ML113260377
| ML113260377 | |
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| Site: | Monticello  |
| Issue date: | 12/31/1991 |
| From: | Huebner L Teledyne Isotopes Midwest Lab |
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'4WTELEDYNE ISOTOPES MIDWEST LABORATORY 700 LANDWEHR ROAD NORTHBROOK, ILLINOIS 60062-2310 (708) 564-0700 FAX (708) 564-4517 NORTHERN STATES POWER COMPANY MINNEAPOLIS, MINNESOTA MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO.
50-263 LICENSE NO. DPR-22 UNITED STATES ANNUAL REPORT TO THE NUCLEAR REGULATORY COMMISSION Radiation Environmental Monitoring Program January 1, 1991 to December 31, 1991 Prepared Under Contract by TELEDYNE ISOTOPES MIDWEST LABORATORY Project No.
8010 Approved by:
y 6 ii VI A. G. Huebner VGeneral Manager 16 April 1992 9205070205 920430 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 Nuclear Radiological Services Department.
The report was prepared by L. G. Huebner, General Manager, Teledyne Isotopes Mid west Laboratory.
He was assisted in the report preparation by other staff members of this laboratory.
ii
Preface List of Tables.
INTRODUCTION.
SUMMARY
RADIATION ENVIRONMENTAL MONITORING PROGRAM (REMP) 3.1 Program Design and Data Interpretation....
3.2 Program Description.
3.3 Program Execution.
3.4 Laboratory Procedures.
3.5 Program Modifications.
3.6 Land Use Census.
RESULTS AND DISCUSSION.
4.1 Atmospheric Nuclear Detonations and Nuclear Accidents.
4.2 Program Findings TABLES.
REFERENCES CITED.
TABLE OF CONTENTS Page 11 111 1
2 3
3 4
5 6
7 7
8 8
8 12 24 A-1 B-1 C-1 APPENDICES A
Interlaboratory Comparison Program Results.
B Data Reporting Conventions.
C Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Area iii No.
1.0 2.0 3.0 4.0 5.0 6.0
LIST OF TABLES No.
Title 5.1 Sample Collection and Analysis Program, 1991.
5.2 Sampling Locations.
5.3 Missed Collections and Analyses, 1991 5.4 Environmental Radiological Monitoring Program Summary In addition, the following tables are in the Appendices:
Appendix A A-1 Interlaboratory Comparison Program Results, 1988-1991 A-2 Interlaboratory Comparison Program Results, (TLDs)
A-3 In-house Spiked Samples A-4 In-house "Blank" Samples.
Attachment B:
Acceptance Criteria for Spiked Samples Addendum to Appendix A:
Explanation of the Results Outside of Control Limits Page 13 15 17 18 A-3 A-15 A-18 A-23 A-28 A-29 Appendix C C-1 Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas C-2 iv
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, 1991.
This Program monitors the levels of radio activity 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, 1992a) 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.
1
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 1991 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.
2
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 radio active 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 signifi cantly 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 3
because of the different characteristic proportions -in which they appear in the fission product mix produced by a nuclear reactor and that pro duced by a nuclear detonation. Each of the three isotopes is produced in roughly equivalent amounts by a reactor:
each constitutes about 10% of the total activity of fission products 10 days after reactor shutdown.
On the other hand, 10 days after a nuclear explosion, the contributions of zirconium-95, cerium-144, and cesium-137 to the activity of the resulting debris are in the approximate ratio 4:1:0.03 (Eisenbud, 1963).
Beryllium-7 is of cosmogenic origin and potassium-40 is a naturally occurring isotope.
They were chosen as calibration monitors and should not be considered as radiological impact indicators.
The other group quantified consists of niobium-95, ruthenium-103 and
-106, cesium-134, barium-lanthanum-140, and cerium-141.
These isotopes are released in small quantities by nuclear power plants, but to date their major source of injection into the general environment has been atmospheric nuclear testing.
Nuclides of the final group, manganese-54, iron-59, cobalt-58 and -60, and zinc-65, are activation products and arise from activation of corrosion products.
They are typical components of nuclear power plant's effluents, but are not produced in significant quantities by nuclear detonations.
Other means of distinguishing sources of environmental radiation can be employed in interpreting the data.
Current radiation levels can be 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 (indi cator 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, 1991).
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 4
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).
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 mi radius, six (6) at special interest locations and one control location, 11.1 mi 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 liquid 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:
5
(1) There were no TLD data for Location M-12A for the fourth quarter of 1991.
The TLDs were lost in the field.
Deviations from the program are summarized in Table 5.3.
3.4 Laboratory Procedures The iodine-131 analyses in milk and drinking water were made using a sensitive radiochemical procedure which involves separation of the iodine using an ion-exchange method and solvent extraction and finally 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) spectromet ry.
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, 1985).
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, 1991).
The. TIML QA Program includes parti cipation in Interlaboratory Comparison (crosscheck)
Programs.
Results obtained in crosscheck programs are presented in Appendix A.
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3.5 Program Modifications During the growing season, milk producers were monitored to determine when the dairy animals were on pasture or fresh cut feed.
The frequency of milk samples was increased to semimonthly at four indicator locations (Peterson,
- Hoglund, Witschen, and Weinand),
plus the control location (Kirchenbauer),
at various times during the period because animals were on pasture or fresh cut feed.
In August 1991, the Witschen Dairy Farm (M-18) went out of business.
The Holthaus Dairy Farm (M-29) was included into the program at this time.
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 ft 2 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 ft 2 or greater gardens producing broad leaf vegetation in each of the meteoro logical sectors within a distance of three miles.
This census shall be conducted at least once per year between the dates of May 1 and October 31.
New locations shall be added to the radiation environmental monitoring program within 30 days and sampling locations having lower calculated doses or a lower dose commitment may be deleted from this monitoring program after October 31 of the year in which the land use census was conducted.
The 1991 land use census was completed on September 30, 1991.
This census did not identify any locations of exposure pathways different from those used in the program during the first six months of the year.
The Witschen farm went out of business and was replaced by the Holthaus Dairy Farm in August, 1991.
There were also four changes in garden sampling locations.
The garden in the NNE sector moved 0.1 mi closer, the E sector moved 0.5 mi closer, the NE sector moved 0.6 mi further away, and the garden in the SW sector moved 0.2 mi further away.
The distance of the Ernst residence in the SSW sector was reevaluated, and determined to be 0.1 mi closer to the plant.
There were no other changes in residence.
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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 1991.
The last reported test was conducted on October 16, 1980 by the People's Republic of China.
The reported yield was in the 200 kiloton to 1 megaton range.
There were no reported accidents at nuclear reactor facilities in 1991.
4.2 Program Findings Results obtained show background levels of radioactivity in the environ mental samples collected in the vicinity of the Monticello Nuclear Generating Plant in 1991.
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 nearly identical at both inner and outer rings (15.2 and 15.8 mR/91 days, respectively).
The mean at special locations was 15.3 mR/91 days.
The mean at the control location was 15.0 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, and 1990 (12.3, 12.5, 13.6, 14.2, 15.3, 15.4, 15.2, 15.2 and 16.2 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 (0.024 pCi/m 3) and 8
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/ m3), 1985 (0.025 pCi/m3, and 1986 (0.026 pCi/m 3 ),
1987 (0.026 pCi/
m3),
1988 (0.030 pCi/m), in 1989 (0.026 pCi/m 3 ), and in 1990 (0.023 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 al., 1969).
It had been attributed to fallout of nuclides from the stratosphere (Gold et al., 1964).
It was pro nounced in 1981, occurred to a lesser degree In 1982, and did not occur in 1983,
- 1984, 1985, or 1987.
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, and 1990.
Two pieces of evidence indicate conclusively that the elevated activity observed during the fourth quarter was not attributable to the Plant operation.
First, elevated activity of similar size occurred simulta neously 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, 1992b).
Gamma spectroscopic analysis of quarterly composites of air particulate filters yielded similar results for indicator and control locations.
Beryllium-7, which is produced continously in the upper atmosphere by cosmic radiation (Arnold and Al-Salih, 1955),
was detected in all samples with an average of 0.054 pCi/m 3 at both indicator 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 of 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 radio-9
contaminants 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.
In summary, the milk data for 1991 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 2.9 pCi/L and was identical or similar to the average level observed in 1977 (3.4 pCi/L), in 1978 (3.8 pCi/L),
in 1979 (3.4 pCi/L), in 1980 (3.2 pCi/L), in 1981 (3.5 pCi/L),
and in 1982 (2.9 pCi/L),
in 1983 (3.3 pCi/L),
in 1984 (2.8 pCi/L), in 1985 (2.8 pCi/L),
in 1986 (2.5 pCi/L),
in 1987 (2.4 pCi/L),
in 1988 (2.7 pCi/L), in 1989 (2.6 pCi/L),
and in 1990 (2.2 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 indi cation of a plant effect.
Well Water The tritium level was below the LLD level of 330 pCi/L in all samples.
All of the gamma scan results were below detection limits.
There was no indication of a plant effect.
Crops Two samples of cabbage were collected in September and analyzed for iodine-131.
The 1-131 level was below 0.022 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 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-occuring isotope, was found to be similar in upstream and downstream samples (2.73 and 2.58 pCi/g wet weight, respectively).
All gamma-emitting isotopes were below their respective LLD levels.
There was no indication of a plant effect.
10
Invertebrates Two samples were collected in July and two in November.
The samples were analayzed for gamma-emitting isotopes.
All of the isotopes, except naturally-occurring K-40, were below detection limits.
Potassium-40 averaged 1.92 pCi/g wet weight at the control location and 1.98 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 two downstream bottom sediment samples, averaging 0.13 pCi/g dry weight in both upstream and downstream samples, and in two shoreline sediment samples, averaging 0.16 pCi/g dry weight, indicating the influence of fallout deposition.
Similar levels of activities and distribution were observed in 1978-1990.
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, 1991.
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-168 M-01S - M-06S M-01C 5
M-1(C),
M-2, M-3, M-4, M-5 5
M-1(C),
M-2, M-3, M-4, M-5 5
M-10(C), M-18, M-24 M-26, M-28a, M-29 C/Q Ambient Gamma C/W GB, GS (QC of each location)
C/W 1-131 G/Md 1-131, GS River Water Drinking Water Well Water Edible Cultivated Crops - Cabbage Edible Cultivated Crops -
Corne Edible Crops Cultivated
- Potatoese Fish (One Species, Edible Portion)
Algae or Aquatic Insects 2
M-8(C), M-9 1
M-14 4
M-10(C), M-11, M-12, M-13 2
M-10(C), M-27 1
M-19 1
M-21 2
M-8(C), M-9 2
M-8(C), M-9 G/W GS(MC), H-3(QC)
G/W GB(MC),
GS(MC),
G/Q H-3, GS G/A 1-131 G/A GS G/A GS G/SA GS G/SA GS a M-28 (Witschen Dairy Farm)
August, 1991.
was replaced by M-29 (Holthaus Dairy Farm) in 13 1-131 (MC)
Table 5.1.
Sample collection and analysis program, Monticello Nuclear Generating Plant, 1991 (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 =
c quarterly, SA = semi-annually, A = annually.
Analysis type is coded as follows:
GB = gross beta, GS = gamma spectro scopy, H-3 = tritium, 1-131 = iodine-131. 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 effluent has been discharged.
14
Table 5.2.
Sampling locations, Monticello Nuclear Generating Plant, 1991 Distance and Type of Direction from Code Typea Collection Site Sampleb Site Stack C
Air Station M-1 Air Station M-2 Air Station M-3 Air Station M-4 Air Station M-5 C
Upstream of Plant Downstream of Plant C
Kirchenbauer Farm City of Monticello Plant Well #1 Ernst Residence City of Minneapolis Montissippi Park Witschen Farm River Irrigated Corn Fieldc River Irrigated Potato Fieldc Weinand Farm Peterson Farm Wise Residence Highest D/Q Garden Hoglund Farm Holthaus Farm RW, RW, M,
AP, AP, AP, AP, AP, BS, BS, WW, AI AI AI AI Al BO, BO, VE F
M M
VE M
M 11.1 0.8 0.6 0.9 2.7 0.2 0.2 11.5 3.2 0.2 0.6 36 1.6 3.0 mi mi mi mi mi mi mi mi mi mi mi mi mi mi 4.8 mi 2.5 mi 0.7 mi 306 0 /NW 1400/SE 104 0/ESE 150 0/SSE 136 0/SE 285 0/WNW 620/ENE 323 0/NW 128 0/SE 267 0/W 2020/SSW 128 0/SE 117 0/ESE 260 0/W 1800/S 111 0/ESE 208 0/SSW M-1 M-2 M-3 M-4 M-5 M-8 M-9 M-10 M-11 M-12 M-13 M-14 M-15 M-18 M-19 M-21 M-24 M-26 M-27 M-28 M-29 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 3.7 mi @ 300 0/WNW 4.1 mi @ 1730/S 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 TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD 0.7 0.8 1.0 0.7 0.6 0.6 0.5 0.5 0.4 0.3 0.4 0.7 1.1 0.8 mi mi mi mi mi mi mi mi mi mi mi mi mi mi 353 0/N 230/NNE 430/NE 920/E 112 0/ESE 133 0/SE 1580/SSE 1830/S 203 0 /SSW 225 0/SW 250 0/WSW 2730/W 317 0/NW 3380/NNW 15
Table 5.2.
Sampling locations, Monticello Nuclear Generating Plant, 1991 (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 & 196th Street TLD 4.3 mi @ 116 0/ESE M-07B Monte Industrial Drive TLD 4.4 mi @ 135 0/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 @ 206 0/SSW M-11B Clifford Vanlith Farm TLD 4.2 mi @ 225 0/SW M-12B Lake Maria State Park TLD 4.4 mi @ 253 0/WSW M-13B Bridgewater Station TLD 4.1 mi @ 271*/W M-14B Richard K Anderson Residence TLD 4.5 mi @ 228 0/WNW M-15B Gary Williamson Residence TLD 4.5 mi @ 308 0/NW M-16B Sand Plain Research Farm TLD 4.3 mi @ 338 0/NNW Special Interest Locations M-01S Dickson Residence TLD 0.5 mi @ 166 0 /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 @ 136 0/SE M-01C C
Kirchenbauer Farm TLD 11.5 mi @ 323 0/NW a "C" denotes control location. All b Sample codes:
AP AI M
VE DW RW Airborne particulate Airborne iodine Milk Vegetation/vegetables Drinking water River water other locations are indicators.
WW BS SS B
c Collected only if the field is irriga active effluent has been discharged.
Well water Bottom (river) sediments Shoreline sediments 0 = Bottom organisms (periphyton or macroinvertebrates)
F = Fish ted by water in which liquid radio-16
Table 5.3.
Missed collections and analyses for 1991 at Monticello Nuclear Generating Plant. All required samples were collected and analyzed except the following.
Collection Date Sample Location or Period Comments TLD M-12A 4th Qtr. 1991 TLD lost in the field.
17
Table 5.4. Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Monticello Nuclear Generating Plant Docket No.
Wright, Minnesota (County, State) 50-263.
Reporting Period January - December 1991 Indicator Location with Highest Control Sample Type and Locations Annual Mean Locations Number of Type Number of Mean (F)c Mean ([)C Mean (F)c Non-routine (Units)
Analysesa LLDb Rangec Locationd Rangec Rangec Resultse TLD (mR/91 days)
Gamma 55 3.0 15.2 (56/56)
M-12A, County 16.5 (3/4)
(See control 0
(Inner Ring, (11.5-18.0)
Road 75, 0.7 mi (15.4-17.6) below.)
General Area of
@ 273 0/W Site Boundary)
TLD (mR/91 days)
Gamma 64 3.0 15.8 (62/62)
M-05B, City of 20.8 (4/4)
(See control 0
(Outer ring, 4 -
(12.1-22.4)
Big Lake (18.1-22.4) below.)
5 miles distant) 4.4 mi @ 87./E TLD (mR/91 days)
Gamma 24 3.0 15.3 (23/23)
M-06S, Monte 16.7 (4/4)
(See control 0
(Special (13.0-18.0)
Service Center (16.0-18.0) below)
Interest Areas) 2.7 mi @ 136 0/SE TLD (mR/91 days)
Gamma 4
3.0 None M-01C, Kirchenbauer 15.0 (4/4) 15.0 (4/4) 0 (Control)
- Farm, 11.5 mi @
(14.1-15.9)
(14.1-15.9) 323'/NW Airborne GB 260 0.003 0.024 (208/208)
M-5f, Station M-5 Q.024 (52/52) 0.024 (52/52) 0 Particlates (0.004-0.070) 2.7 mi @ 136./SE (0.006-0.069)
(0.008-0.071) pCi/m )
M-4, Station M-4 0.024 (52/52) 0 0.9 mi @ 150*/SSE (0.008-0.070)
GS 20 Be-7 0.020 0.054 (16/16)
M-4, Station M-4 0.058 (4/4) 0.054 (4/4) 0 (0.038-0.079) 0.9 mi @ 150 0/SSE (0.039-0.079)
(0.043-0.063)
Mn-54 0.0012
<LLD
<LLD 0
Co-58 0.0014
<LLD
<LLD 0
Co-60 0.0015
<LLD
<LLD 0
Zn-65 0.0026
<LLD
<LLD 0
Zr-Nb-95 0.0027
<LLD
<LLD 0
Ru-103 0.0012
<LLD
<LLD 0
Ru-106 0.011
<LLD
<LLD 0
Cs-134 0.0010
<LLD
<LLD 0
00
Table 5.4.
Radiological Environmental Monitoring Program Summary (continued)
Name of Facility Location of Facility Monticello Nuclear Generatinq Wright, Minnesota (County, State)
Docket No.
50-263 Reporting Period January - December 1991 Indicator Location with Highest Control Sample Type and Locations Annual Mean Locations Number of Type Number of Mean (F)c Mean (F)L Mean (F)c Non-routine (Units)
Analysesa LLDb Rangec Locationd Rangec Rangec Resultse Airborne GS Particulates (pCi/m 3 )
Cs-137 0.0010
<LLD
<LLD 0
(continued)
Ba-La-140 0.0039
<LLD
<LLD 0
Ce-141 0.0022
<LLD
<LLD 0
Ce-144 0.0068
<LLD
<LLD 0
Airborne 1-131 260 0.07
<LLD
<LLD 0
Iodine (pCi/m 3)
Milk 1-131 90 1.0
<LLD
<LLD 0
(pCi/L) 90 K-40 200 1280 (72/72)
M-26, Peterson Farm 1310 (18/18) 1270 (18/18) 0 (1000-1560) 2.3 mi @ 111*/ESE (1140-1560)
(1090-1380)
Cs-134 15
<LLD
<LLD 0
Cs-137 15
<LLD
<LLD 0
Ba-La-140 15
<LLD
<LLD 0
River Water H-3 8
330
<LLD
<LLD 0
(pCi/L) 24 Mn-54 15
<LLD
<LLD 0
Fe-59 30
<LLD
<LLD 0
Co-58 15
<LLD
<LLD 0
Co-60 15
<LLD
<LLD 0
Table 5.4.
Radiological Environmental Monitoring Program Summary (continued)
Name of Facility Location of Facility Monticello Nuclear Generating Wright, Minnesota (County, State)
Plant Docket No.
50-2 Reporting Period January -
263 December 1991 Indicator Location with Highest Control Sample Type and Locations Annual Mean Locations Number of Type Number of Mean (F)c Mean (F)G Mean (F)c Non-routine (Units)
Analysesa LLDb Rangec Locationd Rangec Rangec Resultse River Water Zn-65 30
<LLD
<LLD 0
(pCi/L)
(continued)
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 53
<LLD
<LLD 0
Drinking Water GB 12 1.0 2.9 (12/12)
M-14, Minneapolis 2.2 (12/12)
None 0
(pCi/L)
(1.4-3.4) 36 mi @ 128 0/SE (1.4-3.4) 1-131 12 1.0
<LLD None 0
H-3 4
330
<LLD None 0
GS 12 Mn-54 15
<LLD None 0
Fe-59 30
<LLD None 0
Co-58 15
<LLD None 0
Co-60 15
<LLD None 0
Zn-65 30
<LLD None 0
Zr-Nb-95 15
<LLD None 0
Cs-134 10
<LLD None 0
Cs-137 10
<LLD None 0
Ba-La-140 15
<LLD None 0
Ce-144 72
<LLD None 0
N)
Table 5.4.
Radiological Environmental Monitoring Program Summary (continued)
Name of Facility Location of Facility Monticello Nuclear Generating Wright, Minnesota Plant Docket No.
50 Reporting Period January -
263 December 1991 (County, State)
Indicator Location with Highest Control Sample Type and Locations Annual Mean Locations Number of Type Number of Mean (F)c Mean (F)c Mean (F)c Non-routine (Units)
Analysesa LLDb Rangec Locationd Rangec Rangec Resultse Well Water H-3 16 330
<LLD
<LLD 0
(pCi/L)
GS 16 Mn-54 15
<LLD
<LLD 0
Fe-59 30
<LLD
<LLD 0
Co-58 15
<LLD
<LLD 0
Co-60 15
<LLD
<LLD 0
Zn-65 30
<LLD
<LLD 0
Zr-Nb-95 15
<LLD
<LLD 0
Cs-134 10
<LLD
<LLD 0
Cs-137 10
<LLD
<LLD 0
Ba-La-140 15
<LLD
<LLD 0
Ce-144 76
<LLD
<LLD 0
Crops-Cabbage 1-131 2
0.022
<LLD
<LLD 0
(pCi/g wet)
Fish GS 4
(pCi/g wet)
K-40 0.1 2.58 (2/2)
M-8, Upstream of 2.73 (2/2) 2.73 (2/2) 0 (2.43-2.72)
Plant, 0.2 mi @
(2.42-3.04)
(2.42-3.04) 258*/WNW Mn-54 0.023
<LLD
<LLD 0
Fe-59 0.088
<LLD
<LLD 0
Co-58 0.028
<LLD
<LLD 0
Co-60 0.025
<LLD
<LLD 0
I-.
Table 5.4.
Radiological Environmental Monitoring Program Sumary (continued)
Name of Facility Location of Facility Monticello Nuclear Generating Plant Wright, Minnesota (County, State)
Docket No.
50-263 Reporting Period January - December 1991 Indicator Location with Highest Control Sample Type and Locations Annual Mean Locations Number of Type Number of Mean (F)c Mean (F)C Mean (F)c Non-routine (Units)
Analysesa LLDb Rangec Locationd Rangec Rangec Resultse Fish GS (pCi/g wet)
(continued)
Zn-65 0.056
<LLD
<LLD 0
Zr-95 0.049
<LLD
<LLD 0
Nb-95 0.049
<LLD
<LLD 0
Cs-134 0.017
<LLD
<LLD 0
Cs-137 0.024
<LLD
<LLD 0
Ba-La-140 0.42
<LLD
<LLD 0
Invertebrates GS 4
(pCi/g wet)
Be-7 1.20
<LLD
<LLD 0
K-40 2.98 1.98 (2/2)
M-9, Downstream of 1.98 (2/2) 1.92 (2/2) 0 (1.48-2.49)
Plant, 0.2 mi @
(1.48-2.49)
(0.70-3.15) 62*/ENE Mn-54 0.13
<LLD
<LLD 0
Co-58 0.14
<LLD
<LLD 0
Co-60 0.12
<LLD
<LLD 0
Zn-65 0.29
<LLD
<LLD 0
Zr-Nb-95 0.29
<LLD
<LLD 0
Ru-103 0.17
<LLD
<LLD 0
Ru-106 1.13
<LLD
<LLD 0
Cs-134 0.10
<LLD
<LLD 0
Cs-137 0.12
<LLD
<LLD 0
Ba-La-140 0.83
<LLD
<LLD 0
Ce-141 0.29
<LLD
<LLD 0
Ce-144 0.71
<LLD
<LLD 0
S0.1 L
0
Table 5.4.
Radiological Environmental Monitoring Program Summary (continued)
Name of Facility Location of Facility Monticello Nuclear Generating Wright, Minnesota (County, State)
Plant Docket No.
50-263 Reporting Period January - December 1991 Indicator Location with Highest Control Sample Type and Locations Annual Mean Locations Number of Type Number of Mean (F)c Mean (F)u Mean (F)c Non-routine (Units)
Analysesa LLDb Rangec Locationd Rangec Rangec Resultse Bottom and GS 6
Shoreline Sediments Be-7 0.44
<LLD M-8, Upstream of 0.58 (1/2) 0.58 (1/2) 0 (pCi/g dry)
Plant, 0.2 mi 0 2850/WNW K-40 0.5 10.36 (4/4)
M-8, Upstream of 11.79 (2/2) 11.79 (2/2) 0 (9.15-12.41)
Plant, 0.2 mi @
(11.63-11.95)
(11.63-11.95) 285*/WNW Mn-54 0.035
<LLD
<LLD 0
Co-58 0.041
<LLD
<LLD 0
Co-60 0.048
<LLD
<LLD 0
Zn-65 0.097
<LLD
<LLD 0
Zr-95 0.087
<LLD
<LLD 0
Nb-95 0.071
<LLD
<LLD 0
Ru-103 0.055
<LLD
<LLD 0
Ru-106 0.29
<LLD
<LLD 0
Cs-134 0.029
<LLD
<LLD 0
Cs-137 0.037 0.14 (4/4)
M-15, Montissippi 0.16 (2/2) 0.13 (2/2) 0 (0.072-0.19)
Park 1.6 mi @
(0.079-0.24)
(0.13-0.13) 117*/ESE Ba-La-140 0.24
<LLD
<LLD 0
Ce-141 0.099
<LLD
<LLD 0
Ce-144 0.20
<LLD
<LLD 0
GB = Gross beta; GS = gamma scan.
LLD = Nominal lower limit of detection based on 4.66 sigma error for background sample.
Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).
Locations are specified (1) by name and code (Table 2) and (2) distance, direction, and sector relative to reactor site.
Non-routine results are those which exceed ten times the control station value.
If no control station value is available, the result is considered non-routine if it exceeds ten times the preoperational value for the location.
Three locations had identical annual means of 0.024 pCi/m3,(M-1, M-4, and M-5).
Only M-5 is detailed in this summary.
a b
c d
e f
6.0 REFERENCES
CITED Arnold, J. R. and H. A. Al-Salih.
1955. Beryllium-7 Produced by Cosmic Rays.
Science 121:
451-453.
Eisenbud, M.
1963.
Environmental Radioactivity, McGraw-Hill, New York, New York, pp. 213, 275, and 276.
Hazleton Environmental Sciences Corporation.
1979a.
Radiation Environ mental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1978.
1979b. Radiation Environmental Monitoring for Monticello 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
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 Health 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 - 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 Regu latory Commission, January 1, 1977 -
December 31, 1977 (prepared by NALCO Environmental Sciences), Minneapolis, Minnesota.
.. 1979.
Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S.
Nuclear Regu latory Commission, January 1, 1978 -
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 Regu latory Commission, January 1, 1979 -
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 Regu latory Commission, January 1, 1980 -
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 Regu latory Commission, January 1, 1981 -
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 Regu latory Commission, January 1, 1982 -
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 Regu latory Commission, January 1, 1983 -
December 31, 1983 (prepared by Teledyne Isotopes Midwest Laboratory), Minneapolis, Minnesota.
1985.
Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S.
Nuclear Regu latory Commission, January 1, 1984 -
December 31, 1984 (prepared by Teledyne Isotopes Midwest Laboratory), Minneapolis, Minnesota.
1986.
Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S.
Nuclear Regu latory Commission, January 1, 1985 -
December 31, 1985 (prepared by Teledyne Isotopes Midwest Laboratory), Minneapolis, Minnesota.
25
1987.
Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S.
Nuclear Regu latory Commission, January 1, 1986 -
December 31, 1986 (prepared by Teledyne Isotopes Midwest Laboratory), Minneapolis, Minnesota.
1988. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S.
Nuclear Regu latory Commission, January 1, 1987 -
December 31, 1987 (prepared by Teledyne Isotopes Midwest Laboratory), Minneapolis, Minnesota.
1989.
Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S.
Nuclear Regu latory Commission, January 1, 1988 -
December 31, 1988 (prepared by Teledyne Isotopes Midwest Laboratory), Minneapolis, Minnesota.
1990.
Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S.
Nuclear Regu latory Commission, January 1, 1989 -
December 31, 1989 (prepared by Teledyne Isotopes Midwest Laboratory), Minneapolis, Minnesota.
1991.
Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S.
Nuclear Regu latory Commission, January 1, 1990 -
December 31, 1990 (prepared by Teledyne Isotopes Midwest Laboratory), Minneapolis, Minnesota.
Teledyne Isotopes Midwest Laboratory.
1991.
Analytical Procedures Manual, Revised 15-May-1991.
1991.
Quality Assurance Program Manual, Revision 8, 11-Jul y-1991.
1991.
Quality Control Procedures Manual, Revision 14, 28-June-1991.
1989.
Quality Control
- Program, Revision 11, 5 April 1989.
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 Tbles, 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.
26
1986a.
Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January December 1985.
1986b.
Radiation Environmental Monitoring for Prairie Island 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.
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.
27
U. S. Atomic Energy Commission.
1972.
HASL Procedures Manual, Health and Safety Laboratory, New York, New York.
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 Contami nation of Radioactive Materials, International Atomic Energy Agency,
- p. 125.
28
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 twice a year; the complete Appendix is included in January and July monthly reports only. Please refer to January and July reports for information.
January, 1992
Appendix A 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 November 1991. This program has been conducted by the U.S. Environmental Protection Agency Intercomparison and Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, 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
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 1991.a Concentration in pCi/Lb EPA Resultd Lab Sample Date TIML Result Control Code Type Collected Analysis
+/-2oc 1s, N=1 Limits STW-521 STW-523 STF-524 STW-525 STW-526 STW-527 STM-528 STW-529 STW-530 STAF-531 STW-532 Water Water Food Water Water Water Milk Water Water Jan 1988 Jan 1988 Jan 1988 Feb 1988 Feb 1988 Feb 1988 Feb 1988 Mar 1988 Mar 1988 Air Filter Mar 1988 Wa ter Apr 1988 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 H-3 Uranium 1-131 Ra-226 Ra-228 Gr. alpha Gr. beta Gr. alpha Gr. beta Sr-90 Cs-137 I-131 27.3+/-5.0 15.3+/-1.2 2.3+/-1.2 7.7+/-1.2 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 3.0+/-0.0 4.7+/-1.2 7.1+/-0.6 NAe 4.3+/-1.2 13.3+/-1.3 21.0+/-2.0 48.0+/-0.0 16.7+/-1.2 18.7+/-1.3 Q n7 n 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 3327+/-362 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 7.510.8 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 2700-3954 0.0-13.4 3.3-4.7 5.6-9.6 5.7-9.7 0.0-14.7 4.3-21.7 11.3-28.7 41.3-58.7 14.4-19.6 7.3-24.7 6.2-8.8 A-3 Water 1-1141 Anr 1988
Table A-1. (continued)
Date Collected Analysis Concentration in pCi/Lb EPA Resultd TIML Result Control
+/-2oc 1s, N=1 Limits Apr 1988 Gr. alpha Ra-226 Ra-228 Uranium Gr. beta Sr-89 Sr-90 Co-60 Cs-134 Cs-137 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
NDf ND ND 6.0+/-6.0 ND 3.3+/-1.2 5.3+/-1.2 63.3+/-1.3 7.7+/-1.2 8.3+/-1.2 6483+/-155 14.7+/-1.3 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+/-3.1 527+/-3.1 1587+/-23 8.7+/-4.2 5.3+/-1.2 NDf ND 115.0+/-5.3 52.7+/-6.4 1190+/-66 Water (Blind)
Sample A 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 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 5128-7276 11.3-28.7 17.4-22.6 250.0-354.0 6.3-23.7 83.7-118.3 160.4-229.6 11.3-28.7 16.3-33.7 4600-6530 31.3-48.7 54.8-65.2 78.4-109.6 42.3-59.7 1461-1739 6.3-23.7 0.0-12.7 24.3-41.7 30.5-37.5 88.0-126.0 40.3-57.7 1 133-1347 A-4 Lab Code Sample Type STW-533 534 Water 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 6202+/-620 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 5565+/-557 Sample B STU-535 STW-536
)
STW-538 STW-539 STM-541 STW-542 STF-543 Urine Water Water Water Milk Water Food 1190+/-66 1240+/-62 1133-1347
Table A-1. (continued)
Concentration in nCi/Lb Lab Code STW-544 STW-545 STW-546 STAF-547 STW-548 STW-549 STW-550 STW-551 STW-552 553 Sample Type Water Water Water Date Collected Aug 1988 Aug 1988 Aug 1988 Air Filter Aug 1988 Water Water Water Water Water (Blind)
Sample A Sep 1988 Sep 1988 Oct 1988 Oct 1988 Oct 1988 Analysis 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 H-3 Gr. alpha Ra-226 Ra-228 Uranium Gr. beta Sr-89 Sr-90 Cs-134 Cs-137 Sample B EPA Resultd TIML Result Control
+/-2oc 1s, N=1 Limits 80.0+/-0.0 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+/-10.2 153.0+/-9.2 28.7+/-5.0 16.3+/-1.2 2333+/-127 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 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 2316+/-350 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 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 1710-2927 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 oncentTation in nCi/1 b
Table A-1. (continued)
Lab Code STM-554 STU-555 STW-556 STW-557 STW-559 STW-560
. TW-561 STW-562 STW-563 STW-564 STW-565 STW-566 STAF-567 Sample Type Milk Urine Water Water Water Water Water Water Water Water Water Water Air Filter Date Collected 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 Concentration in pCi/Lb EPA Resultd TIML Result Control Analysis
+/-2oc Is, N=1 Limits 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+/-0.3 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+/-5.0 106.0+/-11.0 2754+/-356 4.9+/-0.7 1.7+/-0.3 5.0+/-6.0 21.0+/-5.0 62.0+/-5.0 20.0+/-1.5 20.0+/-5.0 A-6 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 3.54.9 0.0-16.7 0.0-12.7 193.4-276.6 1.3-18.7 139.2-186.7 146.8-209.2 1.3-18.7 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
Table A-1. (continued)
Analysis Concentration in pi/Lb EPA Resultd TIML Result Control
+/-2oc 1s, N=1 Limits STW-568 569 Water Water (Blind)
Sample A Sample B STM-570
) TW-571 g STW-572 STW-573 STW-574 STW-575 STW-576 STW-577 STAF-579 Milk Water Water Water Water Water Water Water Apr 1989 May 1989 May 1989 Jun 1989 Jun 1989 Jul 1989 Jul 1989 Aug 1989 Air Filter Aug 1989 Apr 1989 lab Code Sample Type Date Collected Gr. alpha Ra-226 Ra-228 U
Gr. beta Sr-89 Sr-90 Cs-134 Cs-137 Sr-89 Sr-90 Cs-137 K40 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 52.3+/-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+/-1.2 31.3+/-2.3 167+/-10 123+/-9.2 40.3+/-1.2 22.3+/-1.2 4513+/-136 16.8+/-3.1 13.8+/-3.7 40.3+/-1.2 84.7+/-5.8 6.0+/-0.0 10.3+/-2.3 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 4503+/-450 17.7+/-2.7 18.3+/-2.7 41.0+/-6.0 83.0+/-8.0 6.0+/-5.0 10.0+/-5.0 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 3724-5282 13.0-22.4 13.6-23.0 30.6+/-51.4 69.1-%.9 0.0-14.7 1.3-18.7 A-7
Table A-1. (continued)
Date Collected Sep 1989 Sep 1989 Oct 1989 Oct 1989 Oct 1989 Concentration in pCi/Lb EPA Resultd TIML Result Control Analysis
+/-2oc 1s, N=1 Limits Sr-89 Sr-90 Gr. alpha Gr. beta Ba-133 Co-60 Zn-65 Ru-106 Cs-134 Cs-137 H-3 Gr. alpha Ra-226 Ra-228 U
Gr. beta Sr-89 Sr-90 Cs-134 Cs-137 Nov 1989 Ra-226 Ra-228 Nov 1989 Jan 1990 Jan 1990 U
Sr-89 Sr-90 Gr. alpha Cr. beta 14.7+/-1.2 9.7+/-1.2 5.0+/-0.0 8.7+/-2.3 60.3+/-10.0 29.0+/-4.0 132.3+/-6.0 155.3+/-6.1 30.7+/-6.1 66.3+/-4.6 3407+/-150 41.7+/-9.4 7.9+/-0.4 4.4+/-0.8 12.0+/-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+/-0.08 22.7+/-5.0 17.3+/-1.2 10.3+/-3.0 12.3+/-1.2 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 3496+/-364 49.0+/-12.0 8.4+/-1.3 4.1+/-0.6 12.0+/-6.0 32.0+/-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 12.0+/-5.0 A-8 Lab Code Sample Type STW-580 STW-581 STW-583 STW-584 STW-585 586 STW-587 STW-588 STW-589 STW-591 Water Water Water Water Water (Blind)
Sample A Sample B Water Water Water Water 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 2866+/-4126 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 Date Collected Jan 1990 Feb 1990 Mar 1990 Mar 1990 STW-592 STW-593 STW-594 STW-595 STAF-596 Analysis 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 EPA Resultd TIML Result Control
+/-2oc 1s, N=1 Limits 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 4976+/-498 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 6.3-23.7 114.8-163.2 114.8-163.2 9.3-26.7 9.3-26.7 61.9-86.1 4113-5839 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 STW-597 598 STM-599 STW-600 B STW-601 Water (Blind)
Sample A Sample B Milk Water Water Apr 1990 Gr. alpha Ra-226 Ra-228 U
Gr. beta Sr-89 Sr-90 Cs-134 Cs-137 Apr 1990 May 1990 May 1990 w
Sr-89 Sr-90 Gr. alpha G,
bIk 81.0+/-3.5 4.9+/-0.4 10.6+/-03 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 6.0+/-2.0 6.7+/-1.2 11.0+/-2.0 2t 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 7.0+/-5.0 7.0+/-5.0 22.0+/-6.0 50.1-129.9 3.6-6.4 7.6-12.8 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 14.3-31.7 81.7-116.3 15.3-32.7 1414.7-1685.3 0.0-15.7 0.0-15.7 11.6-32.4 A-9 Lab Code Air Filter Mar 1990 Sample Type Water Water Water Water
- r.
eta 1.3X1.2 15..
- 6.
7i
Table A-1. (continued)
Concentration in pCi/Lb Date Collected Analysis EPA Resultd TIML Result Control
+/-2oc 1s, N=1 Limits STW-602 STW-603 STW-604 STW-605 STW-606 STW-607 VTAF-608 STW-609 STW-610 STM-611 STW-612 kSTW-613 Water Water Water Water Water Water Jun 1990 Jun 1990 Jul 1990 Jul 1990 Aug 1990 Aug 1990 Air Filter Aug 1990 Water Water Milk Water Water Sep 1990 Sep 1990 Sep 1990 Oct 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 H-3 25.3+/-2.3 155.0+/-10.6 202.7+/-17.2 23.7+/-1.2 27.7+/-3.1 100.7+/-8.1 2927+/-306 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 11.713.1 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 7167+/-330 24.0+/-5.0 148.0+/-15.0 210.0+/-21.0 24.0+/-5.0 25.0+/-5.0 99.0+/-10.0 2933+/-358 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 12.0+/-5.0 12.0+/-5.0 110.0+/-11.0 7203+/-720 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.
5954-8452 A-10 Lab Code Sample Type
Table A-1. (continued)
Analysis Concentration in pCi/Lb EPA Resultd TIML Result Control
+/-2oc 1s, N=1 Limits STW-614 615 Water Sample A Sample B STW-616 STW-617g FTW-618 STW-619 STW-620 STW-621 STW-622 STW-623 STW-624 STW-625 Water Water Water Water Water Water Water Water Water Water Oct 1990 Gr. alpha Ra-226 Ra-228 U
Gr. beta Sr-89 Sr-90 Cs-134 Cs-137 Nov 1990 Ra-226 Ra-228 Nov 1990 Jan 1991 Jan 1991 Jan 1991 Feb 1991 Feb 1991 Feb 1991 Mar 1991 Mar 1991 U
Sr-89 Sr-90 Pu-239 Gr. alpha Gr. beta Co-60 Zn-65 Ru-106 Cs-134 Cs-137 Ba-133 1-131 H-3 Ra-226 Ra-228 U
68.7+/-7.2 12.9+/-0.3 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+/-1.2 41.3+/-8.4 166.7+/-19.7 209.7+/-18.6 9.0+/-2.0 9.7+/-1.2 85.7+/-9.2 81.3+/-6.1 4310.0+/-144.2 31.4+/-3.2 NDh 6.7+/-0.4 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 75.0+/-8.0 4418.0+/-442.0 31.8+/-4.8 21.1+/-5.3 7.6+/-3.0 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 61.1-88.9 3651.2-5184.8 23.5-40.1 11.9-30.3 2.4-12.8 A-11 Lab Code Sample Type Date Collected
Table A-1. (continued)
Concentration in pCi/Lb Date Collected Analysis EPA Resultd TIML Result Control
+/-2oc 1s, N=1 Limits STAF-626 STW-627 628 Air Filter Mar 1991 Water Sample A Sample B
'STM-629 STW-630 STW-631 STW-632 STW-633 STW-634 Milk Water Water Water Water Water Apr 1991 May 1991 May 1991 Jun 1991 Jun 1991 Jul 1991 Gr. alpha Gr. beta Sr-90 Cs-137 38.7+/-12 130.0+/-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 Apr 1991 Gr. alpha Ra-226 Ra-228 U
Gr. beta Sr-89 Sr-90 Cs-134 Cs-137 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 H-3 Ra-226 Ra-228 51.06.0 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+/-12 16.3+/-1.2 74.0+/-6.9 13470.0+/-385.8 14.9+/-0.4 17.6+/-1.8 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 29.7-783 5.9-10.1 8.6-21.8 24.6-35.0 85.5-144.5 19.3-36.7 17.3-34.7 15.3-32.7 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 12480.0+/-1248.0 10314.8-14645.2 15.9+/-2.4 16.7+/-4.2 11.7-20.1 9.4-24.0 A-12
'lab Code Sample Type
Table A-1. (continued)
Concentration in pCi/Lb EPA Resultd TIML Result Control Analysis
+/-2 oc 1s, N=1 Water Water Water Jul 1991 Aug 1991 Aug 1991 Air Filter Aug 1991 STW-635 STW-636 STW-637 STAF-638 STW-639 STW-640 STM-641 Milk Water Water Water 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 12.8+/-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 47.0+/-10.4 24.0+/-2.0 12.0+/-4.0 20.3+/-12 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+/-8.3 196.3+/-15.1 9.7+/-1.2 11.0+/-2.0 94.7+/-3.1 2640.0+/-156.2 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 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 49.0+/-5.0 25.0+/-5.0 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 2454.0+/-352.0 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 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 1843.3-3064.7 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 Lab Code Sample Type Date Collected Limits Water Water STW-642 STW-643 STW-644 645
Table A-1. (continued)
Concentration in pCi/Lb
)
EPA Resultd Lab Sample Date TIML Result Control Code Type Collected Analysis E20 c 1s, N=1 Limits STW-646 Water Nov 1991 Ra-226 5.6+/-1.2 6.5+/-1.0 4.8-8.2 Ra-228 9.6+/-0.5 8.1+/-2.0 4.6-11.6 STW-647 Water Nov 1991 U
24.7+/-23 24.9+/-3.0 19.7-30.1 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/1, except for elemental potassium (K) data in milk, which are in mg/I; 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.
89 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.
A-14
Table A-2. Crosscheck program results, thermoluminescent dosimeters (TLDs).
TLD Type Measurement +/-2oa Teledyne Result Valuec mR Average +/-2od Known (All Participants) 2nd International Intercomparisonb CaF2 :Mn Bulb Field Lab 17.0+/-1.9 20.8+/-4.1 3rd International Intercomparisone CaF2 :Mn Bulb Field Lab 30.7+/-3.2 89.6+/-6.4 34.9+/-4.8 91.7+/-14.6 4th International Intercomparisonf Field Lab (Low)
Lab (High) 5th International Intercomparison8 Field Lab at beginning Lab at the end Field Field at beginning Lab at the end 7th International Comparisonh Field Lab (Co-60)
Lab (Cs-137)
A-15 lab Code 115-2 115-3 17.1 21.3 16.4+/-7.7 18.8+/-7.6 115-4 CaF2 :Mn Bulb 31.5+/-3.0 86.2+/-24.0 14.1+/-1.1 9.3+/-1.3 40.4+/-1.4 115-SA 14.1+/-1.4 12.2+/-2.4 45.8+/-9.2 CaF2 :Mn Bulb 16.0+/-9.0 120+/-7.4 43.9+/-13.2 115-5B LiF-100 Chips 31.4+/-1.8 77.4+/-5.8 96.6+/-5.8 30.3+/-4.8 81.1+/-7.4 85.4+/-11.7 30.0+/-6.0 75.2+/-7.6 88.4+/-8.8 30.0+/-6.0 75.2+/-7.6 88.4+/-8.8 30.2+/-14.6 75.8+/-40.4 90.7+/-31.2 30.2+/-14.6 75.8+/-40.4 90.7+/-31.2 115-7A LiF-100 Chips 75.4+/-2.6 80.0+/-3.5 66.6+/-2.5 75.8+/-6.0 79.9+/-4.0 75.0+/-3.8 75.1+/-29.8 77.9+/-27.6 73.0+/-22.2
Table A-2. Crosscheck program results, thermoluminescent dosimeters (TLDs).
Teledyne Average +/-2od lab Result Known (All Code TLD Type Measurement +/-2oa Valuec Participants)
CaF2 :Mn Bulbs CaSO 4:Dy Cards Field Lab (Co-60)
Lab (Cs-137)
Field Lab (Co-60)
Lab (Cs-137) 71.5+/-2.6 84.8+/-6.4 78.8+/-1.6 76.8+/-2.7 82.5+/-3.7 79.0+/-3.2 75.8+/-6.0 79.9+/-4.0 75.0+/-3.8 75.8+/-6.0 79.9+/-4.0 75.0+/-3.8 75.1+/-29.8 7.9+/-27.6 73.0+/-22.2 75.1+/-29.8 77.9+/-27.6 73.0+/-22.2 8th International Intercomparison 115-8A LiF-100 Chips 115-8B 115-8C CaF2:Mn Bulbs CaSO4 -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 I Field Site 2 Lab (Cs-137)
Field Site 1 Field Site 2 Lab (Cs-137)
Lab Lab A-16 115-7B 115-7C 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 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 10.119.06 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 21.0+/-0.4 20.9+/-1.0 22.4 20.3
Table A-2. (continued)
Teledyne Average +/-2od Lab Result Known (All Code TLD Type Measurement +/-2oa Valuec Participants)
Teledyne Testing) 90-1k Teledyne Lab 20.6+/-1.4 19.6 CaSO 4 :Dy Cards 90-11 Teledyne Lab 100.8+/-4.3 100.0 CaSO4:Dy Cards 91-1m Teledyne Lab 33.4+/-2.0 320 CaSO4-Dy 55.2+/-4.7 58.8 Cards 87.8+/-6.2 85.5 a Lab result given is the mean +/-2 standard deviations of three determinations.
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..
h Seventh International Intercomparison of Environmental Dosimeters conducted in the spring and summer of 1984 at Las Vegas, Nevada, and sponsored by the U.S. 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.
I 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.
Cards were irradiated by Dosimetry Associates, Inc., Northville, MI on October 30, 1990.
Irradiated cards were provided by Teledyne Isotopes, INC., Westwood, NJ. Irradiated on October 8,1991.
A-17
Table A-3. In-house spiked samples.
Concentration in pCi/L Lab Sample Date TIML Expected Code Type Collected Analysis Result Known Precision n=1 Activity 1s, n=1a QC-MI-16 QC-MI-17 QC-W-35 QC-W-36 QC-W-37 QC-MI-18 QC-W-38 QC-W-39 QC-W-40 QC-W-41 QC-MI-19 QC-W-42 QC-W-43 QC-W-44 Milk Milk Water Water Water Milk Water Water Water Water Milk Water Water Water Feb 1988 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-89 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 Co-60 Cs-134 Cs-137 1-131 31.8+/-4.7 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 33.22.3 313+/-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 31.7+/-6.0 27.8+/-3.5 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 17.3+/-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 23.3+/-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-18
Table A-3. In-house spiked samples(continued)
Concentration in pCifL lab Code Sample Type QC-W-45 QC-MI-20 QC-W-46 QC-MI-21 QC-W-47 Nb-MI-22 QC-W-48 QC-W-49 QC-W-50 QC-W-51 QC-MI-23 QC-MI-24 kc-W-52 Water Milk Water Milk Water Milk Water Water Water Water Milk Milk Water Date Collected Oct 1988 Oct 1988 Dec 1988 Jan 1989 Mar 1989 Apr 1989 Apr 1989 Apr 1989 Apr 1989 Jun 1989 Jul 1989 Aug 1989 Sep 1989 Analysis 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 Sr-89 Sr-90 1-131 TIML Result n=1 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 24.0+/-0.6 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+/-6.5 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 Known Activity 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 9.7+/-1.9 A-19 Expected Precision is, n=1a 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 8.3 10.4
Table A-3. In-house spiked samples (continued)
Concentration in pCi/L Lab Sample Date TIML Expected Code Type Collected Analysis Result Known Precision n=1 Activity 1s, n=1a QC-W-53 QC-W-54 QC-MI-25 QC-W-55 QC-W-56 QC-W-57 QC-W-58 QC-W-59 QC-W-60 QC-MI-26 QC-MI-27 QC-MI-28 QC-MI-61 QC-MI-29 QC-W-62 Water Water Milk Water Water Water Water Water Water Milk Milk Milk Water Milk Water Sep 1989 1-131 Sep 1989 Sr-89 Sr-90 Oct 1989 1-131 Cs-134 Cs-137 Oct 1989 1-131 Oct 1989 Co-60 Cs-134 Cs-137 Oct 1989 H-3 Nov 1989 Sr-89 Sr-90 Nov 1989 Sr-89 Sr-90 Dec 1989 Gr. alpha Gr. beta Jan 1990 Cs-134 Cs-137 Feb 1990 Sr-90 Mar 1990 1-131 Apr 1990 Sr-89 Sr-90 Apr 1990 1-131 Cs-134 Cs-137 Apr 1990 Co-60 Cs-134 Cs-137 19.0+/-0.2 25.8+/-4.6 26.5+/-5.3 70.0+/-3.3 22.1+/-2.6 29.4+/-1.5 33.3+/-1.3 15.2+/-0.9 22.1+/-4.4 27.2+/-1.2 3334+/-22 10.9+/-l.4d 10.4+/-l.0d 101.0+/-6.0d 98.0+/-3.0d 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 20.0W0.2 287+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 35.3+/-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+/-10.5d 95.0+/-10.0 d 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 22.7+/-5.0 A-20 10.4 8.7 5.2 10.4 8.7 8.7 10.4 8.7 8.7 8.7 724 8.7 5.2 17.5 17.0 8.7 8.7 8.7 8.7 5.2 63 8.7 5.2 10.4 8.7 8.7 8.7 8.7 8.7 22.7+/-5.0 8.7
Table A-3. In-house spiked samples (continued)
Concentration in pi/L ab
-ode Sample Type Date Collected Analysis TIML Result n=1 Known Activity QC-W-63 QC-W-64 QC-W-65 QC-W-66 QC-MI-30 QC-W-68 QC-MI-31 I -W-69 QC-MI-32 QC-W-70 QC-W-71 QC-W-73 QC-W-74 QC-MI-33 QC-MI-34 C-W-75 Water Water Water Water Milk Water Milk Water Milk Water Water Water Water Milk Milk 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 Jan 1991 Feb 1991 Mar 1991 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 Sr-89 Sr-90 Cs-134 Cs-137 1-131 Sr-89 Sr-90 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+/-0.3 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 20.7+/-3.3 19.0+/-1.4 22.2+/-1.7 26.1+/-1.6 40.7+/-1.8 18.8+/-1.5 16.0+/-0.8 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 25.3+/-5.0 10.6+/-6.0 11.3+/-7.0 61.4+/-12.3 19.2+/-10.0 17.4+/-10.0 32.4+/-6.5 27.3+/-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 21.6+/-5.0 23.0+/-3.0 19.6+/-5.0 22.3+/-5.0 40.1+/-6.0 23.3+/-5.0 17.2+/-3.0 A-21 Expected Precision 1s, n=la 6.6 724 1.0 6.0 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 8.7 113 9.7 5.0 3.0 5.0 5.0 6.0 5.0 3.0
Table A-3. In-house spiked samples (continued)
Lab Code Sample Type QC-W-76 QC-W-77 QC-W-78 QC-MI-35 QC-W-79 QC-MI-36 QC-W-80 QC-W-81 QC-W-82 QC-W-83 QC-MI-37 QC-W-84 Water Water Water Milk Water Milk Water Water Water Water Milk Water Date Collected Apr 1991 Apr 1991 Apr 1991 Apr 1991 Jun 1991 Jul 1991 Oct 1991 Oct 1991 Oct 1991 Oct 1991 Oct 1991 Dec 1991 Analysis 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 H-3 1-131 Cs-134 Cs-137 Gr. alpha Gr. beta Concentration in pCi/L a n=3 unless noted otherwise.
b n=2 unless noted otherwise.
c n=1 unless noted otherwise.
V Concentration in pCi/ml.
A-22 Known Activity Expected Precision 1s, n=la TIML Result n=1 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+/-0.7 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 18.3+/-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 5.9 5.0 5.0 5.0 408 6.0 5.0 5.0 5.0 5.0 10.0 3.0 5.0 5.0 5.0 5.0 4.2 5.0 5.0 5.0 438 5.0 5.0 5.0 5.0 5.0 7.8+/-5.0 11.0+/-5.0
Table A-4. In-house "blank" samples.
Concentration (pCifL)
Date Collected Acceptance Criteria (4.66 u)
Milk "Dead" Water Milk D.I. Water Milk Water Water Milk Water Water Water Lab Code Sample Type Analysis Results (4.66 a)
SPS-5386 SPW-5448 SPS-5615 SPS-5650 Jan 1988 Jan 1988 Mar 1988 SPS-6090 SPW-6209 SPW-6292 SPS-6477 SPW-6478 SPW-6479 SPW-6480
<1
<300
<10
<10
<1
<5
<1 1-131
<0.1
<177
<2.4
<2.5
<0.3
<0.4 2.4+/-0.5
<0.3
<0.04
<0.05
<0.03
<0.03
<0.03
<0.06
<0.01
<0.08
<0.02
<0.5 1.8+/-0.5
<0.4
<0.4
<1
<1
<1
<1
<1
<1
<1
<1
<1
<1 Mar 1988 Jul 1988 Jul 1988 Sep 1988 Oct 1988 Oct 1988 Oct 1988 Oct 1988 H-3 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
<1
<1
<1
<10 1-131 Co-60 Cs-134 Cs-137 H-3
<0.8
<0.7
<0.7
<0.2
<6.1
<5.9
<0.2
<5.7
<3.7
<4.3
<170
<1
<1
<1
<1
<10
<10
<1
<10
<10
<10
<300 A-23
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)
Acceptance Criteria (4.66 )
<0.7
<1.9
<1
<4
<0.6 1.9M0.59
<0.2
<4.3
<4.4
<5
<1
<1
<10
<10
<0.4
<0.6
<0.3
<5.9
<6.2
<150
<0.2
<0.6
<5
<1
<1
<10
<10
<300
<1
<1
<0.6 2.1+/-0.5a
<0.3
<6.4
<7.2
<5
<1
<1
<10
<10
<0.2
<1.0
<1.4 4.8+/-1.oa
<0.2
<6.9
<8.2
<2.0
<0.7
<0.1
<140
<1
<4
<5
<1
<1
<10
<10
<5
<1
<1
<300 A-24
Table A-4. In-house "blank" samples (continued)
Lab Code Sample Type SPS-7605 SPW-7971 SPW-8039 SPS-8040 SPS-8208 S-8312 SPW-8312A SPS-8314 SPS-8510 SPW-8511A SPS-8600 SPM-8877 SPW-8925 Milk Water Water Milk Milk Milk Water Milk Milk Water Milk Milk Water Date Collected 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 Concentration (pCifL)
Analysis Results (4.66 c)
Acceptance Criteria (4.66 a) 1-131 Cs-134 Cs-137 Gr. alpha Gr. 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 1-131 H-3 A-25
<0.2
<8.6
<10
<0.4
<0.8
<0.2
<0.8
<1.0
<0.8 1.6+/-O.5a
<3.6
<4.7
<0.3 1.2+/-0.3a
<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
In-house "blank" samples (continued)
Loncentration (DCi IL)
Lab Code SPW-8926 SPW-8927 SPW-8928 SPW-8929 SPW-69 OSPW-106 SPM-107 SPW-370 SPW-372 SPS-406 SPS-421 SPW-451 Sample Type Water Water Water Water Water Water Milk Water Water Milk Milk Water Date Collected Aug 1990 Aug 1990 Aug 1990 Aug 1990 Sep 1990 Oct 1990 Oct 1990 Oct 1990 Dec 1990 Jan 1991 Feb 1991 Feb 1991 Analysis 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.
Results (4.66 a)
<0.3
<0.7
<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 1.8+/-0.4a
<3.7
<5.2
<0.3
<0.1
<0.9 Acceptance Criteria (4.66 c)
<1
<4
<1
<1
<1
<5
<5
<5
<5
<5
<5
<1
<5
<1
<300
<1
<1
<5
<5
<5
<5
<5
<5
<5
<1
<4
<5
<1
<5
<5
<1
<1
<1 A-26 oncentration (r)Ci/L)
Table A-4.
Table A-4. Jn-house "blank" samples (continued)
Concentration (pCifL)
Lab Code Sample Type SPW-514 SPW-586 SPS-587 SPW-837 SPM-953 SPM-1236 SPW-1254 SPW-1256 SPW-1259 SPW-1444 Water Water Milk Water Milk Milk Water Water Water Water Date Collected Mar 1991 Apr 1991 Apr 1991 Jun 1991 Jul 1991 Oct 1991 Oct 1991 Oct 1991 Oct 1991 Dec 1991 Analysis 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 Co-60 Cs-134 Cs-137 H-3 Gr. alpha Gr. beta Results (4.66 a)
<1.1
<0.9
<0.2
<2.5
<2.4
<2.2
<0.2
<1.7
<1.9
<0.6
<1.1
<0.7 0.4+/-0.3a
<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 Acceptance Criteria (4.66 c)
<5
<1
<1
<5
<5
<5
<1
<5
<5
<1
<4
<5
<1
<1
<5
<1
<5
<5
<5
<1
<1
<5
<5
<5
<300
<1
<4 a Low level of Sr-90 concentration in milk (1 - 5 pCi/L) is not unusual.
A-27
Revision 0, 12-29-86 ATTACHMENT 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 Strontium-89b Strontium-90b Potassium Gross alpha Gross beta Tritium Radium-226, -228 Plutonium Iodine-131, Iodine-129b Uranium-238, Nickel-64b, Technetium-99b Iron-55b 5 to 100 pCi/liter or kg
>100 pCi/liter or kg 5 to 50 pCi/liter or kg
>50 pCi/liter or kg 2 to 30 pCi/liter or kg
>30 pCi/liter or kg
>0.1 g/liter or kg
<20 pCi/liter
>20 pCi/liter
<100 pCi/liter
>100 pCi/liter
<4,000 pCi/liter
>4,000 pCi/liter
<0.1 pCi/liter 0.1 pCi/liter, gram, or sample
<55 pCi/liter
>55 pCi/liter
<35 pCi/liter
>35 pCi/liter 50 to 100 pCi/liter
>100 pCi/liter 5 pCi/liter 5% of known value 5 pCi/liter 10% of known value 3.0 pCi/liter 10% of known value 5% of known value 5 pCi/liter 25% of known value 5 pCi/liter 5% of known value 1s = (pCi/liter) =
169.85 x (known).0933 10% of known value 15% of known value 10% of known value 6 pCi/liter 10% of known value 6 pCi/liter 15% of known value 10 pCi/liter 10% of known value A-28 From EPA publication,' "Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.
b TIML limit.
TIML-BLIND-01
ADDENDUM TO APPENDIX A We following is an explanation of the reasons why certain samples were outside the control limit specified y, the Environmental Protection Agency for the.Interlaboratory Comparions Program starting January 1988.
EPA TIML Control Result Limit Lab Code Analysis (pCi/L)a (pCi/L)a Explanation STF-524 K
1010.7+/-158.5b 1123.5-1336. 5b 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.
STW-532 1-131 9.0+/-2.0 6.2-8.8 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.
STW-534 Co-60 63.3+/-1.3 41.3-58.7 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 STM-554 Sr-90 51.0+/-2.0 54.8-65.2 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.
STW-560 Pu-239 5.8+/-1.1 3.5-4.9 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.
STW-568 Ra-228 2.6+/-1.0 2.7-4.5 The cause of low results is not known.
Next EPA cross check results were within the control imits. No further action is planned.
A-29
ADDENDUM TO APPENDIX A (continued)
TIML Result Analysis (pCi/L)a EPA Control Limit (pCi/L)a Explanation 26.0+/-10.0 45.7+/-4.2 17.3+/-1.2 1300.0+/-69.2c 11.0+/-2.0 38.7+/-1.2 74.0+/-6.9 130.7+/-16.8 30.3-47.7 49.8-60.2 17.4-22.6 1414.7-1685.3c 11.6-32.4 14.6-35.4 51.6-72.4 STM-570 STW-589 STM-599 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.
a Reported in pCi/L unless otherwise noted.
b Concentrations are reported in mg/kg.
c Concentrations are reported in mg/L.
A-30 Lab Code Sr-89 Sr-90 Sr-90 K
TW-601 STAF-626 STW-632 STM-641 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 is unknown.
Sample was reanalyzed in triplicate.
Results of reanalyses were 13.4+/-1.0 pCi/L.
The cause of high results is the difference in geometery between standard used in the TIML lab and EPA filter.
Sample was reanalyzed. Results of the reanalyses were 63.8+/-6.9 pCi/L within EPA limit.
Gr. alpha Gr. alpha Ba-133 1-131
APPENDIX B DATA REPORTING CONVENTIONS B-1
Data Reporting Conventions
.1.0. All activities except gross alpha and gross-beta are decay corrected to collection time or the end of the collection period.
2.0. Single Measurements Each single measurement is reported as follows:
x+/-s where x = value of the measurement; s = 2a counting uncertainty (corresponding to the 95% confidence level).
In cases where the activity is found to be below the lower limit of detection L it is reported as
<L where L = the lower limit of detection based on 4.66o uncertainty for a background sample.
3.0. Duplicate analyses 3.1 Individual results:
xi s
x1 S2 Reported result x+/-s where x = (1/2) (xl +/- x2) 2 2
s = (1/2)
S2+S2 3.2. Individual results:
<L1
<L2 Reported result:
<L where L = lower of LI 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 x and standard deviation(s) of a set of n numbers xj, x2... xn are defined as follows:
1 n
S (x-3)2 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
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/l 300 pCi/1 20,000pCi/l 20,000 pCi/1 300 pCi/1 3,000 pCi/1 30 pCi/1 Gross beta Tritium 100 pCi/i 3 x 106 pCi/i 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