0 18.3 (72/72)
D-31. On-site 22.6 (414)
None 0
(mR/quarter)
(14.4-24.8) 0.5 mi. NW (20.2-24.8)
TLD, within 1.0 mi. of Stack Gamma 24 1.0 19.6 (24/24)
D-48, 22.1 (4/4)
None 0
(mR/quarter)
(14.3-24.1) 1 ml. NW (20.6-24.1)
TLD. within 3.0 mi. of Stack Gamma 40 1.0 16.5 (40/40)
D-37, 21.1 (4/4)
None 0
(mR/quarter)
(12.8-23.6) 3 mi.E (18.4-23.6)
Precipitation (pCVL)
H-3 4
330
GS 12 Mn-54 7.3
Fe-59 13.7
Co-58 5.2
Co-60 5.5
Zn-65 14.6
< LLD
< LLD 0
Nb-95 10.1
< LLD
< LLD 0
20
Table 5.7 Radiological Environmental Program Summary.
Name of Facility Location of Facility Duane Arnold Energy Center Linn, Iowa (County, State)
Docket No.
Reporting Period 50-331 January-December. 2003 Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)'
Mean (F)'
Mean (F)'
Routine (Units)
Analyses' Range' Location0 Range' Range' Results' Precipitation Zr-95 12.6
< LLD
< LLD 0
(pCi/L) 1-131 14.8
< LLD
< LLD 0
(continued)
Cs-134 7.8
< LLD
< LLD 0
Cs-137 6.6
< LLD
< LLD 0
Ba-140 44.6
< LLD
< LLD 0
La-140 10.1
< LLD
< LLD 0
Milk (pCi/L) 1-131 65 1.0
< LLD
< LLD 0
GS 65 K-40 100 1468 (47/47)
D-101, Farm 1684 (11/11) 1406 (18/18) 0 (1158-1982) 4 mi. E (1441-1982)
(1128-1814)
Cs-134 15
< LLD
< LLD 0
Cs-137 18
< LLD
< LLD 0
Ba-140 60
< LLD
< LLD 0
La-140 15
< LLD
< LLD 0
Ground Water GB 24 1.1 3.5 (17/24)
D-58, Farm 6.1 (414)
None 0
(pCiL)
(1.2-7.0) 1 mi. WSW-SW (5.3-7.0)
H-3 24 330
< LLD
< LLD 0
Broadleaf 1-131 5
0.24
< LLD
< LLD 0
Vegetation (pCVg wet)
GS 5
K40 0.5 11.90 (4/4)
D-96, Farm 20.58 (1/1) 16.38 (1/1) 0 (4.13-20.58) 8 mi. SSW Mn-54 0.11
< LLD
< LLD 0
Co-58 0.082
< LLD
< LLD 0
Co-60 0.14
< LLD
< LLD 0
Nb-95 0.14
< LLD
< LLD 0
Zr-95 0.20
< LLD
< LLD 0
Ru-103 0.14
< LLD
< LLD 0
Ru-106 1.03
< LLD
< LLD 0
Cs-134 0.13
< LLD
< LLD 0
Cs-137 0.15
< LLD
< LLD 0
Ce-141 0.21
< LLD
< LLD 0
Ce-144 0.73
< LD
< LLD 0
21
Table 5.7 Radiological Environmental Program Summary.
Name of Facility Location of Facility Duane Arnold Energy Center Linn. Iowa (County. State)
Docket No.
Reporting Period 50-331 January-December. 2003 Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LIDb Mean (F)c Mean (F)'
Mean (F)'
Routine (Units)
Analysesa Range' Locationc Range' Rangec Results' Vegetation GS 13 (Grain)
K-40 0.5 8.48 (11/11)
D-109. Farm 17.10 (212) 11.53 (2/2) 0 (pCilg wet)
(2.32-31.41) 3.6 mi. SW (2.79-31.41)
(2.88-20.17)
Mn-54 0.027
< LLD
< LLD 0
Co-58 0.037
< LLD
< LLD 0
Co-60 0.024
< LLD
< LLD 0
Nb-95 0.032
< LLD
< LLD 0
Zr-95 0.044
< LLD
< LLD 0
Ru-1 03 0.035
< LLD
< LLD 0
Ru-106 0.34
< LLD
< LLD 0
Cs-134 0.038
< LLD
< LLD 0
Cs-137 0.030
< LLD
< LLD 0
Ce-141 0.062
< LLD
< LLD 0
Ce-144 0.19
< LLD
< LLD 0
Soil Sr-90 2 0.028
< LLD None 0
(pCi/gwet)
GS 2
K-40 0.5 10.75 (212)
D-15, On-site 12.96 (1/1)
None 0
(8.54-12.96) 0.5 mi. NW Mn-54 0.015
< LLD None 0
Fe-59 0.037
< LLD None 0
Co-58 0.013
< LLD None 0
Co-60 0.015
< LLD None 0
Zn-65 0.048
< LLD None 0
Nb-95 0.028
< LLD None 0
Zr-95 0.017
< LLD None 0
Ru-1 03 0.020
< LLD None 0
Ru-106 0.16
< LLD None 0
Cs-1 34 0.024
< LLD None 0
Cs-137 0.060 0.14 (2/2)
D-15, On-site 0.14 (1/1)
None 0
(0.13-0.14) 0.5 mi. NW Ce-141 0.049
< LLD None 0
Ce-144 0.15
< LLD None 0
22
Table 5.7 Radiological Environmental Program Summary.
Name of Facility Location of Facility Duane Arnold Energy Center Docket No.
Reporting Period 50-331 Llnn, Iowa (County, State)
January-December. 2003 Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)'
Mean (F)'
Mean (F)c Routine (Units)
Analyses" Range' Location0 Range' Range' Results" Surface Water H-3 20 330
< LLD
< LLD 0
(pCVL)
K40 12 0.5 22.5 (12/12)
D-107, Onsite 22.5 (12/12)
None 0
(16.4-34.6)
Sewage Effluent (16.4-34.6) 0 1-131 12 15
< LLD
< LLD 0
GS 12 Mn-54 15
< LLD
< LLD 0
Fe-59 30
< LLD
< LLD 0
Co-58 15
< LLD
< LLD 0
Co-60 15
< LLD
< LLD 0
Zn-65 30
< LLD
< LLD 0
Nb-95 15
< LLD
< LLD 0
Zr-95 30
< LLD
< LLD 0
Cs-134 15
< LLD
< LLD 0
Cs-137 15
< LLD
< LLD 0
Ba-140 60
< LLD
< LLD 0
La-140 15
< LLD
< LLD 0
Sediments GS 6
(pCVg dry)
K-40 1.0 9.60 (4/4)
D-107, Sewage 10.70 (2/2) 8.73 (2/2) 0 (7.16-10.79)
Effluent Canal (10.60-10.79)
(7.53-9.93)
Mn-54 0.026
< LLD
< LLD 0
Fe-59 0.070
< LLD
< LLD 0
Co-58 0.043
< LLD
< LLD 0
Co-60 0.029
< LLD
< LLD 0
Zn-65 0.077
< LLD
< LLD 0
Nb-95 0.060
< LLD
< LLD 0
Zr-95 0.072
< LLD
< LLD 0
Ru-103 0.050
< LLD
< LLD 0
Ru-106 0.24
< LLD
< LLD 0
Cs-134 0.042
< LLD
< LID 0
Cs-137 0.045 0.057 (114)
D-51.
0.057 (1/1) 0.056 (1/1) 0 Plant Discharge Ce-141 0.095
< LLD
< LLD 0
Ce-144 0.17
< LLD
<LID 0
23
Table 5.7 Radiological Environmental Program Summary.
Name of Facility Location of Facility Duane Arnold Energy Center Linn. Iowa (County, State)
Docket No.
Reporting Period 50-331 January-December. 2003 Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)
Mean (F)'
Mean (F)c Routine (Units)
Analyses' Range' Location0 Range' Range Results' Fish GS 8
(pCi/g wet)
K-40 1.0 2.93 (4/4)
D-49, Upstream 3.10 (414) 3.10 (4/4) 0 (2.70-3.15) 4 mi. NNW (2.70-3.40)
(2.70-3.40)
Mn-54 0.049
< LLD
< LLD 0
Fe-59 0.059
< LLD
< LLD 0
Co-58 0.045
< LLD
< LLD 0
Co-60 0.045
< LLD
< LLD 0
Zn-65 0.087
< LLD
< LLD 0
Nb-95 0.083
< LLD
< LLD 0
Zr-95 0.102
< LLD
< LLD 0
Ru-103 0.064
< LLD
< LLD 0
Ru-106 0.36
< LLD
< LLD 0
Cs-134 0.055
< LLD
< LLD 0
Cs-137 0.048
< LLD
< LLD 0
Ce-141 0.080
< LLD
< LLD 0
Ce-144 0.28
< LLD
< LLD 0
aGB = Gross beta; GS = Gamma spectroscopy b LLD = Nominal lower limit of detectionbased on 4.66 sigma counting error for the background sample.
c 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 exced 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 Required LLDs for 1-131, Cs-134 and Cs-137 (<0.060, <0.060 and <0.080 pCi/g wet, respectively) could not be achieved for two samples, due to low sample weight (<25 grams wet).
24
Figure 5.1 Radiological Environmental Monitoring Program Sampling Stations near the Duane Arnold Energy Center.
Refer to Table 5.3 for sampling locations and Table 5.4 for Type and Frequency of collection.
25
Figure 5.2 Radiological Environmental Monitoring Program Sampling Stations Outside 0.5 miles from the Duane Arnold Energy Center Refer to Table 5.3 for sampling locations and Table 5.4 for Type and Frequency of collection.
26
6.0 REFERENCES
CITED Arnold, J. R. and H. A. Al-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 and 276.
Environmental, Inc., Midwest Laboratory. 2001 - 2003. Environmental Radiological Monitoring Program for the Duane Arnold Energy Center, Annual Report - Part II, Data Tabulations and Analyses, January - December, 2001 - 2003.
2003.
Quality Assurance Program Manual, Rev. 1, 21 October 2003.
2001.
Quality Control Procedures Manual, Rev. 0, 21 September 2000.
2003.
Quality Control Program, Rev. 1, 21 August 2003.
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.
Hazleton Environmental Sciences.
1982 - 1984. Environmental Radiation Monitoring for the Duane Arnold Energy Center, Annual Report - Part II, Data Tabulations and Analyses, January -
December 1981 - 1983.
Hohenemser, C. M. Deicher, A. Ernst, H. Hofsass, G. Lindner, E. Racknagel.
1986.
'Chernobyl,"
Chemtech, October 1986, pp. 596-605.
National Center for Radiological Health, 1968. Radiological Health and Data Reports, Vol. 9, Number 12, 730-746.
Teledyne Brown Engineering Environmental Services, Midwest Laboratory. 1984 - 2000. Environmental Radiological Monitoring Program for the Duane Arnold Energy Center, Annual Report - Part II, Data Tabulations and Analyses, January - December, 1983 - 1999.
Wilson, D. W., G. M. Ward and J. E. Johnson. 1969. In Environmental Contamination by Radioactive Materials, International Atomic Energy Agency. p.125.
27
Environmental, hc.
Mdwest Laboratory an Pl4sheny Tecthncdoges Co.
?WLwid.tr~
- MUtWbboec.lL 0=2-(541) 5840700 fat (847) 584-4517 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, 2003 through December, 2003
Appendix A Interlaboratory Comparison Program Results Environmental, Inc., Midwest Laboratory, formerly Teledyne Brown Engineering Envirorimental Services 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.
The results in Table A-2 were obtained for Thermoluminescent Dosimeters (TLDs), via International Intercomparison of Environmental Dosimeters under the sponsorships listed in Table A-2. Results of internal laboratory testing is also listed.
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. request.
Table A-5 list results of the in-house "duplicatet program for the past twelve months. Acceptance is based on the difference of the results being less than the sum of the errors. Data for previous years available upon request The results in Table A-6 were obtained through participation in the Mixed Analyte Performance Evaluation Program.
The results in Table A-7 were obtained through participation in the Environmental Measurement Laboratory Quality Assessment Program.
Attachment A lists acceptance criteria for 'spiked" samples.
Out-of-limit results are explained directly below the result.
Al
Attachment A ACCEPTANCE CRITERIA FOR OSPIKED' SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSES3 One standard deviation Analysis Level for single determination Gamma Emitters 5 to 100 pCilliter or kg 5.0 pCifliter
> 100 pCi/liter or kg 5% of known value Strontium-89b 5 to 50 pCi/liter or kg 5.0 pCi/liter
> 50 pCi/liter or kg 10% of known value Strontium.90b 2 to 30 pCi/liter or kg 5.0 pCi/liter
> 30 pCi/liter or kg 10% of known value Potassium-40
> 0.1 gAiter or kg 5% of known value Gross alpha 20 pCi/liter 5.0 pCi/liter
> 20 pCi/liter 25% of known value Gross beta 100 pCi/liter 5.0 pCi/liter
> 100 pCi/liter 5% of known value Tritium 4,000 pCi/liter Is = (pCi/liter) =
169.85 x (known)0 0 93 3
> 4,000 pCi/liter 10% of known value Radium-226,-228 0.1 pCi/liter 15% of known value Plutonium 0.1 pCi/liter, gram, or sample 10% of known value Iodine-131, 55 pCi/liter 6.0 pCi/liter Iodine-129b
> 55 pCi/liter 10% of known value Uranium-238, 35 pCi/liter 6.0 pCi/liter Nickel_63b
> 35 pCi/liter 15% of known value Technetium-99b Iron-55b 50 to 100 pCi/liter 10 pCi/liter
> 100 pCi/liter 10% of known value Othersb 20% of known value
' From EPA publication. Environmental Radioactivity Laboratory Intercomparlson Studies Program. Fiscal Year. 1981-1982, EPA-60014-81-004.
b Laboratory limit.
A2
TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.
Concentration (pCi/L)
Lab Code Date Analysis Laboratory ERA Control Resultb Result' Limits STW-973 STW-973 STW-974 STW-974 STW-974 STW-974 STW-974 STW-975 a STW-975 STW-976 STWt-976 STW-976 02117/03 02/17103 02/17/03 02/17/03 02/17/03 02/17/03 02117103 02117/03 02/17103 02/17/03 02t17/03 02/17/03 Sr-89 Sr-90 Ba-1 33 Co-60 Cs-134 Cs-137 Zn-65 Gr. Alpha Gr. Beta Ra-226 Ra-228 Uranium 17.0 + 0.5 8.9 +/- 0.3 14.5 +/- 0.9 37.5 +/- 0.9 18.2 +/- 0.6 42.7 +/-1.0 56.8 +/- 2.2 18.4 +/-0.3 11.7 +/- 0.5 4.1 +/- 0.1 7.6 +/- 0.5 52.9 +/- 1.9 15.9 +/- 5.0 9.0 +/- 5.0 19.5 +/- 5.0 37.4 +/- 5.0 17.8 +/- 5.0 44.2 +/- 5.0 60.3 +/- 6.0 37.6 +/- 9.4 8.6 +/- 5.0 4.7 +/- 0.7 6.5 +/- 1.6 53.7 +/- 5.4 7.2 - 24.6 0.4 - 17.7 10.8 - 28.2 28.7 - 46.1 9.1 - 26.5 35.5 - 52.9 49.9 - 70.7 21.3 - 53.9 0.0 - 17.2 3.5 - 6.0 3.7 - 9.3 44.4 - 63.0 STW-983 S1W.984 STW-985 STW-985 STW-985 STW-985 STW-986 STW-986 '
STW-986 STW-986 STW-986 STW-986 STW-988 STW-988 S1W-988 STW-989 STW-989 STW-989 STW-989 STW-989 STW-990 STW-990 I STW-991 STW-991 05/19/03 05/19103 05/19/03 05/19/03 05/19103 05/19103 05/19103 05/19/03 05/19/03 05/19103 05/19/03 05/19/03 08/18/03 08/18/03 08/18/03 08/18/03 08/18/03 08/18/03 08/18/03 08/18103 08/18/03 08/18/03 08/18/03 08118103 H-3 1-131 Gr. Alpha Ra-226.
Ra-228 Uranium Co-60 Cs-I 34 Cs-137 Gr. Beta Sr-89 Sr-90 Ra-226 Ra-228 Uranium Ba-133 Co-60 Cs-134 Cs-I 37 Zn-65 Gr. Alpha Gr. Beta Sr-89 Sr-90 1290.0 +/- 25.0 19.7 +/- 1.3 54.4 +/- 3.0 14.9 +/- 0.2 13.1 +/-0.6 14.5 +/-0.4 56.9 +/- 8.6 61.6 +/-6.6 143.0 +/- 1.2 309.0 +/- 2.7 33.1 +/- 0.2 28.8 +/- 1.3 13.3 +/- 1.1 11.5 +/- 1.0 12.3 +/- 0.4 18.1 +/-1.9 35.9 +/- 1.3 32.6 +/- 1.8 48.3 +/-0.6 58.9 +/- 2.1 41.8 +/-3.4 51.3 +/- 3.0 57.2 +/-4.3 21.2 +/- 0.9 1250.0 +/- 331.0 20.8 +/- 3.0 70.3 +/- 17.6 16.5 +/- 2.5 10.3 +/-2.6 15.1 +/-3.0 63.8 +/- 5.0 75.7 +/- 5.0 150.0 +/- 7.5 363.0 +/- 54.5 31.3 +/- 5.0 27.4 +/- 5.0 13.4 +/- 2.0 12.5 +/- 3.1 11.4 +/-3.0 20.7 +/- 5.0 37A +/- 5.0 32.6 +/- 5.0 44.3 +/- 5.0 60.2 +/- 6.0 56.2 +/- 16.3 31.6 +/- 5.0.
58.8 +/- 5.0 20.6 +/- 5.0 678.0 - 1820.0 15.6 - 26.0 39.9 - 101.0 12.2 - 20.8 5.8 - 14.8 9.9 - 20.3 55.1 - 72.5 67.0 - 84.4 137.0 - 163.0 269.0 - 457.0 22.6 - 40.0 18.7 - 36.1 9.9 - 16.9 7.1 - 17.9 6.2 - 16.6 12.0 - 29.4 28.7 - 46.1 23.9 - 41.3 35.6 - 53.0 49.8 - 70.6 36.9 - 93.3 22.9 - 40.3 50.1 - 67.5 11.9 - 29.3 AI-I
TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)'.
Concentration (pCUL)
Lab Code Date Analysis Laboratory ERA Control ResultO Result' Limits STW-997 S1W-997 STW-998 S1W-999 STW-999 STW-999 STW-1000 STW-1001 STW-1001 STW-1001 STW-1001 STW-1002 STW-1002 STW-1002 STW-1002 STW-1002 STW-1002 11/18/03 11/16/03 11/18/03 11/18103 11118103 11/18/03 11/18/03 11/18/03 11/18/03 11/18/03 11/18/03 11/18/03 11/18/03 11/18/03 11/18/03 11/18/03 11/18/03 Gr. Alpha Gr. Beta 1-131 Ra-226 Ra-228 Uranium H-3 Gr. Alpha Ra-226 Ra-228 Uranium Co-60 Cs-134 Cs-137 Gr. Beta Sr-89 Sr-90 37.0 +/- 2.0 26.5 i0.8 14.8 +/-0.3 17.2 1.1 6.6 i 0.3 11.7 :+/- 0.3 15900.0 +/- 174.0 32.9 i 0.3 16.5 +/-0.9 6.2 +/- 0.5 9.7 +/- 1.5 27.7 +/- 1.9 21.5 +/- 1.1 66.3 +/- 2.8 159.0 +/- 2.5 48.5 +/- 0.4 10.1 +/-3.0 29.5 +/-7.4 26.3 +/- 5.0 16.5 +/-3.0 17.8 +/- 2.7 6.8 +/- 1.7 11.7 +/-3.0 14300.0 +/- 1430.0 54.2 +/- 3.0 16.1 +/-22A 5.5 +/- 1.4 9.3 +/- 13.6 27.7 +/- 5.0 23.4 +/- 5.0 64.2 +/- 5.0 168.0 +/- 5.0 50.4 +/- 5.0 10.2 +/- 25.2 16.7 -42.3 17.6 - 35.0 11.3 -21.7 13.2 - 22.4 3.8 - 9.7 6.5 -16.9 11800.0 - 16800.0 30.7 - 77.7 11.9 - 20.3 3.1 - 7.9 4.1 -14.5 19.0 - 36.4 17.6 - 29.2 55.5 - 72.9 124.0 - 212.0 41.7 - 59.1 1.5 - 18.9
' Results obtained by Environmental, Inc., Midwest Laboratory as a participant In the environmental samples crosscheck program operated by Environmental Resources Associates (ERA).
b Unless otherwise Indicated, the laboratory result Is given as the mean +/- standard deviation for three determinations.
' Results are presented as the known values, expected laboratory precision (1 sigma,1 determination) and control rimits as provided by ERA.
d Recount of the original sample still low. The ERA blank was spiked In the lab; known value of 20.1 pCUL. measured 21.5 +/- 1.1 pCU/L. No explanation for ERA test failure.
Lower bias observed for gamma spectroscopic analysis. The undiluted sample was reanalyzed; Results of reanalysis. Co-60: 62.3 pCUL.. Cs-134: 69.2 pCL., Cs-137: 152.3 pCVL.
'Reason for deviation unknown. A recount of the original planchets averaged 43.4 pCUL.
Cs-137activity by gamma spectroscopy; 28.3 pCUL. Result of reanalysis; 29.3 pCUL.
A1-2
TABLE A-2. Crosscheck program results; Thermoluminescent Dosimetry, (TLDs).
mR Lab Code TLD Type Date Known Lab Result Control Description Value
+/- 2 sigma Limits Environmental. Inc.
2003-1 2003-1 2003-1 2003-1 2003-1 2003-1 2003-1 2003-1 2003-1 CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaS04: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards 8/8/2003 818/2003 8/8/2003 8/8/2003 8/8/2003 8/8/2003 8/8/2003 8/8/2003 8/8/2003 Reader 1,120 Reader 1,150 Reader 1,180 Reader 1, 180 Reader 1,30 Reader 1, 60 Reader 1,60 Reader 1,90 Reader 1,90 4.69 3.00 2.08 2.08 75.00 18.75 18.75 8.33 8.33 4.74 +/- 0.54 3.02 t 0.20 1.89 i OA5 2.11 +/- 0.22 84A0 +/- 4.87 19.11 +/-1.86 22.82 +/- 5A1 9.05 + 1.17 7.60
- 1.08 3.28 - 6.10 2.10 - 3.90 1 A6 - 2.70 1.46 - 2.70 52.50 - 97.50 13.13 - 24.38 13.13 - 24.38 5.83 - 10.83 5.83 - 10.83 Environmental, Inc.
2003-2 2003-2 2003-2 2003-2 2003-2 2003-2 2003-2 2003-2 2003-2 CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaS04: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaS04: Dy Cards 1112/2004 1/1212004 1/12/2004 1/1212004 1/12/2004 1/12/2004 1/12/2004 1/1212004 1/12/2004 Reader 1, 30 Reader 1,60 Reader 1,60 Reader 1,90 Reader 1, 90 Reader 1, 120 Reader 1, 150 Reader 1, 150 Reader 1,180 61.96 15.49 15.49 6.88 6.88 3.87 2.48 2.48 1.72 73.50 + 2.58 19.70 +/- 0.51 16.93 +/- 1.37 8.06 +/- 0.60 6.64
- 0.58 4.39 +/- 0.17 2.34 +/- 0.18 2.51 +/- 0.16 2.01 +/- 0.13 43.37 - 80.55 10.84 - 20.14 10.84 - 20.14 4.82 - 8.94 4.82 - 8.94 2.71 - 5.03 1.74 - 3.22 1.74 - 3.22 1.20 - 2.24 A2-1
TABLEA-3. In-House"Spike"Samples Concentration (pCiVL)a Lab Code Sample Date Analysis Laboratory results Known Control Type 2s, n=lb Activity Limits' SPW-356 W-10303 W-11303 W-12103 SPAP446 SPW-468 W-20703 SPU-1347 DW-30303 SPCH-964 SPMI-1086 SPMI-1086 SPMI-1086 SPW-1088 SPW-1088 SPW-1088 SPW-1088 SPVE-1110 SPW-1194 SPW-1 194 SPW-1194 W-32103 SPCH-1429 W-40103 SPF-1407 SPF-1407 SPAP-1409 SPU-41203 SPU-41703 SPW-2022 SPW-2053 SPW-2053 SPMI-2055 SPMI-2055 W-50603 W-60303 SPW-3960 SPMI-4019 SPMI-4019 SPMI-4019 SPW-4023 SPW-4023 SPW-4023 SPW-4518 water water water water Air Filter water water Urine water Charcoal Milk Milk Milk water water water water Vegetation water water water water Charcoal water Fish Fish Air Filter Urine Urine water water water Milk Milk water water water Milk Milk Milk water water water water 1/212003 1/312003 1/13/2003 1/21/2003 1/31/2003 1/31/2003 217/2003 3/1/2003 3/3/2003 3/8/2003 3/13/2003 3/13/2003 3/13/2003 311312003 3113/2003 3113/2003 3/13/2003 3/1412003 3121/2003 3/21/2003 3/21/2003 3/21/2003 4/1/2003 4/1/2003 41212003 4/212003 4/2/2003 4/1212003 411712003 4/2512003 4/28/2003 4/28/2003 4/28/2003 4/28/2003 5/6/2003 6/3/2003 7/15/2003 7/18/2003 7/18/2003 7/18/2003 7/18/2003 7118/2003 7/18/2003 8/8/2003 Sr-90 Gr. Beta Gr. Beta Gr. Beta Gr. Beta H-3 Fe-55 H-3 Gr. Beta 1-131 (G)
Cs-137 1-131 1-131(G)
Co-60 Cs-137 1-131(G) 1-131 1-131(G)
Co-60 Cs-1 37 1-131 (G)
C-14 1-131(G)
Gr. Beta Cs-134 Cs-I 37 Gr. Beta H-3 H-3 H-3 Cs-I 37 Sr-9o Cs-I 37 Sr-90 Gr. Beta Gr. Beta H-3 Cs-137 Sr-89 Sr-90 Cs-I 37 Sr-89 Sr-90 Fe-55 34.04 i 1.57 63.24 +/- 1.20 59.75 +/- 1.10 61.56 +/- 1.59 1.49 +/- 0.02 95982.00 + 865.00 9095.00 +/- 114.00 1724.00 +/-412.00 65.44 I 0.59 73.37 +/- 0.28 57.18 +/- 8.03 75.13 f 12.01 65.81 +/- 1.06 27.16 +/- 4.79 51.74 +/- 9.15 68.14 +/- 12.92 76.94 +/- 1.13 122.80 +/- 16.80 31.09 +/- 6.28 55.11 +/-0.13 66.17 +/- 9.15 5201.00 +/- 16.60 8.83 +/- 0.11 67.74 +/- 0.52 0.58 +/- 0.03 1.29 +/- 0.06 1.44 +/- 0.02 1798.50 +/- 409.30 1625.10 +/-401.30 89007.00 +/- 798.00 45.70 +/- 9.44 47.51 +/- 1.87 61.65 +/- 7.17 38.45 +/- 1.59 70.95 +/- 0.53 63.00
- 0.51 88700.00 +/- 822.00 47.17 +/- 7.22 40.95 +/- 4.88 45.30 +/- 1.73 51.92 +/- 6.24 42.49 +/- 10.23 49.69
- 3.04 8176.00 i 107.00 30.93 63.90 63.90 63.99 1.52 89607.00 10587.00 1784.33 63.90 69.45 49.50 67.60 67.56 28.20 49.50 67.60 67.56 124.00 28.15 49.50 67.60 4966.00 9.18 63.39 0.59 1.32 1.51 1784.33 1784.33 88463.00 49.35 44.47 65.80 44.74 63.39 65.73 87369.00 49.11 49.49 44.24 49.11 49.49 44.24 9330.00 24.74 - 37.12 53.90 - 73.90 53.90 - 73.90 53.99 - 73.99
-8.48 - 11.52 71685.60 - 107528.40 8469.60 - 12704.40 1101.27 - 2467.39 53.90 - 73.90 59.45 - 79A5 39.50 - 59.50 54.08 - 81.12 57.56 - 77.56 1820 - 38.20 39.50 - 59.50 57.60 - 77.60 54.05 - 81.07 111.60 - 136.40 18.15 - 38.15 39.50 - 59.50 57.60 - 77.60 2979.60 - 6952.40
-0.82 - 19.18 53.39 - 73.39 0.35 - 0.83 0.79 - 1.85.
-8.49 - 11.51 1101.27 - 2467.39 1101.27 - 2467.39 70770.40 - 106155.60 39.35 - 59.35 35.58 - 53.36 55.80 - 75.80 35.79 - 53.69 53.39 - 73.39 55.73 - 75.73 69895.20 - 104842.80 39.11 - 59.11 39.49 - 59.49 35.39 - 53.09 39.11 - 59.11 39.49 - 59.49 35.39 - 53.09 7464.00 - 11196.00 A3-1
TABLE A-3. In-House "Spike" Samples Concentration (pCVL)
Lab Code Sample Date Analysis Laboratory results Known Control Type 2s, n=1 b Activity Ltmits" SPW-6197 water 10/16/2003 Tc-99 540.14 i 54.00 539.73 377.81 -701.65 SPAP-3958 Air Filter 10/28/2003 Gr. Beta 1.45 +/- 0.02 1.50
-8.50 - 11.50 SPW-6401 water 10/2812003 H-3 84867.00 +/- 826.00 85984.00 68787.20 - 103180.80 SPAP-6403 Air Filter 1012812003 Gr. Beta 1.71 i0.02 1A9
-8.51 -114A9 SPF-6418 Fish 1012812003 Cs-134 0.50 +/- 0.02 0.49 0.29 - 0.69 SPF-6418 Fish 10/28/2003 Cs-137 1.37 +/- 0.05 1.30 0.78 - 1.82 SPW-6421 water 10128/2003 Fe-55 104.18 +/- 1.26 88.18 68.18 - 108.18 SPMI-7459 Milk 12112/2003 Cs-134 41.06 +/- 2.45 41.88 31.88 - 51.88 SPMI-7459 Milk 1211212003 Cs-137 48.48 +/-4.99 48.64 38.64 -58.64 SPMI-7459 Milk 12/12/2003 Sr-89 55.94 +/-4.12 65.80 52.64 - 78.96 SPMI-7459 Milk 12112/2003 Sr-90 41.86 +/- 1.57 43.80 35.04 - 52.56 SPW-7461 water 12112/2003 Cs-134 44.07 +/-14A9 41.88 31.88 -51.88 SPW-7461 water 12112/2003 Cs-137 50.26 t 2.67 48.64 38.64 - 58.64 SPW-7461 water 12/12/2003 Sr-89 56A1 +/-4.87 65.80 52.64 -78.96 SPW-7461 water 12/12/2003 Sr-90 48.44 +/- 1.84 43.80 35.04 - 52.56
'Control limits are based on Attachment A, Page A2 of this report.
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 (pCilL)'
Lab Code Sample Date Analysis Laboratory results (4.66a)
Acceptance Type LLD ActivitV Criteria (4.66 a)
SPW-357 W-10303 W-11303 W-12103 SPAP-447 SPW-469 W-20103 W-20703 DW-30303 water water water water Air Filter water water water 1/212003 113/2003 1/13/2003 1/21/2003 1/31/2003 1/31/2003 2/1/2003 2[712003 3/3/2003 SPCH-965 Charcoal Cani: 318/2003 SPMI-1087 SPMI-1087 SPMI-1087 SPMI-1087 SPW-1089 SPW-1089 SPW-1089 SPW-1089 SPVE-1111 W-32103 Milk Milk Milk Milk water water water water Vegetation water 3/1312003 3113/2003 3/13/2003 3/13/2003 3/13/2003 3/13/2003 3/13/2003 3/13/2003 3/14/2003 3/21/2003 SPCH-1430 Charcoal Cani:4/1/2003 W-40103 SPF-1408 SPF-1408 SPAP-1410 SPU-41203 SPU-41703 SPW-2054 SPW-2054 SPW-2054 SPMI-2056 SPMI-2056 SPMI-2056 W-50603 W-60303 SPW-3960 SPMI-4018 SPMI-4018 SPMI-4018 '
SPW-4024 SPW-4024 SPW-4519 SPW-6401 water Fish Fish Air Filter Urine Urine water water water Milk Milk Milk water water water Milk Milk Milk water water water water 4/1/2003 4/212003
.4/212003 4/2/2003 4/12/2003 4/17/2003 4/28/2003 4/2812003 4/28/2003 4/28/2003 4/28/2003 4/28/2003 5/6/2003 6/3/2003 7/15/2003 7/18/2003 7/18/2003 7/18/2003 7/18/2003 7/18/2003 8/8/2003 10/28/2003 Sr-90 Gr. Beta Gr. Beta Gr. Beta Gr. Beta H-3 Gr. Beta Fe-55 Gr. Beta 1-131 (G)
Cs-134 Cs-1 37 1-131 1-131 (G)
Co-60 Cs-1 34 Cs-137 1-131 1-131 (G)
C-14 1-131 (G)
Gr. Beta Cs-134 Cs-137 Gr. Beta H-3 H-3 Cs-137 Sr-89 Sr-90 Sr-90 Cs-I 37 1-131(G)
Gr. Beta Gr. Beta H-3 Cs-137 Sr-89 Sr-90 Sr-89 Sr-90 Fe-55 H-3 0.50 0.12 0.14 0.12 0.00 160.20 0.17 802.00 0.15 0.01 7A9 7.90 0.33 7.76 4.48 5.60 4.32 0.29 7.53 17.50 0.01 0.14 0.01 0.01 0.00 653.99 648.35 3.16 0.55 0.55 0.77 2.74 3.54 0.12 0.14 156.60 4.10 0.73 0.51 0.83 0.62 527.00 163.80 0.12 +/- 0.25 0.022 +/- 0.10 0.035 +/- 0.10 0.029 i 0.09
-0.0034 +/- 0.00 19.3 +/- 80.30 0.0 +/- 0.12 149 +/-498.00 0.007 +/- 0.11
-0.013 +/- 0.18
-0.050 +/- 0.16
-0.4 +/- 9.200
-0.11 +/- 0.100
-0.0029 +/- 0.002 542.28 +/- 364.780 100.1 +/- 344.800 0.45 +/- 0.50 0.072 +/- 0.260 0.66 +/- 0.430 0 +/- 0.090
-0.035 +/- 0.095 53.4 +/- 80.200 0.39 +/- 0.880 0.93 +/-0.340 0.21 +/- 0.730 0.09 +/- 0.300 87 +/- 369.000
-23.8 +/- 85.000 3
3.2 3.2 3.2 3.2 200 3.2 1000 3.2 9.6 10 10 0.5 20 10 10 10 0.5 20 200 9.6 3.2 100 100 3.2 200 200 10 5
1 1
10 20 3.2 3.2 200 10 5
1 5
1 1000 200 A4-1
TABLE A-4. In-House 'Blank Samples Concentration (pCVL)a Lab Code Sample Date Analysis Laboratory results (4.66a)
Acceptance Type LLD Activityb Criteria (4.66 r)
SPAP-6404 SPF-6419 SPF-6419 SPMI-7460 SPMI-7460 SPMI-7460e Air Filter Fish Fish Milk Milk Milk 10128/2003 10128/2003 10/2812003 12/12/2003 12112/2003 12/12/2003 Gr. Beta Cs-134 Cs-137 Cs-1 34 Cs-1 37 Sr-90 0.87 0.01 0.01 4.52 5.77 0.50
-0.99 :+/- 0.440 1.26- 0.370 3.2 100 100 10 10 I
8 Liquid sample results are reported In pCVlter, air filters( pCifilter), charcoal (pCIcharcoal canister), and sorid samples (pCUkg).
b The activity reported Is the net activity resulL c Low levels of Sr-90 are still detected In the environment A concentration of (1-5 pCVL) In milk Is not unusual.
A4-2
TABLEA-5. In-House"Duplicate"Samples Concentration (pCilL)'
Averaged Lab Code Date Analysis First Result Second Result Result MI-24, 25 MI-24, 25 CF-47,48 CF-47,48 AP-8827, 8828 AP-8869, 8870 MI-119,120 MI-119.120 MI-213, 214 MI-213, 214 MI-262, 263 S-696, 697 S-696, 697 MI-448,449 SW-470,471 SW-470,471 SW-470, 471 MI-517, 518 MI-541, 542 MI-620, 621 DW-922, 923 CF-1048,1049 b LW-1152,1153 F-1120, 1121 F-1120,1121 F-1120, 1121 DW-1278,1279 SO-1380, 1381 LW-1299,1300 LW-1320,1321 W-1403.1404 AP-2019, 2020 MI-1422,1423 MI-2170, 2171 MI-1422,1423 AP-1633,1634 AP-1871,1872 AP-1974,1975 LW-1828,1829 S-1544,1545 DW-1913,1914 MI-1996,1997 MI-1996.1997 1/2/2003 1/2/2003 1/2/2003 112/2003 1/2/2003 1/2/2003 1/8/2003 1/8/2003 1/14/2003 1/14/2003 1/15/2003 1/29/2003 1/29/2003 2/3/2003 2/3/2003 2/3/2003 2/3/2003 2/4/2003 2/5/2003 2/11/2003 3/4/2003 3/10/2003 3/13/2003 3/14/2003 3/14/2003 3/14/2003 3/25/2003 3/25/2003 3/27/2003 3/27/2003 3/31/2003 3/31/2003 4/1/2003 4/1/2003 4/2/2003 4/212003 4/212003 4/2/2003 4111/2003 4115/2003 4/15/2003 4/21/2003 4/22/2003 K-40 Sr-9o Gr. Beta K-40 Be-7 Be-7 K-40 Sr-90 K-40 Sr-90 K-40 Gr. Alpha Gr. Beta K-40 Gr. Beta K-40 (ICP)
K-40 K-40 K-40 K-40 1-131 K-40 H-3 Cs-137 Gr. Beta K-40 1-131 Gr. Beta Gr. Beta H-3 Sr-90 Be-7 K-40 K-40 Sr-90 Be-7 Be-7 Be-7 Gr. Beta K-40 1-131 Sr-90 K-40 1362.00 +/- 117.00 1.45 +/- 0.40 2.72 i 0.10 2.61 +/- 0.31 0.06 +/- 0.01 0.04 +/- 0.02 1351.90 +/- 116.10 2.22 A
0.43 1372.30 +/- 104.80 1.81 i 0.41 1399.20 +/- 200.70 24.70 +/- 4.89 22.89 +/- 2.67 1159.70 +/-157.90 13.62 i 1.23 5.10 +/- 0.51 5.80 +/- 0.51 1437.70 i 125.50 1443.00 +/- 194.80 1294.70 +/- 115.10 0.67 +/- 0.16 3.09 +/- 0.12 1147.26 +/-122.56 0.04 +/- 0.02 2.04 +/- 0.06 1.93 i 0.38 0.37 +/- 0.22 18.60 +/-2.68 2.35 i0.55 487.12
- 104.43 0.96 +/- 0.32 0.07 +/- 0.01 1410.00 +/- 176.00 1452.30 i 129.10 1.84 A0.42 0.05 i 0.01 0.07
- 0.01 0.08 +/- 0.02 2.49 +/- 0.58 15.84 +/-2.36 0.29 +/- 0.21 2.05 *0.74 1580.20 +/- 118.90 1377.00 +/- 188.00 2.21 +/- 0.50 2.84 +/- 0.10 2.32 +/- 0.12 0.05
- 0.02 0.05 +/- 0.02 1234.70 +/- 108.70 1.88 +/- 0.40 1303.80 +/- 109.10 2.29 +/- OA5 1347.70 +/- 126.40 23.23
- 4.64 22.71 +/- 2.73 1396.40
- 106.20 15.21 +/- 1.21 5.20 +/- 0.52 5.90 +/- 0.52 1357.70 +/- 188.00 1385.20 +/- 190.10 1234.10 +/- 165.10 0.79 +/- 0.16 2.67
- 0.07 1094.42 i 120.92 0.05
- 0.01 2.11 +/- 0.06 1.89 +/- 0.25 0.34 +/- 0.29 20.53 +/- 2.83 2.48
- 0.56 422.00 +/- 102.00 1.10 +/- 0.42 0.08
- 0.01 1340.00 +/- 114.00 1472.50 +/- 191.00 1.15
- 0.39 0.06
- 0.01 0.07 +/- 0.01 0.07 +/- 0.02 3.42 +/- 0.63 15.41
- 2.02 0.42 +/- 0.19 3.25 +/- 0.91 1602.10 +/- 120.40 1369.50
- 110.72 1.83 +/- 0.32 2.78 +/- 0.07 2.47 +/- 0.17 0.05 +/- 0.01 0.05 +/- 0.01 1293.30 +/-79.52 2.05 +/- 0.30 1338.05 +/- 75.64 2.05 +/- 0.31 1373.45 +/- 118.59 23.97 +/- 3.37 22.80 +/- 1.91 1278.05
- 95.15 14.42 +/- 0.86 5.15 +/- 0.36 5.85 +/- 0.36 1397.70 +/- 113.02 1414.10 +/- 136.09 1264.40 +/- 100.63 0.73 +/- 0.11 2.88 +/- 0.07 1120.84 +/- 86.09 0.05 +/- 0.01 2.08 +/- 0.04 1.91 +/- 0.23 0.36 +/- 0.18 19.57 +/- 1.95 2.42 +/- 0.39 454.56 +/- 72.99 1.03 +/- 0.26 0.07 +/- 0.01 1375.00 +/- 104.85 1462.40 +/- 115.27 1.50 +/- 0.29 0.06 +/- 0.01 0.07 +/- 0.01 0.08 +/- 0.01 2.96 +/- 0.43 15.63 +/- 1.55 0.36 +/- 0.14 2.65 +/- 0.58 1591.15 +/- 84.61 A5-1
TABLE A-5. In-House "Duplicate" Samples Concentration (pCUL)
Averaged Lab Code Date Analysis First Result Second Result Result LW-2063, 2064 SWU-2275, 2276 G-2149, 2150 TD-2339, 2340 SO-2381, 2382 SO-2381. 2382 SO-2381, 2382 SO-2381, 2382 SO-2381. 2382 DW-2317, 2318 BS-2595,2596 BS-2595, 2596 U-2484, 2485 SO-2645, 2646 SO-2645, 2646 SO-2645, 2646 MI-2696, 2697 MI-2696. 2697 S0-2787,2788 S0-2787, 2788 SO-2787, 2788 MI-2840, 2841 SWU-2864, 2865 BS-2888, 2889 BS-2888, 2889 W-3230, 3231 TD-3036, 3037 SL-2909, 2910 b SL-2909, 2910 SW-3080,3081 SW-3080, 3081 VE-3172, 3173 F-3742, 3743 F-3742, 3743 SO-3325, 3326 MI-3253, 3254 MI-3297, 3298 WW-3380, 3381 SWT-3403,3404 MI-3424,3425 SW-3862,3863 G-3479, 3480 G-3479, 3480 LW-3809,3810 4128/2003 4128/2003 4/30/2003 5/1/2003 5/1/2003 5/11/2003 511/2003 511/2003 5/1/2003 5/612003 5/6/2003 5/6/2003 5/9/2003 511412003 5/14/2003 5114/2003 5/19/2003 511912003 5/28/2003 5/28/2003 5/2812003 5/28/2003 5128/2003 5/29/2003 512912003 5130/2003 6/212003 613/2003 6/312003 6/10/2003 6/1012003 6/11/2003 6/11/2003 6/11/2003 6/13/2003 6(17/2003 6/17/2003 6/23/2003 6/24/2003 6/24/2003 6/24/2003 6/2512003 6/25/2003 6130/2003 Gr. Beta Gr. Beta Be-7 H-3 Cs-137 Gr. Alpha Gr. Beta K-40 Sr-90 1-131 Cs-137 K-40 H-3 Be-7 Cs-137 K-40 K-40 Sr-90 Cs-137 Gr. Beta K-40 K-40 Gr. Beta Cs-137 K-40 Gr. Beta H-3 Gr. Beta K-40 Gr. Alpha Gr. Beta K-40 Gr. Beta K-40 Gr. Beta K-40 Sr-90 Gr. Beta Gr. Beta K-40 Gr. Beta Be-7 K-40 Gr. Beta 2.33 i 0.66 3.62 + 0.67 0.71 +/- 0.19 221.00 +/- 91.00 0.11 0.03 11.14 +/-5.15 35.18 +/- 4.69 18.29 i 0.84 0.06 +/-0.02 1.77 +/- 0.27 0.06 + 0.02 13.74 +/- 0.62 512.00 i 100.00 1.18 + 0.42 0.11 +/- 0.04 16.50 i 1.13 1320.40 + 124.50 1.49 +/- 0.47 0.27 + 0.04
-i9.62 + 1.73 14.77 i 1.02 1179.50 +/- 167.80 3.39 +/- 0.59 0.05 +/- 0.02 9.70 i 0.83 4.33 + 1.00 529.50 + 100.00 7.10 +/- 0.15 3.90 +/- 0.67 4.63 + 1.90 9.07 +/- 1.29 2.62 +/- 0.35 3.47 +/- 0.13 2.94 + 0.39 20.95 i 1.88 1329.40 +/- 121.80 2.14 + 0.57 5.58 +/- 0.69 2.80 +/- 0.56 1422.80 +/- 185.40 3.66 i 1.18 1.52 +/- 0.25 5.02 +/- 0.45 2.12 +/- 0.76 2.68 +/- 0.60 4.60 +/- 0.71 0.69 +/- 0.20 161.00
- 88.00 0.10 +/- 0.02 10.39 +/- 5.60 39.66 +/- 5.24 17.83 +/- 0.84 0.10 +/- 0.02 1 A7 +/- 0.26' 0.06 +/- 0.02 14.10 +/- 0.73 370.00 +/- 95.00 1.21 +/- 0.35 0.09 +/- 0.05 15.33 +/-1.09 1394.10 +/- 113.00 2.01 +/- 0.45 0.23 +/- 0.04 20.81 +/-1.72 14.41 +/- 1.00 1401.70 +/- 120.20 3.41 +/- 0.64 0.07 +/- 0.04 10.17 +/- 0.87 3.28 +/- 1.22 585.50 +/- 102.00 7.60 +/- 0.16 3.49 +/- 0.52 4.47 +/- 1.71 8.98 +/- 1.28 3.17 +/- 0.58 3.71 +/- 0.14 2.70 +/- 0.40 19.97 +/- 2.01 1417.60 +/- 130.90 2.27 +/- 0.50 5.03 +/- 0.69 2.63 +/- 0.55 1216.20 +/- 170.10 3.70 +/- 1.22 1.43 +/- 0.28 5.10 +/- OA8 2.39 +/- 0.72 2.51 +/- 0.45 4.11 +/- 0.49 0.70 +/- 0.14 191.00 +/- 63.29 0.10 +/- 0.02 10.77 +/- 3.80 37A2 +/- 3.52 18.06 +/- 0.59 0.08 +/- 0.01 1.62 +/- 0.19 0.06 +/- 0.02 13.92 +/- 0.48 441.00 +/- 68.97 1.19 +/- 0.27 0.10 +/- 0.03 15.91 +/- 0.79 1357.25 +/- 84.07 1.75 +/- 0.32 0.25 +/- 0.03 20.21 +/- 1.22 14.59 +/- 0.71 1290.60 +/- 103.20 3.40 +/- 0.43 0.06 +/- 0.02 9.93 +/- 0.60 3.81 +/- 0.79 557.50 +/- 71.42 7.35 +/- 0.11 3.70 +/- 0.42 4.55 +/- 1.28 9.02 +/- 0.91 2.90 +/- 0.34 3.59 +/- 0.10 2.82 +/- 0.28 20.46 +/- 1.38 1373.50 +/- 89.40 2.21 +/-0.38 5.31 +/- 0.49 2.72 +/- 0.39 1319.50 +/- 125.80 3.68 +/- 0.85 1.47 +/- 0.19 5.06 +/- 0.33 2.25 +/- 0.52 A5-2
TABLE A-5. In-House 'Duplicate Samples Concentration (pCiIL)
Averaged Lab Code Date Analysis First Result Second Result Result LW-3809, 3810 AP-4105,4106 G-3572,3573 G-3572, 3573 G-3572, 3573 G-3572, 3573 MI-3601, 3602 MI-3601, 3602 AP-3933, 3934 AP-4061, 4062 AP-4147,4148 AP-4084,4085 LW-3786, 3787 WW-4168,4169 CF-3975, 3976 CF-3975, 3976 MI-4020,4021 DW-4272, 4273 SWU-4461, 4462 SL-4398,4399 SL-4398,4399 b SL-4398, 4399 G-4419, 4420 G-4419,4420 G-4419,4420 TD-4550, 4551 MI-4482,4483 MI-4482,4483 G-4526,4527 G-4526, 4527 SWU-4609, 4610 CW-4694, 4695 CW-4694, 4695 LW-4673, 4674 MI-4735.4736 MI-4756,4757 VE-4832, 4833 MI-4860,4861 SO-5082, 5083 SO-5082, 5083 CW-5349, 5350 CW-5349, 5350 ME-4968,4969 ME-4968,4969 6/30/2003 6/30/2003 7/1/2003 7/1/2003 7/1/2003 7/1/2003 7/1/2003 7/1/2003 7/1/2003 7t2/2003 7/2/2003 7/3/2003 7/9/2003 711112003 7114/2003 7/14/2003 7/16/2003 7/29/2003 7/30/2003 8/4/2003 8/4/2003 8/4/2003 8/4/2003 8/4/2003 8/4/2003 8/4/2003 8/6/2003 8/6/2003 8/6/2003 8/6/2003 8/6/2003 8/6/2003 8/6/2003 8/13/2003 8/19/2003 8/19/2003 8/20/2003 8/26/2003 8/28/2003 8/28/2003 8/31/2003 8/31/2003 9/2/2003 9/2/2003 H-3 Be-7 Be-7 Gr. Beta K-40 Sr-90 K-40 Sr-90 Be-7 Be-7 Be-7 Be-7 Gr. Beta Gr. Beta Be-7 K-40 K-40 Gr. Beta Gr. Beta Be-7 Gr. Beta K-40 Be-7 Gr. Beta K-40 H-3 K-40 Sr-9o Be-7 K-40 Gr. Beta Gr. Beta H-3 Gr. Beta K-40 Sr-90 K-40 K-40 Cs-137 Gr. Beta Gr. Beta H-3 Gr. Beta K-40 2814.09 + 167.99 0.07 + 0.01 0.91 i 0.24 6.35 + 0.15 5.44 +/- 0.55 0.01 t 0.00 1318.60 +/- 117.40 0.86 +/- 0.51 0.07 i 0.01 0.07 +/- 0.01 0.08 +/- 0.01 0.09 +/- 0.02 2.13 +/- 0.56 3.79 +/- 1.87 1.64 +/- 0.81 6.54 +/- 0.75 1350.90 +/- 174.90 2.35 +/- 0.92 2.28 +/- 0.44 4.55 +/- 1.05 3.41 +/- 0.12 2.47 +/- 0.67 3.98 +/- 0.63 5.38 +/- 0.14 4.42 +/- 0.66 327.30 +/- 95.10 1301.40 +/- 115.20 0.81 +/- 0.30 1.47 +/- 0.29 5.42 +/- 0.56 3.22 +/- 0.63 1.48 +/- 0.34 22776.41 +/- 428.73 2.86 +/- 0.65 1396.30 +/- 127.90 1.66 +/- 0.47 1.96 +/- 0.50 1312.10 +/- 191.80 0.01 +/- 0.00 20.02 +/- 1.84 1.45 +/- 0.39 24429.50 +/- 444A2 4.90 +/- 0.23 2.46 +/- 0.41 2812.17 +/- 167.94 0.07 +/- 0.01 0.81 +/- 0.28 6.35 +/- 0.15 5.68 +/- 0.28 0.02 +/- 0.00 1435.10 +/- 117.80 1.74 +/- 0.60 0.07 +/- 0.01 0.08 +/- 0.01 0.07 +/- 0.01 0.08 +/- 0.02 2.93 +/- 0.62 4.48 +/- 1.98 1.66 +/- 0.57 6.19 +/- 0.50 1199.80 +/- 153.20 2.29 +/- 0.89 1.93 +/- 0.43 4.50 +/- 1.10 3.12 +/- 0.11 2.44 +/- 0.87 3.93 +/- 0.57 5.35 +/- 0.16 4.32 +/- 0.74 390.20 +/- 92.10 1370.30 +/- 116.80 0.85 +/- 0.31 1.42 +/- 0.28 5.21 +/- 0.63 2.67 +/- 0.64 1.09 +/- 0.34 21831.75 +/- 420.10 3.75 +/- 0.71 1410.10 +/- 120.20 1.53 +/- 0.44 1.43 +/- 0.47 1307.80 +/- 109.30 0.01 i 0.00 20.92 +/- 2.03 1.55 +/- 0.45 24744.25 +/-447.18 5.18 +/- 0.24 2.68 +/- 0.37 2813.13 +/- 118.77 0.07 +/- 0.01 0.86 +/- 0.18 6.35 +/- 0.11 5.56 +/- 0.31 0.01 +/- 0.00 1376.85
- 83.16 1.30 +/- 0.39 0.07
- 0.01 0.08 +/- 0.01 0.07 +/- 0.01 0.08 +/- 0.01 2.53 +/- 0.42 4.14 +/- 1.36 1.65 +/- 0.50 6.36 +/- 0.45 1275.35 +/-116.25 2.32 +/- 0.64 2.10 + 0.31 4.53 +/- 0.76.
3.27 +/- 0.08 2.46 +/- 0.55 3.96 +/- 0.42 5.37 +/- 0.11 4.37 i 0.50 358.75 +/- 66.19 1335.85 +/-82.03 0.83 +/- 0.21 1.45 +/- 0.20 5.31 +/- 0.42 2.95 +/- 0.45 1.29 +/- 0.24 22304.08 +/- 300.12 3.30 +/- 0.48 1403.20 +/- 87.76 1.60 +/- 0.32 1.70 +/- 0.34 1309.95 +/- 110.38 0.01 +/- 0.00 20.47 +/- 1.37 1.50 +/- 0.30 24586.88 +/- 315.23 5.04 +/- 0.17 2.57 +/- 0.28 A5-3
TABLE A-5. In-House Duplicate' Samples Concentration (pCiJL)3 Averaged Lab Code Date Analysis First Result Second Result Result DW-4989,4990 Ml-5154, 5155 MI-5154, 5155 AP-6177, 6178 SWU-5773, 5774 AP-6102, 6103 G-5631, 5632 G-5631. 5632 G-5631, 5632 SO-5660,5661 S0-5660, 5661 SO-5660, 5661 SO-5660, 5661 SO-5660, 5661 AP-6334, 6335 AP-6363, 6364 MI-5794, 5795 Ml-5838, 5839 Ml-5838,5839 BS-5938, 5939 BS-5938, 5939 SS-5959, 5960 MI-6011, 6012 Ml-6034,6035 VE-6055,6056 VE-6055, 6056 MI-6291, 6292 MI-6291, 6292 SS-6435,6436 SS-6435, 6436 CF-6313, 6314 SO-6528,6529 SO-6528,6529 SO-6393,6394 SO-6393, 6394 SO-6393, 6394 SWT-6507, 6508 DW-6647, 6648 BS-6603, 6604 BS-6603,6604 S0-6670, 6671 SO-6670,6671 S-7067,7068 MI-6818, 6819 9/212003 9/8/2003 9/8/2003 9/29/2003 9130/2003 9/30/2003 10/1/2003 10/1/2003 10/1/2003 10/1/2003 10/112003 10/11/2003 10/112003 10/1/2003 10/1/2003 10/2/2003 10/6/2003 10/8/2003 10/8/2003 10/8/2003 10/8/2003 10/13/2003 10/1 3/2003 10/14/2003 10/15/2003 10/15/2003 10/2112003 10/21/2003 10/21/2003 10/21/2003 10/2212003 10/2212003 10/2212003 10(25(2003 10/25/2003 10/25/2003 10/28/2003 10131/2003 11/3/2003 11/3/2003 11/5/2003 11/5/2003 11/10/2003 11/11/2003 Gr. Beta K-40 Sr-90 Be-7 Gr. Beta Be-7 Be-7 Gr. Beta K-40 Cs-I 37 Gr. Alpha Gr. Beta K-40 Sr-90 Be-7 Be-7 Sr-90 K-40 Sr-90.
Cs-I 37 K-40 K-40 K-40 Sr-90 Gr. Beta K-40 K-40 Sr-9o Cs-1 37 K-40 K-40 Cs-I 37 K-40 Cs-137 Gr. Beta K-40 Gr. Beta 1-131 Cs-137 Gr. Beta Cs-I 37 K-40 Cs-I 37 K-40 2.20 +/- 1.04 1365.50 + 116.70 1.19 + 0.39 0.07 +/- 0.01 2.55 +/- 0.63 0.07 + 0.01 1.88 +/- 0.48 5.87 +/- 0.09 5.24 +/- 0.77 0.15 +/- 0.04 12.72 +/- 3.72 32.42 +/- 3.09 18.93 +/- 0.67 0.03 +/- 0.01 0.06 +/- 0.01 0.07 +/- 0.02 1.37 +/- 0.37 1364.30 +/-124.10 0.76 +/- 0.30 0.18 +/- 0.03 15.59 +/- 0.70 7.49 +/- 0.42 1165.20 +/- 118.70 0.86 +/- 0.33 5.18 +/- 0.18 5.31 +/- 0.57 1935.60 + 147.70 1.22 + 0.39 0.05 +/- 0.02 14.08 +/- 0.54 14.56 +/- 0.45 0.15 +/- 0.03 17.46 +/- 0.69 0.09 +/- 0.03 23.21 +/- 1.98 13.98 +/- 0.80 2.64 +/- 0.52 0.46 +/- 0.27 9.03 +/- 0.82 26.83 +/- 1.94 0.15 +/- 0.04 12.96 +/- 0.66 0.21 +/- 0.05 1695.50 +/- 129.80 3.19 +/- 1.14 1456.70 +/- 119.10 1.39 +/- 0.39 0.06 +/- 0.01 2.83 +/- 0.60 0.05 +/- 0.01 2.21 +/-0.40 5.85 +/- 0.08 5.26 +/- 0.58 0.16 +/- 0.05 14.86 +/-3.88 33.60 +/- 3.04 18.25 +/-1.19 0.03 +/- 0.01 0.06 +/- 0.01 0.07 + 0.02 1.02 + 0.37 1414.40 +/- 110.40 1.00 +/- 0.34 0.20 +/- 0.05 16.69 +/- 0.80 7.29 +/- 0.63 1191.20 +/- 99.50 0.90 +/- 0.34 5.33 +/- 0.18 4.52 +/- 0.51 1936.10 +/- 116.50 1.41 +/-0.37 0.05 +/-0.03 14.28 +/- 0.80 14.70 +/- 0.95 0.16 +/- 0.05 17.90 +/- 1.05 0.10 +/- 0.04 21.76 +/- 1.91 14.57 +/- 0.86 2.63 +/- 0.53 0.61 +/- 0.31 8.60 +/-1.13 27.18 +/- 1.95 0.13 +/- 0.04 12.95 +/- 0.72 0.19 +/-0.08 1709.40 +/- 143.00 2.70 +/- 0.77 1411.10 +/- 83.37 1.29 +/- 0.28 0.06 +/- 0.01 2.69 +/- 0.44 0.06 +/- 0.01 2.05 +/- 0.31 5.86 +/- 0.06 5.25 +/- 0.48 0.16 +/- 0.03 13.79 +/- 2.69 33.01 +/-2.17 18.59 +/-0.74 0.03 +/- 0.01 0.06 +/- 0.01 0.07 +/- 0.01 1.19 i 0.26 1389.35 +/- 83.05 0.88 +/- 0.23 0.19 +/- 0.03 16.14 +/- 0.53 7.39 +/- 0.38 1178.20 i 77.44 0.88 +/- 0.24 5.25 +/-0.13 4.92 +/- 0.38 1935.85 +/-94.06 1.31 0.27 0.05 +/- 0.02 14.18 +/-0.48 14.63 +/-0.53 0.16 +/- 0.03 17.68 +/- 0.63 0.10 +/- 0.03 22.48 +/- 1.38 14.27 +/- 0.59 2.63 +/- 0.37 0.53 i 0.21 8.82 i 0.70 27.01 t 1.38 0.14 +/- 0.03 12.96 +/- 0.49 0.20 +/-0.05 1702.45 +/-96.56 A5-4
TABLE A-5. In-House "Duplicate" Samples Concentration (pCilL)a Averaged Lab Code Date Analysis First Result Second Result Result MI-6818, 6819 WL-6987, 6988 SO-7156, 7157 SO-7156, 7157 SO-7156, 7157 SO-7156, 7157 S-7281, 7282 SWU-7198, 7199 DW-7221, 7222 SW-7133, 7134 SW-7133, 7134 W-7519, 7520 SW-7805, 7806 VE-7399, 7400 VE-7399, 7400 SW-7540, 7541 SW-7540, 7541 LW-7736, 7737 AP-7868, 7869 AP-7952, 7953 AP-7994, 7995 11111/2003 11117/2003 11121/2003 11/21/2003 11/21/2003 11/21/2003 11/24/2003 11/25/2003 11/25/2003 12/1/2003 12/1/2003 12/11/2003 1211/2003 121912003 12/912003 12/912003 121912003 12126/2003 12/30/2003 12/30/2003 12/31/2003 Sr-90 Fe-55 Cs-137 Gr. Alpha Gr. Beta K-40 Cs-137 Gr. Beta Gr. Beta Gr. Beta K-40 Fe-55 Sr-9o Gr. Beta K-40 Gr. Alpha Gr. Beta Gr. Beta Be-7 Be-7 Be-7 2.01 +/- 0.41 603.49 +/- 53.32 0.74 +/- 0.08 14.90 +/- 4.24 22.97 +/- 3.12 12.51 +/-1.06 0.82 +/- 0.15 2.60 +/- 0.53 12.32 +/- 1.40 2.10 +/- 0.23 1.50 +/- 0.15 3.03 +/- 0.65 0.59 +/- 0.32 4.99 +/- 0.15 5.04 +/- 0.46 2.64 +/- 1.36 6.62 +/- 1.22 2.62 +/- 0.54 0.05 +/- 0.01 0.04 +/- 0.01 0.05 +/- 0.02 1.59 +/- 0.39 619.65 +/- 53.97 0.77 +/- 0.07 19.25 +/-4.45 25.51 +/- 2.98 12.94 +/-1.07 1.16 +/-0.20 2.54 +/- 0.55 12.38 +/- 1.43 2.46 +/- 0.23 1.40 +/- 0.14 3.12 +/- 0.64 0.56 +/- 0.33 5.24 +/- 0.15 5.34 +/- 0.74 2.10 +/-1.19 5.89 +/- 1.35 2.83 +/- 0.56 0.04 +/- 0.01 0.04 +/- 0.01 0.05 +/- 0.01 1.80 +/- 0.28 611.57 +/- 37.93 0.76 +/- 0.06 17.07 +/- 3.07 24.24 +/- 2.16 12.73 +/- 0.75 0.99 +/- 0.12 2.57 +/- 0.38 12.35 +/- 1.00 2.28 +/- 0.16 1.45 +/-0.10 3.08 +/- 0.46 0.58 +/- 0.23 5.11 +/- 0.11 5.19.+/- 0.43 2.37 +/- 0.91 6.25 +/- 0.91 2.73 +/- 0.39 0.04 +/- 0.01 0.04 +/- 0.01 0.05 +/- 0.01 Note: Duplicate analyses are performed on every twentieth sample received In-house. Results are not listed for those analyses with activities that measure below the LLD.
a Results are reported In units of pCUL, except for air filters (pCVFilter), food products, vegetation, soil, sediment (pCl~g).
b 200 minute count time or longer, resulting In lower error.
A5-5
TABLE A-6. Department of Energys Mixed Analyte Performance Evaluatioh Program (MAPEP)a.
Concentrationb Known Control Lab Code Type Date Analysis Laboratory result Activity LUmitsc STW-972 water 12/01/02 Am-241 0.56 *0.06 0.584 0.09 0.40 - 0.75 STW-972 water 12/01/02 Co-57 57.10
- 1.90 57.00
- 5.70 39.90 - 74.10 STW-972 water 12/01/02 Co-60 38.30 +/-0.60 38.20 +/-3.82 26.74 -49.66 STW-972 water 12/01/02 Cs-134 395.30 +/- 10.10 421.00 +/-42.10 294.70 - 547.30 STW-972 water 12/01/02 Cs-137 316.40 5.30 329.00 +/- 32.90 230.30 -427.70 STW-972 water 12/01/02 Fe-55 94.90 +/-24.50 96.00 +/- 9.60 67.20 - 124.80 STW-972 water 12/01/02 Mn-54 33.40 0.10 32.90 +/-3.29 23.03 -42.77 STW-972 water 12101/02 NI-63 123.80 +/- 5.50 136.50 +/- 13.70 95.55 - 177A5 STW-972 water 12/01/02 Pu-238 0.66 +/- 0.06 0.83 +/- 0.08 0.58 - 1.08 STW-972 water 12/01/02 Pu-239140 0.001 +/- 0.001 0.000
- 0.000 0.000 - 0.005 STW-972 water 12/01/02 Sr-90 13.80 +/-1.00 12.31 +/-1.23 8.62 -16.00 STW-972 water 12/01/02 Tc-99 128.10 +/- 3.80 132.00 +/- 13.20 92.40 - 171.60 STW-972 water 12/01/02 U-233/4 1.60 +/- 0.09 1.54
- 0.15 1.08 -2.00 STW-972 water 12/01/02 U-238 1.64 +/-0.09 1.60 +/- 0.16 1.12 -2.08 S1W-972 water 12/01/02 Zn-65 540.40 +/- 9.90 516.00 +/-51.60 361.20 - 670.80 STSO-987 soil 01/01/03 Co-57 534.36 +/- 2.61 530.00 +/- 53.00 371.00 - 689.00 STSO-987 soil 01/01/03 Co-60 442.16 +/- 2.31 420.00 +/- 42.00 294.00 - 546.00 STSO-987 soil 01/01/03 Cs-134 211.00 +/- 2.30 238.00 +/- 23.80 166.60 -309A0 STSO-987 soil 01/01103 Cs-137 849.50 +/-3.30 832.00 +/- 83.20 582.40 - 1081.60 STSO-987 soil 01/01/03 K-40 716.50 +/- 12.80 652.00 +/- 65.20 456A0 - 847.60 STSO-987 soil 01/01/03 Mn-54 148.76 +/- 2.84 137.00 +/- 13.70 95.90 - 178.10 STSO.987 soil 01/01/03 Ni-63 597.10 +/- 23.50 770.00 +/- 77.00 539.00 - 1001.00 STSO-987 soil 01/01/03 Pu-238 67.05 +/- 3.10 66.90 +/- 6.70 46.83 - 86.97 STSO-987 soil 01/01103 Pu-239/40 52.80 +/- 3.60 52.70 +/- 5.30 36.90 - 68.50 STSO-987 soil 01/01/03 Sr-90 609.50
- 9.80 714.00 +/- 71.40 499.80 - 928.20 STSO-987 soil 01/01/03 U-233/4 99.50 + 7.60 89.00 i 8.90 62.30 - 115.70 STSO-987 soil 01/01/03 U-238 508.60 +/- 42.20 421.00 +/- 42.10 294.70 - 547.30 STSO-987 soil 01/01/03 Zn-65
.492.70 +/- 28.10 490.00 +/-49.00 343.00 - 637.00 E Results obtained by Environmental, Inc.,Midwest Laboratory as a participant in the Department of Energy's Mixed Analyte Performance Evaluation Program, Idaho Operations office, Idaho Falls, Idaho bAll results are In Bqlkg or BqtL as requested by the Department of Energy.
' MAPEP results are presented as the known values and expected laboratory precision (1 sigma, I determination) and control limits as defined by the MAPEP.
A6-1
TABLE A-7. Environmental Measurements Laboratory Quality Assessment Program (EML)-
Concentration' EML Control Lab Code Type Date Analysis Laboratory results Result!
Llmits' STW-977 STW-977 STW-978 STW-978 STW-978 a STW-978 STW-978 e STW-978 STW-978 STW-978 STW-978 water water:
water water water water water water water water water 03/01/03 03/01/03 03101/03 03/01/03 03101/03 03/01/03 03101/03 03101103 03/01103 03/01/03 03/01/03 Gr. Alpha Gr. Beta Am-241 Co-60 Cs-134 Cs-137 H-3 Pu-238 Pu-239140 Sr-90 Uranium 304.30
- 53.10 615.80
- 14.70 2.00 *0.10 221.30 + 1.20 23.30
- 1.10 61 A0
- 0.60 341.90 +22.70 3.70
- 0.20 4.40
- 0.10 4.60
- 0.30 5.10
- 0.60 377.50
- 627.50 2.13 234.00 30.50 63.80 390.00 3.33 3.92 4.34 4.29 0.58 - 1.29 0.61 -1.43 0.79 -1.41
- 0.80 -1.20 0.80 -1.30 0.80 -1.22 0.78 - 2.45 0.74 -1.20 0.79 -1.20 0.69 - 1.34 0.75 -1.33 STSO-979 STSO-979 STSO-979 STSO-979 STSO-979 STSO-979 STSO-979 STSO-979 STSO-979 STSO-979 STSO-979 STVE-980 STVE-980 STVE-980 STVE-980 STVE-980 STVE-980 STVE-980 STAP-981 STAP-981 STAP-981 STAP-981
- STAP-981 STAP-981 STAP-981 STAP-981 STAP-982 STAP-982 soil soil soil soil soil soil son soil soil soil soil Vegetation Vegetation Vegetation Vegetation Vegetation Vegetation Vegetation Air Filter Air Filter Air Filter Air Filter Air Filter Air Filter Air Filter Air Filter Air Filter Air Filter 03/01103 03/01/03 03/01/03 03/01/03 03/01/03 03101/03 03101/03 03/01103 03/01103 03/01/03 03/01/03 03/01/03 03/01/03 03/01/03 03/01/03 03101/03 03/01/03 03/01/03 03101/03 03101/03 03/01103 03101/03 03/01/03 03/01/03 03101/03 03/01/03 03/01/03 03/01/03 Ac-228 Arn-241 Bi-212 Bi-214 Cs-137 K-40 Pb-212 Pb-214 Pu-239/40 Sr-90 Uranium Am-241 Cm-244 Co-60 Cs-137 K-40 Pu-239/40 Sr-90 Am-241 Co-60 Cs-137 Mn-54 Pu-238 Pu-239/40 Sr-90 Uranium Gr. Alpha Gr. Beta 55.60
- 2.50 12.42 i 0.90 57.70
- 3.20 60.40
- 3.20 1416.80 *70.00 653.80
- 11.90 51.10 *5.20 64.70
- 5.10 24A0
- 0.30 54.50
- 2.60 245.00
- 1.50 3.10 *0.20 1 AO 0.50 12.60 + 0.40 449.70
- 6.20 1159.00 *38.60 4.80 *E 0.40 659.70
- 50AO 0.27
- 0.10 30.20
- 0.30 90.30
- 1.30 41.80 + 0.60 0.52
- 0.10 0.35
- 0.10 2.50 : 0.10 0.51 *0.10 0.90 i 0.10 1.50
- 0.10 57.60 15.60 60.60 67.00 1450.00 636.00 57.90 71.10 23.40 64.40 249.00 3.51 2.01 12.10 444.00 1120.00 5.17 650.00 0.34 33.50 99.70 43.80 0.52 0.33 2.80 0.50 1.17 1.50 0.80 - 1.38 0.65 - 2.28 0.50 -1.34 0.78 - 1 A2 0.80 -1.25 0.80 -1.32 0.78 - 1.32 0.76 - 1.46 0.71 -1.30 0.67 -2.90 0.71 - 1.32 0.73 -2.02 0.61 -1.59 0.80 - 1.A4 0.80 -1.31 0.79 -1.39 0.69 - 1.31 0.55 -1.21 0.70 -2.34 0.80 - 1.26 0.80 - 1.32 0.80 - 1.35 0.67 - 1.33 0.73 - 1.26 0.53 -1.84 0.79 -2.10 0.73 - 1.43 0.76 - 1.36 A7-1
TABLE A-7. Environmental Measurements Laboratory Quality Assessment Program (EML)
Concentrationo EML Control Lab Code Type Date Analysis Laboratory results Result" LImits' STW-992 water 09102103 Am-241 9.78
- 0.32 8.76 O.79 - 1.41 The September; 2003 results are preliminary. Control limits used were taken from the March, 2003 data.
Control limits may vary slightly'when the final study Is published.
STW-992 water 09/02/03 Co-60 468.30 *4.10 513.00 0.80 -1.20 STW-992 water 09102103 Cs-134 53.90
- 0.80 63.00 0.80 - 1.30 STW-992 water 09/02/03 Cs-137 76.10
- 1.40 80.30 0.80 -1.22 STW-992 water 09/02103 H-3 355.20
- 12.80 446.30 0.78 - 2.45 STW-992 water 09/02103 Pu-238 1.71
- 0.07 2.07 0.74 -1.20 STW-992 water 09/02/03 Pu-239140 4.24 + 0.01 4.99 0.79 -1.20 STW-992 water 09/02/03 Sr-90 6.70
- 0.50 7.04 0.69 - 1.34 STW-992 water 09102103 Uranium 6.03
- 0.14 5.69 0.75 -1.33 STW-993 water 09/02103 Gr. Alpha 688.00 +/- 7.60 622.00 0.58 - 1.29 STW-993 water 09/02103 Gr. Beta 1985.00 i 111.00 1948.00
.0.61 -1.43 STSO-994 soil 09102103 Arn-241 19.70
- 1.50 18.40 0.65 -2.28 STSO-994 soil 09102103 Cs-1 37 1928.00 +/-119.00 1973.00 0.80 -1.25 STSO-994 soil 09102103 K-40 533.00 +/- 79.00 488.00 0.80 - 1.32 STSO-994 soil
.09/02103 Pu-238 15.30 +/- 0.80 14.60 0.59 -2.88 STSO-994 soil 09/02103 Pu-239140 32.50 +/- 2.30 30.40 0.71 - 1.30 STSO-994 soil 09/02103 Sr-go 69.80 +/- 2.30 80.30 0.67 - 2.90 STSO-994
- soil, 09102103 Uranium.
228.30
- 1i.10 259.30 0.71 -1.32 STAP-995 Air Filter 09102103 Am-241 0.64 +/- 0.05 0.44 0.70 -2.34 STAP-995 Air Filter 09102103 Co-60 48.50 +/- OAO 55.10 0.80 - 126 STAP-995 Air Filter 09102103 Cs-137 51.20 *1.10 54.80 0.80 -1.32 STAP-995 Air Filter 09102103 Mn-54 53.70 +/- 1.10 58.00 0.80 - 1.35 STAP-995 Air Filter 09/02103 Pu-238 0.24 +/- 0.05 0.23 0.67 - 1.33 STAP-995 Air Filter 09/02103 Pu-239/40 0.41 +/- 0.10 0.40 0.73 -1.26 STAP-995 Air Filter 09102103 Sr-90 1.90 +/- 0.10 2.06 0.53 - 1.84 STAP-995 Air Filter 09102103 Uranium 0.80
- 0.06 0.82 0.79 -2.10 STAP-996 Air Filter 09/02103 Gr. Alpha 3.23 +/- 0.07 3.11 0.73 -1.43 STAP-996 Air Filter 09102103 Gr. Beta 4.18
- 0.03 3.89 0.76 - 1.36
' Results are reported In 8qQL with the followung exceptions: Alr Filters (8qlFllter). Soil and Vegetation (Bq/kg).
b The EML result listed Is the mean of repilcate determinations for each nuclide
- the standard error of the mean.
Control limits are reported by EML as the ratio of Reported Value I EML value.
d A low bias for Cs-134 activIty has been observed In the past. No errors have been found In the library or efficiency.
Additional spike analyses will be performed and a correction factored Into the calculation.
- Reporting error.
A7-2
APPENDIX B DATA REPORTING CONVENTIONS B-1
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. Sinale Measurements Each single measurement Is reported as follows:
x i s where:
x = value of the measurement; s = 2s 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 4.66s uncertainty for a background sample.
3.0. Duplicate analyses 3.1 Individual results: For two analysis results; xi +/- si and x2+/- s2 Reported result:
x +/- s; where x= (112) (xi + x2) and s = (1/2) 4I +52 3.2.
Individual results:
<L1, <12 Reported result: <L, where L = lower of Li and L2 3.3.
Individual results:
xi s, <L Reported result:
x i s if x zL; <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 x and standard deviation s of a set of n numbers x1, x2... Xn are defined as follows:
xn Xx s1 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-2
ft APPENDIX C Maximum Permissible Concentrations of Radioactivity in Air and Water Above Background in Unrestricted Areas C-1
Table C-1.
Maximum permissible concentrations of radioactivity in air and water above natural background In unrestricted areasa.
Air (pCi/m 3)
Water (pCVL)
Gross alpha Gross beta Iodine-I 3 1b 1 x 10-3 2.8 x 10-1 Strontium-89 Strontium-90 Cesium-137 Barium-140 Iodine-131 Potassium-40C Gross alpha Gross beta Tritium 8,000 500 1,000 8,000 1,000 4,000 2
10 1 X10 6 a 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-2
APPENDIX D
SUMMARY
OF THE LAND USE CENSUS D-1
Appendix D Summary of the Land Use Census The Duane Arnold Energy Land Use Census for 2003 was completed during late September and early October of 2003. All milk animals, residences 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. The Cedar River was surveyed by boat on July 3rd, 2003 for water use downstream of the DAEC to Cedar Rapids.
There were 189 vegetable gardens identified during the performance of the 2003 Census.
This number exceeds the number of gardens found in the 2002 survey by 11. A new garden to the WNW of the plant resulted in the vegetable receptor for that sector being "moved in" from 2560 to 2460 meters. A list of the nearest gardens is attached.
There were no changes in the milk animal locations with in the 3 mile radius of the plant in the past year. Additional milk receptors were identified between 3 and 5 miles. They are noted on attachments 4 and 5.
The locations of the nearest resident for each sector remained the same in 2003.
21 new homes were built or were under construction within three miles of the DAEC, compared to the 37 new homes identified in 2002. Most of the new houses built were located in the sectors between the plant, Palo and Cedar Rapids (SSW to SE). A listing of the newly identified homes is attached.
The Cedar River survey revealed no new withdrawals of river water compared to previous surveys. Irrigation of the strawberry farm in Palo and fishing remain the only food pathway uses of river water between the DAEC and Cedar Rapids.
As a result of this census, adjustments were made to the MIDAS dose projection software model for the more precise receptor distances.
Pursuant to ESP4.4, no changes were observed offsite that could adversely affect the safe operation of the DAEC or that would warrant a UFSAR update such as new gas pipelines, toxic gas installations or airfield strips.
D-2
APPENDIX E ANNUAL RADIATION DOSE ASSESSMENT E-1
rh Appendix E Annual Radiation Dose Assessment The annual offsite radiation dose to a member of the public was determined by assessment of environmental dosimeter 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 2003 TLD results were compared using a paired difference test. No significant differences in the TLD populations were observed for the 0.5 mile and one mile TLD populations using a confidence level of 99%.
- 2. As stated in Part 1, page 8 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 The contribution of dose to a member of the public most likely to be exposed from effluent releases was calculated by the Meteorological Information and Dose Assessment System (MIDAS) computer program in accordance with ODAM. The calculation methods follow those prescribed by Reg. Guide 1.109.
Because there were no nuclides detected in the environment at or beyond the site boundary that were due to the operation of the DAEC, no comparison of calculated dose from stack releases and dose calculated from environmental contamination was performed.
Following calculation of offsite doses, the appropriateness of REMP sampling station types and locations was reviewed. The current sampling scheme was determined to be more than adequate for the identified receptors.
1.) There were no releases of radioactive material to liquid effluents in 2003.
2.) The maximum dose to air at the site boundary from noble gases released was 2E-03 mrad from gamma radiation at 535 meters SSW.
3.) The maximum dose to air at the site boundary from noble gases released was 6E-02 mrad beta radiation at 535 meters SSW.
4.) The whole body dose equivalent to the maximally exposed individual from noble gases was 2E-03 mrem, at 805 meters West.
5.) The skin dose equivalent to the maximally exposed individual from noble gases was 2E-03 mrem, at 805 meters West.
E-2
'N 6.) The maximally exposed organ due to iodines and particulates with half-lives greater than eight days was the skin of a child at 974 meters SW, with an estimated dose equivalent of 5E-02 mrem.
==
Conclusion:==
No measurable dose due to the operation of the DAEC was detected by environmental TLDs in 2003. The calculated doses are below the regulatory limits stated in Appendix I to 10 CFR 50 and in 40 CFR 190.
Estimated Maximum Offsite Individual Doses for 2003 Type Age Distance Direction Dose or Dose Annual 10 CFR Group (meters)
Equivalent 50, Appendix I (mrem)
Limit Direct Radiation None (as measured by TLDs)
None Liquid Releases None Noble Gas Gamma Air Dose 535 SSW 22E-03 mrad J
10 mrad Beta Air Dose 535 SSW 6E-02 mrad J
20 mrad Whole Body All 805 W
2E-03 mrem l
5 mrem Skin All 805 W
2E-03 mrad J
15 mrem Particulates & Iodines Organ Dose Skiln 974 SW 5E-02 mrem 15 mrem
-ki No Appendix I limit but is used to determine compliance with 40 CFR 190 limits of 25 mrem whole body and 75 mrem thyroid.
E-3