ML113260379
| ML113260379 | |
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| Site: | Monticello  |
| Issue date: | 12/31/1992 |
| From: | Huebner L Teledyne Isotopes Midwest Lab |
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NORTHERN STATES POWER COMPANY MINNEAPOLIS, MINNESOTA MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263 LICENSE NO. DPR-22 ANNUAL REPORT TO THE UNITED STATES REGULATORY COMMISSION Radiation Environmental Monitoring Program January 1, 1992 to December 31, 1992 Project No. 8010 Prepared under Contract I. by TELEDYNE ISOTOPES MIDWEST LABORATORY Project No. 8010 Approved by:
lt 6L
.4 Huebner Gtneral Manager 23 April 93 9305040343 930430 PDR ADOCK 05000263 R
PREFACE The staff of Teledyne Isotopes Midwest Laboratory was responsible for the acquisition of the data presented in this report. Samples were collected by members of the staff of the Nuclear Radiological Services Department. The report was prepared by L.G. Huebner, General Manager, Teledyne Isotopes Midwest Laboratory. He was assisted in the report preparation by other staff members of this laboratory.
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TABLE OF CONTENTS No.
Preface...........................................................................................................................................
ii List of Tables...............................................................................................................................i v
1.0 IN TRO DU CTIO N.......................................................................................................................
1 2.0 SU M M A RY...........................................................................................................................
- ...... 2 3.0 RADIATION ENVIRONMENTAL MONITORING PROGRAM (REMP)........
3 3.1 Program D esign and Data Interpretation........................................................................
3 3.2 Program D escription........................................................................................................
4 33 Program Execution..........................................................................................................
5 3.4 Laboratory Procedures...................................................................................................
6 3.5 Program M odifications..................................................................................................
6 36 Land U se Census..................................................................................................................
6 4.0 RESU LTS AN D DISCU SSIO N...........................................................................................
8 4.1 Atmospheric Nuclear Detonations and Nuclear Accidents..................................
8 4.2 Program Findings.................................................................................................................
8 5.0 TA BLES................................................................................................................................
1.......12 6.0 REFEREN CES CITED..........................................................................................................
24 APPENDICES A
Interlaboratory Com parison Program Results................................................................
A-1 B D ata Reporting Conventions..........................................................................................
B-1 C
Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Area.....................................................
C-1 D
Sam pling Location' M aps..................................................................................................
D-1 111
LIST OF TABLES No.
Title 5.1 Sample Collection and Analysis Program, 1992.............................................................
13 5.2 Sam pling Locations..............................................................................................................
15 53 Missed Collections and Analyses, 1992............................................................................17 5.4 Environmental Radiological Monitoring Program Summary..................................18 In addition, the following tables are in the Appendices:
Appendix A A-1 Interlaboratory Comparison Program Results, 1988-1992.............................................
A-3 A-2 Interlaboratory Comparison Program Results, (TLDs)....................
A-18 A-3 In-house Spiked Sam ples...................................................................................................
A-22 A-4 In-house "Blank" Samples A-29 Attachment B: Acceptance Criteria for Spiked Samples A-35 Addendum to Appendix A: Explanation of the Results O utside of Control Lim its..................................................................................................
A-36 Appendix C C
Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Area..........................................................
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1.0 INTRODUCTION
This report summarizes and interprets results of the Radiation Environmental Monitoring Program (REMP) conducted by Teledyne Isotopes Midwest Laboratory at the Monticello Nuclear Generating Plant, Monticello, Minnesota, during the period January - December, 1992. This Program monitors the levels of radioactivity in the air, terrestrial, and aquatic environments in order to assess the impact of the Plant on its surroundings.
Tabulation of the individual analyses made during the year are not included in this report.
These data are included in a reference document (Teledyne Isotopes Midwest Laboratory, 1993a) available at Northern States Power Company, Nuclear Generation Department.
Monticello Nuclear Generating Plant is a 545 MWe boiling water reactor located on the Mississippi River in Wright County, Minnesota, and operated by Northern States Power Company. Initial criticality was achieved on 10 December 1970. Full power was achieved on 5 March 1971 and commercial operation began on 30 June 1971.
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2.0
SUMMARY
The Radiation Environmental Monitoring Program (REMP) required by the U.S. Nuclear Regulatory Commission (NRC) Technical Specifications for the Monticello Nuclear Generating Plant is described. Results for 1992 are summarized and discussed.
Program findings show background levels of radioactivity in the environmental samples collected in the vicinity of the Monticello Nuclear Generating Plant.
No effect on the environment due to the operation of the Monticello Generating Plant is indicated.
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3.0 RADIATION ENVIRONMENTAL MONITORING PROGRAM (REMP) 3.1 Program Design and Data Interpretation The purpose of the Radiation Environmental Monitoring Program (REMP) at the Monticello Nuclear Generating Plant is to assess the impact of the Plant on its environment. For this purpose, samples are collected from the air, terrestrial, and aquatic environments and analyzed for radioactive content. In addition, ambient gamma radiation levels are monitored by thermoluminescent dosimeters (TLDs).
Sources of environmental radiation include the following:
(1) Natural background radiation arising from cosmic rays and primordial radionuclides; (2) Fallout from atmospheric nuclear detonations; (3) Releases from nuclear power plants; (4) Industrial and medical radioactive waste; and (5) Fallout from nuclear accidents.
In interpreting the data, effects due to the Plant must be distinguished from those due to other sources.
A major interpretive aid in assessment of these effects is the design of the monitoring program at the Monticello Plant which is based on the indicator-control concept. Most types of samples are collected both at indicator locations (nearby, downwind, or downstream) and at control locations (distant, upwind, or upstream).
A plant effect would be indicated if the radiation level at an indicator location was significantly larger than that at the control location. The difference would have to be greater than could be accounted for by typical fluctuations in radiation levels arising from other sources.
An additional interpretive technique involves analyses for specific radionuclides present in environmental samples collected from the Plant site.
The Plant's monitoring program includes analyses for tritium and iodine-131. Most samples are also analyzed for gamma-emitting isotopes with results for the following groups quantified: zirconium-95, cesium-137, cerium-144, beryllium-7, and potassium-40.
"The first three - gamma-emitting isotopes were selected as -radiological impact indicators because of the different characteristic proportions in which they appear in the fission product mix produced by a nuclear reactor and that produced by a nuclear 3
3.1 Program Design and Data Interpretation (continued) 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 nuclear power plant's effluents, but are not produced in significant quantities by nuclear detonations.
Other means of distinguishing sources of environmental radiation are employed in interpreting the data. Current radiation levels are compared with previous levels, including those measured before the plant became operational. Results of the Plant's Monitoring Program can be related to those obtained in other parts of the world.
Finally, results can be related to events known to cause elevated levels of radiation in the environment, e.g., atmospheric nuclear detonations.
3.2 Program Description The sampling and analysis schedule for the Radiation 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 reactor site. To assure that sampling is carried out in a reproducible manner, detailed sampling procedures have been prescribed (Teledyne Isotopes Midwest Laboratory, 1992). Maps of sampling locations are included in Appendix D.
To monitor the air environment, airborne particulates are collected on membrane filters by continuous pumping at five locations. Also, airborne iodine is collected by continuous pumping through charcoal filters at all of these locations. Filters are changed and counted weekly. Particulate filters are analyzed for gross beta activity and charcoal filters for iodine-131. Quarterly composites of particulate filters from each location are gamma-scanned on a HP Ge or Ge(Li) detector. One of the five locations is a control (M-1), and four are indicators (M-2, M-3, M-4, M-5). One of the indicators is located in the geographical sector expected to be most susceptible to any atmospheric emissions from the Plant (highest D/Q sector).
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3.2 Program Description (continued)
As a "Lessons Learned" commitment, ambient gamma radiation is monitored at thirty-seven (37) locations, using CaSO4:Dy dosimeter with four sensitive areas at each location: fourteen (14) in an inner ring in the general area of the site boundary, sixteen (16) in the outer ring within 4-5 mile radius, six (6) at special interest locations and one control location, 11.1 miles distant from the plant. They are replaced and measured quarterly. Also, a complete emergency set of TLDs for all locations is placed in the field at the same time as regular sets. The emergency set is returned to TIML quarterly for annealing and repackaging.
Milk samples are collected monthly from five farms (four indicator and one control).
The milk is collected biweekly during the growing season (May - October), because the milk animals may be on pasture. All samples are analyzed for iodine-131 and gamma-emitting isotopes.
Leafy green vegetables (cabbage) are collected annually from the highest D/Q garden and a control location (M-10) and analyzed for iodine-131. Corn and potatoes are collected annually only if the field is irrigated by water in which radioactive effluent has been discharged. Analysis is for gamma-emitting isotopes.
The terrestrial environment is also monitored by collection of well water from four locations on a quarterly basis. All samples are analyzed for tritium and gamma emitting isotopes.
River water is collected weekly at two locations, one upstream of the plant and one downstream.
Monthly composites are analyzed for gamma-emitting isotopes.
Quarterly composites are analyzed for tritium.
Drinking water is collected weekly from the City of Minneapolis water supply, which is taken from the Mississippi River downstream of the Plant. Monthly composites are analyzed for gross beta, iodine-131, and gamma-emitting isotopes. Quarterly composites are analyzed for tritium.
The aquatic environment is also monitored by semi-annual upstream and downstream collections of fish, algae or aquatic insects, and bottom sediments.
Shoreline sediment is collected semi-annually from one location. All samples are analyzed for gamma-emitting isotopes.
3.3 Program Execution The Program was executed as described in the preceding section with the following exceptions:
(1) Milk samples were not collected after 04-21-92 at the Peterson Dairy Farm (M-26). The farm is no longer in the dairy business.
(2) There was no TLD data for location M-06B for the second quarter of 1992.
The TLD's were lost in the field.
Deviations from the program are summarized in Table 5.3.
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3.4 Laboratory Procedures The iodine-131 analyses in milk and drinking water were made using a sensitive radiochemical procedure which involves separation of the iodine using an ion exchange method and solvent extraction and subsequent beta counting.
All gamma-spectroscopic analyses were performed with an HP Ge or Ge(Li) detector.
Levels of iodine-131 in cabbage and natural vegetation were determined by HP Ge or Ge(Li) spectrometry. The concentrations of airborne iodine-131 in charcoal samples were measured by HP Ge or Ge(Li) spectrometry.
Tritium was determined by a liquid scintillation technique.
Analytical procedures used by the Teledyne Isotopes Midwest Laboratory are specified in detail elsewhere (Teledyne Isotopes Midwest Laboratory, 1992).
Procedures are based on those prescribed by the National Center for Radiological Health of the U.S. Public Health Service (U.S. Public Health Service, 1967) and by the Health and Safety Laboratory of the U.S. Atomic Energy Commission (U.S. Atomic Energy Commission, 1972).
Teledyne Isotopes Midwest Laboratory has a comprehensive quality control/quality assurance program designed to assure the reliability of data obtained. Details of TIML's QA Program are presented elsewhere (Teledyne Isotopes Midwest Laboratory, 1993). The TIML QA Program includes participation in Interlaboratory Comparison (crosscheck) Programs. Results obtained in crosscheck programs are presented in Appendix A.
3.5 Program Modifications One indicator location for milk (M-26) Peterson Farm, went out of business in April, 1992.
3.6 Land Use Census In accordance with the Technical Specifications 4.16 Paragraph B1 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.
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3.6 Land Use Census (continued)
The 1992 land use census was completed on August 28, 1992, and identified two changes in the highest D/Q locations. The Peterson Farm (M-26) is no longer in the dairy business. The Hoglund Farm (M-28) is now ranked as the highest D/Q location for milk. The garden location moved from the SSW sector to the SSE sector. The highest D/Q residence remained the same.
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4.0 RESULTS AND DISCUSSION All of the scheduled collections and analyses were made except those listed in Table 5.3.
All results are summarized in Table 5.4 in a format recommended by the Nuclear Regulatory Commission in Regulatory Guide 4.8. For each type of analysis of each sampled medium, this table lists the mean and range for all indicator locations and for all control locations. The locations with the highest mean and range are also shown.
4.1 Atmospheric Nuclear Detonations and Nuclear Accidents There were no reported atmospheric nuclear tests in 1992. The last reported test was conducted by the People's Republic of China on October 16, 1980. The reported yield was in the 200 kiloton to 1 megaton range.
There were no reported accidents at nuclear facilities in 1992.
4.2 Program Findings Results obtained show background levels of radioactivity in the environmental samples collected in the vicinity of the Monticello Nuclear Generating Plant in 1992.
Ambient Radiation (TLDs)
Ambient radiation was measured in the general area of site boundary, at outer ring 4
- 5 mi distant from the Plant, at special interest areas and at one control location.
The means were identical at both inner and outer rings (15.1 mR/91 days). The mean at special locations was 15.2 mR/91 days. The mean at the controf location was 14.4 mR/91 days. The differences are not statistically significant. The dose rates measured were similar to those observed in 1978, 1983, 1984, 1985, 1986, 1987, 1988, 1989, 1990, and 1991 (12.3, 12.5, 13.6, 14.2, 15.3, 15.4, 15.2, 15.2, 16.2, and 15.5 mR/91 days, respectively). No Plant effect on ambient gamma radiation was indicated.
Airborne Particulates The average annual gross beta concentration in airborne particulates was identical at indicator and control locations (0.023 pCi/m 3) and was nearly identical or similar to the levels observed in 1982 (0.026 pCi/m 3), 1983 (0.023 pCi/m 3), 1984 (0.024 pCi/mi3 ),
1985 (0.025 pCi/m 3), 1986 (0.026 pCi/m 3), 1987 (0.026 pCi/m 3 ), 1988 (0.030 pCi/m 3) 8
Airborne Particulates (continued) 1989 (0.026 pCi/m 3), 1990 (0.023 pCi/m 3 ), and 1991 (0.024 pCi/m 3). The average of 0.026 pCi/m 3 for 1986 does not include the results from May 19 to June 9, 1986, which were influenced by the accident at Chernobyl.
A spring peak in beta activity had been observed almost annually for many years (Wilson et &, 1969). It had been attributed to fallout of nuclides from the stratosphere (Gold et al., 1964). It was pronounced in 1981, occurred to a lesser degree in 1982, and did not occur in 1983, 1984, 1985, 1987, 1988, 1989, 1990, 1991, or 1992. In 1986, the spring peak could not be identified because it was overshadowed by the releases of radioactivity from Chernobyl. The highest averages for gross beta were for the months of January and December, and the first and fourth quarters, as in 1983, 1984, 1985, 1986 (exclusive of the period between May 19, 1986 and June 9, 1986),
1987, 1988, 1989, 1990, and 1991.
Two pieces of evidence indicate conclusively that the elevated activity observed during the first and fourth quarters was not attributable to the Plant operation. In the first place, elevated activity of similar size occurred simultaneously at both indicator and control locations. Secondly, an identical pattern was observed at the Prairie Island Nuclear Generating Plant, about 100 miles distant from the Monticello Nuclear Generating Plant (Northern States Power Company, 1993b).
Gamma spectroscopic analysis of quarterly composites of air particulate filters yielded similar results for indicator and control locations. Beryllium-7, which is produced continuously in the upper atmosphere by cosmic radiation (Arnold and Al-Salih, 1955) was detected in all samples, with an average of 0.066 pCi/m 3 at both indicators and control locations.
All other gamma-emitting isotopes were below their respective LLD limits.
Airborne Iodine Weekly levels of airborne iodine-131 were below the lower limit detection (LLD) of 0.07 pCi/m 3 in all samples.
Milk Iodine-131 results were below the detection limit of 1.0 pCi/l in all samples.
Cesium-137 results were below the LLD level of 15 pCi/l in all samples.
No other gamma-emitting isotopes except naturally-occurring potassium-40 were detected in any of the milk samples. This is consistent with the finding of the National Center for Radiological Health that most radiocontaminants in feed do not find their way into. milk due to the selectiVe metabolism of the cow. The common exceptions are radioisotopes of potassium, cesium, strontium, barium, and iodine (National Center for Radiological Health, 1968).
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Milk (continued)
In summary, the milk data for 1992 show no radiological effects of the plant operation.
River Water and Drinking Water Tritium was below the LLD of 330 pCi/l in all samples. Gross beta in Minneapolis drinking water averaged 2.1 pCi/l and was lower than the average levels observed in 1977 (3.4 pCi/1), in 1978 (3.8 pCi/1), in 1979 (3.4 pCi/1), in 1980 (3.2 pCi/1), in 1981 (3.5 pCi/1), in 1982 (2.9 pCi/1), in 1983 (3.3 pCi/1), in 1984 (2.8 pCi/1), in 1985 (2.8 pCi/1), in 1986 (2.5 pCi/1), in 1987 (2.4 pCi/1), in 1988 (2.7 pCi/1), in 1989 (2.6 pCi/L), in 1990 (2.2 pci/L), and in 1991 (2.9 pCi/L). Comparisons with gross beta data reported by EPA for Minneapolis drinking water sample collected in 1975, 1976, 1977, and 1978 indicates that concentrations of these nuclides are remaining fairly constant and are in the range of drinking water levels in other parts of the country (U.S. Environmental Protection Agency, 1975, 1976, 1977, 1978). Gamma-emitting isotopes were below detection limits in all surface water samples. There was no indication of a plant effect.
Well Water The tritium level was below the LLD level of 330 pCi/1 in all samples. All of the gamma scan results were below detection limits. There was no indication of a plant effect.
Crops Two (2) samples of cabbage were collected in September and analyzed for iodine-131.
The 1-131 level was below 0.054 pCi/g wet weight in both samples. There was no indication of a plant effect. The field sampling personnel conducted a survey at Monticello Plant and found that there were no radioactive liquid effluents released into the Mississippi River. Therefore, it was not necessary to collect and analyze corn or potato samples.
Fish Fish samples were collected in May and October. Flesh was separated from the bones and gamma-scanned. Potassium-40, the naturally-occurring isotope, was found to be similar in upstream and downstream samples (2.45 and 2.68 pCi/g wet weight, respectively). All gamma-emitting isotopes were below their respective LLD levels.
There was no indication of a plant effect.
Invertebrates Two samples were collected in July and two in October. The samples were analyzed for gamma-emitting isotopes. All of the isotopes, except naturally-occurring K-40, were below detection limits.
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Invertebrates (continued)
Potassium-40 averaged 1.88 pCi/g wet weight at the control location and 1.00 pCi/g wet weight at the indicator location. There was no indication of a plant effect.
Bottom and Shoreline Sediments Bottom and shoreline sediment collections were made in June and October and analyzed for gamma-emitting isotopes. Cesium-137 was detected in two upstream and one downstream bottom sediment samples, averaging 0.082 pCi/g dry weight, and in two shoreline sediment samples, averaging 0.093 pCi/g dry weight, indicating the influence of fallout deposition. Similar levels of activities and distribution were observed in 1978-1991.
The only other gamma-emitting isotope detected was naturally-occurring potassium-40. There was no indication of a plant effect.
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5.0 TABLES 12
Table 5.1. Sample collection and analysis program, Monticello Nuclear Generating Plant, 1992.
Locations Collection Analysis Codes Type and Type and Medium No.
(and Type)a Frequencyb Frequencyc Ambient radiation (TLDs)
Airborne particulates Airborne Iodine Milk 37 M-01A - M-14A M-01B - M-16B M-1S - M-06S M-01C 5
M-1(C), M-2 M-3, MA, M-5 5
M1(C), M-2, M-3 MA, M-5 5
River water M-10, M-24, M-26, M-28, M-29 2
M-8(C), M-9 C/Q C/W C/W G/Md G/W Ambient gamma GB, GS (QC of each location) 1-131 1-131, GS GS(MC), H-3(QC)
Drinking water Well Water Edible cultivated crops Cabbage Edible cultivated crops Come Edible cultivated crops Potatoese Fish (one species edible portion)
Algae or Aquatic Insects M-14 M-10(C), M-11 M-12, M-13 M-10(C), M-27 M-19 M-21 2
M-8(C), M-9 2
M-8(C), M-9 G/W GB(MC), I-131(MC)
G/Q G/A G/A G/A G/SA G/SA H-3, GS 1-131 GS GS GS GS 13
Table 5.1. Sample collection and analysis program, Monticello Nuclear Generating Plant, 1992 (continued)
Locations Collection Analysis Codes Type and Type and Medium No.
(and Type)a Frequencyb Frequencyc Bottom Sediment 2
M-8(C), M-9 G/SA GS Shoreline Sediment 1
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.
c Analysis type is code as follows: GB = gross beta, GS = gamma spectroscopy, H-3 = tritium, 1-131 =
iodine 131. Analysis frequency is coded as follows: MC = monthly composite, QC = quarterly composite.
d Milk is collected biweekly during the grazing season (May - October) if milch animals are on pasture.
e Collected only if the field is irradiated by water in which liquid radioactive efluent has been discharged.
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Table 5.2. Sampling locations, Monticello Nuclear Generating Plant, 1992.
Distance and Type of Direction from Code Typea Collection Site Sampleb Site Stack Air Station M-1 Air Station M-2 Air Station M-3 Air Station M-4 Air Station M-5 Upstream of Plant Downstream of Plant Kirchenbauer Farm City of Monticello Plant Well #1 Ernst Residence City of Minneapolis Montissippi Park River Irrigated Corn Fieldc River Irrigated Potato Fieldc Weinand Farm Peterson Farm Wise Residence Highest D/Q Garden Hoglund Farm Holthaus Farm AP, AI AP, AI AP, AI AP, AI AP, AI RW, BS, BO, F RW, BS, BO, F M, WW, VE W W W W W W DW SS M-1 M-2 M-3 M4 M-5 M-8 M-9 M-10 M-11 M-12 M-13 M-14 M-15 M-19 M-21 M-24 M-26 M-27 M-28 M-29 M
M 11.1 mi @ 3060/NW 0.8 mi @ 1400/SE 0.6 mi @ 1040/ESE 0.9 mi @ 150*/SSE 2.7 mi @ 1360/SE 0.2 mi @ 2850/WNW 0.2 mi @ 620/ENE 11.5 mi @ 3230/NW 3.2 mi @ 128*/SE 0.2 mi @ 267*/W 0.6 mi @ 2020/SSW 36 mi @ 128 0/SE 1.6 mi @ 117 0/ESE 4.8 mi @ 1800/S 2.5 mi @ 1110/ESE 0.7 mi @ 2080/SSW 3.7 mi @ 300 0/WNW 4.1 mi @ 1730/S General Area of the Site Boundary North Boundary Road North Boundary Road North Boundary Road Biology Station Road Biology Station Road Biology Station Road County Road 75 County Road 75 County Road 75 County Road 75 County Road 75 County Road 75 North Boundary Road North Boundary Road TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD 0.7 mi @ 3530/N 0.8 mi @ 230/NNE 1.0 mi @ 43/NE 0.7 mi @ 92*/E 0.6 mi @ 112 0/ESE 0.6 mi @ 133 0/SE 0.5 mi @ 158 0/SSE 0.5 mi @ 183*/S 0.4 mi @ 2030 /SSW 0.3 ml @ 2250/SW 0.4 mi 0 2500/WSW 0.7 mi @ 2730/W 1.1 mi @ 317 0/NW 0.8 mi @ 338 0/NNW 15 C
C C
M M
VE M-01A M-02A M-03A M-04A M-05A M-06A M-07A M-08A M-09A M-10A M-11A M-12A M-13A M-14A
Table 5.2. Sampling locations, Monticello Nuclear Generating Plant, 1992 (continued)
Distance and Type of Direction from Code Typea Collection Site Sampleb Site Stack Approximately 4 to 5 miles Distant from the Plant M-01B Sherco #1 Air Station TLD 4.6 mi @ 020/N M-02B County Road 11 TLD 4.4 mi @ 170/NNE M-03B Intersection of County Road TLD 4.5 mi @ 490/NE
& Route 81 M-04B Sherco #6 Air Station TLD 4.2 mi @ 670/ENE M-05B City of Big Lake TLD 4.4 mi @ 870/E M-06B County Road #14 and 196th St.
TLD 4.3 mi @ 116 0/ESE M-07B Monte Industrial Drive TLD 4.4 mi @ 1350/SE M-08B Dale K. Larson Residence TLD 4.6 mi @ 162 0/SSE M-09B Norbert Weinand Farm TLD 4.7 mi @ 1800/S M-10B John Reisewitz Farm TLD 4.4 mi @ 2060/SSW M-11B Clifford Vanlith Farm TLD 4.2 mi @ 2250/SW M-12B Lake Maria State Park TLD 4.4 mi @ 2530/WSW M-13B Bridgewater Station TLD 4.1 mi @ 2710/W M-14B Richard K. Anderson Residence TLD 4.5 mi @ 2280/WNW M-15B Gary Williamson Residence TLD 4.5 mi @ 3080/NW M-16B Sand Plain Research Farm TLD 4.3 mi @ 3380/NNW Special Interest Locations M-01S Dickson Residence TLD 0.5 mi @ 166*/SSE M-02S Edgar Klucas Residence TLD 0.7 mi @ 142 0/SE M-03S Big Oaks Park TLD 1.3 mi @ 890/E M-04S Pinewood School TLD 2.3 mi @ 132 0/SE M-05S Roman Greener Residence TLD 2.5 mi @ 112 0/ESE M-06S Monte Service Center TLD 2.7 mi @ 1360/SE M-01C C
Kirchenbauer Farm TLD 11.5 mi @ 323*/NW a "C" denotes control location. All other locations are indicators.
b Sample Codes:
AP = Airborne particulates WW = Well water AI = Airborne Iodine BS = Bottom (river) sediments M = Milk SS = Shoreline Sediments VE = Vegetation/vegetables BO = Bottom organisms (periphyton or DW = Drinking water macroinvertebrates)
RW = River water F = Fish c Collected only if the field is irrigated by water in which liquid radioactive effluent has been discharged.
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Table 5.3. Missed collections and analyses for 1992 at the Monticello Nuclear Generating Plant. All required samples were collected and analyzed as scheduled except the following:
Collection Date Sample Location or Period Comments.
Milk M-26 05-11-92 Farm out of dairy business TLD M-06B 2nd Qtr., 1992 TLD lost in the field.
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.4. Radiological Environmental Monitoring Program Summary.
Name of Facility Monticello Nuclear Generating Plant.
Location of Facility Wright. Minnesota (County, State)
Docket No. 50-263 Reporting Period lanuary -December 1992 Sample Type and Indicator Location with Highest Control Number of Type Number of Locations Annus Mean Locations Non-routine (Units)
Analysesa LLDb Mean (F)c Mean (F)c Mean (F)c Resultse Rangec Location d Rangec Rangec TLD (mR/91 days)
Gamma 56 3.0 15.1 (56/56)
M-04A, Biology Stn.
16.3(4/4)
(See Control below.)
0 (Inner Ring, General (9.6-17.4)
Road 0.7 mi @ 92*/E (14.7-17.4)
Area at Site Boundary)
M-12A, County Road 16.3(4/4) 75 0.7 mi@ 273-/W (13.8-17.3)
TLD (mR/91 days)
(Inner Ring, 4-5 Gamma 63 3.0 15.1 (63/63)
M-05B, City of Big 19.8(4/4)
(See Control below.)
0 miles distant)
(10.4-21.2)
Lake 4.4 mi@ 87"/E (19.0-21.2)
TLD (mR/91 days)
(Special Interest Gamma 24 3.0 15.2 (24/24)
M-06S, Monte Service 16.8(4/4)
(See Control below.)
0 Areas)
(11.6-18.1)
Center 2.7*mi O (14.9-18.1) 136-/SE TLD (mR/91 days)
(Control)
Gamma 4
3.0 None M-01C, Kirchenbauer 14.4(4/4) 14.4 (4/4) 0 Farm, 11.5 mi @
(12.4-16.0)
(12.4-16.0) 3230/NW Airborne GB 260 0.003 0.023 (208/208)
All locations had 0.023 (260/260) 0.023 (52/52) 0 Particulates (0.009-0.055) identical means (0.009-0.055)
(0.010-0.051)
(pCi/i
- 3)
GS 20 Be-7 0.020 0.065 (16/16)
M-1, Station M-1 0.070(4/4) 0.070(4/4) 0 (0.040-0.103) 11.1 mi O 306*/NW (0.051-0.096)
(0.051-0.096)
Mn-54 0.0025
<LLD
<LLD 0
Co-58 0.0032
<LLD
<LLD 0
Co-60 0.0031
<LLD
<LLD 0
Zn-65 0.0067
<LLD
<LLD 0
Zr-Nb-95 0.0062
<LLD
<LLD 0
Ru-103 0.0029
<LLD
<LLD 0
Ru-106 0.026
<LLD
<LLD 0
Cs-134 0.0024
<LLD
<LLD 0
I.00
5.4. Radiological Environmental Monitoring Program Summary.
Name of Facility Monticello Nuclear Generating Plant Location of Facility Wright, Minnesota (County, State)
Docket No. 5063 Reporting Period lanuary - December 1992 Sample Type and Indicator Location with Highest Control Number of Type Number of Locations AnnuslMean Locations Non-routine (Units)
Analy a LLDb Mean (F)c Mean (F)c Mean (F)C Resultse Rangec Location d Rangec Rane Airborne CS Particulates (pC/m 3 )0 (continued)
Cs-137 0.0024
<LLD
<LLD 0
Ba-La-140 0.010
<LLD
<LLD 0
Ce-141 0.0044
<LLD
<LLD 0
Ce-144 0.013
<LLD
<LLD 0
Airborne Iodine 1-131 260 0.07
<LLD 0
(pC//m3 )
<LLD
- Milk, 1-131 76 1.0
<LLD
<LLD 0
(pCi/L)
M-10, Kirchenbauer 1310(18/18) 1310(18/18) 0 (1050-1540)
Farm 11.5 mi @
(1170-1450)
(1170-1450) 3230/NW Cs-134 15
<LLD
<LLD 0
Cs-137 15
<LLD LLD 0
Other gammas 15
<LLD
<LLD 0
River Water H-3 8
330
<LLD
<LLD 0
(pCl/L)
<LLD
<LLD 0
Fe-59 30
<LLD
<LLD 0
CO58 15
<LLD
<LLD 0
Co-60 15
<LLD
<LLD 0
I.
to0
a 5.4. Radiological Environmental Monitoring Program Summary.
Name of Facility Monticello Nuclear Generating Plant Location of Facility Wright, Minnesota_
(County, State)
Docket No. 50-263 Reporting Period January - December 1992 Sample Type and Indicator Location with Highest Control Numberof Type Number of Locations AnnualMean Locations Non-routine (Units)
Analysesa LLDb Mean (F)c Mean (F)c Mean (F)c Resultse Rangec Location d Rangec Rangec River Water Zn-65 30
<LLD
<LLD 0
(pCi/L) (continued)
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 54
<LLD
<LLD 0
Drinking Water GB 12 1.0 2.1 (12/12)
M-14, Minneapolis 2.1 (12/12)
None 0
(pCi/L)
(1.4-2.6) 36mi@128./SE (1.4-2.6) 1-131 12 1.0
<LLD None 0
H-3 4
330
<LLD None 0
GS 12 Mn-54 15
<LLD None 0
Fe-59 30
<LLD None 0
CO-58 15
<LLD None 0
Co60 15
<LLD None 0
Zn-65 30
<LLD None 0
Zr-Nb-95 15
<LLD None 0
Cs-134 10
<LLD None 0
Cs-137 10
<LLD None 0
Ba-La-140 15
<LLD None 0
Ce-144 48
<LLD None 0
.4. Radiological Environmental Monitoring Program Summary.
Name of Facility Monticello Nuclear Generating Plant.
Location of Facility Wright, Minnesota_
(County, State)
Docet No. 50-269 Reporting Period January - December 1992 Sample Type and Indicator Location with Highest Control Number of Type Number of Locations AnnualMean Locations Non-routine (Units)
Analysesa LLDb Mean (F)c Mean ()C Mean (F)c Resultse Rangec Location d Rangec Rangec Well Water H-3 16 330
<LLD
-LLD 0
(pCi/L)
GS 16 Mn-54 15
<LLD
<LLD 0
Fe-59 30
<LLD
<LLD 0
Co.58 15
<LLD
<LLD 0
Co-60 15
<LLD LLD 0
Zn-65 30
<LLD
<LLD 0
Zr-Nb-95 15
<LLD
<LLD 0
Cs-134 15
<LLD
<LLD 0
Cs-137 18
<LLD LLD 0
Ba-La-140 15
<LLD
<LLD 0
Ce-144 55
<LLD LLD 0
Crops - Cabbage 1-131 2
0.054
<LLD
<LLD 0
(pCi/g wet)
Fish (pCi/g wet)
GS 4
K-40 0.1 2.68 (2/2)
M-9, Downstream of 2.68(2/2) 2.45(2/2) 0 (2.62-2.73)
Plant, 0.2 mi @
(2.62-2.73)
(2.33-2.57) 620/ENE Mn-54 0.022
<LLD
<LLD 0
Fe-59 0.098
<LLD
<LLD 0
Co-58 0.034
<LLD
<LLD 0
Co-60 0.023
<LLD
<LLD 0
.4. Radiological Environmental Monitoring Program Summary.
Name of Facility Monticello Nuclear Generating Plant Location of Facility Wrig Minneta (County, State)
Docket No. 5269 Reporting Period January - December 1992 Sample Type and Indicator Location with Highest Control Number of Type Number of Locations Annua Mean Locations Non-routine (Units)
Analysesa LLDb Mean (F)c Mean (F)c Mean (F)c Resultse Rangec Location d Rangec Rangec Fish - Flesh CS (pC/g wet)
(continued)
Zn-65 0.054
<LLD
<LLD 0
Nb-95 0.067
<LLD
<LLD 0
Zr-95 0.068
<LLD
<LLD 0
Cs-134 0.018
<LLD
<LLD 0
Cs-137 0.018
<LLD
<LLD 0
Ba-La-140 0.75
<LLD
<LLD 0
Invertebrates CS 4
(pC/g wet)
Be-7 1.95
<LLD
<LLD 0
K-40 0.1 1.00(2/2)
M-8, Upstream of 1.88(2/2) 1.88 (2/2) 0 (0.37-1.63)
Plant, 02 ml @
(1.82-1.94)
(1.82-1.94)
<LLD 2850/WNW Mn-54 0.26
<LLD
<LLD 0
Co-58 0.23
<LLD
<LLD 0
Co-60 0.22
<LLD
<LLD 0
Zn-65 0.44
<LLD
<LLD 0
Zr-Nb-95 0.46
<LLD
<LLD 0
Ru-10 0.24
<LLD
<LLD 0
Ru-106 1.64
<LLD
<LLD 0
Cs-134 0.19
<LLD
<LLD 0
Cs-137 0.18
<LLD
<LLD 0
Ba-La-140 0.44
<LLD
<LLD 0
Ce-141 0.50
<LLD
<LLD 0
Ce-144 1.67
<LLD
<LLD 0
N\\3
. Radiological Environmental Monitoring Program Summary.
Name of Facility Monticello Nuclear Generating Plant Location of Facility Wright, Minnesota (County, State)
Docket No. 523 Reporting Period january -December 1992 Sample Type and Indicator Location with Highest Control Number of Type Number at Locations Annua Mean Locations Non-routine (Units)
Analysesa LLDb Mean (F)c Mean (F)c Mean (F)c Resultse Rangec Location d Rangec Rangec Bottom and GS 6
Shoreline Sediments (pCi/g Be-7 0.52
<LLD
<LLD 0
dry)
K-40 0.5 10.72 (4/4)
M-8, Upstream of 11.71 (2/2) 11.71 (2/2) 0 (8.66-11.58)
Plant, 0.2 mi @
(10.42-13.00)
(10.42-13.00) 285-/WNW Mn-54 0.031
<LLD
<LLD 0
CO-58 0.051
<LLD
<LLD 0
Co40 0.038
<LLD
<LLD 0
Zn-65 0.086
<LLD
<LLD 0
Zr-95 0.10
<LLD
<LLD 0
Nb-95 0.12
<LLD
<LLD 0
Ru-103 0.089
<LLD
<LLD 0
Ru-106 0.26
<LLD
<LLD 0
C9-134 0.036
<LLD
<LLD 0
Cs-137 0.025 0.087(3/4)
M-15, Montissippi 0.093(2/2) 0.086(2/2) 0 (0.074-0.11)
Park 1.6 mi @
(0.076-0.11)
(0.071-0.10) 117*/ESE Ba-La-140 4.77
<LLD
<LLD 0
Ce-141 0.19
<LLD
<LLD 0
Ce-144 0.18
<LLD
<LLD 0
a GB =Gro beta GS= gamma scan.
b LLD = Nominal lower limit of detection based on 4.66 sigma 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 code (Table 2) and (2) by distance, direction and sector 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 considred non-routine if it exceeds ten times the typical pre-operational value for the medium or location.
6.0 REFERENCES
CITED Arnold, J. R. and H. A. Al-Salih. 1955. Beryllium-7 Produced by Cosmic Rays. Science 121:
451-453.
Eisenbud, M. 1963. Environmental Radioactivity, McGraw-Hill, New York, New York, pp.
213, ?75 and 276.
Gold, S., H.W. Barkhau, B. Shlein, and B. Kahn, 1964. Measurement of Naturally Occurring Radionuclides in Air, in the Natural Environment, University of Chicago Press, Illinois, 369-382.
Hazleton Environmental Sciences Corporation.
1979a.
Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1978.
1979b.
Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1978.
1980a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1979.
1980b.
Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1979.
1981a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1980.
1981b.
Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1980.
1982a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1981.
1982b.
Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1981.
1983a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1982.
1983b.
Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1982.
24 I
I.
Hohenemser, C. M. Deicher, A. Ernst, H. Hofsass, G. Lindner, E. Racknagel, 1986.
"Chernobyl," Chemtech October 1986, pp. 596-605.
National Center for Radiological Health, 1968. Radiological Helath and Data Reports, Vol.
9, Number 12, 730-746.
Northern States Power Company. 1977. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1, 1976 to December 31, 1976 (prepared by NALCO Environmental Sciences). Minneapolis, Minnesota.
. 1978. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1, 1977 to December 31, 1977 (prepared by Hazleton Environmental Sciences).
Minneapolis, Minnesota.
. 1979. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1, 1978 to December 31, 1978 (prepared by Hazleton Environmental Sciences). Minneapolis, Minnesota.
. 1980.
Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1, 1979 to December 31, 1979 (prepared by Hazleton Environmental Sciences). Minneapolis, Minnesota.
. 1981.
Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1, 1980 to December 31, 1980 (prepared by Hazleton Environmental Sciences). Minneapolis, Minnesota.
. 1982. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1, 1981 to December 31, 1981 (prepared by Hazleton Environmental Sciences).. Minneapolis, Minnesota.
. 1983. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1, 1982 to December 31, 1982 (prepared by Hazleton Environmental Sciences). Minneapolis, Minnesota.
. 1984.
Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1, 1983 to December 31, 1983 (prepared by Teledyne Isotopes Midwest Laboratories).
Minneapolis, Minnesota.
25 h
I.
It St
. 1985. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1, 1984 to December 31, 1984 (prepared by Teledyne Isotopes Midwest Laboratories).
Minneapolis, Minnesota.
. 1986. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1, 1985 to December 31, 1985 (prepared by Teledyne Isotopes Midwest Laboratories).
Minneapolis, Minnesota.
. 1987. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1,.1986 to December 31, 1986 (prepared by Teledyne Isotopes Midwest Laboratories).
Minneapolis, Minnesota.
. 1988. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1, 1987 to December 31, 1987 (prepared by Teledyne Isotopes Midwest Laboratories).
Minneapolis, Minnesota.
. 1989. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1, 1988 to December 31, 1988 (prepared by Teledyne Isotopes Midwest Laboratories).
Minneapolis, Minnesota.
. 1990. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1, 1989 to December 31, 1989 (prepared by Teledyne Isotopes Midwest Laboratories).
Minneapolis, Minnesota.
. 1991.
Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1, 1990 to December 31, 1990 (prepared by Teledyne Isotopes Midwest Laboratories).
Minneapolis, Minnesota.
. 1992. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1, 1991 to December 31, 1991 (prepared by Teledyne Isotopes Midwest Laboratories).
Minneapolis, Minnesota.
Teledyne Isotopes Midwest Laboratory 1992. Analytical Procedures Manual, Revision 5, 21 August 1992.
. 1992. Quality Assurance Program Manual, Revision 1, 20 August 1992.
. 1992. Quality Control Procedures Manual, Revision 16, 14 August 1992.
26
. 1992. Quality Control Program, Revision 12, 20 April 1992.
. 1984a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January -December 1983.
1984b.
Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1983.
. 1985a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1984.
1985b.
Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1984.
. 1986a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1985.
. 1986b. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1985.
. 1987. Sampling Procedures, Monticello Nuclear Generating Plant, Revision 16, 18 December 1987.
. 1987a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1986.
1987b.
Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1986.
. 1988a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January -December 1987.
- 1988b.
Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1987.
. 1989a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1988.
1989b.
Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1988.
. 1990a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1989.
1990b.
Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1989.
27
. 1991a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1990.
1991b.
Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1990.
. 1992a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1991.
1992b.
Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1991.
. 1993a. Radiation Environmental Monitoring for Monticello Nuclear Gefierating Plant, Complete Analysis Data Tables, January - December 1992.
. 1993b.
Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1992.
U.S. Atomic Energy Commission.
1972. HASL Procedures Manual, Health and Safety Laboratory, New York, NY., 10014.
U.S. Public Health Service.
1967. Radioassay Procedures for Environmental Samples, National Center for Radiological Health, Rockville, Maryland (Public Health Service Publication No. 999-RH-27).
Wilson, D. W., G. M. Ward and J. E. Johnson. 1969. In Environmental Contamination by Radioactive Materials, International Atomic Energy Agency. p.125.
28
, i
APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS NOTE: TIML participates in intercomparison studies administered by U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada.
The results are reported in Appendix A. Also reported are results of in-house spikes and blanks. Appendix A is updated quarterly; the complete Appendix is included in January, April, July and October monthly reports only. Please refer to these reports for information.
January, 1993
I,
Interlaboratory Comparison Program Results Teledyne Isotopes Midwest Laboratory (formerly Hazleton Environmental Sciences) has participated in interlaboratory comparison (crosscheck) programs since the formulation of its quality control program in December 1971. These programs are operated by agencies which supply environmental-type samples (e.g., milk or water) containing concentrations of radionuclides known to the issuing agency but not to participant laboratories. The purpose of such a program is to provide an independent check on the laboratory's analytical procedures and to alert it to any possible problems.
Participant laboratories measure the concentration of specified radionuclides and report them to the issuing agency. Several months later, the agency reports the known values to the participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used.
The results in Table A-1 were obtained through participation in the environmental sample crosscheck program for milk, water, air filters, and food samples during the period January 1988 through December 1992.
This program has been conducted by the U.S. Environmental Protection Agency Intercomparison and Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, Las Vegas, Nevada.
The results in Table A-2 were obtained for thermoluminescent dosimeters (TLDs) during the period 1976, 1977, 1979, 1980, 1984, and 1985-86 through participation in the Second, Third, Fourth, Fifth, Seventh, and Eighth International Intercomparison of Environmental Dosimeters under the sponsorships listed in Table A-2. Also Teledyne testing results are listed.
Table A-3 lists results of the analyses on in-house spiked samples.
Table A-4 lists results of the analyses on in-house "blank" samples.
Attachment B lists acceptance criteria for "spiked" samples.
Addendum to Appendix A provides explanation for out-of-limit results.
A-2
i.,
Table A-1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne Isotopes Midwest Laboratory results for milk, water, air filters, and food samples, 1988 through 1992.a Concentration in pCifLb lab Sample Date TIML Result EPA Resultd Code Type Collected Analysis
+/-2oc 1s, N=1 Control Limits STW-521 Water STW-523 Water STF-524 Food STW-525 Water STW-526 Water STW-527 Water STM-528 Milk STW-529 Water STW-530 Water STAF-531 Air Filter STW-532 Water Jan 1988 Jan 1988 Jan 1988 Feb 1988 Feb 1988 Feb 1988 Feb 1988 Mar 1988 Mar 1988 Mar 1988 Apr 1988 Sr-89 Sr-90 27.3+/-5.0 15.3+/-1.2 Gr. alpha 2.3+/-1.2 Gr. beta 7.7+/-1.2 Sr-89 Sr-90 1-131 Cs-137 K
Co-60 Zn-65 Ru-106 Cs-134 Cs-137 H-3 Uranium 1-131 Ra-226 Ra-228 44.0+/-4.0 53.0+/-2.0 102.3+/-4.2 95.7+/-6.4 1011+/-158 69.3+/-2.3 99.0+/-3.4 92.7+/-14.4 61.7+/-8.0 99.7+/-3.0 3453+/-103 3327+/-362 2700-3954 3.0+/-0.0 4.7+/-1.2 7.1+/-0.6 NAe Gr. alpha 4.3+/-1.2 Gr. beta 13.3+/-13 Gr. alpha Cr. beta Sr-90 Cs-137 1-131 21.0+/-2.0 48.0+/-0.0 16.7+/-1.2 18.7+/-13 9.0+/-2.0 A-3 30.0+/-5.0 15.0+/-1.5 4.0+/-5.0 8.0+/-5.0 46.0+/-5.0 55.0+/-2.8 102.0+/-10.2 91.0+/-5.0 1230+/-62 69.0+/-5.0 94.0+/-9.4 105.0+/-10.5 64.0+/-5.0 94.0+/-5.0 21.3-38.7 12.4-17.6
.0.0-12.7 0.0-16.7 37.3-54.7 50.2-59.8 84.3-119.7 82.3-99.7 1124-1336 60.3-77.7 77.7-110.3 86.8-123.2 55.3-72.7 85.3-102.7 3.0+/-6.0 4.0+/-0.4 7.6+/-1.1 7.7+/-1.2 6.0+/-5.0 13.0+/-5.0 20.0+/-5.0 50.0+/-5.0 17.0+/-1.5 16.0+/-5.0 7.5+/-0.8 0.0-13.4 3.3-4.7 5.6-9.6 5.7-9.7 0.0-14.7 4.1-21.7 11.3-28.7 41.3-58.7 14.4-19.6 7.3-24.7 6.2-8.8
Table A-1. (continued)
Concentration in pCi/Lb lab Sample Date TIML Result EPA Resultd Code Type Collected Analysis t2oc 1s, N=1 Control Limits STW-533 534 Water (Blind)
Sample A Sample B Apr 1988 Gr. alpha Ra-226 Ra-228 Uranium Gr. beta Sr-89 Sr-90 Co-60 Cs-134 Cs-137 NDf ND ND 6.0+/-6.0 ND 33+/-1.2 53+/-1.2 63.3+/-13 7.7+/-1.2 83+/-1.2 46.0+/-11.0 6.4+/-1.0 5.6+/-0.8 6.0+/-6.0 57.0+/-5.0 5.0+/-5.0 5.0+/-1.5 50.0+/-5.0 7.0+/-5.0 7.0+/-5.0 27.0-65.0 4.7-8.1 4.2-7.0 0.0-16.4 48.3-65.7 0.0-13.7 2.4-7.6
.41.3-58.7 0.0-15.7 0.0-15.7 STU-535 Urine STW-536 Water STW-538 Water STW-539 Water STM-541 Milk STW-542 Water STF-543 Food Apr 1988 Apr 1988 Jun 1988 Jun 1988 Jun 1988 Jul 1988 Jul 1988 H-3 Sr-89 Sr-90 Cr-51 Co-60 Zn-65 Ru-106 Cs-134 Cs-137 H-3 Sr-89 Sr-90 1-131 Cs-137 K
Gr. alpha Gr. beta Sr-89 Sr-90 1-131 Cs-137 K
6483+/-155 6202+/-620 5128-7276 14.7+/-13 20.0+2.0 331.7+/-13.0 16.0+/-2.0 107.7+/-11.4 191.3+/-11.0 18.3+/-4.6 26.3+/-1.2 5586+/-92 33.7+/-11.4 55.3+/-5.8 103.7+/-3.1 52.7+/-3.1 1587+/-23 8.7+/-4.2 53+/-1.2 NDf ND 115.0+/-53 52.7+/-6.4 1190+/-66 20.0+/-5.0 20.0+/-1.5 302.0+/-30.0 15.0+/-5.0 101.0+/-10.0 195.0+/-20.0 20.0+/-5.0 25.0+/-5.0 11.3-28.7 17.4-22.6 250.0-354.0 6.3-23.7 83.7-118.3 60.4-229.6 11.3-28.7 16.3-33.7 5565+/-557 4600-6530 40.0+/-5.0 60.0+/-3.0 94.0+/-9.0 51.0+/-5.0 1600+/-80 15.0+/-5.0 4.0+/-5.0 33.0+/-5.0 34.0+/-2.0 107.0+/-11.0 49.0+/-5.0 1240+/-62 31.3-48.7 54.8-65.2 78.4-109.6 42.3-59.7 1461-1739 6.3-23.7 0.0-127 24.3-41.7 30.5-37.5 88.0-126.0 40.3-57.7 1133-1347 A-4
.5 Ii Table A-1. (continued)
Concentration in pCifLb Lab Sample Date TIML Result EPA Resultd Code Type Collected Analysis
+/-2oc 1s, N=1 Control Limits STW-544 Water STW-545 Water STW-546 Water STAF-547 Aug 1988 Aug 1988 Aug 1988 Air Filter Aug 1988 STW-548 Water STW-549 Water STW-550 Water Sep 1988 Sep 1988 Oct 1988 1-131 Pu-239 Uranium Gr. alpha Gr. beta Sr-90 Cs-137 Ra-226 Ra-228 Gr. alpha Gr. beta Cr-51 Co-60 Zn-65 Ru-106 Cs-134 Cs-137 80.00.0 11.0+/-0.2 6.0+/-0.0 8.0+/-0.0 26.3+/-1.2 8.0+/-2.0 13.0+/-2.0 9.3+/-0.5 5.8+/-0.4 7.0+/-2.0 11.3+/-1.2 252.0+/-14.0 26.0+/-2.0 158.3+/-10.2 153.019.2 28.7+/-5.0 16.3+/-1.2 76.0+/-8.0 10.2+/-1.0 6.0+/-6.0 8.0+/-5.0 29.0+/-5.0 8.0+/-1.5 12.0+/-5.0 8.4+/-2.6 5.4+/-1.6 8.0+/-5.0 10.0+/-5.0 251.0+/-25.0 25.0+/-5.0 151.0+/-15.0 152.0+/-15.0 25.0+/-5.0 15.0+/-5.0 62.1-89.9 8.5-11.9 0.0-16.4 0.0-16.7
.20.3-37.7 5.4-10.6 3.3-20.7 6.2-10.6 4.0-6.8 0.0-16.7 1.3-18.7 207.7-294.3 16.3-33.7 125.0-177.0 126.0-178.0 16.3-33.7 6.3-23.7 STW-551 Water STW-552 553 Water (Blind)
Sample A Sample B Oct 1988 Oct 1988 H-3 Gr. alpha Ra-226 Ra-228 Uranium Gr. beta Sr-89 Sr-90 Cs-134 Cs-137 2333+/-127 2316+/-350 1710-2927 38.3+/-8.0 4.5+/-0.5 4.4+/-0.6 4.7+/-1.2 51.3+/-3.0 3.7+/-1.2 10.7+/-1.2 15.3+/-2.3 16.7+/-1.2 41.0+/-10.0 5.0+/-0.8 5.2+/-0.8 5.0+/-6.0 54.0+/-5.0 11.0+/-5.0 10.0+/-1.5 15.0+/-5.0 15.0+/-5.0 23.7-58.3 3.6-6.4 3.6-6.4 0.0-15.4 45.3-62.7 2.3-19.7 7.4-12.6 6.3-23.7 6.3-23.7 A-5
Table A-1. (continued)
Concentration in pCifLb Lab Sample Date TIML Result EPA Resultd Code Type Collected Analysis
+/-2oc 1s, N=1 Control Limits STM-554 Milk STU-555 STW-556 STW-557 STW-559 STW-560 STW-561 Urine Water Water Water Water Water STW-562 Water STW-563 STW-564 STW-565 STW-566 STAF-567 Water Water Water Water Air Filter Oct 1988 Nov 1988 Nov 1988 Dec 1988 Jan 1989 Jan 1989 Jan 1989 Feb 1989 Feb 1989 Feb 1989 Mar 1989 Mar 1989 Mar 1989 Sr-89 Sr-90 1-131 Cs-137 K
H-3 Gr. alpha Gr. beta 1-131 Sr-89 Sr-90 Pu-239 Gr. alpha Gr. beta Cr-51 Co-60 Zn-65 Ru-106 Cs-134 Cs-137 1-131 H-3 Ra-226 Ra-228 U
Gr. alpha Gr. beta Sr-90 Cs-137 40.3+/-7.0 51.0+/-2.0 94.0+/-3.4 45.0+/-4.0 1500+/-45 3030+/-209 9.0+/-3.5 9.7+/-1.2 108.7+/-3.0 40.0+/-8.7 24.3+/-3.1 5.8+/-1.1 7.3+/-1.2 5.3+/-1.2 245+/-46 10.0+/-2.0 170+/-10 181+/-7.6 9.7+/-3.0 11.7+/-1.2 109.0+/-4.0 2820+/-20 4.2+/-03 1.9+/-1.0 5.0+/-0.0 21.7+/-1.2 68.3+/-4.2 20.0+/-2.0 21.3+/-1.2 40.0+/-5.0 60.0+/-3.0 91.0+/-9.0 50.0+/-5.0 1600+/-80 3025+/-359 9.0+/-5.0 9.0+/-5.0 115.0+/-12.0 40.0+/-5.0 25.0+/-1.5 4.2+/-0.4 8.0+/-5.0 4.0+/-5.0 235+/-24 10.0+/-5.0 159+/-16 178+/-18 10.0+/-5.0 10.0+/-5.0 06.0+/-11.0 2754+/-356 4.9+/-0.7 1.7+/-03 5.0+/-6.0 21.0+/-5.0 62.0+/-5.0 20.0+/-1.5 20.0+/-5.0 31.3-48.7 54.8-65.2 75.4-106.6 41.3-58.7 1461-1739 2403-3647 0.3-17.7 0.3-17.7
.94.2-135.8 31.3-48.7 22.4-27.6 3.5-4.9 0.0-16.7 0.-127 193.4-276.6 1.3-18.7 139.2-186.7 146.8-209.2 1.318.7 1.3-18.7 86.9-125.1 2137-3371 3.7-6.1 1.2-2.2 0.0-15.4 12.3-29,7 53.3-70.7 17.4-22.6 11.3-28.7 A-6 f,
I
Table A-1. (continued)
Concentration in pifLb Lab Sample Date TIML Result EPA Resultd Code Type Collected Analysis 12oc 1s, N=1 Control Limits STW-568 Water 569 (Blind)
Sample A Sample B STM-570 Milk STW-5719 Apr 1989 Gr. alpha Ra-226 Ra-228 U
Gr. beta Sr-89 Sr-90 Cs-134 Cs-137 Apr 1989
- Water, May 1989 STW-572
- Water, STW-573 Water' STW-574 Water STW-575 Water!
STW-576 Water:
STW-577
- Water, STAF-579 Air Filter May 1989 Jun 1989 Jun 1989 Jul 1989 Jul 1989 Aug 1989 Aug 1989 Sr-89 Sr-90 Cs-137 K-40 Sr-89 Sr-90 Gr. alpha Gr. beta Ba-133 Co-60 Zn-65 Ru-106 Cs-134 Cs-137 H-3 Ra-226 Ra-228 U
1-131 Gr. alpha Cs-137 22.7+/-2.3 3.6+/-0.6 2.6+/-1.0 3.0+/-0.0 523+/-6.1 9.3+/-5.4 7.0+/-0.0 21.0+/-5.2 23.0+/-2.0 26.0+/-10.0 45.7+/-4.2 54.0+/-6.9 1521+/-208
<0.7 5.0+/-1.0 24.0+/-2.0 49.3+/-15.6 50.7+/-12 31.3+/-2.3 167+/-10 123+/-9.2 40.3+/-1.2 22.3+/-1.2 29.0+/-7.0 3.5+/-0.5 3.6+/-0.5 3.0+/-6.0 57.0+/-5.0 8.0+/-5.0 8.0+/-1.5 20.0+/-5.0 20.0+/-5.0 39.0+/-5.0 55.0+/-3.0 50.0+/-5.0 1600+/-80 6.0+/-5.0 6.0+/-1.5 30.0+/-8.0 50.0+/-5.0 49.0+/-5.0 31.0+/-5.0 165+/-17 128+/-13 39+/-5 20+/-5 16.9-41.2 2.6-4.4 2.7-4.5 0.0-13.4 43.3-65.7 0.0-16.7 5.4-10.6
.11.3-28.7 11.3-28.7 30.3-47.7 49.8-60.2 41.3-58.7 1461-1739 0.0-14.7 3.4-8.6 16.1-43.9 41.3-58.7 40.3-57.7 22.3-39.7 135.6-194.4 105.5-150.5 30.3-47.7 11.3-28.7 4513+/-136 4503+/-450 3724-5282 16.8+/-3.1 13.8+/-3.7 40.3+/-12 84.7+/-5.8 6.0+/-0.0 10.3+/-2.3 17.7+/-2.7 18.3+/-2.7 13.0-22.4 13.6-23.0 41.0+/-6.0 30.6+/-51.4 83.0+/-8.0 6.0+/-5.0 10.0+/-5.0 69.1-96.9 0.0-14.7 1.3-18.7 A-7
I,
I Table A-1. (continued)
Concentration in pCifLb tab Sample Date TIML Result EPA Resultd Code Type Collected Analysis
+/-2ac 1s, N=1 Control Limits STW-580 Water Sep 1989 STW-581 Water Sep 1989 STW-583 Water Oct 1989 Sr-89 Sr-90 Gr. alpha Gr. beta Ba-133 Co-60 Zn-65 Ru-106 Cs-134 Cs-137 14.7+/-1.2 9.7+/-1.2 5.0+/-0.0 8.7+/-2.3 603+/-10.0 29.0+/-4.0 132.3+/-6.0 155.3+/-6.1 30.7+/-6.1 66.3+/-4.6 14.0+/-5.0 10.0+/-1.5 4.0+/-5.0 6.0+/-5.0 59.0+/-6.0 30.0+/-5.0 129.0+/-13.0 161.0+/-16.0 29.0+/-5.0 59.0+/-5.0 5.3-22.7 7.4-12.6 0.0-12.7 0.0-14.7 48.6-69.4 21.1-38.7 106.5-151.5 133.3-188.7 20.3-37.7 50.3-67.7 STW-584 Water STW-585 586 Water (Blind)
Oct 1989 Oct 1989 Sample A Sample B STW-587 Water STW-588 Water STW-589 Water STW-591 Water Nov 1989 Nov 1989 Jan 1990 Jan 1990 H-3 Cr. alpha Ra-226 Ra-228 U
Gr. beta Sr-89 Sr-90 Cs-134 Cs-137 Ra-226 Ra-228 U
Sr-89 Sr-90 3407+/-150 3496+/-364 2866-4126 41.7+/-9.4 7.9+/-0.4 4.4+/-0.8 120+/-0.0 31.7+/-2.3 13.3+/-4.2 7.0+/-2.0 5.0+/-0.0 7.0+/-0.0 7.9+/-0.4 8.9+/-1.2 15.0+/-0.0 22.7+/-5.0 17.3+/-1.2 Cr. alpha 10.3+/-3.0 Gr. beta 12.3+/-1.2 A-8 49.0+/-12.0 8.4+/-1.3 4.1+/-0.6 120+/-6.0 320+/-5.0 15.0+/-5.0 7.0+/-3.0 5.0+/-5.0 5.0+/-5.0 8.7+/-1.3 9.3+/-1.2 15.0+/-6.0 25.0+/-5.0 20.0+/-1.5 12.0+/-5.0 120+/-5.0 28.2-69.8 6.2-10.6 3.1-5.1 1.6-22.4 23.3-40.7 6.3-23.7 4.4-9.6 0.0-13.7 0.0-13.7 6.4-11.0 6.9-11.7 4.6-25.4 16.3-33.7 17.4-22.6 3.3-20.7 3.3-20.7
Table A-1. (continued)
Concentration in pCi/Lb lab Sample Date TIML Result EPA Resultd Code Type Collected Analysis
+/-2oc 1s, N=1 Control Limits STW-592 Water STW-593 Water STW-594 Water STW-595 Water STAF-596 STW-597 598 Jan 1990 Feb 1990 Mar 1990 Mar 1990 Air Filter Mar 1990 Water (Blind)
Co-60 Zn-65 Ru-106 Cs-134 Cs-137 Ba-133 H-3 Ra-226 Ra-228 U
Gr. alpha Gr. beta Sr-90 Cs-137 14.7+/-2.3 135.0+/-6.9 133.3+/-13.4 17.3+/-1.2 19.3+/-1.2 78.0+/-0.0 4827+/-83 5.0+/-0.2 13.5+/-0.7 4.0+/-0.0 7.3+/-1.2 34.0+/-0.0 10.0+/-0.0 9.3+/-1.2 15+/-5.0 139.0+/-14.0 139.0+/-14.0 18.0+/-5.0 18.0+/-5.0 74.0+/-7.0 6.3-23.7 114.8-163.2 114.8-163.2 9.3-26.7 9.3-26.7 61.9-86.1 4976+/-498 4113-5839 4.9+/-0.7 12.7+/-1.9 4.0+/-6.0 5.0+/-5.0 31.0+/-5.0 10.0+/-1.5 10.0+/-5.0 4.1-5.7 9.4-16.0 0.0-14.4 0.0-13.7 22.3-39.7 7.4-12.6 1.3-18.7 Apr 1990 Sample A Sample B STM-599 Milk Gr. alpha Ra-226 Ra-228 U
Gr. beta Sr-89 Sr-90 Cs-134 Cs-137 Apr 1990 Sr-89 Sr-90 1-131 Cs-137 K
81.0+/-3.5 4.9+/-0.4 10.6+/-0.3 18.7+/-3.0 51.0+/-10.1 9.3+/-1.2 10.3+/-3.1 16.0+/-0.0 19.0+/-2.0 21.7+/-3.1 21.0+/-7.0 98.7+/-1.2 26.0+/-6.0 1300.0+/-69.2 90.0+/-23.0 5.0+/-0.8 10.2+/-1.5 20.0+/-6.0 52.0+/-5.0 10.0+/-5.0 10.0+/-1.5 15.0+/-5.0 15.0+/-5.0 23.0+/-5.0 23.0+/-5.0 99.0+/-10.0 24.0+/-5.0 1550.0+/-78.0 50.1-129.9 3.6-6.4 7.6-118 9.6-30.4 43.3-60.7 1.3-18.7 8.3-11.7 6.3-23.7 6.3-23.7 14.3-31.7 143-31.7 81.7-116.3 15.3-32.7 1414.7-1685.3 STW-600 Water May 1990 STW-601 Water May 1990 Sr-89 Sr-90 Gr. alpha Gr. beta 6.0+/-2.0 6.7+/-1.2 11.0+/-2.0 12.3+/-1.2 7.0+/-5.0 7.0+/-5.0 22.0+/-6.0 15.0+/-5.0 0.0-15.7 0.0-15.7 11.6-32.4 63-23.7 A-9
Table A-1. (continued)
Concentration in pCi/Lb lab Sample Date TIML Result EPA Resultd Code Type Collected Analysis
+/-2oc 1s, N=1 Control Limits STW-602 Water STW-603 Water STW-604 Water STW-605 Water STW-606 Water STW-607 Water STAF-608 Jun 1990 Jun 1990 Jul 1990 Jul 1990 Aug 1990 Aug 1990 Air Filter Aug 1990 STW-609 Water STW-610 Water STM-611 Milk STW-612 Water Sep 1990 Sep 1990 Sep 1990 Oct 1990 Co-60 Zn-65 Ru-106 Cs-134 Cs-137 Ba-133 H-3 Ra-226 Ra-228 U
1-131 Pu-239 Gr. alpha Gr. beta Sr-90 Cs-137 Sr-89 Sr-90 Gr. alpha Gr. beta Sr-89 Sr-90 1-131 Cs-137 K
Co-60 Zn-65 Ru-106 Cs-134 Cs-137.
Ba-133 25.3+/-2.3 155.0+/-10.6 202.7+/-17.2 23.7+/-11 27.7+/-3.1 100.7+/-8.1 24.0+/-5.0 148.0+/-15.0 210.0+/-21.0 24.0+/-5.0 25.0+/-5.0 99.0+/-10.0 2927+/-306 2933+/-358 11.8+/-0.9 4.1+/-1.4 20.3+/-1.7 43.0+/-1.2 10.0+/-1.7 14.0+/-0.0 65.3+/-1.2 19.0+/-6.9 19.0+/-2.0 9.0+/-2.0 9.0+/-2.0 8.3+/-1.2 10.3+/-1.2 11.7+/-3.1 15.0+/-0.0 63.0+/-6.0 20.0+/-2.0 1673.3+/-70.2 20.3+/-3.1 115.3+/-12.2 152.0+/-8.0 11.0+/-0.0 14.0+/-2.0 116.7+/-9.9 12.1+/-1.8 5.1+/-1.3 20.8+/-3.0 39.0+/-6.0 9.1+/-0.9 10.0+/-5.0 62.0+/-5.0 20.0+/-5.0 20.0+/-5.0.
10.0+/-5.0 9.0+/-5.0 10.0+/-5.0 10.0+/-5.0 16.0+/-5.0 20.0+/-5.0 58.0+/-6.0 20.0+/-5.0 1700.0+/-85.0 20.0+/-5.0 115.0+/-12.0 151.0+/-15.0 120+/-5.0 12.0+/-5.0 110.0+/-11.0 15.3-32.7 130.6-165.4 173.6-246.4 18.2-29.8 16.3-33.7 81.7-116.3 2312-3554 9.0-15.2 2.8-7.4 15.6-26.0 28.6-49.4 7.5-10.7 1.3-18.7 53.3-70.7 11.3-28.7 11.3-28.7 1.3-18.7 0.3-17.7 1.3-18.7 1.3-18.7 7.3-24.7 11.3-28.7 47.6-68.4 11.3-28.7 1552.5-1847.5 11.3-28.7 94.2-135.8 125.0-177.0 3.3-20.7 3.3-20.7 90.9-129 STW-613 Water Oct 1990 H-3 7167+/-330 7203+/-720 A-10 5954-8452
Table A-1. (continued)
Concentration in pCi/Lb Lab Sample Date TIML Result EPA Resultd Code Type Collected Analysis
+/-2oc 1s, N=1 Control Limits STW-614 615 Water Sample A Sample B STW-616 Water STW-6179 Water STW-618 Water STW-619 Water STW-620 Water STW-621 Water Oct 1990 Gr. alpha Ra-226 Ra-228 U
Gr. beta Sr-89 Sr-90 Cs-134 Cs-137 Nov 1990 Nov 1990 Jan 1991 Jan 1991 Jan 1991 Feb 1991 Ra-226 Ra-228 U
Sr-89 Sr-90 Pu-239 Gr. alpha Gr. beta Co-60, Zn-65 Ru-106 Cs-134 Cs-137 Ba-133 68.7+/-7.2 12.9+/-03 4.2+/-0.6 10.4+/-0.6 55.0+/-8.7 15.7+/-2.9 12.0+/-2.0 9.0+/-1.7 7.7+/-1.2 6.8+/-1.0 5.3+/-1.7 35.0+/-0.4 4.3+/-1.2 4.7+/-1.2 3.6+/-0.2 6.7+/-3.0 6.3+/-11.2 41.3+/-8.4 166.7+/-19.7 209.7+/-18.6 9.0+/-2.0 9.7+/-1.2, 85.7+/-9.2 62.0+/-16.0 13.6+/-2.0 5.0+/-1.3 10.2+/-3.0 53.0+/-5.0 20.0+/-5.0 15.0+/-5.0 7.0+/-5.0 5.0+/-5.0 7.4+/-1.1 7.7+/-1.9 35.5+/-3.6 5.0+/-5.0 5.0+/-5.0 3.3+/-0.3 5.0+/-5.0 5.0+/-5.0 40.0+/-5.0 149.0+/-15.0 186.0+/-19.0 8.0+/-5.0 8.0+/-5.0 75.0+/-8.0 STW-622 Water STW-623 Water STW-624 Water STW-625 Water Feb 1991 Feb 1991 Mar 1991 Mar 1991 1-131 H-3 Ra-226 Ra-228 U
81.3+/-6.1 4310.0+/-144.2 31.4+/-3.2 NDh 6.7+/-0.4 75.0+/-8.0 61.1-88.9 4418.0+/-442.0 3651.2-5184.8 31.8+/-4.8 21.1+/-5.3 7.6+/-3.0 23.5-40.1 11.9-303 2.4-128 A-11 34.2-89.8 10.1-17.1 2.7-7.3 5.0-15.4 44.3-61.7 11.3-28.7 6.3-23.7 0.0-15.7 0.0-13.7 5.5-9.3 4.4-11.0 29.3-41.7 0.0 -13.7 0.0-13.7 2.8-3.8 0.0-13.7 0.0-13.7 31.3-48.7 123.0-175.0 153.0-219.0 0.0-16.7 0.0-16.7 61.1-88.9
Table A-1. (continued)
Concentration in pCifLb lab Sample Date TIML Result EPA Resultd Code Type Collected Analysis
+/-2oc 1s, N=1 Control Limits STAF-626 Air Filter Mar 1991 Gr. alpha Gr. beta Sr-90 Cs-137 38.7+/-1.2 130.0+/-4.0 35.7+/-1.2 33.7+/-4.2 25.0+/-6.0 124.0+/-6.0 40.0+/-5.0 40.0+/-5.0 14.6-35.4 113.6-134.4 31.3-48.7 31.3-48.7 STW-627 628 Water Sample A Apr 1991 Cr. alpha Ra-226 Ra-228 U
Gr. beta Sr-89 Sr-90 Cs-134 Cs-137 Sample B STM-629 Milk STW-630 Water STW-631 Water STW-632 Water Apr 1991.
May 1991 May 1991 Jun 1991 Sr-89 Sr-90 1-131 Cs-137 K
Sr-89 Sr-90 Gr. alpha Gr. beta Co-60 Zn-65 Ru-106 Cs-134 Cs-137 Ba-133 51.0+/-6.0 7.0+/-0.8 9.7+/-1.9 27.7+/-2.4 93.3+/-6.4 21.0+/-3.5 23.0+/-0.0 27.3+/-1.2 29.0+/-2.0 24.0+/-8.7 28.0+/-2.0 65.3+/-14.7 54.7+/-11.0 1591.7+/-180.1 40.7+/-2.3 23.7+/-1.2 27.7+/-5.8 46.0+/-0.0 11.3+/-1.2 119.3+/-16.3 162.3+/-19.0 15.3+/-1.2 16.3+/-1.2 74.0+/-6.9 54.0+/-14.0 8.0+/-1.2 15.2+/-3.8 29.8+/-3.0 115.0+/-17.0 28.0+/-5.0 26.0+/-5.0 24.0+/-5.0 25.0+/-5.0 32.0+/-5.0 32.0+/-5.0 60.0+/-6.0 49.0+/-5.0 1650.0+/-83.0 39.0+/-5.0 24.0+/-5.0 24.0+/-6.0 46.0+/-5.0 10.0+/-5.0 108.0+/-11.0 149.0+/-15.0 15.0+/-5.0 14.0+/-5.0 62.0+/-6.0 29.7-78.3 5.9-10.1 8.6-21.8 24.6-35.0 85.5-144.5 19.3-36.7 17.3-34.7 15.3-327 16.3-33.7 23.3-40.7 23.3-40.7 49.6-70.4 40.3-57.7 1506.0-1794.0 30.3-47.7 15.3-32.7 13.6-34.4 37.3-54.7 1.3-18.7 88.9-127.1 123.0-175.0 6.3-23.7 5.3-22.7 51.6-72.4 STW-633 Water STW-634 Water Jun 1991 Jul 1991 H-3 13470.0+/-385.8 12480.0+/-1248.0 10314.8-14645.2 Ra-226 Ra-228 14.9+/-0.4 17.6+/-1.8 15.9+/-2.4 16.7+/-4.2 11.7-20.1 9.4-24.0 A-12
i I
. 4 Table A-1. (continued)
Concentration in pCifLb lab Sample Date TIML Result EPA Resultd Code Type Collected Analysis 12oc is, N=1 Control Limits STW-635 Water Jul 1991 STW-636 Water :
Aug 1991 STW-637 Water Aug 1991 STAF-638 Air Filter Aug 1991 STW-639 Water STW-640 Water STM-641 Milk STW-642 Water STW-643 Water STW-644 Water 645 Sample A Sep 1991 Sep 1991 Sep 1991 Oct 1991 Oct 1991 Oct 1991 Sample B U
1-131 Pu-239 Gr. alpha Gr. beta Sr-90 Cs-137 Sr-89 Sr-90 Gr. alpha Gr. beta Sr-89 Sr-90 1-131 Cs-137 K
Co-60 Zn-65 Ru-106 Cs-134 Cs-137 Ba-133 H-3 Gr. alpha Ra-226 Ra-228 U
Gr. beta Sr-89 Sr-90 Co-60 Cs-134 Cs-137 128+/-0.1 19.3+/-1.2 21.4+/-0.5 33.0+/-2.0 88.7+/-1.2 27.0+/-4.0 26.3+/-1.2 14.2+/-3.0 20.0+/-6.0 19.4+/-1.9 25.0+/-6.0 92.0+/-10.0 30.0+/-5.0 30.0+/-5.0 47.0+/-10.4 49.0+/-5.0 24.0+/-2.0 25.0+/-5.0 12.0+/-4.0 20.3+/-1.2 20.3+/-5.0 19.7+/-3.1 130.7+/-16.8 33.7+/-3.2 1743.3+/-340.8 29.7+/-1.2 75.7+/-8.3 1%.3+/-15.1 9.7+/-1.2 11.0+/-2.0 94.7+/-3.1 10.0+/-5.0 20.0+/-5.0 25.0+/-5.0 25.0+/-5.0 108.0+/-11.0 30.0+/-5.0 1740.0+/-87.0 29.0+/-5.0 73.0+/-7.0 199.0+/-20.0 10.0+/-5.0 10.0+/-5.0 98.0+/-10.0 9.0-19.4 9.6-30.4 16.1-22.7 14.6-35.4 80.4-103.6 21.3-38.7 21.3-38.7 40.3-57.7 16.3-33.7 1.3-18.7 11.3-28.7 16.3-33.7 16.3-33.7 88.9-127.1 21.3-38.7 1589.1-1890.9 20.3-37.7 60.9-85.1 164.3-233.7 1.3-18.7 1.3-18.7 80.7-115.3 2640.0+/-156.2 2454.0+/-352.0 1843.3-3064.7 73.0+/-13.1 20.9+/-2.0 19.6+/-2.3 13.5+/-0.6 55.3+/-3.1 9.7+/-3.1 8.7+/-1.2 20.3+/-1.2 9.0+/-5.3 14.7+/-5.0 82.0+/-21.0 22.0+/-3.3 22.2+/-5.6 13.5+/-3.0 65.0+/-10.0 10.0+/-5.0 10.0+/-5.0.
20.0+/-5.0 10.0+/-5.0 11.0+/-5.0 45.6-118.4 16.3-27.7 12.5-31.9 8.3-18.7 47.7-82.3 1.3-18.7 1.3-18.7 11.3-28.7 1.3-18.7 2.3-19.7 A-13
Table A-1. (continued)
Concentration in pri/Lb Lab Sample Date TIML Result EPA Resultd Code Type Collected Analysis i2oc 1s, N=1 Control Limits STW-646 Water STW-647 Water' STW-648 Water STW-649 Water STW-650 Water STW-651 Water STW-652 Water STW-653 Water STW-654 Water STW-655 Water STW-656 Water STW-657 Water STAF-658 STW-659 660 Nov 1991 Nov 1991 Jan 1992 Jan 1992 Jan 1992 Feb 1992 Feb 1992 Feb 1992 Mar 1992 Mar 1992 Mar 1992 Mar 1992 Air Filter Mar 1992 Water Apr 1992 Sample A Ra-226 Ra-228 U
Sr-89 Sr-90 Pu-239 5.6+/-1.2 9.6+/-0.5 24.7+/-2.3 42.7+/-6.4 18.3+/-3.1 16.1+/-0.8 Gr. alpha 23.7+/-9.2 Gr. beta 27.7+/-4.2 1-131 Co-60 Zn-65 Ru-106 Cs-134 Cs-137 Ba-133 H-3 Ra-226 Ra-228 Rn-2221 U
Rn-2221 Gr. alpha Gr. beta Sr-90 Cs-137 Gr. alpha Ra-226 Ra-228 U
60.3+/-4.2 40.3+/-5.0 148.0+/-15.0 188.7+/-28.8 31.7+/-4.2 51.0+/-3.4 79.0+/-3.4 7714.0+/-119.6 9.0+/-0.4 18.8+/-0.6 25.1+/-1.9 7.0+/-0.0 39.3+/-1.6 13.7+/-1.6 10.0+/-0.0 35.7+/-6.1 12.7+/-1.2 14.5+/-2.1 3.9+/-0.2 6.5+/-1.0 8.1+/-2.0 24.9+/-3.0 51.0+/-5.0 20.0+/-5.0 16.8+/-1.7 30.0+/-8.0 30.0+/-5.0 4.8-8.2 4.6-11.6 19.7-30.1 42.3-59.7 11.3-28.7 13.9-19.7 16.1-43.9 21.3-38.7 59.0+/-6.0 48.6-69.4 40.0+/-5.0 150.7+/-6.1 203.0+/-20.0 31.0+/-5.0 49.0+/-5.0 76.0+/-8.0 7904.0+/-790.0 10.1+/-1.5 15.5+/-3.9 25.3+/-3.0 7.0+/-5.0 41.0+/-5.0 15.0+/-5.0 10.0+/-5.0 40.0+/-10.0 14.9+/-2.2 14.0+/-3.5 40+/-3.0 31.3-48.7 122.0-174.0 168.3-237.7 22.3-39.7 40.3-57.7 62.1-89.9 6533.4-9274.6 7.5-12.7 8.7-22.3 20.1-30.5 0.0-15.7 32.3-49.7 6.3-23.7 1.3-18.7 22.7-57.3 11.1-18.7 7.9-20.1 0.0-9.2 A-14
4 Table A-1. (continued)
Concentration in pCifLb Lab Sample Date TIML Result EPA Resultd Code Type Collected Analysis
+/-2oc 1s, N=1 Control Limits STW-659 660 STM-661 Water Sample B Milk STW-662 Water STM-663 Water STW-664 Water STW-665 Water STW-666 Water STW-667 Water STW-668 Water STW-669 Water STAF-670 Apr 1992 Apr 1992 May 1992 May 1992 Jun 1992 Jun 1992 July 1992 July 1992 August 1992 August 1992 Air Filter August 1992 Gr. beta Sr-89 Sr-90 Co-60 Cs-134 Cs-137 Sr-89 Sr-90 1-131 Cs-137 K
Sr-89 Sr-90 113.0+/-7.2 12.3+/-4.2 15.0+/-1.2 61.0+/-4.0 24.3+/-1.2 24.0+/-2.0 25.3+/-7.6 24.3+/-3.1 78.7+/-9.5 39.3+/-2.3 1610.0+/-72.1 24.0+/-4.0 6.7+/-1.2 Cr. alpha 12.3+/-2.1 Gr. beta 46.0+/-5.0 Co-60 Zn-65 Ru-106 Cs-134 Cs-137 Ba-133 H-3 Ra-226 Ra-228 U
1-131 Pu-239 Gr. alpha Gr. beta Sr-90 Cs-137 20.3+/-1.2 103.3+/-10.6 142.7+/-23.7 14.3+/-2.3 15.0+/-2.0 92.7+/-11.0 2153.3+/-144.6 22.3+/-2.2 16.7+/-3.1 3.6+/-03 47.0+/-3.5 8.5+/-0.9 25.7+/-1.2 69.0+/-2.0 26.0+/-4.0 16.0+/-0.0 140.0+/-21.0 15.0+/-5.0 17.0+/-5.0 56.0+/-5.0 24.0+/-5.0 22.0+/-5.0 38.0+/-5.0 29.0+/-5.0 78.0+/-8.0 39.0+/-5.0 1710.0+/-86.0 29.0+/-5.0 8.0+/-5.0 15.0+/-5.0 44.0+/-5.0 20.0+/-5.0 99.0+/-10.0 141.0+/-14.0 15.0+/-5.0 15.0+/-5.0 98.0+/-10.0
. 103.6-176.4 6.3-23.7 8.3-25.7 47.3-64.7 15.3-32.7 13.3-30.7 29.3-46.7 20.3-37.7 64.1-91.9 30.3-47.7 1560.8-1859.2 20.3-37.7 0.0-16.7 6.3-23.7 35.3-52.7 11.3-28.7 81.7-1163 116.7-1653 6.3-23.7 6.3-23.7 80.7-115.3 2125.0+/-347.0 1523.0-2727.0 24.9+/-3.7 16.7+/-4.2 4.0+/-3.0 45.0+/-6.0 9.0+/-0.9 30.0+/-8.0 69.0+/-10.0 25.0+/-5.0 18.0+/-5.0 18.5-313 9.4-24.0 0.0-9.2 34.6-55.4 7.4-10.6 16.1-43.9 51.7-863 16.3-33.7 9.3-26.7 A-15
-1 1 Table A-1. (continued)
Concentration in pCifLb Lab Sample Date TIML Result EPA Resultd Code Type Collected Analysis
+/-2oc 1s, N=1 Control Limits STW-671 Water STW-672 Water STM-673 Milk STW-674 Water STW-675 Water STW-676
-677 Water Sept. 1992 Sept. 1992 Sept.1992 Oct 1992 OcL 1992 Oct 1992 Sample A Sample B Sr-89 Sr-90 Gr. alpha Gr. beta Sr-89 Sr-90 1-131 Cs-137 K
Co-60 Zn-65 Ru-106 Cs-134 Cs-137 Ba-133 H-3 Gr. alpha Ra-226 Ra-228 U
Gr. beta Sr-89 Sr-90 Co-60 Cs-134 Cs-137 16.0+/-4.0 14.3+/-3.1 43.0+/-13.1 413+/-18.6 11.0+/-3.5 12.7+/-1.2 109.7+/-19.4 14.0+/-3.5 1540.0+/-103.9 11.3+/-2.3 169.7+/-25.0
.170.1+/-2.3 9.7+/-2.3 9.7+/-1.2 80.3+/-9.0 5896.7+/-136.2 24.7+/-5.0 7.1+/-0.4 11.5+/-1.0 9.7+/-0.5 42.7+/-8.1 6.7+/-1.2 10.0+/-2.0 15.0+/-2.0 5.7+/-1.2 8.0+/-2.0 20.0+/-5.0 15.0+/-5.0 45.0+/-11.0 50.0+/-5.0 15.0+/-5.0 15.05.0 100.0+/-10.0 15.05.0 1750.0+/-88.0 10.0+/-5.0 148.0+/-15.0 175.0+/-18.0 8.0+/-5.0 8.0+/-5.0 74.0+/-7.0 11.3-28.7 6.3-23.7 25.9-64.1 41.1-58.7 6.3-23.7 6.3-23.7 827-117.3 S6-3-23.7 1597.3-1902.7 1.3-18.7 122.0-174.0 143.8-206.2 0.0-16.7 0.0-16.7 61.9-86.1 5962.0+/-596.0 4928.0-6996.0 29.0+/-7.0 7.4+/-1.1*
10.0+/-2.5 10.2+/-3.0 53.0+/-10.0 8.0+/-5.0 10.05.0 15.0+/-5.0 5.0+/-5.0 8.0+/-5.0 16.9-41.1 5.5-9.3 5.7-14.3 5.0-15.4 35.7-70.3 0.0-16.7 1.3-18.7 6.3-23.7 0.0-13.7 0.0-16.7 A-16
'S Table A-1. (continued)
Concentration in pCifLb lab Sample Date TIML Result EPA Resultd Code Type Collected Analysis
+/-2oc Is, N=1 Control Limits STW-678 Water Nov. 1992 Ra-226 7.5+/-0.8 7.5+/-1.1 5.6-9.4 Ra-228 5.8+/-0.7 5.0+/-1.3 2.7-7.3 STW-679 Water Nov. 1992 U
15.5+/-1.1 15.2+/-3.0 10.0-20.4 a Results obtained by Teledyne Isotopes Midwest Laboratory as a participant in the environmental 'sample crosscheck program operated by the Intercomparison and Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, U.S.
Environmental Protection Agency (EPA), Las Vegas, Nevada.
b All results are in pCi/l, except for elemental potassium (K) data in milk, which are in mg/l; air filter samples, which are in pCi/filter; and food, which is in mg/kg.
c Unless otherwise indicated, the TIML results are given as the mean +/- 2 standard deviations for three determinations.
d USEPA results are presented as the known values and expected laboratory precision (1s, 1 determination) and control limits as defined by EPA.
e NA = Not analyzed.
f ND = No data; not analyzed due to relocation of lab.
g Sample was analyzed but the results not submitted to EPA because deadline was missed (all data on file).
h ND = No data; sample lost during analyses.
i ND = No data; special EPA testing.
A-17
Table A-2. Crosscheck program results, thermoluminescent dosimeters (TLDs).
mR Teledyne Average +/-2od lab Result Known (All Participants)
Code TLD Type Measurement
+/-2oa Value 2nd International Intercomparisonb 115-2 CaF2 :Mn Field 17.0+/-1.9 17.1 16.4+/-7.7 Bulb Iab 20.8+/-4.1 213 18.8+/-7.6 3rd International Intercomparisone 115-3 CaF2 :Mn Field 30.7+/-3.2 34.9+/-4.8 31.5+/-3.0 Bulb Lab 89.6+/-6.4 91.7+/-14.6 86.2+/-24.0 4th International Intercomparisonf 115-4 CaF2 :Mn Field 14.1+/-1.1 14.1+/-1.4 16.0+/-9.0 Bulb Lab (Low) 9.3+/-1.3 12.212.4 12.0+/-7.4 Lab (High) 40.4+/-1.4 45.8+/-9.2 43.9+/-13.2 5th International Intercomparisong 115-SA CaF2 :Mn Field 31.4+/-1.8 30.0+/-6.0 30.2+/-14.6 Bulb Lab at beginning 77.4+/-5.8 75.2+/-7.6 75.8+/-40.4 Lab at the end 96.6+/-5.8 88.4+/-8.8 90.7+/-312 115-5B LiF-100 Field 30.3+/-4.8 30.0+/-6:0 30.2+/-14.6 Chips Field at beginning 81.1+/-7.4 75.2+/-7.6 75.8+/-40.4 Lab at the end 85.4+/-11.7 88.4+/-8.8 90.7+/-31.2 7th International Comparisonh 115-7A LiF-100 Field 75.4+/-2.6 75.8+/-6.0 75.1+/-29.8 Chips Lab (Co-60) 80.0+/-3.5 79.9+/-4.0 77.9+/-27.6 Lab (Cs-137) 66.6+/-2.5 75.0+/-3.8 73.0+/-22.2 A-18
Table A-2. Crosscheck program results, thermoluminescent dosimeters (TLDs).
mR Measurement Field Lab (Co-60)
Lab (Cs-137)
Field Lab (Co-60)
Lab (Cs-137)
Teledyne Result 120 a 71.5+/-2.6 84.8+/-6.4 78.8+/-1.6 76.8+/-2.7 82.5+/-3.7 79.0+/-13.2 Known Value 75.8+/-6.0 79.9+/-4.0 75.0+/-3.8 75.8+/-6.0 79.9+/-4.0 75.0+/-3.8 Average +/-2od (All Participants) 75.1+/-29.8 77.9+/-27.6 73.0+/-22.2 75.1+/-29.8 77.9+/-27.6 73.0+/-22.2 8th International Intercomparison' 115-8A 115-8B 115-8C LiF-100 Chips CaF2 :Mn Bulbs CaSO 4 :Dy Cards Teledyne Testing 89-1 LiF-100 Chips 89-2 Teledyne CaSO 4 Dy Cards Field Site 1 Field Site 2 Lab (Cs-137)
Field Site 1 Field Site 2 Lab (Cs-137)
Field Site 1 Field Site 2 Lab (Cs-137)
Lab Lab A-19 Iab Code TLD Type 115-7B 115-7C CaF2 : Mn Bulbs CaSO 4-Dy Cards 29.7+/-1.5 10.4+/-0.5 17.2+/-0.9 29.7+/-1.5 10.4+/-0.5 17.2+/-0.9 29.7+/-1.5
,10.4+/-0.5 17.2+/-0.9 28.9+/-12.4 10.1+/-9.06 16.2+/-6.8 28.9+/-12.4 10.1+/-9.0 16.2+/-6.8 28.9+/-12.4 10.1+/-9.0 16.2+/-6.8 29.5+/-1.4 11.3+/-0.8 13.7+/-0.9 32.3+/-1.2 9.0+/-1.0 15.8+/-0.9 32.2+/-0.7 10.6+/-0.6 18.1+/-0.8 21.0+/-0.4 20.9+/-1.0 22.4 20.3
Table A-2. (continued) mR Teledyne Average +/-2od Lab Result Known (All Participants)
Code TLD Type Measurement 12oa Value Teledvne Testing 90-1k Teledyne Lab 20.6+/-1.4 19.6 CaSO 4.Dy Cards 90-21 Teledyne lab 100.8+/-4.3 100.0 CaSO 4:Dy Cards 91-1m Teledyne Lab 33.4+/-2.0 32.0 CaSO 4:Dy 55.2+/-4.7 58.8 Cards 87.8+/-6.2 85.5 92-1n LiF-100 Lab 11.1+/-0.2 10.7 Chips 25.6+/-0.5 25.4 46.4+/-0.5 46.3 92-2o Teledyne Lab (Reader #1) 20.1+/-0.1 20.1 CaSO 4 Dy 40.6+/-0.1 40.0 Cards 60.0+/-13 60.3 Lab (Reader #2) 20.3+/-03 20.1 39.2+/-03 40.0 60.7+/-0.4 60.3 a Lab result given is the mean +/-2 standard deviations of three determinations.
b Second International Intercomparison of Environmental Dosimeters conducted in April of 1976 by the Health and Safety Laboratory (HASL), New York, New York, and -the School of Public Health of the University of Texas, Houston, Texas.
c Value determined by sponsor of the intercomparison using continuously operated pressurized ion chamber.
d Mean +/-2 standard deviations of results obtained by all laboratories participating in the program.
e Third International Intercomparison of Environmental Dosimeters conducted in summer of 1977 by Oak Ridge National Laboratory and the School of Public Health of the University of Texas, Houston, Texas.
f Fourth International Intercomparison of Environmental Dosimeters conducted in summer of 1979 by the School of Public Health of the University of Texas Houston, Texas.
g Fifth International Intercomparison of Environmental Dosimeters conducted in fall of 1980 at Idaho Falls, Idaho and sponsored by the School of Public Health of the University of Texas, Houston, Texas and Environmental Measurements Laboratory, New York, New York, U.S.
Department of Energy.
A-20 F_- I __
Table A-2. (continued) mR Teledyne Average +/-2 od Lab Result Known (All Participants)
Code TLD Type Measurement
+/-2oa Value Footnotes (continued) h Seventh International Intercomparison of Environmental Dosimeters conducted in the spring and summer of 1984 at Las Vegas, Nevada, and sponsored by the US. Department of Energy, The U.S. Nuclear Regulatory Commission, and the U.S. Environmental Protection Agency.
i Eighth International Intercomparison of Environmental Dosimeters conducted in the fall and winter of 1985-1986 at New York, New York, and sponsored by the U.S. Department of Energy.
J Chips were submitted in September 1989 and cards were submitted in November 1989 to Teledyne Isotopes, Inc., Westwood, NJ for irradiation.
k Cards were irradiated by Teledyne Isotopes, Inc., Westwood, NJ on June 19, 1990.
1 Cards were irradiated by Dosimetry Associates, Inc., Northville, MI on October 30,1990.
M Irradiated cards were provided by Teledyne Isotopes, INC., Westwood, NJ. Irradiated on October 8,1991.
n Chips were irradiated by Teledyne Isotopes, Inc., Westwood, NJ on February 26, 1992.
0 Cards were irradiated by Teledyne Isotopes, Inc., Westwood, NJ on April 1, 1992.
A-21 t
Table A-3. In-house spiked samples.
Concentration in pRifL Lab Sample Date TIML Expected Code Type Collected Analysis Result Known Precision 2s, n=3a Activity 1s, n=a QC-MI-16 Milk Feb 1988 Sr-89 31.8+/-4.7 31.716.0 8.7 QC-MI-17 Milk QC-W-35 Water QC-W-36 Water QC-W-37 Water QC-MI-18 Milk QC-W-38 Water QC-W-39 Water QC-W-40 Water QC-W-41 QC-MI-19 Water Milk QC-W-42 Water QC-W-43 Water QC-W-44 Water Feb 1988 Feb 1988 Mar 1988 Mar 1988 Mar 1988 Apr 1988 Apr 1988 Apr 1988 Jun 1988 Jul 1988 Sep 1988 Oct 1988 Oct 1988 Sr-90 1-131 Cs-134 Cs-137 1-131 1-131 1-131 Sr-89 Sr-90 1-131 Cs-134 Cs-137 1-131 H-3 Co-60 Cs-134 Cs-137 Gr. alpha Gr. beta Sr-89 Sr-90 1-131 Cs-137 Sr-89 Sr-90 Co60 Cs-134 Cs-137 1-131 25.5+/-2.7 26.4+/-0.5 23.8+/-2.3 26.5+/-0.8 10.6+/-1.2 9.7+/-1.1 10.5+/-1.3 17.1+/-2.0 18.7+/-0.9 33.2+/-2.3 31.3+/-2.1 29.9+/-1.4 17.1+/-1.1 4439+/-31 23.7+/-0.5 25.4+/-2.6 26.6+/-2.3 12.3+/-0.4 22.6+/-1.0 15.1+/-1.6 18.0+/-0.6 88.4+/-4.9 22.7+/-0.8 48.5+/-3.3 10.9+/-1.0 20.9+/-3.2 38.7+/-1.6 19.0+/-2.4 22.2+/-0.6 27.813.5 23.2+/-5.0 24.2+/-6.0 25.1+/-6.0 14.3+/-1.6 11.6+/-1.1 11.6+/-1.0 19.8+/-8.0 173+/-5.0 26.7+/-5.0 30.2+/-5.0 26.2+/-5.0 14.2+/-5.0 4176+/-500 26.1+/-4.0 29.2+/-4.5 26.2+/-4.0 13.1+/-5.0 20.1+/-5.0 16.4+/-5.0 18.3+/-5.0 86.6+/-8.0 20.8+/-6.0 50.8+/-8.0 11.4+/-3.5 21.4+/-3.5 38.0+/-6.0 21.0+/-3.5 233+/-3.5 5.2 10.4 8.7 8.7 10.4 10.4 10.4 8.7 5.2 10.4 8.7 8.7 10.4 724 8.7 8.7 8.7 8.7 8.7 8.7 5.2 10.4 8.7 8.7 5.2 8.7 8.7 8.7 10.4 A-22
Table A-3. In-house spiked samples(continued)
Concentration inpCi
_L Lab Code Sample Type Date Collected Analysis TIML Result 2s, n=3a Known Activity Expected Precision 1s, n=3a QC-W-45 Water QC-MI-20 Milk QC-W-46 Water QC-MI-21 Milk QC-W-47 Water QC-MI-22 Milk QC-W-48 Water QC-W-49 Water QC-W-50 Water QC-W-51 Water QC-MI-23 Milk QC-MI-24 Milk QC-W-52 Water Oct 1988 Oct 1988 Dec 1988 Jan 1989 Mar 1989 Apr 1989 Apr 1989 Apr 1989 Apr 1989 Jun 1989 Jul 1989 H-3 1-131 Cs-134 Cs-137 Gr. alpha Gr. beta Sr-89 Sr-90 1-131 Cs-134 Cs-137 Sr-89 Sr-90 1-131 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 1-131 H-3 Gr. alpha Gr. beta Sr-89 Sr-90 1-131 Cs-134 Cs-137 Aug 1989 Sr-89 Sr-90 Sep 1989 1-131 A-23 4109+/-43 59.8+/-0.9 49.6+/-1.8 25.8+/-4.6 11.5+/-2.3 26.5+/-2.0 25.5+/-10.3 28.3+/-3.2 540+/-13 24.5+/-2.6 24.00.6 15.2+/-3.8 16.4+/-1.7 36.3+/-1.1 20.8+/-2.8 22.2+/-2.4 23.5+/-2.0 24.2+/-1.1 23.6+/-1.2 37.2+/-3.7 3011+/-59 13.0+/-1.8 26.0+/-1.2 19.4+/-65 27.6+/-3.5 46.8+/-3.2 27.4+/-1.8 24.1+/-1.8 25.4+/-2.7 46.0+/-1.1 9.6+/-0.3 4153+/-500 60.6+/-9.0 48.6+/-7.5 24.7+/-4.0 15.2+/-5.0 25.7+/-5.0 34.0+/-10.0 27.1+/-3.0 550+/-20 22.6+/-5.5 20.5+/-5.0 16.1+/-5.0 16.9+/-3.0 37.2+/-5.0 20.7+/-8.0 20.4+/-8.0 25.1+/-8.0 25.9+/-8.0 23.0+/-8.0 37.2+/-5.0 3089+/-500 15.0+/-5.0 25.5+/-8.0 22.0+/-10.0 28.6+/-3.0 43.4+/-5.0 28.3+/-6.0 20.8+/-6.0 27.2+/-10.0 47.8+/-9.6 9.71.9 724 10.4 8.7 8.7 8.7 8.7 8.7 5.2 10.4 8.7 8.7 8.7 5.2 10.4 8.7 8.7 8.7 8.7 8.7 10.4 724 8.7 8.7 8.7 5.2 10.4 8.7 8.7 8.7 5.2 10.4
Table A-3. In-house spiked samples (continued)
Concentration in prCfL Lab Sample Date TIML Expected Code Type Collected Analysis Result Known Precision 2s, n=3a Activity Is, n=3a QC-W-53 QC-W-54 Water Water QC-MI-25 Milk QC-W-55 QC-W-56 QC-W-57 QC-W-58 Water Water Water Water QC-W-59 Water QC-W-60 Water QC-MI-26 QC-MI-27 QC-MI-28 QC-MI-61 Milk Milk Milk Water QC-MI-29 Milk QC-W-62 Water Sep 1989 Sep 1989 Oct 1989 Oct1989 Oct 1989 Oct 1989 Nov 1989 Nov 1989 Dec 1989 Jan 1990 Feb 1990 Mar 1990 Apr 1990 Apr 1990 Apr 1990 1-131 Sr-89 Sr-90 1-131 Cs-134 Cs-137 1-131 Co-60 Cs-134 Cs-137 H-3 Sr-89 Sr-90 Sr-89 Sr-90 Gr. alpha Gr. beta Cs-134 Cs-137 Sr-90 1-131 Sr-89 Sr-90 1-131 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 19.0+/-0.2 25.8+/-4.6 26.5+/-53 70.0+/-33 22.1+/-2.6 29.4+/-1.5 33.3+/-13 15.2+/-0.9 22.1+/-4.4 27.2+/-1.2 3334+/-22 10.9+/-1. 4d 10.4+/-1.0d 101.06.0d 9 8.0+/-3.Od 10.8+/-1.1 11.6+/-0.5 19.3+/-1.0 25.2+/-1.2 18.0+/-1.6 63.8+/-2.2 17.9+/-5.5 19.4+/-2.5 90.7+/-9.2 18.3+/-1.0 20.3+/-1.0 8.7+/-0.4 20.0+/-0.2 28.7+/-1.4 20.9+/-4.2 24.7+/-4.0 29.7+/-5.0, 73.5+/-20.0 22.6+/-8.0 27.5+/-8.0 353+/-10.0 17.4+/-5.0 18.9+/-8.0 22.9+/-8.0 3379+/-500 11.1+/-1.0d 10.3+/-1.0d 104.1+/-10.Sd 95.0+/-l0.0d 10.6+/-4.0 11.4+/-4.0 20.8+/-8.0 22.8+/-8.0 18.8+/-5.0 62.6+/-6.0 23.1+/-8.7 23.5+/-5.2 82.5+/-8.5 19.7+/-5.0 18.2+/-5.0 9.4+/-5.0 19.7+/-5.0 22.715.0 A-24
.,I 10.4 87 52 10.4 8.7 8.7 10.4 87 8.7 8.7 724 8.7 52 18.0 16.4 8.7 8.7 8.7 8.7 52 10.8 8.7 52 10.4 8.7 8.7 8.7 8.7 87
In-house spiked samples (continued)
Concentration in pRifL Lab Sample Date TIML Expected Code Type Collected Analysis Result Known Precision 2s, n=3a Activity 1s, n=3a QC-W-63 QC-W-64 QC-W-65 QC-W-66 QC-MI-30 Water Water Water Water Milk QC-W-68 Water QC-MI-31 QC-W-69 QC-MI-32 QC-W-70 QC-W-71 QC-W-73 Milk Water Milk Water Water Water QC-W-74 Water Apr 1990 Apr 1990 Jun 1990 Jun 1990 Jul 1990 Jun 1990 Aug 1990 Sep 1990 Oct 1990 Oct 1990 Oct 1990 Oct 1990 Dec 1990 1-131 H-3 Ra-226 U
Sr-89 Sr-90 Cs-134 Cs-137 Gr. alpha Gr. beta 1-131 Sr-89 Sr-90 1-131 Cs-134 Cs-137 H-3 1-131 Co-60 Cs-134 Cs-137 Gr. alpha Gr. beta 63.5+/-8.0 1941+/-130 6.4+/-0.2 6.2+/-0.2 12.8+/-0.4 18.2+/-1.4 46.0+/-1.3 27.6+/-1.3 9.8+/-03 11.4+/-0.6 68.8+/-1.6 17.7+/-1.6 13.9+/-1.6 34.8+/-0.2 25.8+/-1.2 25.3+/-2.0 2355+/-59 55.9+/-0.9 18.3+/-2.7 28.3+/-2.3 22.7+/-1.3 21.4+/-1.0 25.9+/-1.0 66.0+/-6.7 1826.0+/-350.0 6.9+/-1.0 6.0+/-6.0 18.4+/-10.0 18.7+/-6.0 49.0+/-5.0 253+/-5.0 10.6+/-6.0 113+/-7.0 61.4+/-12.3 19.2+/-10.0 17.4+/-10.0 32.4+/-6.5 273+/-10.0 22.4+/-10.0 2276+/-455 51.8+/-10.4 16.8+/-5.0 27.0+/-5.0 22.4+/-5.0 26.1+/-6.5 22.3+/-5.6 a n=3 unless noted otherwise.
b n=2 c n=1 d Concentration in pCi/mL A-25 11.4 724 1.8 10.4 8.7 5.2 8.7 8.7 8.7 8.7 10.4 8.7 5.2 8.7 8.7 8.7 605 10.4 8.7 8.7 8.7 11.3 8.7 Table A-3.
Table A-3. In-house spiked samples (continued)
Sample Type Date Collected Analysis Concentration in pRi/L TIML Result 2s, n=1 e QC-MI-33 Milk QC-MI-34 Milk QC-W-75 Water QC-W-76 Water QC-W-77 Water QC-W-78 Water QC-MI-35 Milk QC-W-79 Water QC-MI-36 Milk QC-W-80 Water QC-W-81 Water QC-W-82 Water QC-W-83 Water QC-MI-37 Milk QC-W-84 Water Jan 1991 Feb 1991 Mar 1991 Apr 1991 Apr 1991 Apr 1991 Apr 1991 Jun 1991 Jul 1991 Oct 1991 Oct 1991 Oct 1991 Oct 1991 Oct 1991 Dec 1991 H-3 1-131 Cs-134 Cs-137 Gr. alpha fG b-&-
Sr-89 Sr-90 Cs-134 Cs-137 1-131 Sr-89 Sr-90 1-131 Co-60 Cs-134 Cs-137 H-3 1-131 Cs-134 Cs-137 Gr. alpha Gr. beta Sr-89 Sr-90 1-131 Cs-137 Sr-89 Sr-90 1-131 Co-60 Cs-134 Cs-137 A-26 lab Code Known Activity Expected Precision 1s, n=1e 20.7+/-33 19.0+/-1.4 22.2+/-1.7 26.1+/-1.6 40.7+/-1.8 18.8+/-1.5 16.0+/-0.8 56.5+/-1.7 16.4+/-2.2 23.8+/-2.5 25.0+/-2.4 4027+/-188 48.0+/-0.8 19.2+/-2.0 22.8+/-2.2 7.4+/-0.7 11.0+/-0.7 28.1+/-2.1 11.6+/-0.7 14.4+/-1.9 34.3+/-3.0 27.4+/-6.9 11.7+/-1.4 19.1+/-0.7 22.6+/-2.7 15.5+/-1.8 17.5+/-2.1 4639+/-137 23.6+/-3.2 22.7+/-2.8 38.3+/-3.0 6.2+/-0.6 11 0"A07 21.6+/-5.0 23.0+/-3.0 19.6+/-5.0 22.3+/-5.0 40.1+/-6.0 233+/-5.0 17.2+/-3.0 59.0+/-5.9 15.7+/-5.0 22.6+/-5.0 21.1+/-5.0 4080+/-408 49.2+/-6.0 22.6+/-5.0 22.1+/-5.0 7.8+/-5.0 11.0+/-5.0 34.0+/-10.0 11.5+/-3.0 183+/-5.0 35.1+/-5.0 24.4+/-5.0 14.1+/-5.0 20.6+/-4.2 22.1+/-5.0 17.6+/-5.0 17.6+/-5.0 4382+/-438 25.8+/-5.0.
22.1+/-5.0 35.1+/-5.0 7.8+/-5.0 11(4-5 A 5.0 3.0 5.0 5.0 6.0 5.0 3.0 5.9 5.0 5.0 5.0 408 6.0 5.0 5.0 5.0 5.0 5.0 3.0 5.0 5.0 5.0 3.0 6.0 5.0 5.0 5.0 438 6.0 5.0 5.0 5.0 50
Table A-3. In-house spiked samples (continued)
Concentration in pCifL Sample Type QC-MI-39 Milk QC-W-85 Water QC-W-90 Water Date Collected Analysis Jan 1992 Sr-89 Sr-90 1-131 Cs-134 Cs-137 Mar 1992 Sr-89 Sr-90 Apr 1992 H-3 Apr 1992 1-131 Apr 1992 Co-60 Cs-134 Cs-137 Apr 1992 Cs-134 Cs-137 Apr 1992 1-131 Jun 1992 Gr. alpha Gr. beta Aug. 1992 Sr-89 Sr-90 Cs-134 Cs-137 Sept. 1992 Sr-89 Sr-90 Oct. 1992 1-131 Oct 1992 Co-60 Cs-134 Cs-137 TIML Result 2s, n=le Known Activity Expected Precision 1s, n=1e A-27 Lab Code QC-W-86 QC-W-87 QC-W-88 QC-MI-40 QC-W41 QC-W-89 QC-MI-42 Water Water Water Milk Milk Water Milk QC-W-91 QC-W-92 Water Water 21.6+/-6.5 38.7+/-1.8 76.8+/-0.9 42.1+/-5.7 55.2+/-6.4 26.2+/-3.1 24.4+/-1.4 4080+/-190 33.5+/-0.6 17.5+/-2.7 28.9+/-2.5 41.0+/-3.0 58.0+/-2.6 43.7+/-3.0 50.3+/-0.8 15.3+/-0.8 17.2+/-0.9 41.4+/-5.9 48.9+/-2.5 20.1+/-2.8 26.2+/-2.7 6.7+/-3.4 16.1+/-1.4 34.9+/-2.2 11.4+/-1.9 18.7+/-2.3 14.1+/-1.8 31.2+/-10.0 42.3+/-8.5 83.7+/-16.0.
49.4+/-10.0 53.0+/-10.0 32.0+/-10.0 28.0+/-6.0 4027+/-403 33.2+/-120 19.7+/-10.0 33.5+/-10.0 38.9+/-10.0 55.9+/-10.0 38.9+/-10.0 55.9+/-11.2 13.6+/-10.0 17.6+/-10.0 51.2+/-10.2 51.9+/-10.4 20.2+/-10.0 26.1+/-10.0 126+/-10.0 15.6+/-6.0 34.9+/-10.0 9.2+/-10.0 143+/-10.0 15.0+/-10.0 5.0 4.2 8.4 5.0 5.0 5.0 3.0 403 6.0 5.0 5.0 5.0 5.0 5.0 5.6 5.0 5.0 5.0 5.2 5.0 5.0 5.0 3.0 6.0 5.0 5.0 5.0
Table A-3.
Date Collected Analysis Oct. 1992 Oct. 1992 Oct 1992 Oct 1992 Oct 1992 H-3 H-3 1-131 1-131 Cs-134 Cs-137 1-131 Cs-134 Cs-137 Concentration in pf/L TIML Result 2s, n=1e 3704+/-186 14,925+/-339 64.2+/-2.7 19.9+/-1.0 14.2+/-3.4 14.1+/-52 36.1+/-1.2 28.2+/-4.0 38.8+/-5.1 Known Activity 3904+/-390 15,616+/-1,562 67.2+/-10.0 21.5+/-6.0 12.7+/-10.0 17.1+/-10.0 43.0+/-10.0 25.4+/-10.0 34.2+/-10.0 e Starting in January 1991, all determinations are single.
A-28 Lab Code Sample Type QC-W-93 QC-W-94 QC-W-95 QC-MI-43 QC-MI-44 Water Water Water Milk Milk Expected Precision 1s, n=1e 367 1562 6.7 6.0 5.0 5.0 6.0 5.0 5.0 In-house spiked samples (continued)
Table A-4. In-house "blank" samples.
Concentration (pCif L)
Sample Type Milk "Dead" Water Milk D.I. Water Milk Water Water Milk Water Water Water Date Collected Jan 1988 Jan 1988 Mar 1988 Mar 1988 Jul 1988 Jul 1988 Sep 1988 Oct 1988 Oct 1988 Oct 1988 Oct 1988 Analysis 1-131 H-3 SPS-5386 SPW-5448 SPS-5615 SPS-5650 1-131 Co-60 Cs-134 Cs-137 H-3 Results (4.66 a)
<0.1
<177
<2.4
<2.5
<0.3
<0.4 2.4+/-0.5a
<0.3
<0.04
<0.05
<0.03
<0.03
<0.03
<0.06
<0.01
<0.08
<0.02
<0.5 1.8+/-0.5a
<0.4
<0.4 Cs-134 Cs-137 1-131 Sr-89 Sr-90 Th-228 Th-230 Th-232 U-234 U-235 U-238 Am-241 Cm-241 Pu-238 Pu-240 Sr-89 Sr-90 1-131 Cs-137 Fe-55 Sr-89 Sr-90 1-131 Cs-134 Cs-137 Acceptance Criteria (4.66 c)
<1
<300
<10
<10
<1
<5
<1
<1
<1
<1
<1
<1
<1
<1
<1
<1
<1
<1
<1
<1
<10
<1
<5
<1
<1
<10
<10
<1
<10
<10
<10
<300 A-29 Lab Code
<0.8
<0.7
<0.7
<0.2
<6.1
<5.9
<0.2
<5.7
<3.7
<4.3
<170 SPS-6090 SPW-6209 SPW-6292 SPS-6477 SPW-6478 SPW-6479 SPW-6480
Table A-4. In-house "blank" samples (continued)
Concentration (pCifL)
Lab Code Sample Type SPW-6625 SPS-6723 SPW-6877 SPS-6963 SPW-7561 SPW-7207 SPS-7208 SPW-7588 SPS-7322 SPW-7559 SPW-7560 SPW-7562 Water Milk Water Milk Water Water Milk Water Milk Water Water Water Date Collected Dec 1988 Jan 1989 Mar 1989 Apr 1989 Apr 1989 Jun 1989 Jun 1989 Jun 1989 Aug 1989 Sep 1989 Oct 1989 Oct 1989 Analysis Gr. alpha Gr. beta Sr-89 Sr-90 1-131 Cs-134 Cs-137 Sr-89 Sr-90 1-131 Cs-134 Cs-137 H-3 Ra-226 Ra-228 Sr-89 Sr-90 1-131 Cs-134 Cs-137 Gr. alpha Gr. beta Sr-89 Sr-90 1-131 Cs-134 Cs-137 Sr-89 Sr-90 1-131 H-3 Results (4.66 c)
<0.7
<1.9
<0.6 1.9+/-O.5a
<0.2
<4.3
<4.4
<0.4
<0.6
<0.3
<5.9
<6.2
<150
<0.2
<0.6
<0.6 2.1+/-0.5a
<0.3
<6.4
<7.2
<0.2
<1.0
<1.4 4.8+/-1.0a
<0.2
<6.9
<8.2
<2.0
<0.7
<0.1 Acceptance Criteria (4.66 a)
<1
<4
<5
<1
<1
<10
<10
<5
<1
<1
<10
<10
<300
<1
<1
<5.
<1
<1
<10
<10
<1
<4
<5
<1
<1
<10
<10
<5
<1
<1
<140 A-30
Lab Code SPS-7605 SPW-7971 SPW-8039 SPS-8040 SPS-8208 SPS-8312 SPW-8312A SPS-8314 SPS-8510 SPW-8511A SPS-8600 SPM-8877 SPW-8925 Sample Type Milk Water Water Milk Milk Milk Water Milk Milk Water Milk Milk Water Date Collected Analysis Results (4.66 a)
Acceptance Criteria (4.66 c)
A-31 Nov 1989 Dec 1989 Jan 1990 Jan 1990 Jan 1990 Feb 1990 Feb 1990 Mar 1990 May 1990 May 1990 Jul 1990 Aug 1990 Aug 1990 1-131 Cs-134 Cs-137 Cr. alpha Cr. beta Ra-226 Sr-89 Sr-90 Sr-89 Sr-90 Cs-134 Cs-137 Sr-89 Sr-90 Sr-89 Sr-90 1-131 1-131 Cs-134 Cs-137 H-3 Sr-89 Sr-90 1-131 Cs-134 Cs-137 I-131 H-3
<0.2
<8.6
<10
<0.4
<0.8
<0.2
<0.8
<1.0
<0.8 1.6+/-0.5a
<3.6
<4.7
<0.3 1.2+/-03a
<0.6
<0.7
<0.3
<0.2
<4.6
<4.8
<200
<0.8 1.7+/-0.6a
<0.3
<5.0
<7.0
<0.2
<200
<1
<10
<10
<1
<4
<1
<5
<1
<5
<1
<10
<10
<5
<1
<5
<5
<1
<1
<10
<10
<300
<5
<1
<1
<10
<10
<1
<300 Table A-4. In-house "blank" samples (continued)
Concentration (pClfL)
Table A-4. In-house "blank" samples (continued)
Concentration (pCi/L)
Acceptance Lab Sample Date Results Criteria Code Type Collected Analysis (4.66 c)
(4.66 a)
SPW-8926 SPW-8927 SPW-8928 SPW-8929 SPW-69 SPW-106 SPM-107 SPW-370 SPW-372 SPS-406 SPS-421 SPW-451 Water Water Water Water Water Water Milk Water Water Milk Milk Water Aug 1990 Aug 1990 Aug 1990 Aug 1990 Sep 1990 Oct 1990 Oct 1990 Oct 1990 Dec.1990 Jan 1991 Feb 1991 Feb 1991 Gr. alpha Gr. beta U-234 U-235 U-238 Mn-54 Co-58 Co-60 Cs-134 Cs-137 Sr-89 Sr-90 Sr-89 Sr-90 H-3 1-131 1-131 Cs-134 Cs-137 Mn-54 Co-58 Co-60 Cs-134 Cs-137 Gr. alpha Gr. beta Sr-89 Sr-90 Cs-134 Cs-137 1-131 Ra-226 Ra-228
<0.3
<0.7
<1
<4
<0.01
<0.02
<0.01
<4.0
<4.1
<2.4
<3.3
<3.7
<1.4
<0.6
<1.8
<0.8
<180
<0.3
<0.4
<3.3
<4.3
<1.7
<2.6
<1.6
<1.7
<1.8
<0.3
<0.8
<0.4 1.8io.4a
<3.7
<5.2
<0.3
<0.1
<0.9
<1
<1
<1
<10
<10
<10
<10
<10
<5
<1
<5
<1
<300
<1
<1
<10
<10
<10
<10
<10
<10
<10
<1
<4
<5
<1
<10
<10
<1
<1
<1 A-32
Table A-4. In-house "blank" samples (continued)
Concentration (pCifL)
Date Collected Analysis Results (4.66 a)
Acceptance Criteria (4.66 c)
SPW-514 Water SPW-586 Water SPS-587 Milk SPW-837 Water SPM-953 Milk SPM-1236 Milk SPW-1254 Water SPW-1256 Water SPW-1259 Water SPW-1444 Water SPM-1578 Milk tab Code Sample Type
<1.1
<0.9
<0.2
<2.5
<2.4
<2.2
<0.2
<1.7
<1.9
<0.6
<1.1
<5
<1
<1
<10
<10
<10
<1
<10
<10 Mar 1991 Apr 1991 Apr 1991 Jun 1991 Jul 1991 Oct 1991 Oct 1991 Oct 1991 Oct 1991 Dec 1991 Jan 1992 Sr-89 Sr-90 1-131 Co-60 Cs-134 Cs-137 1-131.
Cs-134 Cs-137 Gr. alpha Gr. beta Sr-89 Sr-90 1-131 Cs-137 1-131 Cs-134 Cs-137 Sr-89.
Sr-90 1-131 Co40 Cs-134 Cs-137 H-3 Gr. alpha Gr. beta Sr-89 Sr-90 1-131 Cs-134 Cs-137
<1
<4
<0.7 0.4+/-03a
<0.2
<4.9
<0.2
<3.7
<4.6
<2.8
<0.7
<0.4
<3.6
<4.0
<3.6
<160
<0.4
<0.8
<0.5 1.3+/-0.4a
<0.2
<7.2
<8.0
<5
<1
<1
<10
<1
<10
<10
<5
<1
<1
<10
<10
<10
<300
<1
<4
<5
<1
<1
<10
<10 A-33
Table A-4. In-house "blank" samples (continued)
Concentration (vCi/L)
Acceptance Criteria (4.66 c)
Lab Code SPW-1860 SPW-2067 SPW-2114 SPW-2119 SPW-2126 SPM-2133 SPW-2220 SPW-2369 SPM-2500 SPW-2666 SPW-2828 SPM-2829 SPW-3212 SPW-3057 SPW-3294 Sample Type Water Water Water Milk Water Milk Water Water Milk Water Water Milk Water Water Water Date Collected Mar 1992 Apr 1992 Apr 1992 Apr 1992 Apr 1992 Apr 1992 May 1992 Jun 1992 Aug 1992 Sept. 1992 Oct. 1992 Oct. 1992 Oct 1992 Nov. 1992 Dec. 1992 Analysis Sr-89 Sr-90 H-3 C-14 Co-60 Cs-134 Cs-137 1-131 1-131 Co-60 Cs-134 Cs-137 Gr. alpha Gr. beta 1-131 Sr-89 Sr-90 Sr-89 Sr-90 Co-60 Cs-134 Cs-137 1-131 H-3 Co-60 Cs-134 Cs-137 Ra-228 Ra-226 Gr. alpha Gr. beta Results (4.66 c)
<0.6
<0.4
<168
<1.0
<6.3
<4.5
<5.4
<0.2
<0.2
<2.1
<2.1
<2.3
<0.4
<0.8
<0.4
<1.2
<0.9
<0.8
<0.5
<4.8
<6.0
<6.1
<0.3
<177
<9.3
<6.4
<7.2
<1.0
<0.03
<0.4
<0.8 A-34
<5
<1
<300
<200
<10
<10
<10
<1
<1
<10
<10
<10
<1
<4
<1
<5
<1
<5
<1
<10
<10
<10
<1
<300
<10
<10
<10
<1
<1
<1
<4
Revision 0, 12-29-86 ATI'ACHMENT B 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 pCi/liter
>100 pCi/liter or kg 5% of known value Strontium-89b 5 to 50 pCi/liter or kg 5 pCi/liter
>50 pCi/liter or kg 10% of known value Strontium-90b 2 to 30 pCi/liter or kg 3.0 pCi/liter
>30 pCi/liter or kg 10% of known value Potassium
>0.1 g/liter or kg 5% of known value Gross alpha
<20 pCi/liter 5 pCi/liter
>20 pCi/liter 25% of known value Gross beta
<100 pCi/liter 5 pCi/liter
>100 pCi/liter 5% of known value Tritium
<4,000 pCi/liter 1s = (pCi/liter)=
169.85 x (known).0933
>4,000 pCi/liter 10% of known value Radium-226, -228
<0.1 pCi/liter 15% of known value Plutonium 0.1 pCi/liter, gram, or sample 10% of known value Iodine-131,
<55 pCi/liter 6 pCi/liter lodine-129b
>55 pCi/liter 10% of known value Uranium-238,
<35 pCi/liter 6 pCi/liter Nickel-64b,
>35 pCi/liter 15% of known value Technetium-99b Iron-55b 50 to 100 p0/liter 10 pCi/liter
>100 pCi/liter 10% of known value a From EPA publication, "Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.
b TIML limiL A-35 TIML-BLIND-01
The following is an explanation of the reasons why certain samples were outside the control limit specified by the Environmental Protection Agency for the Interlaboratory Comparions Program starting January 1988.
EPA TIML Control Result Limit Lab Code Analysis (pCi/L)a (pCl/L)a Explanation STF-524 K
STW-532 1-131 STW-534 Co-60 STM-554 Sr-90 STW-560 Pu-239 STW-568 Ra-228 1010.7 +/-158.5b 9.0+/-2.0 63.3+/-1.3 51.0+/-2.0 5.8+/-1.1 26+/-1.0 1123.5-1336.5b 6.2-8.8 41.3-58.7 54.8-65.2 3.5-4.9 274.5 Error in transference of data. Correct data was 1105+/-33 mg/kg. Results in the past have been within the limits and TIML will monitor the situation in the future.
Sample recounted after 12 days. The average result was 8.8+/-1.7 pCi/L (within EPA control limits).
The sample was recounted in order to check the decay. Results in the past have been within the limits and TIML will continue to monitor the situation in the future.
High level of Co-60 was due to contamination of beaker. Beaker was discarded upon discovery of contamination and sample was recounted.
Recount results were 53.2+/-3.6 and 50.9+/-2.4 pCi/L The cause of low result was due to very high fat content of milk.
It should be noted that 63% of all participants failed this test Also, the average for all participants was 54.0 pCi/L before the Grubb and 55.8 pCi/L after the Grubb.
The cause of high results is not known though it is suspected that the standard was not properly calibrated by supplier and is under investigation. New Pu-236 standard was obtained and will be used for the next test.
The cause of low results is not known. Next EPA cross check results were within the control imits.
No further action is planned.
A-36 ADDENDUM TO APPENDIX A
I-,
ADDENDUM TO APPENDIX A (continued)
TIML Result Analysis (pCi/L)a EPA Control Limit (pc/L)a Explanation STM-570 Sr-89 Sr-90 STW-589 Sr-90 STM-599 K
STW-601 Gr. alpha 26.0+/-10.0 45.7+/-4.2 17.3+/-1.2 30.3-47.7 49.8-60.2 17.4-22.6 1300.0+/-69.2c 11.0+/-2.0 11.6-32.4 The cause of differencein standard used EPA filter.
high results is the geometery between in the TIML lab and STW-632 Ba-133 STM-641 1-131 STM-661 Sr-89 74.0+/-6.9 130.7+/-16.8 25.3+/-7.6 51.6-72.4 Sample was reanalyzed. Results of the reanalyses were 63.8+/-6.9 pCi/L within EPA limit.
88.9-127.1 The cause of high result is unknown.
In-house spike sample was prepared with activity of 1-131 68.3+/-6.8 pCi/L.
Result of the analysis was 69.1+/-9.7 pCi/L 29.3-46.7 The cause of low result is unknown.
Data was checked for errors. The In house spike sample was prepared with activity of Sr-89 41.0+/-10.0 pCi/L.
Result of the analysis was 37.2+/-3.6 pCi/L A-37 Lab Code STAF-626 Gr. alpha 38.7+/-1.2 14.6-35.4 The cause of low results was falsely high recovery due to suspected incomplete calcium removal. Since EPA sample was used up, internal spike was prepared and analyzed. The results were within control limits (See table A-3, sample QC-MI-24). No further action is planned.
Sample was reanalyzed in triplicate; results of reanalyses were 18.8+/-1.5 pCi/L. No further action is planned.
Sample was reanalyzed in triplicate.
Results of reanalyses were 1421.7+/-95.3 mg/L. The cause of low results was using wrong volume.
Sample was reanalyzed in triplicate.
Results of reanalyses were 13.4+/-1.0 pCi/L
ADDENDUM TO APPENDIX A (continued)
TIML Result Lab Code Analysis (pCi/L)a EPA Control Limit (pCi/L)a Explanation STM-673 K
1540.0+/-10 3.9c 1597.3-1902.7 Activity was calculated using the wrong volume (3.5 L), instead of 3.25 L. Correction for volume resulted in a value of 1660.0+/-110.1 mg/L; within EPA control limits.
a Reported in pCi/L unless otherwise noted.
C Concentrations are reported in mg/L A-38
APPENDIX B DATA REPORTING CONVENTIONS B-1
4 A
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 found to be below the lower limit of detection L it is reported as
<L where L = the lower limit of detection based on 4.660 uncertainty for a background sample.
3.0. Duplicate analyses 3.1 Individual results:
xi si X1 &s2 Reported result x+/-s where x= (1/2) (xl x2) s= (1/2) 52+ 2 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 B-2
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 and standard deviation(s) of a set of n numbers xt, x2... xn are defined as follows:
1 n
L (x-x)2 s =
n-1 4.2 Values below the highest lower limit of detection are not included in the average.
4.3 If all of the 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 figure following those to be retained is less than 5, the figure is dropped, and the retained figures are kept unchanged. As an example, 11.443 is rounded off to 11.44.
4.5.2. If the figure following those to be retained is greater than 5, the figure is dropped and the last retained figure is raised by 1. As an example, 11.446 is rounded off to 11.45.
4.5.3. If the figure following those to be retained is 5, and if there are no figures other than zeros beyond the five, the figure five is dropped, and the last-place figure retained is increased by one if it is an odd number or it is kept unchanged if an even number. As an example, 11.435 is rounded off to 11.44, while 11.425 is rounded off to 11.42.
B-3
a 4
APPENDIX C Maximum Permissible Concentrations of Radioactivity in Air and Water Above Background in Unrestricted Areas C-1
Table C-1. Maximum permissible concentrations of radioactivity in air and water above natural background in unrestricted areas.a Air Water Gross alpha Gross beta Iodine-131b 3 pCi/m 3 100 pCi/m3 0.14 pCi/m3 Strontium-89 Strontium-90 Cesium-137 Barium-140 Iodine-131 Potassium-40c Gross alpha 3,000 pCi/I 300 pCi/I 20,000 pCi/I 20,000 pCi/i 300 pCi/1 3,000 pCi/I 30 pCi/1 Gross beta Tritium 100 pCi/i 3 x 106 pCi/1 a Taken from Code of Federal Regulations Title 10, Part 20, Table II and appropriate footnotes. Concentrations may be averaged over a period not greater than one year.
b From 10 CFR 20 but 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
I*-
APPENDIX D Sampling Location Maps D-1
k.-
MONTI CAD M0024
£ MONTI CAD M00522
I MONTI CAD M00523