ML021840776
| ML021840776 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 05/15/2002 |
| From: | Forbes J Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| M2002049 | |
| Download: ML021840776 (61) | |
Text
Committed to Nu Excen Monticello Nuclear Generating Plant Operated by Nuclear Management Company, LLC Technical Specification 6.7.C.1 US Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 2001 Annual Radiolooical Environmental Operating Report M2002049 In accordance with the Monticello Technical Specification 6.7.C. 1, we are submitting the annual Radiological Environmental Operating Report for the year 2001. Please note Amendment 120 dated 07/24/01 changed our Technical Specification deadline for this report to May 15 of each year.
This letter contains no new NRC commitments, nor does it modify any prior commitments.
Pease contact Paul Hartmann at (763) 271-5172 with any questions or comments.
Jeffrey S. Forbes Site Vice President Monticello Nuclear Generating Plant Attachment c:
Regional Administrator-Ill, NRC NRR Project Manager, NRC Resident Inspector, NRC Minnesota Department of Commerce J:\\LICENSEXPeriodic ReportsR E M PWnnual Radiological Envir OpeW Report 2001.doc 2807 West County Road 75 o Monticello, Minnesota 55362-9637 Telephone: 763-295-5151 & Fax: 763-295-1454 May 15, 2002 pot
Environmental, Inc.
Midwest Laboratory an Allegheny Technologies Co.
700 Landwehr Road
- Northbrook, IL 60062-2310 ph. (847) 564-0700
- fax (847) 564-4517 XCEL ENERGYCORPORATION MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263 LICENSE NO. DPR-22 ANNUAL REPORT TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION Radiological Environmental Monitoring Program January 1 to December 31, 2001 Prepared under Contract by ENVIRONMENTAL, Inc.
Midwest Laboratory Project No. 8010 Approved:
Bronia Gro S.
Laboraory M ager
PREFACE The staff of Environmental, Inc., Midwest Laboratory was responsible for the acquisition of data presented in this report. Samples were collected by personnel of the Monticello Nuclear Generating Plant, operated by Nuclear Management Company, LLC for XCEL Energy Corporation. This report was prepared by Environmental, Inc.,
Midwest Laboratory.
ii
TABLE OF CONTENTS No.
Page Preface................................................................................................................................
ii List of Tables......................................................................................................................
iv List of Figures......................................................................................................................
v
1.0 INTRODUCTION
1 2.0
SUMMARY
2 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)...................
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 3.6 Land Use Census..............................................................................................
6 4.0 RESULTS AND DISCUSSION.......................................................................................
7 4.1 Atmospheric Nuclear Detonations and Nuclear Accidents.................................
7 4.2 Sum m ary of Preoperational Data.....................................................................
7 4.3 Program Findings..............................................................................................
8 5.0 FIGURES AND TABLES................................................................................................
12
6.0 REFERENCES
24 APPENDICES A
Interlaboratory Comparison Program Results..............................................................
A-1 B
Data Reporting Conventions.........................................................................................
B-1 C
Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Area........................................................
C-1 D
Sam pling Location Maps....................................................................................................
D-1 iii
LIST OF TABLES Title Paae Sam ple Collection and Analysis Program.................................................................
13 Sam pling Locations..................................................................................................
14 Missed Collections and Analyses..............................................................................
16 Radiation Environm ental Monitoring Program Sum m ary.........................................
19 The following tables are in the Appendices:
Appendix A Interlaboratory Comparison Program Results..........................................................
A1-1 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................................................
A2 Maximum Permissible Concentrations of Radioactivity in air and water above background in unrestricted areas.........................................................................
C-2 iv No.
5.1 5.2 5.3 5.4 A-1 A-2 A-3 A-4 A-5 A-6 A-7 Appendix C C-1
LIST OF FIGURES No.
Title Page 5-1 Offsite Ambient Radiation (TLDs), inner versus outer ring locations,1985-2001................. 17 5-2 Airborne Particulates; analysis for gross beta, average mean of all indicator locations (M-2, 3, 4, 5) versus control location (M-1), 1985-2001..................
I...18 Appendix D D-1 Sample collection and analysis program: TLD locations, General Area of Site Boundary...................................................................................................
D-2 D-2 Sample collection and analysis program: TLD locations, 4 to 5 miles Distant from the Plant, Control and Special Interest locations..............................................................................
D-3 D-3 Sample collection and analysis program: Radiological Environmental Monitoring Program, Sampling locations................................................................................................
D-4 V
1.0 INTRODUCTION
This report summarizes and interprets results of the Radiological Environmental Monitoring Program (REMP) conducted by Environmental, Inc., Midwest Laboratory for the Monticello Nuclear Generating Plant, Monticello, Minnesota, during the period January - December, 2001. 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 not included in this report. These data are included in a reference document (Environmental, Inc., Midwest Laboratory, 2002a) available at the Monticello Nuclear Generating Plant, Chemistry and Radiation Protection Department.
Monticello Nuclear Generating Plant is a boiling water reactor with a nominal generating capacity of 620 MWe. It is located on the Mississippi River in Wright County, Minnesota, and operated by Nuclear Management Company, LLC. Initial criticality was achieved on December 10, 1970.
Full power was achieved March 5, 1971 and commercial operation began on June 30, 1971.
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2.0
SUMMARY
The Radiological Environmental Monitoring Program (REMP) required by the U.S.
Nuclear Regulatory Commission (NRC) Technical Specifications and the Offsite Dose Calculation Manual (ODCM) for the Monticello Nuclear Generating Plant is described.
Results for the year 2001 are summarized and discussed.
Program findings show background levels of radioactivity in the environmental samples collected in the vicinity of the Monticello Nuclear Generating Plant.
No effect on the environment due to the operation of the Monticello Nuclear Generating Plant is indicated.
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3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 3.1 Program Design and Data Interpretation The purpose of the Radiological Environmental Monitoring Program (REMP) at the Monticello Nuclear Generating Plant 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 (TLD's).
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; (4)
Industrial and medical radioactive waste; and (5)
Fallout from nuclear accidents.
In interpreting the data, effects due to the Plant 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 Monticello Plant 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 plant 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 environmental samples collected from the Plant site. The Plant's monitoring program includes analyses for tritium and iodine-131.
Most samples are also analyzed for gamma-emitting isotopes with results for the following groups quantified: zirconium-95, cesium-137, cerium-144, beryllium-7, and potassium-40.
The first 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 10 days after reactor shutdown. On the other hand, 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). Beryllium-7 is of cosmogenic origin and potassium-40 is a naturally-occurring isotope. They were chosen as calibration monitors and should not be considered as radiological impact indicators.
3
Program Desigqn and Data Interpretation (continued)
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 final group, manganese-54, iron-59, cobalt-58 and -60, and zinc-65, are activation products and arise from activation of corrosion products. They are typical components of a nuclear power plant's effluents, but are not produced in significant quantities by nuclear detonations.
Other means of distinguishing sources of environmental radiation are employed in interpreting the data.
Current radiation levels are compared with previous levels, including those measured before the plant became operational. Results of the Plant'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 Radiological Environmental Monitoring Program (REMP) at the Monticello Plant is summarized in Table 5.1 and briefly reviewed below. Table 5.2 defines the sampling location codes used in Table 5.1 and specifies for each location its type (indicator or control) and its distance, direction, and sector relative to the plant site.
To assure that sampling is carried out in a reproducible manner, detailed sampling procedures have been prescribed (Monticello Generating Plant REMP Surveillances, Current Revision). Maps of sampling locations are included in Appendix D.
To monitor the air environment, airborne particulates are collected on membrane filters by continuous pumping at five locations. Also, airborne iodine is collected by continuous pumping through charcoal filters at all of these locations.
Filters are changed and counted weekly. Particulate filters are analyzed for gross beta activity and charcoal filters for iodine-131. Quarterly composites of particulate filters from each location are gamma-scanned on a HPGe detector. One of the five locations is a control (M-1), and four are indicators (M-2, M-3, M-4, M-5).
One of the indicators is located in the geographical sector expected to be most susceptible to any atmospheric emissions from the Plant (highest D/Q sector).
Ambient gamma radiation is monitored at forty locations, using CaSO4:Dy dosimeters with four sensitive areas at each location: fourteen in an inner ring in the general area of the site boundary, sixteen in the outer ring within 4-5 mile radius, six at special interest locations and four control locations, outside a 10 mile radius from the plant. They are replaced and measured quarterly.
An emergency set of TLDs is placed in the field along side of the regular set. The emergency TLDs are returned to EIML quarterly for annealing and repackaging.
Milk samples are collected monthly from three farms (two indicator and one control).
There are currently only two milk producers within the indicator area. Milk is collected biweekly during the growing season (May - October), because the milk animals may be on pasture. All samples are analyzed for iodine-131 and gamma-emitting isotopes.
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Proaram DescriDtion (continued)
Leafy green vegetables (cabbage) are collected annually from the highest D/Q garden and a control location and analyzed for iodine-131.
Corn and potatoes are collected annually only if the field is irrigated by water in which liquid radioactive effluent has been discharged. Analysis is for gamma-emitting isotopes.
The terrestrial environment is also monitored by the quarterly collections of well water from four locations. Samples are analyzed for tritium and gamma-emitting isotopes.
River water is collected weekly at two locations, one upstream of the plant and one downstream. Monthly composites are analyzed for gamma-emitting isotopes. Quarterly composites are analyzed for tritium.
Drinking water is collected weekly from the City of Minneapolis water supply, which is taken from the Mississippi River downstream of the Plant.
Monthly composites are analyzed for gross beta, iodine-131, and gamma-emitting isotopes.
Quarterly composites are analyzed for tritium.
The aquatic environment is also monitored by semi-annual upstream and downstream collections of fish, invertebrates, and shoreline sediments. Shoreline sediment is also collected semi-annually from one downstream recreational location.
All 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:
(1)
A partial air particulate/air iodine sample was obtained from location M-3 for the week ending 01-31-01, Power was lost for approximately 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> during an ice storm.
(2)
No air particulate/air iodine sample was available from location M-3 for the week ending 06-13-01, The circuit breaker was tripped.
(3)
Invertebrate samples were not available for the upstream and downstream river locations, M-8 and M-9 in May, 2001. Water levels were high due to above average rainfall.
(4)
TLD data was not available from location M-02S for the second quarter, 2001. Both the regular and emergency TLDs were lost in the field.
(5)
Milk samples were not available from M-28 (Hoglund Farm) from July 28 through December, 2001.
Dairy operations have been temporarily discontinued.
Deviations from the program are summarized in Table 5.3.
5
3.4 Laboratory Procedures The iodine-131 analyses in milk and drinking water were made using a sensitive radiochemical procedure which involves separation of the iodine using an ion-exchange method and solvent extraction and subsequent beta counting.
All gamma-spectroscopic analyses were performed with an HPGe detector. Levels of iodine-131 in cabbage and natural vegetation were determined by gamma spectroscopy.
Concentrations of airborne iodine-131 in charcoal samples were also determined by gamma spectroscopy.
Tritium was determined by a liquid scintillation technique.
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, 2000 ).
The QA Program includes participation in Interlaboratory Comparison (crosscheck)
Programs. Results obtained in the crosscheck programs are presented in Appendix A.
3.5 Progqram Modifications There were no program modifications made during the year 2001.
3.6 Land Use Census In accordance with the Offsite Dose Calculation Manual, sec. 07.01, a land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 ft2 producing fresh leafy vegetables, in each of the 16 meteorological sectors within a distance of 5 miles. The census shall also identify the locations of all milk animals and all 500 ft2 or greater gardens producing broad leaf vegetation in each of the meteorological sectors within a distance of three miles. This census shall be conducted at least once per year between the dates of May 1 and October 31.
New locations shall be added to the radiation environmental monitoring program within 30 days and sampling locations having lower calculated doses or a lower dose commitment may be deleted from this monitoring program after October 31 of the year in which the land use census was conducted. The 2001 land use census was conducted between August 6 and September 28, 2001. The highest D/Q locations did not change from the 2000 census, Detailed land use census data are contained in the Land Use Census and Critical Receptor Report, Monticello Nuclear Generating Plant, Chemistry and Radiation Protection Department.
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4.0 RESULTS AND DISCUSSION All of the scheduled collections and analyses were made except those listed in Table 5.3.
All results are summarized in Table 5.4 in a format recommended by the Nuclear Regulatory Commission in Regulatory Guide 4.8. For each type of analysis of each sampled medium, this table lists the mean and range for all indicator locations and for all control locations. The locations with the highest mean and range are also shown.
4.1 Atmospheric Nuclear Detonations and Nuclear Accidents There were no reported accidents at nuclear facilities and no atmospheric nuclear tests conducted in the year 2001. The last reported test was made by the People's Republic of China on October 16, 1980.
4.2 Summary of Preoperational Data The following constitutes a summary of preoperational studies conducted at the Monticello Nuclear Generating Plant during the years 1968 to 1970, to determine background levels expected in the environment, and provided, where applicable, as a means for comparison with present day levels. Strict comparisons, however, are difficult to make, since background levels of radiation were much higher in these years due to radioactive fallout from the atmosphere. Gross beta measurements in fallout averaged 20,600 pCi/m 2 in 1969 and 12,000 pCi/m 2 in 1970. These levels are reflected throughout the various media tested.
In the air environment, ambient gamma radiation (TLDs) averaged 9.1 mRem/4 weeks during preoperational studies (1970). Gross beta in air particulates in 1969 and 1970 averaged 0.20 pCi/m 3.
Present day levels have stabilized at around 0.025 pCi/m 3.
Airborne radioiodine remained below detection levels.
In the terrestrial environment of 1968 to 1970, milk, agricultural crops, and soil were monitored. In milk samples, low levels of Cs-137 and Sr-90 were detected. Cs-137 levels averaged 16.7 pCi/L. Soybean crop measurements in 1969 averaged 35.5 pCi/g for gross beta and 0.3 pCi/g for Cs-137. Gross beta measured in soil averaged 51.7 pCi/g. Present day measurements for cesium-137 are below detection levels in milk and agricultural crops.
The aqueous environment was monitored by testing of river water, bottom sediments, fish, aquatic vegetation, and periphyton. Specific location comparison of drinking, river, and well water concentrations for tritium and gross beta are not possible. However, tritium background levels, measured at seven separate locations from 1968 to 1970, averaged 970 pCi/L.
Present day environmental samples measure below detection levels. Values for gross beta, measured from 1968 to 1970, averaged 9.8 pCi/L in upstream and downstream Mississippi River water, 4.4 pCi/L for well waters, and 18.6 pCi/L for lake waters. Gamma emitters were below the lower limit of detection (LLD). In shoreline sediments, gross beta background levels in 1970 averaged 49.8 pCi/g for both upstream and downstream samples. Cs-137 activity averaged 0.10 pCi/g for both upstream and downstream samples. Low levels of Cs-1 37, occasionally observed today can still be attributed to residual activity from atmospheric fallout. Gross beta levels in 7
4.2 Summary of Preoperational Data (continued) fish flesh averaged 5.3 pCi/g in 1968 and 1969. Cs-137, measured in 1969 and 1970, averaged 0.044 pCi/g. Gross beta background levels, in 1970, for aquatic vegetation, algae, and periphyton samples measured 86.7 pCi/g, 76.5 pCi/g, and 28.1 pCi/g respectively.
4.3 Program Findings Results obtained show background levels of radioactivity in the environmental samples collected in the vicinity of the Monticello Nuclear Generating Plant.
Ambient Radiation (TLD's)
Ambient radiation was measured in the general area of the site boundary, at an outer ring 4 - 5 mi. distant from the Plant, at special interest areas and at four control locations.
The means were similar for both inner and outer rings (14.3 and 13.7 mRem/91 days, respectively). The mean for special locations was 13.5 mRem/91 days.
The mean for control locations was 14.1 mRem/91 days. Dose rates measured at the inner and outer ring locations were similar to those observed from 1985 through 2000 and are tabulated below. No plant effect on ambient gamma radiation is indicated (Figure 5-1).
Year Inner Rinq Outer Ring Doserate Rem/91 days) 1985 12.6 12.8 1986 14.6 14.1 1987 15.4 15.5 1988 14.8 14.7 1989 15.0 15.4 1990 16.1 16.2 1991 15.2 15.8 1992 15.1 15.1 1993 15.6 15.9 1994 14.6 14.0 1995 14.4 13.6 1996 14.0 13.5 1997 13.3 12.8 1998 15.0 14.4 1999 15.1 14.3 2000 15.1 14.5 2001 14.3 13.7 Ambient gamma radiation as measured by thermoluminescent dosimetry.
Average quarterly dose rates, Inner vs. Outer Ring locations 8
Airborne Particulates The average annual gross beta concentrations in airborne particulates were almost identical at indicator and control locations (0.027 pCi/m 3 and 0.026 pCi/m 3, respectively) and were similar to levels observed from 1985 through 2000. The results are tabulated below. The data for 1986 does not include the results from May 19 to June 9, 1986, which were influenced by the accident at Chernobyl. (Figure 5-2).
Year Indicators Control Concentration (pCi/m 3 )
1985 0.025 0.024 1986 0.026 0.026 1987 0.026 0.026 1988 0.030 0.030 1989 0.027 0.026 1990 0.023 0.023 1991 0.024 0.024 1992 0.023 0.023 1993 0.024 0.023 1994 0.023 0.024 1995 0.024 0.025 1996 0.023 0.023 1997 0.023 0.023 1998 0.023 0.023 1999 0.023 0.025 2000 0.027 0.026 2001 0.027 0.026 Average annual gross beta concentrations in airborne particulates.
A spring peak in beta activity had been observed almost annually for many years (Wilson et al., 1969). It had been attributed to fallout of nuclides from the stratosphere (Gold et al., 1964). It was pronounced in 1981, occurred to a lesser degree in 1982, and has not occurred since 1983. The highest averages occur during the months of January and December, and the first and fourth quarters, as seen in 1985 through 2001.
Two pieces of evidence indicate conclusively that the elevated activity observed during the first and fourth quarters was not attributable to the Plant operation. In the first place, elevated activity of similar size occurred simultaneously at both indicator and control locations.
Secondly, an identical pattern was observed at the Prairie Island Nuclear Generating Plant, about 100 miles distant from the Monticello Nuclear Generating Plant (XCEL Energy Corp., 2002b).
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 AI-Salih, 1955) was detected in all samples, with an average activity of 0.060 pCi/m 3 for all locations.
All other gamma-emitting isotopes were below their respective LLD limits.
9
Airborne Iodine Weekly levels of airborne iodine-131 were below the lower limit of detection (LLD) of 0.07 pCi/m 3 in all samples.
Milk Iodine-131 activity measured below the detection limit of 1.0 pCi/L in all samples.
Cesium-1 37 results were below the LLD level of 15 pCi/L in all samples.
No other gamma-emitting isotopes except naturally-occurring potassium-40, were detected in milk samples. This is consistent with the finding of the National Center for Radiological Health (1968) 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.
In summary, the milk data for 2001 show no radiological effects of the plant operation.
River Water and Drinkina Water Tritium was below the LLD of 330 pCi/L in all samples. Gross beta activity in Minneapolis drinking water averaged 2.5 pCi/L and was similar to average levels observed from 1985 through 2000. Gross beta averages are tabulated below.
Year Gross Beta (pCi/L) 1985 2.8 1986 2.5 1987 2.4 1988 2.7 1989 2.6 1990 2.2 1991 2.9 1992 2.1 1993 2.6 1994 2.0 1995 2.3 1996 2.1 1997 2.3 1998 2.4 1999 2.2 2000 2.5 2001 2.5 Average annual concentrations; Gross beta in drinking water.
Comparisons with data reported by the USEPA for Minneapolis drinking water samples collected in 1975, 1976, 1977, and 1978 indicate that concentrations of these nuclides are remaining fairly constant and are consistent with drinking water levels in other parts of the country. Gamma-emitting isotopes were below detection limits in all surface water samples. There was no indication of a plant effect.
10
Well Water Tritium measured below the LLD level of 330 pCi/L in all samples. All gamma isotopic results were below detection limits. There was no indication of a plant effect.
Crops Two samples of cabbage were collected in August and analyzed for iodine-131. Levels of 1-131 measured below 0.012 pCi/g wet weight in both samples.
There was no indication of a plant effect. There were no crops irrigated from the Mississippi River within 5 miles of the plant in 2001; therefore, no corn or potato samples were collected for analysis from irrigated fields.
Fish Fish samples were collected in May and October. Flesh was separated from the bones and gamma-scanned. Naturally-occurring potassium-40 was found to be similar in upstream and downstream samples (2.77 and 2.87 pCi/g wet weight, respectively). All gamma-emitting isotopes were below their respective LLD levels.
There was no indication of any plant effect.
Invertebrates Two samples were collected in October.
The samples were analyzed for gamma emitting isotopes. All gamma-emitting isotopes were below detection limits. There was no indication of any plant effect.
Shoreline Sediments Upstream, downstream and downstream recreational area shoreline sediment collections were made in May and October and analyzed for gamma-emitting isotopes.
Cesium-137 was detected in five of the six samples collected, averaging 0.051 pCi/g dry weight in downstream samples and 0.030 pCi/g dry weight in one of the two control samples, indicating the influence of fallout deposition. Similar levels of activities and distribution were observed in 1978-2000.
The only other gamma-emitting isotopes detected were naturally-occurring beryllium-7 and potassium-40.
There was no indication of a plant effect.
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5.0 FIGURES AND TABLES 12
Table 5.1. Sample collection and analysis program, Monticello Nuclear Generating Plant.
Collection Analysis Location Type and Type and Medium No.
Codes (and Type)a Frequencyb Frequencyc Ambient radiation (TLDs)
Airborne Particulates Airborne Iodine Milk 40 M-01A - M-14A M-01B - M-16B M-01S - M-06S M-01C - M-04C 5
M-1 (C), M-2, M-3, M-4, M-5 5
M-I(C), M-2, M-3, M-4, M-5 3
M-10 (C), M-24, M-28 C/Q C/W C/W G/Md G/W G/W G/Q 2
M-8(C), M-9 Surface water Drinking water 1
M-14 Well water Edible cultivated crops Corne Leafy Vegetable Potatoese Fish (one species, edible portion)
Periphyton or invertebrates Shoreline sediment 4
M-10(C), M-11, M-12, M-27 1
M-19 2
M-27, St. Cloud Farmer's Mkt. (C) 1 M-21 2
M-8(C), M-9 G/A G/A G/A G/SA G/SA G/SA 2
M-8(C), M-9 3
M-8(C), M-9, M-15 Ambient gamma GB, GS (QC of each location) 1-131 1-131, GS GS(MC), H-3(QC)
GB(MC), 1-131 (MC)
H-3, GS GS 1-131 GS GS GS GS a Location codes are defined in Table 5.2. Control stations are indicated by (C). All other stations are indicators.
b Collection type is coded as follows: Cl = continuous, G/ = grab. Collection frequency is coded as follows:
W= weekly, M = monthly, Q = quarterly, SA = semiannually, A = annually.
c Analysis type is coded as follows: GB = gross beta, GS = gamma spectroscopy, H-3 = tritium, 1-131 =
iodine 131. Analysis frequency is coded as follows: MC = monthly composite, QC = quarterly composite.
d Milk is collected biweekly during the grazing season (May - October), if milch animals are on pasture.
0 Collected only if the plant discharges radioactive effluent into the river, then only from river irrigated fields.
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Table 5.2. Sampling locations, Monticello Nuclear Generating Plant.
Distance and Direction from Code Type' Collection Site Sample Typeb Reactor Air Station M-1 Air Station M-2 Air Station M-3 Air Station M-4 Air Station M-5 Upstream of Plant Downstream of Plant Goenner Farm City of Monticello Plant Well #1 City of Minneapolis Montissippi Park River Irrigated Corn Fieldc River Irrigated Potato Fieldc Weinand Farm Wise residence (Highest D/Q Garden)
Hoglund Farm AP, Al AP, Al AP, Al AP, Al AP, Al SW, SS, BO, F SW, SS, BO, F M, WW WW WW DW SS M
VE, WW M
11.0 mi @ 3070/NW 0.9 mi @ 137°/SE 0.7 mi @ 104°/ESE 0.9 mi @ 146°/SSE 2.7 mi @ 134°/SE
"< 1000' upstream of Plant Intake
"< 1000' downstream of Plant Discharge 12.4 mi @ 322°/NW 3.4 mi @ 126°/SE 0.2 mi @ 2320/SW 37.0 mi @ 1320/SE 1.4 mi @ 114°/ESE 4.8 mi @ 1780/S 0.6 mi @ 198°/SSW 3.6 mi @ 300°/WNW General Area of the Site Boundary Sherburne Ave. So.
Sherburne Ave. So.
Sherburne Ave. So.
Biology Station Road Biology Station Road Biology Station Road County Road 75 County Road 75 County Road 75 County Road 75 County Road 75 County Road 75 North Boundary Road North Boundary Road TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD 0.7 mi @ 01I/N 0.8 mi @ 31°/NNE 1.3 mi @ 550/NE 0.6 mi @ 91°/E 0.6 mi @ 118 0/ESE 0.7 mi @ 1300/SE 0.6 mi @ 1480/SSE 0.6 mi @ 1700/S 0.6 mi @ 1920/SSW 0.5 mi @ 218 0°SW 0.4 mi @ 240°/WSW 0.4 mi @ 260°/W 0.8 mi @ 324 0/NW 0.7 mi @ 340 0/NNW 14 C
M-1 M-2 M-3 M-4 M-5 M-8 M-9 C
C M-10 M-11 M-12 M-14 M-1 5 M-19 M-21 M-24 M-27 M-28 M-01A M-02A M-03A M-04A M-05A M-06A M-07A M-08A M-09A M-10A M-11A M-12A M-13A M-14A
Table 5.2. Sampling locations, Monticello Nuclear Generating Plant, (continued).
Distance and Direction from Code Type' Collection Site Sample Typeb Reactor Approximately 4 to 5 miles Distant from the Plant M-01 B M-02B M-03B M-04B M-05B M-06B M-07B M-08B M-09B M-1OB M-1 1 B M-12B M-13B M-14B M-15B M-16B Special Interest Locations M-01S M-02S M-03S M-04S M-05S M-06S M-01C C
M-02C C
M-03C C
M-04C C
Sherco #1 Air Station County Road 11 County Road 73 & 81 County Road 73 (196th St.)
City of Big Lake County Road 14 and 196th St.
Monte Industrial Drive Residence, Hwy 25 & Davidson Ave.
Weinand Farm Reisewitz Farm, Acacia Ave.
Vanlith Farm, 97th Ave.
Lake Maria State Park Bridgewater Station Anderson Residence, Cty Rd. 111 Red Oak Wild Bird Farm Sand Plain Research Farm Osowski Fun Market Edgar Klucas Residence Big Oaks Park Pinewood School Rivercrest Christian Academy Monte Public Works Kirchenbauer Farm County Roads 4 and 15 County Rd 19 and Jason Ave.
Maple Lake Water Tower TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD 4.6 mi @ 03°IN 4.4 mi @ 200/NNE 4.3 mi @ 53°/NE 4.3 mi @ 6801ENE 4.4 mi @ 90°/E 4.4 mi @ 117 0/ESE 4.4 mi @ 136°/SE 4.7 mi @ 161°/SSE 4.8 mi @ 178°/S 4.2 mi @ 204°/SSW 4.0 mi @ 226°/SW 4.2 mi @ 2540/WSW 4.0 mi @ 270°/W 4.3 mi @ 289°/WNW 4.3 mi @ 309°/NW 4.3 mi @ 341°/NNW 0.6 mi @ 234°/SW 1.1 mi @ 143°/SE 1.6 mi @ 102°/ESE 2.4 mi @ 129°/SE 3.1 mi @ 118°/ESE 2.7 mi @ 134°/SE 11.5 mi @ 323°/NW 11.2 mi @ 47*/NE 13.0 mi @ 100°/E 10.3 mi @ 2260/ SW a "C" denotes control location. All other locations are indicators.
b Sample Codes:
AP Airborne particulates Al Airborne Iodine BS Bottom (river) sediments BO Bottom organisms DW Drinking Water F
M RW SS VE WW Fish Milk River Water Shoreline Sediments Vegetation / vegetables Well Water c Collected only if the plant discharges radioactive effluent into the river, then only from river irrigated fields.
15
Table 5.3. Missed collections and analyses at the Monticello Nuclear Generating Plant.
All required samples were collected and analyzed as scheduled with the following exceptions:
16 Plans for Preventing Recurrence AP/AI
- Beta, M-3 1/31/2001 Partial sample; -5 hours None required.
1-131 lost during ice storm.
BO Gamma M-8, M-9 5/16/2001 Seasonal non-availability; None required.
high river level due to above average rainfall.
AP/AI
- Beta, M-3 6/13/2001 Circuit breaker tripped.
Circuit and wiring inspected 1-131 Could not reset.
and updated.
TLD Ambient M-02S 7/3/2001 TLD lost in the field.
TLD placed on a new post Gamma Power pole moved after located in the right-of-way area.
sale of residence.
Ml
- Gamma, M-28 7/25/2001 Hoglund Dairy temporarily Hoglund will inform the MNGP 1-131 through out of dairy business, upon resumption of operation.
Dec., 2001
CJ
- 0)
-J (0
mRI91 days
-4 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001
-I, c*.
C3 CD 0
3 cn (D
CL 0 i.
0 CD cc CD W
0 0
a 0
-'I 3
0 Cl)
Figure 5-2. Airborne Particulates; analysis for gross beta, average mean of all indicator locations versus control location.
-- *-Indicators (M-2, 3, 0.035
_--E---
Control (M-1) 0.033 1
0.031 0.029 0.027 0.0250[_
E' 0.023 0.021 0.019_
0.017 -
0.015 I
r to (D
I-OD
- 0) 0
, N 03 I0--)
W r.-
0W M C.
(0 00 00 O0 C0
- 0)
- 0)
- 0) 0)3
- 0)
- 0)
- 0)
- 0)
- 0) 0 0
- 0)
- 0)
- 0)
- 0)
- 0)
- 0)
- 0)
- 0)
- 0)
- 0)
- 0)
- 0)
- 0)
- 0) 0M 0
0 Sr-T-
',r-N-
4 18
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Monticello Nuclear Generating Plant Wright, Minnesota (County, State)
Docket No.
Reporting Period 50-263 January-December, 2001 Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non Type Number of LLDb Mean (F)f Mean (F)0 Mean (F)0 Routine (Units)
Analysesa Rangec Locationd Range' Range0 Results8 TLD (Inner Ring, Gamma 56 3.0 14.3 (56/56)
M-12A,County Road 75 16.0 (4/4)
(See Control 0
General Area at (10.8-17.7) 0.4 mi @ 260°/W (12.5-17.7) below.)
Site Boundary) mRem/91 days)
TLD (Outer Ring, Gamma 64 3.0 13.7 (64164)
M-09B, Weinand Farm 15.0 (4/4)
(See Control 0
4-5 mi. distant)
(9.5-17.2) 4.8 mi @ 178°/S (11.1-17.2) below.)
mRemI91 days)
TLD (Special Gamma 23 3.0 13.5 (23/23)
M-06S, Monticello P.W.
15.4 (4/4)
(See Control 0
Interest Areas)
(10.0-17.7) 2.7 mi @ 134°/SE (12.5-17.7) below.)
mRem/91 days)
TLD (Control)
Gamma 16 3.0 None M-03C, County Rd.19 &
16.0 (4/4) 14.1 (16/16) 0 mRem/91 days)
Jason, 13.0 mi. @ 100°/E (15.1-17.0)
(11.6-16.6)
Airbome GB 259 0.005 0.027 (206/207)
M-5, Air Station 0.027 (51 /51) 0.026 (52/52) 0 Particulates (0.010-0.058) 2.7 mi @ 134°/SE (0.011-0.055)
(0.012-0.057)
(pCi/m 3)
GS 20 Be-7 0.015 0.060 (16/16)
M-5, Air Station 0.066(4/4) 0.062 (4/4) 0 (0.041-0.081) 2.7 mi @ 134°/SE (0.055-0.078)
(0.045-0.081)
Mn-54 0.0013
< LLD LLD 0
Co-58 0.0011
< LLD LLD 0
Co-60 0.0010
< LLD LLD 0
Zn-65 0.0015
< LLD LLD 0
Zr-Nb-95 0.0019
< LLD LLD 0
Ru-103 0.0015
< LLD LLD 0
Ru-106 0.0081
< LLD LLD 0
Cs-134 0.0008
< LLD LLD 0
Cs-1 37 0.0009
< LLD LLD 0
Ba-La-140 0.0020
< LLD LLD 0
Ce-141 0.0019
< LLD LLD 0
Ce-144 0.0056
< LLD LLD 0
Airbome Iodine 1-131 259 0.07
<LLD LLD 0
(pCi/m 3) 19
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Monticello Nuclear Generating Plant Wright, Minnesota
( County, State)
Docket No.
Reporting Period 50-263 January-December, 2001 20 Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non Type Number of LLDb Mean (F)0 Mean (F)0 Mean (F)f Routine (Units)
Analysesa Rangec Locationd Rangec Range' Resultse Milk (pCi/L) 1-131 50 1.0
< LLD
< LLD 0
GS 50 K-40 200 1374 (30/30)
M-24, Weinand Farm 1379 (20/20) 1361 (20/20) 0 (1220-1563) 4.8 mi @ 178°/S (1220-1563)
(1102-1487)
Cs-134 15
< LLD LLD 0
Cs-137 15
< LLD LLD 0
Ba-La-140 15
< LLD LLD 0
River Water H-3 8
330
< LLD
< LLD 0
(pCi/L)
GS 24 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
Zr-Nb-95 15
< LLD LLD 0
Cs-134 15
< LLD LLD 0
Cs-137 18
< LLD LLD 0
Ba-La-140 15
< LLD LLD 0
Ce-144 46
< LLD LLD 0
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Monticello Nuclear Generating Plant Wright, Minnesota
( County, State)
Docket No.
Reporting Period 50-263 January-December, 2001 Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non Type Number of LLDb Mean (F)c Mean (F)0 Mean (F)c Routine (Units)
Analysesa Range' Locationd Range0 Rangec Resultse Drinking Water GB 12 1.0 2.5 (12/12)
M-14, Minneapolis 2.5 (12/12)
None 0
(pCi/L)
(1.6-3.3) 37.0 mi. @ 1320 /SE (1.6-3.3) 1-131 12 1.0
< LLD None 0
H-3 4
330
< LLD None 0
GS 12 Mn-54 15
< LLD None 0
Fe-59 30
< LLD None 0
Co-58 15
< LLD None 0
Co-60 15
< LLD None 0
Zn-65 30
< LLD None 0
Zr-Nb-95 15
< LLD None 0
Cs-134 10
< LLD None 0
Cs-137 18
< LLD None 0
Ba-La-140 15
< LLD None 0
Ce-144 50
< LLD None 0
Well Water H-3 16 330
< LLD LLD 0
(pCi/L)
GS 16 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
Zr-Nb-95 15
< LLD LLD 0
Cs-134 10
< LLD LLD 0
Cs-137 18
< LLD LLD 0
Ba-La-140 15
< LLD LLD 0
Ce-144 61
< LLD LLD 0
Crops-Cabbage 1-131 2
0.013
< LLD LLD 0
(pCi/gwet) 21
Table 5.4 Radiological Environmental Monioring Program Summary Name of Facility Location of Facility Monticello Nuclear Generating Plant Wright, Minnesota
( County, State)
Docket No.
Reporting Period 50-263 January-December, 2001 Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non Type Number of LLDb Mean (F)0 Mean (F)'
Mean (F)f Routine (Units)
Analysesa Rangec Locationd Range' Rangec Resultse Fish GS 4
(pCi/g wet)
K-40 0.10 2.77 (2/2)
M-8, < 1000' Upstream 2.87 (2/2) 2.87 (2/2) 0 (2.68-2.85) from Plant Intake (2.75-2.99)
(2.75-2.99)
Mn-54 0.018
< LLD
< LLD 0
Fe-59 0.063
< LLD
< LLD 0
Co-58 0.013
< LLD
< LLD 0
Co-60 0.018
< LLD
< LLD 0
Zn-65 0.027
< LLD
< LLD 0
Zr-Nb-95 0.049
< LLD
< LLD 0
Cs-134 0.019
< LLD
< LLD 0
Cs-137 0.017 0.024 (1/2)
M-9, < 1000' Downstream 0.024 (112)
< LLD 0
from Plant Discharge Ba-La-140 0.10
< LLD
< LLD 0
Ce-144 0.11
< LLD
< LLD 0
Invertebrates GS 2
(pCi/g wet)
Be-7 2.99
< LLD
< LLD 0
K-40 7.65
< LLD
< LLD 0
Mn-54 0.27
< LLD
< LLD 0
Fe-59 0.34
< LLD
< LLD 0
Co-58 0.34
< LLD
< LLD 0
Co-60 0.35
< LLD
< LLD 0
Zn-65 0.61
< LLD
< LLD 0
Zr-Nb-95 0.27
< LLD
< LLD 0
Cs-134 0.31
< LLD
< LLD 0
Cs-137 0.18
< LLD
< LLD 0
Ba-La-140 0.53
< LLD
< LLD 0
Ce-144 1.50
< LLD
< LLD 0
22
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Monticello Nuclear Generating Plant Wright, Minnesota
( County, State)
Docket No.
Reporting Period 50-263 January-December, 2001 Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine (Units)
Analysesa Rangec Locationd Rangec Rangec Resultse Shoreline GS 6
Sediments Be-7 0.26
< LLD M-8, Upstream 0.39 (1/2) 0.39 (1/2) 0 (pCi/g dry)
< 1000' from Intake K-40 0.10 10.81 (4/4)
Indicators, M-9, M-15, 10.81 (4/4) 9.41 (212) 0 (10.39-11.23) identical means (10.39-11.23)
(8.83-9.99)
Mn-54 0.030
< LLD
< LLD 0
Co-58 0.030
< LLD
< LLD 0
Co-60 0.023
< LLD
< LLD 0
Zn-65 0.062
< LLD
< LLD 0
Nb-95 0.034
< LLD
< LLD 0
Zr-95 0.050
< LLD
< LLD 0
Ru-103 0.034
< LLD LLD 0
Ru-106 0.21
< LLD LLD 0
Cs-1 34 0.035
< LLD LLD 0
Cs-137 0.019 0.051 (4/4)
M-15, Montissippi Park 0.062 (2/2) 0.030 (1/2) 0 (0.039-0.068) 1.4 mi. @ 114*/ ESE (0.055-0.068)
Ba-La-140 0.064
< LLD
< LLD 0
Ce-144 0.11
< LLD
< LLD 0
a GB = gross beta, GS = gamma scan.
b LLD = nominal lower limit of detection based on a 4.66 sigma counting error for background sample.
c Mean and range are based on detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (F).
d Locations are specified: (1) by name, and/or station code (Table 2) and (2) by distance (miles) and direction relative to reactor site.
8 Non-routine results are those which exceed ten times the control station value. If no control station value is available, the result is considered non-routine if it exceeds ten time the typical preoperational value for the medium or location.
23
6.0 REFERENCES
CITED Arnold, J. R. and H. A. AI-Salih. 1955. Beryllium-7 Produced by Cosmic Rays. Science 121: 451-453.
Eisenbud, M. 1963. Environmental Radioactivity, McGraw-Hill, New York, New York, pp. 213, 275, 276.
Environmental, Inc., Midwest Laboratory.
2002a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January-December, 2000 through 2001.
2002b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 2000 through 2001.
2000.
Quality Assurance Program Manual, Rev. 0, 11 October 2000.
2000.
Quality Control Procedures Manual, Rev. 0, 21 September 2000.
2000.
Quality Control Program, Rev. 0, 12 October 2000.
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, Illinois, 369-382.
Hazleton Environmental Sciences Corporation.
1979a through 1983a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1978 through 1982.
1979b through 1983b.
Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1978 through 1982.
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 Helath and Data Reports, Vol. 9, Number 12, 730-746.
Northern States Power Company.
1969. Monticello Nuclear Generating Plant, Environmental Radiation Monitoring Program, Annual Report, June 18, 1968 to December 31, 1968. Minneapolis, Minnesota.
1970.
Monticello Nuclear Generating Plant, Environmental Radiation Surveillance, Annual Report, January 1, 1969 to December 31, 1969. Minneapolis, Minnesota.
1971.
Monticello Nuclear Generating Plant, Environmental Radiation Surveillance, Annual Report, January 1, 1970 to December 31, 1970. Minneapolis, Minnesota.
24
6.0 REFERENCES
CITED (continued)
Northern States Power Company.
Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1, to December 31, 1977 through 1982 (prepared by Hazleton Environmental Sciences). Minneapolis, Minnesota.
1984 through 2000. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 1983 through 1999 (prepared by Teledyne Brown Engineering Environmental Services, Midwest Laboratory). Northbrook, Illinois Teledyne Brown Engineering Environmental Services, Midwest Laboratory.
1984a to 2000a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 1983 through 1999.
1984b to 2000b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 1983 through 1999.
U.S. Dep't of Energy 1997 HASL-300, Edition 28, Procedures Manual, Environmental Measurements Laboratory, New York, NY.
U.S. Environmental Protection Agency.
1980. Prescribed Procedures for Measurement of Radioactivity in Drinking Water, Cincinnati, Ohio (EPA-600/4-80-032).
1984.
Eastern Environmental Radiation Facility, Radiochemistry Procedures Manual, Montgomery, Alabama (EPA-520/5-84-006).
Wilson, D. W., G. M. Ward and J. E. Johnson. 1969. In Environmental Contamination by Radioactive Materials, International Atomic Energy Agency. p.125.
XCEL Energy Corporation.
2002. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2000 through 2001. (prepared by Environmental, Inc., Midwest Laboratory). Northbrook, Illinois 25
~
Environmental, Inc.
Midwest Laboratory an Allegheny Technologies Co.
700 Landwehr Road
- Northbrook, IL 60062-2310 (847) 564-0700 fax (847) 564-4517 APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS NOTE: Environmental, Inc., Midwest Laboratory participates in intercomparison studies administered by Environmental Resources Associates, and serves as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada. Results are reported in Appendix A. TLD Intercomparison results, in-house spikes, blanks, duplicates and mixed analyte performance evaluation program results are also reported. Appendix A is updated four times a year; the complete Appendix is included in March, June, September and December monthly progress reports only.
January, 2001 through December, 2001
Appendix A Interlaboratory Comparison Program Results Environmental, Inc., Midwest Laboratory, formerly Teledyne Brown Engineering Environmental 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 (e.g., milk or water) 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.
The results in Table A-1 were obtained through participation in the environmental sample crosscheck program for milk, water and air filters during the past twelve months. Data for previous years is available upon request.
This program was conducted by the U.S. Environmental Protection Agency Office of Research and Development National Exposure Research Laboratory Characterization Research Division-Las Vegas, Nevada.
The results in Table A-2 were obtained for Thermoluminescent Dosimeters (TLDs), via various International Intercomparisons of Environmental Dosimeters under the sponsorships listed in Table A-2.
Results of crosscheck testing with Teledyne Brown Engineering are 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.
Table A-5 list results of the in-house "duplicate" program for the past twelve months. Acceptance is based on the difference of the results being less than the sum of the errors. 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
12-31-01 ATTACHMENT A ACCEPTANCE CRITERIA FOR "SPIKED" SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSES' One Standard Deviation Analysis Level for single determinations Gamma Emitters Strontium-89b Strontium-90b Potassium-40 Gross alpha Gross beta Tritium Radium-226,-228 Plutonium Iodine-131, Iodine-1 29b Uranium-238, Nickel-63b Technetium-99b Iron-55b 5 to 100 pCi/liter or kg
> 100 pCi/liter or kg 5 to 50 pCi/liter or kg
> 50 pCi/liter or kg 2 to 30 pCi/liter or kg
> 30 pCi/liter or kg
> 0.1 g/liter or kg 20 pCi/liter
> 20 pCi/liter 100 pCi/liter
> 100 pCi/liter 4,000 pCi/liter
> 4,000 pCi/liter 0.1 pCi/liter 0.1 pCi/liter, gram, or sample 55 pCi/liter
> 55 pCi/liter 35 pCi/liter
> 35 pCi/liter 50 to 100 pCi/liter
> 100 pCi/liter Othersb 5.0 pCi/liter 5% of known value 5.0 pCi/liter 10% of known value 5.0 pCi/liter 10% of known value 5% of known value 5.0 pCi/liter 25% of known value 5.0 pCi/liter 5% of known value Is = (pCi/liter) =
169.85 x (known)0 9""
10% of known value 15% of known value 10% of known value 6.0 pCi/liter 10% of known value 6.0 pCi/liter 15% of known value 10 pCi/liter I
10% of known value 20% of known value A2 From EPA publication, "Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981-1982, EPA-60014-81-004.
b Laboratory limit.
Table A-1.
Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)'.
Concentration in pCi/Lb Lab Sample Date Control Code Type Collected Analysis Laboratory resultc ERA ResultV Limits WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER Gr. Alpha Gr. Beta 1-131 Ra-226 Ra-228 Uranium H-3 Gr. Alpha Ra-226 Ra-228 Uranium Co-60 Cs-I 34 Cs-137 Gr. Beta Sr-89 Sr-90 Ba-I 33 Co-60 Cs-134 Cs-1 37 Zn-65 Ra-226 Ra-228 Uranium Sr-89 Delay in processing may have attributed to deviation.
Result of reanalysis; Sr-89, 35.3 +/- 4.4 pCi/L. Sr-90, 25.0 +/- 2.8 pCi/L.
1-921 WATER Jul, 2001 Sr-90 26.3 +/- 1.1 V-922 WATER Jul, 2001 Gr. Alpha 23.3+/-1.9
/-922 WATER Jul, 2001 Gr. Beta 48.5+/- 4.6
/-924 WATER Aug, 2001 H-3 2,680.0+/- 41.9
/-931 WATER Sep, 2001 Ra-226 10.9+/- 0.2
/-931 WATER Sep, 2001 Ra-228 9.7+/- 1.1 1-931 WATER Sep, 2001 Uranium 11.2+/-0.1 1-932 WATER Oct, 2001 1-131 7.7+/-0.3
/-933 WATER Oct, 2001 Gr. Alpha 82.2 +/- 4.0
/_T,1 WATER Oct. 2001 Ra-226 9.5+/- 1.2 STW-897 STW-897 STW-900 STW-902 STW-902 STW-902 STW-903 STW-917 STW-917 STW-917 STW-917 STW-918 STW-918 STW-918 STW-918 STW-918 STW-918 STW-919 STW-919 STW-919 STW-919 STW-919 STW-920 STW-920 STW-920 STW-921 31.9+/-2.1 25.3 +/- 2.7 27.2 +/- 0.8 4.0_+/- 0.1 13.8+/-0.4 17.0+/- 0.3 17,400.0 +/- 69.7 57.4 +/- 3.5 13.5+/-0.4 10.1 +/--0.6 14.2+/-0.2 27.9+/-1.4 16.0+/-0.4 195.4+/-1.5 340.0+/- 51.0 62.8 +/- 5.7 34.2+/-1.6 37.8 +/- 1.2 49.9 +/- 0.7 16.0+/- 1.4 208.0+/-1.7 37.8 +/- 0.7 14.6+/-0.4 6.2 +/- 0.2 49.0+/-1.0 19.8+/- 1.5 Al-1 Jan, 2001 Jan, 2001 Feb, 2001 Feb, 2001 Feb, 2001 Feb, 2001 Mar, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jul, 2001 45.7 +/- 11.4 16.7 +/-5.0 28.3+/- 3.0 4.7 +/- 0.7 14.4 +/- 3.6 20.4 +/- 3.0 17,800.0 +/-1,780.0 56.0 +/- 14.0 17.7+/-2.7 8.1 +/- 2.0 15.6 +/- 3.0 26.4 +/- 5.0 16.9 +/- 5.0 186.0 +/-9.3 343.0+/-1.7 64.1 +/- 5.0 33.8 +/- 5.0 36.0 +/- 5.0 46.8 +/- 5.0 15.9 +/- 5.0 197.0 +/-9.9 36.2 +/- 5.0 15.4+/-2.3 4.5+/- 1.1 55.7 +/- 5.6 31.2 +/- 5.0 25.9 +/- 5.0 17.8+/- 5.0 53.0+/- 10.0 2,730.0 +/- 356.0 10.8++/-1.6 9.0 +/- 2.2 13.1 +/-3.0 7.7 +/- 2.0 97.5 +/- 24.4 10.8 +/- 1.6 25.9 - 65.5 8.0 - 25.4 23.1 - 33.5 3.4 - 5.9 8.2 - 20.6 15.2 -25.6 14,700. - 20,900.0 31.8-80.2 13.1 -22.3 4.6-11.6 10.4 - 20.8 17.7-35.1 8.2 - 25.6 170.0 - 202.0 252.0 - 428.0 55.5 - 72.8 25.1 - 42.5 27.3 - 44.7 38.1 - 55.5 7.2 - 24.6 180.0 - 214.0 27.5 - 44.9 11.4-19.4 2.6 - 6.5 46.1 - 65.3 22.5 - 39.9
.17.2 - 34.6 9.1 - 26.5 35.7 - 70.3 2,110.0 - 3,350.0 8.0- 13.6 5.1 - 12.8 7.9-18.3 4.2-11.2 55.3-140.0 8.0-13.6 STm STW STV STW STW STW STW STV STV S'l' V U J I ~
Table A-I.
Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.
Concentration in pCilLb Lab Sample Date Control Code Type Collected Analysis Laboratory result' ERA ResulIt Limits STW-933 WATER Oct, 2001 Ra-228 17.0+/- 0.8 15.6 +/- 3.9 8.9-22.4 STW-933 WATER Oct, 2001 Uranium 32.2 +/- 1.4 37.2 +/- 3.7 30.7 - 43.6 STW-934 WATER Oct, 2001 Co-60 82.4+/- 0.9 78.4+/- 5.0 69.7-87.1 STW-934 WATER Oct, 2001 Cs-134 52.2 +/-1.3 54.1 +/- 5.0 45.4-62.8 STW-934 WATER Oct, 2001 Cs-137 39.4+/-0.6 37.9 +/- 5.0 26.3-43.7 STW-934 WATER Oct, 2001 Gr. Beta 166.0+/-7.1 192.0 +/-28.8 142.0 - 242.0 STW-934 WATER Oct, 2001 Sr-89 12.8+/- 0.8 16.7+/-5.0 8.0- 25.4 STW-934 WATER Oct, 2001 Sr-90 6.8 +/- 0.7 7.7 +/- 5.0
-1.0 - 16.4 STW-935 WATER Oct, 2001 Gr. Alpha 63.5i 2.5 64.0+/-16.0 36.5 - 91.5 STW-935 WATER Oct, 2001 Gr. Beta 26.0+/-1.2 21.5 +/- 5.0 12.8-30.2 STW-938 WATER Nov, 2001 Ba-133 66.7+/- 1.2 69.3 +/- 6.9 57.5-81.1 STW-938 WATER Nov, 2001 Co-60 59.3 +/- 0.6 59.7 +/- 5.0 51.0 - 68.4 STW-938 WATER Nov, 2001 Cs-134 86.7+/- 1.5 93.9+/- 5.0 85.2-103.0 STW-938 WATER Nov, 2001 Cs-137 45.0+/-1.0 42.0+/- 5.0 33.3-50.7 STW-938 WATER Nov, 2001 Zn-65 80.7+/-0.6 77.3+/-7.7 63.9-90.7 Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the environmental samples crosscheck program operated by Environmental Resources Associates (ERA).
All results are in pCi/L, except for elemental potassium (K) data in milk, which are in mg/L; air filter samples, which are in pCi/Filter.
c Unless otherwise indicated, the laboratory result is given as the mean +/- standard deviation for three determinations.
d Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA.
Al -2
Table A-2. Crosscheck program results; Thermoluminescent Dosimeters. (TLDs).
mR Lab Known Lab result Code TLD Type Date Measurement Value
+/- 2 Sigma Control Limits Teledyne Brown Enqineerinq 2000-1 LiF-100 Chips 2000-1 LiF-100 Chips 2000-1 LiF-100 Chips Mar, 2000 Mar, 2000 Mar, 2000 Reader 1, #1 Reader 1, #2 Reader 1, #3 17.8 35.5 62.2 14.4+/-0.2 32.4+/-0.1 61.8 +/- 0.9 12.46 - 23.14 24.85 - 46.15 43.54 - 80.86 Teledyne Brown Enqineeringq 2000-2 CaSO,: Dy Cards Mar, 2000 2000-2 CaSO,: Dy Cards Mar, 2000 2000-2 CaSO,: Dy Cards Mar, 2000 Chips and cards irradiated by Teledyne 12th International Intercomparison 022-1 022-1 022-1 022-1 022-1 CaSO,: Dy Cards CaSO,,: Dy Cards CaSO,: Dy Cards CaSO,: Dy Cards CaSO4: Dy Cards Jun, 2000 Jun, 2000 Jun, 2000 Jun, 2000 Jun, 2000 Reader 1,#1 17.8 Reader 1,#2 35.5 Reader 1, #3 62.2 Brown Engineering, Westwood, Field Field 1 Field 2 Field 3 Lab, 1 161.0 548.0 391.0 623.0 391.0 21.3 +/- 0.3 40.1 +/-1.9 69.9 +/- 3.5 New Jersey, in March 184.9+/-1.9 502.2+/-1.7 412.0 +/-2.9 643.2 +/- 2.9 442.8 +/- 2.5 12.46 - 23.14 24.85 - 46.15 43.54 - 80.86 of 2000.
112.70 - 209.30 383.60 - 712.40 273.70 - 508.30 436.10 - 809.90 273.70 - 508.30 Environmental, Inc.
2001-1 CaSO,: Dy Cards 2001-1 CaSO,: Dy Cards 2001-1 CaSO,: Dy Cards 2001-1 CaSO,: Dy Cards 2001-1 CaSO,: Dy Cards 2001-1 CaSO,: Dy Cards 2001-1 CaSO,: Dy Cards 2001-1 CaSO,: Dy Cards Dec, 2001 Dec, 2001 Dec, 2001 Dec, 2001 Dec, 2001 Dec, 2001 Dec, 2001 Dec, 2001 Reader 1,#1 Reader 1, #1 Reader 1, #2 Reader 1, #2 Reader 1, #3 Reader 1, #3 Reader 1, #4 Reader 1, #4 4.0 4.0 7.1 7.1 15.9 15.9 63.6 63.6 3.7+/-0.1 3.4+/-0.1 7.9+/-0.2 7.6+/-0.3 18.6+/-0.4 19.6+/-0.1 78.2 +/- 1.2 79.9 +/- 2.5 2.79-5.17 2.79 - 5.17 4.95-9.19 4.95-9.19 11.13 - 20.67 11.13-20.67 44.53 - 82.69 44.53 - 82.69 A2-1
Table A-3.
In-house "spike" samples.
Concentration in pCi/La Lab Sample Date Laboratory results Known Controlc Code Type Collected Analysis 2s, n=lb Activity Limits SPAP-477 SPW-479 SPW-481 SPW-481 SPW-482 SPW-482 SPW-483 SPW-483 Sample was SPW-485 SPW-485 SPW-485 SPW-485 SPAP-754 SPW-1 037 SPW-1037 SPW-1224 SPW-1224 SPW-1225 SPW-1225 SPW-1272 SPW-1272 SPVE-1274 SPCH-1 276 SPMI-1270 SPM1-1270 The Cs-137 SPMI-1270 SPU-2901 SPW-2161 SPU-3128 SPW-3129 Air Filter Water Water Water Water Water Water Water lost during Water Water Water Water Air Filter Water Water Water Water Water Water Water Water Vegetation Charcoal Milk Milk spike is sus Milk Urine Water Urine Water Jan, 2001 Cs-137 1.76+/-0.02 1.68 Jan, 2001 H-3 54702.00 +/- 644.00 54549.00 Jan, 2001 Gr. Alpha 58.08+/-2.79 69.14 Jan, 2001 Gr. Beta 213.83+/-3.07 220.26 Jan, 2001 Gr. Alpha 51.77 +/- 2.18 69.14 Jan, 2001 Gr. Beta 202.48 +/-2.98 220.26 Jan, 2001 Ra-226 20.11 +/-0.34 20.86 Jan, 2001 Ra-228 10.55+/-2.02 19.43 analysis. Insufficient sample available to perform reanalysis.
Jan, 2001 Co-60 33.53+/-3.40 31.13 Jan, 2001 Cs-1 34 32.80+/-2.54 30.81 Jan, 2001 Cs-1 37 42.10+/-5.60 36.00 Jan, 2001 Sr-90 154.34 +/- 3.49 137.66 Jan, 2001 Gr. Beta 8.53 +/- 0.02 7.88 Feb, 2001 U-233/4 3.74+/-0.10 4.17 Feb, 2001 U-238 3.81 +/-0.10 4.17 Feb, 2001 Ra-226 21.25+/-0.50 20.68 Feb, 2001 Ra-228 21.76+/-2.65 19.27 Feb, 2001 Gr. Alpha 71.87+/-3.07 69.14 Feb, 2001 Gr. Beta 36.30+/-1.47 28.75 Feb, 2001 1-131 56.82+/- 0.71 63.05 Feb, 2001 1-131(g) 65.69+/-10.21 63.05 Feb, 2001 1-131(g) 0.78+/-0.05 0.76 Feb, 2001 1-131(g) 1.57 +/-0.05 1.58 Mar, 2001 Cs-134 31.89 +/-4.71 29.77 Mar, 2001 Cs-1 37 46.61 +/-8.81 35.90 pect; A new cesium spike has been prepared. Reference to S Mar, 2001 1-131(g) 81.92+/-10.80 81.95 Mar, 2001 H-3 51512.00+/-1369.00 50189.00 Mar, 2001 Ra-228 29.92+/- 5.13 31.75 Apr, 2001 H-3 2065.00+/-408.00 2008.00 Apr, 2001 Gr. Alpha 37.94+/- 2.42 34.57 1.01 - 2.35 43639.20 - 65458.80 34.57 - 103.71 198.23 - 242.29 34.57 - 103.71 198.23 - 242.29 14.60 - 27.12 13.60 - 25.26 21.13-41.13 20.81 - 40.81 26.00 - 46.00 110.13 - 165.19
-2.12 - 17.88 2.50 - 5.84
-7.83-16.17 14.48 - 26.88 13.49 - 25.05 34.57 - 103.71 18.75 - 38.75 50.44 - 75.66 53.05 - 73.05 0.45 -'1.06 0.95 - 2.21 19.77 - 39.77 25.90 - 45.90 PMI-3232.
71.95 - 91.95 40151.20 - 60226.80 22.23 - 41.28 1317.37 - 2698.63 17.29 - 51.86 A3-1
Table A-3.
In-house "spike" samples.
Concentration in pCi/L2 Lab Sample Date Laboratory results Known Controlc Code Type Collected Analysis 2s, n=lb Activity Limits SPW-3129 SPAP-3508 SPMI-3232 SPMI-3232 SPMI-3232 SPMI-3232 SPMI-3232 SPSO-3356 SPSO-3356 SPAP-3359 SPW-3376 SPW-3376 SPW-3376 SPW-3377 SPW-3129/1 SPW-3129/1 SPW-3129/2 SPW-3129/2 SPVE-3303 SPSO-5701 SPSO-5701 SPW-5779 SPW-5779 SPW-5779 SPF-5781 SPF-5781 SPW-5937 SPW-59441 SPW-59441 SPAP-5703 SPW-3129/3 Water Air Filter Milk Milk Milk Milk Milk Soil Soil Air Filter Water Water Water Water Water Water Water Water Vegetation Soil Soil Water Water Water Fish Fish Water Water Water Air Filter Water Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 May, 2001 May, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Gr. Beta Gr. Beta Cs-134 Cs-1 37 1-131 1-131(g)
Sr-90 Co-60 Cs-1 37 Cs-1 37 Co-60 Cs-134 Sr-90 1-131 Gr. Alpha Gr. Beta Gr. Alpha Gr. Beta 1-131(g)
Co-60 Cs-137 Co-60 Cs-137 Sr-90 Co-60 Cs-1 37 H-3 Ra-226 Ra-228 Cs-137 Gr. Alpha 117.83 +/- 2.37 0.80 +/- 0.01 32.69 +/- 6.50 44.20 +/- 9.08 48.05 +/- 0.90 55.64 +/- 11.39 143.77 +/- 3.04 18.49 +/- 0.21 18.71 +/-0.24 1.80 +/- 0.01 48.17+/-4.85 37.14+/- 3.90 159.84 +/- 3.42 68.60 +/- 2.63 37.94 +/- 2.42 117.83 +/- 2.37 34.42 +/- 2.14 119.99 +/-2.45 0.81 +/- 0.03 17.42 +/-0.19 16.03 +/- 0.22 250.05 +/- 18.63 178.68 +/- 19.89 72.12+/- 2.24 1.87 +/- 0.08 1.43 +/- 0.07 51177.00 +/- 631.00 36.62 +/-1.74 41.46 +/- 6.44 1.81 +/- 0.02 35.31 +/- 3.04 109.46 0.78 33.96 35.79 56.68 56.68 136.82 19.57 16.61 1.67 45.19 33.96 136.82 85.02 34.57 109.46 34.57 109.46 0.86 19.05 16.52 233.26 175.91 68.12 1.79 1.39 50189.00 34.46 36.06 1.67 34.75 98.51 - 120.41
-9.22 - 10.78 23.96 - 43.96 25.79 - 45.79 45.34 - 68.02 46.68 - 66.68 109.46 - 164.18 9.57 - 29.57 6.61 - 26.61 1.00-2.34 35.19 - 55.19 23.96 - 43.96 109.46 - 164.18 68.02 - 102.02 17.29 - 51.86 98.51 - 120.41 17.29 - 51.86 98.51 - 120.41 0.51 -1.20 9.05 - 29.05 6.52 - 26.52 209.93 - 256.59 158.32 -'193.50 54.50 - 81.74 1.07-2.51 0.83 - 1.95 40151.20 - 60226.80 24.12 - 44.80 25.24 - 46.88 1.00-2.34 17.38 - 52.13 A3-2
Table A-3.
In-house "spike" samples.
Concentration in pCi/La Lab Sample Date Laboratory results Known Control' Code Type Collected Analysis 2s, n=lb Activity Limits SPW-3129/3 Water Jul, 2001 Gr. Beta 113.28+/-3.65 109.46 98.51 - 120.41 SPMI-6145 Milk Jul, 2001 Cs-137 188.45+/-19.10 175.91 158.32 - 193.50 SPW-6604 Water Jul, 2001 Gr. Alpha 35.36 +/- 1.94 34.57 17.29 - 51.86 SPW-6604 Water Jul, 2001 Gr. Beta 112.56 +/-2.46 108.82 97.94 - 119.70 SPW-9008 Water Oct, 2001 H-3 48285.00+/-606.10 50189.00 40151.20-60226.80 SPAP-9010 Air Filter Oct, 2001 Cs-137 1.91 +/- 0.01 1.67 1.00 -2.34 SPW-10723 Water Dec, 2001 U-233/4 40.12+/-1.09 41.73 25.04 - 58.42 SPW-1 0723 Water Dec, 2001 U-238 40.16+/-1.09 41.73 29.21 - 54.25 SPAP-11550 Air Filter Dec, 2001 Gr. Beta 1.58 +/- 0.02 1.56
-.8.44 - 11.56 SPW-11757 Water Dec, 2001 Co-60 43.82+/-3.14 41.36 31.36 - 51.36 SPW-11757 Water Dec, 2001 Cs-134 24.11 +/- 2.42 22.59 12.59 - 32.59 SPW-1 1757 Water Dec, 2001 Cs-137 52.11 +/-4.40 50.89 40.89 - 60.89 SPMI-11759 Milk Dec, 2001 Cs-134 28.03+/-2.64 27.10 17.10 - 37.10 SPMI-11759 Milk Dec, 2001 Cs-137 54.59+/- 5.08 50.89 40.89 - 60.89 SPF-11761 Fish Dec, 2001 Cs-134 0.94+/- 0.02 0.90 0.54-1.26 SPF-11761 Fish Dec, 2001 Cs-137 1.43+/- 0.04 1.43 0.86-2.00 "a
All results are in pCi/L, except for elemental potassium (K) in milk, which are in mg/L.; air filter samples, which are in pCi/Filter; and food products, which are in pCi/kg.
b Results are based on single determinations.
c Control limits are based on Attachment A, Page A2 of this report.
NOTE: For fish, Jello is used for the spike matrix. For vegetation, coleslaw is used for the spike matrix.
A3-3
Table A-4.
In-house "blank" samples.
Lab Code SPAP-478 SPAP-478 SPAP-478 SPW-480 SPW-484 SPW-484 SPW-484 SPW-484 SPW-486 SPW-486 SPW-486 SPW-486 SPAP-755 SPW-1038 SPW-1038 SPW-1223 SPW-1223 SPW-1223 SPW-1223 SPMI-1268 SPMI-1268 SPMI-1268 SPW-1 271 SPW-1271 SPW-1 271 SPVE-1273 VEGETATION SPVE-1273 VEGETATION SPCH-1275 CHARCOAL CANISTER SPW-2164 WATER SPU-3126 URINE 2.0 ml. sample volume.
Sample Date Sample Type AIR FILTER AIR FILTER AIR FILTER WATER WATER WATER WATER WATER WATER WATER WATER WATER AIR FILTER WATER WATER WATER WATER WATER WATER MILK MILK MILK WATER WATER WATER Jan 2001 Jan 2001 Jan 2001 Jan 2001 Jan 2001 Jan 2001 Jan 2001 Jan 2001 Jan 2001 Jan 2001 Jan 2001 Jan 2001 Jan 2001 Feb 2001 Feb 2001 Feb 2001 Feb 2001 Feb 2001 Feb 2001 Feb 2001 Feb 2001 Feb 2001 Feb 2001 Feb 2001 Feb 2001 Feb 2001 Feb 2001 Feb 2001 Mar 2001 Apr 2001 Analysis Co-60 Cs-1 34 Cs-1 37 H-3 Gr. Alpha Gr. Beta Ra-226 Ra-228 Co-60 Cs-134 Cs-1 37 Sr-90 Gr. Beta U-238 U-238 Gr. Alpha Gr. Beta Ra-226 Ra-228 Cs-1 34 Cs-137 1-131(g)
Co-60 Cs-134 Cs-1 37 Cs-134 Cs-137 1-131(g)
< 0.02
< 642.00 0.05 +/- 0.01
-66.00 +/- 335.00
<1.0
<200.0 A4-1 Concentration pCi/LU.
Laboratory results Acceptance (4.66 Sigma)
Criteria LLD Activityb (4.66 Sigma)
< 1.12
<100.0
< 1.66
<100.0
< 2.46
<100.0
< 162.00
-1.86 +/-80.40
<200.0
< 0.68
<1.0
< 1.35
<3.2
< 0.02 0.03 +/-0.01
<1.0
< 0.97 0.43 +/- 0.50
<2.0
< 2.68
<10.0
< 3.46
<10.0
< 5.43
<10.0
< 0.65 0.06 +/- 0.31
<1.0
< 1.60 0.16 +/-0.90
<3.2
< 0.03
<1.0
< 0.00
<1.0
< 0.46
<1.0
< 1.50
<3.2
< 0.02 0.03 +/-0.01
<1.0
< 0.95 0.45 +/- 0.49
<2.0
< 5.86
<10.0
< 3.02
<10.0
< 7.46
<20.0
< 1.06
<10.0
< 2.61
<10.0
< 2.37
<10.0
< 10.04
<100.0
< 6.00
<100.0
< 0.01
<9.6
Table A-4.
In-house "blank" samples.
Concentration pCi/La.
Laboratory results Acceptance Lab Sample Sample (4.66 Sigma)
Criteria Code Type Date Analysis LLD Activity' (4.66 Sigma)
SPDW-3130 SPDW-3130 SPMI-3233 SPMI-3233 SPMI-3233 SPMI-3233 SPMI-3233 Low levels of unusual.
SPSO-3357 SPSO-3357 SPAP-3358 SPW-3375 SPW-3375 SPW-3375 SPW-3375 SPDW-3130 SPDW-3130 SPDW-3130 SPDW-3130 SPVE-3304 SPVE-3304 SPVE-3304 SPSO-5702 SPSO-5702 SPSO-5702 SPAP-5704 SPAP-5704 SPAP-5704 SPW-5780 SPW-5780 SPW-5780 WATER Apr 2001 WATER Apr 2001 MILK Apr2001 MILK Apr2001 MILK Apr2001 MILK Apr2001 MILK Apr2001 Sr-90 are still detected in the SOIL SOIL AIR FILTER WATER WATER WATER WATER WATER WATER WATER WATER VEGETATION VEGETATION VEGETATION SOIL SOIL SOIL AIR FILTER AIR FILTER AIR FILTER WATER WATER WATER Apr 2001 Apr 2001 Apr 2001 Apr 2001 Apr 2001 Apr 2001 Apr 2001 May 2001 May 2001 Jun 2001 Jun 2001 Jun 2001 Jun 2001 Jun 2001 Jul 2001 Jul 2001 Jul 2001 Jul 2001 Jul 2001 Jul 2001 Jul 2001 Jul 2001 Jul 2001 Gr. Alpha Gr. Beta Cs-137 1-131 1-131(g)
Sr-89 Sr-90 environment.
Cs-1 34 Cs-1 37 Cs-137 Co-60 Cs-134 1-131(g)
Sr-90 Gr. Alpha Gr. Beta Gr. Alpha Gr. Beta Co-60 Cs-1 34 Cs-137 Co-60 Cs-1 34 Cs-1 37 Co-60 Cs-1 34 Cs-1 37 Co-60 Cs-1 34 Cs-1 37
< 0.54
< 1.46
< 2.66
< 0.26
< 3.91
< 0.79 A concentration of
< 14.77
< 11.72
< 0.55
< 2.90
< 3.71
< 0.39
< 0.56
< 0.45
< 1.26
< 0.44
< 1.46
< 7.06
< 11.56
< 8.30
< 12.80
< 13.96
<8.10
< 0.79
< 0.84
< 0.60
< 1.86
< 2.46
< 3.77 0.04 +/- 0.38 0.67 +/- 1.04
-0.06 +/-0.14
-0.32 +/- 0.79 1.18 +/-0.35 (1-5 pCi/L) in milk 0.02 0.05 0.15 0.34 0.09 0.66
+/- 0.22
+/- 0.27
+/- 0.34
+/- 0.95
+/- 0.32
+/- 1.04 A4-2
<1.0
<3.2
<10.0
<0.5
<20.0
<5.0
<1.0 is not
- <100.0
<100.0
<100.0
<10.0
<10.0
<20.0
<1.0
<1.0
<3.2
<1.0
<3.2
<100.0
<100.0
<100.0
<100.0
<100.0
<100.0
<100.0
<100.0
<100.0
<10.0
<10.0
<10.0
Table A-4.
In-house "blank" samples.
Concentration pCi/LU.
Laboratory results Acceptance Lab Sample Sample (4.66 Sigma)
Criteria Code Type Date Analysis LLD Activityb (4.66 Sigma)
SPF-5782 SPF-5782 SPW-5938 SPW-59451 SPW-59451 SPDW-3130 SPDW-3130 SPMI-6146 Low levels of unusual.
SPW-6605 SPW-9009 SPAP-9011 SPAP-9011 SPW-5780 SPW-1 0724 SPAP-11549 SPW-1 1756 SPM1-11758 SPMI-1 1758 SPF-1 1760 FISH Jul 2001 Co-60 FISH Jul 2001 Cs-1 34 WATER Jul 2001 H-3 WATER Jul 2001 Ra-226 WATER Jul 2001 Ra-228 WATER Jul 2001 Gr. Alpha WATER Jul 2001 Gr. Beta MILK Jul 2001 Sr-90 Sr-90 are still detected in the environment.
WATER WATER AIR FILTER AIR FILTER WATER WATER AIR FILTER WATER MILK MILK FISH Jul 2001 Oct 2001 Oct 2001 Oct 2001 Oct 2001 Dec 2001 Dec 2001 Dec 2001 Dec 2001 Dec 2001 Dec 2001 Gr. Beta H-3 Co-60 Cs-137 Sr-90 U-238 Gr. Beta Cs-137 Cs-137 1-131(g)
Cs-1 37
< 5.64
< 7.51
< 163.22
< 0.01
< 0.77
- 0.54
< 2.27
< 0.50 A concentration
< 1.34
< 160.00
< 0.76
< 0.58
< 0.54
<0.13
< 0.00
< 2.62
< 4.00
< 16.57
< 7.96
-16.21 +/-85.07 0.04 +/- 0.01 0.70 +/- 0.44 0.36 +/- 0.40
-0.78 +/- 1.35 1.09 +/- 0.36 of (1-5 pCi/L) in milk is 0.55 +/- 1.01
-56.70 +/- 76.50 0.36 +/- 0.30 0.04 +/-0.10 0.01 +/- 0.00 "a Liquid sample results are reported in pCi/Liter, air filter sample results are in pCi/filter, charcoal sample results are in pCi/charcoal, and solid sample results are in pCi/kilogram.
" The activity reported is the net activity result.
A4-3
<100.0
<100.0
<200.0
<1.0
<2.0
<1.0
<3.2
<1.0 not
<3.2
<200.0
<100.0
<100.0
<1.0
<1.0
<3.2
<10.0
<10.0
<20.0
<100.0
Table A-5.
In-house "duplicate" samples.
Lab Codes AP-10675, 10676 AP-10803,10804 AP-10833, 10834 WW-51, 52 MI-72, 73 MI-96, 97 U-858, 859 MI-389, 390 DW-879, 880 SWU-813, 814 MI-708, 709 MI-740, 741 MI-740, 741 MI-789, 790 DW-901, 902 SWU-1544, 1545 DW-1426, 1427 DW-1426, 1427 WW-1476, 1477 MI-1523, 1524 MI-1523, 1524 MI-1572, 1573 MI-1572, 1573 SW-1648, 1649 MI-1800, 1801 SW-1779, 1780 SW-779, 1780 MI-1447, 1448 MI-1447, 1448 WW-2115, 2116 SW-1698, 1699 DW-2272, 2273 WW-2356, 2357 AP-2812, 2813 AP-2812, 2813 LW-2217, 2218 Concentration in pCi/La Sample First Second Averaged nJ +~
VJa U Jan, 2001 Jan, 2001 Jan, 2001 Jan, 2001 Jan, 2001 Jan, 2001 Jan, 2001 Jan, 2001 Jan, 2001 Jan, 2001 Feb, 2001 Feb, 2001 Feb, 2001 Feb, 2001 Feb, 2001 Feb, 2001 Feb, 2001 Feb, 2001 Feb, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Analysis Be-7 Be-7 Be-7 H-3 K-40 K-40 Gr. Beta K-40 Gr. Beta Gr. Beta K-40 1-131 K-40 K-40 Gr. Beta Gr. Beta Gr. Beta H-3 H-3 1-131 K-40 K-40 Sr-90 K-40 K-40 Gr. Alpha Gr. Beta 1-131 K-40 H-3 Gr. Beta Gr. Beta Gr. Beta Be-7 Be-7 Gr. Beta 0.06 +/- 0.02 0.04 +/- 0.01 0.04 +/- 0.01 362.60 +/- 94.70 1,566.90 +/- 196.80 1,418.30+/-117.80 2.17+/-2.47 1,489.20+/-141.10 2.63 +/- 0.52 2.48 +/- 0.58 1,179.40+/-103.00 0.01 +/- 0.26 1,434.00+/-156.50 1,584.30 +/- 158.80 4.67 +/- 1.08 3.13+/- 0.63 2.05 +/- 0.92 42.60 +/- 94.23 53.06 +/- 65.79
-0.01 +/- 0.20 1,396.00+/-184.80 1,499.20+/- 113.30 1.65 +/- 0.44 297.80 +/- 67.20 1,425.80 +/-183.30 2.22 +/- 0.73 6.28 +/- 0.74
-0.65 +/- 0.27 1,496.20 +/-155.40 540.04+/- 111.84 6.07+/-1.75 2.10+/- 0.86 1.22 +/- 0.50 0.07 +/- 0.02 0.07 +/- 0.02 1.85 +/- 0.51 0.06 +/- 0.02 0.04 +/- 0.01 0.04 +/- 0.01 417.20 +/- 96.80 1,372.40 +/- 152.50 1,545.70 +/- 162.50 4.23 +/- 2.74 1,463.30 +/- 168.20 2.37 +/- 0.50 2.46 +/- 0.63 1,280.40 +/- 90.26
-0.12+/- 0.26 1,435.00+/-126.10 1,390.70+/-136.50 5.54 +/-1.13 2.33 +/- 0.52 2.34 +/- 0.93 131.31 +/-95.34 53.06 +/- 93.03
-0.10+/-0.37 1,576.00 +/- 184.90 1,326.00 +/- 118.80 1.51 +/- 0.52 344.80 +/- 82.30 1,372.20 +/- 119.70 2.14 +/-0.69 6.62 +/- 0.70 0.13+/-0.55 1,413.40+/-169.60 500.85+/-110.46 5.57+/-,1.85 1.63+/-0.83 1.32+/- 0.47 0.05 +/- 0.01 0.05 +/- 0.01 2.23 +/- 0.55 0.06 +/- 0.01 0.04 +/- 0.01 0.04 +/- 0.01 389.90 +/- 67.71 1,469.65+/-124.49 1,482.00 +/- 100.35 3.20 +/- 1.84 1,476.25 +/- 109.77 2.50 +/- 0.36 2.47 +/- 0.43 1,229.90 +/- 68.48
-0.05+/-0.18 1,434.50 +/- 100.49 1,487.50+/-104.70 5.11 +/-0.78 2.73 +/- 0.41 2.20 +/- 0.65 86.96 +/- 67.02 53.06 +/- 56.97
-0.06 +/- 0.21 1,486.00 +/-130.71 1,412.60 +/- 82.08 1.58 +/- 0.34 321.30 +/- 53.13 1,399.00 +/-109.46 2.$8 +/-0.50 6.45 +/- 0.51
-0.26 +/- 0.31 1,454.80 +/- 115.01 520.44 +/- 78.59 5.82 +/- 1.27 1.87 +/- 0.60 1.27 +/- 0.35 0.06 +/- 0.01 0.06 +/- 0.01 2.04 +/- 0.37 A5-1 rKtsUit mesful L Resultl
Table A-5.
In-house "duplicate" samples.
Concentration in pCi/La Lab Sample First Second Averaged n.UI 4
1 Uif Codes ca V AP-2833, 2834 AP-3038, 3039 AP-3038, 3039 DW-2398, 2399 LW-2467, 2468 MI-2446, 2447 AP-3017, 3018 SW-2423, 2424 BS-3103, 3104 SWU-3239, 3240 SS-3322, 3323 W-3990, 3991 BS-4347, 4348 BS-4347, 4348 MI-3364, 3365 SO-3385, 3386 SO-3385, 3386 SO-3385, 3386 CL-4068, 4069 MI-3475, 3476 WW-3545, 3546 MI-3681, 3682 SW-3702, 3703 SW-3702, 3703 BS-4021, 4022 BS-4021, 4022 BS-4021, 4022 BS-4021, 4022 BS-4021, 4022 BS-4021, 4022 BS-4021, 4022 F-3813, 3814 G-4158, 4159 SO-4179, 4180 SO-4179, 4180 SO-4179, 4180 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 Apr, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 Analysis Be-7 Be-7 Be-7 Gr. Beta Gr. Beta K-40 Be-7 K-40 Gr. Beta Gr. Beta K-40 Sr-89 K-40 K-40 K-40 Gr. Alpha Gr. Beta K-40 K-40 Gr. Beta Gr. Beta K-40 Gr. Alpha Gr. Beta Cs-1 37 H-3 K-40 Pu-238 Pu-239/40 Ra-226 Sr-90 K-40 Be-7 Ac-228 Bi-214 Cs-137 0.04 +/- 0.01 0.07 +/- 0.02 0.06 +/- 0.02 1.58 +/- 0.89 2.52 +/- 0.53 1,285.40+/-177.10 0.05 +/- 0.01 255.60 +/- 59.80 7.99+/-1.80 3.30 +/- 0.60 15.99 +/- 1.08 91.35+/-18.94 3,982.40 +/- 489.60 3.26 +/- 0.45 1,325.90 +/- 160.20 6.51 +/-3.09 24.63 +/- 3.15 19.17+/- 1.08 1.09 +/- 0.27 1,297.10+/-114.60 1.57 +/- 0.55 1,417.20+/-125.70 4.51 +/-1.66 8.74 +/- 1.36 224.30 +/- 30.20 842.00 +/- 47.00 21,117.00 +/- 953.00 80.30 +/- 36.50 49.40 +/- 31.80 7,436.00 +/- 577.90 10.60 +/- 2.71 2.10+/-0.17 0.37+/- 0.13 0.45+/-0.13 0.31 +/- 0.06 0.46 +/- 0.05 0.06 +/- 0.02 0.07 +/- 0.02 0.07 +/- 0.01 1.81 +/- 0.88 2.42 +/- 0.53 1,376.00+/-175.90 0.05 +/- 0.01 268.40 +/- 65.40 8.17 +/-1.73 4.30 +/- 0.74 15.59 +/- 1.01 85.29 +/- 23.99 3,255.80 +/- 450.10 3.98 +/- 0.49 1,453.20+/-163.00 9.01 +/- 3.44 28.17+/- 3.12 17.94 +/- 0.76 1.13+/- 0.23 1,433.60 +/-156.60 1.36 +/- 0.53 1,496.20+/-124.50 3.22 +/- 1.55 7.11 +/-1.38 205.90 +/- 43.00 860.00 +/- 48.00 21,629.00+/-1,357.00 59.50 +/- 22.00 41.10+/- 19.60 9,126.00 +/- 751.90 16.80 +/- 3.22 2.30 +/- 0.26 0.41 +/-0.14 0.52+/-0.14 0.41 +/- 0.06 0.47 +/- 0.04 A5-2 0.05 +/- 0.01 0.07 +/- 0.01 0.07 +/- 0.01 1.69 +/-0.63 2.47 +/- 0.37 1,330.70+/-124.81 0.05 +/- 0.00 262.00 +/- 44.31 8.08+/-1.25 3.80 +/- 0.48 15.79+/-0.74 88.32+/- 15.28 3,619.10 +/- 332.53 3.62 +/- 0.33 1,389.55 +/- 114.27 7.76 +/- 2.31 26.40 +/- 2.22 18.56 +/- 0.66 1.11+/-0.18 1,365.35 +/- 97.03 1.47 +/- 0.38 1,456.70 +/- 88.46 3.87 +/- 1.13 7.93 +/- 0.97 215.10 +/-26.27 851.00 +/- 33.59 21,373.00 +/-829.10 69.90 +/- 21.31 45.25+/-18.68 8,281.00+/-474.16 13.70+/-2.10 2.20+/-0.16 0.39+/-0.10 0.49+/- 0.10 0.36 +/- 0.04 0.47 +/- 0.03 rxzou L Keul U rO u
Table A-5.
In-house "duplicate" samples.
Concentration in pCi/La Lab Sample First Second Averaged Codes 0J=
L SO-4179, 4180 SO-4179, 4180 SO-4179, 4180 SO-4179, 4180 SO-4179, 4180 BS-4233, 4234 BS-4233, 4234 SWU-4376, 4377 DW-4449, 4450 DW-4397, 4398 MI-4114, 4115 F-4284, 4285 DW-4326, 4327 MI-4470, 4471 SW-4493, 4494 BS-4725, 4726 BS-4725, 4726 BS-4725, 4726 MI-4775, 4776 WW-5110, 5111 G-5085, 5086 G-5085, 5086 MI-5259, 5260 MI-5259, 5260 SWU-5422, 5423 VE-5401, 5402 VE-5401, 5402 AP-5830, 5831 SW-5557, 5558 AP-5851, 5852 SW-5636, 5637 LW-5681, 5682 G-5535, 5536 G-5535, 5536 G-5535, 5536 AP-5788, 5789 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 May, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jun, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Analysis Gr. Beta K-40 Pb-212 Ra-226 TI-208 Cs-1 37 K-40 Gr. Beta Gr. Beta Gr. Beta K-40 K-40 Gr. Beta K-40 Gr. Beta Co-60 Cs-137 K-40 K-40 H-3 Be-7 K-40 K-40 Sr-90 Gr. Beta Gr. Beta K-40 Be-7 Gr. Beta Be-7 Gr. Beta Gr. Beta Be-7 Gr. Beta K-40 Be-7 26.65 +/- 2.63 16.35+/- 0.86 0.35 +/- 0.04 0.56 +/- 0.98 0.14+/-0.03 0.03 +/- 0.01 8.18+/-0.48 2.58 +/- 0.55 2.83 +/- 0.55 9.13+/-1.26 1,325.90 +/- 118.80 2.23 +/- 0.32 2.60 +/- 0.97 1,514.50+/-116.60 4.05+/-1.23 112.00 +/-24.30 3,083.10+/-100.10 8,143.70 +/- 640.40 1,362.20 +/- 71.80 1,173.50+/-129.10 0.89+/-0.17 5.13+/-0.39 1,529.70+/-122.70 1.69 +/- 0.42 2.59 +/- 0.54 8.12+/- 0.24 6.55 +/- 0.52 0.08 +/- 0.01 5.43+/-1.70 0.07 +/- 0.02 4.75+/-1.38 2.42 +/- 0.37 0.99 +/- 0.29 7.62+/-0.12 7.26+/-1.03 0.08 +/- 0.02 A5-3 24.68+/-2.52 16.05 +/- 0.82 0.43 +/- 0.05 1.03 +/- 0.31 0.17+/- 0.03 0.03 +/- 0.02 7.80 +/- 0.58 2.94 +/- 0.58 3.74 +/-0.65 10.20+/-1.34 1,394.70 +/-133.10 2.12 +/-0.35 1.47 +/- 0.83 1,456.80+/-130.90 4.64+/-1.32 84.50 +/- 8.70 3,094.80 +/- 35.30 8,083.80 +/- 225.10 1,363.90 +/-73.40 1,046.80+/-125.20 1.14+/-0.39 5.22 +/- 0.70 1,406.20+/-123.80 1.71 +/-0.44 1.91 +/- 0.52 8.88 +/- 0.26 6.26 +/- 0.65 0.08 +/- 0.01 5.96 +/- 1.56 0.07 +/- 0.02 4.18+/- 1.34 2.18 +/-0.34 0.97 +/- 0.54 7.72 +/-0.12 7.64 +/- 0.93 0.07 +/- 0.02 25.67 +/- 1.82 16.20 +/- 0.59 0.39 +/- 0.03 0.79 +/- 0.51 0.15+/-0.02 0.03 +/- 0.01 7.99 +/- 0.38 2.76 +/- 0.40 3.29 +/- 0.43 9.66 +/- 0.92 1,360.30 +/- 89.20 2.18 +/-0.24 2.04 +/- 0.64 1,485.65 +/- 87.65 4.35 +/- 0.90 98.25+/- 12.91 3,088.95 +/- 53.07 8,113.75 +/- 339.40 1,363.05 +/- 51.34 1,110.15+/- 89.92 1.02 +/- 0.21 5.17+/-0.40 1,467.95+/-87.15 1.70 +/- 0.30 2.25 +/- 0.37 8.50+/-0.18 6.40 +/- 0.42 0.08 +/- 0.01 5.70+/- 1.15 0.07 +/- 0.01 4.47 +/- 0.96 2.30 +/- 0.25 0.98 +/- 0.31 7.67 +/- 0.08 7.45+/-0.69 0.08 +/- 0.01 ZW rXWCOU
Table A-5.
In-house "duplicate" samples.
Lab Codes AP-5872, 5873 AP-5893, 5894 AP-5809, 5810 SW-5724, 5725 SW-5724, 5725 SW-5767, 5768 LW-5920, 5921 SO-6172, 6173 SO-6172, 6173 SO-6172, 6173 MI-6353, 6354 SW-6376, 6377 VE-6424, 6425 VE-6424, 6425 MI-6445, 6446 LW-6489, 6490 MI-6533, 6534 DW-6835, 6836 MI-6693, 6694 MI-6693, 6694 WW-6952, 6953 MI-6906, 6907 VE-6973, 6974 LW-7851, 7852 MI-7001, 7002 MI-7073, 7074 LW-7145, 7146 MI-7221, 7222 MI-7221, 7222 SWU-7527, 7528 VE-7485, 7486 DW-7506, 7507 MI-7622, 7623 MI-7664, 7665 MI-7876, 7877 G-7960, 7961 Sample Date Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Jul, 2001 Aug, 2001 Aug, 2001 Aug, 2001 Aug, 2001 Aug, 2001 Aug, 2001 Aug, 2001 Aug, 2001 Aug, 2001 Aug, 2001 Aug, 2001 Aug, 2001 Aug, 2001 Aug, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Concentration in pCi/La First Second Averaged Result Result Result Analysis Be-7 Be-7 Be-7 Gr. Alpha Gr. Beta 1-131 Gr. Beta Cs-137 K-40 Sr-90 K-40 1-131 Gr. Beta K-40 K-40 Gr. Beta K-40 Gr. Beta K-40 Sr-90 Gr. Beta K-40 K-40 Gr. Beta K-40 K-40 Gr. Beta K-40 Sr-90 Gr. Beta K-40 Gr. Beta K-40 K-40 K-40 Be-7 0.07 +/- 0.02 0.08 +/- 0.02 0.07 +/- 0.02 2.95 +/- 0.70 8.79 +/- 0.71 0.79 +/- 0.31 3.06 +/- 0.64 0.30 +/- 0.05 18.20 +/- 1.08 0.03 +/- 0.01 966.35 +/- 82.28 0.58+/-0.16 2.52 +/- 0.05 3.04 +/- 0.26 1,407.40 +/- 97.10 2.61 +/- 0.57 1,498.60+/-113.90 2.01 +/- 0.59 1,294.30 +/-118.70 1.47 +/- 0.42 5.49 +/- 0.69 1,613.80 +/- 218.50 4.21 +/- 0.24 2.20 +/- 0.48 1,453.80 +/-148.10 1,217.30 +/- 80.83 2.77 +/- 0.53 1,192.90 +/- 95.40 2.10 +/- 0.48 17.51 +/-3.06 2.12 +/-0.47 4.25+/-1.18 1,340.10+/- 111.10 1,408.10 +/-102.70 1,416.40+/- 192.30 1.27 +/- 0.21 0.08 +/- 0.02 0.08 +/- 0.01 0.06 +/- 0.01 2.89 +/- 0.60 8.21 +/- 0.65 0.61 +/- 0.26 3.15+/-0.58 0.32 +/- 0.04 17.55 +/- 0.82 0.05 +/- 0.02 986.31 +/-91.91 0.81 +/- 0.17 2.49 +/- 0.05 3.12+/- 0.37 1,442.20+/-189.60 2.79 +/- 0.54 1,375.50 +/- 129.60 2.36 +/- 0.63 1,417.30 +/-176.50 1.23 +/- 0.41 5.80 +/- 0.69 1,532.70 +/- 135.80 4.29 +/- 0.64 2.12+/-Q.42 1,285.30 +/- 190.50 1,218.30 +/-99.13 3.60 +/- 0.59 1,388.90 +/-132.70 1.72+/-0.47 20.36 +/- 3.31 2.47 +/- 0.34 4.13++/-1.12 1,290.80+/-116.50 1,396.90 +/-114.30 1,318.00 +/- 155.50 1.25 +/- 0.25 A5-4 0.07 +/- 0.01 0.08 +/- 0.01 0.06 +/- 0.01 2.92 +/- 0.46 8.50 +/- 0.48 0.70 +/- 0.20 3.11 +/-0.43 0.31 +/-0.03 17.88 +/- 0.68 0.04 +/- 0.01 976.33 +/- 61.68 0.70+/- 0.12 2.51 +/- 0.03 3.08 +/- 0.23 1,424.80 +/- 106.51 2.70 +/- 0.39 1,437.05 +/- 86.27 2.19 +/- 0.43 1,355.80 +/- 106.35 1.35 +/- 0.29 5.64 +/- 0.49 1,573.25+/-128.63 4.25 +/- 0.34 2.16 +/-0.32 1,369.55+/-120.65 1,217.80 +/- 63.95 3.19 +/- 0.39 1,290.90 +/- 81.72 1.91 +/-0.34 18.93 +/- 2.25 2.30 +/- 0.29 4.19+/-0.81 1,315.45 +/- 80.49 1,402.50 +/- 76.83 1,367.20+/-123.65 1.26+/-0.16
Table A-5.
In-house "duplicate" sariples.
Lab Codes G-7960, 7961 F-8011, 8012 F-8011, 8012 F-8011, 8012 MI-8149, 8150 MI-8343, 8344 VE-8319, 8320 VE-8319, 8320 AP-9069, 9070 AP-9566, 9567 VE-8700, 8701 VE-8700, 8701 VE-8700, 8701 AP-9048, 9049 DW-8636, 8637 DW-8615, 8616 AP-9090, 9091 AP-9166, 9167 AP-9187, 9188 VE-10562, 10563 VE-1 0562, 10563 WW-8636, 8637 DW-8894, 8895 MI-9232, 9233 VE-9518, 9519 WW-10257, 10258 VE-10333, 10334 VE-10333, 10334 MI-10588, 10589 DW-10688, 10689 WW-10905, 10906 SS-10953, 10954 SS-10953,10954 SS-10953,10954 SS-10953,10954 SS-10953, 10954 Sample Date Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Oct, 2001 Oct, 2001 Oct, 2001 Oct, 2001 Oct, 2001 Oct, 2001 Oct, 2001 Oct, 2001 Oct, 2001 Oct, 2001 Oct, 2001 Oct, 2001 Oct, 2001 Oct, 2001 Oct, 2001 Nov, 2001 Nov, 2001 Nov, 2001 Nov, 2001 Nov, 2001 Dec, 2001 Dec, 2001 Dec, 2001 Dec, 2001 Dec, 2001 Dec, 2001 Concentration in pCi/La First Second Averaged Result Result Result Analysis K-40 Cs-1 37 Gr. Beta K-40 K-40 K-40 Gr. Beta K-40 Be-7 Be-7 Be-7 K-40 Sr-90 Be-7 Gr. Beta Gr. Beta Be-7 Be-7 Be-7 Be-7 K-40 Gr. Beta Gr. Beta K-40 K-40 H-3 Be-7 K-40 K-40 Gr. Beta H-3 Ac-228 Bi-214 Co-58 Co-60 Cs-137 5.21 +/- 0.57 0.06 +/- 0.02 3.68+/-0.12 3.47 +/- 0.49 1,551.70 +/-118.00 1,550.30 +/-170.60 3.37 +/-0.10 2.14+/-0.46 0.07 +/- 0.02 0.08 +/- 0.02 0.24 +/-0.10 2.03 +/- 0.24 0.01 +/- 0.00 0.07 +/- 0.01 4.74+/-1.06 4.65 +/- 0.58 0.07 +/- 0.01 0.08 +/- 0.02 0.07 +/- 0.01 309.90 +/-158.80 6,407.10 +/- 620.70 5.08+/-1.20 4.28 +/- 0.89 1,440.70 +/- 46.60 1.91 +/- 0.22 755.90+/-102.50 0.68 +/- 0.26 6.10+/-0.72 1,428.40+/-114.70 3.49 +/- 0.91 233.90 +/- 90.60 1.10+/-0.25 0.69 +/- 0.08 0.21 +/- 0.05 0.93 +/- 0.06 0.13 +/-0.03 5.70 +/- 0.63 0.04 +/- 0.02 3.50+/-0.11 3.38 +/- 0.47 1,489.90+/-123.60 1,368.10+/-126.70 3.42+/-0.11 2.24 +/- 0.37 0.07 +/- 0.01 0.09 +/- 0.03 0.19+/-0.10 2.03 +/- 0.21 0.01 +/-0.00 0.07 +/- 0.00 5.08+/-1.21 4.28 +/- 0.54 0.07 +/- 0.01 0.08 +/- 0.02 0.05 +/- 0.01 348.30+/-168.10 6,057.50+/- 660.40 4.74+/-1.06 3.40 +/- 0.90 1,424.80 +/- 76.40 1.97 +/- 0.39 684.70 +/- 99.90 0.99 +/- 0.26 5.83 +/- 0.72 1,445.50 +/-129.40 2.36 +/- 0.76 226.30 +/- 90.20 0.91 +/-0.16 0.75 +/- 0.08 0.18+/-0.04 0.94 +/- 0.06 0.16+/-0.03 A5-5 5.45 +/- 0.43 0.05 +/- 0.01 3.59 +/- 0.08 3.43 +/- 0.34 1,520.80 +/- 85.44 1,459.20 +/- 106.25 3.39 +/- 0.07 2.19 +/-0.29 0.07 +/- 0.01 0.09 +/- 0.02 0.22+/-0.07 2.03+/-0.16 0.01 +/-0.00 0.07 +/- 0.01 4.91 +/-0.80 4.47 +/- 0.40 0.07+/-0.01 0.08 +/- 0.01 0.06 +/- 0.01 329.10+/-115.62 6,232.30 +/- 453.15 4.91 +/- 0.80 3.84 +/- 0.63 1,432.75 +/- 44.75 1.94 +/- 0.22 720.30 +/- 71.57 0.84+/-0.18 5.97 +/- 0.51 1,436.95 +/- 86.46 2.93 +/- 0.60 230.10 +/- 63.92 1.00+/-0.15 0.72 +/- 0.06 0.19+/-0.03 0.93 +/- 0.04 0.14+/-0.02
Table A-5.
In-house "duplicate" samples.
Concentration in pCi/La Lab Sample First Second Averaged Codes Date Analysis Result Result Result SS-10953, 10954 SS-1 0953, 10954 SS-1 0953, 10954 SS-1 0953, 10954 SS-1 0953, 10954 MI-11033, 11034 M1-11033, 11034 AP-11888, 11889 Dec, 2001 Dec, 2001 Dec, 2001 Dec, 2001 Dec, 2001 Dec, 2001 Dec, 2001 Dec, 2001 K-40 Pb-212 Pb-214 Ra-226 TI-208 K-40 Sr-90 Be-7 9.91 +/- 0.83 0.94 +/- 0.05 0.83 +/- 0.08 1.76 +/-0.37 0.34 +/- 0.05 1,339.80+/-128.70 1.31 +/- 0.41 0.06 +/- 0.02 8.36 +/- 0.80 0.91 +/-0.06 0.82 +/- 0.07 1.67 +/- 0.37 0.31 +/-0.05 1,435.80+/-117.30 1.38 +/- 0.37 0.06 +/- 0.02 9.13+/- 0.57 0.92 +/- 0.04 0.83 +/- 0.05 1.72 +/- 0.26 0.32 +/- 0.04 1,387.80 +/- 87.07 1.35 +/- 0.28 0.06 +/- 0.01 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 pCi/L, except for elemental potassium (K) in milk (mg/L), air filters (pCi/Filter), food products and vegetation (pCi/g), soil and sediments (pCi/kg).
A5-6
Table A-6.
Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)a.
Concentrationb Lab Sample Date MAPEP Resultd Control Code Type Collected Analysis Laboratory resultc Is, N=1 Limits STSO-923 SOIL Jan, 2001 Am-241 Included in the testing series as a "false positive".
0.0 - 2.6 No activity expected. Result of analysis; < 0.8 Bq/L.
100.2 +/- 3.5 1,285.1 +/- 5.3 81.1+/- 1.8 1,210.6+/- 6.6 732.6 +/- 21.2 212.6+/-6.7 110.7+/-7.2 79.6 +/- 5.9 159.8+/- 9.5 45.0 +/- 3.9 165.6+/- 7.4 428.5+/- 10.9 103.0+/- 10.3 1,270.0+/- 127.0 91.1+/- 9.1 1,240.0+/- 124.0 652.0+/- 65.2 203.0+/- 20.3, 115.0+/- 11.5 83.4+/- 8.3 209.0+/- 20.9 60.0+/- 6.0 191.0+/- 19.1 382.0+/- 38.2 72.1 - 133.9 889.0 - 1,651.0 63.8-118.4 868.0 - 1,612.0 456.4 - 847.6 142.1 - 263.9 80.5-149.5 58.4-108.4 146.3 - 271.7 42.0 - 78.0 133.7 - 248.3 267.4 - 496.6
" 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.
b All results are in Bqfkg or Bq/L as requested by the Department of Energy.
0 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 STSO-923 STSO-923 STSO-923 STSO-923 STSO-923 STSO-923 STSO-923 STSO-923 STSO-923 STSO-923 STSO-923 STSO-923 SOIL SOIL SOIL SOIL SOIL SOIL SOIL SOIL SOIL SOIL SOIL SOIL Jan, 2001 Jan, 2001 Jan, 2001 Jan, 2001 Jan, 2001 Jan, 2001 Jan, 2001 Jan, 2001 Jan, 2001 Jan, 2001 Jan, 2001 Jan, 2001 Co-57 Co-60 Cs-134 Cs-1 37 K-40 Mn-54 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Zn-65
Table A-7.
Environmental Measurements Laboratory Quality Assessment Program (EML)Y.
Concentration b Lab Sample Date Control Code Type Collected Analysis Laboratory result EML Resultc Limitsd STSO-904 SOIL STSO-904 SOIL STSO-904 SOIL Naturally-occurring radium of the higher bias seen for STSO-904 SOIL STSO-904 SOIL STSO-904 SOIL STSO-904 SOIL STSO-904 SOIL STSO-904 SOIL STSO-904 SOIL STW-905 WATER STW-905 WATER STW-905 WATER STW-905 WATER STW-905 WATER STW-905 WATER STW-905 WATER STW-905 WATER STW-905 WATER STW-906 WATER STW-906 WATER STAP-907 AIR FILTER STAP-907 AIR FILTER STAP-907 AIR FILTER STAP-907 AIR FILTER STAP-907 AIR FILTER STAP-907 AIR FILTER STAP-907 AIR FILTER Mar, 2001 Ac-228 Mar, 2001 Am-241 Mar, 2001 Bi-212 and thorium daughters are p isotopes of lead and bismuth.
Mar, 2001 Bi-214 Mar, 2001 Cs-1 37 Mar, 2001 K-40 Mar, 2001 Pb-212 Mar, 2001 Pb-214 Mar, 2001 Pu-239/40 Mar, 2001 Sr-90 Mar, 2001 Am-241 Mar, 2001 Co-60 Mar, 2001 Cs-1 37 Mar, 2001 H-3 Mar, 2001 Pu-238 Mar, 2001 Pu-239140 Mar, 2001 Sr-90 Mar, 2001 U-23314 Mar, 2001 U-238 Mar, 2001 Gr. Alpha Mar, 2001 Gr. Beta Mar, 2001 Am-241 Mar, 2001 Co-60 Mar, 2001 Cs-1 34 Mar, 2001 Cs-1 37 Mar, 2001 Mn-54 Mar, 2001 Pu-238 Mar, 2001 Pu-239/40 45.60 +/-4.0 42.70 14.40+/-0.5 14.80 53.20+/-3.1 42.00 resent in the shield background, and a 42.10+/-7.7 1,772.60 +/- 79.8 583.80 +/- 52.6 46.60 +/- 8.5 45.30 +/- 8.6 26.00 +/- 0.8 55.60 +/- 2.2 2.15+/-0.1 97.00 +/- 0.8 70.10+/-4.0 76.50 +/- 5.5 1.69 +/- 0.1 1.69 +/- 0.1 3.85 +/- 0.1 0.90+/-0.1 0.88 +/-0.1 1,724.60 +/- 141.7 1,246.40 +/- 31.1 0.47 +/- 0.0 20.11 +/-0.2 2.71 +/-0.2 9.86 +/- 0.2 7.25 +/- 0.2 0.23 +/- 0.0 0.12+/-0.0 0.80- 1.50 0.63 - 2.64 0.45-1.23 probable cause 32.60 0.78-1.50 1,740.00 468.00 41.50 34.30 25.60 69.00 1.67 98.20 73.00 79.30 1.58 1.64 4.40 1.04 1.04 1,900.00 1,297.00 0.49 19.44 2.83 8.76 6.52 0.22 0.14 0.80- 1.29 0.80- 1.37 0.74-1.36 0.76-1.53 0.71 - 1.33 0.61 - 3.91 0.76 - 1.48 0.80- 1.20 0.80- 1.20 0.74 - 2.29 0.74-1.22 0.75-1.26 0.64-1.50 0.80- 1.40 0.80- 1.29 0;58-1.26 0.56-1.50 0.69 - 2.40 0.79-1.30 0.74-1.21 0.78-1.35 0.80- 1.36 0.66-1.35 0.69-1.29 A7-1
Table A-7.
Environmental Measurements Laboratory Quality Assessment Program (EML)'.
Concentrationb Lab Code STAP-907 STAP-907 STAP-907 STAP-908 STAP-908 STVE-909 STVE-909 STVE-909 STVE-909 STVE-909 STVE-909 STVE-909 STW-925 STW-925 STW-925 STW-925 STW-925 STW-925 STW-925 STW-925 STW-925 STW-926 STW-926 STSO-927 STSO-927 STSO-927 STSO-927 STSO-927 STSO-927 Lab Code Control Laboratory result EML Resultc Limits' Sample Type AIR FILTER AIR FILTER AIR FILTER AIR FILTER AIR FILTER VEGETATION VEGETATION VEGETATION VEGETATION VEGETATION VEGETATION VEGETATION WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER WATER SOIL SOIL SOIL SOIL SOIL SOIL A7-2 Date Collected Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Mar, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Analysis Sr-90 U-233/4 U-238 Gr. Alpha Gr. Beta Am-241 Cm-244 Co-60 Cs-1 37 K-40 Pu-239/40 Sr-90 Am-241 Co-60 Cs-137 H-3 Ni-63 Pu-238 Pu-239/40 Sr-90 Uranium Gr. Alpha Gr. Beta Ac-228 Am-241 Bi-212 Bi-214 Cs-137 K-40 7.41 +/-0.2 0.05 +/- 0.0 0.05 +/- 0.0 2.66 +/- 0.0 2.30 +/- 0.0 6.10+/- 0.2 3.50 +/- 0.5 28.50 +/- 2.1 795.50 +/- 76.4 592.60 +/- 42.5 8.50 +/- 0.6 1,239.60 +/- 130.0 0.70 +/- 0.1 206.70+/-4.7 46.60 +/- 0.8 254.10+/-3.6 50.90 +/- 3.0 1.10 +/-0.1 1.60 +/- 0.1 4.10 +/-0.3 2.20 +/- 0.2 1,220.00 +/- 32.0 8,461.00 +/- 206.0 68.10+/- 1.4 5.20 +/- 1.3 65.10+/-1.6 47.30 +/- 4.7 659.20+/-10.8 737.70+/-16.6 7.10 0.05 0.05 3.97 2.58 6.17 3.69 30.40 842.00 603.00 9.58 1,330.00 0.76 209.00 45.13 207.00 45.25 1.09 1.63 3.73 2.37 1,150.00 7,970.00 59.57 4.43 62.07 36.90 612.33 623.33 0.55 - 2.05 0.80- 1.92 0.80- 1.59 0.57-1.47 0.76-1.52 0.72 - 2.34 0.61 -1.61 0.75-1.51 0.80- 1.37 0.78-1.43 0.67-1.49 0.52-1.23 0.76-1.48 0.80 - 1.20 0.80- 1.24 0.74 - 2.29 0.70- 1.30 0.74-1.22 0.75-1.26 0.64-1.50 0.73-1.37 0.58-1.26 0.56-1.50 0.80- 1.50 0.63 - 2.64 0.45 - 1.23 0.78-1.50 0.80 - 1.29 0.80- 1.37
Table A-7.
Environmental Measurements Laboratory Quality Assessment Program (EML)a.
Concentration Lab Sample Date Control Code Type Collected STSO-927 STSO-927 STSO-927 STSO-927 STSO-927 STVE-928 STVE-928 STVE-928 STVE-928 STVE-928 STVE-928 STVE-928 STAP-929 STAP-929 STAP-929 STAP-929 STAP-929 STAP-929 STAP-929 STAP-929 STAP-929 STAP-930 STAP-930 SOIL 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 AIR FILTER Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001 Sep, 2001
' The Environmental Measurements Laboratory provides the following nuclear species : Air Filters,
- Soil, Vegetation and Water.
' Results are reported in Bq/L with the following exceptions: Air Filter results are reported in Bq/Filter, Soil results are reported in Bq/Kg, Vegetation results are reported in Bq/Kg.
c The EML result listed is the mean of replicate determinations for each nuclide+/-the standard error of the mean.
"Control limits are reported by EML as the ratio of Reported Value / EML value.
A7-3 Analysis Pb-212 Pb-214 Pu-239/40 Sr-90 Uranium Am-241 Cm-244 Co-60 Cs-1 37 K-40 Pu-239/40 Sr-90 Am-241 Co-60 Cs-134 Cs-1 37 Mn-54 Pu-238 Pu-239/40 Sr-90 Uranium Gr. Alpha Gr. Beta EML Resultf Limits-Laboratory result 64.70 +/- 3.8 53.70 +/- 7.7 9.30 +/- 2.9 27.40 +/- 6.3 155.60 +/- 7.8 7.00 +/- 0.3 4.30 +/- 0.8 40.20 +/- 0.9 1,184.00 +/- 2.8 1,023.00 +/- 44.1 8.90+/-1.4 1,364.00 +/-18.4 0.09 +/- 30.0 16.90 +/- 0.3 11.80 +/- 0.2 18.30 +/- 0.3 85.40 +/- 1.3 0.05 +/- 0.0 0.22 +/- 0.0 3.11 +/-0.1 0.24 +/- 0.1 6.30+/-0.1 13.80 +/-0.1 58.33 39.67 8.95 30.60 194.23 6.92 4.31 35.30 1,030.00 898.67 11.02 1,612.80 0.09 17.50 12.95 17.10 81.15 0.07 0.23 3.48 0.22 5.36 12.77 0.74-1.36 0.76 - 1.53 0.71 -1.33 0.61 - 3.91 0.62-1.35 0.72 - 2.34 0.61 -1.61 0.75-1.51 0.80- 1.37 0.78-1.43 0.67-1.49 0.52-1.23 0.69 - 2.40 0.79-1.30 0.74-1.21 0.78-1.35 0.80- 1.36 0.66 - 1.35 0.69-1.29 0.55 - 2.05 0.80 - 2.54 0.57-1.47 0.76-1.52
APPENDIX B DATA REPORTING CONVENTIONS B-1
Data Reportinci Conventions 1.0. All activities, except gross alpha and gross beta, are decay corrected to collection time or the end of the collection period.
2.0. Single Measurements Each single measurement is reported as follows:
x +/- s where:
x = value of the measurement; s = 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 +/- sl and x2 +/- s2 Reported result:
x +/- s; where x = (1/2) (xl + x2) and s = (1/2) 1 + S2 3.2.
Individual results:
<L1,
<L2 Reported result: <L, where L = lower of L1 and L2 3.3.
Individual results:
x +/- s, <L Reported result:
x +/- s if x tL; <L otherwise.
4.0. Computation of Averagies 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:
s 1-x_
2 x
n Ex n-1 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 number s 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
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 (pCi/L)
Strontium-89 Strontium-90 Cesium-1 37 Barium-140 Iodine-131 Potassium-40c Gross alpha Gross beta Tritium 8,000 500 1,000 8,000 1,000 4,000 2
10 I x 106 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 Gross alpha Gross beta Iodine-131b 1 x 103 1
2.8 x 10-1
APPENDIX D Sampling Location Maps D-1
/
Ih Figure D-1. Sample collection and analysis program: TLD locations, General Area of Site Boundary (Table 5.2).
D-2
Figure D-2. Sample Collection and Analysis program:TLD locations, 4-5 miles distant from the Plant, Control and Special Interest locations (Table 5.2).
D-3
9 oi ZAN i
Figure D-3. Sample Collection and analysis program: Radiation Environmental Monitoring Program, Sampling locations (Table 5.2).
D-4