ML20029D214
| ML20029D214 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 12/31/1993 |
| From: | Huebner L TELEDYNE ISOTOPES |
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| NUDOCS 9405040203 | |
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WTELEDYNE e
o ISOTOPES MIDWEST 1.ABORATORY 700 LANDWDIR ROAD NOR11IBROOK,ILUNots 60062-2310 008) 5644100
- FAX 001D 564 4517 NORTHERN STATES POWER COMPANY MINNEAPOLIS, MINNESOTA PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket No. 50-282 License No. DPR-42 50-306 DPR-60 ANNUAL REPORT to the i
UNITED STATES NUCLEAR REGULATORY COMMISSION Radiation Environmental Monitoring Program January 1,1993 to December 31,1993 Project No. 8010 i
Prepared Under Contract by TELEDYNE ISOTOPES MIDWEST LABORATORY Project No. 8010 Approved by:
alt.-
" ~ $. G. Huebner GeneralManager 15 April 1994 9405040203 940427 PDR ADOCK 05000282 R
PREFACE The staff of Teledyne Isotopes Midwest Laboratory was responsible for the acquisition of data presented in this report. Samples were collected by members of the staff of the Prairie Island Nuclear Generating Plant, Northern States Power Company. 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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t TABLE OF CONTENTS Section Page
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Pre fa cc...........................
...........ii List of Tables.....................
..................................iv
1.0 INTRODUCTION
....................................1 2.0
SUMMARY
...............................................................................2 3.0 RADIATION ENVIRONMENTAL MONfrORING PROGRAM (REMP)..... 3 3.1 Program Design and Data Interpretation..............................
.3 3.2 Program Description...................
..........................4 3.3 Program Execu tion........................................................... 5 3.4 Laboratory Procedures......................................
.............5 3.5 Program Modifications........
................6 3.6 Land Use Census........................
......6 4.0 RESULTS AND DISCUSSION..............
... 7 4.1 Atmospheric Nuclear Detonations and Nuclear Ace' '. ants......-...
.7 4.2 Summary of Preoperational Data..........
.........................7 4.3 Program Findings.........................
.................8 5.0 TABLES.....
................11' 6.0 REFE RENCES CITE D................................................................. 2 2 APPENDICES A
Interlaboratory Comparison Program Results......
...................A-1 B
Data Reporting Conventions..................
........................................B-1 C
Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas.............C-1 l
D Special Ground and Well Water Samples.............................................D-1 E
Sampling Location Maps..........................................................E-1
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o TABLE OF CONTENTS Section Page Prefa ce....................
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.......................ii
(
List of Tables..........
.................................................iv
1.0 INTRODUCTION
........1 2.0
SUMMARY
.................................................................................2 3.0 RADIATION ENVIRONMENTAL MONITOIUNG PROGRAM (REMP)..... 3 3.1 Program Design and Data Interpretation..........
............3 3.2 Program Description......
..............................4 3.3 Program Execu tion...................................................
.......5 3.4 Laboratory Procedures.........................
............5 3.5 Program Modifications................
.6 3.6 Land Use Census....
'........... 6 4.0 RESULTS AND DISCUSSION...........................
.....................7 4.1 Atmospheric Nuclear Detonations and Nuclear Accidents..
.... 7 4.2 Summary of Preoperational Data........
.......7 4.3 Program Findings...
..................................8 5.0 TABLES............
...............................11
6.0 REFERENCES
CITED.............................
...............................22 APPENDICES A
Interlaboratory Comparison Program Results.....
..............................A-1 B
Data Reporting Conventions.......
..........................B-1 C
Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Backgromid in Unrestricted Areas..............C-1 D
Special Ground and Well Water Samples........................................D-1 E
Sampling Location Maps..................................
.........................E-1 1
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LIST OF T \\BLES Title Eage l
5.1 Sample Collection and Analysis Program,1993........
..............12 1
1 5.2 Sampling Locations...
................13 5.3 Missed Collections and Analyses,1993............
....16 l
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l 5.4 Environmental Radiological Monitoring Program Sununary....................17 l
In addition, the following tables are in the Appendices:
Appendix A A-1 Interlaboratory Comparison Program Results, 1990-1993..
........A1 A-2 Interlaboratory Comparison Program Results (TLDs).
..............A 1 - 1 A-3 In-house Spiked Samples..
..A2-1 A-3 In-house " Blank" Samples...
..A3-1 Attachment A: Acceptance criteria for spiked samples...
..A2 Accendix C C-1 Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas..........C-2 Appendix D D-4.1 Sample collection and analysis program....................
...............D-6 D-4.2 Sampling locations.................................
......D-7 D-4.3 REMP Summary....................
.......................D-8 D-4.4 REMP Complete Data Table................
........D-9 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 Prairie Island Nuclear Generating Plant, Red Wing, Minnesota, during the period January - December,1993.
This program monitors the levels of radioactivity in the air, terrestrial, and aquatic environments in order to assess the impact of the plant on its surroundings.
Tabulations of the individual analyses made during the year are not included in this report.
These data are included in a reference document (Teledyne Isotopes Midwest Laboratory,1993) available at Northern States Power Company, Nuclear Generation Department.
Prairie Island Nuclear Generating Plant is located on the Mississippi River in Goodhue County, Minnesota, and operated by Northern States Power Company. The plant has two 550 MWe pressurized water reactors. Unit 1 achieved initial criticality on 1 December 1973. Commercial operation at full power began on 16 December 1973. Unit 2 achieved initial criticality on 17 December 1974. Commercial operation at full power began on 21 December 1974.
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SUMMARY
The Radiation Environmental Monitoring Program (REMP) required by the U.S. Nuclear Regulatory Commission (NRC) Technical Specifications for the Prairie Island Nuclear Generating Plant is described. Results for 1993 are summarized and discussed.
Program findings show background levels of radioactivity in the environmental samples collected in the vicinity of the Prairie Island Nuclear Generating Plant with the exception of some of the additional special ground and well water samples. These special ground and well water samples are summarized and documented separately in Appendix D.
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3.0 RADIATION ENVIRONMENTAL MONITORING PROGRAM (REMP) 3.1 Procram Desien and Data Interpretation The purpose of the Radiation Environmental Monitoring Program (REMP) at the Prairie Island Nuclear Generating Plant is to assess the impact of the pfant 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 (TLr's).
Sources of environmental radiation include the following:
(1) Natural background radiation arising from cosmic rays and primordial radionuclides; (2) Fallout from atmospheric nuclear detonations; (3) Releases from nuclear power plants; (4) Industrial and medical radioactive waste; and (5) Fallout from nuclear accidents.
In interpreting the data, effects due to the plant must be distinguished from those due to other sources.
A major interpretive aid in assessment of these effects is the design of the monitoring progran at the Prairie Island 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 controllocation. 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 the 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 pr'oduct mix produced by a nuclear reactor.md that produced by a nuclear detonation. Each of the three isotopes is produced in roughly equivalent amounts by a reactor: each constitutes about 10% of the total activity of fission products 10 days after reactor shutdown. On the other hand, 10 days after a nuclear explosion, the contributions of zirconium-95, cerium-144, and cesium-137 to the activity of the resulting debris are in the approximate ratio 4:1:0.03 (Eisenbud,1963). Beryllium-7 is of cosmogenic origin and potassium-40 is a naturally-occurring isotope. They were chosen as calibration monitors and should not be considered 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 3
by nuclear power plants, but to date their major source of injection into the general environment has been atmospheric nuclear testing. Nuclides of the final group, manganese-54, iron-59, cobalt-58 and -60, and zinc-65, are activation products and arise from activation of corrosion products. They are typical components of a nuclear power plant's effluents, but are not produced in significant quantities by nuclear detonations.
Other means of distinguishing sources of environmental radiation are employed in l
interpreting the data. Current radiation levels are compared with previous levels, l
including those incasured 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 at Prairie Island is summarized in Table 5.1 and briefly reviewed below. Table 5.2 l
defines the sampling location codes used in Table 5.1 and specifies for each location its l
type (indicator or control) and its distance, direction, and sector relative 40 the reactor site. To assure that sampling is carried out in a reproducible manner, detailed sampling procedures have been prescribed (Prairie Island Nuclear Generating Plant,1987). Maps of sampling locations are included in Appendix E.
l To monitor the air environment, airborne particulates are collected on membrane filters by continuous pumping at five locations. Also, airborne iodine is collected by i
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 l
filters for iodine-131. A quarterly composite of the particulate filters from each location is gamma-scanned on an HP Ge or Ge(Li) detector. One of the five locations is a control (P-1), and four are indicators (P-2, P-3, P-4, and P-6).
l Ambient gamma radiation is monitored at fifty (50) locations, using CaSO4:Dy dosimeters with four sensitive areas at each location: ten (10) in an inner ring in the general area of the site boundary, fifteen (15) in the outer ring within a 4-5 mile radius, eight (8) at special interest locations, sixteen (16) in the area of the Independent Spent Fuel Storage Installation (ISFSI), 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 the inner ring, outer ring and special interest locations are 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.
For additional monitoring of the terrestrial environment, green leafy vegetables (cabbage) are collected annually from the highest D/Q garden and a control location (P-38) and analyzed for iodine-131. Corn is collected annually only if fields are irrigated with river water and analyzed for gamma-emitting isotopes. Well water and ground water are 4
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i 3.2 Procram Descriorion coll'ected quarterly from three locations near the plant and analyzed for tritium and gamma-emitting isotopes. River water is collected weekly at two locations, one upstream of the plant (P-5) and one downstream (P-6, Lock and Dam No.3). Monthly composites are analyzed for gamma-emitting isotopes. Quarterly composites are analyzed for tritium.
Drinking water is collected weekly from the City of Red Wing well. 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, periphyton or invertebrates, and bottom sediments. Shoreline sediment is collected semi-annually from one location. All samples are analyzed for gamma-emitting isotopes.
A summary of special tritium sampling of ground and well water is included in Appendix D.
3.3 Procram Execution The Program was executed as described in the preceding section with the following exceptions:
No TLD data was available for the second quarter of 1993 for location P-01S. The TLD was lost in the field.
No milk sample was available from location P-37 for the week of July 27, 1993. Redundant samples were collected, but one was lost in shipment and the other was damaged in shipment.
Deviations from the program are summarized in Table 5.3.
3.4 Laboratorv Procedures All iodine-131 analyses in milk and drinking water were made by using a sensitive radiochemical procedure which involv separation of the element by use of an ion-exchange resin and subsequent beta counting. All gamma-spectroscopic analyses were performed with an HP Ge or Ge(Li) detector. Levels of iodine-131 in cabbage were determined by HP Ge or Ge(Li) spectrometry. Levels of airborne iodine-131 in charcoal samples were measured by HP Ge or Ge(Li) spectrometry.
Tritium levels were determined by liquid scintillation technique.
Analytical procedures used by the Teledyne Isotopes Midwest Laboratory are specified in detail elsewhere (Teledyne Isotopes Midwest Laboratory,1993). 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 5
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1 3.4 Laboratory Procedures (continued)
Quality Assurance Program are presented elsewhere (Teledyne Isotopes Midwest Laboratory,1993). The TIML Quality Assurance Program includes participation in Interlaboratory Comparison (Crosscheck) Programs. Results obtained in crosscheck programs are presented in Appendix A.
3.5 Procram Modifications Eighteen new locations were added to the TLD monitoring program in the third quarter of 1993. Sixteen are ISFSI area locations ( P-011A to P-081A and P-011B to P-08IB ),
l placed inside and outside of the earth berm. Two new indicators ( P-07S and P-08S )
I were added to the special interest areas. A new vegetation control was added in August,1993. Cabbage was collected from the Cain residence (P-38).
3.6 Land Use Census l
In accordance with Technical Specification 4.10, paragraph B1, a land use census is conducted in order to identify the location of the nearest milk animal, the nearest 2
residence, and the nearest garden of greater than 500 ft producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of 5 miles. This l
census is conducted at least once per 12 months between the dates of May I and j
l October 31, New locations are 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 l
of the year in which the land use census was conducted.
1 This land use census insures the updating of the radiation environmental monitormg l
program should sampling locations change within the 5 mile radius from the plant.
The 1993 Land Use Census was completed on July 31,1993. There were no changes in i
any of the highest D/Q locations for dairy, nearest residence, or garden sites in 1993.
The critical receptor location did not change in 1993 due to the requirements of the land use census.
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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 4
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.
J 4.1 Atmosoheric Nuclear Detonations and Nuclear Accidents There were no reported atmospheric nuclear tests in 1993. 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.
4 There were no reported accidents at nuclear reactor facilities in 1993.
4.2 Summary of Preoperational Data The following constitutes a summary of preoperational studies conducted at the Prairie Island Nuclear Power Plant during the years 1970 to 1973, to determine background levels expected in the environment, and provided, where applicable, as a means for 1
comparison with present day levels. Strict comparisons, however, are difficult, since background levels of radiation were much higher in these years due to radioactive fallout from the atmosphere. Gross beta measurements in fallout declined yearly from a level of 2
2 12,167 pCi/m to 1,020 pCi/m, and these declining values are reflected throughout the various media tested.
In the air environment, ambient gamma radiation (TLDs) averaged 9.4 mR/4 weeks during preoperational studies. Gross beta in air particulates declined from levels of 0.38 Airborne:pCi/m3. Average levels today have stabilized to around 0.025 pCi/m,,
to 0.037 3
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' ioiodine remained below detection levels.
In the tes astrial environment of 1970 to 1973, both milk, agricultural crops, and soil were morntored. In milk samples, low levels of Cs-137, I-131, and Sr-90 were detected.
Cs-137 levels declined from 16.5 to 8.6 pCi/L. Measurements today for both Cesium and Iodine are below detection levels. Agricultural crop measurements averaged 57.7 pCi/g for gross beta and 0.47 pCi/g for Cs-137. Gross beta measured in soil averaged 52 pCi/g gross beta.
The aqueous environment was monitored by testing of river, well, and lake waters, bottom sediments, fish, aquatic vegetation, and periphyton. Specific location comparison of drinking, river, and well water concentrations for tritium and gross beta are not possible. However, tritium background levels, measured at eight separate locations, declined steadily from an average concentration of 1020 pCi/L to 490 pCi/L.
Levels of tritium measured today are below detection levels, with the exception of the special tritium sampling described in Appendix D. Values for gross beta, measured from 1970 to 1973, averaged 9.9 pCi/L in downstream Mississippi River water,8.2 pCi/L for well waters, and 11.0 pCi/L for lake waters. Gamma emitters were below the lower limit of detection (LLD). In bottom sediments, gross beta background levels were determined at 51.0 pCi/g. Cs-137 activity, during preoperational studies in 1973, 7
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4.2 Summarv of Preoperational Data (continued).
measured 0.25 pCi/g upstream and 0.21 pCi/g downstream. The lower levels observed today can still be attributed to residual activity from atmospheric fallout. Gross beta in fish, measured in both flesh and skeletal samples, averaged 7.3 and 11.7 pCi/g,
respectively. Gross beta background levels in aquatic vegetation, algae, and periphyton samples measured 76.0 pCi/g,46.0 pCi/g, and 13.6 pCi/g respectively.
4.3 Program Findings Results obtained show background levels of radioactivity in the environmental samples collected in the vicinity of the Prairie Island Nuclear Generating Plant in 1993, with the exception of some of the additional special ground and well water samples (see Appendix D).
Ambient Radiation (TLDs)
Ambient radiation was measured in the general area of site boundary, at the outer ring 4
- 5 mi distant from the Plant, at special interest areas, and at one control location. The means ranged from 15.1 mR/91 days at inner ring locations to 16.5 mR/91 days at outer ring locations. The mean at special locations was 15.3 mR/91 days and 15.4 mR/91 days at the control location. At sixteen new ISFSI area locations, measured inside and outside the earth berm, dose rates measured 15.3 and 16.2 mR/91 days, respectively. The differences are not statistically significant. The dose rates measured at all indicator and control locations were similar to those observed in 1978 (12.1 and 15.1 mR/91 days, respectively); in 1979 (12.6 and 15.3 mR/91 days,respectively; in 1980 (11.2 and 13.5 mR/91 days, respectively); in 1981 (13.0 and 14.5 mR/91 days, respectively); in 1982 (12.0 and 13.0 mR/91 days, respectively); in 1983 (13.0 and 14.9 mR/91 days, respectively); in 1984 (13.9 and 15.3 mR/91 days, respectively); in 1985 (13.9 and 15.4 mR/91 days, respectively); in 1986 (16.6 and 17.0 mR/91 days, respectively); in 1987 (15.4 and 16.0 mR/91 days, respectively) in 1988 (16.2 and 16.7 mR/91 days, respectively); in 1989 (15.8 and 16.3 mR/91 days, respectively); in 1990 (15.9 and 16.3 mR/91 days, respectively); in 1991 (14.7 and 14.5 mR/91 days, respectively); and in 1992 (15.1 and 17.1 mR/91 days ). No plant effect on ambient gamma radiation was indicated.
Airborne Particulates The average annual gross beta concentration in airborne particulates was nearly identical at both indicator and control locations (0.022 and 0.019 pCi/m3), respectively, and was similar to levels observed in 1982 (0.026 pCi/m3),1983 (0.023 pCi/m3),1984 3
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(0.024 pCi/m ),1985 (0.025 pCi/m ),1986 (0.025 pCi/m3),1987 (0.024 pCi/m )
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1990 (0.024 pCi/m ), in 1991 (0.025 pCi/m3) and in 1992 (0.023 and 0.021 pCi/m ).
It was slightly lower than in 1988 (0.030 pCi/m3 at both indicator and control locations) and 1989 (0.028 pCi/m3). The average of 0.025 pCi/m3 or 1986 does not f
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 cial.,1969). It had been attributed to fallout of nuclides from the stratosphere j
(Gold clal.,1964). It was pronounced in 1981, occurred to a lesser degree in 1982, and has not occured since 1983. In 1986, a spring peak could not be identified because it 8
was overshadowed by releases of radioactivity from Chernobyl. The highest averages for gross beta were seen in the months of January and December. The increase of beta activity during the winter months was also observed in 1983, 1984. 1985, 1986 (exclusive of the period between May 19,1986 and June 9, 1986), 1987, 1988, 1989, 1990,1991,1992, and 1993.
Two pieces of evidence indicate conclusively that the elevated activity observed durmg j
the winter months 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 Monticello Nuclear Generating Plant, about 100 miles distant from the Prairie Island Nuclear Generating Plant (Northern States Power Company,1994a).
Gamma spectroscopic analysis of quarterly composites of air particulate filters yielded similar results for indicator and control locations. Beryllium-7, which is produced j
continuously in the upper atmosphere by cosmic radiation (Arnold and Al-Salih,1955),
was detected in all samples. All other gamma-emitting isotopes were below their j
respective LLD limits.
Airborne Iodine Weekly levels of airborne iodine-131 were below the lower limit of detection (LLD) of 3
0.07 pCi/m in all samples.
l Milk Iodine-131 results were below the detection limit of 1.0 pCi/L in all samples. Cs-137 results were below the LLD level of 15 pCi/L in all samples. No other gamma-emitting isotopes, except potassium-40, were detected in any milk samples. This is consistent with the findings of the National Center for Radiological Health that most radiocontaminants in feed do not find their way into milk due to the selective reactor 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 1993 show no radiological effects of the plant operation.
Drinkine Water In drinking water from the City of Red Wing well, tritium activity was below the LLD level of 200 pCi/L in all samples. As with the other well water samples, all analyses for gamma-emitting isotopes yielded results below detection limits. Gross beta averaged 7.5 pCi/L and was similar to levels observed in 1979 (10.5 pCi/L),1980 (11.8 pCi/L),
1981 (pCi/L),1982 (8.9 pCi/L),1983 (8.0 pCi/L),1984 (7.9 pCi/L),1985 (7.1 pCi/L),1986 (6.8 pCi/L),1987 (7.9 pCi/L),1988 (8.0 pCi/L),1989 (7.0 pCi/L),1990 (7.0 pCi/L),1991 (8.0 pCi/L), and 1992 (7.6 pCi/L.
River Water At the upstream and downstream collection sites, quarterly composite tritium levels were below the LLD level of 195 pCi/L in all samples.
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River Water (continuedt River water was also analyzed for gamma-emitting isotopes. All gamma-emitting isotopes were below their respective detection limits. There was no indication of a plant effect.
1 Well Water At the control well P-25, Rohl Farm and three indicator wells (P-8, Community Center; P-6, Lock and Dam No. 3; and P-9, Plant Well No. 2 ) no tritium was detected above i
the LLD level of 193 pCi/L in all but two samples. One sample from location P-9 l
measured 200 pCi/L, and one sample from the control location (P-25) measured 199 pCi/L.
Gamma-emitting isotopes were below detection limits in all samples.
Crops.
Two samples of cabbage were collected in August and analyzed for 1-131. The I-131 level was below 0.028 pCi/g wet weight in both samples. There was no indication of a plant effect.
j The field sampling personnel conducted a survey and found that there was no river water taken for irrigation into fields within 5 miles downstream from the Prairie Island Plant. Therefore, it was not necessary to collect and analyze corn samples.
Eish Fish samples were collected in June and September,1993, and analyzed for gamma emitting isotopes. Only naturally-occurring potassium-40 was detected, and there was no significant difference between upstream and downstream results. There was no indication et a plant effect.
Aauatic Insects or Perinhvton Aquatic insects (invertebrates) or periphyton were collected in June and September, 1993. The samples were analyzed for gamma-emitting isotopes.
Cs-137 was detected in one downstream sample at a level of 0.13 pCi/g wet weight.
Low levels of Cs-137 commonly occur in the environment. The levels observed in both aquatic insect and bottom sediment samples at location P-12 are considered residual activities due to radioactive fallout (Sec. 4.2, Summary of Preoperational Data).
l All other gamma-emitting isotopes, except naturally occurring potassium-40, were below their respective LLDs. No plant effect was indicated.
Ilottom and Shoreline Sediments Sediment collections were made in May and September,1993. The samples were analyzed for gamma-emitting isotopes.
j Cs-137 was detected in one downstream bottom sediment sample (0.041 pCi/g dry weight). All other gamma-emitting isotopes, except naturally-occurring potassium-40, were below their respective LLDs. No plant effect was indicated.
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l 5.0 TABLES
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Table 5.1. Sample collection and analysis program, Prairie Island Nuclear Generating Plant,1993.
Locations Collection Analysis Codes Type and Type and b
Medium Number (and Type)a Frequency FrequencyC Ambient radiation (TLD's) 50 P-01A - P-10A C/Q Ambient gamma P-01B - P-15B P-01S - P-08S P-011A - P-OSIA P-011B - P-08IB P-01C Airborne particulates 5
P-1(C), P-2, C/W GB, GS (QC of P-3, P-4, P-6 each location)
Airbome Iodine 5
P-1(C), P-2, P-3, C/W I-131 P-4, P-6 Milk 5
P-14, P-18, P-25(C), G/Md I-131, GS P-36, P-37 River water 2
P-5(C), P-6 G/W GS(MC), H-3(QC)
Drinking water 1
P-11 G/W GB(MC), I-131(MC)
Well Water 4
P-25(C), P-6, G/Q H-3, GS P-8, P-9 Edible cultivated crops -
leafy green vegetables 2
P-38(C), P-24 G/A I-131 Fish (one species edible portion) 2 P-19(C), P-13 G/SA GS Periphyton or invertebrates 2
P-5(C), P-12 G/SA GS l
Bottom Sediment 2
P-20(C), P-6 G/SA GS Shoreline sediment 1
P-12 G/SA GS a Location codes are defined in Table D-2. Control stations are indicated by (C). All other stations are indicators.
b l
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 coded as follows: GB = gross beta, GS = gamma spectroscopy, H-3 = tritium,I-131 = iodine 131. Analysis frequency is coded as follows: MC = monthly composite, QC = quarterly composite.
d M Ik is collected biweekly during the grazing season (May - October).
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l Table 5-2. Sampling locations, Prairie Island Nuclear Generating Plant,1993.
Distance and Type of Direction from j
a b
i Code Type Collection Site Sample Site Stack P-1 C
Air Station P-1 AP,AI 11.8 mi @ 316 /NNW P-2 Air Station P-2 AP,AI 0.5 mi @ 294 /WNW P-3 Air Station P-3 AP,AI 0.8 mi @ 313 /NW P-4 Air Station P-4 AP,AI 0.4 mi @ 359 /N P-5 C
Upstream of Plant RW, BO 2.3 mi @ 348 /NNW P-6 Lock & Dam #3 & Air AP, AI, RW, Station P-6 WW, BS 1.6 mi @ 129 /SE P-8 Community Center WW 1.0 mi @ 321"/WNW P-9 Plant Well #2 WW 0.3 mi @ 306 /NW P-11 Red Wing Service Center DW 3.3 mi @ 158 /SSE P-12 Downstream of Plant BO, SS 3.0 mi @ 116 /ESE P-13 Downstream of Plant F
3.5 mi @ 113 /ESE P-14 Gustafson Farm M
2.3 mi @ 173 /S P-18 Christiansen Farm M
3.8 mi @ 88 /E P-19 Upstream of Plant F
1.3 mi @ 0 /N P-20 Upstream of Plant F
0.9 mi @ 45 /NE P-24 Suter Residence VE 0.6 mi @ 158 /SSE P-25 C
Rohl Farm M, WW 12.9 mi @ 352 /N P-36 Dosdall Farm M
3.8 mi @ 9 /N P-37 Welsch Farm M
4.1 mi @ 90 /E P-38 C
Cain Residence VE 14.2 mi @ 359 /N General Area of the Site Boundary P-01 A Property Line TLD 0.4 mi @ 359 /N P-02A Property Line TLD 0.3 mi @ 10 /N P-03A Property Line TLD 0.5 mi @ 183 /S P-04A Property Line TLD 0.4 mi @ 204 /SSW P-05A Property Line TLD 0.4 mi @ 225 /SW P-06A Property Line TLD 0.4 mi @ 249 /WSW P-07A Property Line TLD 0.4 mi @ 268 /W P-08A Property Line TLD 0.4 mi @ 291 /WNW P-09A Property Line TLD 0.7 mi @ 317c/NW P-10A Property Line TLD 0.5 mi @ 333 /NNW 13
l Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant,1993 (continued).
Distance and Type of Direction from a
b Site Stack Code Type Collection Site Sample l
Acoroximatelv 4 to 5 miles Distant from the Plant j
P-01B Thomas Killian Residence TLD 4.7 mi @ 355 /N P-02B Roy Kinneman Farm TLD 4.8 mi @ 17 /NNE P-03B Wayne Anderson Farm TLD 4.9 mi @ 46 /NE P-04B Nelson Drive (Road)
TLD 4.2 mi @ 61 /ENE P-05B County Road E and Coulee TLD 4.1 mi @ 102 /ESE P-06S William Hauschibit Residence TLD 4.4 mi @ 112 /ESE P-07B Red Wing Public Works TLD 4.7 mi @ 140 /SE P-08B David Wnuk Residence TLD 4.1 mi @ 165 /SSE P-09B Highway 19 South TLD 4.2 mi @ 187 /S P-10B Cannondale Farm TLD 4.9 mi @ 200 /SSW P-11B Wallace Weberg Farm TLD 4.3 mi @ 221 /SW P-12B Ray Gergen Farm TLD 4.5 mi @ 247 /WSW P-13B Thomas O'Rourke Farm TLD 4.4 mi @ 270 /W P-14B David J. Anderson Farm TLD 4.9 mi @ 306 /NW P-15B Holst Farms TLD 4.2 mi @ 347 /NNW Soecial Interest Locations P-01S Federal Lock & Dam #3 TLD 1.6 mi @ 129 /SE P-02S Charles Suter Residence TLD 0.5 mi @ 155 /SSE P-03S Carl Gustafson Farm TLD 2.2 mi @ 173 /S P-04S Richard Burt Residence TLD 2.0 mi @ 202 /SSW P-05S Kinney Store TLD 2.0 mi @ 270 /W P-06S Earl Flynn Farm TLD 2.5 mi @ 299 /WNW P-07S Indian Community TLD 0.7 mi @ 271 /W P-08S Indian Community TLD 0.7 mi @ 287 /NWW P-01C C
Robert Kinneman Farm TLD 11.1 mi @ 331 /NNW i
i 14
i l
Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant,1993 (continued).
I Distance and Type of Direction from a
Collection Site Sampleb ISFSI Center Code Type l
ISFSI Area Inside Earth Berm P-01IA ISFSINuisance Fence TLD 190' @ 45 /NE P-02IA ISFSINuisance Fence TLD 360' @ 82 /E P-03IA ISFSINuisance Fence TLD 370' @ 100 /E P-04IA ISFSI Nuisance Fence TLD 200' @ 134 /SE P-05IA ISFSINuisance Fence TLD 180' @ 219'/SW l
P-061A ISFSI Nuisance Fence TLD 320' @ 258 /WSW j
P-071A ISFSI Nuisance Fence TLD 320' @ 281 /WNW l
P-081A ISFSI Nuisance Fence TLD 190' @ 318 /NW l
ISFSI Area Outside Earth Berm l
P-011B ISFSI Berm Area TLD 340' @ 3 /N (01SP) l P-02IB ISFSI Berm Area TLD 380' @ 28 /NNE (02SP)
P-03IB ISFSI Berm Area TLD 559' @ 85 /E (03SP)
P-04IB ISFSI Berm Area TLD 590' @ 165 /SSE (04SP)
P-051B ISFSI Berm Area TLD 690' @ 186 /S (05SP)
P-061B ISFSI Berm Area TLD 720' @ 201"/SSW (06SP)
P-071B ISFSI Berm Area TLD 610' @ 271 /W (07SP)
P-081B ISFSI Berm Area TLD 360' @ 332 /NNW (08SP) a "C" denotes control location. All other locations are indicators.
b Sample Codes:
AP = Airborne particulates WW = Well water AI= AirborneIodine DS = 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 15
l Table 5.3. Missed collections and analyses,1993. Prairie Island Nuclear Generating Plant. All required samples were collected and analyzed as scheduled except the following:
Collection Reason for not Plan for Preventing Sample Analysis Location Date conducting REMP as Recurrence or Period required TLD Ambient P-01S 2nd Qtr.,
Lost in the field.
Moved TLD about 25' Radiation 1993 and placed inside locked fenced area near local air sampler.
Milk
- Gamma, P-37 07-27-93 Redundant samples Issued complaint to I-131 collected, but one UPS concerning lost in shipping and damage and loss of other damaged in shipments.
Will shipping.
continue to ship separate redundant samples.
I i
i t
i l
16 l
Table 5.4.
Radiation Environmental Monitoring Program Summary.
Name of Facility Prairie Island Nuclear Power Station Docket No.
50-282, 50-306 location of Facility Goodhue, Minnesota Reporting Pericxl January - December 1993 (County, State)
Indicator location with liighest
. Control Number Sample Type and locations Quarterly Mean Locations Non-Type Number of LLDb Mean (F)C Mean (F)C Mean (F)c Routine a
c Locationd (Umts)
Analyses Range c
Range Resultse Range TLD (mR/91 Gamma 40 3.0 15.1 (40/40)
P-07A, Property Line 15.7 (4/4)
(See Control 0
days) (Inner (11.4-17.5) 0.4 mi @ 268"/W (15.0-16.0) below.)
Ring, Area at Site Boundary)
TLD (mR/91 Gamma 60 3.0 16.5 (60/60)
P-02 B, 20.9 (4/4)
(See Control 0
days)(Outer (13.2-20.9)
Kinneman Farm,4.8 (19.2-22.7) below.)
Ring,4 5 mi @ l7*/NNE miles distant)
Gamma 27 3.0 15.3 (27/27)
P-03S, Gustafson 16.8 (4/4)
(See Control 0
ILD (mR/91 days)(Special (10.8-20.1)
Farm,2.2 mi @
(15.6-18.0) below.)
Interest Areas) 173 /SSE Camma 16 3.0 15.3 (16/16)
P-OIIA,ISFSI 16.2 (2/2)
(See Control 0
TLD (mR/91 days)lSFSI (12.3-16.9)
Nuisance Fence, (15.6-16.9) below.)
Area Inside 190' @ 45*/NE Earth Derm Gamma 16 3.0 16.2 (16/16)
(See Control 0
TLD (mR/91 days)lSFSI (13.5-20.8)
Area,559' @ 85*/E (19.3-20.8) below.)
Area Outside Earth Berm Gamma 4
3.0 None P-01C, R. Kinneman 14.8 (4/4) 14.8 (4/4) 0 TLD(mR/91 days)
Farm,1Li mi @
(13.1-19.1)
(13.1-19.1)
(Control) 331*/NNW Airborne GB 260 0.003 0.022 (208/208)
P-02, P-04, P-06 had 0.022 (156/156) 0.019 (52/52)
O Particulates (0.005-0.064) identical means (0.005-0.064)
(0.007-0.058) 3 (pCi/m )
GS 20 P-6, Air Station P-6 Be-7 0.022 0.068 (16/16) 1.6 mi. @l29*/SE 0.071 (4/4) 0.052 (4 /4) 0 (0.049-0.086)
(0.063-0.086)
(0.047-0.057)
Mn-54 0.0028
<LLD
<LLD 0
Co-58 0.0031
<LLD
<LLD 0
Co-60 0.0041
<LLD
<LLD 0
Zn-65 0.0072
<LLD
<LLD 0
Zr-Nb-95 0.0057 (LLD
<LLD 0
Ru-103 0.0038
<LLD
<LLD 0
Ru-106 0.022
<LLD
<LLD 0
Cs-134 0.0036
<LLD
<LLD 0
<LLD 0
Ba-La-140 0.017 (LLD
<LLD 0
Cc-141 0.0039 (LLD
<LLD 0
Ce 144 0.012
<LLD
<LLD 0
l l
1 17 1
Table 5.4.
Radiation Environmental Monitoring Program Stunmary, Nameof Facihty PrairiaIsland Nuclear PowerStation Docket No.
50-282, 50-306 Location of Facility Goodhue, Minnesota Reporting Period January - December 1993 (County, State)
Indicator Location with liighest Lontrol Number Sample Type and locations Quarterly Mean Locations Non-b Mean (F)C Mean (F)C Mean (F)c Routine Type Number of LLD a
c Locationd (Units)
Analyses Range Range Range Results' c
Airborne 1-131 260 0.07
<LLD
<LLD 0
lodine 3
(pCi/m )
<LLD 0
(pCi/L)
P-14, Gustafson 1500 (18/18) 1360 (18/18) 0 (1?80-1640)
Farm 2.3 mi @
(1290-1640)
(1090-1550) 173*/S Cs-134 15
<LLD
<LLD 0
C&137 15
<LLD
<LLD 0
Other 15
<LLD (LLD 0
gammas River Water H-3 8
195
<LLD
<LLD 0
(pCi/L)
<LLD
<LLD 0
Fe-59 30 (LLD
<LLD 0
Co-58 15
<LLD
<LLD 0
Co-60 15
<LLD
<LLD 0
Zn45 30
<LLD
<.LLD 0
Zr-Nb-95 15
<LLD
<LLD 0
Cs-134 10
<LLD
<LLD 0
Ce137 10
<LLD
<LLD 0
Ba-La-140 15
<LLD
<LLD 0
Ce-144 50
<LLD
<LLD 0
18
l I
Table 5.4.
Radiation Environmental Monitoring Program Summary.
l Name of Facility Prairie Island Nuclear Power Statior.
Docket No.
50-282, 50-306 Location of Facility Goodhue Mmnesota Reporting Period January - December 1993 t
(County, State) indicator Location with Highest
' Control Number i
Sample Type and Locations Quarterly Mean Locations Non-b Type Number of LLD Mean (F)C Mean (F)(
Mean (F)c Routine (Units)
Analyws Rangec Locationd a
c Range Results' Range Dnnking GB 12 1.0 7.5 (12/12)
P-11, Red Wing 7.5 (12/12)
None 0
j Water (pCi/L)
(6.0-10.6)
Service Center 3.3 (6.0-10.6) mi @ IN'/SSE I-131 12 1.0
<LLD None 0
II-3 4
200
<LLD None 0
\\
GS 12 Mn-54 15
<LLD None 0
Fe-59 30
<LLD None O
Co 58 15
<LLD None 0
Co-60 15
<tLD None 0
)
Zn45 30
<LLD None 0
Zr-Nb-95 15
<LLD None 0
Cel}l 10
<LLD None O
Cs-137 10
<LLD None o
Da-La-140 15
<LLD None O
Ce-144 54
<LLD None 0
l 1
Well Water M-3 16 193 200 (1/4)
P-9, Plant Well #2 200 (1/4) 199 (1/4) 0 (pCi/L) l).3 mi. @ 306*/NW
]
GS 16 i
l 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
Cellt 15
<LLD (LLD 0
Ce137 18
<LLD (LLD 0
Ce-144 97 (LLD
<LLD 0
Crops -
I131 2
0.028 (LLD
<LLD 0
Cabbage (pCi/g wet) 19
Table 5.4.
Radiation Environmental Monitoring Program Summary.
Name of Facility Prairie Island Nuclear Power Station Docket No.
50-282, 50-306 Location of Facility Gcxxihue, Minnesota Reporting Period January - December 1993 (County, State)
Indicator Location with Highest Control Number Sample Type and Locations Quarterly Mean Locations Non-Type Number of LLob Mean (F)C Mean (F)C Mean (F)c Routine a
c Locationd (Units)
Analyses Range c
Range Results" Range Fish-Flesh CS 4
(pCi/g wet)
K-40 0.1 2.78 (2/2)
P-19, Upstream of 2.80 (2/2) 2.80 (2/2) 0 (2.59-2.97)
Plant,1.3 mi @
(2.75-2.85)
(2.75-2.85) 0*/N Mn-54 0.024
<i.LD (LLD 0
Fe-59 0.12
<LLD
<LLD 0
Co-58 0.033 (LLD
<LLD 0
Co-60 0.034
<LLD
<LLD 0
.'.n-65 0.070
<LLD
<LLD 0
Zr-Nb-95 0.068
<LLD
<LLD 0
Cs-1M 0.022
<LLD (LLD 0
Cs-137 0.022
<LLD
<LLD 0
Da-La-140 0.23
<LLD
<LLD 0
Invertebrates GS 4
(pCi/g wet)
Be-7 0.70
<LLD
<LLD u
K-40 0.10 1.28 (2/2)
P-12, Downstream 1.28 (2/2) 1.10 (2/2) 0 (1.21-1.35) of Plant,3.0 mi@
(1.21-1.35)
(0.66-1.54) 116*/ESE Mn-54 0.078
<LLD
<LLD 0
Co-58 0.075
<LLD
<LLD 0
Co-60 0.093
<LLD
<LLD 0
Zn-65 0.17
<LLD
<LLD 0
Zr-Nt-95 0.13
<tLD
<LLD 0
Ru-103 0.082
<LLD
<LLD 0
Ru-106 0.64
<LLD
<LLD 0
Cs-134 0.060
<LLD
<LLD 0
Cs-137 0.063
<LLD P-12, Downstream 0.13 (1/2)
<LLD 0
of Plant,3.0 mi @
116*/ESE Da-La-140 0.33
<LLD
<LLD 0
Ce-141 0.11
<LLD
<LLD 0
Cc-144 0.35
<LLD
<LLD 0
20
i Table 5.4.
Radiation Environmental Monitoring Program Summary.
Name of Facility Prairie Island Nuclear Power Station Docket No.
50-282, 50-306 location of Facihty Goodhue, Minnesota Reporting Period January - December 1993 (County, State)
Indicator Location with liighest Control Number Sample Type and locations Quarterly Mean Locations Non-Type Number of LLDb Mean (F)C Mean (F)C Mean (F)c Routine a
c Locationd (Units)
Analyses Range c
Range Results' Range Bottom and GS 6
Shoreline Sediments Be-7 0.31 0.37 (1/4)
P-06, Lock and 0.37 (1/2)
<LLD 0
(pCi/g dry)
Dam No 3, 1.6 mi. @ 129*/SE K-40 0.5 7.62 (4/4)
P-20, Upstream of 9.59 (2/2) 9.59 (2/2) 0 (6.80-9.31)
Plant,0.9 mi. G (9.54-9.64 )
(9.54-9.64) 45'/NE Mn-54 0.032
<LLD
<LLD 0
Co-58 0.042
<LLD
<LLD 0
<LLD 0
Zn-65 0.095
<LLD
<LLD 0
Zr-NI>.95 0.065
<LLD
<LLD 0
Ru-103 0.036
<LLD
<LLD 0
Ru-106 0.28
<LLD
<LLD 0
Cs-134 0.064
<LLD
<LLD 0
Cs-137 0.031 0.041 (1/4)
P-06, Lock and 0.041 (1/2)
<LLD 0
Dam No.3, 1.6 mi. @ 129 /SE Ba-La-140 0.069
<LLD
<LLD 0
Ce-141 0.087
<LLD
<LLD 0
Ce-144 0.25
<LLD
<LLD 0
d GB = Gross beta; GS = gamma scan.
b LLD = Nominallower 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 j
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.
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 typical pre-operational value for the medium or location.
1 21
6.0 REFERENCES
CITED Arnold, J. R. and H. A. Al-Salih.1955. Beryllium-7 Produced by Cosmic Rays. Science 121:
e 451-453.
Eisenbud, M.1963. Environmental Radioactivity, McGraw-Hill, New York, New York, pp.
213,275 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, Chicago, 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.
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.
22
=
~.
l-
=
Northern States Power Company.
1972.
Prairie Island Nuclear Generating Plant, Environmental Monitoring and Ecological Studies Program, January 1,1971 to December 31,1971. Minneapolis, Minnesota.
1973. Prairie Island Nuclear Generating Plant, Environmental Monitoring and Ecological Studies Program, January 1,1972 to December 31, 1972. Minneapolis, Minnesota.
1974. Prairie Island Nuclear Generating Plant, Environmental Monitoring and Ecological Studies Program, Volume 1, January 1,1973 to December 31, 1973.
Minneapolis, Minnesota.
Northern States Power Company.1979.. Prairie Island Nuclear Generating Plant, Annual l
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. Prairie Island 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. Prairie Island 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. Prairie Island 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. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1,1982 to December 31,1982 (prepamd by Hazleton Environmental Sciences). Minneapolis, Minnesota.
1934. Prairie Island 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 Laboratory). Minneapolis, Minnesota.
1985. Prairie Island 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 Laboratory). Mirmeapolis, Minnesota.
1986. Prairie Island 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 Laboratory). Minneapolis, Minnesota.
1987. Prairic Island Nudear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1,1986 to 23
i December 31,1986 (prepared by Teledyne Isotopes Midwest Laboratory). Minneapolis, Minnesota.
1988. Prairie Island 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 Laboratory). Minneapolis, Minnesota.
1989. Prairie Island 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 Laboratory). Minneapolis, Minnesota.
1990. Prairie Island Nucicar 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 Laboratory). Minneapolis, Minnesota.
1991. Prairic Island 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 Laboratory). Minneapolis, Minnesota.
1992. Prairie Island 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 Laboratory). Minneapolis, Minnesota.
1993 Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1,1992 to December 31,1992 (prepared by Teledyne Isotopes Midwest Laboratory). Minneapolis, Minnesota.
Teledyne Isotopes Midwest Laboratory.1993. Quality Control Program, Revision 12.
20 April 1992.
1993. Quality Control Procedures Manual, Revision 17,18 May 1993.
1993. Quality Assurance Program Manual, Revision 1,20 August 1992.
1993. Analytical Procedures, Revised 21 August 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 m
Plant, Complete Analysis Data Tables, January - December 1984.
24
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, Prairie Island Nuclear Generating Plant, Revision 16, 18 December 1987.
1987a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1986.
l 1987b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating i
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 Prairic 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.
l 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 R
l 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 Generating 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.
25
U.S. Public Health Service.1967. Radioassay Procedures for Environmental Samples, National Center for Radiologica! 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.
i i
l 26
1 J
APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS i
NOTE: Teledyne's Midwest Laboratory 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 four times a year; the complete Appendix is included in March, June, September and December monthly progress reports only. Please refer to March, June, September and December progress reports for informaticn.
January,1990 through December,1993
i Appendix A Interlaboratory Comparison Program Results Teledyne's Midwest Laboratory (formerly Hazleton Environmental Sciences) has participated in interlaboratory comparison (crosscheck) programs since the formulation of it's quality control program in December 1971. nese programs are operated by agencies which supply environmental type samples (e.g.,
milk or water) containing concentrations of radionuclides know 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 and air filters during the period 1990-1993.
His program is 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), since 1976 via various Imemational Intercomparisons of Environmental Dosimeters under the sponsorships listed in Table A-2. Also Teledyne testing results are listed.
Table A-3 lists results of the anal:/ses on in-house " spiked" samples for the past twelve months.
Data for previous years available upon request.
1 Table A-4 lists results of the analyses on in-house " blank" samples for the past twelve months.
Data for previous years available epon request.
l Attachment A lists acceptance criteria for " spiked" samples.
Out-of-limit results are explained directly below the result.
Al
1 A
i December,1993 ATTACHMENT A ACC '1.LNCE CRITERIA FOR " SPIKED" SAMPLES LABORATORY PRECISION: ( 4E STANDARD DEVIATION VALUES FOR VARIOUS ANALYSES
- One Standard Deviation Analysis Level for single determinations Gamma Emitters 5 to 100 pCi/ liter or kg 5.0 pCi/ liter
>100 pCi/ liter or kg 5% of known value Strontium-896 5 to 50 pCi/ liter or kg 5.0 pCi/ liter
>50 pCi/ liter or kg 10% of known value Strontium-90 2 to 30 pCi/ liter or kg 5.0 pCi/ liter 6
>30 pCi/ liter or kg 10% of known value Potassium
>0.1 g/ liter or kg 5% of known value Cross alpha s20 pCi/ liter 5.0 pCi/ liter
>20 pCi/ liter 25% of known value Gross beta s100 pCi/ liter 5.0 pCi/ liter
>100 pCi/ liter 5% of known value Tritium s4,000 pCi/ liter is = (pCi/ liter) =
169.85 x (known)**2'
>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 j
Iodine-131, s55 pCi/ liter 6.0 pCi/ liter
>55 pCi/ liter 10% of known value Iodine-1296 i
Uranium-238, s35 pCi/ liter 6.0 pCi/ liter Nickel-64n
>35 pCi/ liter 15% of known value 6
Technetium-99 Iron-55, 50 to 100 pCi/ liter 10 pCi/ liter
>100 pCi/ liter 10% of known value Others6 20% of known value
- From EPA publication, " Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.
6 Teledyne limit.
j A2 i
l j
1 Table A-1.
U.S. Env0 onmental Protection Agency's crosscheck program, comparison of EPA and Teledyne's Midwest Laboratory results for various sample media'.
Concentrationin pCi/L6 Lab Sample Date Tcledyne Results EPA Result' Control Code Type Collected Analyses f2 Sigma
- 1s, N=1 Limits STW-589 WATER Jan,1990 St-89 22.7 i 5.0 25.0 i 5.0 16.3 - 33.7 Sr-90 17.311.2 20.0 i 1.5 17.4 - 22.6 The sample was reanalyzed in triplicate for Sr-90; results of reanalyses were 18.811.5 pCi/L. No further action is planned.
STW-591 WATER Jan,1990 Gr. Alpha 10.3 i 3.0 12.0 1 5.0 3.3 - 20.7 Gr. Beta 12.311.2 12.015.0 3.3 - 20.7 STW-592 WATER Jan,1990 Ba-133 78.010.0 74.017.0 61.9 - 86.1 Co-60 14.7 i 2.3 15.0 i 5.0 6.3 - 23.7 Cs-134 17.3 i 1.2 18.015.0 9.3 - 26.7 Cs-137 19.3 i 1.2 18.015.0 9.3 - 26.7 Ru-106 133.3 i 13.4 139.0 i 14.0 114.8 - 163.2 Zn-65 135.016.9 139.0 i 14.0 114.8 - 163.2 STW-593 WATER Feb,1990 H-3 4827.0 i 83.0 4976.0 i 498.0 4113.0 - 5839.0 STW-594 WATER Mar,1990 Ra-226 5.0i 0.2 4.9 i 0.7 4.1 - 5.7 Ra-228 13.5 i 0.7 12.711.9 9.4 - 16.0 l
STW-595 WATER Mar,1990 Uranium 4.010.0 4.016.0 0.0 - 14.4 STAF-596 AIR FILTER Mar,1990 Cs-137 9.3 i 1.2 10.015.0 1.3 - 18.7 Gr. Alpha 7.3 i 1.2 5.015.0 0.0 - 13.7 Gr. Beta 34.010.0 31.015.0 22.3 - 39.7 Sr-90 10.010.0 10.0 i 1.5 7.4 - 12.6 STW-597 WATER Apr,1990 Gr. Alpha 81.013.5 90.0 i 23.0 50.1 - 129.9 Ra-226 4.9 i 0.4 5.010.8 3.6 - 6.4 Ra-228 10.6 i 0.3 10.211.5 7.6 - 12.8 U
18.7i 3.0 20.0 i 6.0 9.6 - 30.4 STW-598 WATER Apr,1990 Cs-134 16.010.0 15.0 i 5.0 6.3 - 23.7 Cs-137 19.0 i 2.0 15.0 i 5.0 6.3 - 23.7 Gross Beta 51.0 i 10.1 52.015.0 43.3 - 60.7 Sr-89 9.3 i 1.2 10.0 i 5.0 1.3 - 18.7 t-A1-1 t
Table A-1.
U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne's Midwest Laboratory results for various sample media'.
Concentration in pCi/L' Lab Sample Date Teledyne Results EPA Result' Control Code Type Collected Analyses 12 Sigma' 1s, N=1 Limits St-90 10.313.1 10.0 i 1.5 8.3 - 11.7 STM-599 MILK Apr,1990 Cs-137 26.016.0 24.015.0 15.3 - 32.7 I-131 98.7 i 1.2 99.0 i 10.0 81.7 - 116.3 K
1300.0 i 69.2 1550.0 i 78.0 1414.7 - 1685.3 ne K analysis was repeated in triplicate; result of reanalysis l
was 1421.7195.3 mg/L. No further action is planned.
Sr-89 21.713.1 23.015.0 14.3 - 31.7 Sr-90 21.017.0 23.015.0 14.3 - 31.7 STW-600 WATER May,1990 St-89 6.0 t 2.0 7.0i 5.0 0.0 - 15.7 Sr-90 6.7i 1.2 7.015.0 0.0 - 15.7 l
STW-601 WATER May,1990 Gr. Alpha 11.0 i 2.0 22.0 i 6.0 11.6 - 32.4 Gross Alpha analysis was repeated in triplicate; results of reanalyses were 13.411.0 pCl/L No further action is planned.
Gr. Beta 12.3 i 1.2 15.0 i 5.0 6.3 - 23.7 STW-602 WATER Jun,1990 Ba-133 100.7 i 8.1 99.0 i 10.0 81.7 - 116.3 Co-60 25.3 i 2.3 24.0 i 5.0 15.3 - 32.7 Cs-134 23.711.2 24.015.0 18.2 - 29.8 Cs-137 27.7 i 3.1 25.0 i 5.0 16.3 - 33.7 Ru-106 202.7 i 17.2 210.0 i 21.0 173.6 - 246.4 Zn-65 155.0 i 10.6 148.0 i 15.0 130.6 - 165.4 STW-603 WATER Jun,1990 i
H-3 2927.0 i 306.0 2933.0 i 358.0 2312.0 - 3554.0 l
STW-604 WATER Jul,1990 Ra-226 11.8 i 0.9 12.111.8 9.0 - 15.2 Ra-228 4.1 i 1.4 5.1 i 1.3 2.8 - 7.4 STW-605 WATER Jul,1990 U
20.3 i 1.7 20.8 i 3.0 15.6 - 26.0 i
STW-606 WATER Aug,1990 1-131 43.0 i 1.2 39.0 i 6.0 28.6 - 49.4 STW-607 WATER Aug,1990 Pu-239 10.0 i 1.7 9.1 i 0.9 7.5 - 10.7 STAF-608 AIR FILTER Aug,1990 Cs-137 19.0 2.0 20.0 i 5.0 11.3 - 28.7 1
A1-2 l
Table A-1.
U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne's Midwest Laboratory results for various sample media'.
6 Concentsationin pCi/L Lab Sample Date Tcledyne Results EPA Resultd Control Code Type Collected Analyses i2 Sigma' 1s, N=1 Limits Gr. Alpha 14.010.0 10.0i 5.0 1.3 - 18.7 i
G r. Beta 65.3 i 1.2 62.015.0 53.3 - 70.7 Sr-90 19.016.9 20.0 i 5.0 11.3 - 28.7 l
STW-609 WATER Sep,1990 l
Sr-89 9.0i 2.0 10.0 i 5.0 1.3 - 18.7 l
Sr-90 9.012.0 9.0 i 5.0 0.3 - 17.7 l
STW-610 WATER Sep,1990 Gr. Alpha 8.311.2 10.0i 5.0 1.3 - 18.7 Gr. Beta 10.3 i 1.2 10.0 i 5.0 1.3 - 18.7 STM-611 MILK Sep,1990 Cs-137 20.012.0 20.0 i 5.0 11.3 - 28.7 I-131 63.0 i 6.0 58.016.0 47.6 - 68.4 K-40 1673.3 i 70.2 1700.0 i 85.0 1552.5 - 1847.5 Sr-89 11.7 i 3.1 16.015.0 7.3 - 24.7 Sr-90 15.010.0 20.015.0 11.3 - 28.7 l
STW-612 WATER Oct,1990 Ba-133 116.7 i 9.9 110.0 i 11.0 90.9 - 129.0 Co-60 20.3 i 3.1 20.0 i 5.0 11.3 - 28.7 Cs-134 11.0 0.0 12.0 i 5.0 3.3 - 20.7 Cs-137 14.012.0 12.0 i 5.0 3.3 - 20.7 Ru-1f5 152.0 i 8.0 151.0 i 15.0 125.0 - 177.0 7a-65 115.3 i 12.2 115.0 1 12.0 94.2 - 135.8 STW-613 WATER Oct,1990 H-3 7167.0 i 330.0 7203.0 1 720.0 5954.0 - 8452.0 STW-614 WATER Oct,1990 Gr. Aipha 68.717.2 62.0 i 16.0 34.2 - 89.8 Ra-226 12.9 i 0.3 13.612.0 10.1 - 17.1 Ra-228 4.210.6 5.0 i 1.3 2.7 - 7.3 U
10.4106 10.2 i 3.0 5.0 - 15.4 STW-615 WATER Oct,1990 Cs-134 9.0 i 1.7 7.0 i 5.0 0.0 - 15.7 l
Cs-137 7.7i 1.2 5.0 i 5.0 0.0 - 13.7 l
Gross Beta 55.018.7 53.015.0 44.3 - 61.7 i
Sr-89 15.712.9 20.0 i 5.0 11.3 - 28.7 Sr-90 12.0 i 2.0 15.0 i 5.0 6.0 - 23.7 A1-3
Table A-1.
U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne's Midwest Laboratory results for various sample media *.
Concentrationin pCi/L6 Lab Sample Date T ;cdyne Results EPA Resultd Control Code Type Collected Analyses 12 Sigma' Is, N=1 Limits STW-616 WATER Nov,1990 Ra-226 6.8 i 1.0 7.4 1 1.1 5.5 - 9.3 Ra-228 5.311.7 7.7i 1.9 4.4 - 11.0 STW-617 WATER Nov,1990 U
35.0 i 0.4 35.5 i 3.6 29.3 - 41.7 Sample was analyzed but the results were not submitted to the EPA because the deadline was missed (all data on file).
STW-618 WATER Jan,1991 Sr-89 4.311.2 5.015.0 0.0- 13.7 Sr-90 4.7i 1.2 5.015.0 0.0 - 13.7 STW-619 WATER Jan,1991 Pu-239 3.6 i 0.2 3.3 i 0.3 2.8 - 3.8 STW-620 WATER Jan,1991 Gr. AIpha 6.7 i 3.0 5.0 i 5.0 0.0- 13.7 Gr. Beta 6.3
'.2 5.015.0 0.0 - 13.7 STW-621 WATER Feb,1991 Da-133 85.7 i 9.2 75.0 i 8.0 61.1 - 88.9 Co-60 41.3 i 8.4 40.015.0 31.3 - 48.7 Cs-134 9.0 i 2.0 8.015.0 0.0- 16.7 Cs-137 9.7 i 1.2 8.0 i 5.0 0.0- 16.7 Ru-1%
209.7 i 18.6 186.0 i 19.0 153.0 - 219.0 Zn-65 166.7i 19.7 149.0 i 15.0 123.0 - 175.0 STW-622 WATER Feb,1991
{
I-131 81.3 i 6.1 75.018.0 61.1 - 88.9
)
STW-623 WATER Feb,1991 H-3 4310.0 1 144.2 4418.0 i 442.0 3651.2 - 5184.8 STW-624 WATER Mar,1991 Ra-226 31.4 2 ?.2 31.8 i 4.8 23.5 - 40.1 Ra-228 21.115.3 11.9 - 30.3 No data for Ra 228.'as wported; sample was lost during analysis.
STW-625 WATER Mar,1991 U
6.7 i 0.4 7.6i 3.0 2.4 - 12.8 STAF-626 AIR FILTER Mar,1991 Cs-137 33.7 i 4.2 40.0i 5.0 31.3 - 48.7 Al-4
4 Table A-1.
U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Tcledyne's Midwest Laboratory results for various sample media'.
Concentration in pCi/L6 Lab Sample Date Teledyne Results EPA Resultd Control Code Type Collected Analyses 12 Sigma' 1s, N=1 Limits Gr. Alpha 38.7 i 1.2 25.0 i 6.0 14.6 - 35.4 The cause of the high Gross Alpha result is the difference in geometry between the standard used in the TIML lab and the EPA filter.
Cr. Beta 130.0i4.0 124.0 i 6.0 113.6 - 134.4 Sr-90 35.7 i 1.2 40.015.0 31.3 - 48.7 STW-627 WATER Apr,1991 Gr. A1pha 51.0 i 6.0 54.0114.0 29,7 - 78.3 Ra-226 7.0 1 0.8 8.0i 1.2 5.9 - 10.1
~
Ra-228 9.7i 1.9 15.213.8 8.6 - 21.8 U
27.7 i 2.4 29.8 i 3.0 24.6 - 35.0 STW-628 WATER Apr,1991 Cs-134 27.3 i 1.2 24.0 i 5.0 15.3 - 32.7 Cs-137 29.012.0 25.015.0 16.3 - 33.7 Gross Beta 93.3 i 6.4 115.0i l7.0 85.5 - 144.5 Sr-89 21.0 i 3.5 28.015.0 19.3 - 36.7 Sr-90 23.010.0 26.0 i 5.0 17.3 - 34.7 STM-629 MILK Apr,1991 Cs-137 54.7 i 11.0 49.015.0 40.3 - 57.7 I-131 65.3 i 14.7 60.0 i 6.0 49.6 - 70.4 K-40 1591.7 i 180.1 1650.0 i 83.0 1506.0 - 1794.0 Sr-89 24.0 i 8.7 32.0 i 5.0 23.3 - 40.7 Sr-90 28.0 i 2.0 32.0 i 5.0 23.3 - 40.7 STW-630 WATER May,1991 Sr-89 40.7 i 2.3 39.0 i 5.0 30.3 - 47.7 Sr-90 23.7 1.2 24.0 i 5.0 15.3 - 32.7 STW-631 WATER May,1991 Gr. Alpha 27.715.8 24.0 i 6.0 13.6 - 34.4 Gr. Beta 46.010.0 46.0 i 5.0 37.3 - 54.7 STW-632 WATER Jun,1991 Ba-133 74.016.9 62.0 6.0 51.6 - 72.4 Sample was reanalyzed for Ba-133. Result of the reanalysis was 63.816.9 pCi/L; within the EPA control limits.
Co-60 11.3 i 1.2 10.0 i 5.0 1.3 - 18.7 Cs-134 15.3 i 1.2 15.0 i 5.0 6.3 - 23.7 Cs-137 16.3 i 1.2 14.0 i 5.0 5.3 - 22.7 Ru-106 162.3 i 19.0 149.0 i 15.0 123.0 - 175.0 A1-5 l
Table A-1.
U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne's Midwest Laboratory results for various sample media'.
Concentration in pCi/L6 1
tab Sample Date Teledyne Results EPA Result Control d
Code Type Collected Analyses 12 Sigma
- 1s, N=1 Limits Zn-65 119.3 i 16.3 108.0 1 11.0 88.9 - 127.1 STW-633 WATER Jun,1991 H-3 13470.01 385.8 12480.0 i 1248.0 10314.8 - 14645.2 STW-634 WATER Jul,1991 I
Ra-226 14.9 i 0.4 15.912.4 11.7 - 20.1 Ra-228 17.6 i 1.8 16.7 i 4.2 9.4 - 24.0 STW-635 WATER Jul,1991 U
12.8 i 0.1 14.2 i 3.0 9.0 - 19.4 STW-636 WATER Aug,1991 1-131 19.311.2 20.016.0 9.6 - 30.4 STW-637 WATER Aug,1991 J
Pu-239 21.4 i 0.5 19.4 i 1.9 16.1 - 22.7 i
STAF-638 AIR FILTER Aug,1991 Cs-137 26.3 i 1.2 30.0 i 5.0 21.3 - 38.7 Gr. Alpha 33.0 i 2.0 25.0 i 6.0 14.6 - 35.4 i
Gr. Beta 88.7 i 1.2 92.0 i 10.0 80.4 - 103.6 Sr-90 27.0 i 4.0 30.0 i 5.0 21.3 - 38.7 STW-639 WATER Sep,1991 Sr-89 47.0 i 10.4 49.0 i 5.0 40.3.- 57.7 Sr-90 24.0 i 2.0 25.015.0 16.3 - 33.7 STW-640 WATER Sep,1991 Gr. Alpha 12.0 i 4.0 10.0 i 5.0 1.3 - 18.7 l
Gr. Beta 20.3 i 1.2 20.015.0 11.3 - 28.7 STM-641 MILK Sep,1991 Cs-137 33.713.2 30.0 i 5.0 21.3 - 38.7 I-131 130.7 i 16.8 108.0 i 11.0 88.9 - 127.1 The cause of the high result for the I-131 analysis is unknown.
An in-house spike sample was prepared with activity for 1131 of 68.316.8 pCi/L. Result of TIML's analysis of the in-house spike was 69.119.7 pCi/L K
1743.3 340.8 1740.0 i 87.0 1589.1 - 1890.9 Sr-89 20.315.0 25.0 i 5.0 16.3 - 33.7 Sr-90 19.7 i 3.1 25.015.0 16.3 - 33.7 STW-642 WATER Oct,1991 Ba-133 94.7 i 3.1 98.0110.0 80.7 - 115.3 Co-60 29.7 i 1.2 29.0 i 5.0 20.3 - 37.7 Cs-134 9.7i 1.2 10.015.0 1.3 - 18.7 Al-6
~
w
1 l
\\
4 Table A-1.
U.S. Environmental Protection Agency's cmsscheck program, cornparison of EPA and Teledyne's Midwest Laboratory results for various sample media *.
Concentration in pCi/L6 Lab Sample Date Teledyne Results EPA Resultd Control l
Code Type Collected Analyses 12 Sigma' is, N=1 Limits Cs-137 11.012.0 10.0 i 5.0 1.3-18.7 Ru-106 196.3 1 15.1 199.0 i 20.0 164.3 - 233.7 Zn-65 75.7 i 8.3 73.017.0 60.9 - 85.1 STW-643 WATER Oct,1991 H-3 2640.0 i 156.2 2454.0 1 352.0 1843.3 - 3064.7 STW-644 WATER Oct,1991 f
Gr. Alpha 73.0 13.1 82.0 i 21.0 45.6 - 118.4 Ra-226 20.9 i 2.0 22.0 i 3.3 16.3 - 27.7 Ra-228 19.6 i 2.3 22.2 i 5.6 12.5 - 31.9 U
13.510.6 13.513.0 8.3 - 18.7 STW-645 WATER Oct,1991 Co-60 20.311.2 20.015.0 11.3 - 28.7 Cs-134 9.0 i 5.3 10.0 i 5.0 1.3 - 18.7 Cs-137 14.7 i 5.0 11.0 i 5.0 2.3 - 19.7 Gross Beta 55.3 i 3.1 65.0110.0 47.7-82.3 Sr-89 9.7i 3.1 10.0 i 5.0 1.3-18.7 Sr-90 8.7i 1.2 10.0 i 5.0 1.3 - 18.7 STW-646 WATER Nov,1991 Ra-226 5.6 i 1.2 6.5 i 1.0 4.8 - 8.2 Ra-228 9.610.5 8.1 1 2.0 4.6 - 11.6 STW-647 WATER Nov,1991 U
24.7 i 2.3 24.9 i 3.0 19.7 - 30.1 STW-648 WATER Jan,1992 Sr-89 42.7i 6.4 51.0 i 5.0 42.3 - 59.7 Sr-90 18.3 i 3.1 20.015.0 11.3 - 28.7 STW-649 WATER Jan,1992 Pu-239 16.1 i 0.8 16.8 i 1.7 13.9 - 19.7 STW-650 WATER Jan,1992 Gr. Alpha 23.7 i 9.2 30.018.0 16.1 - 43.9 Gr. Deta 27.7 i 4.2 30.0 i 5.0 21.3 - 38.7 STW-651 WATER Feb,1992 I-131 60.314.2 59.0 i 6.0 48.6 - 69.4 STW-652 WATER Feb,1992 Ba-133 79.013.4 76.0 i 8.0 62.1 - 89.9 Co-60 40.3i 5.0 40.015.0 31.3 - 48.7 Cs-134 31.7 i 4.2 31.015.0 22.3 - 39.7 Al-7
l o
}
Table A-1.
U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyme's Midwest Laboratory results for various sample media'.
Concentration in pCi/L6 Lab Sample Date Teledyne Results EPA Resultd Control Code Type Collected Analyses 12 Sigma' is, N=1 Limits Cs-137 51.013.4 49.0 i 5.0 40.3 - 57.7 Ru-106 188.7 i 28.8 203.0 i 20.0 168.3 - 237.7 l
Zn-65 148.0 1 15.0 150.7 i 6.1 122.0 - 174.0 STW-653 WATER Feb,1992 H-3 7714.0 i 119.6 7904.0 i 790.0 6533.4 - 9274.6 STW-654 WATER Mar,1992 Ra-226 9.010.4 10.1 i 1.5 7.5-12.7 Ra-228 18.8 i 0.6 15.5 i 3.9 8.7 - 22.3 STW-655 WATER Mar,1992 Rn-222 0.0 No Data; Special EPA testing.
STW-656 WATER Mar,1992 l
U 25.111.9 25.313.0 20.1 - 30.5 STW-657 WATER Mar,1992 Rn-222 No Data is available; Special EPA testing.
STAF-658 AIR FILTER Mar,1992 Cs-137 10.0 i 0.0 10.015.0 1.3 - 18.7 Gr. Alpha 7.0i 0.0 7.0 5.0 0.0 - 15.7 Gr. Beta 39.3 i 1.6 41.0 i 5.0 32.3 - 49.7 Sr-90 13.7 i 1.6 15.015.0 6.3 - 23.7 STW-659 WATER Apr,1992 Cr. Alpha 35.7 i 6.1 40.0 i 10.0 22.7 - 57.3 Ra-226 12.711.2 14.9 2.2 11.1 - 18.7 l
Ra-228 14.5 i 2.1 14.013.5 7.9 - 20.;
j U
3.9 i 0.2 4.0i 3.0 0.0 - 9.2 l
STW-660 WATER Apr,1992 Co-60 61.014.0 56.0 i 5.0 47.3 - 64.7 Cs-1M 24.3 i 1.2 24.015.0 15.3 - 32.7 Cs-137 24.0 i 2.0 22.015.0 13.3 - 30.7 Gross Beta 113.0 i 7.2 140.0 1 21.0 103.6 - 176.4 j
Sr-89 12.3 4.2 15.0 i 5.0 6.3 - 23.7 l
Sr-90 15.0 i 1.2 17.0 i 5.0 8.3 - 25.7 STM-661 MILK Apr,1992 Cs-137 39.3 i 2.3 39.0 i 5.0 30.3 - 47.7 I-131 78.7 i 9.5 78.0 i 8.0 64.1 - 91.9 Al-8
1 I
Table A-1.
U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne's Midwest Laboratory results for various sample media'.
Concentration in pCi/L6 Lab Sample Date Tcledyne Results EPA Resultd Control Code Type Collected Analyses 12 Sigma' 1s, N=1 Limits K-40 1610.0 1 72.1 1710.0 1 86.0 1560.8 - 1859.2 Sr-89 25.3 i 7.6 38.0 i 5.0 29.3 - 46.7 The cause of the low Sr-89 results is unknown. Data were checked for errors. An in-house spike sample was prepared with activity for Sr-89 of 41.0110.0 - Ci/L. Result of the analysis of the in-house spike sample for Sr-89 was 37.213.6 pCi/L Sr-90 24.3 i 3.1 29.0 i 5.0 20.3 - 37.7 STW-662 WATER May,1992 Sr-89 24.014.0 29.015.0 20.3 - 37.7 Sr-90 6.7i 1.2 8.0 i 5.0 0.0 - 16.7 STW-663 WATER May,1992 Gr. Alpha 12.3 i 2.1 15.015.0 6.3 - 23.7 Gr. Beta 46.015.0 44.015.0 35.3 - 52.7 STW-664 WATER Jun,1992 Ba-133 92.7111.0 98.0110.0 80.7 - 115.3 Co-60 20.311.2 20.015.0 11.3 - 28.7 Cs-134 14.3 i 2.3 15.015.0 6.3 - 23.7 Cs-137 15.0 i 2.0 15.0 i 5.0 6.3 - 23.7 Ru-106 142.7 i 23.7 141.0 i 14.0 116.7 - 165.3 Zn-65 103.3 i 10.6 99.0110.0 81.7 - 116.3 STW-665 WATER Jun,1992 H-3 2153.3 1 144.6 2125.0 1 347.0 1523.0 - 2727.0 STW-666 WATER Jul,1992 Ra-226 22.3 i 2.2 24.913.7 18.5 - 31.3 Ra-228 16.713.1 16.714.2 9.4 - 24.0 STW-667 WATER Jul,1992
{
Uranium 3.6 i 0.3 4.013.0 0.0 - 9.2 STW-668 WATER
' Aug,1992 1-131 47.0i 3.5 45.0 i 6.0 34.6 - 55.4 STW-669 WATER Aug,1992 Pu-239 8.5 i 0.9 9.0 1 0.9 7.4 - 10.6 STAF-670 AIR FILTER Aug,1992 A1pha 25.7 i 1.2 30.0 i 8.0 16.1 - 43.9 Beta 69.0 i 2.0 69.0 i 10.0 51.7 - 86.3 Cs-137 16.010.0 18.015.0 9.3 - 26.7 Sr-90 26.014.0 25015.0 16.3 - 33.7 j
Al-9
)
d i
i Table A-1.
U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne's Midwest Laboratory results for various sample media'.
j l
Concentration in pCi/L6 Lab Sample Date Yeledyne Results EPA Resultd Control Code Type Collected Analyses 12 Sigma' 1s, N=1 Limits STW-671 WATER Sep,1992 Sr-89 16.0 i 4.0 20.0 i 5.0 11.3 - 28.7 St-90 14.3 i 3.1 15.0 i 5.0 6.3 - 23.7 STW-672 WATER Sep,1992 A1pha 43.0 i 13.1 45.0 i 11.0 25.9 - 64.1 Beta 41.3 i 18.6 50.0 i 5.0 14.3 - 58.7 STM-673 MILK Sep,1992 Cs-137 14.0 i 3.5 15.0 i 5.0 6.3 - 23.7 I-131(gamma 109.7 i 19.4 100.0 i 10.0 82. -.117.3 K
1540.0 i 103.9 1750.0 i 88.0 1597.3 - 1902.7
'Ihe K activity was calculated using the wrong volume (3.5 L),
instead of 3.25 L. Correction for volume resulted in a value of 1660.01110.1; within EPA control limits.
Sr-89 11.0 i 3.5 15.0 i 5.0 6.3 - 23.7 Sr-90 12.7 i 1.6 15.015.0 6.3 - 23.7 STW-674 WATER Oct,1992 i
Ba-133 80.3 i 9.0 74.017.0 61.9 - 86.1 i
Co-60 11.3 i 2.3 10.015.0 1.3 - 18.7 Cs-134 9.7 i 2.3 8.015.0 0.0 - 16.7 Cs-137 9.7i 1.2 8.0i 5.0 0.0 - 16.7 Ru-106 170.7 i 2.3 175.0 1 18.0 143.8 - 206.2 Zn-65 169.7 i 25.0 148.0 1 15.0 122.0 - 174.0 STW-675 WATER Oct,1992 H-3 5896.7 i 136.2 5962.0 1 596.0 - 4928.0 - 6996.0 STW-676 WATER Oct,1992 Gr. Alpha 24.715.0 29.0 i 7.0 16.9 - 41.1 Ra-226 7.1 i 0.4 7.411.1 5.5 - 9.3 Ra-228 11.5 i 1.0 10.0 i 2.5 5.7 - 14.3 Uranium 9.710.5 10.2 i 3.0 5.0 - 15.4 STW-677 WATER Oct,1992 li Co 15.012.0 15.015.0 6.3 - 23.7 Cs-134 5.7i 1.2 5.015.0 0.0 - 13.7 Cs-137 8.012.0 8.0 i 5.0 0.0 - 16.7 Gr. Beta 12.7 i 8.1 53.0110.0 35.7 - 70.3 Sr-89 6.7 1.2 8.0 i 5.0 0.0 - 16.7 Sr-90 10.0 i 2.0 110.0 i 5.0 1.3 - 18.7 A1-10
4 Table A-1.
U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne's Midwest Laboratory results for various sample media'.
Concentration in pCi/L' Lab Sample Date Teledyne Results EPA Result Control d
Code Type Collected Analyses i2 Sigma' 1s, N=1 Limits i
STW-678 WATER Oct,1992 Ra-226 7.5 i 0.8 7.5i1.1 5.6 - 9.4 l
Ra-228 5.8 i 0.7 5.0 i 1.3 2.7 - 7.3 STW-679 WATER Nov,1992 Uranium 15.5 i 1.1 15.2 i 3.3 10.0 - 20.4 STW-680 WATER Jan,1993 Sr-89 15.0 i 2.0 15.0 i 5.0 6.3 - 23.7 Sr-90 10.3 i 1.2 10.0 i 5.0 1.3 - 18.7 STW-681 WATER Jan,1993 Pu-239 17.5 i 1.6 20.0 i 2.0 16.5 - 23.5 STW-682 WATER Jan,1993 AIpha 17.1 i 1.2 34.019.0 18.4 - 49.6 Cross Alpha analysis was repeated with similar results. An investigation of possible causes for the deviation from the EPA was conducted with no cause discovered. 'ihe sample was spiked with Th-230; so Alpha Spec Analysis for Th-230 was performed i
in triplicate with results of 15.512.1,13.4fl.4, and 14.8f2.0. It should be noted that 66% of all participants failed this analysis with a grand average of 17.1. This coupled with the support of the Alpha Spec results leaves TIML cause to believe that there may have been 'a dilution error at the EPA. It should be noted that on the next Gross Alpha EPA check, TIML reported results that where exactly the known value. Since no apparent cause can be found, and TIML had outstanding results on the
)
following sample, it is felt that no further investigation is needed.
Beta 46.7i 3.2 44.0 i 5.0 35.3 - 52.7 STW-683 WATER Feb,1993 1-131 106.0 i 10.0 100.0 i 10.0 82.7 - 117.3 STW-684 WATER Feb,1993 j
Uraniurn 7.2 i 0.5 7.6i3.0 2.4 - 12.8 STW-685 WATER Mar,1993 Ra-226 9.3il.3 9.8 i 1.5 7.2-12.4 Ra-228 20.822.2 18.5 i 4.6 10.5 - 26.5 STW-686 WATER Apr,1993 A1pha 88.318.1 95.0124.0 53.4 - 136.6 Ra-226 25.411.4 24.913.7 18.5 - 31.3 Ra-228 17.411.2 19.014.8 10.7 - 27.3 Al-11
.~.
~
-=
Table A-1.
U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne's Midwest Laboratory resuits for various sample media *.
Concentration in pCi/L6 Lab Sample Date Teledyne Results EPA Resultd Control Code Type Collected Analyses i2 Sigma' Is, N=1 Limits Uranium 27.812.2 28.9 i 3.0 23.7 - 34.1 STW-687 WATER Apr,1993 Beta 141.7 i 9.0 177.01 27.0 130.2 - 223.8 Co-60 41.3 i 1.2 39.0 i 5.0 30.3 - 47.7 Cs-134 24.711.2 27.015.0 18.3 - 35.7 Cs-137 30.0 i 0.0 32.0 i 5.0 23.3 - 40.7 Sr-89 28.7 i 9.4 41.015.0 32.3 - 49.7 The EPA report was received 08-16-93. No cause for the low result for Sr-89 was found. The analyst has been observed performing this procedure with no noted descrepancies.
Teledyne will continue to monitor this procedure in the future.
No further action is anticipated unless conditions warrant.
Sr-90 28.0 i 3.5 29.0 t 5.0 20.3 - 37.7 STW-688 WATER Jun,1993 H-3 9613.'s i 46.2 9844.0 i 984.0 8136.8 - 11551.2 STW-689 WATER Jun,1995 Ba-133 101.7 i 10.3 99.0 i 10.0 81.7 - 116.3 Co-60 17.314.6 15.0 i 5.0 6.3 - 23.7 Cs-134 5.7i 1.2 5.0 i 5.0 0.0 - 13.7 Cs-137 6.012.0 5.0 i 5.0 0.0 - 13.7 t
Ru-106 108.0 i 8.0 119.0 i 12.0 98.2 - 139.8 72 65 114.0 i 13.2 103.0 i 10.0 85.7 - 120.3 STW-690 WATER Jul,1993 Sr-89 28.312.3 34.015.0 25.3 - 42.7 Sr-90 25.0 i 1.0 25.0 i 5.0 16.3 - 33.7 STW-691 WATER Jul,1993 AIpha 15.0 i 2.7 15.0 i 5.0 6.3 - 23.7 Beta 41.3 i 4.9 43.016.9 31.0 - 55.0 STW-692 WATER Aug,1993 Uranium 24.9 i 1.4 25.3 i 3.0 20.1 - 30.5 STAF-693 AIR FILTER Aug,1993 A1pha 17.011.0 19.0 i 5.0 10.3 - 27.7 Beta 47.3 i 0.6 47.0 i 5.0 38.3 - 55.7 Cs-137 10.0 i 1.0 9.0 i 5.0 0.3 - 17.7 Sr-90 19.310.6 19.0 i 5.0 10.3 - 27.7 STW-694 WATER Sep,1993 Ra-226 15.9 i 0.7 14.912.2 11.1 - 18.7 A1-12
4 j
4 Table A-1.
U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne's Midwest Laboratory results for various sample media *.
6 4
Concentrationin pCi/L
)
Lab Sample Date Teledyne Results EPA Resultd Control j
j Code Type Collected Analyses i2 Sigma' 1s, N=1 Limits j
Ra-228 21.0 i 1.6 l
20.415.1 11.6 - 29.2 STM-695 MILK Sep,1993 Cs-137 49.0 i 3.0 49.0 i 5.0 40.3 - 57.7 1-131 125.314.5 120.0 i 12.0 99.2 - 140.8 K
1616.7i 37.9 1679.0 i 84.0 1533.3 - 1824.7 e
Sr-89 19.3 i 1.5 30.0 i 5.0 21.3 - 38.7 Report was received 01-18-94; an investigation is underway as to j
the cause of the low Sr-89 result:;. In-house spikes have been prepared and the analysis is in progress (see SPM-4848 and SPM-4849 in future reports). There is no apparent cause of the low Sr-89 results. In-house spikes have been prepared and the analysis is in progress. The analyst has been observed performing this procedure with no discrepancies noted. No further action is planned unless the results of the in-house spikes show a problem.
Sr-90 22.010.0 25.0 i 5.0 16.3 - 33.7 STW-696 WATER Oct,1993 I-131 116.7 i 2.3 117.0 i 12.0 96.2 - 137.8 STW-697 WATER Oct,1993 Gr. Alpha 39.711.5 40.0 i 10.0 22.7 - 57.3 Ra-226 10.6 i 0.5 9.9i 1.5 7.3 - 12.5 Ra 228
~ 13.2 i 1.5 12.5 i 3.1 7.1-17.9 Uranium 15.310.6 15.li 3.0 9.9 - 20.3 STW-698 WATER Oct,1993 Beta 52.0 i 1.0 58.0 i 10.0 40.7 - 75.3 Co-60 10.710.6 10.015.0 1.3 - 18.7 Cs-134 10.0 i 1.0 12.015.0 3.3 - 20.7 Cs-137 12.3 i 1.2 10.015.0 1.3 - 18.7 Sr-89 11.310.6 15.0 i 5.0 6.3 - 23.7 Sr-90 11.0 i 0.0 10.0 i 5.0 1.3 - 18.7 STW-699 WATER Oct,1993 A1pha 18.3 i 2.5 20.0 i 5.0 11.3 - 28.7 Beta 13.7 i 0.6 15.015.0 6.3 - 23.7 STW-700 WATER Nov,1993 H-3 7310.0 i 175.2 7398.0 i 740.0 6114.1 - 8681.9 STW-701 WATER Nov,1993 Da 133 75.7 i 7.6 79.0 i 8.0 65.1 - 92.9 Co-60 30.7 i 2.1 30.0 i 5.0 21.3 - 38.7 A1-13
i l
Table A-1.
U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne's Midwest Laboratory results for various sample media'.
Concentration in pCi/L6 Lab Sample Date Teledyne Results EPA Result Control d
Code Type Collected Analyses i2 Sigma' 1s, N=1 Limits Cs-134 51.315.9 59.015.0 50.3 - 67.7 f
Cs-137 41.7 i 1.2 40.015.0 31.3 - 49.7 Ru-106 163.3 i 3.2 201.0 1 20.0 166.3 - 235.7 The report was received on 02-14-94; the cause of the low Ru-106 is under investigation. It should be noted that the grand average of all participants in this analysis was 175.2 pCi/L, with 54%
of the participants outside of limits.
Zn-65 157.018.7 150.0 1 15.0 124.0 - 176.0
- Results obtained by Teledyne Brown Engineering Environmental Services 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, Neveda.
6 All results are in pCi/L, except for elemental potassium (K) data in milk, which are in mg/L; air filter I
samples, which are in pCi/ Filter.
Unless otherwise indicated, the TBEESML results are given as the mean i 2 standard deviations for three determinations.
i d USEPA results are presented as the known values and expected laboratory precision (1s,1 determination) and control limits as defined by the EPA.
l l
l 1
i l
l Al-14 l
1 i
Table A-2. Crosscheck program results; Thermoluminescent Dosimeters. (TLDs),
mR Lab Teledyne Results Known Average i 2 Sigma Code TLD Type Date Measurement i 2 Sigma Value i 2 Sigma (All Participants) 2nd Intemational Intercomoarison 115-2 CaF,: Mn Bulb Apr,1976 FieId 17.0 i 1.9 17.1 16.4 i 7.7 Lab 20.814.1 21.3 18.817.6 Second International Intercomparison of Environmental Dosimeters conducted in April of 1976 by the Health j
and Safety Laboratory (HASL), New York, New York, and the School of Public Health of the University of Texas, Houston, Texas.
l 3rd International Intercomnarison 115-3 CaF : Mn Bulb Jun,1977 2
FieId 30.7 i 3.2 34.9 i 4.8 31.5 i 3.0 Lab 89.616.4 91.7114.6 86.2 i 24.0 Third International Intercomparison of Environmental Dosimeters conducted in the stunmer of 1997 by Oak Ridge National Laboratory and the School of Public Health of the University of Texas, Houston, Texas.
l 4th Intemational Intercomparison l
115-4 CaF : Mn Bulb Jun,1979 2
Field 14.111.1 14.111.4 16.019.0 Lab, High 40.4 i 1.4 45.819.2 43.9113.2 Lab, Low 9.8 i 1.3 12.2 2.4 12.0 i 7.4 Fourth Intemational Intercomparison of Environmental Dosimeters conducted in the summer of 1979 by the School of Public Health of the University of Texas, Houston, Texas.
5th International Intercomoarison 115-5A CaF,: Mn Bulb Oct,1980 FieId 31.4 i 1.8 30.0 i 6.0 30.2114.6 Lab,End 96.6 i 5.8 88.4 i 8.8 90.7131.2 Lab, Start 77.4 i 5.8 75.2 7.6 75.8140.4 115-5B LiF-100 Chips Oct,1980 FieId 30.3 i 4.8 30.0 i 6.0 30.2 i 14.6 12b, End 85.4111.7 88.4 i 8.8 90.7 i 31.2 Lab, Start 81.1 i 7.4 75.217.6 75.8 i 40.4 Fifth Intemational Intercomparison of Environmental Dosimeters conducted in the 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.
l Ztitlniemational Interrompalisnn 115-7A LiF-100 Chips Jun,1984 FieId 75.412.6 75.8 i 6.0 75.1 29.8 A2-1
l i
Table A-2. Crosscheck program results; Thermoluminescent Dosimeters. (TLDs).
mR Lab Tcledyne Results Known Average i2 Sigma Code TLD Type Date Measurement i 2 Sigma Value 12 Sigma (All Participants)
Lab, Co-60 80.013.5 79.9 i 4.0 77.9 i 27.6 Lab, Cs-137 66.612.5 75.0 i 3.8 73.0f 22.2 115-7B CaF,: Mn Bulb Jun,1984 l
FieId 71.512.6 75.8 i 6.0 75.1 29.8 Lab, Co-60 84.8 i 6.4 79.9 i 4.0 77.9127.6 i
Lab, Cs-137 78.811.6 75.0 i 3.8 73.0f 22.2 115-7C CaSO :Dy Jun,1984 Cards Fie1d 76.812.7 75.8 i 6.0 75.1 i 29.8 Lab, Co-60 82.513.7 79.9 i 4.0 77.9 i 27.6 1
Lab, Cs-137 79.0 i 3.2 75.013.8 73.0122.2 Seventh International Intercomparison of Environmental Dosimeters conducted in the spring and sununer of 1984 at Las Vegas, Neveda, and sponsored by the U.S. Department of Energy, The Nuclear Regulatory j
Commission, and the U.S. Environmental Frotection Agency. Teledyne did not participate in the Sixth i
InternationalIntercomparison of Environmental Dosimeters.
8th International Intercomparison 115-8A LiF-100 Chips Jan,1986 Field, Site 1 29.5 i 1.4 29.711.5 28.9 i 12.4 Field, Site 2 11.3 i 0.8 10.4 0.5 10.119.1 Lab, Cs-137 13.7 i 0.9 17.210.9 16.2 i 6.8 115-8B CaF : Mn Bulb Jan,1986 2
Field, Site 1 32.3 i 1.2 29.7 i 1.5 28.9112.4 FieId, Site 2 9.0 i 1.0 10.410.5 10.1-9.0 i
Lab, Cs-137 15.8 i 0.9 17.210.9 16.216.8 115-8C CaSO,:Dy Jan,1986 Cards Field, Site 1 32.2 0.7 29.7 i l.5 28.9i l2.4 Field, Site 2 10.6 i 0.6 10.4
- 0.5 10.119.0 Lab, Cs-137 18.1 i 0.8 17.2 0.9 16.216.8 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.
10th International intercompadsn A2-2
4 i
Table A-2. Crosscheck program results;1hermoluminescent Dosimeters. (TLDs).
mR Lab Teledyne Results Known Average i2 Sigma Code TLD Type Date Measurement i 2 Sigma Valuei 2 Sigma (All Participants) 115-10A LiF-100 Chips Aug,1993 Field 25.7i l.4 27.0i l.6 26.4110.2 Lab 22.711.6 25.9 i 1.3 25.0 i 9.4 Lab 62.712.6 72.7 i 1.9 69.8 i 20.3 115-10B CaSO.:Dy Aug,1993 Cards Fie1d 26.0 i 2.3 27.0 i 1.6 26.4 i 10.2 Lab 24.1 i 1.7 25.9 i 1.3 25.0 i 9.4 Lab 69.2 i 3.0 72.7 i 1.9 69.8 i 20.3 Tenth International Intercomparison of Environmental Dosimeters conducted in 1993 at Idaho State University and sponsored by the U.S. Department of Energy and the Idaho State University. The Ninth International Intercomparison of Environmental Dosimeters was not available to Teledyne's Midwest Laboratory.
Ieledvne Testing j
89-1 LiF-100 Chips Sep,1989 Lab 21.0 i 0.4 22.4 ND ND = No Data; Teledyne Testing was only performed by Teledyne.
Chips were irradiated by Teledyne Isotopes,Inc., Westwood NJ. in September,1989 89-2 Tcledyne Nov,1989 CaSO.:Dy Cards Lab 20.9 i 1.0 20.3 ND ND = No Data; Tcledyne Testing was only performed by Teledyne.
Cards were irradiated by Teledyne Isotopes, Inc., Westwood NJ. in November,1989.
90-1 Teledyne Jun,1990 CaSO :Dy Cards Lab 20.6 i 1.4 19.6 ND ND = No Data; Teledyne Testing was only performed by Teledyne.
Cards were irradiated by Teledyne Isotopes, Inc., Westwood NJ. on June 19,1990.
90-2 Teledyne Sep,1990 CaSO :Dy Cards Lab 200.8 i 4.3 100.0 ND ND = No Data; Teledyne Testing was only performed by Teledyne.
Cards were irradiated by Dosimetry Associates, Inc., Northville, MI on October 30,1990.
A2-3
Table A-2. Crosscheck program results;Thermoluminescent Dosimeters. (TLDs).
mR Lab Teledyne Results Known Average 12 Sigma Code TLD Type Date Measurement i 2 Sigma Value i 2 Sigma (All Participants) 91-1 Teledyne Oct,1990 CaSO :Dy 4
Cards lab 1 33.4 2.0 32.0 ND Lab 2 55.2i 4.7 58.8 ND Lab 3 87.8i 6.2 85.5 ND ND = No Data; Teledyne Testing was only performed by Teledyne.
Cards were irradiated by Tcledyne Isotopes, Inc., Westwood NJ. on October 8,1991.
92-1 LiF-100 Chips Feb,1992 12b 1 11.1 i 0 2 10.7 ND Lab 2 25.6 i 0.5 25.4 ND Lab 3 46.4i 0.5 46.3 ND ND = No Data; Teledyne Testing was only performed by Teledyne.
Chips were irradiated by Tcledyne Isotopes, Inc., Westwood NJ. on February 26,1992.
92-2 Teledyne Apr,1992 CaSO.:Dy Cards Reader 1, #1 20.110.1 20.1 ND Reader 1, #2 40.6i 0.1 40.0 ND Reader 1, #3 60.0 i 1.3 60.3,
ND Reader 2, #1 20.310.3 20.1 ND Reader 2, #2 39.210.3 40.0 ND Reader 2, #3 60.7 i 0.4 60.3 ND ND = No Data; Teledyne Testing was only performed by Teledyne.
Cards were irradiated by Teledyne Isotopes, Inc., Westwood NJ. on April 1,1992.
93-1 Teledyne Mar,1993 LiF-100 Chips lab 1 10.0 i 1.0 10.2 ND 12b2 25.512.2 25.5 ND 12b3 42.715.7 45.9 ND ND = No Data; Teledyne Testing was only performed by Teledyne.
Cards and Chips were irradiated by Teledyne Isotopes,Inc., Westwood NJ. on March 10,1993. Due to a potential error of 10-12% when cards where irradiated, results of the testing on the cards will not be published. Data is available upon request.
A2-4
Table A-3. In-house " spike" samples.
Concentration in pCi/U Lab Sample Date Tcledyne Results Known Control' Code Type Collected Analyses 2s, n=16 Activity Limits QCMI-26 MILK Jan,1990 Cs-134 19.3 i 1.0 20.8 10.8 - 30.8 Cs-137 25.211.2 22.8 12.8 - 32.8 QCMI-27 MILK Feb,1990 Sr-90 18.011.6 18.8 8.8 - 28.8 QCMI-28 MILK Mar,1990 1-131 63.8 i 2.2 62.6 50.1 - 75.1 QCMI-29 MILK Apr,1990 Cs-134 18.3 i 1.0 19.7 9.7 - 29.7 Cs-137 20.3 i 1.0 18.2 8.2 - 28.2 I-131 90.7 i 9.2 82.5 66.0 - 99.0 QCW-61 WATER Apr,1990 Sr-89 17.915.5 23.1 13.1 - 33.1 St-90 19.4 i 2.5 23.5 13.5 - 33.5 QCW-62 WATER Apr,1990 Co-60 8.7i 0.4 9.4 0.0 - 19.4 Cs-134 20.010.2 19.7 9.7 - 29.7 Cs-137 28.711.4 22.7 12.7 - 32.7 QCW-63 WATER Apr,1990 1131 63.5 i 8.0 66.0 52.8 - 79.2 QCW-64 WATER Apr,1990 1-I-3 1941.0 1 130.0 1826.0 1141.5 - 2510.5 QCW-65 WATER Jun,1990 Ra-226 6.410.2 6.9 4.8 - 9.0 QCW-66 WATER Jun,1990 I
Uranium 6.2 i 0.2 6.0 3.6 - 8.4 QCMI-30 MILK Jul,1990 Cs-134 46.0 i 1.3 49.0 39.0 - 59.0 Cs-137 27.6 i 1.3 25.3 15.3 - 35.3 Sr-89 12.8 i 0.4 18.4 8.4 - 28.4 Sr 90 18.2 i 1.4 18.7 8.7 - 28.7 QCW-68 WATER Jul,1990 Gr. A1pha 9.8 i 0.3 10.6 0.6 - 20.6 Gr. Deta 11.410.6 11.3 1.3 - 21.3 QCMI-31 MILK Aug,1990 1-131 68.8 i 1.6 61.4 49.1 - 73.7 A3-1
l Table A-3. In-house " spike" samples, l
Concentration in pCi/L' l
Lab Sample Date Teledyne Results Known Control' Code Type Collected Analyses 2s, n=16 Activity Limits QCW-69 WATER Sep,1990 l
Sr-89 17.7 i 1.6 19.2 9.2 - 29.2 St-90 13.9 i 1.6 17.4 7.4 27.4 l
QC Mi-32 MILK Oct,1990 Cs 134 25.811.2 27.3 17.3 - 37.3 Cs-137 25.312.0 22.4 12,4 32.4 I-131 a4.8 i 0.2 32.4 20.4 - 44.4 QCW-70 WATER Oct,1990 l
H-3 2355.0 1 59.0 2276.0 1577.3 - 2974.7 QCW-71 WATER Oct,1990 1-131 55.9 i 0.9 51.8 39.8 - 63.8 QCW-73 WATER Oct,1990 Co-60 18.312.7 16.8 6.8 - 26.8 Cs-134 28.3 i 2.3 27.0 17.0 - 37.0 Cs-137 22.7 i 1.3 22.4 12.4 - 32.4 QCW-74 WATER Dec,1990 Gr. Alpha 21.411.0 26.1 13.1 - 39.2 Gr. Beta 25.911.0 22.3 12.3 - 32.3 QCMI-33 MILK Jan,1991 Cs-134 22.2 1.7 19.6 9.6 29.6 Cs-137 26.111.6 22.3 12.3 32.3 Sr-89 20.713.3 21.6 11.6 - 31.6 Sr-90 19.0 i 1.4 23.0 13.0 - 33.0 l
QCMI-34 Mitk Feb,1991 QCW-75 WATER Mar,1991 Sr-89 18.8 1.5 23.3 13.3 - 33.3 St-90 16.0 i 0.8 17.2 7.2 - 27.2 QCMI-35 MILK Apr,1991 Cs-134 19.2 i 2.0 22.6 12.6 - 32.6 Cs-137 22.812.2 22.1 12.1 32.1 1-131 48.0 i 0.8 49.2 37.2 61.2 QCW-76 WATER Apt,1991 1-131 56.5 i 1.7 59.0 47.2 - 70.8 QCW-77 WATER Apt,1991 Co-60 16.4 i 2.2 15.7 5.7 - 25.7 A3-2
l r
4 Table A-3. In house " spike" samples.
i I
\\
l Concentration in pCi/L' Lab Sample Date Tcledyne Results Known Control' Code Type Collected Analyses 2s, n=1' Activity Limits Cs-134 23.812.5 22.6 12.6 - 32.6 Cs-137 25.0 i 2.4 21.1 11.1 - 31.1 f
QCW-78 WATER Apr,1991 H-3 4027.0 i 188.0 4080.0 3264.0 - 4896.0 QCW.79 WATER Jun,1991 Gr. A1pha 7.410.7 7.8 0.0 - 17.8 Gr. Deta 11.0i 0.7 11.0 1.0 - 21.0 SPM-36 MILK Jul,1991 Cs-137 34.313.0 35.1 25.1 - 45.1 1-131 14.411.9 18.3 6.3 - 30.3 Sr-89 28.1 i 2.1 34.0 24.0 - 44.0 Sr-90 11.6 i 0.7 11.5 1.5 - 21.5 QCMI-37 MILK Oct,1991 Cs-134 22.712.8 22.1 12.1 - 32.1 Cs-137 38.3 i 3.0 35.1 25.1 - 45.1 1131 23.6 i 3.2 25.8 13.8 - 37.8 QCW-80 WATER Oct,1991 Sr-89 27.4 i 6.9 24.4 14.4 - 34.4 Sr-90 11.7 i 1.4 14.1 4.1 - 24,1 QCW-81 WATER Oct,1991 1-131 19.1 i 0.7 20.6 8.6 - 32.6 QCW-82 WATER Oct,1991 Co-60 22.612.7 22.1 12.1 - 32.1 Cs-134 15.5 i 1.8 17.6 7.6 - 27.6 Cs-137 17.5 i 2.1 17.6 7.6 - 27'6 QCW-83 WATER Oct,1991 H-3 4639.0 i 137.0 4382.0 3505.6 - 5258.4 QCW-84 WATER Dec,1991 Gr. Alpha 6.2 1 6.0 7.8 0.0 - 17.8 Gr. Deta 11.0 i 0.7 11.0 1.0 - 21.0 QCMI-39 MILK Jan,1992 Cs-134 42.1 i 5.7 49.4 39.4 - 59.4 Cs-137 55.2 i 6.4 53.0 43.0 - 63.0 I-131 76.810.9 83.7 67.0 - 100.4 Sr-89 21.616.5 31.2 21.2 - 41.2 Sr-90 38.7 i 1.8 42.3 33.8 - 50.8 A3-3
Table A 3. In-house " spike" samples.
Concentration in pCi/U Lab Sample Date Teledyne Results Known Controf Code Type Collected Analyses 2s, n=16 Activity Limits QCW-85 WATER Mar,1992 Sr-89 26.213.1 32.0 22.0 - 42.0 Sr-90 24.4 i 1.4 28.0 18.0 - 38.0 QCMI-40 MILK Apr.1992 Cs-134 58.012.6 55.9 45.9 - 65.9 Cs-137 43.713.0 38.9 28.9 - 48.9 QCMI-41 MILK Apr,1992 I-131 50.310.8 55.9 44.7 - 67.1 QCW-86 WATER Apr,1992 11-3 4080.0 1 190.0 4027.0 3221.6 - 4832.4 QCW-87 WATER Apr,1992 1-131 33.510.6 33.2 21.2 - 45.2 QCW-88 WATER Apr,1992 Co-60 17.5 i 2.7 19.7 9.7 - 29.7 Cs-134 28.912.5 33.5 23.5 - 43.5 Cs-137 41.0 i 3.0 38.9 28.9 - 48.9 QCW-89 WATER Jun,1992 Gr. Alpha 15.3 i 0.8 13.6 3.6 - 23.6 Gr. Beta 17.2 i 0.9 17.6 7.6 - 27.6 QCMI-42 MILK Aug,1992 Cs-134 20.112.8 20.2 10.2 - 30.2 Cs-137 26.212.7 26.1 16.1 - 36.1 Sr-89 41.4 i 5.9 51.2 41.0 - 61.4 Sr-90 48.9 i 2.5 51.9 41.5 - 62.3 QCW-90 WATER Sep,1992 Sr-89 6.7i 3.4 12.6 2.6 - 22.6 Sr-90 16.1 i 1.4 15.6 5.6 - 25.6 QCMI-43 MILK Oct,1992 Cs-134 14.213.4 12.7 2.7 - 22.7 Cs-137 14.1 i 5.2 17.1 7.1 - 27.1
{
I-131 19.9 i 1.0 21.5 9.5 - 33.5
)
QCMI-44 MILK Oct,1992 i
Cs-134 28.2 i 4.0 25.4 15.4 - 35.4 Cs-137 38.8 i 5.1 34.2 24.2 - 44.2 I-131 36.1 i 1.2 43.0 31.0 - 55.0 A3-4 i
l l
l e
Table A-3. In-house " spike" samples.
Concentrationin pCi/U 1
Lab Sample Date Teledyne Results Known Control Code Type Collected Analyses 2s, n=1 Activity Limits i
b QCW-91 WATER Oct,1992 I-131 34.9 i 2.2 34.9 22.9 - 46.9
)
QCW-92 WATER Oct,1992 Co-60 11.4 i 1.9 9.2 0.0 - 19.2 l
Cs-134 18.7 i 2.3 14.3 4.3 24.3 Cs-137 14.1 i 1.8 15.0 5.0 - 25.0 I
l QCW-93 WATER Oct,1992 11-3 3704.0 1 186.0 3904.0 3169.2 - 4638.8 QCW-94 WATER Oct,1992 H-3 14925.0 i 339.0 15616.0 12492.8 - 18739.2 l
l QCW-95 WATER Oct,1992 1-131 64.2 i 2.7 67.2 53.8 - 80.6 QCW-36 WATER Dec,1992 A1pha 11.5 i 2.3 15.2 9.1 - 21.3 Beta 26.5 i 2.0 25.7 15.4 - 36.0 l
QCW-96 WATEP.
Dec,1992 Gr. Alpha 8.3 0.6 10.4 0.4 - 20.4 Gr. Deta 19.8 i 1.5 20.6 10.6 - 30.6 SPM-3341 MILK Jan,1993 Cs-134 17.1 i 2.0 21.3 11.3 - 31.3 Cs-137 21.4 i 2.0 23.8 13.8 - 33.8 Sr-89 6.7i 3.1 8.7 0.0 - 18.7 Sr-90 20.0 i 1.2 19.2 9.2 - 29.2 SPM-3387 MILK Feb,1993 I-131 72.5 i 8.4 71.5 57.2 - 85.8 i
SPVE-3401 VEGETATION Feb,1993 (SAW DUST) 1-131 994.5 1 53.2 953.7 763.0 - 1144.4 SPCli-3402 CilARCOAL Feb,1993 I-131 95.2 i 12.8 95.4 76.3 - 114.5 SPW-3434 WATER Apr,1993 Gr. Alpha 10.4 i 1.8 10.4 0.4 - 20.4 Gr. Deta 22.012.0 20.6 10.6 - 30.6 SPW-3556 WATER Apr,1993 Sr-89 18.2i 5.0 22.2 12.2 - 32.2 Sr-90 20.111.8 17.0 7.0 - 27.0 A3-5
1 i
Table A-3. In-house " spike" samples.
Concentration in pCi/L' Lab Sample Date Teledyne Results Known Control' 6
Code Type Collected Analyses 2s, n=1 Activity Lirnits SPW-3597 WATER Apr,1993 H-3 5464.0 i 219.0 5428.0 4342.4 - 6513.6 SPW-3599 WATER Apr,1993 1-131 149.8 i 1.9 145.0 116.0 - 174.0 SPW-3606 WATER Apr,1993 CM4 24.8 i 2.3 21.5 11.5 - 31.5 4
Cs-134 26.4 i 1.9 26.4 16.4 - 36.4 Cs-137 33.9 i 2.6 31.7 21.7 - 41.7 SPM-3631 MILK Apr,1993
)
Cs-134 48.8 i 2.9 52.8 42.8 - 62.8 l
Cs-137 65.212.9 63.4 53.4 - 73.4 l
I-131 139.811.6 145.0 116.0 - 174.0 SPF-3681 FISH May,1993 (JELLO)
Cs-137 68.2 i 7.7 67.6 57.6 - 77.6 Concentrations are in pCi/ Total Volume (550g).
SPW-3842 WATER Jun,1993 i
Th-230 4.2 i 0.5 4.5 2.7 - 6.3 SPW-4160 WATER Jun,1993 Alpha 8.911.4 12.9 7.7 - 18.1 Beta 22.0 i 1.9 31.9 19.1 - 44.7 SPW-4232 WATER Aug,1993 Fe-55 1684.0 i 415.0 1420.0 1136.0 - 1704.0 SPW-4246 WATER Aug,1993 Sr-90 32.2 i 2.6 30.4 24.3 - 36.5 SPM-4247 MILK Aug,1993 1
Sr-89 29.1 i 4.9 35.4 25.4 - 45.4 Sr-90 18.3 i 1.3 19.2 9.2 - 29.2 SPW-4248 WATER Aug,1993 H-3 9910.0 i 300.0 10430.0 8344.0 - 12516.0 SPW-4250 WATER Aug,1993 Co-60 247.0 1 23.1 247.7 222.9 - 272.5 Cs-134 141.6 i 15.9 141.1 127.0 - 155.2 4
A A3-6
Table A-3. In-house " spike" samples.
Concentration in pCi/If Lab Sample Date Tcledyne Results Known Control' 6
Code Type Collected Analyses 2s, n=1 Activity Limits Cs-137 283.5 i 27.8 247.2 222.5 - 271.9 The cause of the high Cs-137 data is unknown. All data was reviewed, no errors where found in the calculations. The employee was observed performing this analysis and no deviations from the procedure where observed. The employee's results have been good in the past; no further action is planned.
SPF-4251 FISH OELLO) Aug,1993 Cs-134 68.8 i 3.3 75.3 65.3 - 85.3 Cs-137 203.6-i 8.2 198.1 178.3 - 217.9 SPS-4262 SEDIMENT Aug,1993 (BOTTOM)
Cs-134 74.1 i 9.9 71.0 61.0 - 81.0 Cs-137 212.4 1 14.8 197.8 178.0 - 217.6 SPW-4377 WATER Sep,1993 I-131 39.0 10.0 42.1 30.1 - 54.1 SPM-4378 MILK Sep,1993 I-131 44.5 i 5.5 42.1 30.1 - 54.1 SPCH-4379 CHARCOAL Sep,1993 1-131 90.3 i 13.5 84.3 67.4 - 101.2 SPVE-4380 VEGETATION Sep,1993 (SAW DUST) 1-131 193.2 20.0 170.2 136.2 - 204.2 SPW-4381 WATER Sep,1993 Sr-89 21.9 i 4.0 28.8 18.8 - 38.8 Sr-90 19.5 i 1.8 19.0 9.0 - 29.0 SPW-4382 WATER Sep,1993 I-129 18.1 i 1.0 18.6 6.6 - 30.6 SPW-4421 WATER Oct,1993 H-3 16900.0 i 368.0 17380.0 13904.0 - 20856.0 SPW-4428 WATER Oct,1993 Co-60 19.3 i 3.1 18.3 8.3 - 28.3 Cs-134 31.5 i 3.3 33.5 23.5 - 43.5 Cs-137 44.4 i 3.6 43.2 33.2 - 53.2 SPM-4426 MILK Oct,1993 Cs-134 30.8 i 4.5 33.0 23.0 - 43.0 Cs-137 43.4 i 6.0 43.2 33.2 - 53.2 1-131 49.7 i 8.6 44.5 32.5 - 56.5 l
A3-7
Table A-3. In-house " spike" samples.
Concentration in pCi/L' Lab Sample Date Teledyne Results Known Control' Code Type Collected Analyses 2s, n=1 Activity Limits 6
SFW-4427 WATER Oct,1993 I-131 95.2 i 10.6 88.9 71.1 - 106.7
- All results are in pCi/L, except elemental potassium (K) data in milk, which are in mg/L; air filter samples, which are in pCi/ Filter; charcoal which are in pCi/ charcoal; and food products which are in mg/kg.
- All sampics prior to January 1991 are the results or three determinations; after January 1991, all determinations are single.
- Control Limits are based on EPA publication;" Environmental Radioactive Laboratory Intercomparison Studies Program", Fiscal Year 1981-1982, EPA-600/4-81-004 (see Attachment A) or limits imposed by Teledyne's Midwest Laboratory.
i i
9 A3-8
Table A-4.
In-house " blank" samples.
Concentration pCi/L*.
Teledyne Results Acceptance Lab Sample Sample (4.66 Sigma)
Criteria Code Tvoe Date Analyses LLD Activitv (4.66 Sigma) 6 SPW-8039 WATER Jan 1990 Ra-226
< 0.2
< 1.0 SPM-8040 MILK Jan 1990 Sr-89
< 0.8
< 5.0 Sr-90
< 1.0
< 1.0 SPM-8208 MILK Jan1!di Cs-134
< 3.6
< 10.0 Cs-137
< 4.7
< 10.0 Sr-89
< 0.8
<5.0 St-90 N/A 1.6 1 0.5
< 1.0 Low level of Sr-90 concentration in milk (1-5 pCi/L) is not unusual.
SPM-8312 MILK Feb 1990 Sr-89
< 0.3
< 5.0 Sr-90 N/A 1.2 i 0.3
< 1.0 l
Low level of Sr-90 concentration in milk (1-5 pCi/L) is not unusual SPW-8312 WATER Feb 1990 Sr-89
< 0.6
<5.0 Sr-90
< 0.7
< 1.0 SPM-8314 MILK Mar 1990 l
l-131
< 0.3
< 1.0 SPM-8510 MILK May 1990 Cs-134
< 4.6
< 10.0 l
< 4.8
< 10.0 l
l-131
< 0.2
< 1.0 SPW-8511 WATER May 1990 4
< 200.0
< 300.0 SPM-8600 MILK Jul 1990 Cs-134
< 5.0
< 10.0 Cs-137
< 7.0
< 10.0 I-131
< 0.3
< 1.0 Sr-89
< 0.8
< 5.0 Sr-90 N/A 1.7 i 0.6
< 1.0 Low level of Sr-90 concentration in milk (1-5 pCi/L) is not unusual.
1 A4-1
4 Table A-4.
In-house " blank" samples.
Concentration pCi/L*.
Teledyne Results Acceptance Lab Sample Sample (4.66 Sigma)
Criteria (4.66 Sigma)
Code Type Date Analyses LLD Activitv6 SPM-8877 MILK Aug 1990 1-131
< 0.2
< 1.0 SPW-8925 WATER Aug 1990 H-3
< 200.0
< 300.0 SPW-8926 WATER Aug 1990 Gr. Alpha
< 0.3
< 1.0 i
Gr. Beta
< 0.7
< 5.0 i
SPW-8927 WATER Aug 1990 U-234
< 0.01
< 1.0 U-235
< 0.02
< 1.0 U-238
< 0.01
< 1.0 SPW-8928 WATER Aug 1990 Co-58
< 4.1
< 10.0 Co-60
< 2.4
< 10.0 Cs-134
< 3.3
< 10.0 Cs-137
< 3.7
< 10.0
]
< 4.0
< 10.0 l
SPW-8929 WATER Aug1990
}
Sr-89
<1.4
< 5.0 Sr-90
< 0.6
< 1.0 3
SPW-69 WATER Sep 1990 l
Sr-89
< 1.8
< 5.0 Sr-90
< 0.8
< 1.0 SPW-106 WATER Oct 1990 H-3
< 180.0
< 300.0 I-131
< 0.3
< 1.0
~
SPM-107 MILK Oct 1990 Cs-134
< 3.3
< 10.0 Cs-137
< 4.3
< 10.0 I-131
< 0.4
< 1.0 SPW-370 WATER Oct 1990 Co-58
< 2.6
< 10.0 Co-60
< 1.6
< 10.0 Cs-134
< 1.7
< 10.0 Cs-137
< 1.8
< 10.0 A4-2
Table A-4.
In-house " blank" samples.
Concentration pCi/L'.
Tcledyne Results Acceptance Lab Sample Sample (4.66 Sigma)
Criteria Code Tvoe Date Analyses LLD Activitv6 (4.66 Sigma)
< 1.7
< 10.0 SPW-372 WATER Dec 1990 Gr. Alpha
< 0.3
< 1.0 Gr. Deta
< 0.8
< 5.0 SPM-406 MILK Jan 1991 Cs-134
< 3.7
< 10.0 Cs-137
< 5.2
< 10.0 Sr-89
< 0.4
< 5.0 Sr-90 N/A 1.8 i0.4
< 1.0 Low level of Sr-90 concentration in milk (1-5 pCi/L) is not unusual.
SPM-421 MILK Feb l991 1-131
< 0.3
< 1.0 SPM-451 MILK Feb 1991 Ra-226
< 0.1
< 1.0 Ra-228
< 0.9
< 1.0 SPW-514 WATER Mar 1991 Sr-89
< 1.1
< 5.0 Sr-90
< 0.9
< 1.0 SPW-586 WATER Apr 1991 Co40
< 2.5
< 10.0 Cs-134
< 2.4
< 10.0 Cs-137
< 2.2
< 10.0 J131
< 0.2
< 1.0 SPM-587 MILK Apr 1991 Cs-134
< 1.7
< 10.0 Cs-137
< 1.9
< 10.0 i
< 0.2
< 1.0 SPW-837 WATER Jun1991 Gr. Alpha
< 0.6
< 1.0 Gr. Beta
< 1.1
< 5.0 SPM-953 MILK Jul1991 Cs-137
< 4.9
< 10.0 I-131
< 0.2
< 1.0 Sr-89
< 0.7
< 5.0 A 4-3
Table A-4.
In-house " blank" samples.
Concentration pCi/L'.
Teledyne Results Acceptance Lab Sample Sample (4.66 Sigma)
Criteria Code Tyne Date Analyses ILD Activitv6 (4.66 Sigma)
Sr-90 N/A 0.4 i0.3
< 1.0 Low level of Sr-90 concentration in milk (1-5 pCi/L) is not unusual.
SPM-1236 MILK Oct 1991 Cs-134
< 3.7
< 10.0 Cs-137
< 4.6
< 10.0 I131
< 0.2
< 1.0 SPW-1254 WATER Oct 1991 Sr-89
< 2.8
< 5.0 j
< 0.7
< 1.0 SPW 1256 WATER Oct 1991 Co-60
< 3.6
< 10.0 Cs-134
< 4.0
< 10.0 Cs-137
< 3.0
< 10.0 I-131
< 0.4
< 1.0 SPW-1259 WATER Oct 1991 H-3
< 160.0
< 300.0 SPW-1444 WATER Dec 1991 Gr. Alpha
< 0.4
< 1.0 Gr. Beta
< 0.8
< 5.0 SPM-1578 MILK Jan 1992 Cs-134
<7.2
< 10.0 Cs-137
< 8.0
< 10.0 I-131
< 0.2
< 1.0 Sr-89
< 0.5
< 5.0 Sr-90 N/A 1.310.4
< 1.0 Low level of Sr-90 concentration in milk (1-5 pCi/L) is not unusual SPW-1860 WATER Mar 1992 Sr-89
< 0.6
< 5.0 i
< 0.4
< 1.0 SPW-2067 WATER Apr 1992 l
< 168.0
< 300.0 SPW-2114 WATER Apr 1992 C-14
< 1.0
< 200.0 l
i A4-4
Table A-4.
In-house " blank" samples.
Concentration pCi/L'.
Teledyne Results Acceptance Lab Sample Sampl.
(4.66 Sigma)
Criteria Code Type Date Analyses LLD Activityb (4.66 Sigma)
SPM-2119 MILK Apr 1992 Co-60
< 6.3
< 10 0 Cs-134
<4.5
< 10.0 Cs-137
< 5.4
< 10.0 SPW-2126 WATER Apr 1992 1-131
< 0.2
< 1.0 SPM-2133 MILK Apr 1992 I-131
< 0.2
< 1.0 SPW-2220 WATER May 1992 Co 60
< 2.1
< 10.0 Cs-134
< 2.1
< 10.0 Cs-137
< 2.3
< 10.0 SPW-2369 WATER Jun1992 Gr. Alpha
< 0.4
< 1.0 Gr. Beta
< 0.8
< 5.0 SPM-2500 MILK Aug 1992 I-131
< 0.4
< 1.0 Sr-89
< 1.2
< 5.0 St-90
< 0.9
< 1.0 SPW-2666 WATER Sep 1992 St-89
< 0.8
< 5.0 Sr-90
<0.5
< 1.0 SPW-2828 WATER Oct 1992 Co-60
< 4.8
< 10.0 Activity result is not available for this sample.
Cs-134
< 6.0
< 10.0 Activity result is not available for this sample.
< 6.1
< 10.0 Activity result is not available for this sample.
< 177.0
< 300.0 1-131
< 0.3
< 1.0 Activity result is not available for this sample.
SPM-2829 MILK Oct 1992 Co-60
< 9.3
< 10.0 Cs-134
< 6.4
< 10.0 Cs-137
< 7.2
< 10.0 A4-5
l l
Table A-4.
In-house " blank" samples.
l Concentration pCi/L*.
Teledyne Results Acceptance Lab Sample Sample (4.66 Sigma)
Criteria Code Type Date Analyses IID Activitv6 (4.66 Sigma)
SPW-3212 WATER Oct 1992 Ra-228
< 1.0
< 1.0 SPW-3057 WATER Nov 1992 Ra-226
< 0.03
< 1.0 SPW-3294 WATER Dec 1992 Gr. Alpha
< 0.4
< 1.0 Gr. Beta
< 0.8
< 5.0 SPM-3342 MILK Jan 1993 Cs-134
<4.1
-0.9 i 2.6
< 10.0 Activity result is not available for this sample.
< 3.9 0.8 i 2.2
< 10.0 Activity result is not available.for this sample.
Sr-89
<0.7
-0.9 1 1.1
< 5.0 l
St-90 N/A 1.6 i 0.5
< 1.0 Low levels of Sr-90 concentration in milk (1-5 pCi/L) is not unusual SPM-3386 MILK Feb l993 1-131
<0.2 0.1 i 0.1
< 1.0 SPW-3557 WATER Mar 1993 Sr ?>
<0.5 0.310.5
< 5.0 Sr-90
<0.5 0.110.2
< 1.0 SPW-3598 WATER Apr 1993 H-3
< 180.0 84.7 i 94.2
< 300.0 SPW-3600 WATER Apr 1993 1-131
< 0.2 0.1 i 0.2
< 1.0 SPW-3601 WATER Apr 1993 Co-60
<4.2
< 10.0 Activity result is not available for this sample.
Cs-134
< 4.4
< 10.0 Activity result is not available'for this sample.
< 3.4
< 10.0 Activity result is not available for this sample.
1-131
< 0.4 0.3 1 0.9
< 1.0 SPM-3651 MILK May 1993 Cs-134
<4.4
< 10.0 Activity result is not available for this sample.
1 A4-6
~
5 i
Table A-4.
In-house " blank" samples.
i Concentration pCi/L*.
Teledyne Results Acceptance Lab Sample Sample (4.66 Sigma)
Criteria Code Type Date Analyses LLD Activityb (4.66 Sigma)
< 6.3
< 10.0 Activity result is not available for this sample.
1-131
< 0.2 0.1 1 0.1
< 1.0 SPFP-3680 FOOD May 1993 Cs-137
< 6.5 0.0 i0.0
< 10.0 SPW-3844 WATER Jun1993 Th-228
< 0.1 0.0 i 0.1
< 1.0 Th-230
< 0.1 0.2 1 0.1
< 1.0 Th-232
< 0.1 0.0 i0.0
< 1.0 SPW-4234 WATER Jun1993 Gr. Alpha
< 0.3 0.010.2
< 1.0 Gr. Beta
< 0.8 0.210.3
<5.0 SPS-4059 SEDIMENT Jul1993 (BO1 TOM)
Cs-134
< 5.0 0.010.0
< 10.0 Cs-137
< 7.2 0.0 1 0.0
< 10.0 SPVE-4060 VEGETATION Jul1993 (SAW DUST)
Cs-134
< 4.8 0.010.0
< 10.0 Cs-137
< 6.4 0.0 i 0.0
< 10.0 I-131(g)
< 13.5 0.0 i 0.0
< 20.0 SPM-4061 MILK Jul1993 Cs-134
< 8.6
.0.010.0
< 10.0 Cs-137
< 5.8 0.0 1 0.0
< 10.0 SPM-4062 MILK Jul1993 Cs-134
< 3.8 1.511.5
< 10.0 Cs-137
< 4.4
-1.613.3
< 10.0 SPW-4063 WATER Jul1993 Co-60
< 4.0 1.2 i 2.3
< 10.0 l
Cs-134
< 3.7 0.3 1 1.2
< 10.0 Cs-137
< 3.2 0.4 1 3.2
< 10.0 SPAP-4064 AIR FILTER Jul1993 (COMPOSITE)
Cs-134
< 2.1 0.0 i 0.0
< 10.0 Cs-137
< 2.8 0.0 1 0.0
< 10.0 A4-7
)
Table A-4.
In-house " blank" samples.
Concentration pCi/L'.
Tcledyne Results Acceptance Lab Sample Sample (4.66 Sigma)
Critr. ia Code Type Date Analyses LLD Activity (4.66 Egma) b SPCH-406 CHARCOAL Jul1993 I-131
< 0.1 0.0 i 0.0
< 1.0 Based on a volume of 300 m' SPW-4233 WATER Aug 1993 Fe-55
< 506.0 0.0 i 0.3
< 1000.0 SPM-4235 MILK Aug 1993 Cs-134
< 8.1 '
1.6 i 1.8
< 10.0 Cs-137
< 4.2
-1.7 i 3.4
< 10.0 I-131
< 0.1 0.0 1 0.2
< 1.0 Sr-89
< 0.8
-1.0 1.1
< 5.0 Sr-90 N/A 1.810.5
< 1.0 Low level of Sr-90 concentration in milk (1-5 pCi/L) is not unusual.
SPW-4241 WATER Aug 1993 H-3
< 190.0 72.9 i 99.1
< 300.0 SPW-4243 WATER Aug 1993 Co-60
< 7.0 0.4 1 3.1
< 10.0 Cs-134
< 7.6 0.8 i 15.6
< 10.0 Cs-137
< 5.4
-0.7 i 4.2
< 10.0 1-131
< 0.5 0.0 1 0.1
< 1.0 l
Sr-89
< 1.1
-0.6 1 0.9
< 5.0 Sr-90
< 0.7 0.410.4
< 1.0 SPW-4244 WATER Aug 1993 j
< 1.0 0.4 i 0.7
< 1.0 Pu-239/240
< 0.3 0.1 i 0.2
< 1.0 Th-228
< 0.4
-0.1 i 0.3
< 1.0 Th-230
< 0.1 0.0 1 0.1
< 1.0 Th-232
< 0.1 0.0 1 0.0
< 1.0 U-233/234
< 0.1 0.1 i 0.1
< 1.0 U-235
< 0.1 0.0 i 0.1
< 1.0 U-238
< 0.1 0.1 1 0.1
< 1.0 SPW-4245 WATER Aug 1993 Ra-226
< 0.1 0.0 1 0.0
< 1.0 Ra-228
< 0.8
-0.2 i 0.5
< 1.0 SPW-4422 WATER Oct 1993 H-3
< 180.0
-27.5 i 88.9
< 300.0 A 4-8
Table A-4.
In-house " blank" samples.
Concentration pCi/L'.
Tcledyne Results Acceptance Lab Sample Sample (4.66 Sigma)
Criteria Code Type Date Analyses LLD Activitv*
(4.66 Sigma) o All results are in pCi/L, except for air filter samples, which are in pCi/ Filter.
)
6 Prior to 1993, results where reported as only an LLD, the activity reported is the net activity result.
j 1
]
A4-9
i December,1993 ATTACHMENT A ACCEPTANCE CRrrERIA FOR " SPIKED" SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSES' One Standard Deviation Analysis Level for single determinations Gamma Emitters 5 to 100 pCi/ liter or kg 5.0 pCi/ liter
>100 pCi/ liter or kg 5% of known value Strontium-89 5 to 50 pCi/ liter or kg 5.0 pCi/ liter b
>50 pCi/ liter or kg 10% of known value Strontium-90 2 to 30 pCi/ liter or kg 5.0 pCi/ liter b
>30 pCi/ liter or kg 10% of known value Potassium
>0.1 g/ liter or kg 5% of known value Gross alpha s20 pCi/ liter 5.0 pCi/ liter
>20 pCi/ liter 25% of known value Gross beta s100 pCi/ liter 5.0 pCi/ liter
>100 pCi/ liter 5% of known value Tritium 14,000 pCi/ liter is = (pCi/ liter) =
169.85 x (known)'""
>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, s55 pCi/ liter 6.0 pCi/ liter
>55 pCi/ liter 10% of known value 6
Iodine-129 Uranium-238, s35 pCi/ liter 6.0 pCi/ liter Nich14p
>35 pCi/ liter 15% of known value Technetium c#
Iron-55, 50 to 100 pCi/ liter 10 pCi/ liter
>100 pCi/ liter 10% of known value Others' 20% of known value
- From EPA publication, " Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.
6 Teledyne limit.
A2
A a
I 1
l APPENDIX B DATA REPORTING CONVENTIONS I
l
)
i l
B-1 i
l
' ~~
~~
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:
xis 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 4.66a uncertainty for a background sample.
3.0 Duplicate analyses 3.1 Individual results:
x11 st x1 s2 Reported result:
x s where x = (1/2) (x1 ix2) 2 2
s = (1/2) s) + s2 3.2 Individual results;
<L1
<L2 Reported result:
<L where L = lower of L and L2 1
3.3 Individual results:
xis
<L Reported resu_1t;.
x i s if x 2 L;
<L otherwise B-2
I 4.0.
Computation of Averaces and Standard Deviations 1
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 R and standard deviation (s) of a set of n numbers x1, x2... xn are defined as follows:
.i R=g Ex s = }II(R-x,)'
1 n-1 4.2 Values below the highest lower limit of detection are not included in.
l 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-1 value x and associated two sigma error is reported.
4.5 In rounding off, the following rules'are followed:
1 4.5.1. If the figure following those to be retained is 1ess than 5, the figure is dropped, and the retained figures are kept unchanged.
As an example,11.443 is rounded off to 11.44..
i 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 nurnber.
As an example,11.435 is rounded off to 11.44, while 11.425 is rounded off to 11.42.
B-3
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i APPENDIX C Maximum Permissible Concentrations of Radioactivity in Air and Water Above Background in Unrestricted Areas 1
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Table C-1.
Maximum permissible concentrations of radioactivity in air and water above natural background in unrestricted areas,
a Air Water 3
Strontium-89 3,000 pCi/L Gross alpha 3
pCi/m Gross beta 100 pCi/m3 Strontium-90 300 pCi/L Iodine-131b 0.14 pCi/m3 Cesium-137 20,000 pCi/L Barium-140 20,000 pCi/L Iodine-131 300 pCi/L Potassium-40c 3,000 pCi/L Gross alpha 30 pCi/L Gross beta 100 pCi/L Tritium 3 x 106 pCi/L 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.
4 C-2
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1 APPENDIX D Special Ground and Well Water Samples D-1
1.0 INTRODUCTION
This appendix to the Radiation Environmental Monitoring Program Annual Report to the United States Regulatory Commission summarizes and interprets results of the special well and surface water samples taken at the Prairie Island Nuclear Generating Plant, Red Wing, Minnesota, during the period January - December,1993. This supplement special sampling program was established in December of 1989 when tritium was detected in a nearby residence well sample.
Tabulations of the special sampling program individual analyses made during the year are included in this appendix. A summary table of tritium analyses is also included in this appendix.
I D-2
4 5
1 2.0 SUMM ARY This special sampling program was established following the detection of tritium in a residence well water sample nearby the PINGP, during 1989. This program is described and the results i
for 1993 are summarized and discussed.
1 Program findings show a low level of tritium in a nearby residence well, some ground water scepage samples and a few other well water samples that are just above the lower limit of detection (LLD). None of these samples qualified as non-routine sample results.
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l 3.0 Special Tritium Sampline Procram 3.1 frogram Desien and Data Interoretation The purpose of this sampling program is to assess the impact of the tritium leaching into the environment (ground water system) from the PINGP discharge canal. For this purpose, special water samoles are collected and analyzed for radioactive content.
3.2 Program Descrip_tmn l
The sampling and analysis schedule for the special water sampling program is summarized in Table 4.1 and briefly reviewed below. Table 4.2 defines the additional sample locations and codes for the special water sampling program.
l Special well and ground water is collected quarterly at eight locations: one sample from the PINGP Biology Station (P-30); one from the nearest residence deep well (P-24d, Suter residence); two ground water seepage from near Birch Lake (P-31 and P-32); well water from the Prairic Islcnd Training Center (P-26); and three other nearby residences (P-27, Nauer residence; P-28, Perkins residence; P-29, Childs residence). The Rohl farm well (part of the quarterly REMP sampling) is used as a control location for these special samples.
3.3 Procram Execution The special water sampling was executed as described in the preceeding section with the following exceptions:
- 1. No water sample was available during the second and third quarters from the Birch Lake locations (P-31 and P-32) due to high water levels in the lake. The ground -
seepage sample locations were under water.
- 2. The Perkin's residence (P-28) had no renters living in the house second quarter, so the water sample was unattainable.
3.4 Erocram Modifications The special water sampling program was modified during the year to a quarterly schedule to correspond to the regular REMP sampling for tritium in water.
3.5 Results and Discussion Results obtained continue to show very low levels of tritium in some well water and ground water samples. Except for a few Suter residence deep well and Birch Lake seepage samples, most of the counting results for the samples are at or near the analysis laboratory's lower limit of detection (LLD). Sample results at the higher levels (Suter's and Birch Lake) are probable due to previous seepage from the PINGP discharge canal water into the ground water. This is thought to occur due to the elevation difference between the Vermillion River and the discharge canal. The Suter residence is between the discharge canal and Birch Lake, which is attached to the Vermillion River. The PINGP discharge canal discharge piping was lengthened during 1991, so that liquid discharges from the plant are released near the end of the discharge canal. In 1992, the underground liquid discharge pipe from the plant to the discharge canal piping was replaced with a double walled leak detectable piping system. It is expected that these modifications will eliminate the radioactive effluent flow into the ground water. Overall 1993 sample results show a slight downward trend as compared to 1992 levels.
D-4
Table D-4.1 Sample collection and analysis program for special well and surface water samples, Prairie Island Nuclear Generating Plant,1993.
Medium No.
Location codes Collection type Analysis typec and frequencyb and typea Well water quarterly 7
P-24d, P-25 (C),P-26, G/Q H-3 P-27, P-28, P-29, P-30 Ground water 2
P-31, P-32 G/Q H-3 a Location codes are defined in table D-4.2. Control Stations are indicated by (C). All other stations are indicators, b Collection ty:>e is coded as follows: C/ = continuous; G/ = grab. Collection frequency is coded as fol.ows: W = weekly; M = monthly; Q = quarterly; SA = semi-annually; A =
annually; X = no specified frequency or one time, c Analysis type is coded as follows: GB = gross beta; GS = gamma spectroscopy; H-3 =
1 D-5
Table D-4.2.
Sampling locations for special well and surface water samples, Prairie Island Nuclear Generating Plant,1993.
a Collection site Type of sampleb Distance and Code type direction from site stack P-24d Suter residence, deep well WW 0.6 mi. @ 158 /SSE P-25 C
Rohl farm WW 12.9 mi @ 352 /N P-26 FITC WW 0.4 mi. @ 258 /WSW P-27 Nauer residence WW 0.9 mi. @ 154 /SSE P-28 Perkins residence WW 1.0 mi. @ 152 /SSE P-29 Childs residence WW l.2 mi. @ 149 /SSE P-30 FINGP Biology Station WW 0.2 mi. @ 32 /NNE P-31 Birch Lake Seepage #1 GW 0.8 mi. @ 169 /SSE P-32 Birch Lake Seepage #2 GW 0.7 mi. @ 179 /S a "C" denotes control location. All other locations are indicators.
b Sample codes: WW = Well water; GW = Ground Water.
D-6
o Table D4.3 Radiological Environmental Monitoring Program Summary: Special well and surface water samples.
Name of Facihty Prairie Island Nuclear Power Station Docket No.
50-282g306 Location of Facility Goodhue, Minnesota Reporting Period January - December 1993 (County, State)
Indicator Location with liighest Control Number Sample Type and Locations Quarterly Mean Locations Non.
b Type Number of LLD Mean (F)C Mean (F)C Mean (F)c Routine a
e Locationd (Units)
Analyses Range Range Range Results' c
Well Water H-3 27 170 293 (10/27)
P-24d, Suter's deep 387 (3/4) 199 0
(pCi/L)
(170-770) well,0.6 mi @
(230-770) 158*/SSE Ground Water i 1-3 4
170 573 (3/4)
P-32, Birch Lake 560 (2/2) 199 0
(pCi/L)
(500 420)
Seepage #2,0.7 mi @
(500,620) 179*/S a H-3 = tritium b
LLD= Nominal lower limit of detection based on 4.66 sigma error for background sample. Value shown is lowest for the period.
c Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).
d Locations are specified (1) by name and code (Table D-4.2) and (2) distance, direction, and sector relative to reactor site.
e Non-routine results are those which exceed ten times the control station value.
0:
D-7
Table D-4.4 Radiological Environmental Monitoring Program, Complete Data Table,1993.
SAMPLE DATES Feb'93 May '93 Aug '93 Nov '93 SAMPLE LOCATIONS pCi/L pCi/L pCi/L pCi/L Suter Residence 770 550
<190 230 Rolh Farm
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<193 199 PFfC 170
<190 200
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<190
<190
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<190 Child Residence
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<190 220
<190 Environ Lab 130
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<190 Birch Lake Seep 2 620 500 D-8
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