ML20029C958

Annual Rept to NRC Radiation Environ Monitoring Program Jan-Dec 1993. W/940421 Ltr

ML20029C958
Person / Time
Site:	Monticello
Issue date:	12/31/1993
From:	Huebner L, Windschill J NORTHERN STATES POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9405030089
Download: ML20029C958 (77)

Text

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Northem States Power Company 1

, Monticello Nuclear Generating Plant 2807 West Hwy 75 Monticello, Minnesota 55362-9637 l

April 21,1994 Monticello Technical Specification TS 6.7.C.1 US Nuclear Regulatory Commission

' Attention: Document Control Desk Washington, DC 20555 Monticello Nuclear Generating Plant Docket No. 50-263 License No. DPR-22 1993 Annual Radiological Environmental Monitoring Report In accordance with the Monticello Technical Specifications, Appendix A to Operating License DPR-22, we are submitting the Annual Radiological Monitoring Report, covering the period January 1 through December 31 of 1993.

l' Respectfully submitted, John Windschill, General Superintendent Radiological Services JEW:mwl Attachment cc: Monticello REMP File Mar.ifest File 020071 94050300s9 931231

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y "RTELEDYNE ISOTOPES MIDWEST LABORA'!ORY 700 LANDWE!!R ROAD NORTl(BROOK. ILUNOIS 60062-2310 C08) 564@00

• FAX 908) 5644517 NORTHERN STATES POWER COMPANY MINNEAPOLIS, MINNESOTA MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263 LICENSE NO. DPR-22 ANNUAL REPORT TO THE UNITED STATES REGULATORY COMMISSION Radiation Environmental Monitoring Program January 1,1993 tc Decernber 31,1993 Project No. 8010 Prepared under Contract by TELEDYNE ISOTOPES MIDWEST LABORATORY Project No. 8010 Approved by:

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A (1 F (6L U' (1Z G. Huebner General Manager f

23 March 1994

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IUtEFACE The staff of Teledyne Isotopes Midwest Laboratory was responsible for the acquisition of the t data presented in this report. Sarnples were collected by members of the staff of the Monticello 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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TABLE OF CONTENTS iL:

No. Page .

Preface... .. . .... . . . . . . . . . . . . , . . . . .... .. ....... ... .. . ...... . ...... ... . . . . . . .ii List of Tables . ... .. . .. ..... .. .. ...............................................iv=

1.0 INTRODUCTION

... .. .. .. .. ..... .. . . . . . . . . ...... . .. . .. .... .... .. ....I 2.0

SUMMARY

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- 3.0 RADIATION ENVIRONMENTAL MONITORING PROGRAM (REMP).. .... 3 3.1 Program Design and Data Interpretation. ..... .... .. . .... . . . . . . . . . . . . . . . . . . . . 3~

3.2 Program Description... . . .... . . .. .... . ... . ... . ... ..... . ... .. ... ... 4 3.3 Program Execution.. . ... .. . ..... .. . . . . .. .. . . . .. .. ........ ... . . . . . . . . . . 5 3.4 Laboratory Procedures . .. .. .. .. .. ..... .... . .. . .. .. .... . . . . . . . . . . . .... ... 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.a.... . .. . . . . . . . . . . . .. ... . .. ..... . . . . .... .... .. .. .21 5

APPENDICES A Interlaboratory Comparison Program Results........ . ........ . . . .... .. ....... ... A-1 f B Data Reporting Conventions. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... ... .. B-1 C Maximum Permissible. Concentrations of Radioactivity in Air and Watcr Above Natural Background in Unrestricted Area... . .. . . . . C-1.

D Sampling Loca tion Maps .... .. .... .. ... . ............. .. ... . . . ..... ... ... . . ... ...... D-1 v

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LIST OF TABLES i

k Na Title Pace j 5.1 Sample Collection and Analysis Program, 1993 . . . . . . . . . . . . . . . . .. . .. . . .. . . . . . . . . . . 1 2 5.2 Sampling Locations.. ... . ...... .. .. .. ... . . . . . . . . . . ... . . . . . . . . . . . . . . . . . . . . .. ..13 5.3 Missed Collections and Analyses, 1993.................................................15  ;

4 i 5.4 Radiation Environmental Monitoring Program Summary . .... .. .... .. ..........16 The following tables are in the Appendices: 1 Appendix A A-1 Interlaboratory Comparison Program Results, milk, water and air filter samples.... .. . .. . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . ..A1-1 A-2 Interlaboratory Comparison Program Results, thermoluminescent .

d osimeters (TLDs) .. . . .. . . .. . . .. . . .. . ... . . .. . .. .. . . ... ... . . .... . .. A2-1 A-3 In-house Spiked Samples.. . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .... ... A3-1 A-4 In-house " Blank" Samples . .. . . .. .. . . . . . . . . . . . . . . . . ....................A4-1 ,

Attachment A: Acceptance criteria for spiked samples.. . .. . ... ..... .... ....A-2  !

Appendix B

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B-1 Data Reporting Conventions. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ....... . .. B-2 .

- Appendix C C-1 Maximum Permissible Concentrations of Radioactivity in air and water above background in unrestricted areas.... .. . .................C-2 b

Appendix D D-1 Sample collection and analysis program, Monticello Nuclear

.. . .., D-2 Generating Plant,1993.. ... . .. .. . . .. . . . . . . . . . . . . ..

D-2 Sampling locations, Monticello Nuclear Generating Plant,1993.... . .......... D-4 F 4 t

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1.0 INTRODUCTION

This report summarizes and interprets results of the Radiation Environmental Monitoring-Program (REMP) conducted by Teledyne Isotopes Midwest Laboratory at the'Monticello

- Nuclear Generating Plant, Monticello, Minnesota, during the period January - December,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.

Tabulation of the individual analyses made during the year are not included in this report.

- These data are included in a reference document (Teledyne Isotopes Midwest Laboratory, 1994a) available at Northern States Power Company, Nuclear Generation Department.

Monticello Nuclear Generating Plant is a 545 MWe boiling water reactor located on the

. Mississippi River in Wright County, Minnesota, and operated by Northern States Power Company. Initial criticality was achieved on 10 December 1970. Full power was achieved on 5 March 1971 and commercial operation began on 30 June 1971.

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SUMMARY

The Radiation Environmental Monitoring Program (REMP) required by the U.S. Nuclear Regulatory Commission (NRC) Technical Specifications for the Monticello Nuclear Generating -

Plant is described. Results for 1993 are summarized and discussed. ,

Program findings show background levels of radioactivity in the environmental samples collected in the vicinity of the Monticello Nuclear Generating Plant.

No effect on the environment due to the operation of the Monticello Generating Plant'is indicated.

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i 3.0 RADIATION ENVIRONMENTAL MONITORING PROGRAM (REMP) 3.1 Program Design and Data Interoretation  ;

The purpose of the Radiation Environmental Monitoring Program (REMP) at the Monticello Nuclear Generating Plant is to assess the impact of the Plant on its environment. For this purpose, samples are collected from the air, terrestrial, and  ;

aquatic environments and analyzed for radioactive content. In addition, ambient gamma radiation levels are monitored by thermoluminescent dosimeters (TLD's).

Sources of environmental radiation include the following:

(1) Natural background radiation arising from cosmic rays and primordial-adionuclides; (2) Fallout from atmospheric nuclear detonations; (3) Releases from nuclear power plants; (4) Industrial and medical radioactive waste; and

(. Fallout from nuclear accidents.

In interpreting the data, effects due to the Plant must be distinguished from those due to other sources.

A major interpretive aid in assessment of these effects is the design of the monitoring

, program at the Monticello Plant which is based on the indicator-control concept. Most types of samples are collected both at indicator locations (nearby, downwind, or downstream) and at control locations (distant, upwind, or upstream). - A plant effect would be indicated if the radiation level at an indicator location was significantly larger than that at the 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 environmental samples collected from the Plant site. The Plant's monitoring program includes analyses for tritium and iodine-131. Most samples are also analyzed for gamma-emitting isotopes with results for the following groups quantified: zirconium-95, ,

cesium-137, cerium-144, beryllium-7, and potassium-40. The first three gamma emitting isotopes were selected as radiological impact indicators because of the different characteristic proportions in which they appear in the fission product mix produced by a nuclear reactor and that produced by a nuclear detonation. Each of the three isotapes 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 o naturally-occurring isotope. They were chosen as calibration monitors and should not be  ;

considered as radiological impact indicators.

The other group quantified consists of niobium-95, ruthenium-103 and -106, cesium-134, .,

barium-lanthanum-140, and cerium-141. These isotopes are released in small quantities l by nuclear power plants, but to date their major source of injection into the general i

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j.3 environment has been atmospheric nuclear testing. Nuclides of the final group, manganese-54, iron-59, cobalt-58 and -60, and zinc-65, are activation products and arise from activation of corrosion products. They are typical components of a nuclear power plant's effluents, but are not produced in significant quantities by nuclear detonations.

Other means of distinguishing sources of environmental radiation are employed in interpreting the data. Current radiation levels are compared with previous levels, including those measured before the plant became operational. Results of the Plant's .

Monitoring Program can be related to those obtained in'other parts of the world.

Finally, results can be related to events known to cause elevated levels of radiation in the environment, e.g., atmospheric nuclear detonations.

3.2 Program Description The sampling and analysis schedule for the Radiation Environmental Monitoring Program (REMP) at the Monticello Plant is summarized in Table 5.1 and briefly reviewed below. Table 5.2 defines the sampling location codes used in Table 5.1 and specifies for each location its type (indicator or control) and its distance, direction, and sector relative to the reactor site. To assure that sampling is carried out in a reproducible manner, detailed sampling procedures have been prescribed (Monticello Nuclear Generating Plant,1987). Maps of sampling locations are included in Appendix D.

To monitor the air environment, airborne particulates are collected on membrane filters by continuous pumping at five locations. Also, airborne iodine is collected by continuous pumping through charcoal filters at all of these locations . Filters are changed and counted weekly. Particulate filters are analyzed for gross beta activity and charcoal filters for iodine-131. Quarterly composites of particulate filters from each location are gamma-scanned on a HP Ge or Ge(Li) detector. One of the five locations is -

a control (M-1), and four are indicators (M-2, M-3, M-4, M-5). One of the indicators is r located in the geographical sector expected to be most susceptible to any atmospheric emissions from the Plant (highest D/Q sector).

As a " Lessons Learned" commitment, ambient gamma radiation is monitored at thirty-seven (37) locations, using CaSO4:Dy dosimeter with four sensitive areas at each location: fourteen (14) in an inner ring in the general area of the site boundary, sixteen (16) in the outer ring within 4-5 mile radius, six (6) at special interest locations and one control location,11.1 miles distant from the plant. They are replaced and measured quarterly. Also, a complete emergency set of TLD's for all locations is placed in the field at the same time as regular sets. The emergency set is returned to TIML quarterly for annealing and repackaging.

Milk samples are collected monthly from four farms (three indicator and one control).

The milk is collected biweekly during the growing season (May - October), because the milk animals may be on pasture. All samples are analyzed for iodine-131 and gamma-emitting isotopes.

Leafy green vegetables (cabbage) are collected annually from the highest D/Q garden and a control location and analyzed for iodine-131. Corn and potatoes are collected annually only if the field is irrigated by water in which radioactive effluent has be'e n discharged. Analysis is for gamma-emitting isotopes.

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The terrestrial environment is also monitored by collection of well water from four locations on a quarterly basis. ' All samples are analyzed for tritium and gamma-emitting -

isotopes.

River water is collected weekly at two locations, one upstream of the plant and one downstream. Monthly composites are analyzed for gamma-emitting isotopes.

Quarterly composites are analyzed for tritium.

E Drinking water is collected weekly from the City of Minneapolis water supply, which is taken from the Mississippi River downstream of the Plant. Monthly composites are analyzed for gross beta, iodine-131, and gamma-emitting isotopes. Quarterly composites are analyzed for tritium.

The aquatic environment is also monitored by semi-annual upstream and downstream collections of fish, algae or aquatic insects, and bottom sediments. Shoreline sedirnent is collected semi-annually from one location. All samples are analyzed for gamma-emitting isotopes.

1 3.3 Procram Execution -'

The Program was executed as described in the preceding section with the following exceptions:

(1) There was no TLD data for location M-04B for the second quarter of 1993. The TLD's were lost in the field.

Deviations from the program are summarized in Table 5.3.

3.4 Lahomforv Procedures The iodine-131 analyses in milk and drinking water were made using a sensitive radiochemical procedure which involves separation of the iodine using an ion-exchange method and so:. vent extraction and subsequent beta counting.

All ganuna-spectroscopic analyses were performed with an HP Ge or Ge(Li) detector.

Levels of iodine-131 in cabbage and natural vegetation were determined by HP Ge or Ge(Li) spectrometry. The concentrations of airborne iodine-131 in charcoal samples were measured by HP Ge or Ge(Li) spectrometry.

Tritium was determined by a liquid scintillation technique.

Analytical procedures used by the Teledyne Isotopes Midwest Laboratory are specified in detail elsewhere (Teledyne Isotopes Midwest Laboratory,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 QA Program are presented elsewhere (Teledyne isotopes Midwest Laboratory,1994).

The TIML QA Program includes participation in Interlaboratory Comparison 5

b 3.4 Laboratory Procedures (continued)

(crosscheck) Programs. Results obtained in crosscheck programs are presented in Appendix A.

3.5 Iiogram Modifications ,

There were no program modifications in 1993.

3,6 Land Use Census ,

In accordance with the Technical Specifications 4.16 Paragraph B1, a land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 ft2 producing fresh leafy -

vegetables,in each of the 16 meteorological sectors within a distance of 5 miles. The census shall also identify the locations of all milk animals and all 500 ft2 or greater gardens producing broad leaf vegetation in each of the meteorological sectors within a distance of three miles. This census shall be conducted at least once per year behveen .

the dates of May 1 and October 31. New locations shall be added to the radiation environmental monitoring program within 30 days and sampling locations having lower calculated doses or a lower dose commitment may be deleted from this monitoring .

program after October 31 of the year in which the land use census was conducted. The 1993 land use census wa3 conducted between August 17 and August 26,1993. One change for the highest D/Q garden location was identified. This location was moved from the SSE sector to the SSW sector. The dairy farm (M-28) is still ranked as the highest D/Q location for milk. The highest D/Q residence remained the same. i e

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t: e 4.0 RESULTS AND DISCUSSION-All of the scheduled collections and analyses were made except those listed in Table 5.3.

All results are summarized in Table 5.4 in a format recommended by the Nuclear Regulatory.

Commission in Regulatory Guide 4.8. For each type of analysis of each sampled medium, this table lists the mean and range for all indicator locations and for all control locations. The locations with the highest mean and range are also shown. >

4.1 Atmospheric Nuclear Detonations and Nuclear Accidents There were no reported atmospheric nuclear tests in 1993. The last reported test was -

conducted by the People's Republic of China on October 16,1980. The reported yield was in the 200 kiloton to 1 megaton range.

There were no reported accidents with significant releases in 1993.

4.2 Summary of Preoperational Data The following constitutes a summary of preoperational studies conducted at the Monticello Nuclear Generating Plant during the years 1968 to 1970, to determine background levels expected in the environment, and provided, where applicable, as a means for comparison with present day levels. Strict comparisons, however, are difficult to make, since background levels of radiation were much higher in these years due to radioactive >

fallout from the atmosphere. Gross beta measurements in fallout averaged 20,600 pCi/m 2 in 1969 and 12,000 pCi/m2 n 1970. These levels are reflected throughout the vaJ us media tested.

In the air environment, ambient gamma radiation (TLDs) averaged 9.1 mR/4 weeks during preoperational studies (1970). Gross beta in air particulates in 1969 and 1970 averaged 0.20 3

pCi/m . Average levels today have stabilized at around 0.025 pCi/m3 . Airborne radiciodine -

remained below detection levels, In the terrestrial environment of 1968 to 1970, milk, agricultural crops, and' soil were '

monitored. In milk samples, low levels of Cs-137 and Sr-90 were detected. Cs-137 levels .

averaged 16.7 pCi/L. Soybean crop measurements in 1969 averaged 35.5 pCi/g for gross beta and 0.3 pCi/g for Cs-137. Gross beta measured in soil averaged 51.7 pCi/g gross beta.

Measurements today for cesium-137 are below detection levels in milk and agricultural crops.

The aquatic environment was monitored by testing of river water, bottom and shoreline sediments, fish, aquatie vegetation, and periphyton. Specific' location comparison of drinking water, river, and well water concentrations for tritium and gross beta are not .

possible, liowever, tritium background levels, measured at seven separate locations from 1968 to 1970, averaged 970 pCi/L. Levels of tritium today measure below 330 pCi/L.

Values for gross beta, measured from 1968 to 1970, averaged 9.8 pCi/L in upstream and downstream Mississippi River water,4.4 pCi/L for well waters, and 18.6 pCi/L for lake waters. Gamma emitters were below the lower limit of detection (LLD). . In bottom sediments, the gross beta background levels in 1970 averaged 49.8 pCi/g for both upstream ,

and downstream samples. Cs-137 activity averaged 0.10 pCi/g for both upstream'and i downstream samples. The lower levels of Cs-137 that are occasionally observed today can i I

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be attributed to residual activity from atmospheric fallout. Gross beta levels in fish flesh averaged 5.3 pCi/g in 1968 and 1969. Cs-137, measured in 1969 and 1970, averaged 0.044 pCi/g. Gross beta backpound levels, in 1970 for aquatic vegetation, algae, and -

periphyton samples measured 36.7 pCi/g,76.5 pCi/g, and 28.1 pCi/g respectively.

. 4.3 Pronram Findings -

Results obtained show background levels of radioactivity in the environmental samples collected in the vicinity of the Monticello Nuclear Generating Plant in 1993.

Ambient Radiation (TLDs)

Ambient radiation was measured in the general area of site boundary, at outer ring 4 - 5 mi. distant from the Plant, at special interest areas and at one control location. The means were similar for both inner and outer rings (15.6 and 15.9 mR/91 days, respectfully). The mean for speciallocations was 15A mR/91 days. The mean for the controllocation was 15.3 mR/91 days. The differences are not statistically significant. The dose rates measured were similar to those observed in 1978, 1983, 1984, 1985, 1986, 1987, 1988, 1989.1990,1991, and 1992 (12.3,12.5,13.6,14.2,15.3,15.4,'15.2,15.2,16.2,15.5, and i 15.2 mR/91 days, respectfully). No Plant effect on ambient gamma radiation was indicated.

Airborne Particulates The average annual gross beta concentration in airborne particulates was identical at 3 indicator and control locations (0.023 pCi/m3 ) and was nearly identical'or similar to the levels observed in 1982 (0.026 pCi/m3 ),1983 (0.023 pCi/m3 ),1984 (0.024 pCi/m3 ),1985 3

(0.025 pCi/m ),1986 (0.026 pCi/m3 ),1987 (0.026 pCi/m3),1988 (0.030 pCi/m 3),1989 -

3 (0.026 pCi/m ),1990 (0.023 pCi/m3),1991 (0.024 pCi/m 3), and 1992 (0.023 pCi/m3 ). The average of 0.026 pCi/m3 for 1986 does not include the results from May 19 to June 9, <

1986, which were influenced by the accident at Chernobyl.

A spring peak in beta activity had been observed almost annually for many years (Wilson et al.,1969). It had been attributed to fallout of nuclides from the stratosphere (Gold et al.,1964). It was pronounced in 1981, occurred to a lesser degree in 1982, and did not occur in 1983 through 1993. In 1986, the spring peak could not be identified because it was overshadowed by the releases of radioactivity from Chernobyl. From'1983 to 1993, .

the highest averages for gross beta occured in the months of January and December (the first and fourth quarters, exclusive of the period between May 19, 1986 and June 9, 1986).

Two pieces of evidence indicate conclusively that the elevated activity observed during the first and fourth quarters was not attributable to the Plant operation. In the first place, elevated activity of similar size occurred simultaneously at both indicator and control locations. Secondly, an identical pattern was observed at the Prairie Island Nuclear Generating Plant, about 100 miles distant from the Monticello Nuclear Generating Plant (Northern States Power Company,1993b).

Gamma spectroscopic analysis of quarterly composites of air particulate filters yielded similar results for indicator and control locations. Beryllium-7, which is produced ,

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' 4 - 6 Airborne Particulates (continued) continuously in the upper atmosphere by cosmic radiation (Arnold and Al-Salih,1955)

was detected in all samples, with an average of 0.061 pCi/m3 at both indicators and control locations. All other gamma-emitting isotopes were below their respective LLD limits.

Airbome Iodine e

Weekly levels of airborne iodine-131 were below the lower lim t of detection (LLD) of 0.07 pCi/m3in all samples.

Milk Iodine-131 results were below the detection limit of 1.0 pCi/L in all samples. )

Cesium-137 results were below the LLD level of 15 pCi/L in all samples.

No other gamma-emitting isotopes except naturally-occurring potassium-40 were detected in any of the milk samples. This is consistent with the finding of the National '

Center for Radiological Health that most radiocontaminants in feed do not find their way into milk due to the selective metabolism of the cow. The common exceptions are ,

radioisotopes of potassium, cesium, strontium, barium, and iodine (National Center for Radiological Health,1968).

In summary, the milk data for 1993 snow no radiological effects of the plant operation.

Biver Water and Drinking Wat<;I Tritium was below the LLD of 330 pCi/L in all samples. Gross beta in Minneapolis drinking water averaged 2.6 pCi/L and was lower or similar to average levels observed in 1977 (3.4 pCi/L), in 1978 (3.8 pCi/L), in 1979 (3.4 pCi/L), in 1980 (3.2 pCi/L), in ~

1981 (3.5 pCi/L), in 1982 (2.9 pCi/L), in 1983 (3.3 pCi/L), in 1984 (2.8 pCi/L), in 1985 (2.8 pCi/L), in 1986 (2.5 pCi/L), in 1987 (2.4 pCi/L), in 1988 (2.7 pCi/L), in 1989 (2.6 pCi/L), in 1990 (2.2 aci/L), in 1991 (2.9 pCi/L), and in 1992 (2.1 pCi/L).

Comparisons with gross beta c ata reported by EPA for Minneapolis drinking water sample collected in 1975,1976,1977, and 1978 indicates that concentrations of these ,

nuclides are remaining fairly constant and are in the range of drinking water levels in '

other parts of the country (U.S. Environmental Protection Agency, 1975, 1976, 1977, 1978). Gamma emitting isotopes were below detection limits in all surface, water samples. There was no indication of a plant effect.

4 Well Water The tritium level was below the LLD level of 330 pCi/L in all samples. All gamma scan results were below detection limits. There was no indication of a plant effect.

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Crops '

Two (2) samples of cabbage were collected in September and analyzed for iodine-131. 5I The I-131 level was below 0.012 pCi/g wet weight in both samples. There was no . 1 indication of a plant effect. The field sampling personnel conducted a survey to a l distance of five miles downstream on the Mississippi River ; no signs of irrigation- 1 were evident. One liquid release of tritium occurred in 1993, with a total ' activity. <

of 1.88 E-05 Ci and an average diluted concentration of 7.69 E-10 pCi/ml. Therefore, l no corn or potato sampics were collected for analysis.  !

Eish Fish samples were collected in April and October. Flesh was separated from the bones . 1 and gamma-scanned. Potassium-40, the naturally-occurring isotope, was found to be similar in upstream and downstream samples (3.14 and 2.86 pCi/g wet. weight, respectively). All gamma-emitting isotopes were below their respective LLD levels.

There was no indication of a plant effect.

Invertebrites  !

Two samples were collected in June and two in October. The samples were analyzed for gamma-emitting isotopes. All o.f the isotopes, except naturally-occurring K-40, were below detection limits. Potassium-40 averaged 2.16 pCi/g wet weight at the control location and 3.86 pCi/g wet weight at the indicator location. There was no indication of a plant effect.

Bottom and Shoreline Sediments Bottom and shoreline sediment collections were made in June and October and analyzed -

for gamma-emitting isotopes. Cesium-137 was detected in two downstream bottom .

sediment samples, averaging 0.083 pCi/g dry weight, and in two shoreline sediment samples, averaging 0.096 pCi/g dry weight, indicating the influence of fallout.

deposition. Similar levels of activities and distribution were observed in 1978-1992.

The only other gamma-emitting isotope detected was naturally-occurring potassium-40.

There was no indication 'of a plant effect.

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Table 5.1; Sample collection and analysis program, Monticello Nuclear Generating Plant,1993.

Locations Collection . Analysis .-

Medium No. Codes (and Type)a Type and . Type and FrequencyC Frequency b Ambient Radiation (TLD's) 37 M-01A - M-14A C/Q Ambient gamma M-01B - M-16B M-01S - M-06S M-01C ,

Airborne particulates 5 M-1(C), M-2, M-3, C/W GB, GS (QC of ead M-4, M-5 location)

AirborneIodine 5 M-1(C), M-2, M-3, C/W I-131-M-4, M-5 Milk 4 M-10 (C), M-24, G/Md I-131, GS ,

M-28, M-29 River water 2 M-8(C), M-9 G/W GS(MC), H-3(QC)

Drinking water 1 M-14 G/W GB(MC), I-131(MC)

GS(MC), H-3(QC) .

Well Water 4 M-10(C), M-11, G/Q H-3, GS M-12, M-13 Edible cultivated crops - 2 M-10 f(C), M-27 G/A I-131 Cabbage Edible cultivated crops - Corne 1 M-19 G/A GS Edible cultivated crops - 1 M-21 G/A GS Potatoese Fish (one species, edible portion) 2 M-8(C), M-9 G/SA GS Algae or Aquatic Insects 2 M-8(C), M-9 G/SA GS Bottom Sediment 2 M-8(C), M-9 G/SA GS Shoreline Sediment 1 M-15 G/SA GS 8

Location codes are defined in Table 5.2. Control stations are indicated by (C). All other stations are indicators.

b Collection type is coded as follows: C/ = continuous, C/ = 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 Analysis frequency is coded as follows: MC = monthly composite, QC = quarterly, H-3 = tritium,1-131 =

composite.

d Milk is collected biweekly during the grating season (May - October) if milk animals are on pasture. )

e Collected only if the field is irrigated by water in which liquid radioactive effluent has been discharged. -!

f No vegetables produced in 1993 at kration M-10, Control cabbage sample obtained in Elk River, MN,13.5 mi. @ l 95* /E. -l e

12

.i l

O ;a ,

Table 5.2. Sampling locations, Monticello Nuclear Generating Plant,'1993.

Distance and  !

Type of Direction from Code Typea Collection Site Sampleb Site Stack M-1 C Air Station M-1 AP, Al ' 11.1 mi @ 306 /NW M-2 Air Station M-2 AP,Al 0.8 mi @ 140 /SE i

' M-3 Air Station M-3 AP, Al 0.6 mi @ 104 /ESE I M-4 Air Station M-4 AP,AI 0.9 mi @ 150 /SSE l M-5 Air Station M-5 AP, AI 2.7 mi @ 136*/SE I M-8 C Upstream of Plant RW, BS, BO, F 0.2 mi @ 285 /WNW l M-9 Downstream of Plant RW, BS, BO, F 0.2 mi @ 62 /ENE M-10 C Kirchenbauer Farm M, WW 11.5 mi @ 323 /NW l M-11 City of Monticello WW 3.2 mi @ 128*/SE l M-12 Plant Well #1 WW 0.2 mi @ 267 /W j M-13 Ernst Residence WW 0.6 mi @ 202 /SSW M-14 City of Minneapolis DW 36.0 mi @ 128'/SE M-15 Montissippi Park SS 1.6 mi @ 117 /ESE

' M-19 River Irrigated Com Fielde  :

M-21 River Irrigated Potato Fieldc M-24 Weinand Farm M 4.8 mi @ 180 /S M-27 Wise Residence - VE 0.7 mi O 208 /SSW i Highest D/Q garden M-28 Hoglund Farm M 3.7 mi @ 300 /WNW '

Highest D/Q dairy M-29 Holthaus Farm M 4.1 mi @ 173 /S C Elk River, MN Vegetable Garden VE 13.5 mi @ 95 / E 1 q

General Area of the Site Boundarv

. M-01 A North Boundary Road TLD 0.7 mi @ 353 /N M-02A North Boundary Road TLD 0.8 mi @ 23*/NNE M-03A North Boundary Road' TLD 1.0 mi @ 43 /NE M-04A Biology Station Road TLD 0.7 mi @ 92 /E M-05A Biology Station Road TLD 0.6 mi @ 112 /ESE l M-06A Biology Station Road TLD 0.6 mi @ 133 /SE M-07A County Road 75 TLD 0.5 mi @ 158 /SSE M-08A- County Road 75 TLD 0.5 mi @ 183 /S M-09A County Road 75 TLD 0.4 mi @ 203'/SSW M-10A County Road 75 TLD 0.3 mi @ 225 /SW M-11 A County Road 75 TLD 0.4 mi @ 250*/WSW .I M-12A County Road 75 TLD 0.7 mi @ 273 /W  ;

M-13A North Boundary Road TLD. 1.1 mi @ 317*/NW-  !

M-14A North Boundary Road TLD 0.8 mi @ 338 /NNW 13

_ __ . ~ . .

Table 5.2. Sampling locations, Monticello Nuclear Generating Plant.1993 (continued).

Distance and Type of Direction From Code Type" . Collection Site Sample Site Stack i r

Approximately 4 to 5 miles Distant from the Plant M-OlB Sherco #1 Air Station TLD 4.6 mi @ 02*/N s M-02B County Road 11 TLD 4.4 mi @ 17*/NNE M-03B Intersection of County Road TLD 4.5 mi @ 49*/NE

& Route 81 M-04B Sherco #6 Air Station TLD 4.2 mi @ 67*/ENE M-05B City of Big Lake TLD 4.4 mi @ 87*/E - '

M-06B County Road #14 and 196th St. TLD 4.3 mi @ l16*/ESE M-07B Monte Industrial Drive TLD 4.4 mi @ 135'/SE M-08B Dale K. Larson Residence TLD 4.6 mi @ 162*/SSE M-09B Norbert Weinand Farm TLD 4.7 mi @ 180*/S  ;

M-10B John Reisewitz Farm TLD 4.4 mi @ 206*/SSW ,

M-l l B Clifford Vanlith Farm TLD 4.2 mi @ 225*/SW '

M-12B Lake Maria State Park TLD 4.4 mi @ 253*/WSW M-13B Bridgewater Station TLD 4.1 mi @ 271*/W M-14 B Richard K. Anderson Residence TLD 4.5 mi @ 228*/WNW  !

M-15B Gary Williamson Residence TLD 4.5 mi @ 308*/NW M-16B Sand Plain Research Farm TLD 4.3 mi @ 338'/NNW t

Special Interest Locations '

M-OlS Osowski's Orchard TLD 0.7 mi @ 230*/SW M-02S Edgar Klucas Residence FLD 0.7 mi @ 142*/SE -

M-03S Big Oaks Park TLD 1.3 mi @ 89*/E -'

M-04S Pinewood School TLD 2.3 mi @ 132*/SE M-05S Roman Greener Residence TLD 2.5 mi @ l12*/ESE M-06S Monticello Public Works Building TLD 2.7 mi @ 136*/SE 1 M-01C C Kirchenbaur Farm TLD 11.5 mi @ 323*/NW  :

" "C" denotes control location. All other locations are indicators.

6 Sample Codes:

AP = Airborne particulates AI = Airborne lodine M = Milk  :

VE = Vegetation / vegetables l DW = Drinking water RW = River water -

WW = Well water  :

BS = Bottom (river) sediments SS = Shoreline sediments BO = Bottom organisms (periphyton or macroinvertebrates) '

F = Fish

' Collected only if the field is irrigated by water in which liquid radioactive effiuent has been discharged.  !

14

+ -. ..n,- .p -- - --

Table 53. Missed collections and analyses for 1993 at the Monticello Nuclear' Generating Plant.

All required samples were collected and analyzed as scheduled except the following:

Collection Reason for not Plans for Preventing -

Sample Analysis Location Date or conducting REMP Recurrence '

Period as required TLD Gamma M-04B 2nd Qtr., TLD lost in the Relocated away_ from 1993 field. highway to reduce potential for vandalism

-t i

k l

l 15 a I

-l

~ ^

i

.4 2 Table 5.4.

^

Radiation Environmental Monitoring Program Summary.

Name of Facility Monticello Nuclear Generating Plant Docket No, 50-263 Location of Facihty Wnght, 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 LLab Mean (F)C Mean (F)C Routine Mean (F)c (Units) Analyses a Rangee Locationd Rangec Range Results0 TLD (mR/91 Gamma 56 3.0 15.6 (56/56) M-12A, Cty Rd 75 17.6 (4/4) (See Control 0 days) (Inner (12.5-20.5) 0.7 mi @ 273'/W (14.7-20.5) below.)

Ring, General Area at Site Boundary)  ;

TLD (mR/91 Gamma 63 3.0 15.9 (63/63) M-05B, City of Big 20.9 (4/4) (See Control 0 days)(Outer (12.3-22.7) Lake 4.4 mi @ 87*/ F (19.2-22.7) below.)

Ring,4 - 5 miles distant)

TLD (mR/91 Gamma 24 30 15.4 (24/24) M-06S, Monte 16.8 (4/4) (See Control 0 days)(Special (12.1-18 0) Service Center 2.7 (15.6-18.0) below.)

Interest Areas) mi @ l36*/SE TLD (mR/91 Gamma 4 3.0 None M-01 C, 15.3 (4/4) 15.3 (4/4) 0 days) Kirchenbauer Farm. (14.4-16.1) (14.4 16.1)

(Control) 11.5 mi @ 323*/NW t

Airterne GB 260 0.003 0 024 (208/208) Three locations had 0.024 (156/156) 0.023 (52/52) O Particulates (0.008-0.064) identical means (0.008-0.064) (0.008-0.057)

(pCi/m3)

CS 20 Be-7 0.020 0.061 (16/16) M-3, Station M-3 0.065 (4/4) 0.061 (4/4) 0 (0.045-0.080) 0.6 mi. @104* /ESE (0.050-0.078) _(0.041-0.070)

Mn-54 0.0013 <LLD - -

<LLD 0 Co-58 0.0016 <LLD - -

(LLD 0 Co-60 0.0016 <LLD - -

<LLD 0 7n-65 0.0031 <LLD - - <LLD 0 Zr-Nb-95 0.0029 <LLD - -

<LLD 0 Ru-103 0.0013 <LLD - -

<LLD 0 Ru-106 0.0097 <LLD - -

(LLD 0 C5-134 0.0014 <LLD - -

(LLD 0 C3-137 0.0012 <LLD - -

<LLD 0  ;

Da-La-140 0.0055 <LLD - -

(LLD 0 _i Ce-141 0.0027 <LLD - -

(LLD 0 '

Cc-144 0.0066 <LLD - - <LLD 0 -

Airborne I-131 260 0.07 <LLD - - (LLD 0 lodine (pCs/m3) 16

Table 5.4. Radiation Environmental Monitoring Program Summary.

Name of Facility ~ Monticello Nuclear Generating Plant Docket No. 50-263 Location of Facility Wright, Minnesota Reporting Period Lanuary - December 1993 (County, State)

Indicator Location with Highest . Control Number j Sample Type and Locations Quarteny Mean Locations Non.

Type Number of LLob Mean (F)C Routine l Mean (F)C Mean (F)c '

(Units) Analyses a Rangec Locationd Rangec Range Resultse i Milk, 1-131 76 1.0 ALLD - -

(LLD 0 (pCi/L) ,

K-40 200 1320 (57/57) M 10, 1360 (19/19) 1360 (19/19) 0 (1160-1500) Kirchenbauer Farm (1120-1520) (1120-1520) 11.5 mi @ 323*/NW Ce134 15 <tLD - -

<LLD 0 Cs-137 15 <LLD - -

<LLD 0 Other 15 <tLD - -

<LLD 0 gammas River Water H3 8 330 <tLD - -

<LLD 0 ~-

(pCi/L)

CS 24 Mn-54 15 <LLD - -

<LLD 0-Fe-59 30 <tLD - -

(LLD 0 Co-58 15 <LLD - -

<LLD 0 C&40 15 <LLD - - <LLD 0 Zn-65 30 <LLD - -

<tLD 0 Zr-Nb-95 15 <LLD - -

(LLD 0 Cw134 10 <LLD - -

(LLD 0 Cs-137 10 <LLD - -

<LLD 0 Ba-La-140 15 <tLD - -

<LLD 0 Ce-144 60 (LLD - -

<LLD 0

?

I 17 1

, , ~ ~ - - . . - -

2 l

.a ;

I l

1 TaNe 5.4. Radiation Environmental Monitoring Program Summary.

Name of Facihty Monticello Nuclear Generating Plant Docket No. 50-263 _l Location of Facihty Wright, Minnesota Reporting Period January - Dewmber 1993 l (County, State) i Indicator Location with flighest Control Number Sample Type and Locations Quarterly Mean Locations Non-Type Number of LLo b. Mean (F)C Mean (F)C Mean (F)c Routine (Units) Analyses a gangec Locationd Rangec Range Results' Dnnking GB 12 1.0 2.6 (12/12) M-14, Minneapolis 2.6 (12/12) None 0 Water (pCi/L) (1.5-5.8) 36 mi @ 128*/SE (1.5-5.8) 1-131 12 1.0 <tLD - -

None 0 11-3 4 330 (LLD - -

None 0 I

~!

GS 12 I i

M n-54 15 <tLD - - None 0 Fe-59 30 <LLD - -

None O Co-58 15 <LLD - -

None O Co-60 15 <LLD - -

None 0 Zn-65 30 <LLD - -

None 0 Zr-Nb-95 15 (LLD - -

None 0 ,

i Cs-1M 10 <LLD - -

None O Cs-137 to <LLD - -

None 0 Da-La-140 15 <LLD - -

None- 0 Ces144 43 <LLD - -

None o Well' Vater II-3 16 330 <LLD - -

<LLD -0 j (pci/L) 4 GS 16 Mn-54 15 <LLD - -

<LLD 0 Fe-59 30 <LLD - -

<LLD 0 ,

1 Co-58 15 <LLD - -

<LLD 0 I Co-60 15 <LLD - -

<LLD 0 Zn-65 30 <LLD - -

<LLD 0 Zr-Nb-95 15 -LLD - -

<LLD 0 Cs-134 15 (LLD - -

(LLD 0 I Cs-137 18 <LLD - -

<LLD 0 Ba-La-140 15 <LLD - -

<LLD 0. .,

i Ce-144 54 (LLD - -

<LLD 0  ;

i Crops - I-131 2 0.012 (LLD - -

<LLD 0 Cabbage (pCi/g wet)

I 1

18

4 Table 5.4 Radiation Environmental Monitoring Program Summa ry.

Name of Facility- Monticello Nuclear Generating Plant Docket No. 50-263 i Location of Facility Wright, Minnesota Reporting Period January - December 1993 (County, State) indicator Location vnth Highest Control Number Sample Type and Locations Quarterly Mean Locations Non-Type Nmnber of LLDb Mean (F)C Mean (F)C Mean (F)c Routine (Units) Analyses a Range c- Locationd Range c Range Resultse Fish GS 4 (pCi/g wet)

K-40 0.1 2.86 (2/2) M-8, Upstream of 3.14 (2/2) 3.14 (2/2) 0 (2.85-2.86) Plant,0.2 mi @ (2.99-3 28) (2.99-3.28) 285*/WNW -$

Mn-54 0.01 6 <LLD - -

<LLD 0 Fe-59 0.053 <LLD - -

<LLD 0 s

Co-58 0.018 <LLD - -

<LLD 0 Co-60 0.017 <LLD - -

<LLD 0 Zn-65 0.049 <LLD - <LLD 0 Nb-95 0.024 <LLD - -

<LLD 0 Zr-95 0.027 <LLD - -

<LLD 0 Cs-1M 0.020 <LLD - -

<tLD 0 Cs-137 0.018 <LLD - -

<LLD 0 Ba-La-140 0. %K) <LLD - -

<LLD 0 Invertebrates GS 4 (pCi/g wet)

De-7 1.95 <LLD - - <LLD 0 K-40 0.1 3.86 (2/2) M-9, Downstream 3.86 (2/2) . 2.16 (2/2) 0 (0.95-6.76) of Plant,0.2 mi @ (0.95-6.76) (2.11 2.21)

<tLD 62*/ENE Mn-54 0.093 <LLD - -

<LLD 0 Co-58 0.12 <tLD - - <LLD 0 Co-60 0.11 <LLD - -

<LLD 0 ,

2n-65 0.21 <LLD - - (LLD 0 Zr-Nb-95 0.17 <LLD - -

<LLD 0 Ru-103 0.15 <LLD - -

(LLD O' Ru-106 0,77 <LLD - - <LLD 0 Cs-134 0.081 <LLD - - <LLD 0 Cs-137 0.088 <LLD - - <LLD 0 Ba-La-140 0.15 <LLD - -

<.LLD 0 Ce-141 0.14 <LLD - -

<LLD 0 Ce-144 0.51 <LLD - -

<LLD 0 19

r

.D- e Table 5.4. Radiation Environmental Monitoring Program Summary.

Name of Facility Monticello Nuclear Generating Plant Docket No. 50-263 Location of Facility Wright, Minnesota Reportmg Period January - December 1993 (County, State)

Indicator Location with lbghest Control Numt er Sample Type and locations - Quarterly Mean Locations Non-Type Number of LLob Mean (F)C Mean (F)C Mean (F)c Routine (Units) Analyses a Range c Laationd Rangee Range Results' Dottom and GS 6 Simreline Sediments Be-7 0.28 (LLD - -

<LLD 0 (pCi/g dry)

K-40 0.5 11.94 (4/4) M-15, Montissippi 12.32 (2/2) 10.11 (2/2) 0 (11.43-1237) Park,1.6 mi @ (12.07-12.57 ) (9.93-10.29) 117"/ESE Mn-54 0.025 (LLD - -

<tLD 0 Co-58 0.035 <LLD - -

<LLD 0 O>40 0.024 <LLD - -

<LLD 0 Zn-65 0.11 <LLD - -

(LLD 0 Zr-95 0.0M eLLD - -

<LLD 0 N h95 0.034 <LLD - -

<LLD 0 Ru-103 0.024 <LLD - -

<LLD 0 Ru-106 0.22 <LLD - -

<LLD 0 Cs-134 0.018 (LLD - -

<LLD 0 ,

Cs-137 0.014 0.090 (4/4) M-15, Montissippi 0.096 (2/2) <LLD 0 (0.083-0.10) Park 1.6 mi @ (0.092-0.10) 117'/ESE 11a.La-140 0.046 <LLD - - <.LLD 0 Ce-141 0.N8 <LLD - -

<LLD 0 Ce-144 0.17 <LLD - -

<LLD 0-d GD e Cross beta; CS = gamma scan. 'l b

LLD = Nominal lower limit of detection based on 4.66 sigma error for background sample.  !

C Mean and range are based on detectable measurements only. Fraction of detectable merurements at specified locations is indicated in parentheses (F).

d Locations are specified: (1) by name, and code (Table 2) and (2) by distance, direction and f.ector relative to reactor site.

e l Non-routine re.sults are those which exceed ten times the control station value. If no control station value is available, the 1 result is considered non-routine if it exceeds ten times the typical pre-operational value for the medium or location.

l l

l 20

1 g,-

q i

l i

6.0' REFERENCES flIEQ

, Arnold, J. R. and H. A. Al-Salih. ,1955. Beryllium-7 Produced by Cosmic Rays. Science 121: i 451-453.- I

.1 Eisenbud,' M. 1963. Environmental Radioactivity, McGraw-Hill, New York, New York, pp.

213,275 and 276.

1 Gold, S., H.W. Barkhau, B. Shlein, and B. Kahn,1964. Measurement of Naturally Occurring - H Radionuclides in Air, in the Naturi. Environment, University of Chicago Press, Illinois, -

369-382.

Hazleton Environmental Sciences Corporation.1979a Radiation Environmental Monitoring for l Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - l December 1978. l 1979b. Radiation Environmental Monitoring for Prairic 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.

m 1983a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1982.

1983b. Radiation Environmental Monitoring for Prairic 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," H Chemtech. October 1986, pp. 596-605. R National Center for Radiological Health,1968. Radiological Helath and Data Reports, Vol. 9, Number 12, 730-746. j Northern States Power Company.1969. Monticello Nuclear Generating Plant, Environmental l Radiation Monitoring Program, Annual Report, June 18,1968 to December 31,1968.

Minneapolis, Minnesota.

21 l

- ~ - . . _

7, ,

Northern States Power Company.1970. Monticello Nuclear Generating Plant, Environmental Radiation Surveillance, Annual Report, January 1,1969 to December 31, 1969.

Minneapolis, Minnesota.

1971. Monticello Nuclear Generating Plant, Environmental Radiation Surveillance,

. Annual Report, January 1,1970 to December 31,1970.- Minneapolis, Minnesota.

Northern States Power Company. 1977. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1,1976 to December 31,1976 (prepared by NALCO Environmental Sciences).

Minneapolis, Minnesota.

1978. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatou Commission, January 1,1977 to -

December 31,1977 (prepared by Hazleton Environmental Sciences). Minneapolis, Minnesota.

1979. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1,1978 to December 31,1978 (prepared by Hazleton Environmental Sciences). Minneapolis, Minnesota.

1980. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1,1979 to December 31,1979 (prepared by Hazleton Environmental Sciences). Minneapolis, Minnesota.

1981. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1,1980 to December 31,1980 (prepared by Hazleton Environmental Sciences). Minneapolis, Minnesota.

1982. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. . Nuclear Regulatory Commission, January 1,1981 to-December 31,1981 (prepared by Hazleton Environmental Sciences). Minneapolis, Minnesota.

1983. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1,1982 to December 31,1982 (prepared by Hazleton Environmental Sciences). Minneapolis, Minnesota.

1984. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1,1983 to December 31,1983 (prepared by Tcledyne isotopes Midwest Laboratories).

Minneapolis, Minnesota.

1985. Monticello Nuclear Generating Plant, Annual Radiation Environmental -

Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1,1984 to December 31,1984 (prepared by Teledyne Isotopes Midwest Laboratories);

Minneapolis, Minnesota.

1986. Monticello Nuclear Generating Plant, Annual Radiation Environmental .

Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1,1985 to l December 31,1985 (prepared by Teledyne Isotopes Midwest Laboratories). j Minneapolis, Minnesota.

i 1

1 22 I

z7: ,

1987. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1,1986 to December 31,1986 (prepared by Teledyne Isotopes Midwest Laboratories).

Minneapolis, Minnesota.

1988. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1,1987 to  ;

December 31,1987 (prepared by Teledyne Isotopes Midwest Laboratories).

Minneapolis, Minnesota.

1989. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1,1988 to December 31,1988 (prepared by Teledyne Isotopes Midwest Laboratories).-

Minneapolis, Minnesota.

1990. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1,1989 to December 31,1989 (prepared by Teledyne isotopes Midwest Laboratories).

Minneapolis, Minnesota 1991. Monticello Nuclear Generatini; Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1,1990 to .

December 31,1990 (prepared by Teledyne Isotopes Midwest Laboratories).

Minneapolis, Minnesota.

1992. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1,1991 to December 31,1991 (prepared by Teledyne Isotopes Midwest Laboratories).

Minneapolis, Minnesota.

1993. Monticello 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 Laboratories).

Minneapolis, Minnesota.

Teledyne Isotopes Midwest Laboratory 1993. Analytical Procedures, Revised,21 August 1992.

1993. Quality Assurance Program Manual, Revision 1, 20 August 1992 1993. Quality Control Procedures Manual, Revision 17,18 May 1993.

1993. Quality Control Program, Revision 12, 20 April 1992. n 1984a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1983.

1984b. Radiation Environmental Monitoring for Prairic 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.

23 i

1985b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1984.

.1986a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1985.

.1986b. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1985.

1987. Sampling Procedures, Monticello Nuclear Generating Plant, Revision 16,18 December 1987.

1987a, Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1986.

1987b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1986.

1988a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1987.

1988b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1987.

1989a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1988.

1989b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1988.

1990a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1989.

1990b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating .

Plant, Complete Analysis Data Tables, January - December 1989.

l' 1991a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1990.

1991b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1990.

1992a. Radiation Environmental Monitoring for Monticello Nuclear Generating.

Plant, Complete Analysis Data Tables, January - December 1991.

1992b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating .

' Plant, Complete Analysis Data Tables, January - December 1991.

1943a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1992.

.,4 1993b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating-Plant, Complete Analysis Data Tables, January - December 1992.

24 4

.1994a. Radiation Environmental Monitoring for Monticello Nuclear Generating

- Plant, Complete Analysis Data Tables, January - December 1993.

.1994b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating  !

Plant, Complete Analysis Data Tables, January - December 1993.

U.S. Atomic Energy Commission. 1972. HASL- Procedures Manual, Health and Safety )

. Laboratory, New York, NY.,10014. '

U.S. Public Health Service.1967. Radioassay Procedures for Environmental Samples, National '

Center for Radiological Health, Rockville, Maryland (Public Health Service Publication  ;

No. 999-RH-27).-

Wilson, D. W., G. M. Ward and J. E. John. son. 1969. In Environmental Contamination by  ;

Radioactive Materials, International Atomic Energy Agency, p.125.

e ,

1 l

q 1

l 1

l l

25 1

APPENDIX A INTERLABORA10RY COMPARISON PROGRAM RESULTS NOTE: Teledyne's Midwest Laboratory participates in intercomparison studies administered by U.S.' EPA i Environmental Monitoring Systems Laboratory, Las Vegas,' Nevada. The results are reported in Appendix A. Also reported are results ofin-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 information.

January,1990 through December,1993 9

se

. . = ~ _ _

1 l

l 1

Appendix A I latedaboratory Comparison Program Results I

1 Teledyne's Midwest Laboratory (formerly Hazleton Environmental Sciences) has participated in i interlaboratory comparison (crosscheck) programs since the formulation of it's quality control program in December 1971. These programs are operated by agencies which supply environmental type samples (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.

This 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 International 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 analyses on in-house " spiked" samples for the past twelve months.

Data for previous years available upon request. l l

Table A-4 lists results of the analyses on in-house " blank" samples for the past twelve months.

Data for previous years available upon request. ,

Attachment A lists acceptance criteria for " spiked" samples.

Out-of-limit results are explained directly below the result.

)

?

Al i

i

4 d December,1993 ATTACHMENT A ACCEPTANCE CRITERIA 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 pC1/ 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-906 2 to 30 pCi/ liter or kg 5.0 pCi/ liter

>30 pCi/ liter or kg 10% of known value Potassium >0.1 g/ liter or kg 5% of known value Gross alpha s20 pCi/ liter 5.0 pCi/ liter

>20 pCi/ liter 25% of known value Gross beta $100 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)*" ,

>4,000 pCi/ liter 10% of known value Radium-226,-228 <0.1 pCi/ liter ' -

15% of known value pjutonium 0.1 pCi/ liter, gram, or sample 10% of known value -

Iodine-131, s55 pCi/ liter 6.0 pCi/ liter Iodine-1296 >55 pCi/ liter 10% of known value ~ '

Uranium-238, s35 pCi/ liter 6.0 pCi/ liter Nickel-64 6 >35 pCi/ liter 15% of known value Technetium-996 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 'l

.d

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 Resultd Control Code Type Collected Analyses f2 Sigma' 1s, N=1 Limits STW-589 WATER Jan,1990 Sr-89 22.7 i 5.0 25.0 i 5.0 ' 16.3 - 33.7 Sr 90 17.3 1.2 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. AIpha 10.3 i 3.0 12.0 i 5.0 3.3 - 20.7 Gr. Beta 12.3 i 1.2 12.015.0 3.3 - 20.7 STW-592 WATER Jan,1990 Ba-133 78.010.0 74.0 i 7.0 61.9 - 86.1 Co-60 14.7 i 2.3 15.015.0 6.3 - 23.7 Cs-1M 17.3 i 1.2 18.015.0 9.3 - 26.7 Cs 137 19.311.2 18.015.0 9.3 - 26.7 Ru-106 133.3 i 13.4 139.0 1 14.0 114.8 - 163.2 7m-65 135.0 i 6.9 -

139.0 i 14.0 114.8 - 163.2 STW-593 WATER Feb,1990 H-3 4827.0 i 83.0 4976.0 1 498.0 4113.0 - 5839.0 STW-594 WATER Mar,1990 Ra-226 5.0 i 0.2 4.910.7 4.1 - 5.7 -

Ra-228 13.510.7 12.7 i 1.9 9.4 - 16.0 STW-595 WATER Mar,1990 Uranium 4.010.0 4.0 i 6.0 0.0 - 14.4 STAF-596 AIR FILTER Mar,1990 Cs-137 9,311.2 10.015.0 1.3 - 18.7 Cr. Alpha 7.3 i 1.2 5.0i 5.0 0.0 - 13.7 G r. Deta 34.0f 0.0 31.0 i 5.0 22.3 - 39.7 Sr 90 10.0i 0.0 10.011.5 7.4 - 12.6 STW-597 WATER Apr,1990 Gr. A1pha 81.0 i 3.5 90.0 i 23.0 50.1 - 129.9 Ra-226 4.9 i 0.4 5.0 i 0.8 . 3.6 - 6.4  :

Ra-228 10.6 i 0.3 10.2 i 1.5 7.6 - 12.8 U 18.713.0 20.0 i 6.0 9.6 - 30.4 STW-598 WATER Apr,1990 Cs 134 16.0 i 0.0 15.015.0 6.3 - 23.7 Cs-137 19.012.0 15.015.0 6.3 - 23.7 Gross Beta 51.0110.1 52.015.0 43.3 - 60.7 ,

Sr-89 9.3 1.2 10.0 i 5.0 1.3 - 18.7- I I

Al-1

. -. ._ _ . . - -. 2 . _ . . - - . - . a 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 Resultd Control Code Type Coller.ted Analyses 12 Sigma' 1s, N=1 Limits Sr-90 10.3 i 3.1 10.0 i 1.5 8.3 - 11.7 STM-599 MILK Apr,1990 Cs-137 26.016.0 24.0 i 5.0 15.3 - 32.7 I-131 98.7 i 1.2 99.0110.0 81.7 - 116.3 K 1300.0 I 69.2 1550.0 i 78.0 1414.7 - 1685.3 The K analysis was repeated in triplicate; result of reanalysis was 1421.7195.3 mg/L. No further action is planned.

Sr-89 21.7 i 3.1 - 23.015.0 14.3 - 31.7 Sr-90 21.0 i 7.0 23.0 i 5.0 14.3 - 31.7 STW-600 WATER May,1990 Sr-89 6.0 i 2.0 7.0 i 5.0 0.0 15.7 R Sr-90 6.7 i 1.2 7.015.0 0.0 - 15.7 -

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 13.4fl.0 pCi/L. No further action is planned.

Gr. Beta 12.311.2 15.0 i 5.0 6.3 - 23.7 STW-602 WATER Jun,1990 Ba-133 100.718.1 99.0 i 10.0 81.7 - 116.3 Co-60 25.3 a 2.3 24.015.0 15.3 - 32.7 Cs-134 23.7 i 1.2 24.015.0 18.2 - 29.8 Cs-137 27.713.1 25.0 i 5.0 16.3 - 33.7' Ru-106 202.7 i 17.2 210.0 1 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 H-3 2927.0 i 306.0 2933.0 i 358.0 2312.0 - 3554.0 STW-604 WATER Jul,1990 .

Ra-226 11.810.9 12.1 i 1.8 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 20.311.7 20.8 i 3.0 15.6 - 26.0 STW 606 WATER Aug,1990 1-131 43.0 i 1.2 39.016.0 28.6 - 49.4 STW-607 WATER Aug,1990 Pu-239 10.0 i 1.7 9.1 1 0.9 7.5 - 10.7 STAF-608 AIR FILTER Aug,1990 Cs-137 19.012.0 20.0 i 5.0 11.3 - 28.7 Al-2 i

b . ..

Table A 1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne's kidwest Laboratory results for various sample media'.

Concentration in pCi/L' Lab Sample Date Tcledyne Results EPA Resultd Control Code Type- Collected Analyses 12 Sigma' 1s, N=1 Limits Gr. Alpha 14.0 i 0.0 10.015.0 1.3 - 18.7 Gr. Beta 65.3 i 1.2 62.015.0 53.3 - 70.7 St-90 19.016.9 20,0 i 5.0 11.3 - 28.7 STW-609 WATER Sep,1990 St-89 9.0 i 2.0 10.015.0 1.3 - 18.7.

Sr-90 9.0 i 2.0 9.0 1 5.0 0.3 17.7 S'lW 610 WATER Sep,1990 Gr. Alpha 8.311.2 10.0 i 5.0 1.3 18.7 Gr. Beta -10.3 i 1.2 10.0 i 5.0 1.3 - 18.7 STM-611 Mif K Sep,1990 Cs-137 20.0 i 2.0 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 11.713.1 16.015.0 7.3 - 24.7-Sr-90 15.0 i 0.0 20.0 i 5.0 11.3 - 28.7 STW-612 WATER Oct,1990 -

Da-133 116.7 i 9.9 110.0 i 11.0 90.9 - 129.0 Co-60 20.3 i 3.1 20.015.0 11.3 - 28:7-Cs-134 11.0 i 0.0 12.015.0 3.3 - 20.7 -

Cs-137 14.0 i 2.0 12.015.0 3.3 20.7 Ru-106 152.0 i 8.0 151.0 i 15.0 125.0 - 177,0-Zn-65 115.3 i 12.2 115.0 i 12.0 94.2 - 135.8 STW-613 WATER Oct,1990 11 3 7167.0 1 330.0 7'03.0 1 720.0 5954.0 - 8452.0 STW-614 WATER Oct,1990 Gr. Alpha 68,.7 i 7.2 62.0116.0 34.2 - 89.8 Ra-226 12.910.3 13.612.0 10.1 - 17.1 Ra-228 4.210.6 5.0 i 1.3 2.7 - 7.3 U 10.4 i 0.6 10.213.0 5.0 - 15.4 STW-615 WATER Oct,1990 Cs-134 9.0i 1.7 7.015.0 0.0 - 15.7-Cs-137 7.711.2 5.0i 5.0 - - 0.0 -'13.7 Gross Deta 55.018.7-- .53.015.0 44.3 - 61.7 Sr-89 15.7 i 2.9 20.015.0 11.3 - 28.7 Sr-90 12.0 i 2.0 -

15.015.0 6.0 - 23.7 l

A 1-3 {

E Table A-1. U.S. Environmental Protection Agency's crosscheck program, cornparison of EPA and Tcledyne's '

Midwest Laboratory results for various sample media',

Concentration in pCi/Lb Lab Sample Date Teledyne Results EPA Resultd Control Code Type Collected Analyses i2 Sigma' 1s, N=1 Limits STW-616 WATER Nov,1990 Ra-226 6.811.0 7.4 i l.1 5.5-9.3 Ra-228 5.311.7 7.7i 1.9 4.4 - 11.0 STW-617 WATER Nov,1990 U 35.010.4 35.513.6 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 4.3 i 1.2 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 3.6i0.2 3.3i0.3 2.8 - 3.8 '

STW-620 WATER Jan,1991 Gr. Alpha 6.7i 3.0 5.0i5.0 0.0 - 13.7 Cr. Beta 6.311.2 5.0i 5.0 0.0 - 13.7 STW-621 WATER Feb,1991 Ba-133 85.7 i 9.2 75.0 i 8.0 61.1 - 88.9 Co-60 41.3 i 8.4 40.0i 5.0 31.3 - 48.7 Cs-134 9.0 t 2.0 8.015.0 0.0 - 16.7 Cs-137 9.7i 1.2 8.0 i 5.0 0.0 - 16.7 Ru-106 209.7 i 18.6 186.0

• 19.0 153.0 - 219.0 Zn-65 166.71 19.7 149.0 i 15.0 123.0 - 175.0 STW-622 WATER Feb,1991 1-131 81.3 i 6.1 75.018.0 61.1 - 88.9 STW-623 WATER Feb,1991 H-3 4310.0 i 144.2 4418.0 i 442.0 3651.2 - 5184.8 STW-624 WATER Mar,1991 Ra-226 31.4 i 3.2 31.8 i 4.8 23.5 - 40.1 Ra-228 21.115.3 11.9 - 30.3 No data for Ra-228 was reported; sample was lost during analysis.

STW-625 WATER Mar,1991 U 6.7i 0.4 7.6 i 3.0 2.4 - 12.8 STAF-626 AIR FILTER Mar,1991 Cs-137 33.7 i 4.2 40.0 i 5.0 31.3 - 48.7 l

- I A1-4

~l

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 Teledyne Results EPA Result' Control Code Type Collected Analyses f2 Sigma

• 1s, N=1 Limits Gr. Alpha 38.7 i 1.2 25.016.0 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.

G r. Beta 130.014.0 124.0 i 6.0 113.6 - 134.4 Sr-90 35.711.2 40.0 i 5.0 31.3 - 48.7 STW-627 WATER Apr,1991 Gr. Alpha 51.016.0 54.0 i 14.0 29.7 - 78.3 Ra-226 7.010.8 8.0i 1.2 5.9 - 10.1 Ra-228 9.711.9 15.2 i 3.8 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 5.0 15.3 - 32.7 Cs-137 29.0 i 2.0 25.015.0 16.3 - 33.7 GrossBeta 93.3 i 6.4 115.0 i 17.0 85.5 - 144.5 St-89 21.0 3.5 28.015.0 19.3 - 36.7 Sr-90 23.010.0 26.015.0 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 65.3114.7 60.016.0 49.6 - 70.4 K-40 1591.7 i 180.1 1650.0 i 83.0 1506.0 - 1794.0 St-89 24.0 i 8.7 32.0 i 5.0 23.3 - 40.7 Sr-90 28.0 +. 2.0 32.0 i 5.0 23.3 - 40.7-STW-630 1NATER May,1991 Sr-89 40.712.3 39.0 i 5.0 30.3 - 47.7 Sr-90 23.7 i 1.2 24.015.0 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 46.0i 0.0 46.015.0 37.3'- 54.7 STW-632 WATER Jun,1991 Ba-133 74.0 i 6.9 62.0 i 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 10.0f 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 14.015.0 5.3 - 22.7 Ru-1% 162.3 i 19.0 149.0 i 15.0 123.0 - 175.0 S

Al-5

. . o 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 Zn-65 119.3 1 16.3 108.0 i 11.0 88.9 - 127.1 STW-633 WATER Jun,1991 H3 13470.0 i 385.8 12480.0 i 1248.0 10314.8 - 14645.2.

STW-634 WATER Jul,1991 Ra-226 14.9 i 0.4 15.912.4 11.7 - 20.1 Ra-228 17.6i 1.8 16.7 i 4.2 9.4 - 24.0 STW-635 WATER Jul,1991 U 12.810.1 , 14.2 i 3.0 9.0 - 19.4 STW-636 WATER Aug, '991 1-131 19.3 i 1.2 20.0 i 6.0 9.6 - 30.4 STW-637 WATER Aug,1991 Pu-239 21.4 i 0.5 19.4 i 1.9 16.1 - 22.7 ST AF-638 AIR FILTER Aug,1991 Cs-137 26.3 i 1.2 30.0 i 5.0 21.3 - 38.7 Gr. AIpha 33.0 i 2.0 25.0 i 6.0 14.6 - 35.4 Gr. Beta 88.7 i 1.2 92.0 i 10.0 80.4 - 103.6 St-90 27.0i 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 - 33.7 i 3.2 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 I-131 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 i 340.8 1740.0 i 87.0 1589.1 - 1890.9  !

St-89 20.3 i 5.0 25.0 i 5.0 16.3 - 33.7 Sr-90 19.7 i 3.1 25.0 i 5.0 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 3 Cs-134 9.7i 1.2 10.015.0 1.3 - 18.7 I

Al-6 l

.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 Resultd Control Code Type Collected Analyses 12 Sigma

• 1s, N=1 Limits Cs-137 11.0 i 2.0 10.0 i 5.0 1.3 - 18.7 Ru 1% 196.3 1 15.1 199.0 1 20.0 164.3 - 233.7 Zn-65 75.7 i 8.3 73.0 i 7.0 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 Gr. Alpha 73.0 i 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 22.215.6 12.5 - 31.9 U 13.510.6 13.5 i 3.0 8.3 - 18.7 STW-645 WATER Oct,1991 Co-60 20.3 i 1.2 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 65.0 i 10.0 47.7 - 82.3 Sr-89 9.7i 3.1 10.0 i 5.0 1.3 - 18.7 Sr-90 8.711.2 10.015.0 1.3 - 19.7 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 i 2.0 4.6 - 11.6 STW-647 WATER Nov,1991 U 24.7 i 2.3 24.913.0 19.7 - 30.1 STW-648 WATER Jan,1992 Sr-89 42.7i 6.4 51.0 i 5.0 42.3 - 59.7 St-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 Cr. Alpha 23.719.2 30.0 i 8.0 16.1 - 43.9 Gr. Deta 27.7 i 4.2 -30.015.0 21.3 - 38.7 STW 651 WATER Feb,1992 1-131 60.3 i 4.2 59.0 i 6.0 48.6 - 69.4 STW-652 WATER Feb,1992 Ba-133 79.0 i 3.4 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 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 Resultd Control Code Type Collected Analyses 12 Sigma' 1s, N=1 Limits Cs-137 51.0 i 3.4 49.015.0 40.3 - 57.7 Ru 106 188.7 1 28.8 203.0 i 20.0 168.3 - 237.7' Zn-65 148.0 i 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 1 790.0 6533.4 - 9274.6 STW-654 WATER Mar,1992 Ra-226 9.0 i 0.4 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 U 25.1 i 1.9 25.3 i 3.0 20.1 - 30.5 STW-657 WATER Mar,1992 Rn-222 No Data is available; Special EPA testing.

STAF458 AIR FILTER Mar,1992

• Cs-137 10.010.0. 10.0 i 5.0 1.3 - 18.7 Cr. A1pha 7.010.0 7.0i5.0 0.0 - 15.7 Gr. Beta 39.311.6 41.015.0 32.3- 49.7 Sr 90 13.7 i 1.6 15.0 i 5.0 6.3 - 23.7 STW-659 WATER Apr,1992 Gr. Alpha 35.7 i 6.1 40.0 i 10.0 22.7 - 57.3 Ra-226 12.7 i 1.2 14.9 i 2.2 11.1 - 18.7 Ra 228 14.5 i 2.1 14.013.5 7.9- 20.1 U 3.9 i 0.2 4.0 i 3.0 0.0 - 9.2 STW-660 WATER Apr,1992 Co-60 61.0 i 4.0 56.015.0 47.3 - 64.7 Cs-134 24.3 i 1.2 24.015.0 '15.3 - 32.7 Cs-137 24.0 i 2.0 22.0 t 5.0 13.3 30.7

. Gross Beta 113.017.2 140.0 1 21.0- 103.6 - 176.4 Sr.89 12.3 i 4.2- 15.015.0 6.3 - 23.7 Sr-90 15.0 i 1.2 17.015.0 8.3 - 25.7 STM-661 MILK Apr,1992 Cs-137 39.312.3 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 A18

9 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 Resultd Control Code Type Collected Analyses 12 Sigma' 1s, N=1 Limits K-40 1610.0 i 72.1 1710.0 i 86.0 1560.8 - 1859.2-Sr-89 25.3 i 7.6 38.015.0 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 pCi/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 St-89 24.0 t 4.0 29.015.0 20.3 - 37.7 Sr-90 6.7 i 1.2 ,

8.0 i 5.0 0.0 - 16.7 STW-663 WATER May,1992 Gr. A1pha 12.3 i 2.1 15.0 i 5.0 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 98.0 i 10.0 80.7 - 115.3 Co-60 20.3 i 1.2 20.0 i 5.0 11.3 - 28.7 Cs-134 14.3 i 2.3 15.0 i 5.0 6.3 - 23.7 Cs-137 15.012.0 15.0 i 5.0 6.3 - 23.7 Ru-1% 142.7 i 23.7 141.0 i 14.0 116.7 - 165.3 Zn-65 103.3 1 10.6 99.0 i 10.0 81.7 - 116 ;

- STW-665 WATER Jun,1992 H3 2153.3 i 144.6 2125.0 1 347.0 1523.0 - 2727.0 STW-666 WATER Jul,1992 Ra-226 22.3 i 2.2 24.9 i 3.7 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 1 0.9 '9.0i0.9 7.4 - 10.6 .

STAF-670 AIR FILTER Aug,1992 AIpha 25.7 i 1.2 30.0 i 8.0 16.1 - 43.9 Beta 69.012.0 69.0 i 10.0 - 51.7 - 86.3 Cs-137 16.0 i.0.0 18.015.0 9.3- 26.7 Sr-90 26.0 i 4.0 25.0 i 5.0 16.3 - 33.7 -

Al-9

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 Resultd Control Code Type Collected Analyses f2 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 Sr-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 41.3118.6 50.0 i 5.0 14.3 - 58.7 STM-673 MILK Sep,1992 Cs-137 14.0 i 3.5 15.015.0 6.3 - 23.7 I-131(gamma 109.7 1 19.4 100.0 i 10.0 82.7 - 117.3 K 1540.0 i 103.9 1750.0 i 88.0 1597.3 - 1902.7 The 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 15.015.0 6.3 - 23.7 Sr-90 12.711.6 15.0 i 5.0 6.3 - 23.7 STW-674 WATER Oct,1992 Ba-133 80.3 i 9.0 74.0 i 7.0 61.9 - 86.1 Co-60 11.3 i 2.3 10.0 i 5.0 1.3 - 18.7 Cs-134 9.7i 2.3 8.0i 5.0 0.0 - 16.7 Cs-137 9.7i 1.2 8.0i 5.0 0.0 - 16.7 Ru-106 170.7f 2.3 175.0 1 18.0 143.8 - 206.2 Zn-65 169.7 i 25.0 148.0 i 15.0 122.0 - 174.0 STW-675 WATER Oct,1992 H-3 5896.7 1 136.2 5962.0 i 596.0 4928.0 - 6996.0 STW-676 WATER Oct,1992 Gr. Alpha 24.7 i 5.0 29.017.0 16.9 - 41.1 Ra-226 7.1i0.4 7.4 i 1.1 5.5 - 9.3 Ra-228 11.5 i 1.0 10.012.5 5.7 - 14.3 Uranium 9.7 i 0.5 10.213.0 5.0 - 15.4 STW-677 WATER Oct,1992 Co-60 15.012.0 15.0 A 5.0 6.3 - 23.7 Cs-134 5.7i 1.2 5.015.0 0.0 - 13.7.

Cs-137 8.0 i 2.0 8.0i 5.0 0.0 - 16.7 Gr. Deta 42.7 i 8.1 53.0 i 10.0 35.7 - 70.3 Sr-89 6.7 i 1.2 8.015.0 0.0- 16.7 Sr-90 10.0 i 2.0 110.0 i 5.0 1.3 - 18.7 Al-10

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 Tcledyne Results EPA Resultd Control Code Type Collected Analyses 12 Sigma' 1s, N=1 Limits STW-678 WATER Oct,1992 Ra-226 7.510.8 7.5i1.1 5.6 - 9.4 Ra-228 5.8 i 0.7 5.0i 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 e STW-681 WATER Jan,1993 Pu-239 17.5 i 1.6 20.012.0 16.5 - 23.5-STW-682 WATER Jan,1993 A1pha 17.1 i 1.2 34.0 i 9.0 18.4 - 49.6 Gross Alpha analysis was repeated with similar results. An investigation of possible causes for the deviation from the EPA was conducted with no cause discovered. The sample was spiked with Th-230; so Alpha Spec Analysis for Th-230 was performed ,

in triplicate with results of 15.512.1,13.411.4, and 14.8f2.0. It should be noted that 66% of all participants failed this analysis with a grand average of 17.1. '1his 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 1131 106.0 i 10.0 -100.0 i 10.0 82.7 - 117.3-STW-684 WATER Feb,1993 Uranium 7.2i0.5 7.6 i 3.0 2.4 - 12.8 -

STW-685 WATER Mar,1993 Ra-226 9.3 i 1.3 9.811.5 7.2 - 12.4 Ra-228 20.8 i 2.2 18.5 i 4.6 10.5 - 26.5 STW-686 WATER Apr,1993 A1pha 88.318.1 95.0 i 24.0 53.4 - 136.6 <

Ra-226 25.4 i 1.4 24.9 i 3.7 18.5 - 31.3 Ra-228 17.4 i 1.2 19.014.8 10.7 - 27.3

'P O

Al-11

j 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 Code Type Collected Analyses f2 Sigma' . 1s, N=1 Limits Uranium 27.8 i 2.2 28.913.0 23.7 - 34.1 STW-687 WATER Apr,1993 Beta 141.7 i 9.0 177.0 1 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 27.0 i 5.0 18.3 - 35.7 Cs-137 30.010.0 32.0 i 5.0 23.3 - 40.7 Sr-89 28.7 i 9.4 41.0 i 5.0 32.3 - 49.7 he 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 act:on is anticipated unless conditions warrant.

Sr-90 28.0 i 3.5 29.0 i 5.0 20.3 - 37.7 STW-688 WATER Jun,1993 H-3 9613.3 i 46.2 9844.0 i 984.0 8136,8 - 11551.2 STW-689 WATER Jun,1993

• Ba-133 101.7 1 10.3 99.0 i 10.0 81.7 - 116.3 Co-60 17.3 i 4.6 15.0 i 5.0 6.3 - 23.7 Cs-134 5.7i 1.2 5.015.0 0.0- 13.7 Cs-137 6.0f 2.0 5.0i 5.0 0.0- 13.7 Ru-106 108.0 i 8.0 119.0 i 12.0 98,2 - 139.8 Zn-65 114.0 i 13.2 103.0 i 10.0 85.7 - 120.3 i 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 A1pha 15.012.7 15.015.0 6.3 - 23.7 -

Beta 41.3 i 4.9 43.016.9 31.0 - 55.0 ,

STW-692 WATER Aug,1993 Uranium 24.911.4 25.3 i 3.0 20.1 - 30.5 STAF-693 AIR FILTER Aug,1993 A1pha 17.011.0 19.015.0 10.3 - 27.7 Beta 47.3 t 0.6 47.015.0 38.3 - 55.7 Cs-137 10.0 i 1.0 9.015.0 0.3- 17.7' Sr 90 19.3 i 0.6 19.015.0 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 V

Table A 1. U.S. Erwironmental 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 Resultd Control Code Type Collected Analyses 12 Sigma' 1s, N=1 Limits Ra-228 21.011.6 . 20.4 i 5.1 11.6 29.2 STM-695 MILK Sep,1993 .

Cs-137 49.013.0 49.0 i 5.0 40.3- 57.7' I-131 125.314.5 120.0 i 12.0 99.2 - 140.8 K 1616.71 37.9 1679.0 i 84.0 1533.3 - 1824.7 Sr-89 19.3iJ.5 30.0 i 5.0 21.3 38.7 Report was received 01-18-94; an investigation is underway as to the cause of the low Sr-89 results. 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 nave 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 9

STW-696 WATER Oct,1993 1-131 116.7 i 2.3 117.0 i 12.0 96.2 - 137.8 STW-697 WATER Oct,1993 Gr. Alpha 39.711.5 40.0110.0 22.7 - 57.3 Ra-226 10.610.5 , 9.9i1.5 7.3 - 12.5 Ra-228 13.2 i 1.5 12.513.1 7.1 - 17.9 Uranium 15.310.6 15.113.0 9.9 - 20.3 STW-698 WATER Oct,1993 Ueta 52.0 i 1.0 58.0 i 10.0 40.7 - 75.3 Co-60 10.7 i 0.6 10.015.0 1.3 - 18.7 Cs-134 10.0 i 1.0'. 12.0 i 5.0 3.3 - 20.7 Cs-137 12.3 i 1.2 10.0 i 5.0 1.3 - 18.7 St-89 11.310.6 15.015.0 6.3 - 23.7 Sr-90 11.010.0 10.015.0 1.3 18.7 STW-699 WATER Oct,1993 A1pha 18.312.5 20.0 i 5.0 11.3 - 28.7.

Deta 13.7 i 0.6 15.0 i 5.0 6.3 - 23.7 STW 700 WATER Nov,1993 1I-3 7310.0 i 175.2 7398.0 i 740.0 6114.1 - 8681.9 l STW-701 WATER Nov,1993 Ba-133 75.717.6 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 l

A1-13 .

l 1

1

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 Resultd Control '

Code Type Collected Analyses i2 Sigma

• 1s, N=1 Limits Cs 134 51.3 i 5.9 . 59.015.0: 50.3 - 67.7 Cs-137 41.711.2 40.015.0 31.3 - 48.7 Ru-106 163.3 i 3.2 201.0 i 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 i 15.0 124.0 - 176.0

• Results obtained by Tcledyne Brown Engineering Environmental Services Midwest Laboratory as a participant in the environmental sampic 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 samples, which are in pCi/ Filter.

' Unless otherwise indicated, the TI3EESML results are given as the mean 12 standard deviations for three determinations.

d USEPA results are presented as the known values and expected laboratory precision (1s,1 determination) and control limits as defined by the EPA.

I I

i

- Al-14 I i

l I

l

Table A 2. Crosscheck program results; Thermoluminescent Dosimeters. (TLDs).

. mR Lab Teledyne Results Known Average i 2 Sigma Code TLD Type Date Measurement t 2 Sigma Value i 2 Sigrna (All Participants) 2nd InternationadateICQmpArison l 115-2 CaF2 : Mn Bulb Apr,1976 l Field 17.0i l.9 17.1 16.4 7.7 Lab 20.8 i 4.1 21.3 18.8 i 7.6 Second International Intercomparison of Environmental Dosimeters conducted in April of 1976 by the Health and Safety Laboratory (HASL), New York, New York, and the School of Public IIcalth of the University of Texas, Houston, Texas.

3rd International Intercomparison 115-3 CaF2 : Mn Bulb Jun,1977 FieId 30.7 i 3.2 34.9 i 4.8 31.5 i 3.0 Lab 89.6 i 6.4 91.7 i 14.6 86.2 i 24.0 Third International Intercomparison of Environmental Dosimeters conducted in the summer of 1997 by Oak Ridge National Laboratory and the School of Public Health of the University of Texas, Houston, Texas.

4th IntcrnationalJnicIcomp.arison 115-4 CaF2 : Mn Bulb Jun,1979 Field 14.111.1 14.111.4 16.019.0 Lab, liigh 40.411.4

• 45.8 i 9.2 43.9 i 13.2 Lab, Low 9.8 i 1.3 12.2 i 2.4 12.017.4 Fourth International Intercomparison of Environmental Dosimeters conducted in the summer of 1979 by the Scnool of Public Health of the University of Texas, Houston, Texas.

5thlaternalienallnterromparisen 115-5A CaF2 : Mn flulb Oct,1980 Fie1d 31.4 i 1.8 30.016.0 30.2 i 14.6 12b,End 96.615.8 88.4 i 8.8 90.7131.2 Lab, Start 7/.4i5.8 75.2 i 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 Lab,End 85.4 i 11.7 88.418.8 90.7f 31.2 -

Lab, Start' 81.li 7.4 ' 75.217.6 75.8140.4 Fifth International 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.

ZihlaternationaLInterrompaIison 115-7A LiF-100 Chips Jun,1984  !

FieId 75.412.6 75.8 i 6.0 75.1129.8 A2-1

Table A 2. Crosscheck program results;'Ihermoluminescent Dosimeters. (TLDs).

.mR Lab Teledyne Results Known Average i 2 Sigma Code TLD Type Date Measurement i 2 Sigma Valuei2 Sigma (All Participants)

Lab, Co-60 80.0 i 3.5 79.9 i 4.0 77.9 i 27.6 Lab, Cs-137 66.612.5 75.0 i 3.8 73.0 i 22.2-115-7B CaF2 : Mn Bulb Jun,1984 Fieid 71.5 i 2.6 75.8 i 6.0 75.1129.8 Lab, Co-60 84.816.4 79.9 i 4.0 77.9 i 27.6 Lab, Cs-137 78.811.6 75.013.8 73.0122.2-115-7C CaSOpDy Jun,1984 Cards FieId 76.8 i 2.7 75.8 i 6.0 75.1 i 29.8 Lab, Co-60 82.5 i 3.7 79.9 i 4.0 77.9 i 27.6 Lab, Cs-137 79.013.2 75.013.8 73.0122.2 Seventh International Intercomparison of Environmental Dosimeters conducted in the spring and summer of 1984 at Las Vegas, Neveda, and sponsored by the U.S. Department of Energy, The Nuclear Regulatory Commission, and the U.S. Environmental Protection Agency. Teledyne did not participate in the Sixth International Intercomparison of Environmental Dosimeters.

811LIDICInaliQnallnlCIrampansen 115-8A LaF-100 Chips Jan,1986 Field, Site 1 29.5 f l.4 29.711.5 28.9112.4 Field, Site 2 11.310.8 10.410.5 10.119.1 Lab, Cs-137 13.710.9 17.2 i 0.9 16.2 i 6.8 115-8 B CaF2 : Mn Bulb Jan,1986 Field, Site 1 32.311.2 29.7 i 1.5 28.9112.4 Field, Site 2 9.011.0 .

10.410.5 ' 10.l i 9.0 Lab, Cs-137 15.810.9 17.210.9 16.2i 6.8 115-8C CaSOpDy Jan,1986 Cards Field, Site 1 32.210.7 29.711.5 ~ 28.9 i 12.4 Field, Site 2 10.6 i 0.6 10.4 i 0.5 10.1i 9.0 Lab, Cs-137 18.110.8 17.2 i 0.9 16.2 i 6.8 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.

1011LInternational Intercomparison A2-2

Table A-2. Crosscheck program results; 7hermoluminescent Dosimeters. (TLDs). >

mR.

Lab Teledyne Results Known . Average i2 Sigma Code TLD Type Date - Measurement i 2 Sigma Value i 2 Sigma (All Participants) 115-10A LiF-100 Chips Aug,1993 Fie1d 25.7 i 1.4 27.0 i 1.6 26.4 i 10.2 Lab 22.7 i 1.6 25.9

• 1.3 25.0 i 9.4 Lab 62.7 i 2.6 72.7 i 1.9 69.8 i 20.3 115-10B CaSOgDy Aug,1993 Cards FieId 26.0 i 2.3 27.0 i 1.6 26.4 i 10.2 Lab 24.1 i 1.7 25.911.3 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.

.Teledyne Testing 89-1 LiF-100 Chips Sep,1989 Lab 21.010.4 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 Teledyne Nov,1989 CaSOgDy Cards Lab 20.9 i 1.0 20.3 ND ND = No Data; Teledyne Testing was only performed by Tcledyne.

Cards were irradiated by Teledyne Isotopes, Inc., Westwood NJ. in November,1989.

90-1 Teledyne Jun,1990 CaSOjDy 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 CaSOgDy Cards Lab 100.8 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..

1 A2-3

. ~ . - . _ ~ = _.

9 4-Table A 2. Crcsscheck program results; Thermoluminescent Dosimeters. (TLDs).

mR Lab Teledyne Results Known Average i2 Sigma Code TLD Type Date Measurement i 2 Sigma Value i 2 Sigma (All Participants) 91-1 Teledyne Oct,1990 CaSO4 :Dy Cards Lab l 33,412.0 32.0 ND 12b 2 55.214.7 58.8 ND Lab 3 87.8 i 6.2 85.5 ND ND = No Data; Teledyne Testing was only performed by Teledyne.

Cards were irradiated by Teledyne Isotopes,Inc., Westwood NJ. on October 8,1991.

92-1 LiF-100 Chips Feb,1992 Lab 1 11.110.2 10.7 ND Lab 2 25.6 i 0.5 25.4 ND lab 3 46.410.5 46.3 ND ND = No Data; Teledyne Testing was only performed by Teledyne.

Cidps were irradiated by Teledyne Isotopes, Inc., Westwood NJ. on February 26,1992, 92-2 Teledyne Apr,1992 CaSO :Dy Cards Reader 1, #1 20.1i 0.1 20.1 ND Reader 1, #2 40.6 i 0.1 40.0 ND Reader 1, #3 60.011.3 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 10.011.0 10.2 ND '

lab 2 25.512.2 25.5 ND -

12b 3 42.7i 5.7 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.

i

'l A2-4 l o

l Tab!c A-3. In-house " spike" samples.

Concentration in pC1/11 Lab Sample Date Teledyne Results Known Control' Code Type Collected Analyses 2s, n=1 b Activity Limits QCMI-26 MILK Jan,1990 Cs-134 19.311.0 20.8 10.8 - 30.8 Cs-137 25.2 i 1.2 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 63.812.2 62.6 50.1 - 75.1 QCMI-29 MILK Apr,1990 Cs-134 18.311.0 . 19.7 9.7 - 29.7 Cs-137 20.3i 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 Sr-90 19.412.5 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 20.0 i 0.2 19.7 - 9.7 - 29.7 Cs-137 28.711.4 22.7 12.7 - 32.7 QCW-63 WATER Apr,1990 1-131 63.518.0 66.0 52.8 - 79.2 QCW-64 WATER Apr,1990 11-3 1941.0 t 130.0 1826.0 1141.5 - 2510.5 QCW-65 WATER Jun,1990 Ra-226 6.4 i 0.2 6.9 4.8 - 9.0 QCW-66 WATER Jun,1990 Uranium 6.2 0.2 6.0 3.6 - 8.4

. QCM1-30 MILK Jul,1990 Cs-134 46.011.3 49.0 39.0 - 59.0 Cs-137 27.6i 1.3 25.3 15.3 - 35.3 Sr-89 12.8 i 0.4 18.4 8.4 - 28.4 Sr-90 18.2i 1.4 18.7 8.7 - 28.7 QCW-68 WATER Jul,1990 Gr. Alpha 9.810.3 10.6 0.6 - 20.6 Gr. Beta 11.4 i 0.6 11.3 1.3 - 21.3 QCMI 31 MILK Aug,1990 1-131 68.811.6 61.4 49.1 - 73.7 A3-1

Table A 3. In-house " spike" samples.

Concentration in pC1/11 Lab Sample Date Teledyne Results Known Control' Code Type Collected Analyses 2s, n=16 Activity Limits QCW-69 WATER Sep,1990 Sr-89 17.7 i 1.6 19.2 9.2 - 29.2 St 90 13.9 i l.6 17.4 7.4- 27.4 QC Mi-32 MILK Oct,1990 Cs-134 25.8 i 1.2 27.3 17.3 - 37.3 Cs 137 25.3 i 2.0 22.4 12.4 32.4 I-131 34.8 i 0.2 32.4 20.4 44.4 QCW-70 WATER Oct,1990 1I-3 2355.0 i 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 18.3 i 2.7 16.8 6.8 - 26.8 Cs-134 28.312.3 27.0 17.0 - 37.0 Cs-137 22.7 i 1.3 22.4 12,4 - 32.4 QCW.74 WATER Dee,1990 Gr. Alpha 21.4 i 1.0 26.1 13.1 - 39.2 Gr. Deta 25.9 i 1.0 22.3 12.3 - 32.3 QCMI-33 MILK Jan,1991 Cs-134 22.2 i 1.7 19.6 9.6 - 29.6 Cs-137 26.1 i 1.6 22.3- 12.3 32.3 St-89 20.7 i 3.3 21.6 11.6 - 31.6 Sr-90 19.011.4 23.0 13.0 - 33.0 ,

QCMI-34 MILK Feb,1991 1-131 '40.7 i 1.8 40.1 28.1 - 52.1 QCW-75 WATER Mar,1991 Sr-89 18.8 i 1.5 23.3 13.3 - 33.3 Er-90 16.010.8 17.2 7.2 27.2 QCMI-35 MILK Apr,1991

, j 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 48.610.8 49.2 37.2 61.2 QCW-76 WATER Apr,1991 i

1-131 56.5 i 1.7 59.0 47.2 - 70.8 QCW.77 WATER Apt,1991 Co-60 16.412.2 15.7 5.7 25.7 A3-2 l

.l l

1 l

l Table A 3. In-house " spike" samples.

Concentration in pCi/L' Lab Sample Date Teledyne Results Known Control' Code Type Collected Analyses 2s, n= 16 Activity Limits Cs 134 23.8 i 2.5 22.6 12.6 - 32.6 Cs 137 25.0 i 2,4 21.1 11.1 - 31.1 QCW 78 WATER Apr,1991 11 3 4027.0 i 188.0 4080.0 3264.0 - 4896.0 QCW-79 WATER Jun,1991 Cr. A1pha 7,4i0.7 7.8 0.0 - 17.8 Gr. Deta 11.010.7 11.0 1.0 - 21.0 SPM 36 MILK Jul,1991 Cs-137 34.3 i 3.0 35.1 25.1 - 45.1 1-131 14.4 i 1.9 18.3 6.3 - 30.3 St-89 28.112.1 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 22.7 i 2.8 22.1 12.1 - 32.1 Cs 137 38.313.0 35.1 25.1 - 45.1 1-131 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 St-90 11.711.4 14.1 4.1 - 24.1 QCW-81 WATER Oct,1991 1131 19.1 i 0.7 20.6 8.6 - 32.6 QCW 82 WATER Oet,1991 Co-60 22.6 i 2.7 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 i1 3 4639.0 i 137.0 4382.0 3505.6 - 5258.4 QCW-84 WATER Dee,1991 Cr. A1pha 6.2 i 6.0 7.8 0.0 - 17.8 Gr. Deta 11.010.7 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 1131 76.8 i 0.9 83.7 67.0 - 100.4-Sr-89 21.6 i 6.5 31.2 21.2 - 41.2 St90 38.7 i 1.8 42.3 33.8 - 50.8 A3-3

. . l l

' Table A 3. In house " spike" samples.

Concentration in pCi/If Lab Sample Date Teledyne Results Known Controf Code Type Collected Analyses 23, n=16

• Activity I.imits QCW-85 WATER Afar,1992 St-89 26.2 3.1 32.0 22.0 42.0 Sr-90 24.4 i 1.4 28.0 18.0 38.0 i QCMI-40 MILK Apt,1992 Cs-134 58.012.6 55.9 45.9 - 65.9 Cs-137 43.713.0 38.9 28.9 - 48.9 l QCMI-41 MILK Apr,1992 1131 50.310.8 55.9 44.7 - 67.1 QCW 86 WATER Apr,1992 II 3 4080.0 i 190.0 4027.0 3221.6 - 4832.4 QCW-87 WATER Apr,1992 I-131 33.510.6 33.2 21.2 - 45.2 QCW-88 WATER Apr,1992 Co-60 17.512.7 19.7 9.7 - 29.7  ;

Cs-134 28.912.5 33.5 23.5 43.5 Cs-137 41.013.0 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. Deta 17.210.9 17.6 7.6 - 27.6 QCMI 42 MILK Aug,1992 Cs-134 20.1 i 2.8 20.2 10.2 - 30.2 Cs-137 26.2 i 2.7 26.1 16.1 - 36.1 Sr-89 41.4 i 5.9 51.2 41.0 - 61.4 Sr-90 48.912.5 51.9 41.5 - 62.3 QCW-90 WATER Sep,1992 Sr-89 6.7 i 3.4 12.6 2.6 22.6 St-90 16.111.4 15.6 5.6 - 25.6 QCMl-43 MILK Oct,1992 '

Cs-134 14.213.4 12.7 2.7 - 22.7 Cs-137 14.115.2 17.1 7.1 - 27.1 1-131 19.9 i 1.0 21.5 9.5 - 33.5 QCMI-44 MILK Oct,1992 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

Table A 3. In house " spike" samples.

Concentration in pCi/L' Lab Sample Date Teledyne Results Known Control' Code Type Collected Analyses 2s, n =16 Activity Limits QCW-91 WATER Oct,1992 1131 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 Cs-134 18.712.3 14.3 4.3 - 24.3 Cs-137 14.1 i 1.8 15.0 5.0 25.0 QCW 93 WATER Oct,1992 H3 3701.0 i 186.0 3904.0 3169.2 - 4638.8 QCW.94 WATER Oct,1992 H3 14925.0 1 339.0 15616.0 12492.8 - 18739.2 QCW-95 WATER Oct,1992 1-131 64.2 i 2.7 67.2 53.8 - 80.6 QCW-36 WATER Dec,1992 A1pha 11.512.3 15.2 9.1 21.3 Beta 26.5 i 2.0 25.7 15.4 - 36.0 QCW-96 WATER pec,1992 Gr. Alpha 8.3.10.6 10.4 0.4 - 20.4 Gr. Deta 19.811.5 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 St-89 6.7 i 3.1 8.7 0.0 18.7 St-90 20.0 i 1.2 19.2 9.2 - 29.2 SPM-3387 MILK Feb,1993 l131 72 5 i 8.4 71.5 57.2 85.8 SPVE 3401 VEGETATION Feb,1993 (SAW DUST) 1-131 994.5 1 53.2 953.7 763.0 - 1144.4 SPCII-3402 CllARCOAL Feb,1993 1131 95.2 i 12.8 95.4 76.3 - 114.5 SPW 3434 WATER Apr,1993 Gr. Alpha 10.411.8 10.4 0.4 - 20.4 l Gr. Deta 22.0 i 2.0 20.6 10.6 - 30.6 SPW 3556 WATER Apr,1993 l

Sr89 18.215.0 22.2 12.2 - 32.2 l

Sr-90 20.111.8 17.0 7.0- 27.0 A3-5 i

Table A-3. In-house " spike" samples.

Concentration in pCi/L' l Lab Sample Date Teledyne Results Known Control' Code Type Collected Analyses 2s, n=1 6 Activity Limits SPW-3597 WATER Apr,1993 H-3 5464.0 i 219.0 5428.0 4342.4 - 6513.6 SPW-3599 WATER Apr,1993 1-131 149.811.9 145.0 116.0 - 174.0 SPW-3606 WATER Apr,1993 Co-60 2 ' 9 i 2.3 21.5 11.5 - 31.5 Cs-134 26.4 i 1.9 26.4 16.4 - 36.4 l Cs-137 33.9 i 2.6 31.7 21.7 - 41.7 SPM-3631 MILK Apr,1993 l Cs-134 48.8 i 2.9 52.8 42.8 - 62.8 l Cs-137 65.2 i 2.9 63.4 53.4 - 73.4 )

1-131 139.811.6 145.0 116.0 - 174.0 l SPF-3681 flSH May,1993 UELLO)

Cs-137 68.2 i 7.7 67.6 57.6 - 77.6 i Concentrations are in pCi/ Total Volume (550g).

SPW-3842 WATER Jun,1993 l

Th-230 4.2 i 0.5 4.5 2.7 - 6.3 i SPW-4160 WATER Jun,1993 f A1pha 8.9i 1.4 12.9 7.7 - 18.1 )

Beta 22.0 i 1.9 31.9 19.1 - 44.7 SPW-4232 WATER Aug,1993 I Fe-55 1684.0 i 415.0 1420.0 1136.0 - 1704.0 SPW-4246 WATER Aug,1993 I Sr-90 32.2 i 2.6 30.4 MILK 24.3 - 36.5

)

SPM-4247 Aug,1993 I St-89 29.1

• 4.9 35.4 25.4 - 45.4 l Sr-90 18.3 i 1.3 19.2 9.2 - 29.2 f SPW-4248 WATER Aug,1993 l H-3 9910.0 i 300.0 10430.0 8344.0 - 12516.0 l SPW-4250 WATER Aug,1993 l Co40 247.0 i 23.1 .

247.7 222.9 - 272.5 I Cs-134 141.6 i 15.9 141.1 127.0 - 155.2 l

t  !

l A3-6

Table A-3. In-house " spike" samples.

L Concentration in pCi/L' Lab Sample Date Teledyne Results Known ControF Code Type Collected Analyses 2s, n=1 6 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 employce's results have been good in the past; no further action is planned.

SPF-4251 FISli (JELLO) Aug,1993 Cs-134 63.8i3.3 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 SFW-4377 WATER Sep,1993 1-131 39.0110.0 42.1 30.1 - 54.1  :

SPM-4378 MILK Sep,1993 1-131 44.5 c 5.5 42.1 30.1 - 54.1 SPCH-4379 CllARCOAL Sep,1993 i 1-131 90.3113.5 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 19.511.8 19.0- 9.0 - 29.0 SPW-4382 WATER Sep,1993 ,

I129 18.111.0 18.6 6.6 - 30.6 ,

SPW-4421 WATER Oct,1993 H-3 16900.0 1 368.0 17380.0 13904.0 - 20856.0 SPW-4428 WATER Oct,1993 Co40 19.3i 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 1

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 I-131 49.718.6 44.5 32.5 - 56.5' l

i 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 6 Activity Limits SPW-4427 WATER Oct,1993 I-131 95.2110.6 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.

6 All samples 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 400/4-81-004 (see Attachment A) or limits imposed by Teledyne's Midwest Laboratory.

e A3-8

Table A-4. In-house " blank" samples.

Concentration pCi/L',

Teledyne Results Acceptance '

Lab Sample Sample (4.66 Sigma) Criteria Code Type Date Analyses ILD Activitv6 (4.66 Sigma)

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 Jan 1990 Cs-134 < 3.6 < 10.0 Cs-137 < 4.7 < 10.0 Sr-89 < 0.8 < 5.0 Sr-90 N/A 1.6 i 0.5 < 1.0 Low level of Sr-90 concentration in milk (1-5 pCi/L) is not unusual.

SPM-8312 MILK Feb l900 St-89 < 0.3 < 5.0 Sr-90 N/A 1.210.3- < 1.0 Low level of Sr-90 concentration in milk (1-5 pCi/L) is not unusual.

SPW-8312 WATER Feb l990 Sr-89 < 0.6 < 5.0 Sr-90 < 0.7 < 1.0 SPM-8314 MILK Mar 1990 1-131 < 0.3 < 1.0 SPM-8510 MILK May 1990 Cs-134 < 4.6 < 10.0 Cs-137 < 4.8 < 10 0 1-131 < 0.2 < 1.0 SPW-8511 WATER May 1990 1I-3 < 200.0 < 300.0 SPM-8600 MILK Jul1990 Cs-134 < 5.0 < 10.0 Cs-137 < 7.0 < 10.0 1-131 < 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.

4 A4-1

Table A-4. In-house " blank" samples.

Concentration pCi/L*.

Teledyne Results Acceptance Lab Sample Sample (4.66 Sigma) Criteria Cnde Tvoe Date Analyses LLD Activitv 6 (4.66 Sigma)

SPM-8877 MILK Aug1990 I-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 Gr. Deta < 0.7 < 5.0 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 Mn-54 < 4.0 < 10.0 SPW.8929 WATER Aug 1990 ,

St-89 < 1.4 < 5.0 Sr-90 < 0.6 < 1.0 SPW-69 WATER Sep 1990 Sr-89 <1.8 < 5.0 Sr-90 < 0.8 < 1.0 SPW-106 WATER Oct 1990 H-3 < 180.0 < 300.0 1-131 < 0.3 < 1.0 SPM-107 MILK Oct 1990 Cs-134 < 3.3 < 10.0 Cs-137 < 4.3 < 10.0 1-131 < 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 r

Table A-4. In-house " blank" samples.

' Concentration pCi/L'.

Teledyne Results Acceptance Lab Sample Sample (4.66 Sigma) Criteria Code Type Date Analyses LLD Activitv6 (4.66 Sigma)

Mn-54 < 1.7 < 10.0 SPW-372 WATER Dec 1990 Gr. Alpha < 0.3 < 1.0 Gr. Beta < 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 N/A Sr-90 1.8 i 0.4 < 1.0 Low level of Sr-90 concentration in milk (1-5 pCi/L) is not unusual. '

SPM-421 MILK Feb 1991 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 Co-60 < 2.5 < 10.0 Cs-134 < 2.4 < 10.0 Cs-137 < 2.2 < 10.0 1-131 < 0.2 < 1.0 SPM-587 MILK Apr 1991 Cs-134 <1.7 < 10.0 Cs-137 < 1.9 < 10.0 I-131 < 0.2 < 1.0 SPW-837 WATER Jun1991 Gr. Alpha < 0.6 '< 1.0 Gr. Deta < 1.1 < 5.0 SPM-953 MILK Jul1991 Cs-137 < 4.9 < 10.0 1-131 < 0.2 < 1.0 Sr-89 < 0.7 < 5.0 A4-3

Table A-4. In-house " blank" samples.

Concentration pCi/L*.

Teledyne Results Acceptance -

Lab Sample Sample (4.66 Sigma) Criteria Code Type Date Analyses LLD Activitv b (4.66 Sigma)

St-90 N/A 0.4 i 0.3 < 1.0 Low !cvel of St-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 ,

I-131 < 0.2 < 1.0 SPW-1254 WATER Oct 1991 Sr-89 < 2.8 < 5.0 Sr-90 < 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 1-131 < 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. Deta < 0.8 < 5.0 SPM-1578 MILK Jan 1992 Cs-134 < 7.2 < 10.0 l Cs-137 < 8.0 < 10.0 1 I-131 < 0.2 < 1.0 4 Sr-89 < 0.5 < 5.0 '

Sr-90 N/A 1.3 i 0.4 < 1.0 Low level of St-90 concentration in milk (1-5 pCi/L) is not unusual.

SPW-1860 WATER Mar 1992 Sr-89 < 0.6 < 5.0 Sr-90 < 0.4 < 1.0  !

SPW-2067 WATER Apr 1992 H-3 < 168.0 < 300.0 SPW-2114 WATER Apr 1992 C-14 < 1.0 < 200.0 i

-I A4-4

~ - - .

l l

1 Table A-4. In-house " blank" samples. I Concentration pCi/L*.

Teledyne Results Acceptance i Lab Sample Sample (4.66 Sigma) Criteria Code Type Date Analyses LLD Activitv6 (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 1-131 < 0.2 < 1.0 SPW-2220 WATER May 1992 Co40 < 2.1 < 10.0 Cs-134 < 2.1. < 10.0 Cs-137 < 2.3 < 10.0 SPW-2369 WATER Jun 1992 Gr. Alpha < 0.4 <1.0 Gr. Beta <0.8 < 5.0 SPM-2500 MILK Aug1992 1-131 <0.4 < 1.0 Sr-89 <1.2 <5.0 Sr-90 < 0.9 < 1.0 SPW-2666 WATER Sep 1992 Sr-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.

Cs-137 < 6.1 < 10.0 '

Activity result is not ave'.. le for this sample.

H-3 < 177.0 < 300.0 1-131 <0.3 < 1.0 Activity result is not available for this sample.

SPM-2829 MILK Oct 1992 Co40 < 9.3 < 10.0 Cs-134 < 6.4 < 10.0 Cs-137 < 7.2 < 10.0 A4-5 I

Table A-4. In-house " blank" samples.

Concentration pCl/IA Teledyne Results Acceptance Lab Sample Sample (4.66 Sigma) Criteria Code Type Date Analyses LI D 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.

Cs-137 <3.9 0.8 i 2.2 < 10.0 Activity result is not available.for this sample.

Sr-89 < 0.7 -0.911.1 < 5.0 .

Sr-90 N/A 1.610.5 < 1.0 Low levels of St-90 concentration in milk (1-5 pCi/L)is not unusual.

SPM-3386 MILK Feb l993 I-131 < 0,2 0.110.1 < 1.0 SPW-3557 WATER Mar 1993 Sr < 0.5 0.310.5 < 5.0 St-90 <0.5 0.110.2 < 1.0 SPW-3598 WATER Apr 1993 H-3 < 180.0 84.7194.2 < 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.

Cs-137 < 3.4 < 10.0 Activity result is not available for this sample, ,

I-131 < 0.4 0.3 i 0.9 < 1.0 SPM-3651 MILK May 1993 Cs-134 < 4.4 < 10.0 Activity result is not available for this sample. ,

A4-6 I

. . . ~_ . - . . . -

. Table A-4. In-house " blank" samples.

Concentration pCl/L*.

Teledyne Results Acceptance Lab Sample Sample (4.66 Sigma) Criteria -

Code Type Date Analyses LLD Activitv* (4.66 Sigma)

Cs-137 < 6.3 < 10.0  !

Activity result is not available for this sample.

1-131 <0.2 0.1 i 0.1 < 1.0 SPFP-3680 FOOD May 1993 Cs-137 <6.5 0.0 1 0.0 < 10.0 GPW-3844 WATER Jun1993 Th-228 <0.1 0.0101 < 1.0 Th-230 <0.1 0.2 Oa < 1.0 Th-232 < 0.1 0.0 i 0.0 < 1.0 '

SPW-4234 WATER Jun 1993 Gr. Alpha < 0.3 0.0 i 0.2 < 1.0 Gr. Beta < 0.8 0.2 i 0.3 < 5.0 SPS-4059 SEDIMENT Jul1993 (BOTTOM)

Cs-134 < 5.0 0.0 i 0.0 < 10.0 Cs-137 < 7.2 0.0 1 0.0 < 10.0 SPVE-4060 VEGETATION Jul1993 (SAW DUST)

Cs-134 <4.8. 0.0 i 0.0 < 10.0 Cs-137 < 6.4 0.0 1 0.0 < 10.0 -

I-131(g) < 13.5 0.0 i 0.0 < 20.0 SPM-4061 MILK Jul1993 Cs-134 <8.6 0.0 i 0.0 < 10.0 Cs-137 <5.8 0.0 i 0.0 < 10.0 SPM-4062 MILK Jul1993 Cs-134 43.8 1.5 i 1.5 < 10.0 Cs-137 <4.4 -1.613.3 < 10.0 SPW-4063 WATER Jul1993 Co40 <4.0 1.2 i 2.3 < 10.0 Cs-134 < 3.7 0.3 i 1.2 < 10.0 Cs-137 < 3.2 0.4 i 3.2 < 10.0 SPAP-4064 AIR FILTER Jul 1993 I (COMPOSITE) i Cs-134 < 2.1 0.0 1 0.0 < 10.0 ~

Cs-137 <2.8 0.0 t 0.0 < 10.0 A4 . I f'

\

Table A-4. In-house " blank" samples.

Concentration pCi/L*.

Teledyne Results Acceptance Lab Sample Sample (4.66 Sigma) Criteria Code Tvrie Date Analyses ILD Activitv 6 (4.66 Sigma)

SPCH-406 CHARCOAL Jul1993 1-131 < 0.1 0.0 1 0.0 < 1.0 Based on a volume of 300 m' SPW-4233 WATER Aug1993 Fe-55 < 506.0 0.0 1 0.3 < 1000.0 >

SPM4235 MILK Aug 1993 Cs-134 < 8.I ' 1.611.8 < 10.0 Cs-137 < 4.2 -1.7 i 3.4 < 10.0 1-131 < 0.1 0.0 1 0.2 < 1.0 Sr-89 < 0.8 -1.0 i 1.1 < 5.0 Sr-90 N/A 1.8 i 0.5 < 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 Aug1993 Co-60 < 7.0 0.4 i 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 I-131 < 0.5 0.0 1 0.1 < 1.0 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 Pu-238 < 1.0 0.410.7 < 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 i 0.1 < 1.0 Th-232 < 0.1 0.0 i 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 i 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 1 0.5 < 1.0 SPW-4422 WATER Oct 1993 '

H-3 < 180.0 -27.5188.9 < 300.0 A4-8

I 1

j l

Table A-4. In-house " blank" samples.

1

\

Concentration pCi/L*.  ;

Teledyne Results Acceptance l Lab Sample Sample (4.66 Sigma) Criteria Code Tvoe Date Analvscs LLD Activitv6 (4.66 Sigma)

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.

9 f

k 4

i

+

2 e

A4-9

I-December,1993 -

ATTACHMENT A ACCEPTANCE CRITERIA FOR

• SPIKED" SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSES' One Standard Deviation Analysis Level for singic determinations Camma Emitters 5 to 100 pCi/ liter or kg 5.0 pCi/ liter

>100 pCi/ liter or kg 5% of known value v

Strontium-896 5 to 50 pCi/ liter or kg 5.0 pCi/ liter

>50 pCi/ liter or kg 10% of known value .

1 Strontium-906 2 to 30 pCi/ liter or kg 5.0 pCi/ liter

>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 $100 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)**

>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 lodine-131, s55 pCi/ liter 6.0 pCi/ liter -

Iodine-129h >55 pCi/ liter 10% of known value .

Uranium-238, s35 pCi/ liter 6.0 pCi/ liter Nickel-646 >35 PCi/ liter 15% of known value Technetium-996 -?

Iron-55, 50 to 100 pCi/ liter 10 pCi/ liter

>100'pCi/ liter 10% of known value .

6 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 lim;t.

A2 4

~,_....._.,._e._. . _.___._. . . . _ , . . . . _ . . _ _ _ _ . . . . . . _ . _ _ . _ _ _ _ . . _ _ _ _ _ . _ . . . . _ _ _ _ _ _ _ . . _ . . . _

..

u  :;;

e a

APPENDIX B DATA RFPORTING CONVENTIONS n

t J

5 h '

U-1

l l

l Data Reporting Conventions l

1.0 All activities except gross alpha and gross beta are decay corrected to collection time or the end of the collection period. .l 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 4.660 uncertainty for a-background sample.

3.0 RupJicate analyses 3.1 Individual results xl ist x1 s2 Reported result: xis where x = (1/2) (x1 i x2) 2 2 s = (1/2) s1 + s2 7

3.2 Individual results: <L1

<L2 Reported result: <L where L = lower of L1 and L2 3.3 Individual results xis

<L Reported result: x i s if x 2 L;

<L otherwise B-2

)

4.0. Computation of Averages and Standard Deviations 4.1 Averages and standard deviations listed in the tables are computed

' from all of the individual measurements over the period averaged; for example, an annual standard deviation would not be the average of quarterly standard deviations. The average R and standard deviation (s) of a set of n numbers x1, x2 xn are defined as follows:

1 x=g Ex s=

n-1 4.2 Values below the highest lower limit of detection are not included in the average.

4.3 If all of the values in the averaging group are less than the highest LLD, the highest LLD is reported.

4.4 If all but one of the values are less than the highest LLD, the single value x and associated two sigma error is reported.

4.5 In rounding off, the following rules are followed:

4.5.1. If the figure following those to be retained is less than 5,-the figure is dropped, and the retained figures are kept unchanged.

As an example,11.443 is rounded off to 11.44.

4.5.2. If the figure followind those to be retained is greater than 5, the figure is dropped ar.d the last retained figure is raised by 1. As an example,11.440 is rounded off to 11.45.

4.5.3. If the figure following those to be retained is 5, and.if there are no figures other than zeros beyond the five, the figure five.is dropped, and the last-place figure retained is increased by one if:

it is an odd number or it is kept unchanged if an even number.

As an example,11.435 is rounded off to 11.44, while 11.425 is rounded off to 11.42.

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a APPENDIX C >

Maximum Permissible Concentrations ~

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Potassium-40C 3,000 pCi/L Gross alpha 30 pCi/L >

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c A natural radionuclide.

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