L-MT-12-042, Submittal of 2011 Annual Radiological Environmental Operating Report
| ML12135A041 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 05/10/2012 |
| From: | O'Connor T Xcel Energy, Northern States Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-MT-12-042 | |
| Download: ML12135A041 (71) | |
Text
&XcelEnergy Monticello Nuclear Generating Plant 2807 W County Road 75 Monticello, MN 55362 May 10, 2012 L-MT-12-042 Technical Specification 5.6.1 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket 50-263 Renewed Facility Operating License No. DPR-22 2011 Annual Radiological Environmental Operating Report In accordance with the Monticello Nuclear Generating Plant Technical Specification 5.6.1, the Northern States Power Company, a Minnesota corporation (NSPM), doing business as Xcel Energy, is submitting the Annual Radiological Environmental Operating Report for the year 2011.
Summary of Commitments commitments and no revisions to existing commitments.
/[imo~t J O'Connbr Site '//c,* President, Monticello Nuclear Generating Plant Norteefn States Power Company - Minnesota Enclosure cc: Administrator, Region III, USNRC Project Manager, Monticello, USNRC Resident Inspector, Monticello, USNRC Minnesota Department of Commerce
ENCLOSURE1 RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT JANUARY 1 - DECEMBER 31, 2011 68 pages follow
Environmental, Inc.
'7kWf AIIMidwest Laboratory 700 Landwethr Road - North~brook. IL 60062-2310 phone (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, 2011 Prepared under Contract by ENVIRONMENTAL, Inc.
Midwest Laboratory Project No. 8010 Approved:
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 Northern States Power Co. -Minnesota for XCEL Energy Corporation. This report was prepared by Environmental, Inc., Midwest Laboratory.
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TABLE OF CONTENTS No. Page P re fa c e .............................................................................................................................
Lis t o f T a b le s ...................................................................................................................... iv Lis t o f F igu re s ..................................................................................................................... v
1.0 INTRODUCTION
................................................................................................................ 1 2 .0 S U MM A R Y .......................................................................................................................... 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 FIG UR ES AND TA BLES ............................................................................................... 12 6 .0 R E F E R E N C E S .................................................................................................................. 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 E Ground Water Monitoring Well Samples ......................................................................... E-1 iii
LIST OF TABLES No. Title Page 5.1 Sample Collection and Analysis Program ........... ;.................................................... 13 5.2 Sampling Locations .................................................................................................... 14 5.3 Missed Collections and Analyses ............................................................................. 17 5.4. Radiation Environmental Monitoring Program Summary ......................................... 20 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 ............................................................................................. A4-1 A-5 In-house "Duplicate" Samples .................................................................................... A5-1 A-6 Department of Energy MAPEP comparison results ...................................................... A6-1 A-7 Environmental Resources Associates, Crosscheck Program Results (EML study replacement) .................................................................................. 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 Appendix E E-1 Sample Collection and Analysis Program, Ground Water .............................................. E-6 E-2 Sampling Locations for Ground Water Monitoring Wells ............................................... E-6 E-3 Ground Water Monitoring Program Summary ................................................................ E-7 iv
LIST OF FIGURES No. Title Page 5-1 Offsite Ambient Radiation (TLDs), inner versus outer ring locations ..................................... 18 5-2 Airborne Particulates; analysis for gross beta, average-mean of all indicator locations versus control location ......................................................................................... 19 The following figures are located in the Appendices:
Appendix D D-1 Sample collection and analysis program: TLD locations, In n e r R in g ............................................................................................................................... D -2 D-2 Sample collection and analysis program: TLD locations, O ute r R in g ............................................................................................................................. D -3 D-3 Sample collection and analysis program: TLD locations, C o n tro ls ................................................................................................................................... D -4 D-4 Sample collection and analysis program: Radiation Environmental Monitoring Program, Milk sa m p ling lo c a tio ns ........................................................................................................... D -5 D-5 Sample collection and analysis program: Radiation Environmental Monitoring Program, Sludge, Ground water and Shoreline sampling locations ........................................................ D-6 Appendix E E-1 Sample collection and analysis program:
Ground water, On-site monitoring well locations ..................................................................... E-8 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, 2011.
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.
Tabulations 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, 2011a) available at the Monticello Nuclear Generating Piant, Chemistry and Radiation Protection Department.
The Monticello Nuclear Generating Plant is a boiling water reactor with a nominal generating capacity of 600 MWe. It is located on the Mississippi River in Wright County, Minnesota, owned by Xcel Energy Corporation and operated by Northern States Power Co.-Minnesota. 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 2011 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, with the exception of the period from March 17 through May 11, 2011. The detection of iodine-1 31 in charcoal cartridges and milk and slight elevations of Cs-134 and Cs-137 in air particulate composites are consistent with and attributable to radioactive elements released from the Fukushima Daiichi reactors or fuel pools in the aftermath of the March 11, 2011 Japanese earthquake and tsunami.
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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 Generatin'Pl'ant 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-1 31. Most samples are also analyzed for gamma-emitting isotopes with results for the following groups quantified: zirconium-95, cesium-1 37, cerium-1 44, 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.
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.
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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 D/Q sector).
Ambient gamma radiation is monitored at forty locations, using CaSd 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 me~asured quarterly.
Milk sampling from two goat farms (one indicator and one control), was added to the program in the fourth quarter of 2010. Samples are collected monthly from November through April and biweekly during the growing season (May - October), when animals may be on pasture. The samples are analyzed for iodine-131 and gamma-emitting isotopes. In addition, pasture grass and vegetation are collected from locations M-41, M-42 and M-43 (C) and analyzed for iodine-1 31 and other gamma emitting isotopes, as substitute for dairy sampling.
Vegetables, corn and potatoes are collected annually if fields are irrigated by water in which liquid radioactive effluent has been discharged. Analysis is done for gamma-emitting isotopes.
Ground water is monitored by quarterly collections from three off-site locations (one control and two indicators) and one on-site Plant well. To prevent possible groundwater contamination due to plant operations, samples from seventeen on-site monitoring wells are collected and analyzed for tritium and gamma emitting isotopes. The Ground Water Monitoring Program is further described in Appendix E.
Quarterly collections of storm water runoff were added to monitor another possible pathway to the groundwater aquifer. The samples are analyzed for tritium and gamma emitting isotopes (Appendix E).
River water is collected weekly at two locations, one upstream of the plant and one downstream.
Monthly composites are analyzed for gamma-emitting isotopes. Quarterly composites are analyzed for tritium.
Drinking water is collected weekly from the City of Minneapolis water supply, which is taken from the Mississippi River downstream of the Plant. Monthly composites are analyzed for gross beta, iodine-131, and gamma-emitting isotopes. Quarterly composites are analyzed for tritium.
The aquatic environment is also monitored by semi-annual upstream and downstream collections of fish, invertebrates, and shoreline sediments. Shoreline sediment is also collected from one downstream recreational location. All samples are analyzed for gamma-emitting isotopes.
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3.3 Program Execution The Program was executed as described in the preceding section with the following exceptions:
(1) Air Particulates / Air Iodine:
No air particulate / air iodine sample was available from location M-01 for the week ending June 29, 2011. There was no power, due to an open fuse.
No air particulate/air iodine sample was available from location M-03 for the week ending September 14, 2011. Run-time was significantly lower than expected.
(2) Thermoluminescent Dosimeters:
The TLD for location M-05S was missing in the field for the third quarter, 2011.
The TLD for location M-1 B was missing in the field for the fourth quarter, 2011.
(3) Surface Water:
Surface water was not collected at location M-08 during the months of January and February, 2011, due to unsafe ice conditions. The June 14, 2011 sample for composite was damaged in transit.
(4) Well Water:
Well water was not collected at location MW-1 in January, 2011.
The January, 2011 sample collected from MW-12A sample was damaged in transit.
Well water from location MW-1 3A, October 17, 2011, was damaged in transit.
(5) Wilk Milk was not available from locations M-16 and M-17 for January and February, 2011 collections. No milk was available from location M-1 7 after November 9, 2011.
(6) Invertebrates Bottom organisms were not collected in the Spring of 2011, due to high river levels.
Bottom organisms could not be collected from control location M-8 in the Fall of 2011, due to high river levels.
Deviations from the program are summarized in Table 5.3.
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 analyses are performed using high-purity germanium (HPGe) detectors.
Levels of iodine-131 in cabbage and natural vegetation and concentrations of airborne iodine-131 in charcoal samples were determined by gamma spectroscopy.
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3.4 Laboratory Procedures (continued)
Tritium concentrations are determined by liquid scintillation.
Analytical Procedures used by Environmental, Inc. are on file and are available for inspection.
Procedures are based on those prescribed by the Health and Safety Laboratory of the U.S. Dep't of Energy, Edition 28, 1997, U.S. Environmental Protection Agency for Measurement of Radioactivity.in Drinking Water, 1980, and the U.S. Environmental Protection Agency, EERF, Radiochemical Procedures Manual, 1984.
Environmental, Inc., Midwest Laboratory has a comprehensive quality control/quality assurance program designed to assure the reliability of data obtained. Details of the QA Program are presented elsewhere (Environmental, Inc., Midwest Laboratory, 2011). 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 program modifications made for 2011.
3.6 Land Use Census In accordance with the MNGP Chemistry Manual, Procedure 1.05.41, "Annual Land Use Census and Critical Receptor Identification", a land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 ft2 producing fresh leafy vegetables, in each of the 16 meteorological sectors within a distance of 5 miles. The census shall also identify the locations of all milk animals and all 500 ft2 or greater gardens producing broad leaf vegetation in each of the meteorological sectors within a distance of three miles. This census shall be conducted at least once per year between the dates of May 1 and October 31. New locations shall be added to the radiation environmental monitoring program within 30 days and sampling locations having lower calculated doses or a lower dose commitment may be deleted from this monitoring program after October 31 of the year in which the land use census was conducted.
The 2011 land use census was conducted between August 30 and September 7, 2011.
In the WNW and NW sectors, the highest D/Q value for nearest garden increased by greater than 20%. Closer gardens were identified. The highest D/Q locations for nearest resident and milk animal did not change from the 2010 census. No changes to the sampling procedures were required.
The location for critical receptor did not change from the 2010 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 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 The Fukushima Daiichi nuclear accident occurred on March 11, 2011, releasing large amounts of radioactive isotopes into the atmosphere and Pacific Ocean. Positive iodine-131, cesium-134 and cesium-137 activities were detected in environmental background samples from March through May. The accident, rated seven on the International Nuclear Event Scale (INES) compares with Chernobyl, rated level seven, and Three Mile Island rated level five.
There were no atmospheric nuclear tests conducted in the year 2011 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/mn 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-1 37 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 environmental samples collected outside of the Site Protected Area in 2011. The trace levels of strontium-90 and cesium-137, still measurable in soil and sediment samples, are generally attributed to deposition of fallout from previous decades.
Tritium was identified in some groundwater samples collected within the site Protected Area.
Ambient Radiation (TLD's)
Ambient radiation was measured in the general area of the site boundary, at an outer ring 4 - 5 mi.
distant from the Plant, at special interest areas and at .four control locations. The means were similar for both inner and outer rings (14.8 and 14.3 mRem/91 days, respectively). The mean for special interest locations was 14.1 mRem/91 days and the mean for the control locations was 15.5 mRem/91 days. Dose rates measured at the inner and outer ring locations were similar to those observed from 1996 through 2010 and are tabulated below. No plant effect on ambient gamma radiation is indicated(Figure 5-1).
Year Inner Rinq Outer Ring Dose rate rnRem/91 days) 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 2006 16.5 15.6 2007 16.1 15.1 2008 15.2 14.6 2009 14.9 14.4 2010 14.7 14.3 2011 14.8 14.3 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 3 in airborne particulates were identical at both indicator and control locations ( 0.026 pCi/m ), similar to levels observed from 1996 through 2010. The results are tabulated below.
Year Indicators Control
.3 Concentration (p~i/m) 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 2006 0.024 0.025 2007 0.027 0.028 2008 0.028 0.029 2009 0.029 0.030 2010 0.026 0.026 2011 0.029 0.027 Average annual gross beta concentrations in airborne particulates.
Typically, the highest average readings occur during the months of January and December, and the first and fourth quarters, as observed in 1996 through 2011.
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 ýArnold and AI-Salih, 1955) was detected in all samples, with an average activity of 0.066 pCi/m for all locations. In the second quarter, 2011, traces of Cs-1 34 and Cs-1 37 were detected in air particulates composited from location M-03. Low levels of radiocesium were observed in air particulates throughout the U.S., following the Fukushima event. All other gamma-emitting isotopes were below their respective LLD limits.
Airborne Iodine Following the Fukushima Daiichi accident, measurable radioiodine was detected in weekly collections of activated charcoal cartridges. For the weeks ending March 23, March 30 and April 6, 2011, activity for all locations averaged 0.076, 0.056 and 0.109 pCi/m , respectively. Iodine could still be detected at two locations, M-1 and M-2 for the week ending April 13, 2011 at an average activity of 0.034 pCi/m3. Measurements for the rest of the year were below the required lower limit of detection of 0.030 pCi/m 3 .
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River Water and Drinkino Water Tritium activity measured below the LLD of 500 pCi/L in all samples. Gross beta activity in Minneapolis drinking water averaged 2.2 pCi/L and was similar to average levels observed from 1995 through 2010. Gross beta averages are tabulated below.
Year Gross Beta (pCi/L) _ Year Gross Beta (piL 1996 2.1 _ 2004 2.7 1997 2.3 I 2005 1 2.8 1998 2.4 1 2006 2.1 1999 2.2 i 2007 2.8 2000 2.5 I 2008 2.1 2001 2.5 2009
) 2.3 2002 2.9i 2010 2.9 2003 3.0 2011 2.2____
Average annual concentrations; Gross beta in drinking water.
Comparisons with data reported by the USEPA for Minneapolis drinking water samples collected from 1980 through 2005 indicate that concentrations of these nuclides are remaining fairly constant. Gamma-emitting isotopes were below detection limits in all surface water samples.
There was no indication of a plant effect.
Goat Milk Iodine-131 was detected in milk sampled from locations M-16 and M-17 for the March 30, 2011 collection, at a concentration of 1.5 pCi/L. The activity was also detected in the April and May collections from location M-16 (1.3 and 1.1 pCi/L, respectively. The activity is consistent with releases from Fukushima. All other results were below a detection limit of 0.5 pCi/L in all samples. Cs-137 results were below the LLD level of 5 pCi/L in all samples. No other gamma-emitting isotopes, except naturally-occurring potassium-40, were detected in any milk samples.
In summary, the data for 2011 showed no radiological effects of the plant operation.
Pasture Grass Pasture grass was collected in August and September, 2011. 1-131 concentrations measured below 0.021 pCi/g wet weight in all samples. With the exceptions of naturally-occurring beryllium-7 and potassium-40, no other gamma-emitting isotopes were detected.
Crops Vegetation collection was not required for 2011. No crops within five miles of the plant, were found using irrigation water from the Mississippi River.
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Fish Fish were collected in May and October. Flesh was separated from the bones and analyzed by gamma spectroscopy. Only naturally-occurring potassium-40 was found in the upstream and downstream samples (3.12 and 2.92 pCi/g wet weight, respectively). Other gamma-emitting.
isotopes remained below detection limits. There was no indication of a plant effect.
Invertebrates One sample from downstream location M-09 was obtained in September, 2011. High water prevented further collections. The sample was analyzed by gamma spectroscopy. 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 July and October of 2011 and analyzed for gamma-emitting isotopes. Low levels of cesium-137 were detected in three of four downstream samples, averaging 0.047 pCi/g dry weight. Similar levels of activity and distribution have been observed since 1978, and are indicative of the influence of fallout deposition. Naturally-occurring potassium-40 was also detected. There was no indication of a plant effect.
Ground Water Monitoring Program Monitoring Wells (on-site)
Measurable tritium above 500 pCi/L was detected in 13 of 166 samples collected from seventeen on-site monitoring wells. The activities ranged from 540 to 2,317 pCi/L, similar or lower than concentrations seen in 2010. The highest activities were observed at well MW-9A.
Gamma isotopic measurements were below detection limits.
- Stormwater Run-off (on-site)
Tritium activity was detected in two of the seven stormwater runoff samples submitted for analysis in 2011 and measured 772 and 585 pCi/L. Gamma isotopic results were below detection limits.
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5.0 FIGURES AND TABLES 12
Table 5.1. Sample collection and analysis program, Monticello Nuclear Generating Plant.
Collection Analysis Location Type and Type and Medium No. Codes (and Type) a Frequency b Frequency c Ambient radiation 40 M-01A - M-14A, M-01B - M-16B C/Q Ambient gamma (TLDs) M-01S - M-06S, M-01C - M-04C Airborne Particulates 5 M-1(C), M-2, M-3, M-4, M-5 C/W GB, GS (QC of each location)
Airborne Iodine 5 M-1(C), M-2, M-3, M-4, M-5 C/W 1-131 Milk 2 M-16, M-17 (C) G/M 1-131, GS Pasture grass, Vegetation d 3 M-41, M-42, M-43(C) 3x/year GS 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)
Well water 4 M-10(C), M-11, M-12, M-27, M-43(C) G/Q H-3, GS On-site monitoring wells 17 M-33 to M-40, M-44 to M-52 Edible cultivated cropse -
Leafy Vegetable 2 M-27, Available Producer (C) G/A 1-131 Com 1 M-19 G/A GS Potatoes 1 M-21 G/A GS Fish 2 M-8(C), M-9 G/SA GS (one species, edible portion)
Periphyton or invertebrates 2 M-8(C), M-9 G/SA GS Shoreline sediment 3 M-8(C), M-9, M-15 G/SA GS a Location codes are defined in Table 5.2. Control stations are indicated by (C). All other stations are indicators.
b Collection type is coded as follows: C/ = continuous, G/ = grab. Collection frequency is coded as follows:
W= weekly, M = monthly, Q = quarterly, SA = semiannually, A = annually.
CAnalysis 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, oC = quarterly composite.
d Pasture grass and vegetation collections added to supplement dairy sampling.
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 Code Type a Collection Site Sample Type b Direction from Reactor M-1 Air Station M-1 AP, Al 11.0 mi @ 307°/NW M-2 Air Station M-2 AP, Al 0.8 mi @ 140°/SE M-3 Air Station M-3 AP, Al 0.6 mi @ 104°/ESE M-4 Air Station M-4 AP, Al 0.8 mi @ 147°/SSE M-5 Air Station M-5 AP, Al 2.6 mi @ 134 0 /SE M-8 Upstream of Plant Intake SW, SS, B0, F < 1000' upstream M-9 Downstream of Plant Discharge SW, SS, BO, F < 1000' downstream M-10 Campbell Farm WW 10.6 mi @ 357°1N M-11 City of Monticello WW 3.3 mi @ 127°/SE M-12 Plant Well #1 WW 0.26 mi @ 252°/WSW M-14 City of Minneapolis DW 37.0 mi @ 132°/SE M-15 Montissippi Park SS 1.27 mi @ 114°/ESE M-16 Kitzman Farm M 3.0 mi @ 165°'SSE M-17 Greninger Farm M 7.8 mi @ 250°/WSW M-19 River Irrigated Corn Field VE M-21 River Irrigated Potato Field c VE M-27 Wise residence (Highest D/Q Garden) VE, WW 0.64 mi @ 207°/SSW
- a. Available Producer' VE > 10.0 mi.
M-33 Monitoring Well #1 WW 593' @ 299°/WNW M-34 Monitoring Well #2 WW 749' @ 301 '[WNW M-35 Monitoring Well #3 WW 770' @ 304°/NW M-36 Monitoring Well #4 WW 0.1 mi @ 25°/NNE M-37 Monitoring Well #5 WW 0.1 mi @ 253°/WSW M-38 Monitoring Well #6 WW 229' @ 228°/SW M-39 Monitoring Well #7 WW 0.2 mi @ 66°/ENE M-40 Monitoring Well #8 WW 0.3 mi @ 150°/SSE M-41 Training Center VE 0.8 mi @ 151°/SSE M-42 Biology Station Road VE 0.6 mi @ 134°/SE M-43 Imholte Farm VE, WW 12.3 mi @ 313°/NW M-44 Monitoring Well #9 WW 0.1 mi @ 310°/NW M-45 Monitoring Well #10 WW 0.1 mi @ 292°/WNW M-46 Monitoring Well #11 WW 0.1 mi @ 283°/WNW M-47 Monitoring Well #12A WW 0.1 mi @ 330°/NW M-48 Monitoring Well #12B WW 0.1 mi @ 326°/NW M-49 Monitoring Well #13A WW 0.12 mi @ 316°/NW M-50 Monitoring Well #13B WW 0.12 mi @ 316°/NW M-51 Monitoring Well #98 WW 0.1 mi @ 310°/NW M-52 Monitoring Well #14 WW 0.17 mi @ 306°/NW Storm water Runoff 0.1 mi @ 27°/NE 14
Table 5.2. Sampling locations, Monticello Nuclear Generating Plant.
Distance and Code Typea Collection Site Sample Typeb Direction from Reactor General Area of the Site Boundary M-01A Sherburne Ave. So. TLD 0.75 mi @ 353°/N M-02A Sherburne Ave. So. TLD 0.79 mi @ 23°/NNE M-03A Sherburne Ave. So. TLD, 1.29 mi @ 55°/NE M-04A Biology Station Road TLD 0.5 mi @ 86°/E M-05A Biology Station Road TLD 0.48 mi @ 118°/ESE M-06A Biology Station Road TLD 0.54 mi @ 135°/SE M-07A County Road 75 TLD 0.5 mi @ 155°/SSE M-08A County Road 75 TLD 0.48 mi @ 1720/S M-09A County Road 75 TLD 0.38 mi @ 209°/SSW M-10A County Road 75 TLD 0.38 mi @ 226°/SW M-1 1A County Road 75 TLD 0.4 mi @ 239°/WSW M-12A County Road 75 TLD 0.5 mi @ 262°/W M-13A North Boundary Road TLD 0.89 mi @ 324°/NW M-14A North Boundary Road TLD 0.78 mi @ 334°/NNW Approximately 4 to 5 miles Distant from the Plant M-01B Sherco #1 Air Station TLD 4.66 mi @ 02*/N M-02B County Road 11 TLD 4.4 mi @ 18°/NNE M-03B County Road 73 & 81 TLD 4.3 mi @ 51°/NE M-04B County Road 73 (196th St.) TLD 4.2 mi @ 67°/ENE M-05B City of Big Lake TLD 4.3 mi @ 89'/E M-06B County Road 14 and 196th St. TLD 4.3 mi @ 117°/ESE M-07B Monte Industrial Drive TLD 4.3 mi @ 136°/SE M-08B Residence, Hwy 25 & Davidson Ave. TLD 4.6 mi @ 162°/SSE M-09B Weinand Farm TLD 4.7 mi @ 178°/S M-10B Reisewitz Farm, Acacia Ave. TLD 4.2 mi @ 204°/SSW M-11B Vanlith Farm, 97th Ave. TLD 4.0 mi @ 228°/SW M-12B Lake Maria State Park TLD 4.2 mi @ 254°ANSW M-13B Bridgewater Station TLD 4.1 mi @ 270°/W M-14B Anderson Residence, Cty Rd. 111 TLD 4.3 mi @ 289°/WNW M-15B Red Oak Wild Bird Farm TLD 4.3 mi @ 309°/NW M-16B Sand Plain Research Farm TLD 4.4 mi @ 341*/NNW 15
Table 5.2. Sampling locations, Monticello Nuclear Generating Plant.
Distance and Code Type' Collection Site Sample Typeb Direction from Reactor Special Interest Locations M-01S Osowski Fun Market TLD 0.66 mi @ 242/VWSW M-02S Krone Residence TLD 0.5 mi @ 224°/SW M-03S Big Oaks Park TLD 1.53 mi @ 102°/ESE M-04S Pinewood School TLD 2.3 mi @ 131 °/SE M-05S Rivercrest Christian Academy TLD 3.0 mi @ 118°/ESE M-06S Monte Public Works TLD 2.6 mi @ 134°/SE M-01C C Kirchenbauer Farm TLD 11.5 mi @ 323°/NW M-02C C County Roads 4 and 15 TLD 11.2 mi @ 47°/NE M-03C C County Rd 19 and Jason Ave. TLD 11.6 mi @ 130°/SE M-04C C Maple Lake Water Tower TLD 10.3 mi @ 2260/ SW Protected Area ISFSI-1 ISFS1-1 (neutron) and 1-01 (gamma) TLD NE corner of ISFSI ISFSI-2 ISFSI-2 (neutron) and 1-02 (gamma) TLD North side of ISFSI, center ISFSI-3 ISFSI-3 (neutron) and 1-03 (gamma) TLD NW corner of ISFSI ISFSI-4 ISFSI-4 (neutron) and 1-04 (gamma) TLD West side of ISFSI, middle ISFSI-5 ISFSI-5 (neutron) and 1-05 (gamma) TLD West side of ISFSI, at center of array ISFSI-6 ISFSI-6 (neutron) and 1-06 (gamma) TLD SW corner of ISFSI 1SFSI-7 ISFSI-7 (neutron) and 1-07 (gamma) TLD South side of ISFSI, center ISFSI-8 ISFSI-8 (neutron) and 1-08 (gamma) TLD SE corner of ISFSI ISFSI-9 ISFSI-9 (neutron) and 1-09 (gamma) TLD East side of ISFSI, at center of array ISFSI-10 ISFSI-10 (neutron) and 1-10 (gamma) TLD East side of ISFSI, middle ISFSI-11 ISFS1-1 1 (neutron) and I-11 (gamma) TLD OCA fence south, on exit road ISFSI-12 ISFSI-12 (neutron) and 1-12 (gamma) TLD OCA fence middle, on exit road ISFSI-13 ISFSI-13 (neutron) and 1-13 (gamma) TLD OCA fence north, on exit road ISFSI-14 ISFSI-14 (neutron) TLD Posted with TLD M12A ISFSI-15 ISFSI-15 (neutron) .TLD Posted with TLD M10A ISFSI-16 ISFSI-16 (neutron) TLD Posted with TLD M02S Neutron Control A C TLD Posted with TLD M03C Neutron Control B C TLD Posted with TLD M04C Neutron Control C C TLD Posted with TLD M02C Neutron Control D C TLD Posted with TLD M01C "C" denotes control location. All other locations are indicators.
Sample Codes: AP Airborne particulates F Fish Al Airborne Iodine SW River Water BS Bottom (river) sediments SS Shoreline Sediments BO Bottom organisms TLD Thermoluminescent Dosimeter DW Drinking Water VE Vegetation / vegetables WW Well Water c Collected only if the plant discharges radioactive effluent into the river, then only from river irrigated fields.
16
Table 5.3. MISSED COLLECTIONS AND ANALYSES 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 - January Water frozen. None Required SW Gamma M-08 February Water frozen. None Required SW For composite M-08 6/14/2011 Sample damaged in transit. None Required WW Gamma, H-3 MW-1 1/17/2011 Well not sampled, frozen. None Required WW Gamma, H-3 MW-12A 1/17/2011 Container damaged in transit. None Required WW Gamma, H-3 MW-13A 10/17/2011 Container damaged in transit. None Required TLD Gamma M-5S 10/3/2011 TLD missing in field. Replaced, vandalism TLD Gamma M-1B 1/4/2012 TLD missing in field. Replaced, vandalism AP/AI Beta, 1-131 M-1 6/29/2011 No power at sampler. Power restored by utility.
AP/AI Beta, 1-131 M-3 9/14/2011 Elapsed time low. Replaced with spare, repaired affected pump.
MI Gamma, 1-131 M-16, 17 1/31/2011 Milking discontinued until Spring. None Required MI Gamma, 1-131 M-17 12/14/2011 Milking discontinued for the year. None Required BO Gamma M-8, M-9 Spring High water prevented sampling. None Required BO Gamma M-8 Fall High water prevented sampling. None Required 17
Figure 5-1. Offsite Ambient Radiation (TLDs); Inner Ring versus Outer Ring locations.
18
Figure 5-2. Airborne Particulates; analysis for gross beta, average mean of all indicator locations versus control location.
0.035 , 1 -
- Indicators (M-2, 3, 4, 5)
Control (M-1) 0.033 I _ - !
0.031 . ...
0.029 0.027 _ _ -__
0.025 1 , -
0.023 /_ I_
.2 1 0.0219 _
0.019- _ I __ __ _
0.017 _ _1 0.015 L (0 1,.- CO 0 * ,
o Cli C1 N 0 ,. 0D 1 (NC4C4 1
19
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Monticello Nuclear Generating Plant Docket No. 50-263 Location of Facility Wright, Minnesota Reporting Period January-December, 2011
( 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)c Routine (Units) Analysesa Rangec Locationd Rangec Rangec Resultse Direct Radiation TLD (inner Ring, Gamma 56 3.0 14.8 (56/56) M-11A, County Rd 75, 16.3 (4/4) (See Control 0 General Area at (11.2-18.5) 0.4 mi @ 250°/WSW (14.5-18.5) below.)
Site Boundary) mRem/91 days)
TLD (Outer Ring, Gamma 63 3.0 14.3 (63/63) M-07B 15.8 (4/4) (See Control 0 4-5 mi. distant) (11.0-18.6) 4.4 mi @ 135°/SE (14.8-16.9) below.)
mRem/91 days)
TLD (Special Gamma 23 3.0 14.1 (23/23) M-06S, Mont. Pub. Wks. 17.0 (4/4) (See Control 0 Interest Areas) (9.8-18.6) 2.7 mi @ 136°/SE (15.6-18.6) below.)
mRem/91 days)
TLD (Control) Gamma 16 3.0 None M-03C, Rte. 19 & Jason, 16.5 (4/4) 15.5 (16/16) 0 mRem/91 days) 11.6 mi @ 130°/SE (13.6-18.3) (12.1-18.3)
Airborne Pathway Airborne GB 258 0.002 0.029 (207/207) M-4, Air Station 0.030 (52/52) 0.027 (51/51) 0 Particulates (0.010-0.070) 0.8 mi @ 147°/SSE (0.010-0.070) (0.007-0.062)
(pCi/mr)
GS .20 Be-7 0.015 0.067 (16/16) M-3, Air Station 0.070 (4/4) 0.065 (4/4) 0 (0.053-0.093) 0.6 mi @ 104°/ESE (0.061-0.093) (0.056-0.078)
Mn-54 0.0010 < LLD < LLD 0 Co-58 0.0012 < LLD < LLD 0 Co-60 0.0010 < LLD < LLD 0 Zn-65 0.0018 < LLD < LLD 0 Zr-Nb-95 0.0014 < LLD < LLD 0 Ru-103 0.0013 < LLD < LLD 0 Ru-106 0.0098 < LLD < LLD 0 Cs-134 0.0011 0.0013 (1/16) M-3, Air Station < LLD 0 0.6 mi @ 104°/ESE Cs-137 0.0010 0.0014 (1/16) M-3, Air Station < LLD 0 0.6 mi @ 104°/ESE Ba-La-140 0.0035 .< LLD .< LLD 0 Ce-141 0.0023 < LLD < LLD 0 Ce-144 0.0063 < LLD < LLD 0 Airborne Iodine 1-131 258 0.03 0.077 (13/207) M-4, Air Station 0.098 (3/52) 0.067 (4/51) 0 (pCi/mr) (0.036-0.134) 0.8 mi @ 147°/SSE (0.061-0.134) (0.031-0.112) 20
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Monticello Nuclear Generating Plant Docket No. 50-263 Location of Facility Wright, Minnesota Reporting Period January-December, 2011
( 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)cr Routine (Units) Analysesa Rangec Locationd Rangec Range' Resultse Waterborne Pathway River Water (pCi/L) H-3 8 500 < LLD < LLD 0 GS 22 Mn-54 10 < LLD <LLD 0 Fe-59 30 < LLD < LLD 0 Co-58 10 .< LLD < LLD 0 Co-60 10 < LLD < LLD 0 Zn-65 30 < LLD <LLD 0 Zr-Nb-95 15 < LLD <LLD 0 Cs-134 10 < LLD < LLD 0 Cs-137 10. < LLD <LLD 0 Ba-La-140 15 < LLD < LLD 0 Ce-144 43 < LLD - LLD 0 Drinking Water GB 12 1.0 2.2 (12/12) M-14, Minneapolis 2.2 (12/12) None 0 (pCi/L) (1.0-3.0) 37.0 mi. @ 132° /SE (1.0-3.0) 1-131 12 1.0 < LLD None 0 H-3 4 500 < LLD None 0 GS 12 Mn-54 10 < LLD None 0 Fe-59 30 < LLD None 0 Co-58 10 < LLD None 0 Co-60 10 < LLD None 0 Zn-65 30 < LLD None 0 Zr-Nb-95 15 < LLD None 0 Cs-134 10 < LLD None 0 Cs-137 10 < LLD None 0 Ba-La-140 15 < LLD None 0 Ce-144 27 < LLD None 0 Well Water H-3 16 500 < LLD < LLD 0 (pCi/L) GS 16 Mn-54 10 < LLD < LLD 0 Fe-59 30 < LLD < LLD 0 Co-58 10 < LLD < LLD 0 Co-60 10 < LLD < LLD 0 Zn-65 30 < LLD < LLD 0 Zr-Nb-95 15 < LLD < LLD 0 Cs-134 10 < LLD < LLD 0 Cs-137 10 < LLD < LLD 0 Ba-La-140 15 < LLD < LLD 0 Ce-144 46 < LLD < LLD 0 21
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Monticello Nuclear Generating Plant Docket No. 50-263 Location of Facility Wright, Minnesota Reporting Period January-December, 2011
( 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)' Mean (F)c Routine (Units) Analysesa Rangec Locationd Rangec Rangec Resultse Waterborne Pathway Invertebrates GS 1 (pCi/g wet) Be-7 0.33 < LLD none 0 K-40 0.65 < LLD none 0 Mn-54 0.024 " LLD none 0 Fe-59 0.075 < LLD none 0 Co-58 0.036 < LLD none 0 Co-60 0.024 < LLD none 0 Zn-65 0.057 < LLD none 0 Zr-Nb-95 0.044 < LLD none 0 Ru-103 0.051 < LLD none 0 Ru-106 0.31 < LLD none 0 Cs-134 0.036 < LLD none 0 Cs-137 0.040 < LLD none 0 Ba-La-140 0.072 < LLD none 0 Ce-144 0.12 < LLD none 0 Shoreline GS 6 Sediments Be-7 0.27 < LLD < LLD 0 (pCi/g dry)
K-40 0.10 10.30(4/4) M-09, Downstream 10.75 (2/2) 10.50 (2/2) 0 (9.78-11.35)
- 1000' of discharge (10.16-11.35) (9.51-11.48)
Mn-54 0.022 < LLD < LLD 0 Fe-59 0.068 < LLD < LLD 0 Co-58 0.021 < LLD < LLD 0 Co-60 0.018 < LLD < LLD 0 Zn-65 0.042 < LLD < LLD 0 Nb-95 0.038 < LLD < LLD 0 Zr-95 0.048 < LLD < LLD 0 Ru-103 0.027 < LLD " LLD 0 Ru-106 0.16 < LLD " LLD 0 Cs-134 0.016 < LLD < LLD 0 Cs-137 0.015 0.047 (3/4) M-09, Downstream 0.065 (2/2) " LLD 0 (0.028-0.091)
- 1000' of discharge (0.040-0.091)
Ba-La-140 0.064 < LLD < LLD 0 Ce-144 0.14 < LLD < LLD 0 22
Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Monticello Nuclear Generating Plant Docket No. 50-263 Location of Facility Wright, Minnesota ) Reporting Period January-December, 2011 County, State
(( 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)c Routine (Units) Analysesa Rangec Locationd Rangec Rangec Resultse Ingestion Pathway Milk (pCi/L) 1-131 33 0.5 < LLD - < LLD 0 GS 33 K-40 200 1821 (16/16) M-16, Kitzman 1821 (16 /16) 1818 (17/17) 0 (1629-1994) 3.0 mi @ 165°/SSE (1629-1994) (1655-1922)
Cs-134 5 < LLD < LLD 0 Cs-137 5 < LLD < LLD 0 Ba-La-140 5 <LLD < LLD 0 Vegetation GS 9 (Pasture Grass, Mn-54 0.011 < LLD < LLD 0 Weeds, Leaves) Fe-59 0.027 '< LLD < LLD 0 Co-58 0.012 < LLD < LLD .0 (pCi/gwet) Co-60 0.009 < LLD < LLD 0 Zn-65 0.035 < LLD < LLD 0 Nb-95 0.013 < LLD < LLD 0 1-131 0.021 < LLD < LLD 0 Cs-134 0.013 < LLD < LLD 0 Cs-1 37 0.014 < LLD < LLD 0 Fish GS 10 (pCi/g wet) K-40 0.10 3.12 (5/5) M-09, Downstream 3.12 (5/5) 2.92 (5/5) 0 (2.55-3.58) < 1000' of discharge (2.55-3.58) (2.74-3.21)
Mn-54 0.021 < LLD < LLD 0 Fe-59 0.062 < LLD < LLD 0 Co-58 0.028 < LLD < LLD 0 Co-60 0.025 < LLD < LLD 0 Zn-65 0.033 < LLD < LLD 0 Zr-Nb-95 0.029 < LLD < LLD 0 Cs-134 0.024 < LLD < LLD 0 Cs-137 0.028 < LLD < LLD 0 Ba-La-140 0.067 < LLD < LLD 0 Ce-144 0.16 < LLD < LLD 0 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).
Locations are specified: (1) by name, and/or station code and (2) by distance (miles) and direction relative to reactor site.
e 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 2012a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January-December, 2000 through 2011.
2001b through 2012b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 2000 through 2011.
1984a to 2000a. (formerly Teledyne Brown Engineering Environmental Services, Midwest Laboratory)
Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 1983 through 1999.
1984b to 2000b. (formerly Teledyne Brown Engineering Environmental Services, Midwest Laboratory)
Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 1983 through 1999.
1979a to 1983a. (formerly Hazleton Environmental Sciences Corporation) Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 1978 through 1982.
1979b to 1983b. (formerly Hazleton Environmental Sciences Corporation) Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January -
December, 1978 through 1982.
2009. Quality Assurance Program Manual, Rev. 2, 10 November 2009.
2009. Quality Control Procedures Manual, Rev. 2, 08 July 2009.
2009. Quality Control Program, Rev. 2, 12 November 2009.
Gold, S., H.W. Barkhau, B. Shlein, and B. Kahn, 1964. Measurement of Naturally Occurring Radionuclides in Air, in the Natural Environment, University of Chicago Press, Illinois, 369-382.
National Center for Radiological Health, 1968. Radiological Health and Data Reports, Vol. 9, Number 12, 730-746.
Northern States Power Company.
1969 through 1971. Monticello Nuclear Generating Plant, Environmental Radiation Monitoring Program, Annual Report, June 18, 1968 to December 31, 1968, 1969, 1970. Minneapolis, Minnesota.
1978 through 2008. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1, to December 31, 1977 through 2007.
24
6.0 REFERENCES
CITED (continued)
U.S. Dep't of Energy 1997 HASL-3(0, 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).
__ 2009. RadNet, formerly Environmental Radiation Ambient Monitoring System, Gross Beta in Air, Gross Beta in Drinking Water (MN) 1981- 2005.
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.
___ 2009 to 2012. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2008 through 2011. Minneapolis, Minnesota.
- 2009 to 2012. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2008 through 2011.
Minneapolis, Minnesota.
25
Environmental, Inc.
Midwest Laboratory 700 Landwehr Road - Norfhbfook, IL 60062-2310 phone (847) 564-0700
- tax (047) 564-4517 APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS NOTE: Environmental Inc., Midwest Laboratory participates in intercomparison studies administered by Environmental Resources Associates, and serves as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada. Results are reported in Appendix A.TLD Intercomparison results, in-house spikes, blanks, duplicates and mixed analyte performance evaluation program results are also reported. Appendix A is updated four times a year; the complete Appendix is included in March, June, September and December monthly progress reports only.
January through December, 2011
Appendix A Interlaboratory Comparison Proqram Results Environmental, Inc., Midwest Laboratory has participated in interiaboratory comparison (crosscheck) programs since the formulation of it's quality control program in December 1971. These programs are operated by agencies which supply environmental type samples containing concentrations of radionuclides known to the issuing agency but not to participant laboratories. The purpose of such a program is to provide an independent check on a laboratory's analytical procedures and to alert it of any possible problems.
Participant laboratories measure the concentration of specified radionuclides and report them to the issuing agency. Several months later, the agency reports the known values to the participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used.
Results in Table A-1 were obtained through.participation in the environmental sample crosscheck program administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada.
Table A-2 lists results for thermoluminescent dosimeters (TLDs), via International Intercomparison of Environmental Dosimeters, when available, and internal laboratory testing.
Table A-3 lists results of the analyses on in-house "spiked" samples for the past twelve months. All samples are prepared using NIST traceable sources. Data for previous years available upon request.
Table A-4 lists results of the analyses on in-house "blank" samples for the past twelve months. Data for previous years available upon request.
Table A-5 lists REMP specific analytical results from the in-house "duplicate" program for the past twelve months. Acceptance is based on the difference of the results being less than the sum of the errors.
Complete analytical data for duplicate analyses is available upon request.
The results in Table A-6 were obtained through participation in the Mixed Analyte Performance Evaluation Program.
Results in Table A-7 were obtained through participation in the environmental sample crosscheck program administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurement Laboratory Quality Assessment Program (EML).
Attachment A lists the laboratory precision at the 1 sigma level for various analyses. The acceptance criteria in Table A-3 is set at +/- 2 sigma.
Out-of-limit results are explained directly below the result.
Al
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 g/liter or kg 5% of known value Gross alpha - 20 pCilliter 5.0 pCi/liter
> 20 pCi/liter 25% of known value Gross beta !5100 pCi/liter 5.0 pCi/liter
> 100 pCi/liter 5% of known value Tritium - 4,000 pCi/liter +/- lo =
169.85 x (known)0.933
> 4,000 pCi/liter 10% of known value Radium-226,-228 > 0.1 pCi/liter 15% of known value Plutonium Ž- 0.1 pCi/liter, gram, or sample 10% of known value Iodine-131, -555 pCi/liter 6 pCi/liter Iodine-129b > 55 pCi/liter 10% of known value Uranium-238, -<35 pCi/liter 6 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 Other Analyses b 20% of known value a From EPA publication, "Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.
Laboratory limit.
A2
TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.
Concentration (pCi/L)
Lab Code Date Analysis Laboratory ERA Control Result b Result C Limits Acceptance STW-1243 04/04/11 -Sr-89 68.2 +/- 5.8 63.2 51.1 -71.2 Pass STW-1243 04/04/11 Sr-90 44.3 +/- 2.4 42.5 31.3 - 48.8 Pass STW-1244 04/04/11 Ba-133 69.8 + 3.9 75.3 63.0 - 82.8 Pass STW-1244 04/04/11 Co-60 87.9 + 3.8 88.8 79.9 - 100.0 Pass STW-1244 04/04/11 Cs- 134 69.5 + 3.7 72.9 59.5 - 80.2 Pass STW-1244 04/04/11 Cs-137 77.9 + 5.3 77.0 69.3 - 87.4 Pass STW-1244 04/04/11 Zn-65 105.2 + 8.4 98.9 89.0-118.0 Pass STW-1245 .04/04/11 Gr. Alpha 41.5 +/- 2.3 50.1 26.1 -62.9 Pass STW-1245 04/04/11 Gr. Beta 48.9 +/- 1.8 49.8 33.8 - 56.9 Pass STW-1246 04/04/11 1-131 26.6 +/- 1.7 27.5 22.9 - 32.3 Pass STW-1247 04/04/11 Ra-226 13.2 +/-0.6 12.1 9.0 -14.0 Pass STW-1247 04/04/11 Ra-228 11.2 +/-0.6 11.6 7.6 - 14.3 Pass STW-1247 04/04/11 Uranium 36.4 +/- 0.6 39.8 32.2 - 44.4 Pass STW-1248 04/04/11 H-3 10322 +/-285 10200.0 8870 -11200 Pass STW-1256 10/07/11 Sr-89 68.7 +/- 6.0 69.7 56.9 - 77.9 Pass STW-1256 10/07/11 Sr-90 36.9 +/- 2.4 41.1 30.2 - 47.2 Pass STW-1257 10/07/11 Ba-133 88.2 + 7.8 96.9 81.8 - 106.0 Pass STW-1257 10/07/11 Co-60 116.5 +/- 7.1 119.0 107.0 - 133.0 Pass STW-1257 10/07/1.1 Cs-1 34 38.8 +/- 8.0 33.4 26.3 - 36.7 Fail STW-1257 10/07/11 Cs-1 37 45.6 + 7.3 44.3 39.4 -51.7 Pass STW-1257 10/07/11 Zn-65 84.9 + 15.4 76.8 68.9 - 92.5 Pass STW-1258 10/07/11 Gr. Alpha 35.7 +/- 3.8 53.2 27.8 -66.6 Pass STW-1258 10/07/11 Gr. Beta 36.1 +/- 3.3 45.9 30.9 -53.1 Pass STW-1259 10/07/11 1-131 25.0 +/- 1.1 27.5 22.9 - 32.3 Pass STW-1260 10/07/11 Ra-226 12.2 +/- 0.6 11.6 8.7 - 13.4 Pass STW-1260 10/07/11 Ra-228 11.5 +/- 1.7 10.3 6.7 - 12.8 Pass STW-1260 10/07/11 Uranium 46.6 +/- 0.5 48.6 39.4 - 54.0 Pass STW-1261 10/07/11 H-3 17435 +/-382 17400 15200 -19100 Pass 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.
Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA.
d The sample was reanalyzed. Result of reanalysis was acceptable, 32.9+/- 7.4 pCi/L.
Al-1
TABLE A-2. Thermoluminescent Dosimetry, (TLD, CaSO 4: Dy Cards).
mR Lab Code Date Known Lab Result Control Descrition Value _ 2 sigma Limits Acceptance Environmental, Inc.
2010-2 12113/2010 100 cm. 4.94 4.65 +/- 0.57 3.46 - 6.42 Pass 2010-2 12/13/2010 110 cm. 4.09 3.50 +/- 0.74 2.86 - 5.32 Pass 2010-2 12/13/2010 120 cm. 3.43 2.68 +/- 0.36 2.40 -4.46 Pass 2010-2 12/13/2010 150 cm. 2.2 1.75 +/- 0.42 1.54 -2.86 Pass 2010-2 12/13/2010 180 cm. 1.53 1.32 +/- 0.52 1.07 -1.99 Pass 2010-2 12/13/2010 40 cm. 30.89 38.56 +/- 2.11 21.62 -40.16 Pass 2010-2 12/13/2010 50 cm. 19.77 23.35 +/- 1.82 13.84 -25.70 Pass 2010-2 12/13/2010 60 cm. 13.73 14.53 +/- 1.24 9.61 - 17.85 Pass 2010-2 12/13/2010 60 cm. 13.73 15.84 +/- 1.53 9.61 - 17.85 Pass 2010-2 12/13/2010 80 cm. 7.72 8.33 +/- 0.74 5.40 - 10.04 Pass 2010-2 12/13/2010 90 cm. 6.1 5.93 +/- 0.73 4.27 - 7.93 Pass Environmental, Inc.
2011-1 7/6/2011 100 cm. 6.71 5.64 +/- 0.30 4.70 - 8.72 Pass 2011-1 7/6/2011 110 cm. 5.54 4.60 +/- 0.46 3.88 - 7.20 Pass 2011-1 7/6/2011 120 cm. 4.66 4.68 +/- 0.29 3.26 -6.06 Pass 2011-1 7/6/2011 150 cm. 2.98 2.93 +/- 0.66 2.09 -3.87 Pass 2011-1 7/6/2011 180 cm. 2.07 2.05 +/- 0.18 1.45 -2.69 Pass 2011-1 7/6/2011 40 cm. 41.92 52.36 +/- 3.08 29.34 - 54.50 Pass 2011-1 7/6/2011 45 cm. 33.12 41.83 +/- 3.46 23.18 -43.06 Pass 2011-1 7/6/2011 50 cm. 26.83 28.61 +/- 2.63 18.78 - 34.88 Pass 2011-1 7/6/2011 60 cm. 18.63. 21.00 +/- 1.15 13.04 -24.22 Pass 2011-1 7/6/2011 70 cm. 13.69 13.24 +/- 1.76 9.58 -17.80 Pass 2011-1 7/6/2011 80 cm. 10.48 12.18 +/- 0.65 7.34 -13.62 Pass 2011-1 7/6/2011 90 cm. 8.28 7.95 +/- 0.82 5.80 -10.76 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.
SPW-202 1/17/2011 U-238 4.19 +/- 0.19 4.17 0.00 - 16.17 Pass W-20111 2/1/2011 Ra-226 16.32 +/- 0.47 16.77 11.74 -21.80 Pass W-20711 2/7/2011 Gr. Alpha 23.02 +/- 0.45 20.00 10.00 -30.00 Pass W-20711 2/7/2011 Gr. Beta 46.59 +/- 0.41 45.20 35.20 - 55.20 Pass XWW-331 2/11/2011 Ba-133 144.30 +/- 8.50 144.40 129.96 - 158.84 Pass XWW-331 2/11/2011 Cs-134 22.20 +/- 3.70 21.50 11.50 -31.50 Pass XWW-331 2/11/2011 Cs-137 64.70 +/- 7.40 61.00 51.00 -71.00 Pass XWW-331 2/11/2011 H-3 13399 +/- 334 12538 10030 - 15046 Pass SPAP-567 2/14/2011 Gr. Beta 46.90 +/- 0.11 48.10 28.86 - 67.34 Pass SPAP-569 2/14/2011 Cs-134 7.70 +/- 1.70 7.49 0.00 - 17.49 Pass SPAP-569 2/14/2011 Cs-137 102.47 +/- 3.20 106.79 96.11 -117.47 Pass SPAP-571 2/14/2011 H-3 75815 +/- 542 73230 58584 - 87876 Pass SPW-581 2/15/2011 Cs-134 39.91 +/- 1.38 37.45 27.45 -47.45 Pass SPW-581 2/15/2011 Cs-137 56.28 +/- 2.28 53.39 43.39 - 63.39 Pass SPW-581 2/15/2011 Sr-89 112.92 +/- 5.61 121.42 97.14 -145.70 Pass SPW-581 2/15/2011 Sr-90 47.80 +/- 2.02 42.07 33.66 - 50.48 Pass SPMI-583 2/15/2011 Cs-137 57.04 +/- 2.76 53.39 43.39 - 63.39 Pass SPMI-583 2/1512011 Sr-90 36.27 +/- 1.47 42.07 33.66 - 50.48 Pass SPW-602 2/17/2011 U-238 3.98 +/- 0.19 4.17 0.00 - 16.17 Pass SPW-686 2/25/2011 Ni-63 167.41 +/- 3.05 208.11 145.68 - 270.54 Pass SPF-1113 3/17/2011 Cs-137 2369 +/- 22 2170 1953 -2387 Pass XWW-1602 3/21/2011 Ba-1 33 26.83 +/- 6.35 28.58 18.58 - 38.58 Pass XWW-1602 3/21/2011 Cs-1 34 18.90 +/- 4.06 16.30 6.30 - 26.30 Pass XWW-1602 3/21/2011 Cs-137 33.98 +/- 5.88 30.50 20.50 - 40.50 Pass XWW-1602 3/21/2011 H-3 7348 +/- 248 7617 6094 -9140 Pass XWW-2537 4/4/2011 Ba-133 43.40 +/- 4.26 42.70 32.70 - 52.70 Pass XWW-2537 4/4/2011 Cs-134 13.50 +/- 2.40 11.90 1.90 -21.90 Pass XWW-2537 4/4/2011 Cs-137 68.30 +/- 5.90 60.70 50.70 - 70.70 Pass XWW-2537 4/4/2011 H-3 7134 +/- 257 7234 5787 -8681 Pass SPW-2877 5/3/2011 Ra-228 25.23 +/- 2.48 31.62 22.13 -41.11 Pass SPMI-3167 5/24/2011 Cs-134 33.04 +/- 8.25 34.19 24.19 -44.19 Pass SPMI-3167 5/24/2011 Cs-137 51.53 +/- 8.63 53.06 43.06 - 63.06 Pass SPMI-3167 5/24/2011 Sr-89 90.89 +/- 4.30 93.47 74.78 - 112.16 Pass SPMI-3167 5/24/2011 Sr-90 41.17 +/- 1.53 41.80 33.44 - 50.16 Pass W-52411 5/24/2011 Ra-226 17.90 +/- 0.42 16.80 11.76 -21.84 Pass W-60711 6/7/2011 Gr. Alpha 23.00 +/- 0.49 20.00 10.00 - 30.00 Pass W-60711 6/7/2011 Gr. Beta 43.27 +/- 0.42 45.20 35.20 - 55.20 Pass SPAP-4167 7/7/2011 Cs-134 6.92 +/- 1.45 6.57 0.00 - 16.57 Pass SPAP-4167 7/7/2011 Cs-137 108.02 +/- 2.84 105.80 95.22 - 116.38 Pass SPW-4169 7/7/2011 Cs-134 34.52 +/- 4.79 32.84 22.84 - 42.84 Pass SPW-4169 7/7/2011 Cs-137 58.29 +/- 6.19 52.92 42.92 - 62.92 Pass A3-1
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 SPW-4169 7/7/2011 Sr-89 66.12 +/- 4.18 69.64 55.71 - 83.57 Pass SPW-4169 7/7/2011 Sr-90 41.72 +/- 1.79 41.68 33.34 - 50.02 Pass SPW-4171 7/7/2011 H-3 70582 +/- 767 71646 57317 -85975 Pass SPW-4180 7/7/2011 Tc-99 95.69 +/- 1.65 97.02 67.91 - 126.13 Pass SPW-41821 7/7/2011 Ra-228 32.57 +/- 2.63 30.63 21.44 - 39.82 Pass SPW-4241 7/7/2011 Ni-63 403.01 +/- 4.66 415.20 290.64 - 539.76 Pass SPW-4180 7/8/2011 Tc-99 100.30 +/- 1.75 97.02 67.91 -126.13 Pass SPW-5029 7/29/2011 C-14 3991 +/-17 4739 2843 - 6634 Pass SPW-5031 7/29/2011 Fe-55 13801 +/-331 14895 11916 -17874 Pass W-91411 9/14/2011 Gr. Alpha 21.58 +/- 0.44 20.00 10.00 -30.00 Pass W-91411 9/14/2011 Gr. Beta 43.02 +/- 0.40 45.20 35.20 - 55.20 Pass SPW-91511 9/15/2011 Tc-99 29.92 +/- 1.07 32.34 20.34 -44.34 Pass W-91911 9/19/2011 Ra-226 17.06 +/- 0.42 16.80 11.76 -21.84 Pass W-100711 10/7/2011 Gr. Alpha 22.05 +/- 0.45 20.00 10.00 -30.00 Pass W-100711 10/7/2011 Gr. Beta 45.51 +/- 0.41 45.20 35.20 - 55.20 Pass W-101111 10/11/2011 Ra-226 16.02 +/- 0.40 16.80 11.76 -21.84 Pass XWW-7220 11/17/2011 Ba-133 25.11 +/- 4.36 27.47 17.47 - 37.47 Pass XWW-7220 11/17/2011 Cs-1 34 14.09 +/- 3.11 16.60 6.60 - 26.60 Pass XWW-7220 11/17/2011 Cs-137 35.59 +/- 4.28 29.98 19.98 -39.98 Pass W-113011 11/30/2011 Ra-226 16.12 +/- 0.39 16.80 11.76 -21.84 Pass W-120111 12/1/2011 Gr. Alpha 21.34 +/- 0.43 20.00 10.00 -30.00 Pass W-120111 12/1/2011 Gr. Beta 45.55 +/- 0.41 45.20 35.20 - 55.20 Pass SPW-41823 12/9/2011 Ra-228 26.98 +/- 2.38 29.40 20.58 - 38.22 Pass SPMI-8906 12/22/2011 Cs-134 29.11 +/- 3.52 28.14 18.14 -38.14 Pass SPMI-8906 12/22/2011 Cs-137 58.27 +/- 7.62 52.36 42.36 - 62.36 Pass SPW-8916 12/22/2011 Cs-134 31.74 +/- 3.63 28.14 18.14 -38.14 Pass SPW-8916 12/22/2011 Csr137 56.48 +/- 6.12 52.36 42.36 - 62.36 Pass SPAP-8902 12/23/2011 Gr. Beta 45.72 +/- 0.11 47.11 28.27 -,65.95 Pass SPAP-8904 12/23/2011 Cs-134 5.19 +/- 0.63 5.63 0.00 - 15.63 Pass SPAP-8904 12/23/2011 Cs-137 101.21 +/- 2.55 104.71 94.24 -115.18 Pass SPW-8918 12/23/2011 H-3 136759 +/- 1056 137638 110110 -165166 Pass SPW-8922 12/23/2011 Ni-63 202.21 +/- 3.75 206.88 144.82 - 268.94 Pass SPW-8924 12/23/2011 Tc-99 126.10 +/- 1.86 129.36 90.55 - 168.17 Pass SPF-8926 12/23/2011 Cs-1 34 0.34 +/- 0.01 0.33 0.20 - 0.47 Pass SPF-8926 12/23/2011 Cs-137 2.34 +/- 0.02 2.09 1.25 -2.93 Pass 8 Liquid sample results are reported in pCi/Liter, air filters( pCi/filter), charcoal (pCi/m3), and solid samples (pCi/g).
b Laboratory codes as follows: W (water), MI (milk), AP (air filter), SO (soil), VE (vegetation).
CH (charcoal canister), F (fish), U (urine).
CResults are based on single determinations.
Control limits are established from the precision values listed in Attachment A of this report, adjusted to +/- 2a.
NOTE: For fish, Jello is used for the Spike matrix. For Vegetation, cabbage is used for the Spike matrix.
A3-2
TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)a Lab Code Sample Date Analysisb Laboratory results (4.66a) Acceptance Type LLD ActivityC Criteria (4.66 c)
SPW-202 Water 1/17/2011 U-238 0.10 0.12 +/- 0.12 1 W-20111 Water 2/1/2011 Ra-226 0.04 0.05 +/- 0.03 1
.W-20711 Water 2/7/2011 Gr. Alpha 0.44 -0.02 +/- 0.29 W-20711 Water 2/7/2011 Gr. Beta 0.75 -0.03 +/- 0.53 3.2 SPAP-566 Air Filter 2/14/2011 Gr. Beta 0.64 2.24 +/- 0.61 3.2 SPAP-568 Air Filter 2/14/2011 Cs-134 2.34 100 SPAP-568 Air Filter 2/14/2011 Cs-137 1.56 100 SPAP-570 Air Filter 2/14/2011 H-3 103.20 -49.40 +/- 52.50 200 SPW-580 Water 2/15/2011 Cs-134 2.68 10 SPW-580 Water 2/15/2011 Cs-1 37 2.84 10 SPW-580 Water 2/15/2011 Sr-89 0.73 0.24 +/- 0.57 5 SPW-580 Water 2/15/2011 Sr-90 0.57 0.02 +/- 0.27 1 SPMI-582 Milk 2/15/2011 Cs-134 3.49 10 SPMI-582 Milk 2/15/2011 Cs-137 3.54 10 SPMI-582 Milk 2/15/2011 1-131(G) 4.14 20 SPMI-582 Milk 2/15/2011 Sr-89 0.71 0.16 +/- 0.67 5 SPMI-582 Milk 2/15/2011 Sr-90 0.55 0.59 +/- 0.32 1 SPW-601 Water 2/17/2011 U-238 0.20 0.09 +/- 0.17 1 SPW-685 Water 2/25/2011 Ni-63 1.61 0.05 +/- 0.98 20 SPF-1 112 Fish 3/17/2011 Cs-1 34 6.74 100 SPF-1112 Fish 3/17/2011 Cs-137 5.45 100 BKW-401 11 Water 4/1/2011 1-131 4.16 10 BKW-401 11 Water 4/1/2011 Co-60 3.11 10 BKW-401 11 Water 4/1/2011 Cs-1 34 4.73 10.
BKW-401 11 Water 4/1/2011 Cs-1 37 5.04 10 SPW-2887 Water 5/3/2011 Ra-228 0.72 0.46 +/- 0.39 2 W-52411 Water 5/24/2011 Ra-226 0.04 0.05 +/- 0.03 1 W-60711 Water 6/7/2011 Gr. Alpha 0.51 0.00 +/- 0.36 1 W-60711 Water 6/7/2011 Gr. Beta 1.58 0.38 +/- 1.12 3.2 SPAP-41164 Air Filter 7/7/2011 Gr. Beta 0.72 1.04 +/- 0.48 3.2 SPW-4168 Water 7/7/2011 Cs-134 3.41 10.
SPW-4168 Water 7/7/2011 Cs-137 2.45 10 SPW-4168 Water 7/7/2011 Sr-89 0.72 0.40 +/- 0.50 5 SPW-4168 Water 7/7/2011 Sr-90 0.51 -0.19 +/- 0.21 1 SPW-4171 Water 7/7/2011 H-3 152.00 37.10 +/- 81.80 200 SPW-41811 Water 7/7/2011 Ra-228 0.77 0.51 +/- 0.42 2 A4-1
TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)a Lab Code Sample Date Analysiso Laboratory results (4.66a) Acceptance Type LLD Activityc Criteria (4.66 u)
SPW-4241 Water 7/7/2011 Ni-63 1.70 0.09 +/- 1.03 20 SPW-4179 Water 7/8/2011 Tc-99 1.20 -0.96 +/- 0.71 10 SPW-5028 Water 7/29/2011 C-14 109.80 61.90 +/- 59.20 200 SPW-5031 Water 7/29/2011 Fe-55 140.60 0.00 +/- 85.30 1000 W-91411 Water 9/14/2011 Gr. Alpha 0.48 -0.06 +/- 0.33 1 W-91411 Water 9/1412011 Gr. Beta 0.78 -0.43 +/- 0.53 3.2 SPW-91511 Water 9/15/2011 Tc-99 1.11 -0.62 +/- 0.66 10 W-91911 Water 9/19/2011 Ra-226 0.03 0.04 +/- 0.02 1 W-100711 Water 10/7/2011 Gr. Alpha 0.44 -0.26 +/- 0.28 1 W-100711 Water 10/7/2011 Gr. Beta 0.76 -0.43 +/- 0.52 3.2 W-101111 Water 10/11/2011 Ra-226 0.04 0.05 +/- 0.03 1 W-113011 Water 11/30/2011 Ra-226 0.03 0.04 +/- 0.02 1 W-120111 Water 12/1/2011 Gr. Alpha 0.41 -0.20 +/- 0.27 1 W-120111 Water 12/1/2011 Gr. Beta 0.75 -0.10 +/- 0.53 3.2 SPW-41813 Water 12/9/2011 Ra-228 0.71 0.17 +/- 0.35 2 SPMI-8905 Milk 12/22/2011 Cs-134 3.27 10 SPMI-8905 Milk 12/22/2011 Cs-137 3.38 10 SPMI-8905 Milk 12/22/2011 1-131(G) 2.17 20 SPW-8915 Water 12/22/2011 Cs-134 3.37 10 SPW-8915 Water 12/22/2011 Cs-137 3.45 10 SPW-8915 Water 12/22/2011 1-131(G) 3.38 20 SPAP-8901 Air Filter 12/23/2011 Gr. Beta 0.78 0.50 +/- 0.46 3.2 SPAP-8903 Air Filter 12/23/2011 Cs-1 34 1.65 100 SPAP-8903 Air Filter 12/23/2011 Cs-137 2.41 100 SPW-8917 Water 12/23/2011 H-3 150.20 -3.04 +/- 78.80 200 SPW-8921 Water 12/23/2011 Ni-63 16.92 -4.60 +/- 10.16 20 SPW-8923 Water 12/23/2011 Tc-99 5.66 -5.45 +/- 3.34 10 SPF-8925 Fish 12/23/2011 Cs-1 34 7.15 100 SPF-8925 Fish 12/23/2011 Cs-1 37 9.73 100 a Liquid sample results are reported in pCi/Liter, air filters( pCi/filter), charcoal (pCi/charcoal canister), and solid samples (pCi/kg).
b 1-131(G); iodine-131 as analyzed by gamma spectroscopy.
c Activity reported is a net activity result. For gamma spectroscopic analysis, activity detected below the LLD value is not reported.
A4-2
TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance CF-20, 21 1/3/2011 Be-7 0.24 +/- 0.14 0.34 +0.17 0.29 +/- 0.11 Pass CF-20, 21 1/3/2011 K-40 10.37 +/- 0.43 9.76 +/- 0.68 10.07 +/- 0.40 Pass CF-20, 21 1/3/2011 Sr-90 0.01 +/- 0.01 0.01 +/- 0.01 0.01 +/- 0.00 Pass WW-65, 66 1/6/2011 H-3 321.91 +/- 97.19 345.76 +/- 98.16 333.83 +/- 69.06 Pass BS-165, 166 1/11/2011 Cs-137 0.13 +/- 0.02 0.15 +/- 0.02 0.14 +/- 0.01 Pass BS-165, 166 1/11/2011 H-3 286.00 +/- 80.00 284.00 +/- 80.00 285.00 +/- 56.57 Pass BS-165, 166 1/11/2011 K-40 14.11 +/- 0.52 13.79 +/- 0.60 13.95 +/- 0.40 Pass BS-176, 177 1/11/2011 H-3 391.00 +/- 92.00 332.00 +/- 89.00 361.50 +/- 64.00 Pass BS-176, 177 1/11/2011 K-40 9.06 +/- 0.44 8.28 +/- 0.81 8.67 +/- 0.46 Pass BS-197, 198 1/11/2011 Cs-1 37 0.14 +/- 0.03 0.15 +/- 0.04 .0.15 +/- 0.03 Pass BS-197, 198 1/11/2011 H-3 459.00 +/- 103.00 283.00 +/- 95.00 371.00 +/- 70.06 Pass BS-197, 198 1/11/2011 K-40 14.40 +/- 0.77 14.16 +/- 1.23 14.28 +/- 0.73 Pass WW-358, 359 1/17/2011 H-3 331.44 +/- 93.05 407.65 +/- 95.91 369.55 +/- 66.81 Pass DW-20009, 20010 1/19/2011 Ra-226 3.66 +/- 0.57 2.74 +/- 0.43 3.20 +/- 0.36 Pass DW-20009, 20010 1/19/2011 Ra-228 1.51 +/- 0.64 1.36 +/- 0.60 1.44 +/- 0.44 Pass WW-337, 338 1/25/2011 H-3 21986.00 +/- 402.00 21896.00 +/- 401.00 21941.00 +/- 283.90 Pass W-491, 492 1/27/2011 Ra-226 6.70 +/- 0.50 6.10 +/- 0.50 6.40 +/- 0.35 Pass W-491, 492 1/27/2011 Ra-228 6.60 +/- 1.30 8.40 +/- 1.40 7.50 +/- 0.96 Pass DW-20014, 20015 1/28/2011 Gr. Alpha 1.91 +/- 0.71 2.34 +/- 0.80 2.13 +/- 0.53 Pass SWU-447,448 1/31/2011 Gr, Beta 7.42 +/- 1.17 6.85 +/- 1.11 7.14 +/- 0.81 Pass W-694, 695 2/7/2011 H-3 628.26 +/- 104.30 692.37 +/- 106.89 660.32 +/- 74.67 Pass DW-20022, 20023 2/9/2011 Ra-228 0.71 +/- 0.47 1.13 +/- 0.54 0.92 +/- 0.36 Pass SW-626, 627 2/16/2011 H-3 1268.17 +/- 129.52 1144.65 +/- 125.39 1206.41 +/- 90.14 Pass LW-825, 826 2/24/2011 Gr. Beta 2.65 +/- 0.82 2.45 +/- 0.74 2.55 +/- 0.55 Pass SWT-845, 846 3/1/2011 Gr. Beta 1.11 +/- 0.39 0.80 +/- 0.37 0.96 +/- 0.27 Pass MI-998, 999 3/7/2011 K-40 1760.10 +/- 127.50 1708.50 +/- 131.60 1734.30 +/- 91.62 Pass W-1024, 1025 3/7/2011 H-3 489.83 +/- 101.09 581.39 +/- 105.06 535.61 +/- 72.90 Pass WW-1156, 1157 3/16/2011 Gr. Beta 1.79 +/- 0.78 0.47 +/- 0.66 1.13 +/- 0.51 Pass P- 1198, 1199 3/17/2011 H-3 504.00 +/- 133.00 597.00 +/- 136.00 550.50 +/- 95.11 Pass SW-1434, 1435 3/28/2011 H-3 15523.00 +/- 359.00 15968.00 +/- 364.00 15745.50 +/- 255.63 Pass WW-1588, 1589 3/28/2011 Gr. Beta 1.81 +/- 1.23 2.81 +/- 1.38 2.31 +/- 0.92 Pass SG-1714, 1715 3/28/2011 Gr. Alpha 8.82 +/- 0.81 8.58 +/- 0.74 8.70 +/- 0.55 Pass SG-1714, 1715 3/28/2011 Gr. Beta 13.78 +/- 0.65 12.76 +/- 0.58 13.27 +/- 0.44 Pass AP-1862, 1863 3/28/2011 Be-7 0.09 +/- 0.02 0.08 +/- 0.02 0.08 +/- 0.01 Pass W-2143, 2144 3/28/2011 H-3 536.40 +/- 99.37 466.79 +/- 96.46 501.59 +/- 69.25 Pass AP-2269, 2270 3/28/2011 Be-7 0.07 +/- 0.01 0.08 +/- 0.01 0.07 +/- 0.01 Pass DW-20061, 20062 3/28/2011 Gr. Alpha 2.82 +/- 1.33 3.89 +/- 1.26 3.36 +/- 0.92 Pass SWU-1455, 1456 3/29/2011 Gr. Beta 2.50 +/- 0.75 2.75 +/- 0.83 2.62 +/- 0.56 Pass SWU-1522, 1523 3/29/2011 Gr. Beta 1.36 +/- 0.87 2.14 +/- 0.96 1.75 +/- 0.65 Pass PM-1543, 1544 3/29/2011 Gr. Beta 13.81 +/- 0.26 13.67 +/- 0.27 13.74 +/- 0.19 Pass PM-1543, 1544 3/29/2011 Sr-90 8.12 +/- 3.20 7.71 +/- 3.25 7.91 +/- 2.28 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 SWT-5885, 5886 3/29/2011 Gr. Beta 1.21 +/- 0.54 0.77 +/- 0.54 0.99 +/- 0.38 Pass AP-1883, 1884 3/30/2011 Be-7 0.07 +/- 0.01 0.09 +/- 0.02 0.08 +/- 0.01 Pass AP-2248, 2249 3/30/2011 Be-7 0.06 +/- 0.01 0.06 +/- 0.01 0.06 +/- 0.01 Pass DW-20066, 20067 3/30/2011 Ra-226 2.14 +/- 0.16 2.10 +/- 0.16 2.12 +/-0.11 Pass DW-20066, 20067 3/30/2011 Ra-228 2.55 +/- 0.65 1.78 +/- 0.62 2.17 +/- 0.45 Pass P-1567, 1568 4/1/2011 H-3 289.00 +/- 103.00 296.00 +/- 103.00 292.50 +/- 72.83 Pass MI-1609, 1610 4/4/2011 1-131 0.85 +/- 0.17 0.91 +/- 0.18 0.88 +/- 0.13 Pass MI-1609, 1610 .4/4/2011 K-40 1323.80 +/- 112.00 1323.20 +/- 96.22 1323.50 .1 73.83 Pass MI-1 609, 1610 4/4/2011 Sr-90 0.85 +/- 0.33 0.97 +/- 0.34 0.91 +/- 0.24 Pass S-1651, 1652 4/4/2011 Ac-228 0.88 +/- 0.08 1.03 +/- 0.22 0.96 +/- 0.12 Pass S-1651, 1652 4/4/2011. Pb-214 1.09 +/- 0.12 0.84 +/- 0.16 0.97 +/- 0.10 Pass AP-1841, 1842 4/7/2011 Be-7 0.12+/- 0.02 0.12 +/- 0.01 0.12 +/-0.01 Pass AP-1841, 1842 4/7/2011 Cs-137 0.00 +/- 0.00 0.00 +/- 0.00 0.00 +/- 0.00 Pass AP-1841, 1842 4/7/2011 1-131(G) 0.02 +/- 0.00 0.03 +/- 0.00 0.03 +/- 0.00 Pass S-1990, 1991 4/7/2011 Ac-228 15.83 +/- 0.39 16.12 +/- 0.64 15.98 +/- 0.37 Pass S-1990, 1991 4/7/2011 Pb-214 11.21 +/- 0.23 11.81 +/- 1.22 11.51 +/- 0.62 Pass WW-2552, 2553 4/7/2011 H-3 761.09 +/- 116.48 759.04 +/- 116.41 760.07 +/- 82.34 Pass PM-1904, 1905 4/11/2011 K-40 13585.00 +/- 611.00 14278.00 +/- 648.00 13931.50 +/- 445.32 Pass PM-1904, 1905 4/11/2011 Sr-90 9.94 +/- 3.05 5.62 +/- 2.52 7.78 +/- 1.98 Pass P-2011, 2012 4/11/2011 H-3 670.00 +/- 108.00 619.00 +/- 106.00 644.50 +/- 75.66 Pass WW-2053, 2054 4/13/2011 H-3 220.20 +/- 86.50 246.80 +/- 87.80 233.50 +/- 61.63 Pass BS-2095, 2096 4/13/2011 K-40 12.88 +/- 0.72 13.56 +/- 1.08 13.22 +/- 0.65 Pass DW-20099, 20100 4/13/2011 U-233/4 1.64 +/- 0.40 1.31 +/- 0.34 1.48 +/- 0.26 Pass DW-20099, 20100 4/13/2011 U-238 1.49 +/- 0.39 1.28 +/- 0.33 1.39 +/- 0.26 Pass WW-2416, 2417 4/19/2011 H-3 217.10 +/- 97.00 184.90 +/- 95.60 201.00 +/- 68.10 Pass P-2185, 2186 4/20/2011 H-3 405.00 +/- 93.00 504.00 +/- 98.00 454.50 +/- 67.55 Pass WW-2353, 2354 4/20/2011 H-3 525.54 +/- 119.74 399.41 +/- 115.99 462.48 +/- 83.35 Pass DW-20115, 20116 4/26/2011 U-233/4 11.94 +/- 2.34 10.71 +/- 1.19 11.33 +/- 1.31. Pass DW-20115, 20116 4/26/2011 U-238 2.70 +/- 1.15 3.89 +/- 0.72 3.30 +/- 0.68 Pass SO-2960, 2961 4/27/2011 K-40 22.63 +/- 1.36 22.90 +/- 0.03 22.77 +/- 0.68 Pass MI-2657, 2658 5/2/2011 K-40 1319.30 +/- 101.30 1403.20 +/- 131.60 1361.25 +/- 83.04 Pass DW-20130, 20131 5/2/2011 U-233/4 7.59 +/- 0.90 7.62 +/- 0.83 7.61 +/- 0.61 Pass DW-20130, 20131 5/2/2011 U-238 4.67 +/- 0.72 4.84 +/- 0.66 4.76 +/- 0.49 Pass DW-20148, 20149 5/3/2011 U-233/4 6.64 +/- 0.83 6.35 +/- 0.81 6.50 +/- 0.58 Pass DW-20148, 20149 5/3/2011 U-238 6.11 +/-0.83 5.18 +/- 0.73 5.65 +/- 0.55 Pass PM-2810, 2811 5/4/2011 Cs-1 34 18.64 +/- 12.16 33.33 +/- 11.86 25.99 +/- 8.49 Pass PM-2810, 2811 5/4/2011 Cs-137 28.99 +/- 14.92 21.17 +/- 12.16 25.08 +/- 9.62 .Pass PM-2810, 2811 5/4/2011 K-40 14368.00 +/- 720.00 14309.00 +/- 638.00 14338.50 +/- 481.00 Pass WW-3065, 3066 5/16/2011 H-3 280.51 +/- 86.98 179.46 +/- 82.83 229.98 +/- 60.05 Pass WW-3086, 3087 5/16/2011 H-3 341.14 +/- 85.94 377.97 +/- 87.43 359.56 +/- 61.30 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 SG-3134, 3135 5/16/2011 Ac-228 11.19 +/- 0.82 12.50 +/- 0.84 11.85 +/- 0.59 Pass SG-3134, 3135 5/16/2011 Pb-214 9.12 +/- 0.17 9.37 +/- 0.42 9.25 +/- 0.23 Pass F-3221, 3222 5/23/2011 K-40 2.73 +/- 0.39 2.81 +/- 0.42 2.77 +/- 0.29 Pass SS-3434,3435 5/25/2011 K-40 11533.00 +/- 563.70 11236.00 +/- 566.10 11384.50 +/- 399.45 Pass AP-3329, 3330 5/26/2011 Be-7 0.24 +/- 0.11 0.23 +/- 0.13 0.24 +/- 0.08 Pass WW-3350, 3351 6/1/2011 H-3 235.37 +/- 83.98 173.12 +/- 81.05 204.25 +/- 58.36 Pass G-3413,3414 6/1/2011 Be-7 0.28 +/- 0.10. 0.25 +/- 0.09 0.27 +/- 0.07 Pass G-3413, 3414 6/1/2011 Gr. Beta 11.04 +/- 0.31 10.85 +/- 0.31 10.95 +/- 0.22 Pass G-3413, 3414 6/1/2011 K-40 6.80 +/- 0.33 6.71 +/- 0.38 6.76 +/- 0.25 Pass AP-3602, 3603 6/3/2011 Be-7 0.20 +/- 0.08 0.25 +/- 0.10 0.22 +/- 0.07 Pass SO-3797, 3798 6/8/2011 Ac-228 0.99 +/- 0.05 1.00 +/- 0.06 1.00 +/- 0.04 Pass SO-3797, 3798 6/8/2011 Bi-212 1.10 +/- 0.12 1.08 +/- 0.17 1.09 +/- 0.10 Pass SO-3797, 3798 6/8/2011 Bi-214 0.87 +/- 0.02 0.86 +/- 0.02 0.87 +/- 0.01 Pass SO-3797, 3798 6/8/2011 Cs-1 37 0.41 +/- 0.01 0.39 +/- 0.01 0.40 +/- 0.01 Pass SO-3797, 3798 6/8/2011 K-40 16.08 +/- 0.26 16.27 +/- 0.29 16.18 +/- 0.19 Pass SO-3797, 3798 6/8/2011 Pb-212 0.98 +/- 0.10 0.93 +/- 0.02 0.96 +/- 0.05 Pass SO-3797, 3798 6/8/2011 Pb-214 0.95 +/- 0.02 0.91 +/- 0.02 0.93 +/- 0.01 Pass SO-3797, 3798 6/8/2011 Th-232 0.47 +/- 0.05 0.49 +/- 0.04 0.48 +/- 0.03 Pass SO-3797, 3798 6/8/2011 U-233/4 0.16 +/- 0.02 0.15 +/- 0.02 0.16 +/- 0.01 Pass SO-3797, 3798 6/8/2011 U-238 0.16 +/- 0.02 0.13 +/- 0.02 0.15 +/- 0.01 Pass MI-3935, 3936 6/20/2011 K-40 1764.60 +/- 119.40 1843.10 +/- 136.50 1803.85 +/- 90.68 Pass BS-4172, 4173 6/21/2011 Cs-137 51.50 +/- 23.78 48.57 +/- 17.06 50.04 +/- 14.63 Pass BS-4172, 4173 6/21/2011 K-40 11730.00 +/- 679.60 11120.00 +/- 512.30 11425.00 +/- 425.53 Pass DW-20183, 20184 6/21/2011 U-233/4 10.00 +/- 1.00 8.40 +/- 0.90 9.20 +/- 0.67 Pass DW-20183, 20184 6/21/2011 U-238 6.70 +/- 0.80 6.10 +/- 0.80 6.40 +/- 0.57 Pass WW-4019,4020 6/24/2011 Gr. Beta 3.56 +/- 1.20 3.16 +/- 1.21 3.36 +/- 0.85 Pass PM-4193, 4194 6/30/2011 K-40 14795.00 +/- 759.00 14660.00 +/- 750.00 14727.50 +/- 533.52 Pass LW-4235, 4236 6/30/2011 Gr. Beta 2.70 +/- 0.72 2.11 +/- 0.78 2.41 +/- 0.53 Pass AP-4367, 4368 7/7/2011 Be-7 0.17 +/- 0.10 0.19 +/- 0.11 0.18 +/- 0.07 Pass MI-4416, 4417 7/11/2011 K-40 1342.40 +/- 91.49 1447.00 +/- 114.80 1394.70 +/- 73.40 Pass W-4914,4915 7/11/2011 H-3 576.36 +/- 110.35 584.67 +/- 110.67 580.52 +/- 78.14 Pass MI-4438, 4439 7/12/2011 K-40 1280.60 +/- 107.50 1381.20 +/- 112.70 1330.90 +/- 77.87 Pass VE-4481, 4482 7/13/2011 K-40 4452.60 +/- 332.40 4767.90 +/- 349.70 4610.25 +/- 241.24 Pass AP-4677, 4678 7/15/2011 Be-7 0.18 +/- 0.08 0.23 +/- 0.09 0.20 +/- 0.06 Pass W-5537,5538 7/18/2011 H-3 650.13 +/- 105.19 695.39 +/- 106.94 672.76 +/- 75.00 Pass P-4764, 4765 7/19/2011 H-3 179.82 +/- 84.81 138.72 +/- 82.79 159.27 +/- 59.26 Pass WW-5211, 5212 7/24/2011 H-3 191.94 +/- 85.50 136.22 +/- 82.76 164.08 +/- 59.50 Pass A5-3
TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance VE-4998, 4999 7/25/2011 Be-7 543.90 +/- 158.20 488.30 +/- 163.80 516.10 +/- 113.86 Pass VE-4998, 4999 7125/2011 K-40 2562.20 +/- 319.80 2414.00 +/- 350.00 2488.10 +/- 237.05 Pass DW-20258, 20259 7/25/2011 U-23314 21.34 +/- 1.52 24.93 +/- 2.93 23.14 +/- 1.65 Pass DW-20258, 20259 7/25/2011 U-235 0.57 +/- 0.26 0.69 +/- 0.26 0.63 +/- 0.18 Pass DW-20258, 20259 7/25/2011 U-238 14.11 +/- 1.24 15.81 +/- 1.23 14.96 +/- 0.87 Pass DW-20269, 20270 7/25/2011 U-233/4 4.93 +/- 0.73 4.65 +/- 0.68 4.79 +/- 0.50 Pass DW-20269, 20270 7/25/2011 U-238 3.26 +/- 0.60 2.53 +/- 0.50 2.90 +/- 0.39 Pass DW-20280, 20281 7/25/2011 U-233/4 3.58 +/- 0.58 3.33 +/- 0.56 3.46 +/- 0.40 Pass DW-20280, 20281 7/25/2011 U-238 1.64 +/- 0.40 2.11 +/-0.45 1.88 +/- 0.30 Pass MI-5019, 5020 7/26/2011 K-40 1348.50 +/- 101.00 1347.40 +/- 109.70 1347.95 +/- 74.56 Pass W-5447,5448 7/26/2011 H-3 246.31 +/- 99.19 241.99 + 99.02 244.15 +/- 70.08 Pass G-5124,5125 7/28/2011 Gr. Beta 7.48 +/- 0.20 7.17 - 0.19 7.33 +/- 0.14 Pass AP-5232, 5233 7/28/2011 Be-7 0.15 +/- 0.08 0.22 +/- 0.13 0.19 +/- 0.08 Pass SL-5169, 5170 8/1/2011 Be-7 2.37 +/- 0.16 2.17 +/-+0.17 2.27 +/- 0.12 Pass SL-5169, 5170 8/1/2011 Gr. Beta 4.74 +/- 0.45 3.94 + 0.39 4.34 +/- 0.30 Pass SL-5169, 5170 8/1/2011 K-40 3.12 +/- 0.16 2.96 +/- 0.21 3.04 +/- 0.13 Pass G-5190, 5191 8/1/2011 Be-7 3.14 +/- 0.30 3.44 +/- 0.27 3.29 +/- 0.20 Pass G-5190, 5191 8/1/2011 Gr. Beta 8.07 +/- 0.28 7.86 +/- 0.27 7.97 +/- 0.19 Pass G-5190, 5191 8/1/2011 K-40 5.51 +/- 0.46 5.57 +/- 0.44 5.54 +/- 0.32 Pass DW-20291, 20292 8/2/2011 U-233/4 3.24 +/- 0.54 2.60 +/- 0.50 2.92 +/- 0.37 Pass DW-20291, 20292 8/2/2011 U-238 1.59 +/- 0.38 2.00 +/- 0.43 1.80 +/- 0.29 Pass SG-5342,5343 8/5/2011 Ac-228 14.41 +/- 0.36 14.13 +/- 0.48 14.27 +/- 0.30 Pass SG-5342, 5343 8/5/2011 Bi-212 4.14 +/- 0.65 4.73 +/- 1.21 4.44 +/- 0.69 Pass SG-5342, 5343 8/5/2011 K-40 7.67 +/- 0.92 7.95 +/- 1.21 7.81 +/- 0.76 Pass SG-5342, 5343 8/5/2011 Pb-214 10.72 +/- 0.21 10.67 +/- 0.28 10.70 +/- 0.18 Pass SG-5342,5343 8/5/2011 TI-208 0.96 +/- 0.06 1.00 +/- 0.06 0.98 +/- 0.04 Pass MI-5405, 5406 8/8/2011 K-40 1545.30 +/- 116.00 1388.00 +/- 98.20 1466.65 +/- 75.99 Pass DW-20301, 20302 8/9/2011 Gr. Alpha 6.36 +/- 1.09 5.30 +/- 1.08 5.83 +/- 0.77 Pass DW-20301, 20302 8/9/2011 Gr. Beta. 14.36 +/- 0.92 13.51 +/- 0.89 13.94 +/- 0.64 Pass DW-5603, 5604 8/16/2011 Ra-228 1.68 +/- 0.88 2.26 +/- 0.91 1.97 +/- 0.63 Pass VE-5753, 5754 8/22/2011 Be-7 0.78 +/- 0.20 0.75 +/- 0.23 0.77 +/- 0.15 Pass VE-5753, 5754 8/22/2011 K-40 6.16 +/- 0.51 6.63 +/- 0.57 6.40 +/- 0.38 Pass S-5801, 5802 8/29/2011 Ac-228 0.43 +/- 0.09 0.38 +/- 0.07 0.41 +/- 0.06 Pass S-5801, 5802 8/29/2011 K-40 6.54 +/- 0.51 5.96 +/- 0.49 6.25 +/- 0.35 Pass S-5801, 5802 8/29/2011 Pb-212 0.31 +/- 0.03 0.36 +/- 0.03 0.34 +/- 0.02 Pass S-5801, 5802 8/29/2011 Pb-214 0.28 +/- 0.04 0.25 +/- 0.04 0.27 +/- 0.03 Pass S-5801, 5802 8/29/2011 TI-208 0.14 +/- 0.02 0.12 +/- 0.02 0.13 +/- 0.01 Pass S-5801 5802 8/29/2011 U-235 0.05 +/- 0.02 0.04 +/- 0.01 0.05 +/- 0.01 Pass ME-5996, 5997 9/1/2011 Gr. Alpha 0.03 +/- 0.02 0.03 +/- 0.02 0.03 +/- 0.01 Pass ME-5996, 5997 9/1/2011 Gr. Beta 2.55 +/- 0.07 2.62 +/- 0.07 2.58 +/- 0.05 Pass ME-5996, 5997 9/1/2011 K-40 2.66 +/- 0,35 2.24 +/- 0.58 2.45 +/- 0.34 Pass A5-4
TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance SL-6017, 6018 9/6/2011 Be-7 0.47 +/- 0.17 0.51 +/- 0.19 0.49 +/- 0.13 Pass SL-6017, 6018 9/6/2011 Gr. Beta 4.23 +/- 0.16 3.94 +/- 0.15 4.09 +/- 0.11 Pass SL-6017, 6018 9/6/2011 K-40 4.43 +/- 0.55 4.24 +/- 0.53 4.34 +/- 0.38 Pass VE-6038, 6039 9/7/2011 Sr-90 1.86 +/- 0.98 2.30 +/- 0.92 2.08 +/- 0.67 Pass SW-6059, 6060 9/8/2011 H-3 219.75 +/- 97.52 177.41 +/- 95.76 198.58 +/- 68.34 Pass VE-6302, 6303 9/1312011 Be-7 0.76 +/- 0.24 0.85 +/- 0.20 0.81 +/- 0.16 Pass VE-6302, 6303 9/13/2011 Gr. Beta 27.00 +/- 1.02 25.50 +/- 0.95 26.25 +/- 0.70 Pass VE-6302, 6303 9/13/2011 H-3 6966.00 +/- 249.00 6947.00 +/- 249.00 6956.50 +/- 176.07 Pass VE-6302, 6303 9/13/2011 K-40 20.62 +/- 0.68 20.63 +/- 0.64 20.63 +/- 0.47 Pass W-7098,7099 9/19/2011 H-3 586.61 +/- 103.06 525.71 +/- 100.63 556.16 +/- 72.02 Pass W-6407,6408 9/20/2011 Ra-228 1.61 +/- 0.94 0.79 +/- 0.81 1.20 +/- 0.62 Pass MI-6479, 6480 9/27/2011 K-40 1384.10 +/- 111.10 1411.40 + 105.00 1397.75 +/- 76.43 Pass W-6579,6580 9/27/2011 H-3 287.97 +/- 99.68 285.95 + 99.60 286.96 +/- 70.45 Pass AP-7015, 7016 9/27/2011 Be-7 0.08 +/- 0.02 0.09 +/- 0.02 0.08 +/- 0.01 Pass AP-6105, 6106 9128/2011 Be-7 0.11 +/- 0.02 0.09 +/- 0.02 0.10 +/- 0.01 Pass LW-6603, 6604 9/28/2011 Gr. Beta 2.15 +/- 1.04 1.65 + 0.90 1.90 +/- 0.69 Pass AP-7056, 7057 9/29/2011 Be-7 0.08 +/- 0.02 0.06 + 0.01 0.07 +/- 0.01 Pass G-6730,6731 10/3/2011 Be-7 4.24 +/- 0.36 4.47 +/- 0.37 4.36 +/- 0.26 Pass G-6730, 6731 10/3/2011 Gr. Beta 8.27 +/- 0.33 7.93 +/- 0.31 8.10 +/- 0.23 Pass G-6730, 6731 10/3/2011 K-40 6.46 +/- 0.56 5.41 +/- 0.50 5.94 +/- 0.38 Pass AP-7077, 7078 10/3/2011 Be-7 0.08 +/- 0.01 0.07 +/- 0.01 0.07 +/- 0.01 Pass AP-7077, 7078 10/3/2011 Be-7 0.08 +/- 0.01 0.07 +/- 0.01 0.07 +/- 0.01 Pass VE-6798, 6799 10/4/2011 K-40 11.76 +/- 0.65 11.91 +/- 0.62 11.84 +/- 0.45 Pass AP-6820, 6821 10/6/2011 Be-7 0.22 +/- 0.08 .0.18 +/- 0.10 0.20 +/- 0.06 Pass W-7755,7756 10/9/2011 H-3 261.92 +/- 96.52 221.92 +/- 94.80 241.92 +/- 67.65 Pass BS-7944, 7945 10/10/2011 Cs-137 291.17 +/-34.00 330.68 +/- 36.40 310.93 +/- 24.90 Pass BS-7944, 7945 10/10/2011 K-40 14237.00 +/- 686.40 15359.00 +/- 703.80 14798.00 +/- 491.55 Pass BS-7140, 7141 10/13/2011 K-40 2.59 +/- 0.35 2.58 +/- 0.52 2.59 +/- 0.31 Pass AP-7168, 7169 10/13/2011 Be-7 0.25 +/- 0.09 0.25 +/- 0.11 0.25 +/- 0.07 Pass DW-20349, 20350 10/13/2011 U-233/4 1.77 +/- 0.41 2.25 +/- 0.77 2.01 +/- 0.44 Pass DW-20349, 20350 10/13/2011 U-238 0.28 +/- 0.19 0.31 +/- 0.33 0.30 +/- 0.19 Pass WW-7667, 7668 10/1912011 H-3 1049.11 +/- 116.32 1071.39 +/- 117.10 1060.25 +/- 82.53 Pass WW-7381, 7382 10/21/2011 H-3 1904.40 +/- 145.45 1813.62 +/- 142.91 1859.01 +/- 101.95 Pass SS-7495, 7496 10/26/2011 K-40 10.16 +/- 0.55 9.56 +/- 0.49 9.86 +/- 0.37 Pass W-7516,7517 10/27/2011 H-3 191.46 +/- 84.47 224.05 +/- 86.03 207.76 +/- 60.28 Pass VE-7537, 7538 10/2812011 K-40 2.08 +/- 0.23 2.41 +/- 0.21 2.24 +/- 0.16 Pass MI-7622, 7623 10/31/2011 K-40 1386.20 +/- 116.80 1407.90 +/- 116.50 1397.05 +/- 82.48 Pass DW-20399,20400 10/31/2011 U-233/4 5.70 +/- 0.70 5.70 +/- 0.70 5.70 +/- 0.49 Pass DW-20399, 20400 10/31/2011 U-238 3.10 +/- 0.50 3.70 +/- 0.70 3.40 +/- 0.43 Pass BS-7600, 7601 11/1/2011 Gr. Beta 6.83 +/- 1.44 5.31 +/- 1.35 6.07 +/- 0.98 Pass A5-5
TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance SG-8471,8472 11/1/2011 Gr. Alpha 13.63 t 2.32 11.13 +/- 2.00 12.38 +/- 1.53 Pass SG-8471, 8472 11/1/2011 Gr. Beta 20.30 +/- 1.43 17.65 +/- 1.42 . 18.98 +/- 1.01 Pass DW-20424, 20425 11/7/2011 U-233/4 5.90 +/- 0.80 6.10 +/- 0.80 6.00 +/- 0.57 Pass DW-20424, 20425 11/7/2011 U-235 0.10 +/-_0.10 0.30 +/-_0.20 0.20 +/-0.11 Pass DW-20424, 20425 11/7/2011 U-238 4.30 +/- 0.70 3.70 +/- 0.60 4.00 _ 0.46 Pass DW-20424, 20425 11/7/2011 U-238 10.30 +/- 1.00 10.10 +/- 1.00 10.20 + 0.71 Pass DW-20435, 20436 11/8/2011 U-233/4 11.00 +/- 1.10 10.60 +/- 0.80 10.80 +/-0.68 Pass DW-20435, 20436 11/8/2011 U-238 5.90 +/- 0.80 4.90 +/- 0.60 5.40 _ 0.50 Pass SG-7902, 7903 11/10/2011 Ac-228 21.38 +/- 0.47 20.48 +/- 0.52 20.93 + 0.35 Pass SG-7902, 7903 11/10/2011 K-40 9.72 +/- 1.04 9.53 +/- 0.92 9.63 + 0.69 Pass SG-7902, 7903 11/10/2011 Pb-212 3.99 +/- 0.10 3.99 +/- 0.10 3.99 +/- 0.07 Pass SG-7902, 7903 11/10/2011 Pb-214 9.15 +/-0.23 9.14 +/- 0.21 9.15 +/- 0.16 Pass BS-8033, 8034 11/11/2011 Cs-137 0.03 +/- 0.02 0.03 +/- 0.02 0.03 +/- 0.01 Pass LW-8075, 8076 11/16/2011 Gr. Beta 1.93 +/- 0.62 2.55 +/- 0.64 2.24 +/- 0.44 Pass AP-8193, 8194 11/17/2011 Be-7 0.21 +/-_0.11 0.26 +/--0.13 0.24 +/-_0.08 Pass F-8663, 8664 11/19/2011 Cs-137 0.03 +/- 0.02 0.03 +/- 0.02 0.03 +/- 0.01 Pass F-8663, 8664 11/19/2011 Gr. Beta 3.55 +/- 0.10 3.71 +/- 0.10 3.63 +/- 0.07 Pass F-8663, 8664 11/19/2011 K-40 3.04 +/- 0.42 3.05 +/- 0.35 3.05 +/- 0.27 Pass DW-20449, 20450 11/28/2011 U-233/4 0.70 +/- 0.20 0.80 +/- 0.20 0.75 +/- 0.14 Pass DW-20449, 20450 11/28/2011 U-238 0.60 +/- 0.20 0.60 +/- 0.20 0.60 +/- 0.14 Pass SWU-8388, 8389 11/29/2011 Gr. Beta 1.66 +/- 0.57 1.65 +/- 0.59 1.66 +/- 0.41 Pass AP-8841, 8842 12/15/2011 Be-7 0.23 +/- 0.12 0.19 +/- 0.09 0.21 +/- 0.07 Pass W-8886, 8887 12/15/2011 Gr. Alpha 0.83 +/- 0.81 1.58 +/- 0.99 1.21 +/- 0.64 Pass W-8886, 8887 12/15/2011 Gr. Beta 6.80 +/- 1.25 5.94 +/- 1.22 6.37 +/- 0.87 Pass W-8886, 8887 12/15/2011 Ra-226 0.23 +/- 0.15 0.41 +/- 0.16 0.32 +/- 0.11 Pass SO-8958, 8959 12/21/201.1 K-40 14.58 +/- 0.86 15.07 +/- 0.87 14.83 +/- 0.61 Pass AP-8907, 8908 12/22/2011 Be-7 0.15 +/- 0.06 0.11 +/- 0.07 0.13 +/- 0.05 Pass AP-9196, 9197 12/28/2011 Be-7 0.06 +/- 0.01 0.07 +/- 0.01 0.06 +/- 0.01 Pass LW-9091, 9092 12/29/2011 Gr. Beta 1.97 +/- 0.63 1.74 +/- 0.60 1.86 +/- 0.44 Pass Note: Duplicate analyses are performed on every twentieth sample received in-house. Results are not listed for those analyses with activities that measure below the LLD.
a Results are reported in units of pCi/L, except for air filters (pCi/Filter), food products, vegetation, soil, sediment (pCi/g).
A5-6
TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)a.
b Concentration Known Control Lab Code c Date Analysis Laboratory result Activity Limits d Acceptance STW-1237 e 02/01/11 Am-241 0.35 +/- 0.10 0.53 0.37 - 0.69 Fail STW-1237 02/01/11 Co-57 < 0.2 0.00 Pass STW-1237 02/01/11 Co-60 24.10 +/- 0.40 24.60 17.20 - 32.00 Pass STW-1237 02/01/11 Cs-134 19.80 +/- 0.40 21.50 15.10 -28.00 Pass STW-1 237 02/01/11 Cs-137 29.40 +/- 0.50 29.40 20.60 - 38.20 Pass STW-1237 02/01/11 H-3 238.90 +/- 8.80 243.00 170.00 - 316.00 Pass STW-1237 02/01/11 K-40 95.40 +/- 3.10 91.00 64.00 -118.00 Pass STW-1237 02/01/11 Mn-54 32.50 +/- 0.60 31.60 22.10 -41.10 Pass STW-1237 02/01/11 Ni-63 16.30 +/- 0.60 18.60 13.00 - 24.20 Pass STW-1237 02/01/11 Pu-238 1.11 +/- 0.12 1.06 0.75 - 1.38 Pass STW-1237 02/01/11 Pu-239/40 0.88 +/- 0.12 0.81 0.57 - 1.05 Pass STW-1237 02/01/11 Sr-90 8.70 +/- 0.70 8.72 6.10 -11.34 Pass STW-1 237 02/01/11 Tc-99 7.60 t 0.60 8.99 6.29 - 11.69 Pass STW-1237 02/01/11 Zn-65 <0.5 0.00 Pass STW-1238 02/01/11 Gr. Alpha 0.82 t 0.07 1.14 0.34 -1.93 Pass STW-1238 02/01/11 Gr. Beta 2.82 +/- 0.07 2.96 1.48 -4.44 Pass STVE-1239 02/01/11 Co-57 11.27 +/- 0.21 9.94 6.96 - 12.92 Pass STVE-1239 02/01/11 Co-60 4.95 +/- 0.16 4.91 3.44 - 6.38 Pass STVE-1239 02/01/11 Cs-134 5.18 +/- 0.19 5.50 3.85 - 7.15 Pass STVE-1239 02/01/11 Cs-137 < 0.09 0.00 Pass STVE-1239 02/01/11 Mn-54 6.91 +/- 0.25 6.40 4.48 - 8.32 Pass STVE-1239 02/01/11 Zn-65 3.10 +/- 0.32 2.99 2.09 - 3.89 Pass STSO-1240 02/01/11 Co-57 984.10 +/- 4.10 927.00 649.00 - 1205.00 Pass STSO-1240 02/01/11 Co-60 540.70 +/- 3.00 482.00 337.00 - 627.00 Pass STSO-1240 02/01/11 Cs-1 34 726.70 +/- 5.92 680.00 476.00 - 884.00 Pass STSO-1240 02/01/11 Cs-137 883.10 +/- 4.70 758.00 531.00 -985.00 Pass STSO-1240 02/01/11 K-40 622.70 +/- 16.70 540.00 378.00 - 702.00 Pass STSO-1240 02/01/11 Mn-54 -0.30 +/- 1.00 0.00 Pass STSO-1240 02/01/11 Ni-63 384.00 +/- 16.90 582.00 407.00 - 757.00 Fail STSO-1240 02/01/11 U-233/4 166.60 +/- 7.30 176.00 123.00 -229.00 Pass STSO-1240 02/01/11 U-238 172.00 +/- 7.40 184.00 129.00 -239.00 Pass STSO-1240 02/01/11 Zn-65 1671.00 +/- 13.10 1359.00 951.00 - 1767.00 Pass STAP-1241 02/01/11 Am-241 0.00 +/- 0.01 0.00 -0.10 -0.10 Pass STAP-1241 02/01/11 Co-57 3.48 +/- 0.06 3.33 2.33 - 4,33 Pass STAP-1241 02/01/11 Co-60 0.00 +/- 0.02 0.00 -0.10 -0.10 Pass STAP-1241 02/01/11 Cs-134 3.44 +/- 0.27 3.49 2.44 - 4.54 Pass STAP-1241 02/01/11 Cs-137 2.46 +/- 0.27 2.28 1.60 -2,96 Pass A6-1
TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)a.
Concentration b Known Control Lab Code C Date Analysis Laboratory result Activity Limits d Acceptance STAP-1241 02/01/11 Gr. Alpha 0.39 +/- 0.05 0.66 0.20 -1.12 Pass STAP-1241 02/01/11 Gr. Beta 1.54 +/- 0.07 1.32 0.66 - 1.99 Pass STAP-1241 02/01/11 Mn-54 2.90 +/- 0.10 2.64 1.85 - 3.43 Pass STAP-1 241 02/01/11 Pu-238 0.07 +/- 0.02 0.10 0.07 -0.13 Pass STAP-1241 02/01/11 Pu-239/40 0.06 _ 0.02 0.08 0.05 -0.10 Pass STAP-1241 g 02/01/11 Sr-90 1.89 +/- 0.15 1.36 0.95 -1.77 Fail STAP-1241 02/01/11 U-233/4 0.13 +/- 0.02 0.18 0.13 -0.23 Pass STAP-1241 02/01111 U-238 0.14 +/- 0.02 0.19 0.13 -0.24 Pass STAP-1241 02/01/11 Zn-65 3.80 +/- 0.18 3.18 2.23 -4.13 Pass STW-1249 08/01/11 1-129 7.32 + 0.30 9.50 6.70 -12.40 Pass STVE-1250 08/01/11 Co-57 0.01 +/- 0.02 0.00 Pass STVE-1250 08/01/11 Co-60 3.57 +/- 0.13 3.38 2.37 - 4.39 Pass STVE-1250 08/01/11 Cs-1 34 -0.02 +/- 0.04 0.00 -0.10 -0.10 Pass STVE-1250 08/01/11 Cs-137 5.28 +/- 0.20 4.71 3.30 -6.12 Pass STVE-1250 08/01/11 Mn-54 6.48 +/- 0.22 5.71 4.00 - 7.42 Pass STVE-1250 08/01/11 Zn-65 7.35 +/- 0.34 6.39 4.47 - 8.31 Pass STSO-1251 08/01/11 Co-57 1333.90 +/- 4.20 1180.00 826.00 - 1534.00 Pass STSO-1251 08/01/11 Co-60 701.30 +/- 3.40 644.00 451.00 -837.00 Pass STSO-1251 08/01/11 Cs-134 0.71 +/- 1.05 0.00 Pass STSO-1251 08/01/11 Cs-1 37 1106.00 +/- 5.60 979.00 685.00 - 1273.00 Pass STSO-1251 08/01/11 K-40 749.20 +/- 19.00 625.00 438.00 -813.00 Pass STSO-1251 08/01/11 Mn-54 984.30 55.40 848.00 594.00 - 1102.00 Pass STSO-1251 08/01/11 Ni-63 0.11 - 1.21 0.00 Pass STSO-1251 08/01/11 Pu-238 97.90 + 7.40 93.60 65.50 -121.70 Pass STSO-1251 08/01/11 Pu-239/40 78.80 + 6.40 77.40 54.20 - 100.60 Pass STSO-1251 08/01/11 Sr-90 219.40 +/- 16.70 320.00 224.00 -416.00 Fail STSO-1251 08/01/11 Tc-99 110.00 +/-8.00 182.00 127.00 -237.00 Fail STSO-1251 08/01/11 U-233/4 267.00 +/- 10.20 263.00 184.00 -342.00 Pass STSO-1251 08/01/11 U-238 280.30 +/- 10.40 274.00 192.00 -356.00 Pass STSO-1251 08/01/11 Zn-65 1639.90 +/- 11.40 1560.00 1092.00 -2028.00 Pass STAP-1252 08/01/11 Co-57 5.06 +/- 0.08 5.09 3.56 - 6.62 Pass STAP-1252 08/01/11 Co-60 3.13 +/- 0.09 3.20 2.24 -4.16 Pass STAP-1252 08/01/11 Cs-134 0.01 +/- 0.03 0.00 -0.10 -0.10 Pass STAP-1252 08/01/11 Cs-137 2.61 +/- 0.09 2.60 1.82 -3.38 Pass STAP-1252 08/01/11 Mn-54 0.01 +/- 0.03 0.00 -0.10 -0.10 Pass STAP-1252 08/01/11 Pu-238 0.13 +/- 0.02 0.12 0.08 -0.15 Pass STAP-1252 08/01/11 Pu-239/40 0.15 +/- 0.02 0.14 0.10 -0.18 Pass STAP-1252 08/01/11 Sr-90 1.65 +/- 0.16 1.67 1.17 -2.17 Pass A6-2
TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)a.
Concentration b Known Control Lab Code c Date Analysis Laboratory result Activity Limits d Acceptance STAP-1252 08101/11 U-233/4 0.17 +/- 0.02 0.16 0.11 - 0.21 Pass STAP-1252 08/01/11 U-238 0.17 +/- 0.02 0.17 0.12 -0.22 Pass STAP-1252 08/01/11 Zn-65 4.46 +/- 0.23 4.11 2.88 -5.34 Pass STW-1254 08/01/11 Co-57 37.20 +/- 0.50 36.60 25.60 - 47.60 Pass STW-1254 08/01/11 Co-60 28.80 +/- 0.40 29.30 20.50 - 38.10 Pass STW-1254 08/01/11 Cs-134 18.00 +/- 0.60 19.10 13.40 - 24.80 Pass STW-1254 08/01/11 Cs-137 0.06 +/- 0.13 0.00 - Pass STW-1254 08/01/11 H-3 1039.90 +/- 17.90 1014.00 710.00 - 1318.00 Pass STW-1254 08/01/11 K-40 161,40 +/- 4.10 156.00 109.00 -203.00 Pass STW-1254 08/01/11 Mn-54 25.70 +/- 0.50 25.00 17.50 -32.50 Pass STW-1254 08/01/11 Ni-63 0.60 +/- 2.00 0.00 - Pass STW-1254 08/01/11 Pu-238 0.04 +/- 0.02 0.02 0.00 - 1.00 Pass STW-1254 08/01/11 Pu-239/40 2.27 +/- 0.14 2.40 1.68 -3.12 Pass STW-1254 08/01/11 Sr-90 15,60 +/- 1.80 14.20 9.90 - 18.50 Pass STW-1254 08/01/11 Tc-99 -0,30 +/- 0.50 0.00 - Pass STW-1254 08/01/11 U-233/4 2,78 +/- 0.20 2.78 1.95 - 3.61 Pass STW-1254 08/01/11 U-238 2.86 +/- 0.21 2.89 2.02 - 3.76 Pass STW-1254 08/01/11 Zn-65 30,20 +/- 0.90 28.50 20.00 - 37.10 Pass STW-1255 08/01/11 Gr. Alpha 0.72 +/- 0.12 0.87 0.26 -1.47 Pass STW-1255 08/01/11 Gr. Beta 4.71 +/- 0.15 4.81 2.41 -7.22 Pass 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 b Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).
' Laboratory codes as follows: STW (water). STAP (air filter), STSO (soil), STVE (vegetation).
MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and control limits as defined by the MAPEP. A known value of "zero" indicates an analysis was included in the testing series as a "false positive". MAPEP does not provide control limits.
Result of a repeat analysis was still unacceptable. ERA crosschecks for Am-241 were acceptable, but biased low.
Matrix spikes were prepared, ( 5.17 and 51.7 pCi/L), to verify method; results were acceptable, 4.4 and 47.5 pCi/L.
Am-241 has been added to the internal spike and blank program for 2012.
An error in percent recovery was found, result of recalculation, 427.3 +/- 18.8 Bq/kg dry.
No errors found in calculation or procedure, results of reanalysis; 1.73 Bq/filter.
h The analyses were repeated through a strontium column; mean result of triplicate analyses, 304.2 Bq/kg.
' The lab does not currently analyze soil for Tc-99, but is evaluating the procedure. After consultation with Eichrom, the analysis was repeated using a matrix spike correction. Mean result of triplicate reanalyses; 183.3 Bq/kg.
A6-3
TABLE A-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.
Concentration (pCi/L) b Lab Code b Date Analysis Laboratory ERA Control Result C Result Limits Acceptance STAP-1230 03/21/11 Am-241 46.0 +/- 1.8 62.5 36.6 - 85.7 Pass STAP-1230 03/21/11 Co-60 401.2 +/- 12.1 390.0 302.0 - 487.0 Pass STAP-1230 03121/11 Cs-134 268.2 +/- 24.8 279.0 182.0 - 345.0 Pass STAP-1230 03/21/11 Cs- 137 345.3 +/- 24.9 312.0 234.0.- 410.0 Pass STAP-1230 03/21/11 Mn-54 < 1.9 0.0 Pass STAP-1230 03/21/11 Pu-238 76.1 +/- 3.2 69.0 47.4 - 90.7 Pass STAP-1230 03/21/11 Pu-239/40 70.50 +/- 3.10 65.5 47.5 - 85 Pass STAP-1230 03/21/11 Sr-90 208.40 +/- 18.70 185.0 81.4 -288 Pass STAP-1230 03/21/11 U-233/4 56.10 +/- 2.10 61.5 38.7 -91 Pass STAP-1230 03/21/11 U-238 58.90 +/- 2.60 61.0 39.0 - 87 Pass STAP-1230 03/21/11 Uranium 118.50 +/- 5.52 125.0 63.9 -199 Pass STAP-1 230 03/21/11 Zn-65 312.60 +/- 23.40. 279.0 193.0 -386 Pass STAP-1231 03/21/11 Gr. Alpha 88.40 +/- 3.70 74.3 38.5 -112 Pass STAP-1231 03/21/11 Gr. Beta 85.10 +/- 2.80 69.5 42.8 - 102 Pass STSO-1232 03/21/11 Ac-228 1327.8 +/- 97.5 1490.0 958.0 -2100.0 Pass STSO-1 232 03/21/1.1 Am-241 662.8 +/- 88.1 914.0 546.0 -1170.0 Pass STSO-1232 03/21/11 Bi-212 1396.2 +/- 185.3 1400.0 368.0 -2090.0 Pass STSO-1232 03/21/11 Bi-214 841.1 +/- 33.2 725.0 445.0 - 1040.0 Pass STSO-1232 03/21/11 Co-60 2423.7 +/- 27.1 2220.0 1620.0 -2980.0 Pass STSO-1232 03/21/11 Cs-134 2481.3 +/- 42.2 2450.0 1580.0 -2950.0 Pass STSO-1232 03/21/11 Cs-137 2108.2 +/- 30.2 1920.0 1470.0 -2490.0 Pass STSO-1232 03/21/ 11 K-40 11497.3 +/- 276.6 11500.0 8320.0 - 15600.0 Pass STSO-1232 03/21/11 Mn-54 < 17.4 0.0 Pass STSO-1232 03/21/11 Pb-212 994.7 +/- 30.0 1440.0 931.0 -2030.0 Pass STSO-1232 03/21/11 Pb-214 918.3 +/- 42.6 805.0 482.0 -1200.0 Pass STSO-1232 03/21/11 Pu-238 1593.6 +/- 156.7 1420.0 813.0 -2000.0 Pass STSO-1232 03/21/11 Pu-239/40 1428.9 +/- 143.4 1400.0 956.0 -1860.0 Pass STSO-1232 03/21/11 Sr-90 8638.0 +/- 442.8 7590.0 2740.0 - 12400.0 Pass STSO-1232 03/21/11 Th-234 1350.1 +/- 180.0 962.0 305.0 - 1830.0 Pass STSO-1232 03/21/11 U-233/4 748.0 +/- 94.4 972.0 616.0 -1210.0 Pass STSO-1232 03/21/11 U-238 909.0 +/- 104.9 962.0 588.0 - 1220.0 Pass STSO-1232 03/21/11 Uranium 1690.8 +/- 104.9 1980.0 1130.0 -2670.0 Pass STSO-1232 03/21/11 Zn-65 2356.2 +/- 57.1 1990.0 1580.0 -2670.0 Pass A7-1
TABLE A-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.
Concentration (pCi/L) D Lab Code b Date Analysis Laboratory ERA Control Result C Result a Limits Acceptance STVE-1233 03/21/11 Am-241 2377.5 +/- 83.2 3200.0 1820.0 - 4400.0 Pass STVE-1233 03/21/11 Cm-244 602.9 +/- 38.4 812.0 400.0 - 1260.0 Pass STVE-1233 03/21/11 Co-60 810.2 +/- 32.4 733.0 496.0 - 1050.0 Pass STVE-1233 03/21/11 Cs-134 849.4 +/- 54.5 770.0 441.0 - 1070.0 Pass STVE-1233 03/21/11 Cs-137 889.9 +/- 36.3 829.0 608.0 - 1150.0 Pass STVE-1233 03/21/11 K-40 28146.70 +/- 698.80 25800.0 18500.0 - 36500 Pass STVE-1233 03/21/11 Mn-54 < 19.3 0.0 Pass STVE-1233 03/21/11 Pu-238 3068.10 +/- 170.70 2990.0 1610.0 -4380 Pass STVE-1233 03/21/11 Pu-239/40 3180.00 +/- 88.90 3100.0 1920.0 - 4230 Pass STVE-1233 03/21/11 Sr-90 8549.20 +/- 675.00 7890.0 4410.0 - 10500 Pass STVE-1233 03/21/11 U-233/4 2418.60 +/- 142.50 2610.0 1790.0 - 3460 Pass STVE-1233 03/21/11 U-238 2417.00 +/- 142.50 2590.0 1820.0 - 3270 Pass STVE-1233 03/21/11 Uranium 4929.80 +/- 142.50 5320.0 3660.0 - 6860 Pass STVE-1233 03/21/11 Zn-65 962.40 +/- 62.50 799.0 577.0 - 1090 Pass STW-1 234 03/21/11 Am-241 100.0 +/- 6.4 135.0 92.5 - 182.0 Pass STVV-1234 03/21/11 Co-60 401.6 +/- 7.2 411.0 358.0 - 486.0 Pass STW-1234 03/21/11 Cs-134 222.7 +/- 12.3 231.0 171.0 -265.0 Pass STW-1234 03/21/11 Cs-137 410.3 +/-9.5 417.0 354.0 - 500.0 Pass STW-1234 03/21/11 Mn-54 <3.0 0.0 Pass STW-1234 03/21/11 Pu-238 130.9 +/- 5.5 131.0 99.1 - 162.0 Pass STW-1234 03/21/11 Pu-239/40 113.0 +/-5.0 119.0 92.1 - 147.0 Pass STW-1234 03/21/11 Sr-90 739.6 +/- 13.0 773.0 491.0 - 1030.0 Pass STW-1234 03/21/11 U-233/4 83.4 +/- 3.8 94.3 71.1 -122.0 Pass STW-1234 03/21/11 U-238 85.5 +/- 3.9 93.5 71.4 -116.0 Pass STW-1234 03/21/11 Uranium 172.0 +/- 8.5 192.0 138.0 -256.0 Pass STW-1234 03/21/11 Zn-65 114.5 +/- 10.8 111.0 94.1 -138.0 Pass STW-1235 03/21/11 Gr. Alpha 97.6 +/- 2.9 112,0 49.7 - 166.0 Pass STW-1235 03/21/11 Gr. Beta 99.6 +/- 2.0 99.8 58.4 - 146.0 Pass STW-1236 03/21/11 H-3 16307.0 +/- 377.0 15200.0 9900.0 - 22500.0 Pass 8 Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assessment Program (EML).
b Laboratory codes as follows: STW (water), STAP (air filter), STSO (soil), STVE (Vegetation). Results are reported in units of pCi/L, except for air filters (pCilFilter), vegetation and soil (pCi/kg).
c Unless otherwise indicated, the laboratory result is given as the mean +/- standard deviation for three determinations.
d Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA. A known value of "zero" indicates an analysis was included in the testing series as a "false positive". Control limits are not provided.
A7-2
APPENDIX B DATA REPORTING CONVENTIONS B-1
Data Reporting Conventions 1.0. All activities, except gross alpha and gross beta, are decay corrected to collection time or the end of the collection period.
2.0. 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 If duplicate analyses are reported, the convention is as follows.
3.1 Individual results: For two. analysis results; x1 +/- s, and x2 +/- s, Reported result: x +/- s; where x = (1/2) (x1 + x2 ) and s = (1/2) is + S_
3.2. Individual results: < L1 , < L2 Reported result: < L, where L = lower of L1 and L2 3.3. Individual results: x +/- s, < L Reported result: x +/- s if x > 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 x1, x2 ... xn are defined as follows:
-x =n1 Xx Xx- x2 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 numbers are kept unchanged. As an example, 11.443 is rounded off to 11.44.
4.5.2. If the number following those to be retained is equal to or greater than 5, the number is dropped and the last retained number is raised by 1. As an example, 11.445 is rounded off to 11.45.
B-2
APPENDIX C Maximum Permissible Concentrations of Radioactivity in Air and Water Above Background in Unrestricted Areas C-1
Table C-1. Maximum permissible concentrations of radioactivity in air and water above natural a
background in unrestricted areas Air (pCi/m3) Water (pCi/L)
-3 Gross alpha 1 x 10 Strontium-89 8,000 Gross beta 1 Strontium-90 500 b
Iodine-1 31 2.8 x 10 Cesium-1 37 1,000 Barium-1 40 8,000 Iodine-1 31 1,000 Potassium-40 4,000 Gross alpha 2 Gross beta 10 Tritium l x10 6 a
Taken from Table 2 of Appendix B to Code of Federal Regulations Title 10, Part 20, and appropriate footnotes.
Concentrations may be averaged over a period not greater than one year.
b Value adjusted by a factor of 700 to reduce the dose resulting from the air-grass-cow-milk-child pathway.
c A natural radionuclide.
C-2
MNGP APPENDIX D Sampling Location Maps D-1
Figure D-1, Sample Collection and Analysis Program: TLD locations, Inner Ring. (Table 5.2)
D-2
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Figure D-4, Sample Collection and Analysis Program: Radiological Environmental Monitoring Program, Milk Sampling locations. (Table 5.2)
D-5
Figure D-5, Sample Collection and Analysis Program: Radiological Environmental Monitoring Program, Sludge, Ground Water and Shoreline sampling locations. (Table 5.2)
D-6
APPENDIX E Ground Water Monitoring Well Samples
1.0 INTRODUCTION
This appendix to the Radiological Environmental Monitoring Program Annual Report to the United States Nuclear Regulatory Commission summarizes and interprets results of the Ground Water Monitoring Program samples taken at the Monticello Nuclear Plant, Monticello, Minnesota, during the period January - December 2011. This sampling program was established in October of 2006 following the industry initiative on ground water monitoring.
Complete data tables for each period and sampling location, are provided in a reference document, (Environmental, Inc., Midwest Laboratory, "Complete Analyses Data Tables, January - December, 2011") available at the Monticello Nuclear Generating Plant, Chemistry and Radiation Protection Department.
E-2
2.0
SUMMARY
The Ground Water Sampling Program was established following industry events where tritium was discovered in ground water surrounding commercial nuclear facilities. This program is described and the results for 2011 are summarized and discussed.
Program findings for 2011 detected low levels of tritium in monitoring wells located on the plant property at or near the expected natural background levels, with the exception of Monitoring Wells MW-9A and MW-10. The 2011 sample results (excluding MW-9A and MW-IO) all measured below the required limit of 500 pCi/L. Storm water runoff samples ranged from 772 pCi/L to below 500 pCi/L. The measurements for 2011 are below the Environmental Protection Agency's drinking water standard of 20,000 pCi/L and present no harm to members of the public.
None of the samples monitored for gamma-emitting isotopes showed activity greater than the LLD.
A summation of the analytical data for both ground water monitoring wells and storm water runoff samples is provided in Table E-3.
E-3
3.0 Ground Water Sampling Program 3.1 Program Design and Data Interpretation The purpose of this sampling program is to assess the impact of any tritium leaching into the environment (ground water system) from MNGP. For this purpose, water samples are collected and analyzed for tritium content.
3.2 Program Description The sampling and analysis schedule for the Ground Water Monitoring Program is summarized in Table E-1 and briefly reviewed below. Table E-2 defines the additional sample locations and codes for the Ground Water Sampling Program.
Sampling from the groundwater monitoring wells was conducted monthly at twelve locations and quarterly for five locations.
3.3 Program Execution The Ground Water Monitoring Program was executed as described in the preceding section.
Monitoring Well M-14 was installed in the fall of 2010, but only one sample had been collected due to inaccessibility of the well. The well was sampled monthly in 2011.
3,4 Program Modifications There were no changes to the program for 2011.
E-4
3.5 Results and Discussions Results obtained show tritium in ground water samples at or near expected natural background levels, with the exception of monitoring wells, MW-9A and MW-10.
Excluding data for wells MW-9A and MW-1 0, the 2011 sample results are similar or slightly lower than averages seen in 2010 and within the range of expected background tritium levels in groundwater, due to tritium concentrations measured in precipitation. Sampling points in North America have shown tritium concentrations in precipitation ranging from 5 pCi/L to 157 pCi/L (Environmental Isotope Data No. 10; World Survey of Isotope Concentration in Precipitation (1988-1991).
The tritium activity detected at sites MW-9A and MW-10 ranged from a high of 2317 pCi/L to
< 500 pCi/L. The levels were significantly lower than measurements taken in 2010. Previous investigations concluded that the higher tritium activity was due to a 1981 spill from the Condensate Storage Tanks, that had infiltrated the surface and migrated towards MW-9.
None of the groundwater samples analyzed for gamma-emitting isotopes showed activity greater than LLD.
E-5
Table E-1. Sample Collection and Analysis Program, Ground Water.
Medium Number Sample Codes Collection type Analysis Type Ground Water 25 MW-4, MW-5, MW-6, MW-7, Grab H-3, Gamma Quarterly MW-8 Ground Water 142 MW-1, MW-2, MW-3, MW-gA, Grab. H-3 Monthly MW-9B, MW-10, MW-11, MW-12A, MW-12B, MW-13A, MW-1i3B, MW-14 Table E-2. Sampling locations for Ground Water Monitoring Wells.
Sample Type Vendor Well Distance from Compass Sector Code Number Stack (miles) Heading from Stack Ground Water M-33 MW-1 0.11 299 WNW Ground Water M-34 MW-2 0.14 301 WNW Ground Water M-35 MW-3 0.15 305 NW Ground Water M-36 MW-4 0.1 25 NNE Ground Water M-37 MW-5 0.1 253 WSW Ground Water M-38 MW-6 229 Feet 228 SW Ground Water M-39 MW-7 0.2 66 ENE Ground Water M-40 MW-8 0.3 150 SSE Ground Water M-44 MW-9A 0.1 310 NW Ground Water M-51 MW-9B 0.1 310 NW Ground Water M-45 MW-10 0.1 292 WNW Ground Water M-46 MW-1 1 0.1 283 WNW Ground Water M-47 MW-12A 0.1 330 NW Ground Water M-48 MW-12B 0.1 326 NW Ground Water M-49 MW-13A 0.12 316 NW Ground Water M-50 MW-13B 0.12 316 NW Ground Water M-52 MW-14 0.17 306 NW E-6
Table E-3. Ground Water Monitoring Program Summary.
Name of Facility Monticello Nuclear Generating Plant Docket No. 50-263 Location of Facility Wright, Minnesota Reporting Period January-December, 2011
( County, State )
Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)' Mean (F)c Mean (F)c Routine (Units) Analyses' Range' Locationd Range' Range' Results' Groundwater H-3 166 500 819 (13/166) MW-9A, Onsite, 1445 (3/12) none 13 Monitoring Wells (540-2317) 0.1 mi,@ 310°/NW (820-2317)
(pCi/L) GS 142 Mn-54 10 < LLD none 0 Fe-59 30 < LLD none 0 Co-58 10 < LLD none 0 Co-60 10 < LLD none 0 Zn-65 30 < LLD - none 0 Zr-Nb-95 15 < LLD none 0 Cs-134 10 < LLD none 0 Cs-137 10 < LLD none 0 Ba-La-140 15 < LLD none 0 Ce-144 56 < LLD none 0 Stormwater H-3 7 500 679 (2/7) Sewer Lift Station 679 (2/7) none 2 Runoff (585-772) On-site (585-772)
(pCi/L) GS 3 Mn-54 10 < LLD none 0 Fe-59 30 < LLD none 0 Co-58 10 < LLD none 0 Co-60 10 < LLD none 0 Zn-65 30 < LLD none 0 Zr-Nb-95 15 < LLD none 0 1-131 30 < LLD none 0 Cs-134 10 < LLD none 0 Cs-137 10 < LLD none 0 Ba-La-140 15 < LLD none 0 Ce-144 45 < LLD none 0 GB = gross beta, GS = gamma scan.
b LLD = nominal lower limit of detection based on a 4.66 sigma counting error for background sample.
c Mean and range are based on detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (F).
d Locations are specified: (1) by name, and/or station code 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.
E-7
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