L-MT-05-041, 2004 Annual Radiological Environmental Operating Report
| ML051250473 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 04/29/2005 |
| From: | Thomas J. Palmisano Nuclear Management Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| FOIA/PA-2010-0209, L-MT-05-041 | |
| Download: ML051250473 (60) | |
Text
I4 A.
No Committed to Nuclear Excels April 29, 2005 Monticello Nuclear Generating Plant Operated by Nuclear Management Company, LLC L-MT-05-041 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 2004 Annual Radiological Environmental Operating 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 2004.
This letter contains no new NRC commitments, nor does it modify any prior commitments.
Thomas J. Palmisano Site Vice President, Monticello Nuclear Generating Plant Nuclear Management Company, LLC Enclosure cc:
Administrator, Region IlIl, USNRC Project Manager, Monticello, USNRC Resident Inspector, Monticello, USNRC Minnesota Department of Commerce 2807 West County Road 75
- Monticello, Minnesota 55362-9637 Telephone: 763-295-5151 a Fax: 763-295-1454 JF
- Ii I
ENCLOSURE 1 ANNUAL REPORT TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION, RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM, JANUARY 1 TO DECEMBER 31,2004 58 pages follow
II to Environmental, Inc.
Midwest Laboratory an Allegheny Technobgles Co.
700 Landwehr Road
- NHtibrook IL 60062-2310 ph. (847) 564-0700
- tax (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 I to December 31, 2004 Prepared under Contract by ENVIRONMENTAL, Inc.
Midwest Laboratory Project No. 8010 iBroia ro, M.S.
a rato anager Approved:
J PREFACE The staff of Environmental, Inc., Midwest Laboratory was responsible for the acquisition of data presented in this report. Samples were collected by personnel of the Monticello Nuclear Generating Plant, operated by Nuclear Management Company, LLC for XCEL Energy Corporation. This report was prepared by Environmental, Inc., Midwest Laboratory.
ii
r TABLE OF CONTENTS No.
1.0 2.0 3.0 4.0 5.0 6.0 APPENDICES Page Preface...........
ii List of Tables
.Iv List of Figures..
v INTRODUCTION
.I
SUMMARY
.2 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 RESULTS AND DISCUSSION...................
7 4.1
- Atmospheric Nuclear Detonations and Nuclear Accidents
.7 4.2 Summary of Preoperational Data............................
7:
7 4.3 Program Findings...................
.8 FIGURES AND TABLES.12 REFERENCES.24 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 Hii
7 I
a No.
5.1 5.2 5.3 5.4 LIST OF TABLES Title Page 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:
Appendix A A-1 Interlaboratory Comparison Program Results.......................................... Al-1 A-2 Thermoluminescent dosimeters (TLDs)...............................
A2-1 A-3 In-house Spiked Samples...............................
A3-1 A-4 In-house "Blank" Samples..
............................. 4-1 A-5 In-house "Duplicate" Samples...............................
A5-1 A-6 Department of Energy MAPEP comparison results......
....................... A6-1 A-7 Environmental Measurements Laboratory Quality (EML) Assessment Program comparison results.
A7-1 Attachment A: Acceptance criteria for spiked samples.A2 Appendix C C-1 Maximum Permissible Concentrations of Radioactivity in air and water above background in unrestricted areas.C-2 iv
A LIST OF FIGURES No.
Title Paae 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 Appendix 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...............
0:
D-3 D-3 Sample collection and analysis program: TLD 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
iA
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 Nuc'lear Generating Plant, Monticello, Minnesota, during the period January - December, 2004.
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, 2005a) 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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i 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 2004 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-1 37 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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Program Design 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-1 31. 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 DIQ 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-1 31. 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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i Program Description (continued)
Drinking water is collected weekly from the City of Minneapolis water supply, which is taken from the Mississippi Rivbr downstream of the Plant. Monthly composites are analyzed for gross beta, iodine-131, and gari'ma-emitting isotopes. Quarterly composites are analyzed for tritium.
The aquatic environment is also monitored by semi-annual upstream and downstream collections of fish, invertebrates, and shoreline sediments.
Shoreline sediment is also collected semi-annually from one downstream recreational location. All samples are analyzed for gamma-emitting isotopes.
3.3 Program Execution The Program was executed as described in the preceding section with the following exceptions:
(1)
Surface water samples could not be collected from M-08 (upstream) for the weeks ending 02-04-04 through 02-18-04 and weeks ending 12-21-04 and 12-29-04. The shoreline was frozen.
(2)
Milk samples were not available from M-28 (Hoglund Farm) June 30th through October 6th, 2004. Dairy operations were temporarily discontinued. Collections were resumed on 10-20-04.
(3)
No air particulate I air iodine sample was available from location M-1 for the week ending 07-14-04. Power was interrupted due to an open fuse.
(4)
TLD data was not available from location M-06B for the third quarter, 2004. The TLD was missing in the field.
(5)
No air particulate / air iodine sample was available from location M-1 for the week ending 11-17-04. No power was available to the sampler.
(6)
No air particulate / air iodine sample was available from location M-2 for the week ending 12-15-04. Power was interrupted due to an open fuse.
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.
Gammna-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 control/quality assurance program designed to assure the reliability of data obtained.
Details of the QA Program are presented elsewhere (Environmental, Inc., Midwest Laboratory, 2003 ). The QA Program includes participation in Interlaboratory Comparison (crosscheck) Programs.
Results obtained in the crosscheck programs are presented in Appendix A.
3.5 Program Modifications There were no new program modifications in 2004.
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 2004 land use census was conducted between August 23 and September 3, 2004.
Increased D/Q values by sector (> 20%) were calculated for four nearest garden and one nearest resident. These changes resulted in identifying a different location for the nearest garden (Wise, 0.64 mi. SSW) in 2004.
Milk animal locations remained unchanged. The highest D/Q locations for nearest residence and nearest milk animal did not change from the 2003 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 5.4 in a format recommended by the Nuclear Regulatory Commission in Regdlatory 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 2004. The last reported test was made by the People's Republic of China on October 16,1980.
4.2 Summary of Preoperational Data The following constitutes a summary of preoperational studies conducted at the Monticello Nuclear Generating Plant during the years 1968 to 1970, to determine background levels expected In the environment, and provided, where applicable, as a means for comparison with present day levels. Strict comparisons, however, are difficult to make, since background levels of radiation were much higher in these years due to radioactive fallout from the atmosphere. Gross beta measurements in fallout averaged 20,600 pC/m n In 1969 and 12,000 pCi/im 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 33 pCVm. Present day levels have stabilized at around 0.025 pCVMi. Airborne radioiodine remained below detection levels.
In the terrestrial environment of 1968 to 1970, milk, agricultural crops, and soil were monitored. In milk samples, low levels of Cs-137 and Sr-90 were detected. Cs-137 levels averaged 16.7 pCi/L.
Soybean crop measurements in 1969 averaged 35.5 pCi/g for gross beta and 0.3 pCilg 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 pCVL.
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 pCilg 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 pCVg in 1968 and 1969. Cs-137, measured in 1969 and 1970, averaged 0.044 pClg. 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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A -
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 (16.0 and 15.4 mRem/91 days, respectively). The mean for special locations was 15.1 mRem/91 days. The mean for control locations was 15.4 mRem/91 days. Dose rates measured at the inner and outer ring locations were similar to those observed from 1989 through 2003 and are tabulated below. No plant effect on ambient gamma radiation is indicated (Figure 5-1).
Year Inner Ring Outer Rin Dose rate (mRem/91 days) 1989 15.0 15.4 1990 16.1 16.2 1991 15.2 15.8 1992 15.1 15.1 1993 15.6 15.9 1994 14.6 14.0 1995 14.4 13.6 1996 14.0 13.5 1997 13.3 12.8 1998 15.0 14.4 1999 15.1 14.3 2000 15.1 14.5 2001 14.3 13.7 2002 15.9 14.8 2003 15.6 15.0 2004 16.0 15.4
.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 and control locations (0.024 pCilm ) and were similar to levels observed from 1989 through 2003.
The results are tabulated below.
Year l
Indicators l
Control Concentration (pCi/i )
1989 0.027 0.026 1990 0.023 0.023 1991 0.024 0.024 1992 0.023 0.023 1993 0.024 0.023 1994 0.023 0.024 1995 0.024 0.025 1996 0.023 0.023 1997 0.023 0.023 1998 0.023 0.023 1999 0.023 0.025 2000 0.027 0.026 2001 0.027 0.026 2002 0.028 0.028 2003 0.027 0.027 2004 0.024 0.024 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 1989 through 2004.
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., 2004b).
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 (Amold and Al-Salih, 1955) was detected in all samples, with an average activity of 0.057 pCim 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 0.07 pCiM 3 in all samples.
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Milk lodine-131 activity measured below the detection limit of 1.0 pCUL in all samples. Cesium-137 results were below the LLD level of 15 pCUL in all samples.
No other gamma-emitting isotopes except naturally-occurring potassium-40, were detected in milk samples. This is consistent with the finding of the National Center for Radiological Health (1968) that most radiocontaminants in feed do not find their way Into milk due to the selective metabolism of the cow. The common exceptions are radioisotopes of potassium, cesium, strontium, barium, and iodine.
In summary, the milk data for 2004 show no radiological effects of the plant operation.
River Water and Drinking Water Tritium activity measured below the LLD of 330 pCi/L In all samples. Gross beta activity In Minneapolis drinking water averaged 2.7 pCi/L and was similar to average levels observed from
,1989 through 2003. Gross beta averages are tabulated below.
Year Gross Beta I (pCiJL) 1989 2.6 1990 2.2 1991 2.9 1992 2.1 1993 2.6 1994 2.0 1995 2.3 1996 X
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 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 330 pCi/L in all samples. All gamma isotopic results were below detection limits. There was no indication of a plant effect.
Crops Cabbage and broccoli were collected In September from three locations and analyzed for iodine-131. Levels of 1-131 measured below 0.009 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 2004; therefore, no corn or potato samples were collected for analysis from irrigated fields.
Fish Fish samples were collected in May and October. Flesh was separated from the bones and gamma-scanned. Naturally-occurring potassium-40 was found to be similar in upstream and downstream samples (2.59 and 2.73 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. With the exception of naturally-occurring potassium-40, 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 the downstream samples, averaging 0.099 pCig dry weight, and less than 0.027 pCig dry weight In the 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-14A M-01B - M-16B M-01S - M-06S M-OIC - M-04C 5
M-1 (C), M-2, M-3, M4, M-5 CIQ Ambient gamma CAN GB, GS (QC of each location)
Airborne Iodine 5
M-1 (C), M-2, M-3, M4, M-5 C/W 1-131 1-131, GS Milk 3
M-10 (C), M-24, M-28 GIMd Surface water 2
Drinking water I
M-14 G/W GB(MC), 1-131(MC)
Well water 4
M-10(C), M-11, M-12, M-27 Edible cultivated crops -
Corn' Leafy Vegetable Potatoes' Fish (one species, edible portion)
I M-19 2
M-27, St. Cloud Farmer's Mkt. (C)
I M-21 2
M-8(C), M-9 GIQ GIA GIA GIA H-3, GS GS 1-131 GS GS GISA Periphyton or invertebrates Shoreline sediment 2
M-8(C), M-9 3
M-8(C), M-9, M-15 GISA GS GS GISA
- Location codes are defined In Table 5.2. Control stations are indicated by (C). All other stations are indicators.
b Collection type Is coded as follows: Cl = continuous, GI = 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.
a 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 Types Collection Site Sample Typeb Reactor M-1 M-2 M-3 M-4 M-5 M-8 C
Air Station M-1 Air Station M-2 Air Station M-3 Air Station M4 Air Station M-5 Upstream of Plant Downstream of Plant AP, Al AP, Al AP, Al AP, Al AP, Al SW, SS, BO. F SW, SS, BO. F C
M-9 M-10 M-1 I M-12 M-14 M-15 M-19 M-21 M-24 M-27 C
Campbell Farm M, WW City of Monticello WW Plant Well #1 WW City of Minneapolis DW Montissippi Park SS River Irrigated Coin Field' River Irrigated Potato Fieldc Weinand Farm M
Wise residence VE, WW
- a. Available Producer VE Hoglund Farm M
Trefethen residence (Highest D/Q Gard(VE 11.0 ml @ 307*/NW 0.9 ml @ 137°/SE 0.7 ml @ 1040/ESE 0.9 ml @ 146O/SSE 2.7 mi @ 134'/SE
< 1000' upstream of Plant Intake
< 1000' downstream of Plant Discharge 10.6 ml © 357 0/N 3.4 mi @ 126/SE 0.2 ml @ 2320/SW 37.0 mi @ 132°/SE 1.4 ml @ 114°1ESE 4.8 mi@ 1780/S 0.6 ml @ 198°/SSW
> 10.0 mi.
3.6 mi @ 300°WNW 1.1 mi @ 143°/SE M-28 M-29 General Area of the Site Boundary M-01A M-02A M-03A M-04A M-05A M-06A M-07A M-08A M-09A M-10A M-11A M-12A M-13A M-14A Sherburne Ave. So.
Sherburne Ave. So.
Sherburne Ave. So.
Biology Station Road Biology Station Road Biology Station Road County Road 75 County Road 75 County Road 75 County Road 75 County Road 75 County Road 75 North Boundary Road North Boundary Road TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD 0.7 mi @ 01O/N 0.8 mi @ 31°/NNE 1.3 mi @ 55°/NE 0.6 mi @ 91 °/E 0.6 mi @ 118If/ESE 0.7 mi @ 1300/SE 0.6 ml @ 148°/SSE 0.6 mi @ 170°/S 0.6 mi @ 192°/SSW 0.5 mi @ 218°/SW 0.4 mi @ 24001WSW 0.4 mi @ 260°N 0.8 mi @ 324°/NW 0.7 mi @ 3400/NNW 14
Table 5.2. Sampling locations, Monticello Nuclear Generating Plant, (continued).
Distance and Direction from Code Type' Collection Site Sample Typeb Reactor Armroximatelv 4 to 5 miles Distant from the Plant M-01B Sherco #1 Air Station TLD 4.6 ml @ 03°/N M-02B County Road 11 TLD 4.4 mi @ 20°/NNE M-03B County Road 73 & 81 TLD 4.3 mi @ 53°1NE M-04B County Road 73 (196th St.)
TLD 4.3 ml @ 68°lENE M-05B City of Big Lake TLD 4.4 ml @ 90°lE M-06B County Road 14 and 196th St.
TLD 4.4 ml @ 117°/ESE M-07B Monte Industrial Drive TLD 4.4 ml @ 136lSE M-08B Residence, Hwy 25 & Davidson Ave.
TLD 4.7 mi @ 161°/SSE M-09B Weinand Farm TLD 4.8 mi @ 178°/S M-1 OB Reisewitz Farm, Acacia Ave.
TLD 4.2 ml @ 204°/SSW M-11 B Vanlith Farm, 97th Ave.
TLD 4.0 ml @ 226°lSW M-12B Lake Maria State Park TLD 4.2 ml @ 254°SW M-13B Bridgewater Station TLD 4.0 ml @ 2701W M-14B Anderson Residence, Cty Rd. 111 TLD 4.3 mi @ 289°WNW M-1 5B Red Oak Wild Bird Farm TLD 4.3 ml @ 309'/NW M-16B Sand Plain Research Farm TLD 4.3 ml @ 341°/NNW Special Interest Locations M-01S Osowski Fun Market TLD 0.6 ml @ 234/SW M-02Sd Edgar Klucas Residence TLD 1.1 ml @ 143°/SE M-02S Krone Residence TLD 0.5 ml 0 223°SW M-03S Big Oaks Park TLD 1.6 ml @ 102°/E M-04S Pinewood School TLD 2.4 ml @ 129/SE M-05S Rivercrest Christian Academy TLD 3.1 ml @ 11 B'IESE M-06S Monte Public Works TLD 2.7 mi 0 134°/SE M-01C C
Kirchenbauer Farm TLD 11.5 ml 0 323°/NW M-02C C
County Roads 4 and 15 TLD 11.2 ml @ 47/NE M-03C C
County Rd 19 and Jason Ave.
TLD 13.0 ml @ 100°1E M-04C C
Maple Lake Water Tower TLD 10.3 ml @ 226/ SW
' 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 I 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 02-04-04 Shoreline frozen None required.
02-11-04 02-18-04 MI
- Gamma, M-28 6/30/2004 Hoglund Dairy temporarily out Hoglund will inform the MNGP 1-131 through of business for the summer.
upon resumption of operation.
10/20/2004 Operation resumed 10/20/04.
AP/AI
- Beta, M-01 7/14/2004 Air sampler failure due Electrician checked sampler and 1-131 to open fuse.
replaced fuse.
TLD Ambient M-06B 10/4/2004 TLD missing In the field.
Gamma AP/AI
- Beta, M-01 11/17/2004 No power to sampler.
Reset sample house breaker.
1-131 APIAI
- Beta, M-02 12/15/2004 Air sampler failure due Electrician checked sampler and 1-131 to open fuse.
replaced fuse.
SW Gamma M-08 12-21-04 Shoreline frozen None required.
12-29-04 16
Figure 5-1. Offsite Ambient Radiation (TLDs); Inner Ring versus Outer Ring locations..
-Inner Ring Outer Rina I
20 19 18 17 16 15
>1 "D 14 E
13 12 11 10 4
oM 0
N M
L Ol i D
c oD
- 0)
CD N
M 9
co
- 0)
CD M
a; CD
- 0)
CD 0
0o 0
0 0
0 M)
- 0)
)
- 0)
)
- 0)
- 0)
- 0)
- 0)
- 0) 0>
0 0 o a
N N
N I CN 17
Figure 5-2. Airborne Particulates; analysis for gross beta, average mean of all indicator locations versus control location.
l mIndicators (M-2, 3, 4, 5)l L
Control (M-1) 5 0.0335..
0.031.____. __
0.029---_. __
C.,
0.021_
0.017 0.015 1
I a) 0
~
CIJ CI
(
t-co a) 0 N
'IT~
°0
(
(0 (0
0
(
0 (0
(0 X0 0
0 0
0o 0
0 oo0 0
0 0
(0 (0
a)
(0 0
0 (0
0 0
0 0
l -
-N N
N N
18
h Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Monticello Nuclear Generating Plant Wright, Minnesota (County, State )
Docket No.
Reporting Period 50-263 January-December. 2004 Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)'
Mean (F)f Mean (F)
Routine (Units)
Analyses' Range' Looationd Range' Range' Results TLD (Inner Ring, Gamma 56 3.0 16.0 (56/56)
M-12A 18.4 (4 14)
(See Control 0
General Area at (14.1-20.4) 0.7 ml © 273i1W (17.2-20.4) below.)
Site Boundary) mRem/91 days)
TLD (Outer Ring, Gamma 63 3.0 15.4 (63163)
M-09B, Welnand Farm 16.7 (4 /4)
(See Control 0
4-5 ml. distant)
(12.7-17.9) 4.7 ml @ 180'1S (15.3-17.7) below.)
mRem/91 days)
TLD (Special Gamma 24 3.0 15.1 (24/24)
M-06S, Mont. Pub. Wks.
17.3 (4/4)
(See Control 0
Interest Areas)
(11.0-17.9) 2.7 ml © 136'/SE (16.6-17.9) below.)
mRem/91 days)
TLD (Control)
Gamma 16 3.0 None M-03C, County Rd.19 &
16.5 (4M4) 15.4 (16116) 0 mRem/91 days)
Jason, 13.0 ml. @
100'1E (15.6-18.4)
(13.9-18.4)
Airborne GB 257 0.005 0.024 (207/207)
M-3 0.025 (52152) 0.024 (50/50) 0 Particulates (0.008-0.065) 0.6 ml © 104/1ESE (0.009-0.065)
(0.008-0.061)
(pCI/m3 )
GS 20 Be-7 0.015 0.057 (16/16)
M-1 (C) 0.061 (4/4) 0.061 (414) 0 (0.041-0.080) 11.1 ml © 306'/NW (0.053-0.078)
(0.053-0.078)
Mn-54 0.0011
< LLD
<LLD 0
Co-58 0.0008
< LLD
<LLD 0
Co-60 0.0009
< LLD c
LLD 0
Zn-65 0.0019
< LLD
< LLD 0
Zr-Nb-95 0.0016
< LLD
< LLD 0
Ru-103 0.0012
< LLD LLD 0
Ru-1 06 0.0063
< LLD
< LLD 0
Cs-134 0.0011
< LLD
< LLD 0
Cs-1 37 0.0009
< LLD
< LLD 0
Ba-La-140 0.0038
< LLD
< LLD 0
Ce-141 0.0018
< LLD
< LLD 0
Ce-144 0.0050
< LLD LLD 0
Airbome Iodine 1-131 257 0.07
< LLD
<LLD 0
(pCU n 3
)
19
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Monticello Nuclear Generating Plant Wright. Minnesota (County, State )
Docket No.
Reporting Period 50-263 January-December, 2004 Indicator Location with Highest Control Number Sample Type and' Locations Annual Mean Locations Non-Type Number of LLDb Mean (Ffc Mean (F)c Mean (F)'
Routine (Units)
Analyses'a Range' Locationd Range' Range' Results' Milk (pCi/L) 1-131 49 1.0
< LLD
<LLD 0
GS 49 K-40 200 1315 (30/30)
M-28 1319 (11 /11) 1318 (19119) 0 (1197-1502)
Hoglund Farm (1197-1502)
(1215-1450)
Cs-134 15
< LLD
< LLD 0
Cs-137 15
< LLD
< LLD 0
Ba-La-140 15
< LLD
< LLD 0
River Water H-3 8
330
< LLD
<LLD 0
(pCi/L)
GS 24 Mn-54 15
< LLD
< LLD 0
Fe-59 30
< LLD
< LLD 0
Co-58 15
< LLD
< LLD 0
Co-60 15
< LLD
< LLD 0
. Zn-65 30
< LLD
< LLD 0
Zr-Nb-95 15
< LLD
< LLD 0
Cs-134 15
< LLD
< LLD 0
Cs-137 18
< LLD
< LLD 0
Ba-La-140 15
< LLD
< LLD 0
Ce-144 45
< LLD
< LLD 0
20
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Monticello Nuclear Generating Plant.
Docket No.
50-263 Reporting Period January-December, 2004 Wright, Minnesota (County, State)
Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)',.
Mean (F)f Mean (F)'
Routine (Units)
Analyses' Range' Locationd Range' Range'-
Results' Drinking Water GB 12 1.0 2.7 (12/12)
M-14, Minneapolis 2.7 (12112)
None 0
(pCVL)
(1.5-6.4) 37.0 mi. @ 132' ISE (1.5-6.4) 1-131 12 1.0
< LLD None 0
H-3 4
330
< LLD None 0
GS 12 Mn-54 15
< LLD None 0
Fe-59 30 c 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
.18
< LLD None 0
Ba-La-140 15
< LLD None 0
Ce-144 65
< LLD None 0
Well Water H-3 16 330
< LLD
< LLD 0
(pCUL)
GS 16 Mn-54 15
< LLD
< LLD 0
Fe-59 30
< LLD
< LLD 0
Co-58 15
< LLD
< LLD 0
Co-60 15
< LLD
< LLD 0
Zn-65 30
< LLD'
< LLD 0
Zr-Nb-95 15
< LLD
< LLD 0
Cs-134 -
10
< LLD
< LLD 0
Cs-137 18
< LLD
< LLD 0
Ba-La-140 15
< LLD
< LLD 0
Ce-144 57
< LLD
< LLD 0
Crops - Cabbage GS 2
(pC[/gwet) 1-131 0.009
< LLD
< LLD 0
Cs-134 0.010
< LLD
< LLD 0
Cs-137 0.008
< LLD
< LLD 0
21
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Monticello Nuclear Location of Facility Wright. Minnesota
( County, Stat Generating Plant Docket No.
50-263 Reporting Period January-December, 2004 a
)
Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (Ffc Mean (F)f Mean (Ff Routine (Units)
Analysesa Range' Locatlond Range' Ranrge' Results' Fish GS 4
(pCi/g wet)
K40 0.10 2.73 (2/2)
M-09, Downstream 2.73 (2/2) 2.59 (2/2) 0 (2.18-3.27) 0.2 ml © 621JENE (2.18-3.27)
(2.35-2.82)
Mn-54 0.025
< LLD
< LLD 0
Fe-59 0.057
< LLD
< LLD 0
Co-58 0.030
< LLD
< LLD 0
Co-60 0.016
< LLD
< LLD 0
Zn-65 0.042
< LLD LLD 0
Zr-Nb-95 0.037
< LLD
< LLD 0.
Cs-134 0.018
< LLD
< LLD 0
Cs-137 0.025
< LLD
< LLD 0
Ba-La-140 0.19
< LLD
< LLD 0
Ce-144 0.14
< LLD
< LLD 0
Invertebrates GS 4
(pC/g wet)
Be-7 1.53 1.80 (1/2)
M-09, Downstream 1.80 (1/2)
< LLD 0
0.2 ml @ 621/ ENE K40 2.74
< LLD M-08, Upstream 3.23 (1/2) 3.23 (1/2) 0 0.2 ml @ 285/ WNW Mn-54 0.18
< LLD
< LLD 0
Fe-59 0.26
< LLD
< LLD 0
Co-58 0.20
< LLD
< LLD 0
Co-60 0.14
< LLD
< LLD 0
Zn-65 0.27
< LLD
< LLD 0
Zr-Nb-95 0.14
< LLD
< LLD 0
Ru-103 0.15
< LLD
< LLD 0
Ru-106 1.64
< LLD
< LLD 0
Cs-134 0.13
< LLD
< LLD 0
Cs-137 0.17
< LLD
< LLD 0
Ba-La-140 0.70
< LLD
< LLD 0
Ce-144 0.70
< LLD
< LLD 0
22
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Monticello Nuclear Generating Plant.
Docket No.
50-263 Reporting Period January-December, 2004 Wright. Minnesota (County, State)
Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-b Type Number of LLD Mean (F)'.
Mean (F)
Mean (F)
Routine (Units)
Analysesa Range Locationd Range' Range' Results' Shoreline GS 6
Sediments Be-7 0.28
< LLD.
< LLD 0
(pCl/g dry)
K-40 0.10 10.48 (4/4).
M-15, Montissippi Park 10.58 (2/2) 10.07 (2/2) 0 (10.02-11.14) 1.6 ml @ 117'1ESE (10.02-11.14)
(9.92-10.22)
Mn-54 0.032
<LLD
<LLD 0
Fe-59 0.068'
<LLD
<LLD 0
Co-58 0.030
<LLD
<LLD 0
Co-60 0.027
<LLD
< LLD 0
Zn-65 0.062
<LLD
< LLD 0
Nb-95 0.035
< LLD
<LLD 0
Zr-95 0.052
<LLD
<LLD 0
Ru-103 0.028
<LLD
< LLD 0
Ru-106 0.21
<LLD
<LLD 0
Cs-134 0.039
<LLD
<LLD 0
Cs-137 0.027
.0.099 (4/4)
M-15, Montissippi Park 0.14 (2/2)
<LLD 0
(0.031-0.24) 1.6 ml © 117'/ESE (0.031-0.24)
Ba-La-140 0.048
<LLD
<LLD 0
Ce-144 0.11
<LLD
< LLD 0
a GB = gross beta, GS = gamma scan.
b LLD = nominal lower limit of detection based on a 4.66 sigma counting error for background sample.
'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. AI-Salih. 1955. Beryllium-7 Produced by Cosmic Rays. Science 121: 451-453.
Eisenbud, M. 1963. Environmental Radioactivity, McGraw-Hill, New York, New York, pp. 213, 275, 276.
Environmental, Inc., Midwest Laboratory.
2001a through 2005a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January-December, 2000 through 2004.
2001b through 2005b.
Radiation Environmental Monitoring for Prairie Island 'Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 2000 through 2004.
2003.
Quality Assurance Program Manual, Rev. 1, 01 October2003.
2000.
Quality Control Procedures Manual, Rev. 0, 21 September 2000.
2003.
Quality Control Program, Rev. 1, 21 August 2003.
Gold, S., H.W. Barkhau, B. Shlein, and B. Kahn, 1964.
Measurement of Naturally Occurring Radionuclides in Air, in the Natural Environment, University of Chicago Press, Illinois, 369-382.
Hazleton Environmental Sciences Corporation.
1979a through 1983a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1978 through 1982.
1979b through 1983b.
Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1978 through 1982.
Hohenemser, C. M. Deicher, A. Ernst, H. Hofsass, G. Lindner, E. Racknagel, 1986.
"Chernobyl,"
Chemtech, October 1986, pp. 596-605.
National Center for Radiological Health, 1968. Radiological Helath and Data Reports, Vol. 9, Number 12, 730-746.
Northern States Power Company.
1969. Monticello Nuclear Generating Plant, Environmental Radiation Monitoring Program, Annual Report, June 18, 1968 to December 31, 1968. Minneapolis, Minnesota.
1970.
Monticello Nuclear Generating Plant, Environmental Radiation Surveillance, Annual Report, January 1, 1969 to December 31, 1969. Minneapolis, Minnesota.
1971.
Monticello Nuclear Generating Plant, Environmental Radiation Surveillance, Annual Report, January 1, 1970 to December 31, 1970. Minneapolis, Minnesota.
24
6.0 REFERENCES
CITED (continued)
Northern States Power Company.
Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1, to December 31, 1977 through 1982 (prepared by Hazleton Environmental Sciences). Minneapolis, Minnesota.
1984 through 2000. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 1983 through 1999 (prepared by Teledyne Brown Engineering Environmental Services, Midwest Laboratory). Northbrook, Illinois Teledyne Brown Engineering Environmental Services, Midwest Laboratory.
1984a to 2000a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January-December, 1983 through 1999.
1984b to 2000b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 1983 through 1999.
U.S. Dept 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.
2005. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2000 through 2004. (prepared by Environmental, Inc., Midwest Laboratory). Northbrook, Illinois 25
Environmental, kic.
Mdwest Laboratory an Alegheny Technldogbs Co.
700LandwetwRood *othbxocKIL 600622 (547)5640700 fax(547)5844517 APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS NOTE:
Environmental Inc., Midwest Laboratory participates in Intercomparison studies administered by Environmental Resources Associates, and serves as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada. Results are reported In Appendix A. TLD Intercomparison results, In-house spikes, blanks, duplicates and mixed analyte performance evaluation program results are also reported. Appendix A is updated four times a year, the complete Appendix is included in March, June, September and December monthly progress reports only.
V.
January through December, 2004
Appendix A lnterlaboratory Comparison Program Results Environmental, Inc., Midwest Laboratory, formerly Teledyne Brown Engineering Environmental Services Midwest Laboratory has participated In interlaboratory comparison (crosscheck) programs since the formulation of it's quality control program in December 1971. These programs are operated by agencies which supply environmental type samples 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 Oduplicate' program for the past twelve months. Acceptance Is based on the difference of the results being less than the sum of the errors. Data for previous years available upon request.
The results In Table A-6 were obtained through participation in the Mixed Analyte Performance Evaluation' Program.
The results in Table A-7 were obtained through participation In the Environmental Measurement Laboratory Quality Assessment Program.
Attachment A lists acceptance criteria for "spiked' samples.
Out-of-limit results are explained directly below the result.
Al
a Attachment A ACCEPTANCE CRITERIA FOR SPIKED' SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSESa 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 0.1 galiter or kg 5% of known value Gross alpha s 20 pCi/liter 5.0 pCi/liter
> 20 pCi/liter 25% of known value Gross beta s 100 pCi/liter 5.0 pCi/liter
> 100 pCilliter 5% of known value Tritium s 4,000 pCi/liter i 1a = (pCi/liter) =
169.85 x (known) 0933
> 4,000 pCi/liter 10% of known value Radium-226,-228 2 0.1 pCi/liter 15% of known value Plutonium 2 0.1 pCi/liter, gram, or sample 10% of known value Iodine-131, s 55 pCi/liter 6.0 pCi/liter Iodine-129b
> 55 pCI/liter 10% of known value Uranium-238, s 35 pCi/liter 6.0 pCi/liter Nickel-63b
> 35 pCiUliter 15% of known value Technetium-99b Iron-55b 50 to 100 pCi/liter 10 pCi/liter
> 100 pCi/liter 10% of known value Othersb 20% of known value
' From EPA publication, 'Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981-1982, EPA-60014-811004.
b Laboratory limit.
A2
TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)8.
Concentration (pCUL)
Lab Code Date Analysis Laboratory ERA Control Resultb Result' Limits STW-1005 STW-1005 STW-1006 STW-1006 STW-1006 STW-1006 STW-1006 STW-1007 STW-1007 STW-1008 STW-1008 STW-1008 STW-1015 STW-1015 STW-1016 STW-1016 STW-1016 STW-1016 STW-1016 STW-1017 STW-1017 STW-1018 STW-1019 STW-1019 STW-1019 STW-1020 STW-1028 STW-1028 STW-1029 STW-1029 STW-1029 STW-1029 STW-1029 S1W-1030 STW-1030 STW-1030 STW-1031 STW-1031 STW-1031 02/17/04 02/17/04 02/17/04 02/17/04 02/17/04 02/17/04 02/17/04 02/17104 02/17/04 02/17/04 02/17/04 02/17/04 05/18/04 05118104 05/18/04 05118/04 05/18/04 05/18/04 05/18/04 05/18/04 05/18/04 05/18/04 05/18/04 05/18/04 05/18/04 05/18/04 08/17/04 08/17/04 08/17/04 08/17/04 08/17/04 08/17/04 08/17/04 08/17/04 08/17/04 08/17/04 08/17/04 08/17/04 08/17/04 Sr-89 Sr-90 Ba-I 33 Co-60 Cs-134 Cs-137 Zn-65 Gr. Alpha Gr. Beta Ra-226 Ra-228 Uranium Sr-89 Sr-90 Ba-133 Co-60 Cs-134 Cs-137 Zn-65 Gr. Alpha Gr. Beta 1-131 Ra-226 Ra-228 Uranium H-3 Sr-89 Sr-90 Ba-133 Co-60 Cs-134 Cs-137 Zn-65 Gr. Alpha Gr. Beta Gr. Beta Ra-226 Ra-228 Uranium 36.5 +/- 6.5 13.4 +/- 0.8 60.9 +/- 2.8 95.2 +/- 1.5 71.2 +/- 5.4 157.0 +/- 6.5 103.0 +/- 1.1 15.6 +/- 1.2 46.3 +/- 4.4 8.7 +/- 0.2 16.6 +/- 0.4 34.2 +/- 0.8 39.7 +/- 3.3 12.4 +/- 0.9 96.9 +/- 2.4 39.9 +/- 0.5 48.8 +/- 0.8 82.6 +/- 2.3 77.5 +/- 1.5 32.4 +/- 2.1 63.4 +/- 3.5 25.2 +/- 0.4 16.0 +/- 1.1 12.6 +/- 0.9 13.0 +/- 0.0 32043 +/- 166 16.1 +/-1.9 13.4 +/- 0.1 30.2 +/- 3.9 24.9 +/- 1.9 21.4 +/- 3.4 205.6 +/-4.3 145.5 +/- 3.0 47.7 +/- 9.1 28.1 +/- 2.5 28.1 +/- 2.5 6.9 +/- 0.5 13.1 +/-1.4 6.0 +/- 0.1 44.9 +/- 4.5 11.6 +/- 1.2 63.2 +/- 6.3 96.4 +/- 9.6 75.8 +/- 7.6 155.0 +/- 15.5 102.0 +/-10.2 16.6 +/- 1.7 41.5 +/- 4.2 9.3 +/- 0.0 18.2 +/- 1.8 33.0 +/- 3.3 45.9 +/- 5.0 11.6 +/-5.0 101.0 +/- 10.1 41.6 +/- 5.0 50.5 +/- 5.0 82.5 +/- 5.0 75.2 +/- 7.5 38.8 +/- 9.7 59.6 +/- 10.0 25.1 +/- 3.0 17.3 +/-2.6 10.3 +/-2.6 12.7 +/- 3.0 30900 +/- 3090 20.0 +/- 2.0 13.6 +/-1.4 32.1 +/- 3.2 24.0 +/- 2.4 21.6 +/- 2.2 193.0 +/- 19.3 143.0 +/- 14.3 57.0 +/- 5.7 20.0 +/- 2.0 20.0 +/- 2.0 6.3 +/- 0.6 14.7 +/- 1.5 6.2 +/- 0.6 36.2 - 53.6 2.9 - 20.3 52.3 - 74.1 87.7 - 105.0 67.1 - 84.5 142.0 - 168.0 84.4 - 120.0 7.9 -25.3 32.8 - 50.2 6.9 - 11.7 10.3 - 26.1 27.8 - 38.2 37.2 - 54.6 2.9 - 20.3 83.5 -118.0 32.9 - 50.3 41.8 - 59.2 73.8 - 91.2 62.2 - 88.2 22.0 - 55.6 42.3 - 76.9 19.9 - 30.3 12.8 - 21.8 5.8 -14.8 7.5 -17.9 25600 - 36200 11.3 - 28.7 4.9 - 22.3 23.4 -40.8 15.3 - 32.7 12.9 - 30.3 176.0 - 210.0 118.0 - 168.0 32.3 - 81.7 11.3 - 28.7 11.3 - 28.7 4.6 - 7.9 8.3 - 21.1 1.0 - 11.4 Al-1
6 TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)".
Concentration (pCi/L)
Lab Code Date Analysis Laboratory ERA Control Result' Resultc Limits STW-1037 11/15/04 Sr-89 42.2 i 3.5 45.7 i 5.0 37.0 -51.5 STW-1037 11/15104 Sr-90 37.3 +/- 1.3 36.6 +/- 5.0 27.9 -45.3 STW-1038 11/15/04 Ba-133 75.5 +/-0.8 78.4 +/-7.8 64.8 -92.0 STW-1038 11/15/04 Co-60 12.2 +/-0.7 11.7 +/-5.0 3.0 -20.4 STW-1038 11/15/04 Cs-134 43.6 +/-0.5 42.9 +/-5.0 34.2 -51.6 STW-1038 11/15/04 Cs-137 59.5 +/-2.9 60.1 +/-5.0 51.4 -68.8 STW-1038 11/15/04 Zn-65 50.7 +/- 3.2 50.9 +/- 5.1 42.1 -59.7 STW-1039 11/15/04 Gr. Alpha 23.9 +/-2.2 31.7 +/-7.9 18.0 -45.4 STW-1039 11/15/04 Gr. Beta 35.8 +/-1.3 36.3 +/- 5.0 27.6 -45.0 STW-1040 11/15104 1-131 22.4 +/-1.9 22.0 +/-5.0 16.9 -27.3 STW-1041 11/15104 Ra-226 9.8+/-0.4 9.2+/-1.4 6.8-11.6 STW-1041 11/15/04 Ra-228 8.6 +/-0.3 7.1 +/-1.8 7.0 -10.2 STW-1041 11/15/04 Uranium 11.1 +/-0.3 11.4 +/-3.0 6.2 -16.6 STW-1042 11/15/04 H-3 21218.0 +/- 285.0 20700.0 +/- 2070.0 17100.0 -24300.0
- 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.
A1-2
6 TABLE A-2. Crosscheck program results; Thermoluminescent Dosimetry, (TLDs).
mR Lab Code TLD Type Date Known Lab Result Control Description Value
- 2 sigma Limits Environmental. Inc.
2003-1 CaSO4: Dy Cards 2003-1 CaSO4: Dy Cards 2003-1 CaSO4: Dy Cards 2003-1 CaSO4: Dy Cards 2003-1 CaSO4: Dy Cards 2003-1 CaSO4: Dy Cards 2003-1 CaSO4: Dy Cards 2003-1 CaSO4: Dy Cards 2003-1 CaSO4: Dy Cards 8/8/2003 818/2003 818/2003 8/8/2003 8/8/2003 818/2003 8/812003 8/8/2003 8/8/2003 Reader 1, 120 Reader 1,150 Reader 1, 180 Reader 1, 180 Reader 1, 30 Reader 1, 60 Reader 1, 60 Reader 1, 90 Reader 1, 90 4.69 3.00 2.08 2.08 75.00 18.75 18.75 8.33 8.33 4.74 +/- 0.54 3.02 +/- 0.20 1.89 +/- 0.45 2.11 +/- 0.22 84.40 +/- 4.87 19.11 +/-1.86 22.82 +/- 5.41 9.05 +/- 1.17 7.60 +/- 1.08 3.28 - 6.10 2.10 - 3.90 1.46 - 2.70 1.46 - 2.70 52.50 - 97.50 13.13 - 24.38 13.13 - 24.38 5.83 - 10.83 5.83 - 10.83 Environmental. Inc.
2003-2 2003-2 2003-2 2003-2 2003-2 2003-2 2003-2 2003-2 2003-2 CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards CaSO4: Dy Cards 1/12/2004 1/12/2004 1/12/2004 1/12/2004 1/12/2004 1/12/2004 1/12/2004 1/1212004 1/12/2004 7/12/2004 7/12/2004 7/12/2004 7/12/2004 7/12/2004.
7/12/2004 7/12/2004 7/12/2004 7/12/2004 Reader 1,30 Reader 1, 60 Reader 1, 60 Reader 1, 90 Reader 1, 90 Reader 1, 120 Reader 1, 150 Reader 1, 150 Reader 1, 180 Reader 1, 30 cm Reader 1, 30 cm Reader 1, 60 cm Reader 1, 60 cm Reader 1, 90 cm Reader 1, 90 cm Reader 1, 120 cm Reader 1, 150 cm Reader 1, 180 cm 61.96 15.49 15.49 6.88 6.88 3.87 2.48 2.48 1.72 55.23 55.23 13.81 13.81 6.14 6.14 3.45 2.21 1.53 Environmental, Inc.
2004-1 CaSO4: Dy Cards 2004-1 CaSO4: Dy Cards 2004-1 CaSO4: Dy Cards 2004-1 CaSO4: Dy Cards 2004-1 CaSO4: Dy Cards 2004-1 CaSO4: Dy Cards 2004-1 CaSO4: Dy Cards 2004-1 CaSO4: Dy Cards 2004-1 CaSO4: Dy Cards 73.50 i 2.58 19.70 i 0.51 16.93
- 1.37 8.06
- 0.60 6.64 +/-0.58 4.39 +/- 0.17 2.34 +/- 0.18 2.51 +/-0.16 2.01 +/-0.13 61.07 +/- 4.38 62.82 +/- 1.75 14.10 +/- 0.56 14.03 +/- 0.48 5.97 +/- 0.21 6.26 +/- 0.14 4.40 +/- 0.63 2.34 +/- 0.12 1.65 +/- 0.02 43.37 - 80.55 10.84 - 20.14 10.84 - 20.14 4.82 - 8.94 4.82 - 8.94 2.71 - 5.03 1.74 - 3.22 1.74 - 3.22 1.20 - 2.24 38.66 - 71.80 38.66 - 71.80 9.67 - 17.95 9.67 - 17.95 4.30 - 7.98 4.30 - 7.98 2.42 - 4.49 1.55 - 2.87 1.07 - 1.99 A2-1
A TABLEA-3. In-House"Spike"Samples.
Concentration (pCi/L)a Lab Code Sample Date Analysis Laboratory results Known Control Type 2s, n=1b Activity Limits' SPVE-707 SPCH-711 SPW-721 SPAP-733 SPW-735 SPW-735 SPW-735 SPW-735 SPMI-737 SPMI-737 SPMI-737 SPMI-737 SPW-1 109 Vegetation Charcoal water Air Filter water water water water Milk Milk Milk Milk water 2/20/2004 2/20/2004 2/20/2004 2/25/2004 2/25/2004 2125/2004 2/25/2004 2/25/2004 2125/2004 2/25/2004 2/25/2004 2/25/2004 3/18/2004 1-131(G) 1-131 (G)
Ni-63 Gr. Beta Cs-1 34 Cs-137 1-131 1-131 Cs-134 Cs-137 1-131 1-131 Fe-55
- 5.68 +/- 0.15 6.35 +/- 0.11 161.00
- 13.20 1.39 +/- 0.02 41.59 +/- 7.02 64.11 +/-7.39 36.55 +/- 0.48 41.97 +/- 8.93 37.40 +/- 5.40 69.13 +/- 9.58 45.03 +/- 0.53 44.43 +/- 9.22 39.98 +/- 1.72 4.93 6.94 169.00 1.48 39.10 64.56 40.08 40.08 39.10 64.56 40.08 40.08 39.98 2.96 - 6.90 0.00 - 16.94 101.40 - 236.60 0.00 - 11.48 29.10 -49.10 54.56 - 74.56 28.08 - 52.08 28.08 - 52.08 29.10 -49.10 54.56 - 74.56 28.08 - 52.08 28.08 - 52.08 23.99 - 55.97 SPW-1496 SPMI-1683 SPW-1683 SPW-1683 SPMI-1685 SPMI-1685 SPMI-1685 SPMI-1685 SPMI-1685 SPW-1686 SPW-1686 SPVE-1862 SPCH-1886 SPAP-1888 SPF-1917 SPF-1917 SPW-3151 SPW-4232 SPAP-4234 SPW-5712 SPW-5712 SPW-5712 SPMI-5714 water Milk water water Milk Milk Milk Milk Milk water water Vegetation Charcoal Air Filter Fish Fish water water Air Filter water water water Milk 4/7/2004 4/16/2004 4116/2004 4/1612004 4/1612004 4/16/2004 4/16/2004 41612004 4/1612004 4/16/2004 4/16/2004 4/26/2004 4/2612004 4/2712004 4/29/2004 4/2912004 6/24/2004 8/4/2004 8/4/2004 10/612004 10/612004 10/6/2004 10/6/2004 H-3 Sr-90 1-131 1-131 (G)
Cs-134 Cs-137 1-131 1-131(G)
Sr-90 Cs-1 34 Cs-1 37 1-131(G) 1-131(G)
Gr. Beta Cs-134 Cs-137 Fe-55 H-3 Gr. Beta Cs-134 Cs-137 Sr-90 Sr-90 80006.60 +/- 776.00 42.80 +/- 1.81 54.47 +/- 0.73 65.82 +/- 8.86 33.60 +/- 4.24 61.77 +/- 7.59 65.85 +/- 0.79 75.56 +/- 11.86 42.56 +/- 1.66 39.31 +/- 4.35 67.73 +/- 7.92 1.32 +/- 0.03 2.90 +/- 0.07 1.35 +/- 0.02 1.44 *0.04 1.33 +/- 0.06 33.85
- 1.61 80225.00 +/- 785.00 1.63 +/- 0.02 61.04 +/- 2.51 62.01 +/- 2.76 48.40 +/- 2.00 41.61 +/- 1.57 83896.00 43.43 66.60 66.60 37.29 64.36 66.60 66.60 43.43 37.29 64.36 1.12 2.80 1.48 1.47 1.29 37.32 82380.00 1.46 63.61 63.66 42.94 42.94 67116.80 - 100675.20 34.74 - 52.12 53.28 - 79.92 56.60 -76.60 27.29 -47.29 54.36 - 74.36 53.28 - 79.92 56.60 - 76.60 34.74 - 52.12 27.29 -47.29 54.36 - 74.36 0.67 - 1.57 1.68 - 3.92 0.00 - 11.48 0.88 - 2.06 0.77 -1.81 22.39 - 52.25 65904.00 - 98856.00 0.00 - 11.46 53.61 - 73.61 53.66 - 73.66 34.35 - 51.53 34.35 -51.53 A3-1
TABLE A-3. In-House "Spike' Samples Concentration (pCi1L)
Lab Code Sample Date Analysis Laboratory results Known Control Type 2s, n=1b Activity LImitsc SPMI-7418 Milk 12/22/2004 Cs-1 34 59.09 +/- 2.59 59.25 49.25 -69.25 SPMI-7418 Milk 12/2212004 Cs-1 37 65.45
- 5.61 63.35 53.35 - 73.35 SPW-7420 water 12/22/2004 Cs-134 58.42 +/- 1.99 59.25 49.25 - 69.25 SPW-7420 water 12/22/2004 Cs-1 37 64.26 +/- 4.18 63.35 53.35 -73.35 SPW-7420 water 12/22/2004 Sr-89 105.26 : 4.21 103.47 82.78 -124.16 SPW-7420 water 12122/2004 Sr-90 48.24
- 1.70 42.72 34.18 - 51.26 SPAP-7437 Air Filter 12/22/2004 Gr. Beta 1.65 +/- 0.02 1.45 0.00 - 11.45 SPF-7524 Fish 12/2912004 Cs-134 1.11 0.03 1.27 0.76-1.78 SPF-7524 Fish 12/29/2004 Cs-1 37 1.21 +/-0.05 1.19 0.71 - 1.67 SPW-7526 water 12/2912004 H-3 78615.70 +/- 773.70 80543.00 64434.40 -96651.60 SPW-7532 water 12/29/2004 Fe-55 30894.00 +/- 1484.00 32752.00 26201.60 - 39302.40 SPW-7540 water 12/29/2004 Tc-99 30.28 +/- 1.11 32.98 20.98 - 44.98
- Liquid sample results are reported In pCIIIter, air filters (pCi/m3), charcoal (p0l/m), and solid samples (pCi/g).
b Results are based on single determinations.
c Control limits are based on Attachment A, Page A2 of this report.
NOTE: For fish, Jello is used for the Spike matrix. For Vegetation, cabbage is used for the Spike matrix.
A3-2
TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)O Lab Code Sample Date Analysis Laboratory results (4.66a)
Acceptance Type LLD Activityb Criteria (4.66 cy)
SPCH-712 SPW-722 SPAP-734 SPW-736 SPW-736 SPW-736 SPW-736 SPMI-738 SPMI-738 SPMI-738 SPMI-738 SPW-1110 Charcoal Water Air Filter Water Water Water Water Milk Milk Milk Milk Water 2/20/2004 2/20/2004 2/25/2004 2/25/2004 2/25/2004 2/2512004 2/25/2004 2/25/2004 2/25/2004 2125/2004 2/2512004 3/18/2004 1-131(G)
Ni-63 Gr. Beta Cs-134 Cs-137 1-131 1-131(G)
Cs-134 Cs-137 1-131 1-131 (G)
Fe-55 2.24.
2.64 0.96 2.47 1.91 0.15 3.24 2.54 5.34 0.16 5.36 772.70
-0.78 +/- 1.58
-1.02 +/- 0.42
-0.031 +/- 0.10
-0.071 +/- 0.10 168.4 +/-480.90 9.6 20 3.2 10 10 0.5 20 10 10 0.5 20 1000 SPW-1497 SPW-1684 SPW-1684 SPW-1684 SPW-1684 SPW-1684 SPW-1684 SPMI-1686 SPMI-1686 SPMI-1686 SPMI-1686 SPMI-1686 SPMI-1686 SPVE-1863 SPCH-1887 SPAP-1889 SPF-1918 SPF-1918 SPW-3152 SPW4233 SPAP-4235 SPW-5711 SPW-5711 SPW-5711 SPW-5711 Water Water Water Water Water Water Water Milk Milk Milk Milk Milk Milk Vegetation Charcoal Air Filter Fish Fish Water Water Air Filter Water Water Water Water 4/7/2004 4/16/2004 4/16/2004 4/16/2004 4/16/2004 4/16/2004 4/16/2004 4/16/2004 4/1612004 4/16/2004 4/16/2004 4/16/2004 4/16/2004 4/26/2004 4/26/2004 4/27/2004 4/29/2004 4/29/2004 6/2412004 8/4/2004 8/4/2004 10/612004 10/612004 10/6/2004 10/6/2004 H-3 Cs-134 Cs-137 1-131 1-131 (G)
Sr-89 Sr-90 Cs-1 34 Cs-1 37 1-131 1-131(G)
Sr-89 Sr-90 1-131 (G) 1-131 (G)
Gr. Beta Cs-1 34 Cs-1 37 Fe-55 H-3 Gr. Beta Co-60 Cs-134 Cs-i 37 Sr-90 152.30 2.43 2.53 0.50 4.49 0.64 0.64 5.00 4.16 0.45 6.53 0.71 0.71 3.55 7.04 0.74 7.13 6.59 790.30 154.23 0.96 4.26 6.02 5.28 0.61 81.4 +/- 79.40 0.21 +/- 0.26 0.19 +/- 0.52 0.13 +/- 0.31 0.13 +/- 0.24 0.11 +/- 0.70 0.66 +/- 0.40
-0.96 +/- 0.35
-70.0 +/- 474.50 102.67 +/- 81.38
-0.99 +/- 0.38
-0.13 +/- 0.27 200 10 10 0.5 20 5
1 10 10 0.5 20 5
1 20 9.6 3.2 100 100 1000 200 3.2 10 10 10 I
A4-1
TABLE A-4. In-House "Blank7 Samples Concentration (pCi/L)a Lab Code Sample Date Analysis Laboratory results (4.66a)
Acceptance Type LLD Activityb Criteria (4.66 a)
SPMI-5713 SPMI-5713 SPMI-5713 SPMI-5713 SPMI-7419 SPMI-7419 SPMI-7419 SPW-7421 SPW-7421 SPAP-7438 SPF-7525 SPF-7525 SPW-7526 SPW-7533 SPW-7535 SPW-7540 Milk Milk Milk Milk Milk Milk Milk Water Water Air Filter Fish Fish Water Water Water Water 10/6/2004 10/612004 10/6/2004 1016/2004 12/22/2004 12122/2004 12122/2004 1212212004 12122/2004 12/22/2004 1212912004 12/29/2004 12/29/2004 12/29/2004 12/29/2004 12/29/2004 Cs-134 Cs-137 1-131 (G)
Sr-90 Cs-134 Cs-137 Sr-90 Sr-89 Sr-90 Gr. Beta Cs-134 Cs-137 H-3 Fe-55 Ni-63 Tc-99 4.60 5.81
. 6.07 0.68 8.66 5.61
- 0.82 1.21 0.82 0.93 8.27 10.60 164.80 753.00 13.10 1.19 1.4 +/- 0.45 1.67 +/- 0.48 0.58 +/- 0.94 0.26 +/- 0.41
-0.78 +/- 0.40
-47.0 +/- 84.60 118.6 +/- 465.80 4.3 +/- 8.10
-0.036 +/- 0.72 10 10
-20 1
10 10 1
5 1
3.2 100 100 200 1000 20 10
- Liquid sample results are reported In pCilLter, air filters( pCilfilter), charcoal (pCVcharcoal canister), and solid samples (pCig).
b Activity reported Is a net activity resulL For gamma spectroscopic analysis, activity detected below the LLD value Is not reportec
' 1-131(G); lodine-131 as analyzed by gamma spectroscopy.
d Low levels of Sr-90 are still detected In the environment. A concentration of (1-5 pCUL) In milk Is not unusual.
A4-2
I TABLEA-5. In-House"Duplicate"Samples Concentration (pCVL)m Averaged Lab Code Date Analysis First Result Second Result Result E-30, 31 E-30, 31 WW-58, 59 WW-58, 59 TD-7889, 7890 MI-79,80 MI-79,80 S-100, 101 SW-225, 226 SW-225, 226 U-304, 305 SW-345, 346 SWT-423, 424 SWU-469,470 TD-545, 546 MI-524, 525 MI-567, 568 MI-567, 568 MI-588, 589 SWU-778, 779 LW-1014.1015 SW-966, 967 SW-966, 967 SW-966, 967 SW-1249,1250 LW-1464.1465 AP-1633,1634 AP-1714,1715 TD-1489,1490 SWT-1299,1300 DW-1420,1421 DW-1510,1511 BS-1537,1538 WW-1654,1655 LW-1680,1681 MI-1735,1736 MI-1802,1803 MI-1802,1803 U-1781, 1782 SWT-1933,1934 F-1912,1913 F-1912,1913 LW-1960,1961 115/2004 115/2004 115/2004 1/5/2004 115/2004 1/7/2004 1/72004 1/13/2004 1/13/2004 1/13/2004 1/16/2004 1/27/2004 1/27/2004 1/27/2004 2/2/2004 2/4/2004 2/9/2004 2/9/2004 2/11/2004 2/24/2004 3/1/2004 3/9/2004 3/9/2004 3/9/2004 3/31/2004 3/31/2004 3/31/2004 3/31/2004 4/1/2004 4/2/2004 4/2/2004 4/2/2004 4/6/2004 4/13/2004 4/13/2004 4/14/2004 4/19/2004 4/19/2004 4/21/2004 4/27/2004 4/29/2004 4/29/2004 4/29/2004 Gr. Beta K-40 Gr. Beta K-40 H-3 K-40 Sr-90 Cs-1 37 Gr. Alpha Gr. Beta Gr. Beta 1-131 Gr. Beta Gr. Beta H-3 K-40 K-40 Sr-90 K-40 Gr. Beta Gr. Beta Gr. Alpha Gr. Beta H-3 Gr. Beta Gr. Beta Be-7 Be-7 H-3 Gr. Beta Gr. Beta 1-131 Gr. Beta Gr. Beta Gr. Beta K-40 K-40 Sr-90 Gr. Alpha Gr. Beta H-3 K-40 Gr. Beta 1.27 +/- 0.06 1.33 +/- 0.21 4.20 +/- 1.33 2.30 +/- 0.23 16582.00 +/- 366.00 1451.50 +/- 125.90 0.90 +/- 0.31 8.50 +/- 0.23 2.62 +/- 1.26 6.37 +/- 1.15 5.18 +/- 1.38 1.32 +/- 0.24 2.34 +/- 0.54 2.99 +/- 0.57 658.40 +/- 104.60 1240.00 +/- 147.90 1322.90 +/- 105.50 0.98 +/- 0.48 1185.70 +/- 157.80 2.55 +/- 0.54 1.78 +/- 0.56 2.70 +/- 1.43 8.06 +/- 1.20 182.04 +/- 86.24 4.71 +/-1.11 2.13 +/- 0.52 0.05 +/- 0.02 0.04 +/- 0.01 681.00 +/- 110.00 3.13 +/- 0.57 1.29 +/- 0.83 0.68 +/- 0.27 6.81 +/- 1.20 6.83 +/- 1.17 2.45 +/- 0.64 1384.90 +/- 182.00 1327.50 +/- 109.10 0.72 +/- 0.40 0.20 +/- 1.90 2.60 +/- 0.55 8875.00 +/- 250.00 3406.90 +/- 533.30 2.23 +/- 0.55 1.26 +/- 0.05 1.11 +/- 0.20 4.46 +/- 1.34 2.70 +/- 0.27 16060.00 +/- 360.00 1383.60 +/- 115.50 1.05 +/- 0.34 8.52 +/- 0.21 2.05 +/- 1.16 4.92 +/- 1.06 7.04 +/- 1.53 1.56 +/- 0.21 2.38 +/- 0.52 3.09 +/- 0.67 712.30 +/- 106.60 1265.60 +/- 166.30 1340.80 +/- 112.80 0.79 +/- 0.42 1337.70 +/- 160.00 2.53 +/- 0.56 2.06 +/- 0.57 2.96 +/- 1.63 7.33 +/- 1.21 198.87 +/- 86.97 5.25 +/- 1.10 2.39 +/- 0.53 0.05 +/- 0.02 0.05 +/- 0.01 709.00 +/- 111.00 3.64 +/- 0.60 1.62 +/- 0.87 0.62 +/- 0.36 6.76 +/- 1.23 5.60 +/- 1.12 2.93 +/- 0.62 1408.20 +/- 187.90 1206.30 +/- 113.30 0.77 +/- 0.41
-0.30 +/- 2.40 2.33 +/- 0.52 9119.00 +/- 253.00 3550.60 +/- 581.40 2.38 +/- 0.57 1.27 +/- 0.04 1.22 +/- 0.15 4.33 +/- 0.94 2.50 +/- 0.18 16321.00 +/- 256.69 1417.55 +/- 85.43 0.97 +/- 0.23 8.51 +/- 0.16 2.34 +/- 0.86 5.65 +/- 0.78 6.11 +/-1.03 1.44 +/- 0.16 2.36 +/- 0.38 3.04 +/- 0.44 685.35 +/- 74.67 1252.80 +/- 111.28 1331.85 +/- 77.22 0.89 +/- 0.32 1261.70 +/- 112.36 2.54 +/- 0.39 1.92 +/- 0.40 2.83 +/- 1.08 7.69 +/- 0.85 190.45 +/- 61.24 4.98 +/- 0.78 2.26 +/- 0.37 0.05 +/- 0.01 0.05 +/- 0.01 695.00 +/- 78.14 3.39 +/- 0.41 1.46 +/- 0.60 0.65 +/- 0.23 6.78 +/- 0.86 6.21 +/- 0.81 2.69 +/- 0.45 1396.55 +/- 130.80 1266.90 +/- 78.64.
0.74 +/- 0.28
-0.05 +/- 1.53 2.46 +/- 0.38 8997.00 +/- 177.84 3478.75 +/- 394.47 2.31 +/- 0.40 A5-1
TABLEA-5. In-House"Duplicate"Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result BS-2083, 2084 BS-2083, 2084 BS-2083, 2084 BS-2083, 2084 Ml-2225, 2226 SW-2267, 2268 SW-2267, 2268 MI-2437, 2438 MI-2437, 2438 F-2413, 2414 SO-2578, 2579 SO-2578, 2579 SO-2578, 2579 SS-2603, 2604 SS-2603, 2604 G-2677, 2678 G-2677, 2678 G-2677, 2678 G-2677, 2678 DW-2700, 2701 TD-2876, 2877 Ml-2724, 2725 Ml-2724, 2725 BS-2921, 2922 TD-2876, 2877 BS-2897, 2898 SWU-3092, 3093 CF-2986, 2987 CF-2986, 2987 MI-2977, 2978 MI-3007, 3008 W-3031, 3032 W-3071, 3072 SW-3145, 3146b DW-3278, 3279 AP-3922, 3923 AP-3637, 3638 LW-3589, 3590 LW-3589, 3590 LW-3589, 3590 AP-3943, 3944 5/312004 5/312004 5/312004 51312004 5/11/2004 5/11/2004 5/1112004 5/1712004 5/17/2004 512012004 5/26/2004 5/26/2004 5/26/2004 5126/2004 5/2612004 6/1/2004 6/11/2004 6/1/2004 6/1/2004 6/112004 6/11/2004 6/3/2004 6/3/2004 6/3/2004 61420o04 6/4/2004 6/9/2004 6/14/2004 6/1412004 6/15/2004 6/15/2004 6/18/2004 6/21/2004 6/22/2004 6/25/2004 6/28/2004 6/29/2004 6/30/2004 6/30/2004 6/30/2004 6/30/2004 Be-7 Gr. Beta K-40 Sr-90 K-40 Gr: Alpha Gr. Beta K-40 Sr-90 K-40 Cs-1 37 Gr. Beta K-40 Cs-137 K-40 Be-7 Gr. Beta K-40 Sr-90 Gr. Beta H-3 K-40 Sr-90 K-40 H-3 Gr. Beta Gr. Beta Be-7 K-40 K-40 K-40 H-3 H-3 1-131 1-131 Be-7 Be-7 Gr. Alpha Gr. Beta H-3 Be-7 1.10 i 0.44 28.44 +/- 2.27 6.75 +/- 0.89 0.12 +/- 0.04 1396.30 +/- 124.20 2.95 +/- 1.44 6.80 +/- 1.18 1549.00 +/- 123.40 1.83 +/- 0.44 2844.60 +/- 550.40 0.16 +/- 0.02 28.07 +/- 3.24 19.41 +/- 0.78 0.06 +/- 0.02 10.18 +/- 0.63 1.31 +/- 0.25 5.73 +/- 0.12 5.56 +/- 0.49 0.01 +/- 0.00 1.82 +/- 1.01 13116.00 +/- 324.00 1509.00 +/- 116.10 1.64 +/- 0.46 8.32 +/- 0.63 13116.00 +/- 324.00 9.31 +/- 1.43 1.95 +/- 0.71 0.69 +/- 0.12 4.50 +/- 0.32 1486.70 +/- 120.10 1333.90 +/- 121.30 642.00 +/- 108.00 273.00 +/- 94.00 0.97 +/- 0.20 0.67 +/- 0.26 0.08 +/- 0.01 0.08 +/- 0.01 0.28 +/- 0.55 1.91 +/- 0.64 8369.20 +/- 262.57 0.08 +/- 0.02 1.17 +/- 0.20 25.56 +/- 2.04 6.35 +/- 0.53 0.17 +/- 0.05 1227.60 +/- 125.40 2.41 +/- 1.37 7.25 +/- 1.21 1566.20 +/- 118.60 1.99 +/- 0.42 2963.00 +/- 532.30 0.21 +/- 0.05 28.73 +/- 3.00
- 18.93 +/- 1.04 0.06 +/- 0.02 10.43 +/- 0.56 1.25 +/- 0.23 5.86 +/- 0.12 5.78 +/- 0.50 0.01 +/- 0.01 2.66 +/- 0.94 12746.00 +/- 320.00 1489.20 +/- 126.10 1.81 +/-0.44 8.55 +/- 0.62 12746.00 +/- 320.00 8.82 +/- 1.39 2.55 +/- 0.76 0.84 +/- 0.19 3.82 +/- 0.48 1291.60 +/- 167.40 1355.80 +/- 176.50 562.00 +/- 105.00 203.00 +/- 92.00 1.43 +/- 0.20 0.48 +/- 0.25 0.07 +/- 0.01 0.07 +/- 0.01 1.29 +/- 0.89 2.86 +/- 0.70 -
8226.01 +/- 260.51 0.09 +/- 0.02 1.14 +/- 0.24 27.00 +/-1.53 6.55 +/- 0.52 0.15 +/- 0.03 1311.95 +/- 88.25 2.68 +/- 0.99 7.03 +/- 0.84 1557.60 +/- 85.58 1.91 +/- 0.30 2903.80 +/- 382.85 0.18 +/- 0.03 28.40 +/- 2.21 19.17 +/- 0.65 0.06 +/- 0.02 10.30 +/- 0.42 1.28 +/- 0.17 5.79 +/- 0.09 5.67 +/- 0.35 0.01 +/- 0.00 2.24 +/- 0.69 12931.00 +/- 227.69 1499.10 +/- 85.70 1.73 +/- 0.32 8.44 +/- 0.44 12931.00 +/- 227.69 9.06 +/- 1.00 2.25 +/- 0.52 0.76 +/- 0.11 4.16 +/- 0.29 1389.15 +/- 103.01 1344.85 +/- 107.08 602.00 +/- 75.31 238.00 +/- 65.76 1.20 +/- 0.14 0.57 +/- 0.18 0.07 +/- 0.01 0.07 +/- 0.01 0.79 +/- 0.53 2.39 +/- 0.48 8297.61 +/-184.94 0.08 +/- 0.01 A5-2
TABLE A-5. In-House "Duplicate" Samples Concentration (pCiUL)8 Averaged Lab Code Date Analysis First Result Second Result Result E-3327, 3328 E-3327, 3328 G-3377, 3378 G-3377, 3378 G-3377, 3378 VE-3681, 3682 CF-3707, 3708 CF-3707, 3708 SW-3773, 3774 LW-3849, 3850 SWU-4307, 4308 MI-4051, 4052 VE-4079, 4080 MI-4163, 4164 MI-4163, 4164 WW-4387, 4388 MI-4286, 4287 MI-4286. 4287 VE-4370, 4371 VE-4408,4409 VE-4467, 4468 MI-4492, 4493 MI-4492. 4493 MI-4518, 4519 VE-4748, 4749 VE-4748, 4749 LW-4769, 4770 ME-4905, 4906 ME-4905, 4906 MI-4926,4927 MI-4926, 4927 VE-5027, 5028 VE-5027, 5028 SW-5003, 5004 MI-5050, 5051 MI-5050, 5051 WW-5072, 5073 SW-5216, 5217 SW-5216, 5217 7/1/2004 7/1/2004 7/1/2004 7/1/2004 7/1/2004 7/13/2004 7/13/2004 7/13/2004 7/14/2004 7/14/2004 7/14/2004 7/28/2004 7/2812004 7/28/2004 7/28/2004 8/3/2004 8/4/2004 8/4/2004 8/4/2004 8/5/2004 8/9/2004 8/10/2004 8/10/2004 8/1112004 8/25/2004 8/25/2004 8/26/2004 9/1/2004 9/112004 911/2004 9/1/2004 9/2/2004 9/2/2004 9/7/2004 9s7/2004 917/2004 9/7/2004 9/14/2004 9/14/2004 Gr. Beta K-40 Be-7 Gr. Beta K-40 K-40 Be-7 K-40 H-3 Gr. Beta Gr. Beta K-40 K-40 K-40 Sr-90 Gr. Beta K-40 Sr-90 H-3 K-40 K-40 K-40 Sr-90 K-40 Gr. Beta K-40 Gr. Beta Gr. Beta K-40 K-40 Sr-90 Gr. Beta K-40 1-131 K-40 Sr-90 Gr. Beta Gr. Alpha Gr. Beta 1.21 +/- 0.06 1.08 +/- 0.20 1.10 +/- 0.13 6.42 +/- 0.19 5.26 +/- 0.31 2.65 +/- 0.45 1.97 +/- 0.44 5.39 +/- 0.44 10697.20 +/- 295.70 2.21 +/- 0.54 3.49 +/- 0.57 1190.70 +/- 204.60 4.90 +/- 0.51 1422.40 +/- 186.50 0.87 +/- 0.32 5.94 +/- 0.76 1435.20 +/-76.90 1.88 +/- 0.40 0.54 +/- 0.08 2.03 +/- 0.39 6.28 +/- 0.76 1478.70 +/- 116.70 1.35 +/- 0.40 1197.30 +/- 158.50 2.31 +/- 0.05 1.70 +/- 0.25 2.00 +/- 0.58 3.06 +/-0.10 2.33 +/- 0.67 1316.20 +/- 115.40 3.62 +/- 0.52 2.43 +/- 0.07 1.77 +/- 0.20 1.69 +/- 0.23 1559.40 +/- 131.80 2.26 +/- 0.52 4.31 +/- 0.70 4.34 +/- 1.71 7.97 +/- 1.24 1.35 +/- 0.07 1.30 +/- 0.22 1.16 +/-0.16 6.28 +/- 0.19 5.36 +/- 0.28 2.90 +/- 0.61 2.11 +/- 0.25 4.98 +/- 0.42 10689.60 +/- 295.70 2.32 +/- 0.65 3.68 +/- 0.61 1357.00 +/- 145.90 4.62 +/- 0.61 1330.80 +/- 181.00 1.00 +/- 0.35 6.28 +/- 0.76 1404.70 +/- 80.54 1.31 +/- 0.35 0.62 +/- 0.08 2.12 +/- 0.32 6.11 +/- 0.75 1472.50 +/- 105.10 1.08 +/- 0.42 1350.20 +/- 202.30 2.32 +/- 0.05 1.94 +/- 0.31 2.07 +/- 0.58 2.93 +/- 0.10 3.26 +/- 0.58 1285.80 +/- 117.30 2.07 +/- 0.43 2.39 +/- 0.06 1.94 +/- 0.31 1.50 +/- 0.25 1560.70 +/- 121.20 1.61 +/-0.47 4.11 +/- 0.69 4.30 +/- 1.77 8.58 +/- 1.29 1.28 +/- 0.05 1.19 +/- 0.15 1.13 +/- 0.10 6.35 +/- 0.13 5.31 +/- 0.21 2.77 +/- 0.38 2.04 +/- 0.25 5.19 +/- 0.30 10693.40 +/- 209.09 2.27 +/- 0.42 3.59 +/- 0.42 1273.85 +/- 125.65 4.76 +/- 0.40 1376.60 +/- 129.95 0.93 +/- 0.24 6.11 +/-0.54 1419.95 +/- 55.68 1.59 +/- 0.26 0.58 +/- 0.06 2.08 +/- 0.25 6.20 +/- 0.53 1475.60 +/- 78.53 1.22 +/- 0.29 1273.75 +/- 128.50 2.31 +/-0.04 1.82 +/- 0.20 2.04 +/- 0.41 3.00 +/- 0.07 2.80 +/- 0.44 1301.00 +/- 82.27 2.84 +/- 0.34 2.41 +/- 0.05 1.86 +/- 0.18 1.59 +/- 0.17 1560.05 +/- 89.53 1.94 +/- 0.35 4.21 +/- 0.49 4.32 +/- 1.23 8.27 +/- 0.89 A5-3
TABLE A-5. In-House "Duplicatew Samples Concentration (pCVL)a Averaged Lab Code Date Analysis First Result Second Result Result G-5237, 5238 G-5237, 5238 LW-5316, 5317 SS-5450, 5451 AP-6308, 6309 SWU-5495, 5496 AP-6070, 6071 G-5516, 5517 G-5516, 5517 AP-6258. 6259 F-7211, 7212 F-7211, 7212 BS-5902, 5903 BS-5902, 5903 E-5654. 5655 E-5654, 5655 MI-5676, 5677 SO-5756, 5757 S0-5756, 5757 SO-5756, 5757 VE-6483, 6484 MI-5923, 5924 SS-6046, 6047 SS-6046,6047 SS-6046.6047 DW-6208. 6209 BS-6694. 6695 VE-6354, 6355 VE-6354, 6355 DW-6462, 6463 LW-6377, 6378 SS-6504, 6505 LW-6762, 6763 BS-6576. 6577 BS-6576, 6577 S0-6715, 6716 SO-6715, 6716 SO-6715, 6716 S0-6715, 6716 VE-6673. 6674 VE-6673, 6674 VE-6673, 6674 9/15/2004 9/15/2004 9/16/2004 9/24/2004 9/27/2004 9/28/2004 9/28/2004 9/29/2004 9/29/2004 9/29/2004 9/29/2004 9/29/2004 10/1/2004 10/1/2004 10/4/2004 10/4/2004 10/4/2004 10/4/2004 10/4/2004 10/4/2004 10/6/2004 10/12/2004 10/13/2004 10/13/2004 10/13/2004 10/15/2004 10/19/2004 10/25/2004 10125/2004 10127/2004 10/28/2004 10/29/2004 10/31/2004 11/1/2004 11/1/2004 11/2/2004 11/2/2004 11/2/2004 11/2/2004 11/8/2004 11/8/2004 11/8/2004 Be-7 K-40 Gr. Beta K-40 Be-7 Gr. Beta Be-7 Be-7 K-40 Be-7 Cs-137 K-40 Co-60 Co-60 Gr. Beta K-40 K-40 Gr. Alpha Gr. Beta K-40 K-40 K-40 Cs-1 37 Gr. Beta K-40 1-131 K-40 Gr. Beta K-40 Gr. Beta Gr. Beta K-40 Gr. Beta Gr. Beta K-40 Cs-137 Gr. Alpha Gr. Beta K-40 Gr. Alpha Gr. Beta K-40 1.18 +/-0.23 7.16 +/- 0.58 2.76 +/- 0.58 10.33 +/- 0.66 0.08 +/- 0.01 3.38 +/- 1.78 0.08 +/- 0.01 1.81 +/- 0.29 7.35 +/- 0.70 0.07 +/- 0.01 0.04 +/- 0.01 2.76 +/- 0.27 0.25 +/- 0.05 2.53 +/- 0.11 1.40 +/- 0.06 1.32 +/- 0.26 1311.00 +/- 122.00 7.12 +/- 3.09 19.66 +/- 2.63 16.45 +/- 0.86 9.35 +/- 0.55 1333.60 +/- 183.50 0.02 +/- 0.01 7.93 +/-1.72 5.77 +/- 0.42 0.89 +/- 0.26 11.84 +/- 0.67 4.82 +/- 0.14 4.71 +/- 0.54 8.46 +/- 1.27 2.18 +/- 0.54 9.28 +/- 0.61 1.85 +/- 0.66 11.02 +/- 1.54 9.43 +/- 0.71 0.29 +/- 0.04 10.94 +/- 3.95 21.33 +/- 3.10 10.42 +/- 0.71 0.07 +/- 0.04 4.50 +/- 0.12 4.05 +/- 0.49 1.28 +/- 0.24 7.56 +/- 0.55 2.64 +/- 0.54 10.10 +/- 0.74 0.08 +/- 0.01 4.41 +/- 1.94 0.08 +/- 0.01 1.74 +/- 0.30 7.43 +/- 0.62 0.07 +/- 0.01 0.05 +/- 0.02 3.07 +/- 0.26 0.26 +/- 0.03 2.52 +/- 0.06 1.32 +/- 0.06 1.22 +/- 0.24 1398.00 +/- 125.00 6.69 +/- 2.92 22.32 +/- 2.65 17.52 +/- 0.78 9.88 +/- 0.23 1552.40 +/- 179.20 0.02 +/- 0.01 9.57 +/- 1.88 5.77 +/- 0.40 0.65 +/- 0.27 12.75 +/- 0.79 4.76 +/- 0.14 4.82 +/- 0.61 8.22 +/- 1.24 2.33 +/- 0.53 8.51 +/- 0.78 1.69 +/- 0.64 13.77 +/- 1.77 8.84 +/- 0.68 0.33 +/- 0.06 14.72 +/- 4.16 24.82 +/- 3.10 12.16 +/- 1.06 0.14 +/- 0.05 4.48 +/- 0.12 4.65 +/- 0.55 1.23 +/- 0.17 7.36 +/- 0.40 2.70 +/- 0.40 10.22 +/- 0.50 0.08 +/-0.01 3.90 +/- 1.32 0.08 +/- 0.01 1.77 +/- 0.21 7.39 +/- 0.47 0.07 +/- 0.01 0.05 +/- 0.01 2.92 +/- 0.19 0.25 +/- 0.03 2.52 +/- 0.06 1.36 +/- 0.04 1.27 +/- 0.18 1354.50 +/- 87.33 6.91 +/- 2.13 20.99 +/- 1.87 16.99 +/- 0.58 9.61 +/- 0.30 1443.00 +/- 128.24 0.02 +/- 0.01 8.75 +/- 1.27 5.77 +/- 0.29 0.77 +/- 0.19 12.29 +/- 0.52 4.79 +/- 0.10 4.77 +/- 0.41 8.34 +/- 0.89 2.25 +/- 0.38 8.89 +/- 0.50 1.77 +/- 0.46 12.40 +/-1.17 9.14 +/- 0.49 0.31 +/- 0.04 12.83 +/- 2.87 23.07 +/- 2.19 11.29 +/- 0.64 0.11 +/- 0.03 4.49 +/- 0.09 4.35 +/- 0.37 A5-4
TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result SO-6820, 6821 11/10/2004 K-40 14.41 +/- 1.03 15.01 +/- 1.09 14.71 +/-0.75 S0-6820,6821.
11/10/2004 Sr-90 0.04 +/-0.02 0.07 +/- 0.02 0.06 +/- 0.02 SWU-7160, 7161 11/3012004 Gr. Beta 4.39 +/- 1.98 3.09 +/- 1.77 3.74 +/- 1.33 MI-7062, 7063 12/1/2004 K-40 1456.00 +/- 124.80 1640.50 +/- 131.40 1548.25 +/- 90.61 MI-7062, 7063 12/1/2004 Sr-90 1.13 +/- 0.41 0.98 +/- 0.43 1.06 +/- 0.30 S-7281,7282 12/5/2004 Cs-137 0.82 +/- 0.15 1.16 +/- 0.20 0.99 +/- 0.12 VE-7343, 7344 12/13/2004 Gr. Beta 5.25 +/- 0.14 5.08 +/- 0.14 5.16 +/- 0.10 VE-7343, 7344 12/13/2004 K-40 4.23 +/- 0.71 4.33 +/- 0.69 4.28 +/- 0.49 MI-7317, 7318 12/14/2004 K-40 1702.80 +/- 129.70 1536.80 +/- 115.10 1619.80 +/- 86.70 WW-7375, 7376 12/1412004 Gr. Beta 14.13 +/- 1.03 15.22 +/- 1.06 14.68 +/- 0.74 SWU-7507, 7508 12/1412004 Gr. Beta 4.48 +/- 0.66 5.31 +/- 0.69 4.89 +/- 0.48 DW-7563,7564 12/27/2004 Gr. Beta 1.88 +/- 0.51 2.34 +/- 0.52 2.11 +/- 0.37 P-7698, 7699 12/27/2004 H-3 246.01 +/- 95.00 259.06 +/- 95.51 252.53 +/- 67.35 AP-7741, 7742 12/28/2004 Be-7 0.06 +/- 0.02 0.05 +/- 0.02 0.05 +/- 0.01 Note: Duplicate analyses are performed on every twentieth sample received in-house. Results are not listed for those analyses with activities that measure below the LLD.
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.
A5-5
TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)0.
Concentrationb Known
. Control Lab Code Type Date Analysis Laboratory result Activity Limits' STSO-1022 soil STSO-1022 soil STSO-1022 soil STSO-1022 soil STSO-1022 soil STSO-1022 soil STSO-1022 soil STSO-1022 d I soil STSO-1022 d1s5 0 jl STSO-1022 d I 5 0ol STSO-1022 soil.
05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 Am-241 Co-57 Co-60 Cs-134 Cs-137 K-40 Ni-63 Tc-99 U-233/4 U-238 Zn-65 65.90 +/- 4.50 388.90 +/- 4.00 524.80 +/- 7.10 403.40 +/- 4.60 829.10 +/- 7.60 620.60 +/- 29.50 254.80 +/- 8.40 59.00 +/- 6.00 24.70 +/- 3.60 24.20 +/- 3.50 743.00 +/- 13.10 66.97 +/- 6.70 399.60 +/- 40.00 518.00 +/- 51.80 414.40 +/-41.40 836.20 +/- 83.62 604.00 +/- 60.40 357.05 +/- 35.70 117.66 +/-11.78 37.00 +/- 3.70 38.85 +/- 3.90 699.30 +/- 69.90 46.88 - 87.06 279.72 - 519.48 362.60 - 673.40 290.08 - 538.72 585.34 - 1088.00 422.80 - 785.20 249.94 -464.17 82.36 - 152.96 25.90 -48.40 27.20 - 50.51 489.51 - 909.09 STAP-1023 Air Filter STAP-1023 Air Filter STAP-1 024 Air Filter STAP-1 024 Air Filter STAP-1024 Air Filter STAP-1 024 9 Air Filter STAP-1 024 Air Filter STAP-1024 Air Filter STAP-1 024 Air Filter STAP-1 024 Air Filter STAP-1 024 Air Filter STAP-1 024 Air Filter STAP-1 024 Air Filter STAP-1024 Air Filter 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 05/01104 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 Gr. Alpha Gr. Beta Am-241 Co-57 Co-60 Cs-1 34 Cs-137 Mn-54 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Zn-65 0.06 +/- 0.02 1.37 +/- 0.08 0.08 +/- 0.03 2.07 +/- 0.06 2.11 +/- 0.08 1.78 +/- 0.08 1.76 +/- 0.08 2.84 +/- 0.11 0.12 +/- 0.01 0.08 +/- 0.01 0.66 +/- 0.19 0.23 +/- 0.03 0.23 +/- 0.03 3.90 +/- 0.22 0.40 +/- 0.04 1.20 +/- 0.12 0.10 +/- 0.01 2.40 +/- 0.24 2.30 +/- 0.23 2.90 +/- 0.29 2.00 +/- 0.20 3.00 +/- 0.30 0.13 +/- 0.01 0.09 +/- 0.01 0.80 +/- 0.08 0.21 +/- 0.02 0.22 +/- 0.02 4.00 +/- 0.40 0.00 - 0.80 0.60 - 1.80 0.07 - 0.13 1.68 - 3.12 1.61 -2.99 2.03 - 3.77 1.40 - 2.60 2.10 - 3.90 0.09 - 0.17 0.06 - 0.12 0.56 -1.04 0.15 - 0.27 0.15 - 0.29 2.80 - 5.20 STW-1026 STW-1026 STW-1026 STW-1026 STW-1026 STW-1026 STW-1026 STW-1026 STW-1026 STW-1026 STW-1026 STW-1026 STW-1026 water water water water water water water water water water water water water 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 05/01/04 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 0.56 +/- 0.07 184.10 +/- 13.50 164.40 +/- 11.70 201.10 +/- 14.00 245.50 +/- 15.80 37.60 +/- 25.30 76.50 +/- 5.40 272.10 +/- 17.50 94.40 +/- 3.20 1.11 +/- 0.09 0.01 +/- 0.01 6.20 +/- 1.10 10.70 +/- 1.00 0.60 +/- 0.06 185.00 +/- 18.50 163.00 +/- 16.30 208.00 +/- 20.80 250.00 +/- 25.00 33.00 +/- 3.30 83.00 +/- 8.30 267.00 +/- 26.70 100.00 +/- 10.00 1.20 +/- 0.12 0.00 +/- 0.00 7.00 +/- 0.70 10.00 +/- 1.00 0.42 - 0.78 129.50 - 240.50 114.10 - 211.90 145.60 - 270.40 175.00 - 325.00 23.10 - 42.90 58.10 - 107.90 186.90 - 347.10 70.00 - 130.00 0.84 - 1.56 0.00 - 0.10 4.90 - 9.10 7.00 - 13.00 A6-1
TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)a.
Concentrationb Known Control Lab Code Type Date Analysis Laboratory result Activity Limitsc STW-1026 water 05/01/04 U-233/4 0.14 +/- 0.02 0.12 +/- 0.01 0.08 - 0.16 STW-1026 water 05/01/04 U-238 0.94 +/- 0.05 0.90 +/- 0.09 0.63 - 1.17 STW-1026 water 05/01/04 Zn-65 219.60 +/- 27.90 208.00 +/- 20.80 145.60 -270.40 STW-1027 water 05/01/04 Gr. Alpha 1.20 +/- 0.10 1.20 +/- 0.12 0.00 -2.40 STW-1027 water 05/01/04 Gr. Beta 4.30 +/- 0.10 4.10 +/- 0.41 2.05 - 6.15 Results obtained by Environmental, Inc. Midwest Laboratory as a participant in the Department of Energy's Mixed Analyte Performance Evaluation Program, Idaho Operations office, Idaho Falls, Idaho bAll results are In Bq/kg or Bq/L as requested by the Department of Energy.
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.
d The cause of the deviation seems to be incomplete dissolution of the sample.
e A spiked soil sample was prepared. Known activity; 32.98 pCVg; laboratory result 33.47 pCVg.
'The sample was reanalyzed with the same results. Investigation Is In progress.
g Based on the results of gamma emitting isotopes (Cs-1 37 and Co-60), the filter geometry appears to be biased by -10%. Addition of the summation peak at 1400 KeV results In a recalculation of 2.12 +/- 0.15 Bq/sample.
A6-2
TABLE A-7. Environmental Measurements Laboratory Quality Assessment Program (EML)
Concentrationa EML Control Lab Code Type Date Analysis Laboratory results Resultb Limitsc STW-1009 STW-1009 STW-1009 STW-1009 STW-1009 STW-1009 STW-1009 STW-1009 water water water water water water water water 03101/04 03101/04 03101104 03101/04 03101/04 03101/04 03/01104 03/01/04 Am-241 Co-60 Cs-137 H-3 Pu-238 Pu-239/40 Sr-90 Uranium 1.21 +/- 0.02 152.30 +/- 0.30 50.40 +/- 0.90 263.50 +/- 10.00 1.03 +/- 0.04 2.90 +/- 0.10 5.20 +/- 0.30 4.35 +/- 0.21 1.31 163.20 51.95 186.60 1.10 3.08 4.76 4.62 0.66 - 1.56 0.87 -1.17 0.90 - 1.25 0.69 - 1.91 0.68 - 1.33 0.62 - 1.38 0.73 - 1.65 0.40 - 1.45 STW-1010 water STW-1010 water 03/01/04 Gr. Alpha 208.00 i 20.70 03101/04 Gr. Beta 1063.00 +/- 27.00 STSO-1 011 STSO-1011 STSO-1011 STSO-1 011 STSO-1011 STSO-1011 Soil Soil Soil Soil Soil Soil 03/01/04 03101/04 03/01/04 03/01/04 03/01/04 03101/04 Am-241 Cs-137 K-40 Pu-239/40 Sr-90 Uranium 14.10 +/- 4.30 1292.00 +/- 13.00 563.00 +/- 83.00 20.70 +/- 1.10 72.10 +/- 5.80 139.10 +/- 10.20 326.00 1170.00 13.00 1323.00 539.00 22.82 51.00 180.22 0.55 - 1.31 0.75 - 1.65 0.52 - 2.41 0.74 - 1.40 0.70 - 1.59 0.62 - 1.99 0.58 - 2.96 0.27 - 1.48 STVE-1012 STVE-1012 STVE-1012 STVE-1012 STVE-1 012 STVE-1012 Vegetation Vegetation Vegetation Vegetation Vegetation Vegetation 03101/04 03/01/04 03/01/04 03/01/04 03101/04 03101/04 Am-241 Co-60 Cs-1 37 K-40 Pu-239/40 Sr-90 4.50 +/- 0.20 14.10 +/- 0.40 573.90 +/- 6.00 709.00 +/- 19.30 6.60 +/- 0.50 766.50 +/- 51.30 4.93 14.47 584.67 720.00 6.81 734.00 0.58 - 2.86 0.64 - 1.49 0.75 - 1.48 0.45 - 1.51 0.60 - 1.98 0.50 - 1.37 STAP-1013 STAP-1013 STAP-1013 d STAP-1013 STAP-1013 STAP-1013 STAP-1013 STAP-1013 Air Filter Air Filter Air Filter Air Filter Air Filter Air Filter Air Filter Air Filter 03/01/04 03101/04 03/01/04 03101/04 03/01/04 03/01/04 03/01/04 03/01/04 Am-241 Co-60 Cs-134 Cs-137 Pu-238 Pu-239140 Sr-90 Uranium 0.11 +/- 0.01 30.90 +/- 1.08 12.30 +/- 1.30 24.90 +/- 0.60 0.04 +/- 0.01 0.17 +/- 0.02 1.80 +/- 0.20 0.17 +/- 0.01 0.10 35.40 18.20 26.40 0.04 0.16 1.76 0.17 0.62 - 1.93 0.74 - 1.25 0.70 -1.21 0.72 - 1.32 0.61 - 1.55 0.67 - 1.58 0.62 - 2.26 0.79 - 2.88 STAP-1014 Air Filter STAP-1014 Air Filter 03/01/04 Gr. Alpha 03/01/04 Gr. Beta 1.09 +/- 0.06 2.68 +/- 0.05 1.20 2.85 0.82 - 1.58 0.75 - 1.94
- Results are reported In Bq/L with the following exceptions: Air Filters (Bq/Filter), Soil and Vegetation (Bqlkg).
b The EML result listed Is the mean of replicate determinations for each nuclide +/- the standard error of the mean.
c Control limits are reported by EML as the ratio of Reported Value / EML value.
d Probable effect of summation peaks and slight difference In filter geometry.
A7-1
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 i s where:
x = value of the measurement; s = 2s counting uncertainty (corresponding to the 95% confidence level).
In cases where the activity is less than the lower limit of detection L, it is reported as: <L, where L = the lower limit of detection based on 4.66s uncertainty for a background sample.
3.0. Duplicate analyses 3.1 Individual results: For two analysis results; x1 +/-s1 and X2 i s2 Reported result:
x i s; where x = (1/2) (x (1/2)
S 3.2.
Individual results:
<LI, '2 Reported result: 4L, where L = lower of Li and L2 3.3.
Individual results:
x +/- s, 4 Reported result:
x +/- s if x AL; 4 otherwise.
4.0. Computation of Averages and Standard Deviations 4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements over the period averaged; for exampLe, an annual standard deviation would not be the average of quarterly standard deviations. The average x and standard deviation s of a set of n numbers x1, x2... xn are defined as follows:
X Ex S=
n-1 4.2 Values below the highest lower limit of detection are not included in the average.
4.3 If all values in the averaging group are less than the highest LLD, the highest LLD is reported.
4.4 If all but one of the values are less than the highest LLD, the single value x and associated two sigma error is reported.
4.5 In rounding off, the following rules are followed:
4.5.1. If the number following those to be retained is less than 5; the number is dropped, and the retained number s are kept unchanged. As an example, 11.443 is rounded off to 11.44.
4.5.2. If the number following those to be retained Is equal to or greater than 5, the number Is dropped and the last retained number Is raised by 1. As an example, 11.445 Is rounded off to 11.45.
B-2
APPENDIX C Maximum Permissible Concentrations of Radioactivity in Air and Water Above Background in Unrestricted Areas C-I
Table C-1.
Maximum permissible concentrations of radioactivity in air and water above natural background in unrestricted areasa.
Air (pCUm3)
Water (pCVL-Gross alpha I x 10-3 Strontium-89 8,000 Gross beta I
Strontium-90 500 lodine-131b 2.8 x 10-1 Cesium-137 1,000 Barium-140 8,000 Iodine-131 1,000 Potassium-400 4,000 Gross alpha 2
Gross beta 10 Tritium I x 106 a Taken from Table 2 of Appendix B to Code of Federal Regulations Title 10, Part 20, and appropriate footnotes.
Concentrations may be averaged over a period not greater than one year.
b Value adjusted by a factor of 700 to reduce the dose resulting from the air-grass-cow-milk-child pathway.
c A natural radionuclide.
C-2
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