L-MT-06-031, 2005 Annual Radiological Environmental Operating Report
| ML061280617 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 05/04/2006 |
| From: | Conway J Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| FOIA/PA-2010-0209 L-MT-06-031 | |
| Download: ML061280617 (59) | |
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Committed to Nuclear flence Monticello Nuclear Generating Plant Operated by Nuclear Management Company, LLC May 4, 2006 L-MT-06-031 Technical Specification 6.7.C.1 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Monticello Nuclear Generating Plant Docket 50-263 License No. DPR-22 2005 Annual Radiolocical Environmental Operatina Report In accordance with the Monticello Nuclear Generating Plant Technical Specification 6.7.C.1, the Nuclear Management Company, LLC is submitting the Annual Radiological Environmental Operating Report for the year 2005.
This letter contains no new NRC commitments, nor does it modify any prior commitments.
1'-X T. Conway Site Vice President. Monticello N lear eneratina Plant Nuclear Management Company, Enclosure cc:
Administrator, Region ll, USNRC Project Manager, Monticello, USNRC Resident Inspector, Monticello, USNRC Minnesota Department of Commerce
~42S 2807 West County Road 75
- Monticello, Minnesota 55362-9637 Telephone: 763-295-5151
- Fax: 763-295-1454
ENCLOSURE I ANNUAL REPORT TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION, RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM, JANUARY 1 TO DECEMBER 31, 2005 57 pages follow
Environmental, Inc.
Midwest Laboratory an Allegheny Technologies Co.
700 Landwehr Road
- Northbrook, IL 60062-2310 ph. (847) 564-0700
- fax (847) 564-4517 XCEL ENERGY CORPORATION 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, 2005 Prepared under Contract by ENVIRONMENTAL, Inc.
Midwest Laboratory Project No. 8010 Approved:
Lb MnaerM.S.
Xby Manager
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.
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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 Summary 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
Sampling Location Maps...................................
D-1 iii
No.
5.1 5.2 5.3 5.4 LIST OF TABLES Title Pace Sample Collection and Analysis Program....................................................
13 Sampling Locations...................................................
14 Missed Collections and Analyses................................................... 16 Radiation Environmental Monitoring Program Summary.............................................. 19 The following tables are in the Appendices:
Aopendix A A-1 Interlaboratory Comparison Program Results.
.................................................... A1-1 A-2 Thermoluminescent dosimeters (TLDs).............
....................................... A2-1 A-3 In-house Spiked Samples...................................................
A3-1 A-4 In-house "Blank" Samples................................................... A4-1 A-5 In-house "Duplicate" Samples..................................................... A5-1 A-6 Department of Energy MAPEP comparison results.................................................... A6-1 Attachment A: Acceptance criteria for spiked samples................................................... A2 Maximum Permissible Concentrations of Radioactivity in air and water above background in unrestricted areas.............
...................................... C-2 Appendix C C-1 iv
LIST OF FIGURES No.
Title Page 5-1 Offsite Ambient Radiation (TLDs), inner versus outer ring locations......................................... 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).18 ADpendix D D-1 Sample collection and analysis program: TLD locations, Inner Ring.D-2 D-2 Sample collection and analysis program: TLD locations, Outer Ring.D-3 D-3 Sample collection and analysis program: TLLD locations, Controls.D-4 D-4 Sample collection and analysis program: Radiation Environmental Monitoring Program, Milk sampling locations............................................................................................................ D-5 D-5 Sample collection and analysis program: Radiation Environmental Monitoring Program, Milk, Sludge, Ground water and Shoreline sampling locations.D-6 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, 2005.
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, 2006a) available at the Monticello Nuclear Generating Plant, Chemistry and Radiation Protection Department.
The 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 2005 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. 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.
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Proaram Desion and Data Interpretation (continued)
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 determined by gamma spectroscopy. 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 CaSO 4: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.
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.
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Proaram Description (continued)
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 Prociram Execution The Program was executed as described in the preceding section with the following exceptions:
(1)
Surface water samples could not be collected from M-08 (upstream) for the weeks ending 01-05-05 through 03-16-05. The shoreline was frozen.
(2)
No air particulate / air iodine sample was available from location M-2 for the week ending 05-11-05. The sampler pump failed.
(3)
No air particulate / air iodine sample was available from location M-5 for the week ending 05-18-05. Power was interrupted due to an open fuse.
(4)
Milk samples were not available from M-28 (Hoglund Farm) June 29th through October 5th, 2005. Dairy operations were temporarily discontinued. Collections were resumed on 10-20-05.
(5)
No air particulate / air iodine sample was available from location M-4 for the week ending 09-14-05. The breaker was tripped due to lightning.
(6)
The timer reading for air particulate I air iodine sampling from location M-3, for the week ending 09-28-05, showed a deficiency of approximately 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />.
(7)
Bottom organisms from the upstream location M-8 were not available for the collection of 10-27-05.
Deviations from the program are summarized in Table 5.3.
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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.
Gamma-spectroscopic analysis is performed using a high-purity germanium (HPGe) detector.
Levels of iodine-1 31 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 controllquality assurance program designed to assure the reliability of data obtained.
Details of the QA Program are presented elsewhere (Environmental, Inc., Midwest Laboratory, 2003 ). The QA Program includes participation in Interlaboratory Comparison (crosscheck) Programs.
Results obtained in the crosscheck programs are presented in Appendix A.
3.5 Program Modifications There were no new program modifications in 2005.
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 I 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 2005 land use census was conducted between August 29 and September 7, 2005.
An increased DIQ value (> 20%) was calculated for one nearest resident in the WNW sector. The change resulted from greater accuracy in measurement through the use of GPS location identification.
In summary, the highest D/Q locations for nearest garden, nearest residence and nearest milk animal did not change from the 2004 census.
Details of the land use census 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 5A4 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 2005. 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 2
2 beta measurements in fallout averaged 20,600 pCi/M in 1969 and 12,000 pCi/M 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 3
3 pCi/M. Present day levels have stabilized at around 0.025 pCi/M. 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-1 37 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-137, occasionally observed today can still be attributed to residual activity from atmospheric fallout. Gross beta levels in 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.
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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 (15.6 and 15.2 mRemf91 days, respectively). The mean for special locations was 15.0 mRemI91 days. The mean for control locations was 15.1 mRem/91 days. Dose rates measured at the inner and outer ring locations were similar to those observed from 1990 through 2004 and are tabulated below. No plant effect on ambient gamma radiation is indicated (Figure 5-1).
Year Inner Rin Outer Ring Dose rate (mRemf91 days) 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 2002 15.9 14.8 2003 15.6 15.0 2004 16.0 15.4 2005 15.6 15.2 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 identical at indicator 3
and control locations (0.025 pCi/M ) and were similar to levels observed from 1990 through 2004.
The results are tabulated below.
Year Indicators l
Control 3
Concentration (pCi/m) 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 2002 0.028 0.028 2003 0.027 0.027 2004 0.024 0.024 2005 0.025 0.025 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 usually occur during the months of January and December, and the first and fourth quarters, as seen in 1990 through 2005.
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., 2005b).
Gamma spectroscopic analysis of quarterly composites of air particulate filters yielded similar results for indicator and control locations.
Beryllium-7, which is produced continuously in the upper atmosphere by cosmic radiation (Arnold and Al-Salih, 1955) was detected in all samples, with an average activity of 0.057 pCi/m for all locations. All other gamma-emitting isotopes were below their respective LLD limits.
Airborne Iodine Weekly levels of airborne iodine-131 were below the lower limit of detection (LLD) of 0.03 pCi/M 3 in all samples.
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Milk lodine-131 activity measured below the detection limit of 0.5 pCi/L in all samples.
One milk sample from location M-28 tested positive for Cs-137, at a concentration of 10.1 pCi/L.
Low levels of cesium-137 are still detected in soil, and are generally attributed to fallout deposition. Ingestion of soil due to low grazing on pasture is the most likely source of Cs-137 activity in milk.
No other gamma-emitting isotopes except naturally-occurring potassium-40, were detected. 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. Common exceptions are radioisotopes of potassium, cesium, strontium, barium, and iodine.
In summary, the milk data for 2005 show no radiological effects of the plant operation.
River Water and Drinking Water Tritium activity measured below the LLD of 500 pCi/L in all samples. Gross beta activity in Minneapolis drinking water averaged 2.8 pCi/L and was similar to average levels observed from 1990 through 2004. Gross beta averages are tabulated below.
Year l
Gross Beta 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 2002 2.9 2003 3.0 2004 2.7 2005 2.8 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.
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Well Water Tritium measured below the LLD level of 500 pCi/L in all samples. All gamma isotopic results were below detection limits. There was no indication of a plant effect.
Crovs Cabbage and broccoli were collected in September from three locations and analyzed for iodine-131. Levels of 1-131 measured below 0.031 pCi/g wet weight in both samples. Other gamma-emitting isotopes were below respective LLD levels. There was no indication of a plant effect.
There were no crops irrigated from the Mississippi River within 5 miles of the plant in 2005; 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 (3.07 and 3.11 pCi/g wet weight, respectively). All gamma-emitting isotopes were below their respective LLD levels. There was no indication of any plant effect.
Invertebrates Samples were collected in May and 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. Low levels of cesium-137 were detected in three of four downstream samples, averaging 0.14 pCi/g dry weight, and 0.029 pCi/g dry weight in one of two control samples. Similar levels of activity and distribution have been observed since 1978, and are indicative of the influence of fallout deposition The only other gamma-emitting isotope detected was naturally-occurring 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)'
Frequency' Frequencyc Ambient radiation (TLDs)
Airborne Particulates 40 M-01A - M-1 4A M-01B - M-16B M-01S - M-06S M-01 C - M-04C 5
M-1(C), M-2, M-3, M-4, M-5 C/Q C/W Ambient gamma GB, GS (QC of each location)
Airborne Iodine 5
M-1(C), M-2, M-3, M-4, M-5 C/W 1-131 1-131, GS Milk 3
M-10 (C), M-24, M-28 GIMd Surface water 2
M-8(C), M-9 G/W GS(MC), H-3(QC)
Drinking water 1
M-14 G/W GB(MC), 1-131(MC)
H-3, GS Well water 4
M-10(C), M-11, M-12, M-27 GIQ Edible cultivated crops -
Corn' Leafy Vegetable Potatoes' Fish (one species, edible portion) 1 M-19 2
M-27, St. Cloud Farmer's Mkt, (C) 1 M-21 2
M-8(C), M-9 GIA G/A GIA GS 1-131 GS GS G/SA Periphyton or invertebrates Shoreline sediment 2
M-8(C), M-9 3
M-8(C), M-9, M-15 G/SA GS GS G/SA a Location codes are defined in Table 5.2, Control stations are indicated by (C). All other stations are indicators.
bCollection type is coded as follows: Cl = continuous, GJ = 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.
e 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 Typea Collection Site Sample Typeb Reactor M-1 M-2 M-3 M-4 M-5 M-8 M-9 M-1 0 M-11 M-12 M-14 M-15 M-19 M-21 M-24 M-27 C
Air Station M-1 Air Station M-2 Air Station M-3 Air Station M-4 Air Station M-5 C
Upstream of Plant Downstream of Plant C
Campbell 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)
- a. Available Producer 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 VE M
11.0 mi @ 307'/NW 0.8 mi @ 140'/SE 0.6 mi @ 104'/ESE 0.8 mi @ 1461lSSE 2.6 mi @ 1340/SE
< 1000' upstream of Plant Intake
< 1000' downstream of Plant Discharge 10.6 mi @ 357°/N 3.3 mi @ 127w/SE 0.26 mi @ 2520/SW 37.0 mi @ 1320/SE 1.27 ml @ 114'/ESE 4.7 mi @ 1800/S 0.64 mi @ 207°/SSW
> 10.0 mi.
3.8 mi @ 300°/WNW M-28 General Area of the Site Boundary M-O1A M-02A M-03A M-04A M-05A M-06A M-07A M-08A M-09A M-1OA M-11A M-12A M-13A M-14A 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 0.75 mi @ 353°lN 0.79 mi @ 23°/NNE 1.29 mi @ 55°/NE 0.5 mi @ 86°/E 0.48 mi @ 118°/ESE 0.54 mi @ 135°/SE 0.5 mi @ 155°/SSE 0.48 mi @ 1720/S 0.38 mi @ 209°/SSW 0.38 mi @ 226°/SW 0.4 mi @ 239°lWSW 0.5 mi @ 262 0°W 0.89 mi @ 324°/NW 0.78 mi @ 334°/NNW 14
Table 5.2. Sampling locations, Monticello Nuclear Generating Plant, (continued).
Distance and Direction from Code Typea Collection Site Sample Typeb Reactor Approximately 4 to 5 miles Distant from the Plant M-01B M-02B M-03B M-04B M-05B M-06B M-07B M-08B M-09B M-10B M-11B M-12B M-13B M-14B M-15B M-16B 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 TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD 4.66 mi @ 02°/N 4.4 ml @ 180/NNE 4.3 ml @ 51°/NE 4.2 mi @ 67°/ENE 4.3 ml @ 89°/E 4.3 mi @ 117 01ESE 4.3 mi @ 136°/SE 4.6 mi @ 162°/SSE 4.7 mi @ 178°/S 4.2 ml @ 204°/SSW 4.0 ml @ 228'/SW 4.2 mi @ 254°/WSW 4.1 ml @ 270°/W 4.3 ml @ 289°/WNW 4.3 ml @ 309°/NW 4.4 mi @ 341°/NNW 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
Osowski Fun Market Krone 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 0.66 ml @ 2421VWSW 0.5 ml @ 224°/SW 1.53 ml @ 102°/ESE 2.3 ml @ 131°/SE 3.0 ml @ 118°/ESE 2.6 ml @ 134°/SE 11.5 ml @ 323°/NW 11.2 mi @ 47°/NE 11.6 mi @ 130°1SE 10.3 ml @ 226°/ 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
Fish M
RW SS TLD VE WW Milk River Water Shoreline Sediments Thermoluminescent Dosimeter 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:
Collection Reason for not Sample Analysis Location Date or conducting REMP Plans for Preventing Type Period as required Recurrence SW Gamma M-08 01-05-05 Shoreline frozen None required.
through 03-16-05 AP/AI
- Beta, M-02 5/11/2005 Air sampler malfunction.
Sampler pump replaced.
1-131 AP/AI
- Beta, M-05 5/18/2005 Air sampler failure due Electrician checked sampler and 1-131 to open fuse.
replaced fuse.
Ml
- Gamma, M-28 6/29/2005 Hoglund Dairy temporarily out Hoglund will inform the MNGP 1-131 through of business for the summer.
upon resumption of operation.
10/5/2005 Operation resumed 10/20/05.
AP/AI
- Beta, M-04 9/14/2005 Breaker tripped during storm. Reset breaker.
1-131 AP/AI
- Beta, M-03 9/28/2005 Air sampler timer deficient Replaced timer.
1-131 by 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />.
BO Gamma M-08 10/27/2005 No sample available.
None required.
16
Figure 5-1. Offsite Ambient Radiation (TLDs); Inner Ring versus Outer Ring locations.
I-Inner 2-- Outer 20l------
X_
18 -
17 -
11
_ 1 10 l
.k i_
o CN M
'1 LO (D
1-00
- 0) 0 Of M
I )
- 0) a)
a)
C)
C M
M M
C a 8
)
0 0
0
- 0)
C C
0 0
0 T
CN4 N
CN N
(N E
17
Figure 5-2. Airborne Particulates; analysis for gross beta, average mean of all indicator locations versus control location.
Indicators (M-2, 3, 4, 5)
I i 0.035
! 0,033 ]<
0.031
_ f _
0.029
--. K 1
0.027 >;
0L 0.021
- f L --
0.015 u
LJ O
N C\\
' )
)
CD t-M 0
0 O-N C) r UL
- 0)
- 0)
- 0)
- 0)
CT)
- 0)
)
- 0)
CY) 0 0
0 0
0 0
0
- 0)
- 0)
- 0)
- 0)
C)
- 0)
- 0)
- 0)
- 0) 0 0
0 0
0 0
_N N
_N N
N Control (M-1) 0.035 0.033 0.031 0.029 0.027 0.025 E
0.023 0
0.021 0.019 0.017 0.015 O
r _
C')
e U )
(O C-.
>)
- 0) 0 N
C' C
U7 01 0
0 V) 0 c
C )
?
Zs o
o o
- 0)
- 0)
)
i 0
0
- 0) a0
- 0)
- 0)
C) o 0
0 0
0 o
N N
CON N
N CON 18
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Monticello Nuclear Generating Plant Docket No.
Reporting Period Wright, Minnesota
( County, State )
50-263 January-December, 2005 Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLD' Mean (F)0 Mean (F)f Mean (F)0 Routine (Units)
Analysesa Rangec Locationd Range' Rangec Results' TLD (Inner Ring, Gamma 56 3.0 15.6 (56/56)
M-12A, County Rd. 75, 17.4 (4 /4)
(See Control 0
General Area at (12.5-18.4) 0.5 mi @ 262°/W (15.2-18.4) below.)
Site Boundary) mRem/91 days)
TLD (Outer Ring, Gamma 64 3.0 15.2 (64/64)
M-09B, Weinand Farm 16.5 (4 /4)
(See Control 0
4-5 mi. distant)
(12.3-17.7) 4.7 mi @ 178'/S (14.6-17.7) below.)
mRem/91 days)
TLD (Special Gamma 24 3.0 15.0 (24/24)
M-06S, Mont. Pub. Wks.
16.9 (4 /4)
(See Control 0
Interest Areas)
(11.3-17.7) 2.6 mi @ 134°/SE (15.5-17.7) below.)
mRem/91 days)
TLD (Control)
Gamma 16 3.0 None M-03C, County and 16.1 (4 /4) 15.1 (16/16) 0 mRem/91 days)
Jason, 11.6 mi @ 130°/SE (15.5-17.3)
( 13.7-17.3)
Airborne GB 256 0.005 0.025 (204/204)
M-5, Air Station 0.026 (51 /51) 0.025 (52/52) 0 Particulates (0.007-0.064) 2.6 mi @ 134°/SE (0.009-0.058)
(0.010-0.066)
(pCi/m3)
GS 20 Be-7 0.015 0.063 (16/16)
M-2, Air Station 0.071 (4/4) 0.064 (4/4) 0 (0.037-0.100) 0.8 mi @ 140°/SE (0.052-0.100)
(0.040-0.086)
Mn-54 0.0007
< LLD
< LLD 0
Co-58 0.0008
< LLD
< LLD 0
Co-60 0.0010
< LLD
< LLD 0
Zn-65 0.0016
< LLD
< LLD 0
Zr-Nb-95 0.0012
< LLD
< LLD 0
Ru-103 0.0011
< LLD
< LLD 0
Ru-106 0.0079
< LLD
< LLD 0
Cs-134 0.0009
< LLD
< LLD 0
Cs-137 0.0008
< LLD
< LLD 0
Ba-La-140 0.0030
< LLD
< LLD 0
Ce-141 0.0020
< LLD
< LLD 0
Ce-144 0.0055
< LLD
< LLD 0
Airborne Iodine 1-131 256 0.03
< LLD
< LLD 0
(pCi/m3) 19
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Monticello Nuclear Generating Plant Wright, Minnesota Docket No.
50-263 Reporting Period January-December, 2005
( County, State )
Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLD' Mean (F)c Mean (F)'
Mean (F)'
Routine (Units)
Analysesa Rangec Locationd Range' Range' Resultse Milk (pCi/L) 1-131 49 0.5
< LLD
<- LLD 0
GS 49 K-40 200 1305 (30130)
M-28 1331 (11 /11) 1285 (19119) 0 (1180-1430)
Hoglund Farm (1235-1430)
(1174-1395)
Cs-134 5
< LLD
< LLD 0
Cs-1 37 5
10.1 (1130)
M-28 10.1 (1/11)
< LLD 0
Hoglund Farm Ba-La-140 5
< LLD
< LLD 0
River Water H-3 8
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 15
< LLD
< LLD 0
Cs-137 18
< LLD
< LLD 0
Ba-La-140 15
< LLD
< LLD 0
Ce-144 46
< LLD
< LLD 0
20
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Monticello Nuclear Location of Facility Wright, Minnesota Generating Plant Docket No.
50-263 Reporting Period January-December, 2005
( County, State )
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)'
Routine (Units)
Analysesa Rangec Locationd Rangec Range0 Results' Drinking Water GB 10 1.6 2.8 (10112)
M-14, Minneapolis 2.8 (10/12)
None 0
(pCUL)
(2.1-4.6) 37.0 mi. @ 132° /SE (2.1-4.6) 1-131 10 1.0
< LLD None 0
H-3 4
500
< LLD None 0
GS 10 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 51
< LLD None 0
Well Water H-3 16 500
< LLD
< LLD 0
(pCi/L)
GS 16 Mn-54 15
< LLD cLLD 0
Fe-59 30
< LLD cLLD 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 c-
<LLD 0
Cs-137 18
< LLD c-
<LLD 0
Ba-La-140 15
< LLD c-LLD 0
Ce-144 56
< LLD c-
<LLD 0
Crops -Cabbage GS 2
(pCi/gwet) 1-131 0.031
< LLD c-
<LLD 0
Cs-134 0.008
< LLD
< LLD 0
Cs-137 0.019
21
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Monticello Nuclear Location of Facility Wright, Minnesota Generating Plant Docket No.
50-263 Reporting Period January-December, 2005
( County, State )
Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)0 Mean (F)c Mean (F)c Routine (Units)
Analysesa Range' Locationd Range0 Range' Resultse Fish GS 4
(pCi/g wet)
K-40 0.10 3.11 (2/2) 2 3.11 (2/2) 3.07 (2/2) 0 (3.05-3.17)
M-09 (3.05-3.17)
(2.82-3.32)
Mn-54 0.024
< LLD
< LLD 0
Fe-59 0.048
< LLD
< LLD 0
Co-58 0.031
< LLD
< LLD 0
Co-60 0.025
< LLD
< LLD 0
Zn-65 0.045
< LLD
< LLD 0
Zr-Nb-95 0.053
< LLD
< LLD 0
Cs-134 0.017
< LLD
< LLD 0
Cs-137 0.020
< LLD
< LLD 0
Ba-La-140 0.15
< LLD
< LLD 0
Ce-144 0.09
< LLD
< LLD 0
Invertebrates GS 4
(pCi/g wet)
Be-7 0.74
< LLD
< LLD 0
K140 1.27
< LLD
< LLD 0
Mn-54 0.05
< LLD
< LLD 0
Fe-59 0.16
< LLD
< LLD 0
Co-58 0.07
Co-60 0.06
< LLD
< LLD 0
Zn-65 0.13
< LLD
< LLD 0
Zr-Nb-95 0.13
< LLD
< LLD 0
Ru-103 0.12
< LLD
< LLD 0
Ru-106 0.53
< LLD
< LLD 0
Cs-134 0.06
< LLD
< LLD 0
Cs-137 0.05
< LLD
< LLD 0
Ba-La-140 0.51
< LLD
< LLD 0
Ce-144 0.42
< LLD
< LLD 0
22
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Monticello Nuclear Generating Plant Wright, Minnesota Docket No.
Reporting Period 50-263 January-December, 2005
( County, State )
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)
Routine (Units)
Analyseso Rangec Locationd Range' Range 0 Resultse Shoreline GS 6
Sediments Be-7 0.34
< LLD
< LLD 0
(pCi/g dry)
K-40 0.10 11.46 (4/4)
M-09, Downstream 12.14 (2/2) 10.81 (2/2) 0 (9.77-12.23) 0.2 mi @ 62 0/ENE (12.04-12.23)
(10.31-11.31)
Mn-54 0.026
< LLD
< LLD 0
Fe-59 0.135
< LLD
< LLD 0
Co-58 0.033
< LLD
< LLD 0
Co-60 0.025
< LLD
< LLD 0
Zn-65 0.075
< LLD
< LLD 0
Nb-95 0.073
< LLD
< LLD 0
Zr-95 0.072
< LLD
< LLD 0
Ru-103 0.050
< LLD
< LLD 0
Ru-106 0.25
< LLD
< LLD 0
Cs-1 34 0.036
< LLD
< LLD 0
Cs-137 0.025 0.14 (3/4)
M-09, Downstream 0.15 (2/2) 0.029 (112) 0 (0.11-0.20) 0.2 mi @ 62 0/ENE (0.11-0.20)
Ba-La-140 0.37
< LLD
< LLD 0
Ce-144 0.15
< 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.
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.
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. Al-Salih. 1955. Beryllium-7 Produced by Cosmic Rays. Science 121: 451-453.
Eisenbud, M. 1963. Environmental Radioactivity, McGraw-Hill, New York, New York, pp. 213, 275, 276.
Environmental, Inc., Midwest Laboratory.
2001a through 2006a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January-December, 2000 through 2005.
2001b through 2006b.
Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 2000 through 2005.
2003.
Quality Assurance Program Manual, Rev. 1, 01 October 2003.
2005.
Quality Control Procedures Manual, Rev. 0, 17 September 2005.
2003.
Quality Control Program, Rev. 1, 21 August 2003.
Gold, S., H.W. Barkhau, B. Shlein, and B. Kahn, 1964.
Measurement of Naturally Occurring Radionuclides in Air, in the Natural Environment, University of Chicago Press, 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 I 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.
11984b 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.
2006. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2000 through 2005. (prepared by Environmental, Inc., Midwest Laboratory). Northbrook, Illinois 25
Environmental, Inc.
Midwest Laboratory X/
an Allegheny Technologies Co.
700 Landwehr Road. Northbrook, IL 60062-2310 ph. (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 perfon-nance 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, 2005 through December, 2005
Appendix A Interlaboratorv Comparison Program Results Environmental, Inc., Midwest Laboratory has participated in interlaboratory comparison (crosscheck) programs since the formulation of it's quality control program in December 1971. These programs are operated by agencies which supply environmental type samples containing concentrations of radionuclides known to the issuing agency but not to participant laboratories. The purpose of such a program is to provide an independent check on a laboratory's analytical procedures and to alert it of any possible problems.
Participant laboratories measure the concentration of specified radionuclides and report them to the issuing agency. Several months later, the agency reports the known values to the participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used.
Results in Table A-1 were obtained through participation in the environmental sample crosscheck program administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada.
The results in Table A-2 list results for thermoluminescent dosimeters (TLDs), via International Intercomparison of Environmental Dosimeters, when available, and internal laboratory testing.
Table A-3 lists results of the analyses on in-house 'spiked" samples for the past twelve months. All samples are prepared using NIST traceable sources. Data for previous years available upon request.
Table A-4 lists results of the analyses on in-house "blank" samples for the past twelve months. Data for previous years available upon request.
Table A-5 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.
Attachment A lists acceptance criteria for "spiked' samples.
Out-of-limit results are explained directly below the result.
Al
Attachment A ACCEPTANCE CRITERIA FOR 'SPIKED" SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSES' One standard deviation Analysis Level for single determination Gamma Emitters 5 to 100 pCi/liter or kg 5.0 pCi/liter
> 100 pCi/liter or kg 5% of known value Strontium-89b 5 to 50 pCi/liter or kg 5.0 pCi/liter
> 50 pCi/liter or kg 10% of known value Strontium-90b 2 to 30 pCi/liter or kg 5.0 pCi/liter
> 30 pCi/liter or kg 10% of known value Potassium-40 2 0.1 g/liter or kg 5% of known value Gross alpha
- 20 pCi/liter 5.0 pCi/liter
> 20 pCi/liter 25% of known value Gross beta
- 100 pCi/liter 5.0 pCi/liter
> 100 pCi/liter 5% of known value Tritium
- 4,000 pCi/liter l ao = (pCi/liter) =
169.85 x (known)0093 3
> 4,000 pCi/liter 10% of known value Radium-226,-228 2 0.1 pCi/liter 15% of known value Plutonium
Ž 0.1 pCi/liter, gram, or sample 10% of known value lodine-131,
- 55 pCi/liter 6.0 pCi/liter Iodine-129b
> 55 pCi/liter 10% of known value Uranium-238, 5 35 pCi/liter 6.0 pCi/liter Nickel-63b
> 35 pCi/liter 15% of known value Technetium-99b Iron-55b 50 to 100 pCi/liter 10 pCi/liter
> 100 pCi/liter 10% of known value Othersb_
20% of known value a From EPA publication, "Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.
b Laboratory limit.
A2
TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)".
Concentration (pCi/L)
Lab Code Date Analysis Laboratory ERA Control Resuitb Resultc Limits Acceptance STW-1051 STW-1051 STW-1052 STW-1052 STW-1 052 STW-1052 STW-1052 STW-1053 STW-1 053 STW-1054 STW-1054 STW-1054 02/1 5/05 Sr-89 02/15/05 Sr-90 02/15/05 Ba-133 02/15/05 Co-60 02/15/05 Cs-1 34 02/15/05 Cs-137 02/15/05 Zn-65 02/15/05 Gr. Alpha 02/15/05 Gr. Beta 02/15/05 Ra-226 02/15/05 Ra-228 02/15/05 Uranium 28.0 +/- 1.2 25.1 +/- 0.7 52.9 +/- 2.8 54.4 +/- 0.4 67.7 +/- 1.8 39.6 +/- 1.8 159.7 +/-3.0 55.1 +/-1.8 46.8 +/- 1.3 13.7 +/- 1.5 13.3 +/- 0.6 5.1 +/-0.2 29.4 24.4 53.4 56.6 64.9 40.2 161.0 67.9 51.1 14.1 13.7 5.0 20.7 - 38.1 15.7 - 33.1 44.2 - 62.6 47.9 - 65.3 56.2 - 73.6 31.5 - 48.9 133.0 - 189.0 38.5 - 97.3 38.5 - 97.3 10.4 - 17.8 7.8 - 19.6 0.0 - 10.2 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass STW-1055 STW-1055 STW-1 056 STW-1 056 STW-1056 STW-1 056 STW-1 056 STW-1 057 STW-1057 STW-1058 STW-1 059 STW-1 059 STW-1059 STW-1 060 05/17/05 Sr-89 05/17/05 Sr-90 05/17/05 Ba-i 33 05/17/05 Co-60 05/17/05 Cs-i 34 05/17/05 Cs-137 05/17/05 Zn-65 05/17/05 Gr. Alpha 05/17/05 Gr. Beta 05/17/05 1-131 05/17/05 Ra-226 05/17/05 Ra-228 05/17/05 Uranium 05/17/05 H-3 45.1 +/- 4.1 7.5 +/- 0.9 87.1 +/- 2.0 38.4 +/- 0.8 75.3 +/- 0.7 201.0 +/- 8.4 130.0 +/- 6.7 42.7 +/- 2.9 34.0 +/- 0.4 14.7 +/- 0.5 6.6 +/- 0.1 19.3 +/- 0.7 9.6 +/-0.1 24100.0 +/- 109.0 41.3 5.9 88.4 37.0 78.6 194.0 118.0 37.0 34.2 15.5 7.6 18.9 10.1 24400.0 32.6 - 50.0 0.0 - 14.6 73.1 - 104.0 28.3 - 45.7 69.9 - 87.3 184.0 - 218.0 97.6 - 138.0 21.0 - 53.0 25.5 - 42.9 10.3 - 20.7 5.6 - 9.5 10.7 - 27.1 4.9 - 15.3 20200.0 - 28600.0 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass STW-1 067 STW-1067 STW-1068 STW-1068 STW-1 068 STW-1 068 STW-1 068 STW-1 069 STW-1069 STW-1 070 STW-1070 STW-1 070 08/16/05 Sr-89 08/16/05 Sr-90 08/16/05 Ba-133 08/16/05 Co-60 08/16/05 Cs-134 08/16/05 Cs-1 37 08/16/05 Zn-65 08/16/05 Gr. Alpha 08/16/05 Gr. Beta 08/16/05 Ra-226 08/16/05 Ra-228 08/16/05 Uranium 29.1 +/- 3.0 36.0 +/- 0.6 107.0 +/- 1.7 15.2 +/- 0.2 89.1 +/- 0.3 72.1 +/- 1.0 67.4 +/- 1.4 44.3 +/- 1.5 58.4 +/-2.1 16.6 +/- 1.5 6.2 +/- 0.3 4.5 +/- 0.1 28.0 33.8 106.0 13.5 92.1 72.7 65.7 55.7 61.3 16.6 6.2 4.5 19.3 - 36.7 25.1 - 42.5 87.7 - 124.0 4.8 - 22.2 83.4 - 101.0 64.0 - 81.4 54.3 - 77.1 31.6 - 79.8 44.0 - 78.6 12.3 - 20.9 3.5 - 8.9 0.0 - 9.7 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A1-1
TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.
Concentration (pCi/L)
Lab Code Date Analysis Laboratory ERA Control Resultb Resultc Limits Acceptance STW-1 072 STW-1 072 STW-1 073 STW-1 073 STW-1 073 STW-I 073 STW-1 073 STW-1 074 d STW-1 074 STW-1 075 STW-1 076 STW-1076 e STW-1 076 STW-1 077 1/1 15/05 11/15/05 11/15/05 11/15/05 11/15/05 11/15/05 11/15/05 11/15/05 11/15/05 11/15/05 11/15/05 11/15/05 1 1/15/05 11/15/05 Sr-89 Sr-90 Ba-1 33 Co-60 Cs-1 34 Cs-1 37 Zn-65 Gr. Alpha Gr. Beta 1-131 Ra-226 Ra-228 Uranium H-3 20.6 +/- 0.4 15.0 +/- 0.3 31.8 +/- 1.8 85.0 +/- 1.4 37.2 +/- 2.1 27.8 +/- 0.7 109.0 +/- 1.0 41.1 +/- 1.2 42.7 +/- 0.5 20.5 +/- 0.6 7.8 +/- 0.6 5.5 +/- 0.6 15.5 +/- 0,3 12500.0 +/- 238.0 19.0 16.0 31.2 84.1 33.9 28.3 105.0 23.3 39.1 17.4 8.3 3.5 16.1 12200.0 10.3 - 27.7 7.3 - 24.7 22.5 - 39.9 75.4 - 92.8 25.2 - 42.6 19.6 - 37.0 86.8 - 123.0 13.2 - 33.4 30.4 - 47.8 12.2 - 22.6 6.2 - 10.5 2.0 - 5.0 10.9 - 21.3 10100.0 - 14300.0 Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Fail Pass Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).
b Unless otherwise indicated, the laboratory result is given as the mean +/- standard deviation for three determinations.
c Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA.
d The original samples were calculated using an Am-241 efficiency. The samples were spiked with Th-232. Samples were recounted and calculated using the Th-232 efficiency. Results of the recount: 27.01 +/- 2.35 pCi/L.
e Decay of short-lived radium daughters contributed to a higher counting rate. Delay of counting for 100 minutes provided better results.
The reported result was the average of the first cycle of 100 minutes, the average of the second cycle counts was 4.01 pCi/L A1-2
TABLE A-2, Crosscheck program results; Thermoluminescent Dosimetry, (TLD, CaSO4: Dy Cards).
mR Lab Code Date Known Lab Result Control Description Value
+/- 2 sigma Limits Acceptance Environmental, Inc.
2005-1 4/4/2005 2005-1 4/4/2005 2005-1 4/4/2005 2005-1 4/4/2005 2005-1 4/4/2005 2005-1 4/4/2005 2005-1 4/4/2005 2005-1 4/4/2005 2005-1 4/4/2005 30 cm 60 cm 60 cm 90 cm 90 cm 120 cm 120 cm 150 cm 180 cm 55.01 13.75 13.75 6.11 6.11 3.44 3.44 2,2 1.53 64.02 +/- 2.86 15.43 +/- 1.02 14.98 +/- 0.80 6.24 +/- 0.16 5.45 +/- 0.48 3.50 +/- 0.35 3.15 +/- 0.18 2.31 +/- 0.25 1.65 +/- 0.41 38.51 - 71.51 9.63 - 17.88 9.63 - 17.88 4.28 - 7.94 4.28 - 7.94 2.41 - 4.47 2.41 - 4.47 1.54 - 2.86 1.07 - 1.99 Pass Pass Pass Pass Pass Pass Pass Pass Pass Environmental, Inc.
2005-2 2005-2 2005-2 2005-2 2005-2 2005-2 2005-2 2005-2 2005-2 9/12/2005 9/12/2005 9/12/2005 9/12/2005 9/12/2005 9/12/2005 9/12/2005 9/12/2005 9/12/2005 30 cm 60 cm 75 cm 90 cm 90 cm 120 cm 150 cm 150 cm 180 cm 54.84 13.71 8.77 6.09 6.09 3.43 2.19 2.19 1.52 59.30 +/- 2.66 17.55 +/- 1.30 8.24 +/- 0.38 5.94 +/- 0.49 5.93 +/- 0.37 3.42 +/- 0.18 1.71 +/- 0.14 1.87 +/- 0.27 1.58 +/- 0.99 38.39 - 71.29 9.60 - 17.82 6.14 - 11.40 4.26 - 7.92 4.26 - 7.92 2.40 - 4.46 1.53 - 2.85 1.53 - 2.85 1.06 - 1.98 Pass Pass Pass Pass Pass Pass Pass Pass Pass A2-1
TABLE A-3. In-House 'Spike" Samples Concentration (pCi/L)a Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 C Activity Limits d Acceptance W-11105 W-11105 SPW-764 SPAP-766 STW-2887 W-30105 W-30105 SPW-1836 SPW-1836 SPMI-1 838 SPMI-1838 SPMI-1838 SPMI-1838 SPMI-1838 SPMI-1838 SPVE-1932 SPCH-1935 SPAP-1966 SPAP-1966 SPAP-1966 SPAP-1968 SPAP-1968 SPW-2098 SPW-2922 SPW-2922 SPW-2922 SPW-2922 SPAP-2892 SPW-2895 w-60105 w-60105 SPF-3089 SPF-3089 SPW-SPW-47731 SPW-47732 SPW-4775 SPMI-4834 SPMI-4834 SPMI-4834 SPMI-4834 1/11/2005 1/11/2005 2/18/2005 2/18/2005 2/28/2005 3/1/2005 3/1/2005 4/15/2005 4/15/2005 4/15/2005 4/15/2005 4/15/2005 4/15/2005 4/15/2005 4/15/2005 4/18/2005 4/18/2005 4/18/2005 4/18/2005 4/18/2005 4/18/2005 4/18/2005 4/26/2005 5/31/2005 5/31/2005 5/31/2005 5/31/2005 6/1/2005 6/1/2005 6/1/2005 6/1/2005 6/7/2005 6/7/2005 7/1/2005 8/24/2005 8/24/2005 8/24/2005 8/30/2005 8/30/2005 8/30/2005 8/30/2005 Gr. Alpha Gr. Beta H-3 Gr. Beta Tc-99 Gr. Alpha Gr. Beta 1-131 1-131 (G)
Cs-134 Cs-137 1-131 1-131(G)
Sr-89 Sr-90 1-131 (G)
I-131 Cs-134 Cs-134 Cs-1 37 Cs-134 Cs-137 Fe-55 Cs-1 34 Cs-134 Sr-89 Sr-90 Gr. Beta H-3 Gr. Alpha Gr. Beta Cs-134 Cs-137 Ni-63 C-1 4 C-1 4 Fe-55 Cs-1 34 Cs-1 37 Sr-89 Sr-90 24.05 +/- 1.01 61.59 +/- 1.11 77595.00 i 764,00 416.08 +/- 5.52 32.91 +/- 1.23 25.22 +/- 0.45 62.27 +/- 0.48 109.79 +/- 0.94 110.25 +/- 9.68 25.94 +/- 1.28 59.31 +/- 3.66 97.71 +/-0.81 109.45 +/- 3.06 104.44 +/- 2.89 8.97 +/- 0.79 1.00 +/- 0.04 382.40 +/- 14.95 52.10 +/- 7.27 57.28 +/- 13,47 124.68 +/- 18.41 52.10 +/- 7.27 116.79 +/- 14.00 2565.20 +/- 63.66 27.01 +/- 1.09 65.38 +/- 2.92 107.90 +/- 3.60 11.11 +/- 1.13 420.32 +/- 5.55 75271.00 +/- 724.00 23.69 +/- 0.52 60.08 +/- 0.57 1.08 +/- 0.05 2.54 +/- 0.10 20.57 +/- 1.10 2112.30 +/- 9.13 2294.10 +/- 10.37 2633.50 +/- 62.40 49.27 +/- 4.68 58.17 +/- 8.18 66.39 +/- 3.13 11.15 +/- 1.13 20.08 65.70 80543.00 463.00 32.98 20.08 65.73 106.30 106.30 26.60 60.90 106.30 106.30 108.20 7.53 0.73 328.64 53.35 53.35 121.77 53.35 121.77 3017.60 25.54 60.71 113.90 6.90 448.00 78676.00 20.08 65.73 1.02 2.43 16.75 2370.80 2370.80 2777.50 47.02 60.37 65.90 9.60 10.04 - 30.12 55.70 - 75.70 64434.40 - 96651.60 370.40 - 509.30 20.98 - 44.98 10.04 - 30.12 55.73 - 75.73 85.04 - 127.56 95.67 - 116.93 16.60 - 36.60 50.90 - 70.90 85.04 - 127.56 95.67 - 116.93 86.56 - 129.84 0.00 - 17.53 0.44 - 1.02 262.91 - 394.37 43.35 - 63.35 43.35 - 63.35 109.59 - 133.95 43.35 - 63.35 109.59 - 133.95 2414.08 - 3621.12 15.54 - 35.54 50.71 - 70.71 91.12 - 136.68 0.00 - 16.90 358.40 - 492.80 62940.80 - 94411.20 10.04 - 30.12 55.73 - 75.73 0.61 - 1.43 1.46 - 3.40 10.05 - 23.45 1422.48 - 3319.12 1422.48 - 3319.12 2222.00 - 3333.00 37.02 - 57.02 50.37 - 70.37 52.72 - 79.08 0.00 - 19.60 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A3-1
TABLE A-3. In-House "Spike" Samples Concentration (pCi/L)
Lab Code Date Analysis Laboratory results Known Control 2s, n=1b Activity Limitsc Acceptance SPW-4836 SPW-4836 SPW-4836 SPW-4836 SPW-5014 W-90705 W-90705 SPW-5237 SPW-5508 SPW-6019 SPF-6293 SPF-6293 SPAP-6309 SPAP-6309 SPAP-6311 SPW-6451 W-1 20105 W-1 20105 SPW-7440 SPW-7440 SPMI-7442 SPMI-7442 8/30/2005 8/30/2005 8/30/2005 8/30/2005 8/3012005 9/7/2005 9/7/2005 9/22/2005 9/2612005 10/24/2005 11/4/2005 11/4/2005 11/7/2005 11/7/2005 11/7/2005 11/10/2005 121112005 12/112005 12/30/2005 12/30/2005 12/31/2005 12/31/2005 Cs-134 Cs-1 37 Sr-89 Sr-90 H-3 Gr. Alpha Gr. Beta C-14 Ni-63 Tc-99 Cs-1 34 Cs-137 Cs-134 Cs-137 Gr. Beta H-3 Gr. Alpha Gr. Beta Cs-1 34 Cs-1 37 Cs-134 Cs-137 47.35 +/- 5.19 62.91 +/- 9.08 11.04 +/- 0.98 65.89 +/- 2.79 77518.20 +/- 753.80 24.61 +/- 0.48 58.35 +/- 0.49 2387.40 +/- 11.00 20.64 +/- 1.23 547.99 +/- 6.69 941.30 +/-44.10 2570.40 +/- 105,30 41.24 i 1.91 114.03 +/- 5.01 1.58 +/- 0.02 77126.00 +/- 747.00 25.16 + 0.45 74.58 + 0.81 42.67 i 4.22 61.19 i7.20 40.41 i 5.66 60.05 +/- 7.80 47.02 60.37 9.60 65.90 77602.52 20.08 65.73 2370.80 16.70 539.22 886.00 2400.00 44.03 120.24 1.42 76749.00 20.08 65.73 42.03 59.91 42.03 59.91 37.02 - 57.02 50.37 - 70.37 0.00 - 19.60 52.72 - 79.08 62082.02 - 93123.02 10.04 - 30.12 55.73 - 75.73 1422.48 - 3319.12 10.02 - 23.38 377.45 - 700.99 797.40 - 974.60 2160.00 - 2640.00 34.03 - 54.03 108.22 - 132.26 1.14 - 11.42 61399,20 - 92098.80 10.04 - 30.12 55.73 - 75.73 32.03 - 52.03 49.91 - 69.91 32.03 - 52.03 49.91 - 69.91 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass a Liquid sample results are reported in pCi/Liter, air filters( pCi/filter), charcoal (pCi/i 3), and solid samples (pCilg).
bLaboratory codes as follows: W (water), MI (milk), AP (air filter), SO (soil), VE (vegetation),
CH (charcoal canister), F (fish).
' Results are based on single determinations.
d Control limits are based on Attachment A, Page A2 of this report.
NOTE: For fish, Jello is used for the Spike matrix, For Vegetation, cabbage is used for the Spike matrix.
A3-2
TABLE A-4. In-House "Blank" Samples Concentration (pCiIL)a Lab Code Sample Date Analysis Laboratory results (4.66a)
Acceptance Type LLD Activityb Criteria (4.66 o)
W-11105 W-11105 SPW-765 SPAP-766 STW-2888 W-30105 W-30105 water water water Air Filter water water water 1/11/2005 1/11/2005 2/18/2005 2/1812005 2/28/2005 3/1/2005 3/1/2005 Gr. Alpha Gr. Beta H-3 Gr. Beta Tc-99 Gr. Alpha Gr. Beta 0.055 0.15 165.8 0.72 1.32 0.067 0.18 0.00 i 0.038
-0.016 +/- 0.10 7.4 +/- 82.5 0.29 +/- 0.48 0.45 +/- 0.81
-0.007 +/- 0.043
-0.04 +/- 0.11 3.2 200 3.2 10 1
3.2 SPW-1837 SPW-1837 SPW-1 837 SPW-1 837 SPMI-1839 SPMI-1839 SPMI-1839 SPCH-1934 SPW-2097 SPW-2923 SPW-2923 SPW-2896 w-60105 w-60105 SPF-3090 SPF-3090 SPW-SPW-4774 SPW-4776 SPMI-4835 SPMI-4835 SPMI-4835 SPMI-4835 SPMI-4835 SPMI-4835 d SPW-4837 SPW-4837 SPW-4837 SPW-4837 SPW-4837 SPW-5015 SPW-5238 water
- water water water Milk Milk Milk Charcoal water water water water water water Fish Fish water water water Milk Milk Milk Milk Milk Milk water water water water water water water 4/15/2005 4/15/2005 4/15/2005 4/15/2005 4/15/2005 4/15/2005 4/15/2005 4/18/2005 4/26/2005 5/31/2005 5/31/2005 6/1/2005 6/1/2005 6/1/2005 6/7/2005 6/7/2005 7/1/2005 8/2412005 8/24/2005 8/30/2005 8/30/2005 8/30/2005 8/30/2005 8/30/2005 8/3012005 8/30/2005 8/30/2005 8/30/2005 8/30/2005 8/30/2005 8/30/2005 9/22/2005 Cs-134 Cs-137 1-131 I-1 31 (G) 1-131 Sr-89 Sr-90 1-131(G)
Fe-55 Cs-134 Cs-137 H-3 Gr. Alpha Gr, Beta Cs-1 34 Cs-137 Ni-63 C-14 Fe-55 Co-60 Cs-134 Cs-1 37 1-131(G)
Sr-89 Sr-90 Co-60 Cs-134 Cs-137 Sr-89 Sr-90 H-3 C-1 4 4.66 5.38 0.30 6.56 0.26 0.54 0.53 2.34 859.0 3.29 3.87 138.30 0.061 0.16 15.69 11.71 1.60 12.18 833 4.42 4.18 6.25 5.37 0.66 0.66 2.48 3.85 3.00 0.63 0.63 142.8 17.10
-0.13 +/- 0.16
-0.083 +/- 0.14
-0.069 +/- 0.56 0.88 +/- 0.34 96.1 +/- 528.4 48.1 +/- 85.9 0.002 +/- 0.043 0.056 +/- 0.11 0.79 +/- 0.99 2.84 +/- 6.45 275 +/- 525
-0.23 +/- 0.65 1.02 +/- 0.41 0.25 +/- 0.53
-0.035 +/- 0.29 168 +/- 93 3.02 +/- 9.04 10 10 0.5 20 0.5 5
9.6 1000 10 10 200 1
3.2 100 100 20 200 1000 10 10 10 20 5
10 10 10 5
1 200 200 A4-1
TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)8 Lab Code Sample Date Analysis Laboratory results (4.66a)
Acceptance Type LLD Activityb Criteria (4.66 a)
W-90705 W-90705 SPW-5238 SPW-5509 SPW-6020 SPF-6294 SPF-6294 SPAP-6310 SPAP-631 0 SPAP-6312 W-1 20105 W-1 20105 SPMI-741 9 SPMI-741 9 SPMI-7419 SPW-742 1 SPW-7421 SPW-7441 SPW-744 1 SPMI-7443 SPMI-7443 water water water water water Fish Fish Air Filter Air Filter Air Filter water water Milk Milk Milk water water water water Milk Milk 9/7/2005 917/2005 9/22/2005 9/2612005 10124/2005 11/4/2005 11/4/2005 11/7/2005 11/7/2005 11/7/2005 12/11/2005 12/11/2005 12/22/2005 12122/2005 12/22/2005 12/22/2005 12/22/2005 12/30/2005 12/30/2005 12/30/2005 12/30/2005 Gr. Alpha Gr. Beta C-14 Ni-63 Tc-99 Cs-1 34 Cs-1 37 Cs-1 34 Cs-137 Gr. Beta Gr. Alpha Gr. Beta Co-60 Cs-1 37 1-131(G)
Co-60 Cs-1 37 Cs-1 34 Cs-1 37 Cs-1 34 Cs-137 0.056 0.16 17.10 1.25 4.81 18.60 12.99 3.23 3.86 1.22 0.05 0.15 7.24 5.61 10.96 2.43 3.12 4.25 1.63 4.74 8.53 0.034 +/- 0.04 0.082 +/- 0.11 3.02 +/- 9.04 1.23 +/- 0.79
-1.75 +/- 2.90
-0.64 +/- 0.64 0.033 +/- 0.04
-0.043 +/- 0.11 3.2 200 20 10 100 100 100 100 3.2 1
3.2 10 10 20 10 10 10 10 10 10 a Liquid sample results are reported in pCi/Liter, air filters( pCi/filter), charcoal (pCi/charcoal canister), and solid samples (pCi/g).
b Activity reported is a net activity result. For gamma spectroscopic analysis, activity detected below the LLD value is not reported c 1-131 (G); iodine-1 31 as analyzed by gamma spectroscopy.
d Low levels of Sr-90 are still detected in the environment. A concentration of (1-5 pCi/L) in milk is not unusual.
A4-2
TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)8 Averaged Lab Code Date Analysis First Result Second Result Result Acceptance SW-62, 63 SW-62, 63 CF-95, 96 CF-95, 96 AP-791, 792 WW-353, 354 SO-383, 384 LW-431, 432 MI-486, 487 SW-511, 512 TD-628, 629 DW-538, 539 MI-564, 565 DW-50134, 5 SWU-893, 894 SW-925, 926 SW-950, 951 SW-950, 951 SW-973, 974 DW-50248, 9 DW-1264, 1265 AP-1955, 1956 AP-1 890, 1891 AP-2025, 2026 MI-1346, 1347 AP-2048, 2049 AP-2081, 2082 SWU-1521, 1522 1/3/2005 1/3/2005 1/3/2005 1/3/2005 1/14/2005 1/19/2005 1/19/2005 1/27/2005 2/1/2005 2/1/2005 2/112005 21312005 2/8/2005 2/11/2005 2/22/2005 2/25/2005 3/1/2005 3/1/2005 3/1/2005 3/16/2005 3/19/2005 3/28/2005 3/29/2005 3/29/2005 3/30/2005 3/30/2005 3/30/2005 3/31/2005 Gr. Beta K-40 Gr. Beta K-40 Be-7 Gr. Beta H-3 Gr. Beta K-40 1-131 H-3 Gr. Beta K-40 Gr. Beta Gr. Beta Gr. Beta Gr. Beta Gr. Beta 1-1 31 Gr. Alpha 1-131 Be-7 Be-7 Be-7 K-40 Be-7 Be-7 Gr. Beta 3.01 +/- 0.57 2.00 +/- 0.20 6.26 +/- 0.23 5.68 +/- 0.59 0.057 +/- 0.017 8.37 453.50 2.45 1319.40 0.37 489663 3.93
+/- 1.21
+/- 107.20
+/- 0.54
+/- 163.60
+/- 0.22
+/- 1918
+/- 1.18 1316.20 +/- 171.10 18.41 +/- 0.98 4.00 +/- 0,96 5.97 +/- 1.51 0.92 +/- 0.27 2.06 +/- 0.40 1.08 +/- 0.19 5.27 i 1.06 0.54 +/- 0.21 0.071 +/- 0.009 0.060 +/- 0.013 0.063 +/- 0.012 1252.80 +/- 120.50 0.075 +/- 0.018 0.073 +/- 0.016 2.83 +/- 1.16 2.39 +/- 0.58 2.10 +/- 0.20 6.28 +/- 0.23 5.37 +/- 0.48 0.07 +/- 0.04 10.28 +/- 1.34 417.90 +/- 106.00 2.20 +/- 0.54 1177.20 +/- 179.70 0.44 +/- 0.23 491225 +/- 1915 3.62 +/- 1.10 1292.60 +/- 154.40 16.76 i 0.98 4.20 i 0.72 6.14 +/- 1.55 1.21 +/- 0.27 2.29 +/- 0.44 0.92 +/- 0.18 4.17 +/- 0.90 0.73 +/- 0.20 0.071 +/- 0.009 0.069 +/- 0.013 0.071 +/- 0.011 1334.10 +/- 106.60 0.071 i0.015 0.061 +/- 0.018 3.46 +/- 1.23 2.70 +/- 0.41 2.05 +/- 0.14 6.27 +/- 0.16 5.53 +/- 0.38 0.06 +/- 0.02 9.32 +/- 0.90 435.70 +/- 75.38 2.33 +/- 0.38 1248.30 +/- 121.51 0.40 +/- 0.16 490444 +/- 1355 3.78 +/- 0.81 1304.40 +/- 115.23 17.59 +/- 0.69 4.10 +/- 0.60 6.06 +/- 1.08 1.07 +/- 0.19 2.18 +/- 0.30 1.00 +/- 0.13 4.72 +/- 0.70 0.63 +/- 0.15 0.071 +/- 0.006 0.065 +/- 0.009 0.067 +/- 0.008 1293.45 +/- 80.44 0.073 +/- 0.012 0.067 +/- 0.012 3.14 +/- 0.85 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass WW-1738,1739 SW-1857,1858 LW-1911, 1912 F-1976,1977 Ml-2111, 2112 SWU-2158, 2159 DW-2349, 2350 S0-2305, 2306 SO-2305, 2306 SO-2305, 2306 SO-2305, 2306 SO-2305, 2306 MI-2260, 2261 F-2630, 2631 VE-2502, 2503 4/5/2005 4/13/2005 4/14/2005 4/18/2005 4/26/2005 4/26/2005 4/29/2005 5/2/2005 5/2/2005 5/2/2005 5/2/2005 5/2/2005 5/3/2005 5/5/2005 5/10/2005 Gr. Beta Gr. Beta Gr. Beta K-40 K-40 Gr. Beta 1-131 Cs-1 37 Gr. Alpha Gr. Beta K-40 Sr-90 K-40 K-40 Gr. Alpha 11.44 +/- 1.17 7.04 +/- 1.71 2.50 +/- 0.63 3.09 +/- 0.60 1291.50 +/- 177.90 3.69 +/- 0.74 0.58 +/- 0.27 0.11 +/- 0.05 7.55 +/- 2.88 28.74 +/- 2.57 21.51 +/- 1.22 32.90 +/- 9.90 1028.10 +/- 99.36 3.08 +/- 0.46 0.06 +/- 0.03 11.14 +/- 1.62 9.96 +/- 1.65 3.23 +/- 0.67 3.33 +/- 0.40 1323.70 +/- 108.80 3,54 +/- 0.66 0.49 +/- 0.27 0.11 +/- 0.04 12.41 +/- 3.38 28.17 +/- 2.52 21.42 +/- 1.24 29.60 +/- 13.90 1206.70 +/- 118.50 3.04 +/- 0.51 0.07 +/- 0.04 11.29 +/- 1.00 8.50 +/- 1.19 2.86 +/- 0.46 3.21 +/- 0.36 1307.60 +/- 104.27 3.62 +/- 0.50 0.53 +/- 0.19 0.11 +/- 0.03 9.98 +/- 2.22 28.46 +/- 1.80 21.47 +/- 0.87 31.25 +/- 8.53 1117.40 +/- 77.32 3.06 +/- 0.34 0.07 +/- 0.03 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A5-1
TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance VE-2502, 2503 VE-2502, 2503 G-2546, 2547 G-2546, 2547 SS-2787, 2788 SS-2787, 2788 SO-3056, 3057 SO-3056, 3057 b SS-3175, 3176 SO-2865, 2866 SO-2865, 2866 S0-2865, 2866 DW-2935, 2936 SWU-3103, 3104 G-2958, 2959 G-2958, 2959 b G-2958, 2959 BS-4089, 4090 BS-4089, 4090 DW-50527, 8 VE-3278, 3279 MI-3299, 3300 BS-3348, 3349 BS-3348, 3349 BS-3348, 3349 DW-3486, 3487 SWT-3631, 3632 W-3507, 3508 VE-3555, 3556 VE-3555, 3556 AP-3781, 3782 LW-3610, 3611 SW-3760, 3761 5/10/2005 5/10/2005 5/11/2005 5/11/2005 5/18/2005 5/18/2005 5/19/2005 5/19/2005 5/23/2005 5/25/2005 5/25/2005 5/25/2005 5/27/2005 6/1/2005 6/1/2005 6/1/2005 6/1/2005 6/3/2005 6/3/2005 6/8/2005 6/13/2005 6/15/2005 6/17/2005 6/17/2005 6/17/2005 6/28/2005 6/28/2005 6/29/2005 6/29/2005 6/29/2005 6/29/2005 6/30/2005 6/30/2005 Gr. Beta K-40 Be-7 K-40 Cs-137 K-40 Cs-137 K-40 K-40 Cs-137 Gr. Beta K-40 1-1 31 Gr. Beta Be-7 Gr. Beta K-40 Co-60 Cs-1 37 Gr. Alpha K-40 K-40 Co-60 Cs-1 37 K-40 Gr. Beta Gr. Beta H-3 Gr. Beta K-40 Be-7 Gr. Beta Gr. Beta 3.81 +/- 0.10 3.79 +/- 0.40 0.81 +/- 0.39 9.43 +/- 1.00 0.13 +/- 0.04 12.44 +/- 0.76 0.18 +/- 0.04 20.06 +/- 1.10 6.06 +/- 0.44 0.18 +/- 0.04 32.95 +/- 2.48 21.93 +/- 0.97 0.51 +/- 0.34 3.29 +/- 0.49 1.06 +/- 0.40 8.06 +/- 0.07 5.93 +/- 0.73 0.11 +/- 0.02 0.60 +/- 0.05 11.58 +/- 1.31 6.34 +/- 0.59 1215.40 +/- 110.20 0.20 +/- 0.04 2.59 +/- 0.10 11.57 +/- 0.81 0.97 +/- 0.54 2.12 +/- 0.53 38717 +/- 382 7.53 +/- 0.18 5.70 +/- 0.52 0.09 +/- 0.02 1.37 +/- 0.35 9.70 +/- 1.63 3.86 +/-0.10 4.30 +/- 0.59 1.25 +/- 0.38 7.96 +/- 0.85 0.14 + 0.05 13.33 +/- 0.83 0.17 +/- 0.01 21.73 +/- 0.36 5.96 +/- 0.61 0.18 +/- 0.03 33.88 +/- 2.36 22.32 +/- 0.98 0.56 +/- 0.30 3.75 +/- 0.66 1.21 +/- 0.28 7.79 +/- 0.07 6.05 +/- 0.28 0.10 +/- 0.02 0.62 +/- 0.05 13.52 +/- 1.43 7.29 +/- 0.68 1250.70 +/- 106.70 0.22 +/- 0.04 2.51 +/- 0.07 11.82 +/- 0.76 1.67 +/- 0.58 1.62 +/- 0.56 38017 +/- 535 7.56 +/- 0.18 5.64 +/- 0.53 0.08 +/- 0.02 1.40 +/- 0.36 9,77 +/- 1.61 3.83 +/- 0.07 4.04 +/- 0.36 1.03 +/- 0.27 8.70 +/- 0.66 0.13 +/- 0.03 12.88 +/- 0.56 0.18 +/- 0.02 20.90 +/- 0.58 6.01 +/- 0.38 0.18 +/- 0.02 33.41 +/- 1.71 22.13 +/- 0.69 0.53 +/- 0.23 3.52 +/- 0.41 1.14 +/- 0.24 7.93 +/- 0.05 5.99 +/- 0.39 0.11 +/- 0.02 0.61 +/- 0.04 12.55 +/- 0.97 6.81 +/- 0.45 1233.05 i 76.70 0.21 +/- 0.03 2.55 +/- 0.06 11.69 i 0.56 1.32 i 0.40 1.87 +/- 0.39 38367 +/- 329 7.55 +/- 0.13 5.67 +/- 0.37 0.09 +/- 0.01 1.39 +/- 0.25 9.73 +/- 1.15 Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass E-3654, 3655 E-3654, 3655 MI-3676, 3677 DW-3739, 3740 W-3808,3809 DW-3938, 3939 VE-3896, 3897 MI-3963, 3964 DW-4068, 4069 7/5/2005 7/5/2005 7/5/2005 715/2005 7/6/2005 7/812005 7/12/2005 7/13/2005 7/15/2005 Gr. Beta K-40 K-40 1-131 H-3 1-131 K-40 K-40 1-131 1.76 +/- 0.07 1.49 +/- 0.25 1383.90 +/- 116.20 1.93 +/- 0.24 4189.61 +/- 196.68 1.11 +/- 0.30 3.44 +/- 0.62 1438.70 +/- 102.80 0.64 +/- 0.27 1.69 1.05 1428.20 2.18 4438.33 1.26 3.60 1351.80 0.91
+/- 0.07
+/- 0.21
+/- 125.40
+/- 0.23
+/- 201.39
+/- 0.31
+/- 0.36
+/- 100.80
+/- 0.28 1.72 +/- 0.05 1.27 +/- 0.16 1406.05 +/- 85.48 2.05 +/- 0.17 4313.97 +/- 140.75 1.18 +/- 0.22 3.52 +/- 0.36 1395.25 +/- 71.99 0.78 +/- 0.20 Pass Pass Pass Pass Pass Pass Pass Pass Pass A5-2
TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance VE-4290, 4291 VE-4290, 4291 SWU-4311, 4312 SWU-4311, 4312 G-4383, 4384 G-4383, 4384 G-4383,4384 MI-4425,4426 TD-4446, 4447 SL-4473, 4474 SL-4473, 4474 VE-4532, 4533 VE-4618, 4619 VE-4618, 4619 VE-4618, 4619 F-4639, 4640 F-4639, 4640 F-4639, 4640 DW-4730, 4731 Ml-485S, 4856 MI-4855, 4856 MI-4945, 4946 MI-4945, 4946 TD4921, 4922 VE-4900, 4901 VE-4900, 4901 7/26/2005 7/26/2005 7/26/2005 7/26/2005 8/1/2005 8/1/2005 8/1/2005 8/1/2005 8/1/2005 8/4/2005 8/4/2005 8/5/2005 8/9/2005 8/9/2005 8/9/2005 8/11/2005 8/11/2005 8/11/2005 8/12/2005 8/28/2005 8/28/2005 8/31/2005 8/31/2005 9/1/2005 9/2/2005 9/2/2005 Gr. Alpha Gr. Beta Gr. Beta H-3 Be-7 Gr. Beta K-40 K-40 H-3 Gr. Beta K-40 Gr. Beta Gr. Alpha Gr. Beta K-40 Cs-137 Gr. Beta K-40 1-131 K-40 Sr-90 K-40 Sr-90 H-3 Gr. Beta K-40 Gr. Alpha K-40 K-40 Gr. Alpha Gr. Beta K-40 Gr. Beta 1-131 Gr. Beta 1-131 Be-7 K-40 K40 Be-7 Cs-1 37 0.11 +/- 0.04 4.55 +/- 0.13 2.62 +/- 0.64 192.30 +/- 92.90 2.06 +/- 0.49 8.76 +/- 0.22 6.74 +/- 0,64 1358.10 +/- 169.20 563.00 +/- 252.00 5.44 +/- 0.48 2.91 +/- 0.83 31.20 +/- 1.20 0.09 +/- 0.05 4.60 +/- 0.13 4.19 +/- 0.46 0.05 +/- 0.02 3.33 +/- 0.11 2.62 +/- 0.57 0.82 i 0.23 1341.50 i 107.70 0.77 i 0.37 1388.90 i 158.90 0.67 +/- 0.34 5737.00 +/- 266.00 3.40 +/- 0.06 2.15 +/-0.27 6.17 +/- 1.42 18.81 +/- 1.12 1584.00 +/- 194.00 0.10 +/- 0.06 6.05 +/- 0.18 4.61 +/- 0.46 1.09 +/- 0.33 0.44 +/- 0.22 2.92 +/- 0.56 0.45 +/- 0.27 0.91 +/- 0.40 1.43 +/- 0.34 1228.80 +/- 78.13 1286.10 +/- 550.80 726.97 +/- 76.24 0.05 +/- 0.03 4.69 +/- 0.14 1.67 +/- 0.37 304,60 +/- 97.40 1.76 +/- 0.29 8.40 +/- 0.20 6.88 +/- 0.92 1267.90 +/- 164.40 529.00 +/- 251.00 4.57 +/- 0.42 2.74 +/- 0.54 31.70 +/- 1.20 0.09 +/- 0.04 4.54 +/- 0.12 4.34 +/- 0.47 0,05 +/- 0.02 3.37 +/- 0.10 2.58 +/- 0.59 0.83 +/- 0.25 1340.00 +/- 114.70 0.87 +/- 0.37 1307.50 +/- 165.20 0.82 +/- 0.36 5860.00 +/- 269.00 3.51 +/- 0.06 2.27 +/- 0.24 6.08 +/- 1.46 19.52 +/- 0.86 1707.60 +/- 173.00 0.09 +/- 0.05 5.92 +/- 0.17 4.74 +/- 0.69 1.18 +/- 0,34 0.31 +/- 0.20 2.95 +/- 0.59 0.55 +/- 0.29 0.64 +/- 0.30 1.38 +/- 0.43 1297.00 +/- 81.03 1222.90 +/- 394.40 677.49 +/- 70.03 0.08 +/- 0.03 4.62 +/- 0.09 2.15 +/- 0.37 248.45 +/- 67.30 1.91 +/- 0.28 8.58 +/- 0.15 6.81 +/- 0.56 1313.00 +/- 117.96 546.00 +/- 177.84 5.00 +/- 0.32 2.82 +/- 0.49 31.45 +/- 0.85 0.09 +/- 0.03 4.57 +/- 0.09 4.27 +/- 0.33 0.05 +/- 0.02 3.35 +/- 0.07 2.60 +/- 0.41 0.83 +/- 0.17 1340.75 +/- 78.67 0.82 +/- 0.26 1348.20 +/- 114.61 0.75 +/- 0.25 5798.50 +/- 189.15 3.45 +/- 0.04 2.21 +/- 0.18 6.13 +/- 1.02 19.17 +/- 0.71 1645.80 +/- 129.97 0.10 +/- 0.04 5.98 +/- 0.12 4.68 +/- 0.41 1.13 +/- 0.24 0.38 +/- 0.15 2.93 +/- 0.41 0.50 +/- 0.20 0.78 +/- 0.25 1.41 +/- 0.27 1262.90 +/- 56.28 1254.50 +/- 338.72 702.23 +/- 51.76 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass DW-50769, 50770 9/2/2005 VE-4990, 4991 MI-5011, 5012 VE-5119, 5120 VE-5119, 5120 VE-5119, 5120 LW-5361, 5362 SW-5098, 5099 LW-5178, 5179 DW-5239, 5240 CF-5432, 5433 CF-5432, 5433 MI-5292, 5293 BS-5340, 5341 BS-5340, 5341 9/6/2005 9/8/2005 9/12/2005 9/12/2005 9/12/2005 9/12/2005 9/13/2005 9/14/2005 9/16/2005 9/19/2005 9/19/2005 9/21/2005 9/23/2005 9/23/2005 A5-3
TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance BS-5340, 5341 DW-5382, 5383 MI-5405, 5406 AP-5769, 5770 AP-5983, 5984 AP-5878, 5879 9/23/2005 9/2312005 9/27/2005 9/27/2005 9/27/2005 9/29/2005 K-40 1-131 K-40 Be-7 Be-7 Be-7 12404 0.79 1324.80 0.08 0.08 0.06
+/- 1154
+/- 0.31
+/- 112.20
+/- 0.01
+/- 0.01
+/- 0.01 13033 +/- 983 0.53 +/- 0.31 1366.80 +/- 99.44 0.09 +/- 0.02 0.08 +/- 0.01 0.07 +/- 0.01 12719 +/- 758 0.66 +/- 0.22 1345.80 +/- 74.96 0.08 +/- 0.01 0.08 +/- 0.01 0.07 +/- 0.01 Pass Pass Pass Pass Pass Pass G-5526, 5527 G-5526, 5527 G-5526, 5527 VE-5721, 5722 VE-5721, 5722 VE-5721, 5722 CF-5695, 5696 CF-5695, 5696 LW-6129, 6130 LW-6129, 6130 DW-50844, 5 LW-5748, 5749 AP-6485, 6486 SWU-6156, 6157 VE-6186, 6187 LW-6203, 6204 SO-6270, 6271 SO-6270, 6271 SO-6270, 6271 TD-6320, 6321 SO-6605, 6606 CF-6509, 6510 SW-6638, 6639 SO-6887, 6888 SO-6887, 6888 SO-6887, 6888 SWT-6721, 6722 VE-6775, 6776 LW-6743, 6744 DW-51023, 4 SWT-7282, 7283 10/3/2005 10/3/2005 10/3/2005 10/10/2005 10/10/2005 10/10/2005 10/11/2005 10/11/2005 10/11/2005 10/11/2005 10/11/2005 10/12/2005 10/20/2005 10/25/2005 10/26/2005 10/27/2005 10/28/2005 10/2812005 10/28/2005 11/1/2005 11/11/2005 11/14/2005 11/22/2005 11/22/2005 11/22/2005 11/22/2005 11/29/2005 11/29/2005 11/30/2005 12/2/2005 12/27/2005 Be-7 Gr. Beta K-40 Gr. Alpha Gr. Beta K-40 Be-7 K-40 Gr. Beta H-3 Gr. Beta Gr. Beta Be-7 Gr. Beta K-40 Gr. Beta Cs-1 37 Gr. Beta K-40 H-3 Gr. Beta K-40 1-131 Gr. Alpha Gr. Beta K-40 Gr. Beta Gr. Beta Gr. Beta Gr. Alpha Gr. Beta 4.03 +/- 0.62 8.10 +/- 0.30 4.93 +/- 0.67 0.07 + 0.05 5.09 +/- 0.15 4.27 + 0.43 2.70 + 0.37 11.79 +/- 0.86 1.34 +/- 0.25 304.35 +/- 95.31 5.30 +/- 1.50 1.09 +/- 0.25 0.10 +/- 0.03 4.69 +/- 1.34 2.90 +/- 0.49 2.92 +/- 0.62 0.33 +/- 0.03 26.85 +/- 2.78 13.67 +/- 0.74 444202 +/- 1770 18.22 +/- 2.23 0.85 +/- 0.14 0.95 +/- 0.35 6.80 +/- 2.92 19.27 +/-2.16 14.29 1.11 0.98 i 0.31 12.75 i 0.28 3.19 i 0.47 0.55 i 1.40 1.62 +/- 0.37 4.07 +/- 0.80 8.80 +/- 0.40 6.00 +/- 0.72 0.08 +/- 0.06 5.00 +/- 0.16 4.20 +/- 0.34 2.80 +/- 0.34 13.11 +/- 0.68 1.85 +/- 0.29 369.23 +/- 97.88 4.20 +/- 1.40 1.89 +/- 0.28 0.09 +/- 0.03 4.18 +/- 1.34 2.83 +/- 0.51 3.09 +/- 0.66 0.34 +/- 0.04 22.25 +/- 2.41 14.02 +/- 0.76 446633 +/- 1775 18.47 +/- 2.22 0.99 +/- 0.22 0.67 +/- 0.31 10.27 +/- 3.26 18.43 +/- 2.21 13.78 +/- 0.78 0.87 +/- 0.31 13.16 +/- 0.21 2,50 +/- 0.44 2.21 +/- 1.31 1.85 +/- 0.38 4.05 +/- 0.51 8.41 +/- 0.24 5.47 +/- 0.49 0.08 +/- 0.04 5.05 +/-0.11 4.23 +/- 0.27 2.75 +/- 0.25 12.45 +/- 0.55 1.59 +/- 0.19 336.79 +/- 68.31 4.75 +/- 1.03 1.49 +/- 0.19 0.09 +/- 0.02 4.44 +/- 0.95 2.87 +/- 0.35 3.01 +/- 0.45 0.33 +/- 0.03 24.55 +/- 1.84 13.85 +/- 0.53 445418 +/- 1253 18.35 +/- 1.57 0.92 +/- 0.13 0.81 +/- 0.23 8.53 +/- 2.19 18.85 +/- 1.54 14.03 +/- 0.68 0.93 +/- 0.22 12.96 +/- 0.18 2.85 +/- 0.32 1.38 +/- 0.96 1.74 +/- 0.27 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Note: Duplicate analyses are performed on every twentieth sample received in-house.
analyses with activities that measure below the LLD.
Results are not listed for those a Results are reported in units of pCi/L, except for air filters (pCi/Filter), food products, vegetation, soil, sediment (pCi/g).
b 600 minute count time or longer, resulting in lower error.
c Recount of W-5748, 2.38 +/- 0.85 pCi/L Averaged result; 2.14 +/- 0.45 pCi/L A5-4
TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)a.
Concentration b Known Control Lab Codec Date Analysis Laboratory result Activity Limits d Acceptance STW-1 045 01/01/05 Gr. Alpha STW-1 045 01/01/05 Gr. Beta 0.45 +/- 0.10 1.90 +/- 0.10 0.53 1.67 0.00 - 1.05 0.84 - 2.51 Pass Pass STW-1046 STW-1 046 STW-1 046 STW-1 046 STW-1 046 STW-1 046 STW-1046 STW-I 046 STW-1046 STW-1 046 STW-1 046 STW-1 046 STW-1046 STW-1 046 STW-1 046 STW-1 046 STVE-1 047 STVE-1 047 STVE-1 047 STVE-1 047 STVE-1 047 STVE-1 047 STSO-1 048 STSO-1048 STSO-1048 STSO-1048 STSO-1048 STSO-1048 STSO-1048 STSO-1048 STSO-1048 STSO-1048 STSO-1 048 STSO-1 048 STSO-1 048 STSO-1 048 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01101/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01105 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 Am-241 Co-57 Co-60 Cs-134 Cs-137 Fe-55 H-3 Mn-54 Ni-63 Pu-238 Pu-239/40 Sr-90 Tc-99 U-23314 U-238 Zn-65 Co-57 Co-60 Cs-1 34 Cs-1 37 Mn-54 Zn-65 Am-241 Co-57 Co-60 Cs-134 Cs-1 37 K-40 Mn-54 Ni-63 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Zn-65 1.62 +/- 0.12 239.40 +/- 1.20 248.70 +/- 1.00 115.50 +/- 1.80 328.50 +/- 1.70 64.90 +/- 7.00 304.00 +/- 9.70 334.80 +/- 1.90 7.10 +/- 1,60 0.01 +/- 0.02 2.50 +/- 0.14 0.70 +/- 0.80 43.20 +/- 1.40 3.31 +/- 0.20 3.38 +/- 0.20 538.40 +/- 3.80 10.60 +/- 0.20 3.00 +/- 0.20 4.80 +/- 0.40 4.10 +/- 0.30 5.10 +/- 0.30 6.20 +/- 0.50 96.60 +/- 10.00 264.00 +/- 2.00 226.50 +/- 2.20 760.60 +/- 3.70 336.20 +/- 3.60 663.70 +/- 18.00 541.30 +/- 3.90 924.30 +/- 17.20 0.60 +/- 0.80 78.00 +/- 4.80 514.60 +/- 18.70 47.90 +/- 4.00 226.30 +/- 8.60 851.30 +/- 7.30 1.72 227.00 251.00 127.00 332.00 75.90 280.00 331.00 9.00 0.02 2.40 0.00 42.90 3.24 3.33 496.00 9.88 3.15 5.00 4.11 5.18 6.29 109.00 242.00 212.00 759.00 315.00 604.00 485.00 1220.00 0.48 89.50 640.00 62.50 249.00 810.00 1.20 - 2.24 158.90 - 295.10 175.70 - 326.30 88.90 - 165.10 232.40 - 431.60 53.13 - 98.67 196.00 - 364.00 231.70 - 430.30 0.00 - 20.00 0.00 - 1.00 1.68 - 3.12 0.00 - 5.00 30.03 - 55.77 2.27 - 4.21 2.33 - 4.33 347.20 - 644.80 6.92 - 12.84 2.21 - 4.10 3.50 - 6.50 2.88 - 5.34 3.63 - 6.73 4.40 - 8.18 76.30 - 141.70 169.40 - 314.60 148.40 - 275.60 531.30 - 986.70 220.50 - 409.50 422.80 - 785.20 339.50 - 630.50 854.00 - 1586.00 0.00 - 1.00 62.65 - 116.35 448.00 - 832.00 43.75 - 81.25 174.30 - 323.70 567.00 - 1053.00 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass STAP-1050 01/01/05 Gr. Alpha STAP-1050 01/01/05 Gr. Beta 0.11 +/- 0.03 0.38 +/- 0.05 0.23 0.30 0.00 - 0.46 0.15 - 0.45 Pass Pass A6-1
TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)r.
Concentration b Known Control Lab Codec Date Analysis Laboratory result Activity Limits d Acceptance STAP-1 049 STAP-1 049 STAP-1 049 STAP-1 049 STAP-1 049 STAP-1 049 STAP-1 049 STAP-1 049 STAP-1 049 e STAP-1 049 STAP-1 049 STAP-1 049 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 01/01/05 Am-241 Co-57 Co-60 Cs-1 34 Cs-1 37 Mn-54 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Zn-65 0.10 +/- 0.04 4.76 +/- 0.64 2.84 +/- 0.22 3.54 +/- 0.37 2.20 +/- 0.27 3.15 +/- 0.21 0.16 +/- 0.04 0.17 +/-0.02 2.24 +/- 0.34 0.34 +/- 0.02 0.35 +/- 0.02 3.12 +/- 0.15 0.10 4.92 3.03 3.51 2.26 3.33 0.20 0.17 1.35 0.34 0.35 3.14 0.07 - 0.13 3.44 - 6.40 2.12 - 3.94 2.46 - 4.56 1.58 - 2.94 2.33 - 4.33 0.14 - 0.25 0.14 - 0.25 0.95 - 1.76 0.24 - 0.44 0.25 - 0.46 2.20 - 4.08 Pass Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass STW-1061 STW-1061 STW-1 061 STW-1061 STW-1 061 STW-1 061 STW-1 061 STW-1 061 STW-1 061 STW-1 061 STW-1061 STW-1061 STW-1 061 STW-1 061 STW-1 061 STW-1 061 STW-1 062 STW-1 062 STSO-1 063 STSO-1 063 STSO-1 063 STSO-1 063 STSO-1 063 STSO-1 063 STSO-1 063 STSO-1 063 STSO-1 063 STSO-1 063 STSO-1 063 STSO-1 063 STSO-1 063 STSO-1 063 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/0 1/05 07/01/05 07/01/05 07/01/05 07/0 1/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/0 1/05 07/01/05 07/01/05 Am-241 Co-57 Co-60 Cs-1 34 Cs-1 37 Fe-55 H-3 Mn-54 Ni-63 Pu-238 Pu -239/40 Sr-90 Tc-99 U-233/4 U-238 Zn-65 Gr. Alpha Gr. Beta Am-241 Co-57 Co-60 Cs-134 Cs-1 37 K-40 Mn-54 Ni-63 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Zn-65 2.21 +/- 0.13 293.20 +/- 7.30 275.70 +/- 1.30 171.80 +/- 4.00 342.10 +/- 2.20 167.80 +/- 9.30 514.20 +/- 12.60 437.00 +/- 2.50 105.10 +/- 3.60 1.64 +/- 0.12 2.32 +/- 0.13 9.20 +/- 1.30 72.30 +/- 2.30 4.11 +/- 0.18 4.14 +/- 0.18 364.60 +/- 4.90 0.57 +/- 0.05 1.36 +/- 0.05 48.40 +/- 3.90 608.30 +/- 2.80 322.70 +/- 2.40 632.10 +/- 5.20 512.40 +/- 4.20 720.50 +/- 19.00 516.80 +/- 5.10 366.50 +/- 13.30 68.80 +/- 15.00 0.00 +/- 0.00 602.90 +/- 17.20 61.50 +/- 1.00 164.50 +/- 16.70 874.70 +/- 8.40 2.23 272.00 261.00 167.00 333.00 196.00 527.00 418.00 100.00 1.91 2.75 8.98 66.50 4.10 4.26 330.00 0.79 1.35 81.10 524.00 287.00 568.00 439.00 604.00 439.00 445.00 60.80 0.00 757.00 52.50 168.00 823.00 1.56 - 2.90 190.40 - 353.60 182.70 - 339.30 116.90 - 217.10 233.10 - 432.90 137.20 - 254.80 368.90 - 685.10 292.60 - 543.40 70.00 - 130.00 1.34 - 2.48 1.93 - 3.58 6.29 - 11.67 46.55 - 86.45 2.87 - 5.33 2.98 - 5.54 231.00 - 429.00 0.21 - 1.38 0.85 - 1.92 56.77 - 105.43 366.80 - 681.20 200.90 - 373.10 397.60 - 738.40 307.30 - 570.70 422.80 - 785.20 307.30 - 570.70 311.50 - 578.50 42.56 - 79.04 0.00 - 0.00 529.90 - 984.10 36.75 - 68.25 117.60 - 218.40 576.10 - 1070.00 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A6-2
TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)a.
Concentration b Known Control Lab Codec Date Analysis Laboratory result Activity Limits d Acceptance STVE-1064 STVE-1064 STVE-1064 STVE-1064 STVE-1064 STVE-1064 STVE-1064 STVE-1 064 STVE-1064 STVE-1064 STVE-1 064 STVE-1 064 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07101/05 Am-241 Co-57 Co-60 Cs-1 34 Cs-1 37 Mn-54 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Zn-65 STAP-1 065 07/01/05 Gr, Alpha STAP-1 065 07/01/05 Gr. Beta 0.18 +/- 0.03 15.90 +/- 0,20 4.80 +/- 0.10 4.60 +/- 0.20 5.90 +/- 0.30 7.20 +/- 0.20 0.04 +/- 0.02 0.13 +/- 0.02 2.80 +/- 0.30 0.28 +/- 0.03 0.33 +/- 0.04 11.00 +/- 0.50 0.30 +/- 0.04 0.97 +/- 0.06 0.14 +/- 0.03 5.81 +/- 0.17 2.79 +/- 0.14 3.67 +/- 0.12 2.93 +/- 0.23 4.11 +/- 0.26 0.11 +/- 0.02 0.10 +/- 0.01 2.25 +/- 0.29 0.28 +/- 0.02 0.28 +/- 0.02 4.11 +/- 0.26 0.23 13.30 4.43 4.09 5.43 6.57 0.00 0.16 2.42 0.33 0.35 10.20 0.48 0.83 0.16 6.20 2.85 3.85 3.23 4.37 0.10 0.09 2.25 0.27 0.28 4.33 0.16 - 0.30 9.31 - 17.29 3.10 -5.76 2.86 - 5.32 3.80 - 7.06 4.60 - 8.54 0.00 - 1.00 0.11 -0.21 1.69 -3.15 0.23 - 0.43 0.24 - 0.45 7.14 -13.26 0.00 - 0.80 0.55 - 1.22 0.11 - 0.21 4.34 - 8.06 2.00 - 3.71 2.70 - 5.01 2.26 - 4.20 3.06 - 5.68 0.07 - 0.13 0.06 - 0.12 1.58 - 2.93 0.19 - 0.35 0.20 - 0.37 3.06 - 5.68 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass STAP-1 066 STAP-1 066 STAP-1 066 STAP-1 066 STAP-1 066 STAP-1 066 STAP-1 066 STAP-1066 STAP-1 066 STAP-1 066 STAP-1066 STAP-1 066 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 07/01/05 Am-241 Co-57 Co-60 Cs-1 34 Cs-1 37 Mn-54 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Zn-65 a 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 bResults are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation) as requested by the Department of Energy.
c Laboratory codes as follows: STW (water), STAP (air filter), STSO (soil), STVE (vegetation).
c MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and control limits as defined by the MAPEP.
@ The strontium carbonate precipitates were redissolved and processed. The average of the three analyses was 1.34 1 although the recovery was only 30%. The result of a new analysis was 1.56 pCi/L.
Incorrect sample weight used in calculation. Result of recalculation: 97.0 +/- 7.8 Bq/kg.
A6-3
APPENDIX B DATA REPORTING CONVENTIONS B-1
Data Reporting Conventions 1.0. All activities, except gross alpha and gross beta, are decay corrected to collection time or the end of the collection period.
2.0. Single Measurements Each single measurement is reported as follows:
x +/- s where:
x = value of the measurement; s = 2a counting uncertainty (corresponding to the 95% confidence level).
In cases where the activity is less than the lower limit of detection L, it is reported as: < L, where L = the lower limit of detection based on 4.66a uncertainty for a background sample.
3.0. Duplicate analyses 3.1 Individual results:
For two analysis results; x1 +/-s1 and x2 s+/-
2 Reported result:
x +/- s; where x = (1/2) (x + x2) and s = (1/2)
+S 3.2.
Individual results:
< L,. < L2 Reported result: < L, where L = lower of Li and L2 3.3.
Individual results:
x +/- s, < L Reported result:
x +/- s if x 2 L; <L otherwise.
4.0. Computation of Averages and Standard Deviations 4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements over the period averaged; for example, an annual standard deviation would not be the average of quarterly standard deviations. The average x and standard deviation s of a set of n numbers xi, x2... x are defined as follows:
x YnEx s=
nT X8 n-i 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-I
Table C-1.
Maximum permissible concentrations of radioactivity in air and water above natural a
background in unrestricted areas Air (pCi/m3)
Water (pCi/L)
Gross alpha Gross beta b
Iodine-i131
-3 1 x 10 1
2.8 x 101 Strontium-89 Strontium-90 Cesium-1 37 Barium-1 40 Iodine-1 31 Potassium-40 Gross alpha Gross beta Tritium 8,000 500 1,000 8,000 1,000 4,000 2
1 0 6
1 x 10 a
Taken from Table 2 of Appendix B to Code of Federal Regulations Title 10, Part 20, and appropriate footnotes.
b Concentrations may be averaged over a period not greater than one year.
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
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