ML20247B529

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Radiation Environ Monitoring Program Jan-Dec 1997, for Monticello Nuclear Generating Plant
ML20247B529
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Site: Monticello Xcel Energy icon.png
Issue date: 12/31/1997
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TELEDYNE BROWN ENGINEERING CO.
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NUDOCS 9805080076
Download: ML20247B529 (74)


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"A' TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES MIDWEST LABORATORY u$ I i l0$$if l

NORTHERN STATES POWER COMPANY MINNEAPOLIS, MINNESOTA MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263 LICENSE NO. DPR-22 ANNUAL REPORT TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION 5 Radiation Environmental Monitoring Program January 1 to December 31,1997 Project No. 8010 Prepared under Contract by TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES MIDWEST LABORATORY Project No. 8010 t'

Approved by: /Sd Al B) la r ab,,'hi.S.

eh z1 Lead 14 April 1998 9805080076 980430 3, DR ADOCK O

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PREFACE )

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i The staff of Teledyne Brown Engineering Environmental Services, Midwest Laboratory was responsible for the acquisition of the data presented in this report. Samples were collected by {

4 members of the staff of the Monticello Nuclear Generating Plant, Northern States Power Company. The report was prepared by staff members of Teledyne Brown Engineering Environmental Services, Midwest Laboratory.  ;

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I TABLE OF CONTENTS l

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Nih Eage Preface.............................................................................................,ii. 1 Lis t o f Tables . .. . .. . . . . . . . . . . . . . . . . . . .. . . . . . . .. . . . . . . . . . . . .. .. .. .. .. .. .. .. . . . . . . . . . . . . .. .iv L i s t o f Fi g u r e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . .... .. .. . . . . . . .v k

l 1.0 INTRO D U CTIO N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I )

' 2.0

SUMMARY

................................................................. ............... ....2 3.0 RADIATION ENVIRONMENTAL MONITORING PROGRAM (REMP).. .... 3 3.1 Program Design and Data Interpretation..... .... .. . . . . . . . . . . . . . . . .....3 3.2 Program Description . ......... .. .... ........ ... .... ... ......... .............4 t 3.3 ' Program Execu tion .. .. .. ... . . .... .. .. ... . .. . .. .. .. .. . . . .. . . . . . . . . . . . . ......5 j l 3.4 Labora tory Procedures .. ....... . .. .... . .... ......... . . . . . . . . . . .........6 1

! 3.5 Program Modifications ......... . . .... . . . . . . . . . . . . . .. . .. .....6

, 3.6 Lan d Use Cen s u s .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . . . . . . . . . . .6  :

i l 4.0 RESULTS AND DISCUSSION......... . ...... ... ... .... .. . ... ... .. .. .... . .. . ... 7 l 4.1 Atmospheric Nuclear Detonations and Nuclear Accidents.... . .7 l 4.2 Summary of Preoperational Data... ........... .. .. .... . . . . .......7 '

4.3 Program Findings . . ... . . .. . . . . . . . ... . .. .. .. .. . .. . . . .. . . . . . . . . . ..........8

! 5.0 FIG URES AND TA BLES .. .... ... . . .. .. . .. . . . . . . . . .. . . . . . . . . . . . . . . . ...............12 l

! 6.0 RE FE R ENC ES CITE D . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . ..24 i APPENDICES

-A Interlaboratory Comparison Program Results. ... ... . . . . . . . . . . . . . . . . . . . . ..A-1 B Data Reporting Conventions .. ......... ... ........ . .. ... . ... .... .. .. . . . . . . . . ..B-1 C Maximum Permissible Concentrations of Radioactivity in Air and i

Water Above Natural Background in Unrestricted Area.. . ..C-1 l D - Sa mpling Location M a ps .. . ... .... . . . . .. .. . . . . .. . . . . . . . . . .. . . . . . . . . . . .. . . . . . . .... . . . . . . . D- 1 l  :

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LIST OF TABLES 1

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h Iith Page j 5.1 Sample Collection and Analysis Program, 1997. . . . . . . . . . .. . . . . . . . . . . . . . . . . . 1 3 5.2 Sa mp li n g Loca ti ons. . .. . .. . .. . .. . . . .. . . ... . .... . . . . . . . . . . . . . . . . . . . . . . . . . . . ....14 l

( 5.3 Missed Collections and Analyses,1997.. . . . . ... . . . . . . . . ...... .......16.

i l 5.4. Radiation Environmental Monitoring Program Summary ......... .. . .... .19 j 4

l The followitig tables are in the Appendices:

Appendix A l A-1 Interlaboratory Comparison Program Results . . .. . . . . . . . . . . . . . . . . .. . . . . .~A l - 1 1

A-2 Interlaboratory Comparison Program Results, thermoluminescent dosimeters (TLDs).. ...... ....... ... . . . . . . . . . . . . . . . . . . ... . ... ..A2-1 A-3 In-house Spiked Samples.... .. ....... ................. . .... ... . . . . . . . . ..... .... A 3- 1 1

.A-4 In-house " Blank" Samples . ... . . . ... . . . . .. . ... . . .. . .. . .. .. . . . . . . . . . .. . . . . .. ... ...... A 4- 1 l

A-5 In-house " Duplicate" Samples..... .. .... .. ... ..... ...... .. . . . . . . . . .. . .... A5-1 A-6 Department of Energy MAPEP comparison results.... . . . . .........A6-1 A-7 Environmental Measurements Laboratory Quality (EML) Assessment

! Pragram comparison results ... ...... ..... ............ .. .... . . . . .. . .A 7- 1 Attachment A: Acceptance criteria for spiked samples.. . . . .. .. ..A2 Appendix C i, C-1 Maximum Permissible Concentrations of Radioactivity in air a'id water above background in unrestricted areas.... . . . . ..C-2 l

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LIST OF FIGURES l ,

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I j No. Title page l 5.1 Offsite Ambient Radiation (TLDs), inner versus outer ring locations,1984-1997... . .17 5.2 Airborne Particulate; analysis for gross beta, average mean of all indicator l locations (M-2,3,4,5) versus control location (M-1),1984-1997. . .. . . ... . . . . . . . .18 l

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1.0 ETRODUCTION 1

This report summarizes and interpreis results of the Radiation Environmental Monitoring Program (REMP) conducted by Teledyne Brown Engineering Environmental Services, Midwest Laboratory at the Monticello Nuclear Generating Plant, Monticello, Minnesota, during the period January - December,1997. 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. 1 Tabulation of the individual analyses made during the year are not included in this report.

These data are included in a reference document (Teledyne Brown Engineering Environmental Services, Midwest Laboratory,1998a) available at Northern States Power Company, Monticello Nuclear Generating Plant, Radiological Services Department.

l Monticello Nuclear Generating Plant is a 575 MWe boiling water reactor located on the l 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 S I l

March 1971 and commercial operation began on 30 June 1971.

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SUMMARY

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

Plant is described. Results for 1997 are summarized and discussed.

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

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

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' 3.0 RADIATION ENVIRONMENTAL MONITORING PROGRAM (REMP)  !

l 3.1 Procram Design and Data Interpretation The purpose of the Radiation Environmental Monitoring Program (REMP) at the Monticello Nuclear Generating Plant is to assess the impa-t 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).

1 Sources of environmental radiation include the followmg:

(1) Natural background radiation arising from cosmic rays and l primordial radionuclides; (2) Fallout from atmospheric nuclear detonations; (3) Releases from nuclear power plants; (4) Industrial and medical radioactive waste; and (5) Fallout from nuclear accidents.

i 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 I 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.

l 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 i

isotopes were selected as radiological impact indicators because of the diffeient characteristic proportions in which they appear in the fission product mix produced by l

a nuclear reactor and that produced by a nuclear detonation. Each of the three isotopes is produced in roughly equivalent amounts by a reactor: each constitutes about 10% of the total activity of fission products 10 days after reactor shutdown. On the other hand,10 days after a nuclear explosion, the contributions of zirconium-95, cerium-144, and cesium-137 to the activity of the resulting debris are in the approximate ratio 4:1:0.03 (Eisenbud,1963). Beryllium-7 is of cosmogenic origin and potassium-40 is a naturally-occurring isotope. They were chosen as calibration monitors and should not be considered as radiological impact indicators.

The other group quantified consists of niobium-95, ruthenium-103 and -106, cesium-134, barium-lanthanum-140, and cerium-141. These isotopes are released in small quantities by nuclear power plants, but to date their major source of injection into the general 3

. Program Design and Data Interpretation (continuedl 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.

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

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 l reviewed below. Table 5.2 defines the sampling location codes used in Table 5.1 and i specifies for each location its type (indicator or control) and its distance, direction, and I sector relative to the reactor site. To assure that sampling is carried out in a reproducible manner, detailed sampling procedures have been prescribed (Monticello Generating Plant REMP Surveillance, Current Revision). Maps of sampling locations are included in Appendix D.

' To monitor the air environment, airborne particulate 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 .echanged l 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 1 (M-1), and four are indicators (M-2, M-3, M-4, M-5). One of the indicators is located in I l the geographical sector expected to be most susceptible to any atmospheric emissions

l. from the Plant (highest D/Q sector).

l l Ambient gamma radiation is monitored at thirty-seven locM .. , using CaSO4:Dy dosimeter with four sensitive areas at each location: fourteen iri an inner ring in the general area of the site boundary, sixteen in the outer ring within 4-5 mile radius, six at special interest locations and one control location,11.1 miles distant from the plant.

They are replaced and measured quarteriv. 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 TBEESML quarterly for annealing and repackaging.

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

There are currently only two milk producers within the indicator area. 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 vamma-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 4

Emgram Description (continued) annually only if the field is irrigated by water in which radioactive effluent has been discharged. Analysis is for gamma-emitting isotopes.

The terrestrial environment is also monitored by collection of well water from four locations on a quarterly basis. All samples are analyzeJ . :r 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.

y' 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, inverNbrates, and shoreline sediments. Shoreline sediment is also collected semi-annually from one downstream recreational location. All samples are analyzed for garnma-emitting isotopes.

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

(1) There was no Air particulate / Air Iodine sample available at location M-4 for the week ending 05-14-97. The sampler pump failed due to an open circuit breaker.

(2) There was no TLD data for location M-11 A for the second quarter of 1997. The TLD was lost in shipping.

(3) There was no TLD data for location M-7D for the third quarter of 1997. The TLD was lost in the field due to a major storm.

(4) There was no Air particulate / Air Iodine sample available at location M-1 for the week ending 06-26-97. The sampler pump line cord had come unplugged.

(5) There was no Air particulate / Air lodint sample available at location M-5 for the week ending 07-07-97. Power was shut off for building repairs.

(6) No Air Iodine analyses for stations M-1 through M-5 were performed for the week ending 07-30-97. The samples were received too late for meaningful analysis, due to the UPS strike.

(7) No Iodine-131 analyses for locations M-10, M-24 and M-28 were performed for the week of 07-30-97. The samples were received too late for meaningful analysis, due to the UPS strike.

Deviations from the program are summarized m Table 5.3.

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3.4 Laboratory Procedures The iodine-131 analyses in milk and drinking water were made using a sensitive l

radiochemical pru n which involves separation of the iodine using an ion-exchange method and solvent extraction and subsequent beta counting.

All gamma-spectroscopic analyses were performed with an HPGe or Ge(Li) detector.

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

Tritium was determined by a liquid scintillation technique.

Analytical procedures used by the Teledyne Brown Engineering Environmental Services, Midwest Laboratory are on file and are available for inspection. 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 i Laboratory of the U.S. Atomic Energy Commission (U.S. Atomic Energy Commission, -

1972).

Teledyne Brown Engineering Environmental Services, Midwest Laboratory has a comprehensive quality control / quality assurance program designed to assure the reliability of data obtained. Details of TBEESML's QA Program are presented elsewhere (Teledyne Isotopes Midwest Laboratory,1992). The TBEESML QA Program includes participation in Interlaboratory Comparison (crosscheck) Programs. Results obtained in crosscheck programs are presented in Appendix A.

3.5 Program Modifications Well water was not available from location M-13 for the third and fourth quarters of 1997. The water was collected from the Wise residence (M-27).

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3.6 Land Use Census l 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 nf all milk animals and all 500 ft2 or greater gardens producing broad leaf vegetation in each of the meteorological sectors within a distance of three miles. This census shall be conducted at least once per year between the dates of May 1 and October 31. New locations shall be added to the radiation environmental monitoring program within 30 days and sampling locations having lower calculated doses or a lower dose commitment may be deleted from this monitoring program after October 31 of the year in which the land use census was conducted. The 1997 land use census was conducted between July 21 and August 8,1997. No changes to the highest D/Q garden, residence or dairy locations from the 1996 census were identified. The highest D/Q locations remained; Resident (0.6 mi./SW), Garden (0.7 mi./SSW), and Dairy (3.7 mi./WNW) Detailed land use census data are contained in the Land Use Census and Critical Receptor Report, Aug 1997, Monticello Nuclear Generating Plant, Radiological Services Department.

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4.0 RESULTS AND DISCUSSION j i

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 recom.nended 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 1997. The last reported test was conducted by the People's Republic of China on October 16,1980. The r ported yield was in the 200 kiloton to 1 megaton range.

There were no reported accidents at nuclear facilities in 1997.

4.2 Summary of Preoperational Data The following constitutes a summary of preoperational studies conducted at the Monticello Nuclear Generatir.g 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 l 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 in 1970. These levels are reflected l throughout the various media tested.

In the air environment, ambient gamma radiation (TLDs) averaged 9.1 mR/4 weeks I during preoperational studies (1970). Gross beta in air particulate in 1969 and 1970 i averaged 0.20 pCi/m 3. Present day levels have stabilized at around 0.025 pCi/m3 )j Airborne radioiodine remained below detection levels.

In the terrestrial environment of 1968 to 1970, milk, agricultural crops, and soil were  ;

monitored. In milk samples, low levels of Cs-137 and Sr-90 were detected. Cs-137 l levels averaged 16.7 pCi/L. Soybean crop measurements in 1969 averaged 35.5 pCi/g i

for gross beta and 0.3 pCi/g for Cs-137. Gross beta measured in soil averaged 51.7 pCi/g . Present day measurements for cesium-137 are below detection levels in milk and agricultural crops.

The aqueous environment was monitored by testing of river water, bottom sediments, fish, aquatic vegetation, and periphyton. Specific location comparison of drinking, river, and well water concentrations for tritium and gross beta are not possible. However, tritium background levels, measured at seven separate locations from 1968 to 1970, averaged 970 pCi/L. Present day environmental samples measure below detection levels. Values for gross beta, measured from 1968 to 1970, averaged 9.8 pCi/L in upstream and downstream Mississippi River water,4.4 pCi/L for well waters, and 18.6 pCi/L for lake waters. Gamma emitters were below the lower limit of detection (LLD).

In shoreline sediments, gross beta background levels in 1970 averaged 49.8 pCi/g for both upstream and downstream samples. Cs-137 activity averaged 0.10 pCi/g for both upstream and downstream samples. The lower levels of Cs-137 occasionally observed today can still be attributed to residual activity from atmospheric fallout.

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Summarv of Preoperational Data (continued)

Gross beta levels in fish flesh averaged 5.3 pCi/g in 1968 and 1969. Cs-137, measured l in 1969 and 1970, averaged 0.044 pCi/g. Gross beta background levels, in 1970, for I aquatic vegetation, algae, and periphyton samples measured 86.7 pCi/g,76.5 pCi/g, and 28.1 pCi/g respectively.

4.3 Procram Findines Results obtained show background levels of radioactivity in the environmental samples collected in the vicinity of the Monticello Nuclear Generating Plant in 1997.

Ambient Radiation (TLD's)

Ambient radiation was measured in the general area of the site boundary, at an outer ring 4 - 5 mi. distant from the Plant, at special interest areas and at one control location.

The means were similar for both inner and outer rings (13.3 and 12.8 mR/91 days, respectively). The mean for special locations was 12.7 mR/91 days. The mean for the control location was 11.0 mR/91 days. Dose rates measured at the inner and outer ring locations were similar to those observed from 1984 through 1996 and are tabulated below. No plant effect on ambient gamma radiation is indicated (Figure 5-1).

Yrar Inner Ring Outer Ring D_ese rate _(mR/91 days) 1984 l 13.6 13.6 1985 12.6 12.8 1986 14.6 14.1 1987 15.4 15.5 1988 14.8 14.7 1989 15.0 15.4 ,

1990 16.1 16.2 I 1991 15.2 15.8 l 1992 15.1 15.1 1993 15.6 15.9 l 1994 14.6 14.0 l 1995 14.4 13.6 14.0 13.5 1996 1997 13.3 12.8 1

I l Ambient gamma radiation as measured by thermoluminescent dosimetry. l Average quarterly dose rates, Inner vs. Outer Ring locations l

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Airborne Particulate The average annual gross beta concentrations in airborne particulate were identical at i

both indicator and control locations (0.023 pCi/m 3) and were similar to levels observed from 1984 through 1996. The results are tabulated below. The data for 1986 does not include the results from May 19 to June 9,1986, which were influenced by the accident at Chernobyl. (Figure 5-2).

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. Year Indicators Control l Concentration (oCi/m3) 1984 0.025 0.024 1985 0.025 0.024 1986 0.026 0.026 1987 0.026 0.026 1988 0.030 0.030 J' 1989 0.027 0.026 1990 0.023 0.023 1991 0.024 0.024 4 1992 0.023 0.023 1993 0.024 0.023 1994 0.023 0.024 1995 0.024 0.025 1996 0.023 0.023 1997 0.023 0.023 '

Average annual gross beta concentrations in airborne particulate.

A s aring peak in beta activity had been observed almost annually for many years (Wi son 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 1997. In 1986, the spring peak could not be identified I because it was overshadowed by the releases of radioactivity from Chernobyl. The l highest averages for gross beta were for the months of January and December, and the first and fourth quarters, as in 1984 through 1997 (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,1998b).

Gamma spectroscopic analysis of quarterly composites of air particulate filters yielded similar results for indicator and control locations. Beryllium-7, which is produced continuously in the upper atmosphere by cosmic radiation (Arnold and Al-Salih,1955) was detected in all samples, with an average of 0.073 pCi/m3 at both indicator and control locations. All other gamma-emitting isotopes were below their respective LLD limits.

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I Airborne lodine i

l Weekly levels of airborne iodine-131 were below the lower limit of detection (LLD) of j 0.07 pCi/m3 ni all samples.

Milk o

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

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 1997 show no radiological effects of the plant operation.

River Water and Drinking Water  ;

Tritium was below the LLD of 330 pCi/L in all samples. Gross beta in Minneapolis drinking water everaged 2.3 pCi/L and was less than or similar to average levels l observed from 19E4 through 1996. Gross beta averages are tabulated below.- t Gross Beta l (pCi/L) 1984 2.8  ;

1985 2.8  !

i 1986 2.5 1987 2.4 1988 2.7 1989 2.6  ;

1990 2.2 1991 2.9 1992 2.1 1993 2.6 1994 2.0 1995 2.3 1996 2.1 1997 2.3 Average annual concentrations; Gross beta in drinking water.

l Comparisons with gross beta ' data reported by EPA for Minneapolis drinking water

. sample collected in 1975,1976,1977, and 1978 indicates that concentrations of these 1-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.

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

Crops l ' Two (2) samples of cabbage were collected in September and analyzed for iodine-13L l

The I-131 level was below 0.013 pCi/g wet weight in both samples. There was no indication of a plant effect. There were no crops irrigated from the Mississippi River j within 5 miles of the plant in 1997; therefore, no corn or potato samples were collected J for analysis from irrigated fields. '

l l Fish samples were collected in April and October. Flesh was separated from the bones and gamma-scanned. Potassium-40, the' naturally-occurring isotope, was found to be - ,

similar in upstream and downstream samples (2.64 and 2.84 pCi/g wet weight, respectively). All gamma-emitting isotopes were below their respective LLD ' levels.

There w .s no indication of a plant effect.

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, Invertebrates Two samples were collected in May and two in October. The samples were analyzed for gamma-emitting isotopes. All isotopes were below detection limits. There was no indication of a plant effect.

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Shoreline Sediments Upstream, downstream and downstream recreational area shoreline sediment j collections were made in May and October and analyzed for gamma-emitting isotopes.

Cesium-137 was detected in both downstream samples, averaging 0.10 pCi/g dry weight, and recreational area samples, averaging 0.14 pCi/g dry weight, and indicate ,

l the influence of fallout deposition. Similar levels of activities and distribution were i observed in 1978-1996. The only other gamma-emitting isotope detected was naturally- l occurring potassium-40. There was no indication of a plant effect.  !

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l 5.0 FIGURES AND TABLES I

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Table 5.1. Sample collection and analysis program, Monticello Nuclear Generating Plant,1997.

Locations Collection Analysis Medium No. Codes (and Type)a Frequencyb Typec Ambient Radiation (TLD's) 37 M-01 A - M-14 A C/Q Ambient gamma M-01B - M-16B M-01S - M-06S M-01C Airborne particulate 5 M-1(C), M-2, M-3, C/W GB, GS (QC of each M-4, M-5 location)

Airborne Iodine 5 M-1(C), M-2, M-3, C/W I-131 M-4, M-5 j Milk 3 M-10 (C), M-24, G/Md 1 131, GS M-28 I 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, M-27 Edible cultivated crops - 1 M-27 G/A I131 Cabbage Edible cultivated crops - Corne 1 M-19 G/A GS Edible cultivated crops - 1 M-21 G/A GS Potatoese 1 M-8(C), M-9 I Fish (one species, edible portion) 2 G/SA GS '

Algae or Aquatic Insects 2 M-8(C), M-9 G/SA GS GS Shoreline Sediment 3 M-8(C), M-9, M-15 G/SA l_ a Location codes are defined in Table 5.2. Control stations are indicated by (C). All other stations are l

indicators, i b

Collection type is coded as follows: C/ = continuous, G/ = grab. Collection frequency is coded as follows: W= weekly, M = monthly, Q = quarterly, SA = semiannually, A = annually.

c Analysis type is coded as follows: GB = gross beta, GS = gamma spectroscopy, H-3 = tritium,1-131 = ,

iodine 131. Analysis frequency is coded as follows: MC = monthly composite, QC = quarterly  !

composite.

d Milk is collected biweekly during the grazing 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.

13 w_______-_______-___-_-_--___ -__ --

I Table 5.2. Sampling locations, Monticello Nuclear Generating Plant,1997. l i

Distance and j Type of Direction from l Code Type a Collection Site Sampleb Reactor Site l

)

M-1 C Air Station M-1 AP, Al 11.1 mi G 306 /NW M-2 Air Station M-2 AP, AI 0.8 mi @ 140 /SE M-3 Air Station M-3 AP,AI 0.6 mi @ 104 /ESE M-4 Air Station M-4 AP,AI 0.9 mi O 150 /SSE M-5 Air Station M-5 AP,AI {

2.7 mi G 136"/SE J M-8 C Upstream of Plant RW, BS, BO, F 0.2 mi @ 285"/WNW )

M-9 Downstream of Plant RW, BS, BO, F 0.2 mi @ 6'2 /ENE M-10 C Goenner Farm M, WW, VE 11.5 mi @ 323"/NW M-11 City of Monticello WW 3.2 mi G 128 /SE M-12 Plant Well #1 WW 0.2 mi @ 267 /W 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 Corn Fielde M-21 River Irrigated Potato Fielde M-24 Weinand Farm M 4.8 mi @ 180 /S M-27 Wise Residence VE, WW 0.7 mi @ 208'/SSW Highest D/Q Garden M-28 Hoglund Farm M 3.7 mi @ 300 /WNW M-29 Holthaus Farm M 4.1 mi @ 173 /S General Area of the Site Boundary M-01 A North Boundary Road TLD 0.7 mi @ 353 /N i M-02A North Boundary Road TLD 0.8 mi @ 23 /NNE M-03A North Boundary Road TLD 1.0 mi @ 43 /NE I M-04A Biology Station Road T1. 0 0.7 mi @ 92 /E l M-05A Biology Station Road TLD 0.6 mi @ 112 /ESE l M-06A Biology Station Road TLD 0.6 mi @ 133 /SE j M-07A County Road 75 TLD 0.5 mi @ 158 /SSE M-08A County Road 75 TLD 0.5 mi @ 183 /S i 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 M-12A County Road 75 TLD 0.7 mi @ 273"/W M-13A North Boundary Road TLD 1.1 mi G 317"/NW M-14A North Boundary Road TLD 0.8 mi @ 338"/NNW 14 1 __.-._________o

l i

Table 5.2. Sampling locations, Monticello Nuclear Generating Plant,1997 (continued),

Distance and Direction Code Type a Collection Siie Type of Sampleb from Reactor Site Approximately 4 to 5 miles Distant from the Plant M-01B Serco #1 Air Station TLD 4.6 mi @ 02 /N M-02B County Road 11 TLD 4.4 mi @ 17 /NNE M 03B Intersection of County Road & TLD 4.5 mi @ 49 /NE 1 Route 81 l

M-04B Sherco #6 Air Station TLD 4.2 mi @ 67 /ENE i M-05B City of Big Lake TLD 4.4 mi G 87 /ESE M-06B County Road #14 and 196th Street TLD 4.3 mi @ 116 /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-11B 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-14B Richard K. Anderson Residence TLD 4.5 mi @ 228 /NW M-15B Gary Williamson Residence TLD 4.5 mi @ 308 /NNW l M-16B Sand Plain Research Farm TLD 4.3 mi @ 338"/NNW l

Special Interest Locations M-01S Osowski Orchard Fun Market TLD 0.7 mi @ 130 /SW M-02S Edgar Klucas Residence TLD 0.7 mi @ 142 /SE M-03S Big Oaks Park TLD 1.3 mi @ 89'/E M-04S Pinewood School TLD 2.3 mi e 132 /SE i M 05S Rivercrest Christian Academy TLD 2.6 mi @ 112 /ESE i M-06S Monticello Public Works TLD 2.7 mi @ 136 /SE l M-01C C Goenner Farm TLD 11.5 mi @ 323'/NW '

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

b Sample Codes:

AP = Airborne particulate ,

Al = Airbome lodine l BS =

Bottom (river) sediments BO = Bottom organisms (periphyton or macroinvertebrates)

DW = Drinking water F = Fish M = Milk RW = River water l SS = Shoreline Sediments l i VE = Vegetation / vegetables '

l WW = Well water i c Collected only if the field is irrigated by water in which liquid radioactive effluent has been discharged.

15 L

Table 5.3. Missed collections and analyses for 1997 at the Monticello Nuclear Generating Plant.

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

1 1

Collection Reason for not Plans for Preventmg j Sample Analysis Location Date or conducting REMP Recurrence Period as required ,

1 AP/AI Gross Beta, M-4 05-14-97 Sampler pump Monitor for recurrence; Gamma failure; Open repair if necessary.

circuit breaker. 1 TLD Gamma, M-11 A 2nd TLD lost in Isolated incident Qtr.,1997 shipping.

l AP/AI Gross Beta, M-1 06-26-97 Air sampler Placed signs at all sampling l Gamma failure; Power locations to contact the REMP i disconnected, coordinator if the need to j secure the pump occurs l

I AP/AI Gross Beta, M-5 07-07-97 Power secured for Requested the Public Works J Gamma building reppirs. supervisor to inform us when the need to secure power to the l air station is necessary.

AI I-131 M-1, 2, 3, 7-30-97 Samples received None required; isolated M-4, 5 too late for I-131 incident.

analysis, due to UPS strike.

)

MI I-131 M-10, 24, 7-30-97 Samples received None required; isolated i M-28 too late for I-131 incident. l analysis, due to UPS strike.

)

)

l TLD Gamma M-7B 3rd Qtr., TLD lost in the None required; Act of l 1997 field, due to Nature.

! major storm. j l

)

l l

> 1 l

I 16 i

u

l~

!. Figure 5-1. Offsite Ambient Radiation (TLDs); Inner Ring versus Outer Ring locations.

l i

20

-e- Inner Ring 19I .

-o- Outer Ring

_ l 18 ~ 1 17 -- ,

u h 16= N E>

p15- _ _ _

I E

14 - '

t 13-J -

12-

~

11 =_

10 ~

1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 i

l l

l l

l 17

I Figure 5-2. Airbome Particulate; analysis for gross beta, average mean of all indicator locations versus control location.

0.035 0.033 - -e- Indicators (M-2,3,4,5) 1

-o- Control (M-1) l 0.031 - 1 0.029 - - --

g 0.027-7

[  :  :)

Q 0.025 0.023 - . -:  :)

0.021 -

0.019 - - - --

0.017 - -- -- --

0.015 1984 1985 1986 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 l

t 18

Table 5.4. Radiation Environmental Monitoring Progn n Summary.

Nameof Facility Monticello Nuclear G eerating Plant Docket No. 50-263 Location of Facility Wright, Minnesota Reporting Period January - December 1997 (County, State)

Indicator Location with Rghest Control Number Sample Type and Locations Annual Mean Locations Non.

Type Number of LLDb Mean (F)C Mean (F)C Mean (F)c ' Routine (Units) Analysesa Range c Locationd Range e Range Results" TLD (mR/91 Gamma 55 3.0 ' 13.3.(55/55) M-01 A,'M-12A 14.1 (8/8) (See Control . 0 days) (Inner - (9.4 15,8) ' (Both identical (11.5-15.8) below.)

Rmg, General means)

Area at Site Boundary) '

TLD (mR/91 Gamma 63 3.0 12.8 (63/63) M 100, 14.0 (4/4) (See Control 0 days)(Outer (7.8-15.7) Acacia Ave., (11.3-15.7) below.)

Ring,4 5 4.4 ml @ 206*/SSW j miles distant) i TLD (mR/91 Gamma 24 3.0 12.7 (24/24) M-06S, Monticello 13.7 (4/4) (See Control 0 days)(Special (9.0-14.7) Public Works Bldg. (11.8-14.7) below.)

Interest Areas) 2.7 mi @ l36'/SE TLD (mR/91 Gamma 4 3.0 None .

M-01 C, 11.0 (4/4) 11.0 (4/4) o days) Kirchenbauer Farm. (9.4-11.9) (9.4-11.9)

, (Control) 11.5 mi @ 323'/NW i

Airborne GB 259 0.002 0.023 (207/207) M.5, Air Station 0.024 (52/207) 0.023 (52/52) 0 Particulate (0.008-0.060) 2.7 mi. 0136*/SE (0.012-0.057) (0.010-0.059)

.. (pCi/m3) GS 20 Be-7 0.020 0.074 (16/16) M-2, Air Station 0.076 (4/4) 0.068 (4/4) 0 (0.048-0.11) 0.8 mi.C140 /SE (0.049 0.11) (0.046-0.10)

Mn 54 0.0010 <LLD -

<LLD 0 I

Co-58 0.0013 <LLD - -

<LLD 0 Co-60 0.0009 <LLD - <LLD 0 Zn-65 0.0018 <LLD - -

<LLD 0 Zr-Nb-95 0.0018 <LLD - - <LLD 0 l Ru-103 0.0013 <LLD - -

<LLD 0 Ru-106 0.0087 <LLD - -

<LLD 0 Cs-134 0.0011 <LLD - <LLD 0 Cs-137 0.0009 (LLD - -

<LLD 0 Ba-La-140 0.0027 <LLD - - <LLD 0 Ce-141 0.0018 <LLD. - -

<LLD 0 Ce-144 0.0058 <LLD - - <LLD 0 Airbome 1131 254 0.07 <LLD - - 0 lodine (pCi/m3) 19 1

r___.-_________. _. - _

l l

Table 5.4. Radiation Environmental Monitoring Program Summary, Name of Facility Monticello Nuclear Generating Plant Docket No 50-263 Location of Facility Wnght, Minnesota keperting Period January - December 1997 (County, State)

Indicator Location with Highest Cont ra>l Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLob Mean (F)C Mean (F)C Mean (F)c Routine (Units) Analyses a Range c Location d Range e Range Result # ]

Milk, I 131 54 1.0 <LLD - -

<LLD 0 (pCi/L)

GS 57 K-40 200 1420 (38/38) M 24 Weinand 1440 (19/19) 1420 (19/19) 0 l (1260-1740) Farm,4.8 mi @ (1260-1740) (1230-1690) I 180*/S j Cs-134 15 <LLD -

<LLD 0 Cs-137 15 <LLD - <LLD 0 Ba-La-140 15 <LLD - <LLD 0 i

River Water 11 3 8 330 <LLD - <LLD 0 I (pCi/L)

CS 24 l

Mn 54 15 <LLD - - <LLD 0 l Fe-59 30 <LLD - - <LLD 0 Co-58 15 <LLD - - <LLD 0 Co-60 15 (LLD- - - <LLD 0 Zn-65 30 <LLD - - <tLD 0 Zr-Nb-95 15 <LLD - - <LLD 0 Cs 134 15 <LLD - - <LLD 0 Cs 137 18 <LLD - -

<LLD 0 Ba-La-140 15 (LLD - - <LLD 0 Ce-144 68 <LLD - -

<LLD 0 20

l l

l

\

l I

Table 5.4. Radiation Environmental Monitoring Program Summary. .

l Name of racihty Monticello Nuclear Generating Plant Docket No. 50-263 l Location of Facihty Wnght, Minnesota Reporting Period January - December IW7 l (County, State)

Indicator Location with thghest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)C Mean (F)C Routine Mean (F)c (Uruts) Analyses a Range c Locationd Range e Range Resultse Drud.ing GB 12 1.0 2.3 (12/12) M-14, Minneapolis 2.3 (12/12) None 0 W4 ter (pCi/L) (1.5-2.9) 36.0 mi @ 128*/SE (1.5-2.9) 1-131 12 1.0 <LLD - -

None o H-3 4 330 (LLD - - None O GS 12 Mn-54 15 <LLD - -

None 0 Fe '9 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 O Cs-134 10 GLD - - None O Cs-137 10 <LLD - - None 0 Ba-La-140 15 <LLD - - None O Ce-144 61 <LLD - - None 0 Well Water H-3 16 130 <LLD - -

<LLD 0 .i (pCi/L)

Mn-54 15 <.LLD - -

<LLD 0 j Fe-59 30 <LLD - - <LLD 0 Co-58 15 (LLD - - <LLD 0 Co-60 15 <LLO -

(LLD 0 Zn-65 30 <LLD - -

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

Cs-1M 10 <LLD - -

<LLD 0 C5-137 18 <LLD - - <LLD 0 Ba-La-140 15 <LLD - - <LLD 0 l Ce-144 66 <LLD - -

<LLD 0 Crops - I-131 2 0.013 <LLD - - <LLD 0 Cabbage (pCi/g wet) l l

l 21 l

l

l l

Table 5.4. Radiation Environmental Monitoring Program Sum: nary.

Name of Facility Monticello Nuclear Generating Plant Docket No. 50 '>63 location of Facility Wright, Minnesota Reporting Period January - December 1997 (County, State)

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLob Mean (F)C Mean (F)C Mean (F)c Routine (Units) Analysesa Range t Locationd Rangec Range Results0 l

i Fish C;S 4 (pCi/g wet)

K-40 0.1 2.84 (2/2) M 9, Downstream 2.84 (2/2) 2.64 (2/2) 0 (2.63-3.05) of Plant,0.2 mi @ (2.63-3.05) (2.32-2.95) i 62*/ ENE l Mn-54 0.018 <LLD - -

< LI.D 0 Fe-59 0.060 <LLD - -

<LLD 0 Co-58 0.018 <LLD -

<LLD 0 l I

Co-60 0.020 <LLD - -

<LLD 0 Zn-65 0 031 <LLD - -

<LLD 0 Nb-95 0.030 <LLD - -

<LLD 0 Zr-95 0.032 <LLD - -

<LLD 0 l

Cs-134 0.027 <LLD - -

<LLD 0 l 1

Cr-137 0.022 <LLD - -

<LLD 0 Ba-La-140 0.027 <LLD - -

(LLD 0 invertebrates CS 4 (pCi/g wet)

Be 7 1.26 <LLD - - <LLD 0 K-40 3.80 <LLD - -

<LLD 0 Mn-54 0.14 <LLD - -

<LLD 0 Co-58 0.13 <LLD - -

<LLD 0 Coe 0.14 (LLD - -

<LLD 0 Zn-65 0.54 <LLD - - <LLD 0 Zr-Nb-95 0.25 <LLD - -

<LLD 0 Ru-103 0.17 <LLD - -

<LLD r Ru-106 1.31 <LLD - -

(LLD 0 Cs-134 0.14 (LLD - - <LLD 0 Cs-137 0.17 (LLD - -

<tLD 0 Ba-La-140 0.36 <LLD - - <LLD 0 Ce-141 0.26 <'LD - -

(LLD 0 Ce-144 0.71 <LLD - -

<LLD 0 22 l

Table 5.4. Radiation Environrnental Monitormg Program Summary.

Nameof Facility Monticella Nuclear Generating Plant Docket No. 50-263 Location of Facility Wright, Minnesota Reporting Period Januarv - December 1w7 (County, State)

Indicator Location with Highest Cont rol N umber Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)C Mean (F)C Routine Mean (F)c (Units) Analyses a Range c locationd Ra ee Range Result #

Shoreline CS 6 Sediments (pCi/g dry) De-7 0.24 (LLD - -

<LLD "

K-40 0.5 11.03 (4/4) M 15, Montissippi 11.20 (2/2) 10 14 (2/2)

(10.39-11.32) Park 1.6 mi @ (l1.10-11.30 ) (9.05-11.22) 117'/ESE Mn-54 0.025 (LLD - -

<LLD 0 Co-58 0.029 <LLD -

<LLD 0 Co-60 0.033 <LLD - -

<LLD 0 Zn-65 D.095 <LLD - -

(LLD 0 Nb-95 0.044 <LLD - -

(LLD 0 Zr-95 0.053 <LLD - -

<LLD 0 Ru-103 0.028 <LLD -

(LLD 0 Ru-1% 0.23 <LLD - -

<LLD 0 Cs 134 0.033 <LLD - -

<LLD' O j l

Cs-137 0.024 0.10 (4/4) M 15, Montissippi 0.14 (2/2) (LLD 0 l (0.055-0.14) Park 1.6 mi @ (0.14 0.14) I 117'/F.SE Da-La-140 0.081 <LLD - -

<LLD 0 Ce-141 0.048 (LLD - -

<LLD 0 Ce-144 0.14 <LLD -

<LLD 0 ;I a GB = Gross beta; GS = gamma scan.

b LLD = Nominallower hmit of detection bani on 4.66 sigma error for background sample.

c Mean and range are based on detectable measurements only. Fraction of detectable measurements at specified locations is  ;

indicated in parentheses (F). -

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

' Non-routine results are those whkh exceed ten titues the control station value. If no control station value is available, the result is considered non-routine if it exceeds ter tinies the typical pre-operational value for the medium or lacation.

l l

ll 1

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4

6.0 REFERENCES

CIIER 1

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

451-453. ]

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

213,275 and 276.

Gold, S., H.W. Barkhau, B. Shlein, and B. Kahn,1964. Measurement of Naturally Occurring Radionuclides in Air,in the Natural Environment, University of Chicago Press, Illinois, 369-382.  !

l Hazleton EnvironmentalSciences Corporation.1979a through 1983a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1978 through 1982.

Hazleton Environmental Sciences Corporation.1979b through 1983b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1978 through 1982.

Hohenemser, C M. Deicher, A. Ernst, H. Hofsass, G. Lindner, E. Racknagel,1986. "Chernobyl,"

Qwmtech. October 1986, pp. 596-605.

National Center for Radiological Health,1968. Radiological Helath and Data Reports, Vol. 9, Number 12, 730-746.

Northern States Power Company.1969. Monticello Nuclear Generating Plant, Environmental Radiation Monitoring Program, Annual Report, June 18,1968 to December 31,1968. j Minneapolis, Minnesota, i i

i 1970. Monticello Nuclear Generating Plant, Environmental Radiation Surveillance, l Annual Report, January 1,1969 to December 31,1969. Minneapolis, Minnesota. j 1

1971. Monticello Nuclear Generating Plant, Environmental Radiation Surveillance,  !

Annual Report, January 1,1970 to December 31,1970. Minneapolis, Minnesotc. j 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 through 1983. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1,  ;

to December 31,1977 through 1982 (prepared by Hazleton Environmental Sciences).

l Minneapolis, Minnesota.

1984 through 1998. Monticello Nuclear Generating Plant, Annual Radiation l Environraental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 l' to December 31, 1983 through 1997 (prepared by Teledyne Brown Engineering Environmental Services, Midwest Laboratory). Northbrook, Illinois 24 l

l

\ __ __________-

r 1 i l

)

1984a through 1998a. 11adiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1983 l through 1997.

1984b through 1998b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Ar,alysis Data Tables, January - December 1983 through 1997.

Teledyne Bf own Engineering Environmental Services, Midwest Laboratory 1992. Quality Assurance Program Manual, Revision 1, 20 August 1992.

1994. Quality Control Procedures Manual, Revision 18, 27 September 1994.

1995. Quality Control Program, Revision 0, 20 July 1995.

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

Laboratory, New York, NY.,16014.

U.S. Public Health Service.1967. Radioassay Procedures for Environmental Samples, National Center for Radiological Health, Rockville, Maryland (Public Health Service Publication No. 999-RH-27).

Wilson, D. W., G. M. Ward and J. E. Johnson. 1969. In Environmental Contamination by Radioactive Materials, International Atomic Energy Agency. p.125.

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E-__--_--___---_-_--___

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APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS I l l

l l

t I

l l

l NOTE: Teledyne's Midwest Laboratory participates in intercomparison studies administered by U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada. The results are reported in

~

l Appendix A. Also reported are results of Intemational Intercomparison and Teledyne testing of  :

l TLD's, as well as, in-house spikes, blanks, duplicates and mixed analyte performance evaluation }

l program results. Appendix A is updated four times a year; the complete Appendix is included in !

March, June, September and December monthly progress reports only, i January,1997 through December,1997 A-1 l

Anoendix A Interlaboratory Comoarison Program Results I

Teledyne Brown Engineering Environmental Services Midwest Laboratory (formerly Hazleton I Environruental Sciences) has participated in interlaboratory comparison (crosscheck) programs since the .j 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 known to the issuing agency but not to participant laboratories. The purpose of such a program is to provide an independent check on the laboratory's analytical procedures and to alert it to any possible problems.

l Participant laboratories measure the concentration of specified radionuclides and report them to the l 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. l The results in Table A-1 were obtained through participation in the environmental sample crosscheck program for milk, water and air filters during the past twelve months. Data for previous years is available upon request.

This program is conducted by the U.S. Environmental Protection Agency Office of Research and Development National Exposure Research Laboratory Characterization Research Division-Las Vegas, Nevada.

The results in Table A-2 were obtained for Thermoluminescent Dosimeters (TLDs), via various InternationalIntercomparisons of Environmental Dosimeters under the sponsorships listed in Table A-2. I Also Teledyne testing results are listed.

Table A-3 lists results of the analyses on in house " spiked" samples for the past twelve months. All samples are prepared using NIST traceable sources. Data for previous years available upon request.

Table A-4 lists results of the analyses on in-house " blank" samples for the past twelve months. Data for previous years available upon request.

l Table A-5 list results of the in-house " duplicate" program for the past twelve months. Acceptance is based on the difference of the results being less than the sum of the errors. Data for previous years available upon request.

The results in Table A-6 were obtained through participation in the mixed analyte performance evaluation program.

The results in Table A-7 were obtained through participation in the Environmental Measurement Laboratory Quality Assessment Program.

Attachment A lists acceptance criteria for " spiked" samples.

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

Al f

1

12-31-97 ,

A*ITACHMENT A ACCEPTANCE CRITERIA FOR " SPIKED" SAMPLES l

LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSES

  • One Standard Deviation Analysis Level for single determinations Gamma Emitters 5 to 100 pCi/ liter or kg 5.0 pCi/ liter

>100 pCi/ liter or kg 5% of known value Strontium-89 6

5 to 50 pCi/ liter or kg 5.0 pCi/ liter

>50 pCi/ liter or kg 10% of known value l 5.0 pCi/ liter j Strontium-90 6

2 to 30 pCi/ liter or kg

>30 pCi/ liter or kg 10% of known value l

Potassium-40 >0.1 g/ liter or kg - 5% of known value Gross alpha s20 pCi/ liter 5.0 pCi/ liter

>20 pCi/ liter 25% of known value Gross beta s100 pCi/ liter 5.0 pCi/ liter

>100 pCi/ liter 5% of known value Tritium 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 1

Plutonium 0.1 pCi/ liter, gram, or sample 10% of known value lodine-131, s55 pCi/ liter 6.0 pCi/ liter Iodine-129 6 >55 pCi/ liter 10% of known value Uranium-238, s35 pCi/ liter 6.0 pCi/ liter Nickel-63 6 >35 pCi/ liter 15% of known value  ;

6 Technetium-99 50 to 100 pCi/ liter 10 pCi/ liter 1#

  • 55 >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. l 6

Teledyne limit.

A2 l

1-

- - - - - - - - - - _ . - - - . ~ . - - . - - - - - - - . . - . - . . - - - - - - - _ . - - - - - - - - - - - - - - - - - - - _ - _ - _ . - - - - , _ _ A

l l

! Table A-1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne's

! Midwest Laboratory results'.

l Concentration in pCi/L l d

Lab Sample Date Teledyne Results EPA Result Control l Code Type Collected Analysis 2 Sigma' Is, N=1 Limits

- STW-782 WATER Jan,1997 Sr-89 9.710.6 12.0 5.0 3.3 - 20.7 STW-782 WATER Jan,1997 Sr-90 24.0 i 1.0 25.015.0 16.3 - 33.7 STW-783 WATER Jan,1997 Gr. Alphe 10.0 1.4 5.2 5.0 0.0 - 13.9 STW-783 WATER Jan,1997 Gr. Beta 15.812.0 14.7 5.0 6.0 - 23.4 STW-784 WATER Feb,1997 I-131

)

l 86.012.0 86.0 9.0 70.4 - 101.6 i STW-784 WATER Feb,1997 I-131 79.312.0 86.0 9.0 70.4 - 101.6

, STWW-786 WATER Feb,1997 Ra-226 6.7 t 0.2 5.9 0.9 4.3 - 7.5 STWW-786 WATER Feb,1997 Ra-228 8.4 1.1 8.2 2.1 4.6 - 11.8 STWW-786 WATER Feb 1997 Uranium 26.5 i 1.3 27.0 3.0 21.8 - 32.3 l STW-787 WATER Mar,1997 H-3 ,

7,594.0 1 279.7 7,900.0 790.0 6,529.4 - 9,270.6 STW-794 WATER Apr,1997 Gr. Alpha 44.3 1.6 48.0 12.0 27.2 - 68.8 STW-794 WATER Apr,1997 Ra-226 10.710.9 13.0 2.0 9.5 - 16.5 l STW-794 WATER Apr,1997 Ra-228 4.710.4 3.1 0.8 1.7 - 4.5 All raw data and calculations were reviewed for errors. The analysis was repeated with the technic;an ,

observed by the lab supervisor; the result of the reanalysis 3.110.5 pCi/L The suspected cause of the higher result was the lower than expected recovery of barium tracer. No further action is planned at this time.

l STW-794 WATER Apr,1997 Uranium 26.8 0.3 24.0 3.0 18.8 - 29.2 STW-795 WATER Apr,1997 Co-60 21.7 i 0.6 21.0 5.0 12.3 - 29.7

! STW-795 WATER Apr,1997 Cs-134 27.3i l.2 31.0i 5.0 22.3 - 39.7 STW-795 WATER Apr,1997 Cs-137 21.7 1.5 22.0 5.0 13.3 - 30.7 l l STW-795 WATER Apr,1997 Gr. Beta 98.2 i 2.1 102.1 15.3 75.6 - 128.6 l l STW-795 WATER Apr,1997 Sr-89 21.3 i l.2 24.0 t 5.0 15.3 - 32.7 i l STW-795 WATER Apr,1997 St-90 12.7 i 0.6 13.0 i 5.0 4.3 - 21.7 STW-796 WATER Jun,1997 Ba-133 24.7 1.2 25.0 5.0 16.3 - 33.7 STW-796 WATER Jun,1997 Co-60 18.7 0.6 18.0 i 5.0 9.3 - 26.7 STW-796 WATER Jun,1997 Cs-134 19.7 i 0.6 22.0 5.0 13.3 - 30.7 STW-796 WATER Jun,1997 Cs-137 52.0 i 2.0 49.0 i 5.0 40.3 - 57.7 I STW-796 WATER Jun,1997 Zn-65 101.0 i 2.0 100.0 1 10.'O 82.7 - 117.3 STW-797 WATER Jun,1997 Ra-226 2.7 0.1 3.0 0.5 2.1 - 3.9 STW-797 WATER Jun,1997 Ra-228 2.3 i 0.3 3.1 0.8 1.7 - 4.5 l STW-797 WATER Jun,1997 Uranium 38.1 1.0 40.3 4.0 33.4 - 47.2 l STW-799 WATER Jul,1997 Sr-89 37.7 3.2 44.0 5.0 35.3 - 52.7 i STW-799 WATER Jul,1997 Sr-90 16.0 1.0 16.0 5.0 7.3 - 24.7 STW-802 WATER Jul,1997 I-131 10.7 1.2 10.0 6.0 0.0 - 20.4 STW-800 WATER Jul,1997 Gr. Alpha 3.1 0.3 3.1 5.0 0.0 - 11.8 STW-800 WATER Jul,1997 Gr. Beta 13.9 0.2 15.1 5.0 6.4 - 23.8 STW-801 WATER Aug,1997 H-3 11,348.7 1 241.4 11,010.0 1,101.0 9,099.8 - 12,920.2 WATER STW-803 Sep,1997 Ra-226 20.010.8 20.0 ?o 14.8 - 25.2 Al-1

i i

i Table A-1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne's Midwest Laboratory results'.

Concentration in pCi/L" Lab Sample Date Teledyne Results EPA Result' Control Code Type Collected Analysis i2 Sigma

  • 1s, N=1 Limits STW-803 WATER Sep,1997 Ra-228 7.0 0.1 S.0 2.0 4.5 - 11.5 .

STW-803 WATER Sep,1997 Uranium 5.0 i 0.1 5.1 3.0 0.0 - 10.3 I STW-811 WATER Nov,1997 Ba-133 97.3 5.0 99.0 t 10.0 81.7 - 116.3 STW-811 WATER Nov,1997 Co-60 28.3 1.7 27.0 i 5.0 18.3 - 35.7  :

STW-811 WATER Nov,1997 Cs-134 9.7i l .0 10.0 5.0 1.3 - 18.7 STW-811 WATER Nov,1997 Cs-137 78.0 3.5 74.0 5.0 65.3 - 82.7 l STW-811 WATER Nov,1997 Zn-65 76.7 i 2.1 75.0 8.0 61.1 - 88.9

  • Results obtained by Teledyne Brown Engineering Environmental Services Midwest Laboratory as a q participant in the environmental sample crosscheck program operated by the Intercomparison and j Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, U.S. '

Environmental Protection Agency (EPA), Las Vegas, Nevada.

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 TBEESML 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.

l

,1 I

Al-2 l

i  !

w___ ___ - _ _ _ _ _ __ _ _ _ _ _ _

1 l

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

mR

- l Lab Teledyne Results Known Average i2 Sigma l Code TLD Type Date Measurement i 2 Sigma Value (All Participants) i 2nd International Intercomoarison 115-2 CaF2 : Mn Bulb Apr,1976 Field 17.011.9 17.1 16.4 7.7 115-2 CaF2 : Mn Bulb Apr,1976 Lab 20.8 i 4.1 21.3 18.8 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 Health of the University of l Texas, Houston, Texas.

3rd Intemational Intercomparison 115-3 CaF2 : Mn Bulb Jun,1977 Field 30.7 i 3.2 34.914.8 31.513.0 115-3 CaF2 : Mn Bulb Jun,1977 Lab 89.616.4 91.7 14.6 86.2 24.0 Third International Intercomparison of Environmental Dosimeters conducted in the summer of 1977 by Oak Ridge National Laboratory and the School of Public Health of the University of Texas, Houston, Texas.

4th International Intercomoarison 115-4 CaF2 : Mn Bulb Jun,1979 Field 14.1 1.1 14.1 1.4 16.0 9.0 115-4 CaF2 : Mn Bulb Jun,1979 Lab, High 40.4 1.4 45.8 9.2 43.9113.2 l 115-4 CaF : Mn Bulb Jun,1979 Lab, Low 9.8 i l.3 12.2 2.4 12.017.4 Fourth InternationalInterco.mparison of Environmental Dosimeters conducted in the summer of 1979 by the School of Public Health of the University of Texas, Houston, Texas.

5th International Intercomnarison 115-5A CaF:: Mn Bulb Oct,1980 Field 31.4 1.8 30.016.0 30.2 14.6 ,

115-5A CaF2 : Mn Bulb Oct,1980 Lab,End 96.6 5.8 88.4 8.8 90.7 31.2 115-5A CaF2 : Mn Bulb Oct,1980 Lab, Start 77.4 5.6 75.2 7.6 75.8 40.4 Fifth International Intercomparison of Environmental Dosimeters conducted in the fall of 1980 at Idaho Falls, l Idaho and sponsored by the School of Public Health of the University of Texas, Houston, Texas and the Environmental Measurements Laboratory, New York, New York, U.S. Department of Energy.

5th International Intercomp_aris.oll l 115-5B LiF-100 Chips Oct,1980 Field 30.3 i 4.8 30.0 6.0 30.2 14.6 115-5B LiF-100 Chips Oct,1980 Lab,End 85.4 11.7 88.4 i 8.8 90.7 31.2 115-5B LiF-100 Chips Oct,1980 Lab, Start 81.1 7.4 75.217.6 75.8 40.4 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 the Environmental Measurements Laboratory, New York, New York, U.S. Department of Energy.

6th International Intercomoarison 115-6 Teledyne did not participate in the Sixth International Intercomparison of Environmental Dosimeters.

l 7th International Intercomoarison l

115-7A LiF 100 Chips Jun,1984 Field 75.4 t 2.6 75.8 6.0 75.1 29.8 115-7A LiF-100 Chips Jun,1984 Lab, Co-60 . 80.0 i 3.5 79.9 4.0 77.9 27.6 ,

115-7A LiF-100 Chips Jun,19M Lab, Cs-137 66.6 t 2.5 75.0 3.8 73.0 22.2 A2-1

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

mR Lab Teledyne Results Known Average 2 Sigma Code 'i oD Type Date Measurement 12 Sigma Value (All Participants)

Seventh International 1ntercomparison of Environmental Dosimeters conducted in the spring and summer of 1984 at Las Vegas, Nevada, and sponsored by the U.S. Department of Energy, The Nuclear Regulatory ,

Commission, and the U.S. Environmental Protection Agency. '

i 7th International Intercomnarison 115-7B LiF-100 Chips Jun,19M Field 71.512.6 75.816.0 75.1 29.8 115-7B LiF-100 Chips Jun,19M Lab Co-60 84.816.4 79.914.0 77.9 27.6 115-7B LiF-100 Chips Jun,1984 Lab, Cs-137 78.811.6 75.013.8 73.0 i 22.2 Seventh InternationalIntercomparison of Environmental Dosimeters conducted in the sprmg and summer of 1984 at Las Vegas, Nevada, and sponsored by the U.S. Department of Energy, The Nuclear Regulatory Commission, and the U.S. Environmental Protection Agency.

7th International Intercomnarison 115-7C CaSO4 : Dy Jun,1984 Field 76.812.7 75.8 6.0 75.1129.8 Cards 115-7C CaSO4 : Dy Jun,1984 Lab, Co-60 82.5 i 3.7 79.9 4.0 77.9 27.6

Cards 115-7C CaSO4
Dy Jun,1984 Lab, Cs-137 79.0 i 3.2 75.0 3.8 73.0 x 212 Cards

! Seventh InternationalIntercomparison of Environmental Dosimeters conducted in the spring and summer of 1984 at Las Vegas, Nevada, and sponsored by the U.S. Department of Energy, The Nuclear Regulatory Commission, and the U.S. Environmental Protection Agency.

8th International Intercomnarison 115-8A LiF-100 Chips Jan,1986 Field, Site 1 29.5 1.4 29.7 i l.5 28.9 12.4 115-8A LiF-100 Chips Jan,1986 Field, Site 2 11.3 0.8 10.4 0.5 10.1 9.1 115-8 A LiF-100 Chips Jan,1986 Lab, Cs-137 13.7 i 0.9 17.210.9 16.2 6.8 Eighth International Intercomparison of Environmental Dosimeters conducted in the fall and winter of 1985-1906 at New York, New York, and sponsored by the U.S. Department of Energy.

8th International Intercomparison {

115-8B LiF-100 Chips Jan,1986 Field, Site 1 32.311.2 29.7 1.5 28.9 12.4 115-8B LiF-100 Chips Jan,1986 Field, Site 2 9.0 1.0 10.4 0.5 10.119.0 115-8B LiF-100 Chips Jan,1986 Lab, Cs-137 15.8 0.9 17.2 0.9 16.216.8 i Eighth International Intercomparison of Environmental Dosimeters conducted in the fall and winter of

! 1985-1986 at New York, New York, and sponsored by the U.S. Department of Energy.

8th International Intercomparison 115-8C CaSO4 : Dy Jan,1986 Field, Site 1 32.2 i 0.7 29.7 1.5 28.9 12.4 Cards 115-8C CaSO4 : Dy Jan,1986 Field, Site 2 10.6 0.6 10.410.5 10.1 9.0 Cards 115-8C CaSO4 : Dy Jan,1986 Lab, Cs-137 18.110.8 17.2 0.9 16.2 6.8 Cards i

A2-2

\

4 L______._________________ _ _ _ _ _ _ _ _ _ _ _ . . .

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

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

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.

9th International Intercomnarison 115-9 j Re Ninth International Intercomparison of Environmental Dosimeters was not available to Teledyne's )

Midwest Laboratory.

)

10th International Intercomparison 115-10A LiF-100 Chips Aug,1993 Field 25.7 1.4 27.0 1.6 26.4 10.2 115-10A LiF-100 Chips Aug,1993 Lab,1 22.7 1.6 25.9 1.3 25.0 9.4 115-10A LiF-100 Chips Aug,1993 Lab,2 62.7 2.6 72.7 1.9 69.8 20.3 The 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.

10th Intemational Intercomparison 115-10B CaSO,: Dy Aug,19^3 Field 26.0 i 2.3 27.0 1.6 26.4 i 10.2 Cards

)

115-10B CaSO,: Dy Aug,1993 Lab,1 24.111.7 25.9 1.3 25.0 9.4 j Cards i 115-10B CaSO4 : Dy Aug,1993 Lab,2 69.2 i 3.0 72.7 1.9 69.8 20.3 Cards The Tenth International Intercomparison of Environmental Dosimeters conducted in 1993 at Idaho State University and sponsc,:ed by the U.S. Department of Energy and the Idaho State University.

lith International Intercomparison 115-11 Apr,1997 The Eleventh International Intercomparison of Environmental Dosimeters was conducted in 1997 and was organized by the Department of Energy's Environmental Measurements Laboratory in collaboration with Brookhaven National Laboratory and the National Institute of Standards and Technology.

l Results for the Eleventh International Intercomparison were originally reported in error; The results are being i re-evaluated and will ba reported in a later update.

l Teledvne Testing i

89-1 LiF-100 Chips Sep,1989 Lab 21.010.4 22.4 ND l ND = No Data; Teledyne Testing was only performed by Teledyne.

l Chips were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in September,1989.

Teledvne Testing 89-2 CaSO4 : Dy Nov,1989 Lab 20.9 1.0 20.3 ND l Cards ND = No Data; Teledyne Testing was only performed by Teledyne.

l Cards were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in June,1990.

\ -

A2-3 L___-_____-____________.

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

mR Lab Teledyne Results Known Average i2 Sigma Code TLD Type Date Measurement 2 Sigma Value (All Participants)

Teledvne Testine 90-1 CaSO4 : Dy Jun,1990 Lab 20.611.4 19.6 ND Cards ND = No Data; Teledyne Testing was only performed by Teledyne.

Cards were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in June,1990.

Diedvne Testing 90-2 CaSO,: Dy Jun,1990 Lab 100.8 4.3 100.0 ND Cards L ND = No Data; Teledyne Testing was only performed by Teledyne. I Cards were irradiated by Dosimetry Asssociates,Inc., Northville, MI, in October,1990.

Teledene Testing j

91-l' CaSO4 : Dy Oct,1990 Lab,1 33.412.0 32.0 ND '

Cards 91-1 CaSO.: Dy Oct,1990 Lab,2 55.2 i 4.7 58.8 ND Cards 91-1 CaSO4 : Dy Oct,1990 Lab,3 87.8 i 6.2 85.5 ND Cards ND = No Data; Teledyne Testing was only performed by Teledyne.

Cat ds were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in October,1991.

Teledyne Testing 92-1 LiF-100 Chips Feb,1992 ' Lab,1 11.1 0.2 10.7 ND 92-1 LiF-100 Chips Feb,1992 Lab,2 25.6 0.5 25.4 ND 92-1 LiF-100 Chips Feb,1992 Lab,3 46.410.5 46.3 ND ND = No Data; Teledyne Testing was only performed by Teledyne.

Chips were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in February,1992.

Diedyne Testing 92-2 CaSO.: Dy Apr,1992 Reader 1, #1 20.1 0.1 20.1 ND Cards 92-2 CaSO : Dy Apr,1992 Reader 1, #2 40.6i 0.1 40.0 ND Cards 92 2 CaSO4 : Dy Apr,1992 Reader 1, #3 60.0i l.3 60.3 ND Cards i 92-2 CaSO,: Dy Apr,1992 Reader 2, #1 20.3 0.3 20.1 ND Cards 92-2 CaSO4 : Dy Apr,1992 Reader 2, #2 39.2 i 0.3 40.0 ND l Cards 92-2 CaSO : Dy Apr,1992 Reader 2, #3 60.7 i 0.4 60.3 ND Cards A2-4 i

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

mR

! Lab Teledyne Results Known Average 2 Sigma l Code TLD Type Date Measurement 2 Sigma Value (All Participants)

ND = No Data; Teledyne Testing was only performed by Teledyne.

Cards were irradhted by Teledyne Isotopes, Inc., Westwood, New Jersey, in April,1992.

Teledyne Testing 93-1 Teledyne Mar,1993 Lab,1 10.0 1.0 10.2 ND LiF-100 Chips 93-1 Teledyne Mar,1993 Lab,2 25.2 2.2 25.5 ND LiF-100 Chips 93-1 Teledyne Mar,1993 Lab,3 42.715.7 45.9 ND LiF-100 Chips ND = No Data; Teledyne Testing was only performed by Teledyne.

Chips were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in March,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.

Teledyne Testing 94-1 Teledyne Nov,1994 Lab,1 15.6 0.4 14.9 ND LiF-100 Chips 94-1 T lyra Nov,1994 Lab,2 30.2 0.4 29.8 ND LiF-ivJ Cl.ips 94-1 Teledyne Nov,1994 Lab,3 59.2 0.3 59.7 ND LiF-100 Chips 94-1 CaSO4 : Dy Nov,1994 Reader 1, #1 14.9 0.1 14.9 ND Cards 94-1 CaSO : Dy Nov,1994 Reader 1, #2 4 30.8 i 0.1 29.8 ND Cards 94-1 CaSO4 : Dy Nov,1994 Reader 1, #3 58.9 0.3 59.7 ND Cards 94-1 CaSO4 : Dy Nov,1994 Reader 2, #1 15.4 0.2 14.9 ND Cards 94-1 CaSO4 : Dy Nov,1994 Reader 2, #2 31.4 0.2 29.8 ND Cards 94-1 CaSO4 : Dy Nov,1994 Reader 2, #3 60.110.3 59.7 ND Cards ND = No Data; Teledyne Testing was only performed by Teledyne.

Cards were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in November,1994.

Teledvne Testing 95-1 LiF-100 Chips Mar,1995 Lab,1 16.1 0.2 15.7 95-1 LiF-100 Chips Mar,1995 Lab,2 31.7 0.1 32.3 95-1 LiF-100 Chips Mar,1995 Lab,3 59.710.6 60.8 95-1 CaSO : Dy Mar,1995 Reader 1, #1 4 16.410.1 15.7 ND Cards A2-5

I i

l l

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

]

mR Lab Teledyne Results Known Average 2 Sigma Code TLD Type Date Measurement i 2 Sigma Value (All Participants) 95-1 CaSO4 : Dy Mar,1995 Reader 1, #2 34.9 i 0.1 32.3 ND Cards 95-1 CaSO : Dy Mar,1995 Reader 1, #3 4 64.4 1.5 60.8 ND Cards ND = No Data; Teledyne Testing was only performed by Teledyne.

Cards and Chips were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in March,1995.

Teledyne Testinc 95-2 CaSO4 : Dy Mar,1995 Reader 2, #1 16.4 i 0.2 15.7 ND Cards 95-2 CaSO4 : Dy Mar,1995 Reader 2, #2 33.910.4 32.3 ND I Cards

{

95-2 CaSO4 : Dy Mar,1995 Reader 2, #3 60.5 i 0.3 60.8 ND l Cards '

ND = No Data; Teledyne Testing was only performed by Teledyne.

Cards and Chips were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in March,1995.

Teledvne Testing ,

96-1 LiF-100 Chips Mar,1996 Lab,1 15.9 i 0.3 15.4 l 96-1 LiF-100 Chips Mar,1996 Lab,2 29.4 0.3 30.8 96-1 LiF-100 Chips Mar,1996 Lab,3 62.5 1.3 62.5 l 96-1 CaSO4 : Dy Mar,1996 Reader 1, #1 14.4 0.1 15.4 ND Cards 96-1 CaSO4 : Dy Mar,1996 Reader 1, #2 31.8 0.1 30.8 ND Cards 96-1 CaSO4 : Dy Mar,1996 Reader 1, #3 64.7 i 0.4 62.5 ND Cards Teledvne Testing 96-2 CaSO4 : Dy Mar,1996 Reader 2, #1 14.310.4 15.4 ND Cards 96-2 CaSO4 : Dy Mar,1996 Reader 2, #2 31.8 0.1 30.8 ND Cards 96-2 CaSO : Dy Mar,1996 Reader 2, #3 4 68.6 i 0.1 62.5 ND Cards ND = No Data; Teledyne Testing was only performed by Teledyne.

Chips and Cards were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in to ; ca,1996.

Idedyne Testing 97-1 LiF-100 Chips Mar,1997 Lab,1 13.4 1.4 15.0 97-1 LiF-100 Chips Mar,1997 Lab,2 29.8 i 0.6 30.1 97-1 LiF-100 Chips Mar,1997 Lab,3 63.4 i 0.9 60.2 A2-6 L____________-________

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

Telcdyne Results Known Average 2 Sigma Code TLD Type Date Measurement i 2 Sigma Value (All Participarsl

! 97-1 CaSO.: D;- Mar,1997 Reader 1, #1 15.5 0.1 15.0 ND Cards I

! '97-1 CaSO4 : Dy Mar,1997 Reader 1, #2 34.010.1 30.1 ND {

(.ards 97-1 CaSO4 : Dy Mar,1997 Reader 1, #3 68.312.1 60.2 ND Cards }

7eledvne Testing 97-2 CaSO.: Dy Mar,1997 Reader 2, #1 16.8 0.3 15.0. ND Cards i 97-2 CaSO.: Dy Mar,1997 Reader 2, #2 36.210.2 30.1- ND Cards i 97-2 CaSO : Dy Mar,1997 Reader 2, #3 69.610.2 60.2 ND Cards ND = No Data; Teledyne Testing was only performed by Teledyne. 1

- Chips and Cards were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in March,1997.

l l

I i.

f

)

I l

l A2-7

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

l Concentration in pCi/L' Lab Sarnple Date Teledyne Results Known Control" l Code Type Collected Analysis 2s, n=1 6 Activity Limits SPW-844 WATER Jan,1997 Th-230 3.120 0.104 3.070 1.842 - 4.298 SPW-344 WATER Jan,1997 Th-232 3.355 0.10S 3.070 1.842 - 4.298 l

l SPW-548 WATER Feb,1997 Gr. Beta 43.881 1.303 41.860 31.860 - 51.860 l

SPMI-534 MILK Feb,1997 Cs-134 48.649 4.940 56.400 46.400 - 66.400 .

SPMI-534 MILK Feb,1997 Cs-137 54.700 8.450 52.300 42.300 - 62.300 SPMI-533 MILK Feb,1997 Sr-89 49.849 7.940 40.030 30.030 - 50.030 l SPMI-535 MILK Feb,1997 St-90 48.856 1.740 50.300 40.240 - 60.360 SPW-536 WATER Feb,1997 H3 27229.744 452.056 2S234.000 22587.200 - 338SO.800 S P W-53 -- WATER Feb,1997 Co-60 65.219 8.790 62.950 52.950 - 72.950 SPW-547 WATER Feb,1997 Cs-134 52.996 8.000 56.430 46.430 - 66.430 SPW 547 WATER Feb,1997 Cs-137 60.419 12.?00 52 320 42.320 - 62.320 SPW-600 WATER Feb,1997 I-131 72.182 1.009 66.300 53.040 - 79.560 SPW-600 WATER Feb,1997 I-131(g) 68.816 14.800 66.300 39.780 - 76.300 l

l SPCH-701 CHARCOAL Feb,1997 I-131(g) 1,171 0.023 1.080 0.648 - 1.512 l CANISTER SPAP-704 AIR FILTER Feb,1997 Gr. Beta 6.302 0.041 5.740 0.000 - 15.740 SPW-838 WATER Feb,1997 Ra-226 19.770 0.189 17.300 12.110- 22.490 SPW-838 WATER Feb,1997 Ra-228 36.784 2.571 31.300 21.910 - 40.690 SPW-840 WATER Feb,1997 Sr-90 35.822 2.020 33.520 26.816 - 40.224 SPW-841 WATER Feb,1997 I-129 15.525 i 0.854 14.942 2.942 - 26.941 SPW-843 WATER Feb,1997 Fe-55 1.418 0.530 1.535 0.000 - 21.535 SPAP-2730 AIR FILTER Mar,1997 Cs-137 2.151 0.025 1.900 1.140 - 2.660 SPMI-1670 MILK Apr,1997 Cs-134 50.282 8.920 53.600 43.600 - 63.600 SPMI-1670 MILK Apr,1997 Cs-137 56.090 14.900 52.100 42 100 - 62.100 SPW-2073 WATER Apr,1997 Co-60 54.077 i 4.280 51.300 41.300 - 61.300 l

l SPW 2073 WATER Apr,1997 Cs-134 47.636 4.150 53.200 43.290 - 63.200 ,

SPW-2073 WATER Apr,1997 Cs-137 60.688 5.760 52.100 42.100 - 62.100 l SPW-2075 WATER Apt,1997 Gr. Alpha 34.554 2.677 41.300 20.650 - 61.950 SPW-2075 WATER Apr,1997 Gr. Beta 38.729 1.658 41.700 31.700 51.700 SPW-2546 WATER Apr,1997 H-3 25445.478 428.384 26257.000 21005.600 - 31508.400 SPF-3434 FISH May,1997 Cs-134 0.199 0.020 0.222 0.133 - 0.311 )

SPF-3434 FISH May,1997 Cs-137 0.234 0.037 0.227 0.136 - 0.31S SPW-3750 WATER Jun,1997 I-131 76.174 0.776 71.800 57.440 - 86.360 SPW-3750 WATER Jun,1997 I-131(g) 66.587 8.750 71.800 43.080 - 81.800 l SPMI-3752 MILK Jun,1997 1-131 79.851 0.833 71.800 57.440 - 86.160 SPMI-3752 MILK Jun,1997 I-131(g) 78.887 i 7.750 71.800 43.080 - 81.800 l SPCH-3754 CA A Jun,1997 1-131(g) 81.869 i 0.317 76.600 45.960 - 86.600 E )

SPMI-4216 MILK Jul,1997 Cs-134 38.265 5.450 39.500 29.500 - 49.500 SPMI-4216 MILK Jul,1997 Cs 137 46.472 10.600 41.500 31.500 - 51.500 i SPMI 4216 MILK Jul,1997 I-131 75.247 0.831 83.230 66.584 - 99.876 SPMI-4216 MILK Jul,1997 I131(g) 84.872 7.010 83.230 49.938 - 93.230 l

A3-1

l l

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

1 I

Concentration ir, pCi/L' l Lab Sample Date Teledyne Results Known Controf Code Type Collected Analysis 2s, n=1" Activity Limits SPMI-4216 hilLK Jul,1997 Sr-90 33.610 1.430 33.210 26.568 - 39.852 l SPW-4420 WATER Jul,1997 Co-60 26.270 4.360 24.900 14.900 - 34.900 SPW-4420 WATER Jul,1997 Cs-134 36.591 5.040 39.540 29.540 - 49.540 SPW-4420 WATER Jul,1997 Cs-137 45.552 7.770 41.480 31.480 - 51.480 SPW-4420 WATER Jul,1997 1131(g) 85.221 9.660 83.230 49.938 - 93.230 SPW-4420 WATER Jul,1997 Sr-90 36.285 1.629 33.210 26.568 - 39.852 SPMf-4916 h1 ILK Jul,1997 1-131(g) 84.870 7.010 83.230 49 938 - 93.230 SPW-5470 WATER Jul,1997 Fe-55 4.548 0.640 5.477 0.000 - 25.4~,7 SPW-5472 WATER Jul,1997 H-3 41026.000 329.000 41578.000 33262.400 - 49893.600 SPW-5474 WATER Jul,1997 Gr. Alpha 49.266 2.081 41.305 20.653 - 61.95S SPW-5474 WATER Jul,1997 Gr. Beta 44.450 1.334 41.406 31.406 - 51.406 SPF-5476 FISH Jul,1997 Cs-134 0.641 0.030 0.700 0.420 - 0.980

$PF-5476 FISH Jut,1997 Cs-137 0.632 0.042 0.527 0.316 - 0.738 SPW-7500 WATER Oct,1997 Co-60 30.424 7.530 3314' '3.642 - 43.642 SPW-7500 WATER Oct,1997 Cs-134 37.410 6.690 36.086 26.086 - 46.086 SPW-7500 WATER Oct,1997 Cs-137 52.845 1 11.300 41.221 31.221 - 51.221 The Cs-137 spike is suspect. No errors were found in the spectroscopy program and the Cs-134 and Co-60 test results on the same sample were very good. Sample results prepared with a new standard are acceptable.

SPW-7500 WATER Oct,1997 I-131 78.126 1.201 78.302 62.642 - 93.962 SPMI-7505 hilLK Oct,1997 Cs ' 34 15.166 3.250 18.043 8.043 - 28.043 SPMI-7505 hi!LK Oct,1997 Cs-137 91.110 i 8.370 82.440 72.440 - 92.440 SPMl-7505 h11LK Oct,1997 I-131 73.529 i 1.253 78.302 62.642 - 93.962 SPMI-7503 hi!LK Oct,1997 I-131(g) 74.613 i 8.810 78.302 46.981 - 88.302 SPMI-7506 hilLK Oct,1997 Sr-89 31.281 i 4.601 39.490 29A90 - 49.490 SPCH-7727 CHARCOAL Oct,1997 I-131(g) 0.450 1 0.050 0.440 0.254 - 0.616 CANISTER SPAP-7730 AIR FILTER Oct,1997 Gr. Beta 3.080 0.030 3.040 1.824 - 4.256 (ss)

SPF-8485 FISH Nov,1997 Cs-134 0.306 i 0.025 0.318 0.191 - 0.445 SPF-8485 FISH Nov,1997 Cs-137 0.738 0.049 0.649 0.389 0.509 SPW-9315 WATER Nov,1997 Gr. Alpha 51.420 i 6.385 41.280 20.640 - 61.920 SPW-9315 WATER Nov,1997 Gr. Beta 48.938 i 3.735 43.164 33.164 - 53.361 SPW-9706 . WATER Dec,1997 Gr. Alpha 40.480 1 4.598 41.280 20.640 - 61.920 SPW-9853 WATER Dec,1997 Co-60 44.900 8.290 42.080 32.080 - 52.0S0 SPW-9853 WATER Dec,1997 Cs-134 40.010 7.010 37.850 27.850 - 47.850

  • All results are in pCi/L, except for elemental potassium (K) in milk, which are in mg/L.; air filter samples, which are in pCi/ Filter; and food products, which are in mg/kg.
  • All samples are the results of single determinations.

' Control limits are based on Attachment A, page A2 of this report.

t NOTE: Foi fish, Jello is used for the spike matrix. For vegetation, Sawdust is used for the spike matrix.

A3-2

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

Concentration pCi/L' Teledyne Results Acceptance Lab Sample Sample (4.66 Sigma) Criteria Code Type Date Analysis LLD Activitv' (4 66 Sicma)

SPW-845 WATER Jan 1997 Th-226 <0.9 -0 263 0.560 <1.000 SPW-845 WATER Jan 1997 Th-230 <0.2 0.191 0.236 <1.000 SPW-845 WATER Jan 1997 Th-232 <0.2 -0.018 0.145 <1.000 SPMI-533 MILK Feb l997 Cs-134 <2.7 -0.531 0.647 < 10.000 i SPMI-533 MILK Feb l997 Cs-137 <5.5 0.526 3.380 < 10.000

! SPW-2 WATER Feb l997 Ra-226 <0.1 0.000 0.034 <1.000 SPMI-533 M1LK Feb 1997 1-131 <0,5 -0.031 0.316 < 0.500

)

SPMI-533 . MILK Feb 1997 Sr-89 <0 7 -0.994 0.952 <5.000 l SPMI 533 MILK Feb l997 Sr-90 N/.A 1.695 0.439 <1.000 f i Low level of Sr-90 concentration in milk (1-5 pCi/L) is not unusual. l I SPW-537 WATER Feb l997 Co-60 <3.1 0.065 0.179 < 10 000 SPW-537 WATER Feb 1997 Cs-134 <3.5 0.905 1.100 < 10.000 SPW-537 WATER Feb l997 Cs-137 < 1.7 -1.430 1.800 < 10.000 SPW-537 WATER Feb 1997 Gr. Alpha <0.4 -0.109 0.218 ,

<1.00u l SPW-537 WATER Feb l997 Gr. Beta < 0. 9 -0.155 0.596 < 3.200 SPW-537 WATER Feb l997 I-131 <0.4 -0.275 0.235 <0.500 l SPW-537 WATER Feb l997 Sr-89 < 0. 8 -0.167 0.557 < 5.000 SPW-537 WATER Feb 1997 Sr-90 <0.5 0.099 0.239 <1.000 SPW-842 WATER Feb 1997 Fe-55 <0.7 -0.403 0.374 < 1000.000 SPW-d42 WATER Feb l997 I-129 <0.9 -0.129 0.442 <1.500 i SPW-842 WATER Feb 1997 Ra-226 <0.04 0.013 0.026 <1.000 SPAP-2731 AIR FILTER Mar 1997 Co-60 <2.5 0.000 0.000 < 10.000 SPAP-2731 AIR FILTER Mar 1997 Cs-134 <2.6 -0.000 0.000 < 10.000 SPAP-2731 AIR FILTER Mar 1997 Cs-137 <2.9 0.000 0.001 < 10.000 SPMI-1669 MILK Apr1997 Cs-134 <5.5 0.069 0.118 < 10.000 SPMI-1669 MILK Apr1997 Cs-137 <3.8 0.717 2.480 < 10.000 SPW-2074 WATER Apr1997 Co-60 <3.6 0.857 8.380 < 10.000

' SPW 2074 WATER Apr1997 Cs-134 <4.7 1610 10.200 < 10.000 SP'N-2074 WATER Apr1997 Cs-137 <5.0 1.800 3.200 < 10.000 SPW-2074 WATER Apr1997 Gr. Alpha <0.5 0.119 0.307 <1.000 SPW-2074 WATER Apr 1997 Gr. Eeta < 1. 3 0.464 0.720 < 3.200 SPW 2547 WATER Apr 1997 H-3 < 150 12.822 75.126 < 200.000 SPW-5 WATER May 1997 Ra-226 <0.03 -0.053 0.025 <1.000 l

SPF-3435 FISH May 1997 Cs-134 <0.015 -0.014 0.002 < 10.000 I

SPF-3435 FISH May 1997 Cs-137 <0.016 0.001 0.011 < 10.000 SPW-6 WATER Jun1997 Ra-226 <0.04 -0.044 0.027 <1.000 A4-1

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

)

Concentration pCi/ L*. I Teledyne Results Acceptance Lab Sample Sample (4.66 Sigma) Criteria Type l Code Date Analysis LLD Activitv' (4.66 Siema) j l

SPW-3751 WATER Jun 1997 1-131 <0.3 -0.127 0.145 < 0.500 SPMI-3753 MILK Jun1997 I-131 <0.3 0.089 0.167 < 0.500 SPCH-3755 CHARCOAL Jun1997 I-131(g) <0.017 0.010 0.009 < 9.600 CANISTER SPMI-4217 MILK Jul1997 Co-60 <4.8 -0.392 1.230 < 10.000 SPMI-4217 MILK Jul1997 Cs-134 <3.0 -0.874 1.700 < 10.000 SPMI-4217 MILK Jul1997 Cs-137 <5.9 1.600 i 3.430 < 10.000 SPMI-4217 MILK Jul1997 I-131 < 0. 3 -0.049 0.171 <0.500 SPW-4421 WATER Jul1997 Co-60 < 1.9 -4.660 4.750 < 10.000 SPW-4421 WATER Jul1997 Cs-134 <4.7 -1.450 3.090 < 10.000 SPW-4421 WATER Jul1997 Cs-137 <6.7 0.739 4.550 < 10.000 SPMI-4217 MILK Jul1997 Sr-89 < 1. 5 -0.165 1.901 <5.000 SPMI-4217 MILK Jul1997 Sr-90 N/A 1.677 0.418 <1.000 Low level of Sr-90 concentration in milk (1-5 pCi/L) is not unusual.

SPW-4421 WATER Jul1997 Sr-89 <1.7 0.917 1.547 <5.000 SPW-4421 WATER Jul1997 Sr-90 <0.6 0.341 0.332 <1.000 SPW-5471 WATER Jul1997 Fe-55 <733 48.157 448.317 < 1000.000 SPW-5473 WATER Jul1997 H-3 <161 22l700 58.200 < 200.000 S.oW-5475 WATER Jul1997 Gr. Alpha <0.6 0.170 0.425 <1.000 SPW-5475 WATER Jul1997 Gr. Beta <0.5 0.173 0.473 < 3.200 SPF-5477 FISH Jul1997 Co-60 <0.011 -0.001 0.002 < 10.000 SPF-E477 FISH Jul1997 Cs-134 <0.015 0.005 0.00S < 10.000 SPF-5477 FISH Jul1997 Cs-137 <0.018 0.006 0.010 < 10.000 SPW-7591 WATER Oct 1997 I-131 <0.4 0.010 0.009 <0.500 SPW-7501 WATER Oct 1997 Sr-89 < 1.1 -0.650 0.800 < 5.000 SPW-7504 WATER Oct 1997 Sr-90 <0.4 0.150 0.210 <1.000 SPMI-7507 MILK Oct 1997 Co-60 <6.2 -1.190 1.620 < 10.000 SPMI-7507 MILK Oct 1997 Cs-134 <4.9 1.710 1.950 < 10.000 SPMI-7507 MILK Oct 1997 Cs-137 <6.5 -0.232 .3.740 < 10.000 SPMI 7507 MILK Oct 1997 I-131 < 0. 3 -0.022 0.157 <0.500 SPMI-7507 MILK Oct 1997 Sr-89 < 1. 0 0.662 1.107 < 5.000 SPMI-7507 MILK Oct 1997 Sr-90 N/A 1.031 0.319 <1.000 Low level of St-90 concentration in milk (1-5 pCi/L) is not unusual.

R A-W-11 WATER Dec 1997 Ra-228 <0.7 0.134 0.318 <1.000 SPW-9852 WATER Dec 1997 Co-60 <2.4 -1.600 9.460 < 10.000 l SPW-9852 WATER Dec 1997 Cs-134 <5.7 -0.450 2.340 < 10.000 A 4-2

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

Concentration pCi/L".

Teledyne Results Acceptance Lab Sample Sample (4.66 Sigma) Criteria Code Type Date Analysis LLD Activity" (4.66 Siema)

SPW-9852 WATER Dec 1997 Cs-137 <6.0 2.190 3.550 < 10.000 I

' Liquid sample results are reported in pCi/ Liter, air filter sample results are in pCi/ filter, charcoal sarnple results are in pCi/ charcoal, and solid sample results are in pCi/ kilogram.

The activity reported is the net activity result.

A4-3

l l

Table A-5. In-house " duplicate" samples.

Concentration in pCi/L' l Lab Sample First Second Averaged l Codes

  • Date Analysis Result Result Result l SW - 42, 43 Jan,1997 Gr. Beta 3.0753 0.9097 2.5036 0.8819 2.7S94 0.6335 MI - 63,64 Jan,1997 Co-60 0.8960 2.5500 0.8290 1.4300 0.8625 t 1.4618 MI - 63,64 Jan,1997 Cs-137 0.4480 2.0600 0.7240 1.3800 0.5S60 1.2398 ,

MI - 19,20 Jan,1997 Co-60 2.7900 2.6200 1.4300 2.4700 2.1100 1.8004 I MI - 19,20 Jan,1997 Cs-137 -0.8750 2.7600 2.3900 1.9100 0.7575 1.6782 MI - 92,93 Jan,1997 I-131 0.0455 t 0.2124 0.1031 0.2405 0.0743 0.1604 MI - 92,93 Jan,1997 K-40 1,466.8000 129.0000 1,417.3000 163.0000 1,442.0500 i 103.9331 WW - 116,117 Jan,1997 I-131 0.1299 0.2579 -0.0824 0.2359 0.0237 0.1747 LW - 146,147 Jan,1997 Co-60 -0.1850 0.4500 1.9100 16.9000 0.8625 8.4530 LW - 146,147 Jan,1997 Cs-137 -0.8360 i 2.1600 0.2350 3.4500 -0.3005 2.0352 LW - 146,147 Jan,1997 Gr. Beta 6.9782 1.4082 7.8900 1.5599 7.4341 i 1.0507 LW - 224,225 Jan,1997 Co-60 1.8300 4.2500 -1.2200 0.9290 0.3050 2.1752 LW - 224,225 Jan,1997 Cs-137 -0.9650 3.4000 1.4500 1.7100 0.2425 1.9029 l

LW - 224,225 Jan,1997 Gr. Beta 6.2889 1.3951 7.3610 1.5370 6.8250 1.0379 j WW - 322,323 Jan,1997 H-3 -5.4270 80.6586 -14.4721 80.2518 -9.9496 56.8906 CW - 355,356 Jan,1997 Gt ieta 3.1262 1.4281 2.05S9 1.4561 2.5926 1.0198 CW - 355,356 Jan,1997 Gr. Beta -0.3849 i l.2993 0.44D + 1.3725 0.0296 0.9450 CW - 299,300 Jan,1997 Gr. Beta 2.4965 1.0877 2.7913 2. t o 2.6439 0.9146 CW - 299,300 Jan,1997 Gr. Beta 0.2070 i l.3507 0.7394 1.3%./ 0.4732 0.9715 SW - 441, 442 Jan,1997 Co-60 -0.2460 i 1.3100 0.3250 0.3190 0.0395 0.6741 SW - 441,442 Jan,1997 Cs-137 0.0619 2.3900 3.0200 2.8400 1.5410 1.8559 SWU - 389,390 Jan,1997 Gr. Beta 2.7555 0.5392 2.6585 0.5182 2.7070 0.3739 SWU - 389, 390 Jan,1997 H-3 158.6398 94.8968 125.0455 93.5661 141.8427 66.6333 MI - 377,378 Jan,1997 1-131 0.1482 1 0.2260 0.0950 0.2541 0.1216 0.1'700 MI- 377,378 Jan,1997 K-40 1,379.5000 122.0000 1,304.8000 i 113.0000 1,342.1500 83.1460 MI 377,378 Jan,1997 Sr-89 -0.4172 0.8436 -0.2671 0.7827 -0.3421 0.5754 MI - 377,378 Jan,1997 Sr-90 0.9881 0.3785 1.0431 0.3340 1.0156 0.2524 CW - 416,417 Jan,1997 Gr. Beta 3.7493 i 1.2558 4.5363 1.1489 4.1428 0.8510 CW - 416,417 Jan,1997 Gr. Beta 0.1479 1.3455 0.6807 1.3926 0.4143 0.9682 PW - 607,608 Jan,1997 Co-60 -0.4870 i 0.6140 0.8310 2.4300 0.1720 1.2532 PW - 607,608 Jan,1997 Cs-137 -0.7370 2.6100 0.2580 3.0900 -0.2395 2.0224 PW - 607,608 Jan,1997 Gr. Beta 5.7315 t l.8872 5.5786 1.7689 5.6550 1.2933 CW - 846,847 Jan,1997 Gr. Alpha 0.0484 1 0.4520 0.6758 0.4786 0.3621 0.3292 CW - 846,847 Jan,1997 Gr. Beta 1.3287 0.5381 2.1250 0.5415 1.7268 0.3817 CW - 846,847 Jan,1997 H-3 1,518.5023 i 131.0155 1,631.7608 134.0877 1,575.1316 93.7344 CW - 846,847 Jan,1997 Sr-89 0.3800 i 0.5210 0.7406 0.8976 0.5603 0.5189 CW - 846,847 Jart,1997 St-90 0.1424 0.2458 0.7292 0.3717 0.4358 0.2228 A5-1

7_

h ,,

Table A-5. In-house " duplicate" samples.

Concentration in pCi/L' Lab Sample First Second Averaged  !

Codes" Date Analysis Result Result Result /

' WW - 576,577 Fel,1997 H-3 150.9770 i 84.0813 241.2023 87.8687 196.0S97 60.80S3 MI - 486,487 Feb,1997 I-131 -0.0797 0.1694 -0.1161 0.1703 -0.0979 0.1201 i MI- 486,487 Feb,1997 K 40 1,278.2000 167.0000 1,316.5000 1 n.0000 1,297.3500 d 109.2817 MI - 486,'487 Feb,1997 St-89 -0.8027 0.9962 -0.4554 0.94S4 -0.6290 0.6S77 l

MI - 486,487 Feb,1997 Sr-90 1.8013 i 0.4825 1.4592 0.4537 1.6453 0.3312  !

MI - 510,511 Feb,1997 Co-60 0.6890 1.0200 -2.2000 4.1400 -0.7555 2.1319 MI - 510,511 Feb,1997 Cs-137 0.7830 i 2.6300 2.2400 3.2800 1.5115 2.1021 MI - 510,511 Feb,1997 I131 0.0764 i 0.2227 0.0373 0.2345 0.0568 0.1617 I MI - 531,532 Feb,1997 I-131 0.0368 i 0.1942 -0.0045 0.2095 0.0161 0.1429 MI - 531,532 Feb,1997 K-40 1,300.3000 178.0000 1,4S8.5000 156.0000 1,394.4000 118.3427 l

CW - 554,555 Feb,1997 Gr. Beta 3.6552 1.5170 2.7825 1.4922 3.2189 1.0639 I

l. CW - 554,555 Feb,1997 Gr. Beta 0.5033 1.0364 -0.2368 0.9931 0.1332 0.7177 l MI - 632,633 Feb,1997 I-131 -0.2709 i 0.2349 -0.1024 0.1676 -0.1867 0.1443 MI - 632,633 Feb,1997 K-40 1,408.0000 165.0000 1,243.1000 145.0000 1,325.5500 109.8294 MI - 723,724 Feb,1997 I-131 -0.0581 0.2376 l 0.2433 0.2658 0.0926 0.1783' l

MI - 723,724 Feb,1997 K-40 1,574.8000 218.0000 1,396.8000 162.0000 1,485.8000 135.8013 )

LW 757,758 Feb,1997 Gr. Beta 3.7439 0.9482 4.0547 0.9711 3.8993 0.6786 CW - 883, 884 Feb,1997 Gr. Beta 1.2996 i 1.2901 2.3358 1.3877 1.8177 0.9474 DW - 1030,1031 Feb,1997 Gr. Beta 2.0791 i 0.4817 2.0596 0.5098 2.0694 0.3507 DW - 1030,1031 Feb,1997 I-131 -0.1816 0.3127 -0.1217 0.3071 -0.1517 0.2192 SWU - 929,930 Feb,1997 Gr. Beta 2.4729 0.6238 2.9908 i 0.6691 2.7319 0.4574 SWU - 929, 930 Feb,1997 H-3 170.1477 84.5878 202.2735 85.9328 186.2106 60.2900 WW - 979, 980 Feb,1997 H3 102.1168 92.0531 12.4533 88.3392 57.2850 63.7918 I SW - 1370,1371 Feb,1997 H3 50.6979 i 78.8916 -8.0656 76.2734 21.3161 54.8669 ,

LW - 953,954 Mar,1997 Co-60 0.7490 i 1.7500 -1.3300 3.8800 -0.2905 2.1282 l LW - 953,954 Mar,1997 Cs-137 -0.3220 2.2800 1.5500 2.7200 0.6140 i 1.7746

! , LW - 953,954 Mar,1997 Gr. Beta 3.7343 i 1.0079 4.6558 0.9898 4.1951 0.7063

' SW - 1036,1037 Mar,1997 Gr. Deta 1.7736 0.7279 2.126S 0.7453 1.9502 0.5209 l SW - 1576,1577 Mar,1997 H-3 219.6612 84.0956 250.7943 85.3666 235.2277 i 59.9156 SW - 1576,1577 - Mar,1997 Sr-89 -0.5258 1.1183 -0.6149 i 0.9822 -0.5704 0.7442

SW - 1576,1577 Mar,1997 ' Sr-90 0.6723 i 0.3462 0.7181 0.3074 0.6952 0.2315

- MI- 1055,1056 Mar,1997 I-131 0.1081 i 0.1729 0.0400 0.1677 0.0741 0.1204 .l MI- 1055,1056 Mar,1997 K 40 1,452.9000 1 126.0000 1,530.3000 124.0000 1,491.6000 88.3912 LW - 1120,1121 Mar,1997 Gr. Beta 2.5963 1 0.6078 1.8604 0.6077 2.2283 i 0.4298 MI- 1158,1159 Mar,1997 I-131 0.0239 0.2040 0.0708 0.2015 0.0473 i 0.1434

. MI- 1158,1159 Mar,1997 K-40 1,523.5000 i 152.0000 1,418.5000 157.0000 1,471.0000 109.2623 CW - 1187,1188 Mar,1997 Gr. Beta 4.8369 i 1.9131 3.4999 1.8196 4.1684 i 1.3201 AS-2

Table A-5. In-house " duplicate" samples, j l

I Concentration in pCi/ L' l Lab  !

Sample First Second Averaged j Codes

  • Date Analysis Result Result Result

_ j CW - 1187,1188 Mar,1997 Gr. Beta 0.1481 1.5087 -0.0SS5 1.4S96 0.0296 1.0601 1

LW < 1145,1146 Mar,1997 Co-60 1.5000 3.3300 3.6600 6.9500 LW - 1145,1146 2.5800 3.8533 )

Mar,1997 Cs-137 1.6200 i 3.2500 -0.9330 4.1100 0.3435 2.6199 LW - 1145,1146 Mar,1997 Gr. Beta 4.2278 1.2135 3.5675 1.2356 3.8976 0.8659

MI - 1275,1276 Mar,1997 I-131 -0.0683 0.2309 0.3734 0.4565 I

0.1525 0.255S MI- 1275,1276 Mar,1997 K-40 1,491.1000 193.0000 1,754.0000 177.0000 1,622.5500 130.9370 WW - 1309,1310 Mar,1997 H-3 4,282.80S9 188.1304 4,034.4635 183.5207 4,15S.6362 131.40S6 SWT - 1519,1520 Mar,1997 Gr. Beta 2.5242 0.6065 2.0921 0.5S46 2.3082 0.4212 WW - 1539,1540 Mar,1997 Gr. Beta 1.2878 0.6S03 1.846S 0.7043 1.5673 0.4896 WW - 1539,1540 Mar,1997 H-3 -34.4755 72.6445 41.3706 76.1590 3.4476 52.6246 DW - 1688,16S9 Mar,1997 Gr. Beta 4.5141 t 1.3660 4.6SS6 1.26S1 4.6013 0.9319 DW - 1688,1689 Mar,1997 I-131 -0.1688 i 0.3758 0.3183 0.3363 0.074S 0.2522 SW - 2204, 2205 Mar,1997 H-3 62.0000 152.0000 112.0000 152.0000 87.0000 107.4S02 CW - 1909,1910 Mar,1997 H-3 435.8375 96.4774 430.4271 96.2750 433.1323 6S.14S3 LW - 1931,1932 Mar,19F H-3 168.9801 83.1073 137.7304 81.7913 153.3552 SS.3023 CW - 1599,1600 Mar,1997 Gr. Beta 3.4372 i l.5949 3.4464 1.5289 3.4418 1.1047

! CW - 1599,1600 Mar,1997 Gr. Beta 1.0978 0.9656 1.0340 0.952S 1.0659 0.6783 j l AP - 2572,2573 Mar,1997 Co-60 -0.0006 0.0102 -0.0002 0.0002 -0.0004 0.0051 i AP - 2572,2573 Mar,1997 Cs-137 0.000S 0.0007 0.0000 0.0005 0.0004 0.0004 l

SWU - 2045,2046 Mar,1997 Sr-89 -0.0237 0.7179 0.1072 0.6305 0.0417 0.4777 I SWU - 2045, 2046 Mar,1997 Sr-90 0.3676 0.3471 0.1910 0.2933 0.2793 0.2272 MI - 1641,1642 Apr,1997 I-131 -0.6675 i 0.3099 -0.5511 0.3244 -0.6093 0.2243 MI - 1641,1642 Apr,1997 K-40 1,556.3000 111.0000 1,393.1000 160.0000 1,474.7000 97.3666 LW - 1763,1764 Apr,1997 Gr. Beta 2.3656 0.8258 2.1732 0.8478 2.2694 0.5917

{

LW - 1763,1764 Apt,1997 H-3 97.1488 79.2640 160.3540 82.0162 128.7514 57.0295 AP - 1974,1975 Apr,1997 Sr-89 -0.0001 i 0.0006 -0.0005 0.0015 -0.0003 0.000S AP - 1974,1975 Apr,1997 Sr-90 0 0001 0.0002 0.0001 0.0004 0.0001 0.0002 AP - 1994,1995 Apt,1997 Co-60 -0.0003 t 0.0013 0.0002 0.0007 -0.0000 0.0007 i

! AP - 1994,1995 Apr,1997 Cs-134 -0.0001 0.0006 -0.0001 0.0016 -0.0001 0.0008 i l AP - 1994,1995 Apr,1997 Cs-137 -0.0002 0.0005 -0.0001 0.0005 -0.0002 0.0004 AP .1994,1995 Apr,1997 I-131(g) -0.0001 0.0002 0.0001 0.0002 0.0000 0.0001 l AP - 1994,1995 Apt,1997 K-40 0.0306 0.0192 0.0114 0.0180 0.0210 0.0132 WW - 1665,1666 Apr,1997 1-131 -0.4430 0.2674 -0.0311 0.2626 -0.2370 0.1874

{  ;

WW - 1708,1709 Apr,1997 Gr. Beta 1.2245 i 0.6161 1.2S58 0.6134 1.2551 0.4347 WW - 1785,1786 Apr,1997 Gr. Beta 2.9118 i 2.0703 0.3820 2.1095 1.6469 1 1.4779 I

WW - 1785,1786 Apr,1997 H-3 -19.0365 i 73.7753 -74.4153 71.129S -46.7259 51.2402 WW - 1785,1786 Apt,1997 Sr-89 0.6539 0.6546 -0.4951 0.5197 0.0794 0.4179 A5-3

Table A-5. In-house " duplicate" samples.

Concentration in pCi/L' Lab Sample First Second Averaged Codes

  • Date Analysis Result Result Result WW - 1785,1786 Apr,1997 Sr-90 -0.0023 i 0.2013 0.2468 0.2347 0.1223 0.1546 l WW - 1737,1738 Apr,1997 Gr. Beta 15.0355 i 1.5075 15.6924 1.6231 15.3640 1.1076 WW - 1737,1738 Apr,1997 H-3 13.8405 i 75.2790 -5.1902 74.3991 4.3251 52.9201 LW - 2848,2849 Apr,1997 Gr. Beta 2.4095 0.6377 1.7316 0.5601 2.0706 0.4244
Mi - 1845,1846 Apr,1997 Co-60 0.0309 0.0778 -1.8500 22.4000 -03096 11.2001 MI- 1845,1846 Apr,1997 Cs-134 0.1600 0.1350 0.5860 1 2.2600 0.3730 1.1320 MI - 1845,1846 Apr,1997 Cs-137 0.7580 i 1.1500 0.6290 2.6700 0.6935 1.4536 Mi - 1845,1846 Apr,1997 I-131 -0.2586 0.2297 -0.0829 0.2149 -0.1708 0.1573 MI - 1845,1846 Apr,1997 I-131(g) -0.0707 i 0.2"O -0.7200 3.2700 -0.3954 1.6417 MI - 1845,1846 Apr,1997 K-40 1,592.5000 ;2.5000 1,559.3000 i 127.0000 1,575.9000 68.7118 MI- 1845,1846 Apr,1997 Sr-89 0.2592.c 1.3259 -0.3095 0.8315 -0.0252 0.7825 MI- 1845,1846 Apr,1997 Sr-90 1.3583 0.3573 0.8755 0.2294 1.1169 0.2123 F - 2175,2176 Apr,1997 Gr. Alpha 0.0245 i 0.0359 0.0672 0.0377 0.0453 0.0260 F - 2175,2176 Apr,1997 Gr. Deta 2.3387 i 0.2713 1.7003 0.3684 2.0195 0.2288 F - 2175,2176 Apr,1997 K-40 2.5383 0.3610 2.5345 0.3640 2.5364 0.2563 F - 2175,2176 Apr,1997 Sr-89 0.0003 i 0.0053 0.0021 0.0048 0.0012 0.0036 l F - 2175,2176 Apr,1c97 Sr-90 -0.0002 i 0.0018 -0.0003 0.0016 -0.0002 0.0012 SWU - 2091, 2092- Apt,1997 Gr. Beta 3.3295 1 0.6698 2.7374 1 0.6670 3.0334 i 0.4726 SWU - 2091, 2092 Apr,1997 H-3 42.6019 76.2782 46.1034 76.4388 44.3526 53.9936 SWU - 2636,2637 Apr,1997 H-3 17.9011 i 75.4236 92.3927 78.7712 55.1469 54.5290 SL - 2432,2433 Apr,1997 K-40 1.8447 0.4400 1.6811 0.5400 1.7629 i 0.3483 WW - 2462, 2463 Apr,1997 Co-60 -0.5320 i 0.7550 0.4650 0.7810 -0.0335 0.5431 WW - 2462, 2463 Apr,1997 Cs-137 0.6250 i 3.6500 -1.4600 3.4400 -0.4175 2.5078 WW - 2462,2463 Apr,1997 H-3 19.6154 75.4335 -21.9230 73.5027 -1.1538 52.6613  !

F - 2412,2413 Apr,1997 K-40 3.0009 0.1660 3.0594 i 0.1470 3.0302 i 0.1109 LW - 2550,2551 Apr,1997 Gr. Beta 2.0074 0.8317 3.6936 0.8973 2.8505 0.6117 LW - 2550,2551 Apr,1997 K-40 102.7800 i 55.6000 96.6520 54.9000 99.7160 39.0684 SP - 2806,2807 Apr,1997 Gr. Alpha 0.0245 0.3861 0.1365 0.3720 0.0805 0.2681 j SP - 2806,2807 Apr,1997 Sr-89 -1.4194 i 6.8147 -5.6447 8.6109 -3.5321 5.4906 l 7.1752 2.9780 4.9147 1.8862 I SP - 2806. 2807 Apr,1997 Sr-90 2.6542 2.3158 I

PW - 2736,2737 Apr,1997 Co-60 0.1300 4.6800 -0.6250 t 9.8400 -0.2475 5.44S1 j PW - 2736,2737 Apr,1997 Cs-137 -0.2740 i 4.2100 1.7400 3.3400 0.7330 2.6870  !

PW - 2736,2737 Apr,1997 Gr. Deta 2.8037 i 1.5036 2.6658 1.4461 2.7348 1.0431 WW - 2712, 2713 Apt,1997 H-3 1,482.0205 1 125.6515 1,596.1107 128.75.!4 1,539.0656 89.9520 SW - 2657,2658 May,1997 Gr. Beta 13.2730 1 1.3358 13.1663 1.2719 13.2201 0.9222 S O - 2677,2678 May,1997 Cs-137 0.1078 0.1000 0.2313 0.0507 0.1697 0.0561 j S O - 2677, 2678 May,1997 Gr. Alpha 5.5187 i 3.4094 8.3190 4.0540 6.9189 2.6486 A5-4

l Table A-5. In-house " duplicate" samples.

I Concentration in pCi/ L" Lab Sample First Second Averaged ,

Codes

  • Date Analysis Result Result Result l l S O -2677,2678 May,1997 Gr. Deta 21.9926 2.7808 21.8461 3.0S06 21.9193 2.0750 S O - 2677, 2678 May,1997 Sr-89 0.0075 0.0954 -0.0008 0.0S0S 0.0034 0.0625

! S O - 2677, 2678 May,1997 Sr-90 0.0713 0.0197 0.0642 0.0164 0.0677 0.0128 MI - 2764,2765 May,1997 Co-60 0.0636 i 0.0966 -1.5300 7.2300 -0.7332 3.6153 l MI - 2764,2765 May,1997 Cs-137 5.5000 1 5.2800 1.7700 4.9900 3.6350 3.6324 MI - 2764,2765 May,1997 I-131 -0.1635 0.1612 -0.0766 0.1452 -0.1201 0.1085 l

MI - 2828, 2829 May,1997 1-131 -0.0153 0.2503 -0.0855 0.2257 -0.0504 0.1685 MI - 2828,2829 May,1997 K-40 1,786.4000 126.0000 1,897.0000 192.0000 1,841.7000 114.8260 G - 2879,2880 May,1997 Co-60 0.0044 0.1100 -0.0207 1 0.2030 -0.0081 0.1154 G - 2879,2880 May,1997 Cs-134 0.0081 0.0305 -0.0030 0.0133 0.0025 0.0106 G - 2879,2SSO May,1997 Cs 137 0.0006 0.0234 0.0013 0.0166 0.0010 0.0143 i 6.4712 0.2029 6.6206 0.1927 6.5450 0.1399 l G - 2879,2880 May,1997 Gr. Deta G - 2879,2880 May,1997 I-131(g) 0.0093 i 0.0456 0.0220 1 0.6620 0.0157 0.3318 I

G - 2879,2880 May,1997 K-40 6.2539 i 0.8340 5.7979 i 0.7160 6.0259 0.5496 S O - 2904, 2905 May,1997 Co-60 -0.0097 0.0201 -0.0021 0.0224 -0.0059 0.0150 S O - 2904, 2905 May,1997 Cs-134 0.0348 i 0.0682 0.0208 i 0.1500 0.0278 0.0S24 S O - 2904, 2905 May,1997 Cs-137 0.2709 i 0.0541 0.276S 0.0463 0.2738 e 0.0356 S O - 2904, 2905 May,1997 Gr. Beta 24.4695 1 2.3915 26.5459 2.5962 25.5077 1.7649 S O - 2904, 2905 May,1997 K-40 18.8100 i 1.0100 19.1610 t 0.8920 18.9855 0.6738 F - 2926,2927 May,1997 Co-60 0.0071 0.0082 -0.0010 0.0015 0.0031 0.0042 l F - 2926,2927 May,1997 Cs-137 -0.0047 i 0.0122 -0.0029 0.00S8 -0.003S 0.0075 SW - 3008, 3009 May,1997 H-3 101.2957 91.5729 123.2634 t 92.4471 112.2795 65.0616 MI - 3050,3051 May,1997 Sr-89 -0.1527 i 0.9022 0.0234 0.8795 -0.0646 0.6300 MI- 3050,3051 May,1997 Sr-90 0.9779 i 0.3707 0.9427 0.3596 0.9603 0.25S3 F - 3C.*0, 3071 May,1997 Co-60 -0.0093 i 0.0979 0.0094-i 0.0303 0.0000 0.0512 F - 3070,3071 May,1997 Cs-137 0.0064 0.0113 -0.0003 1 0.0078 0.0030 0.0069 G - 3090,3091 May,1997 K-40 5.0649 0.2170 4.9752 0.2830 5.0201 i 0.1783 MI 3116.3117 May,1997 1-131 -0.1346 0.1762 -0.0964 t 0.1650 -0.1155 0.1207 F - 3277,3278 May,1997 Gr. Beta 2.9487i 0.1093 3.0022 0.1035 2.9755 0.0753 F - 3277, 3278 May,1997 K-40 2.8485 0.2780 .2.4647 0.3130 2.6566 0.2093 MI - 3232, 3233 May,1997 I-131 -0.1723 i 0.2021 -0.2680 i 0.2044 -0.2202 0.1437 MI - 3232,3233 May,1997 K-40 1,550.6000 121.0000 1,517.9000 141.0000 1,534.2500 92.9005 BS - 3311,3312 May,1997 Co-60 -0.0035 0.0348 -0.0044 1 0.0031 -0.0039 0.0175 BS 3311,3312 May,1997 Cs-137 0.0676 1 0.0334 0.0677 0.0297 0.0676 0.0223 F-3484,3485 May,1997 K-40 2.4582 1 0.3320 1.8380 0.2990 2.1481 0.2234 SW - 3533,3534 May,1997 H-3 -95.4129 i 90.4309 -117.7172 89.5093 -106.5650 63.6193 WW - 3395,3396 May,1997 I-131 -0.1507 i 0.1841 -0.0473 i 0.2108 -0.0990 0.1399 u my -

I A5 -5

l Table A-5. In-house " duplicate" samples.

Concentration in pCi/ L' Lab Sample First Second Averaged Codes

  • Date Analysis Result Result Result l F - 3720,3721 May,1997 K-40 2.6063 i 0.4030 2.6623 0.3390 2.6343 0.2633 i

LW - 3464,3465 May,1997 Co-60 -0.2860 i 1.2700 -0.0583 0.0489 -0.1722 0.6355 i LW - 3464,3465 May,1997 Cs-137 2.4600 1 2.8100 1.5000 3.2400 1.9800 2.1444 LW - 3464,3465 May,1997 Gr. Beta 3.3532 0.9801 3.7723 0.9839 3.5628 i 0.6944 SW - 3883,3884 May,1997 H-3 -20.5031 i 87.7694 124.8827 93.7412 52.1898 64.2084 M! - 3513,3514 Jun,1997 I-131 -0.1592 i 0.1592 -0.1028 i 0.1714 -0.1310 0.1170 M1 - 3513,3514 lun,1997 K-40 1,560.3000 1 129.0000 1,521.9000 i l79.0000 1,541.1000 110.3200 l P - 3794,3795 Jun,1997 H-3 109.9207 i 93.1034 24.2198 89.6079 67.0702 64.6100 F - 4049,4050 Jun,1997 K-40 2.8350 0.3980 3.0237 1 0.2420 2.9294 0.2329 i

MI - 3903,3904 Jun,1997 I-131 0.1530 0.1840 -0.1290 0.1587 0.0130 0.1215 MI- 3903,3904 Jun,1997 K-40 2,020.1000 i 142.0000 1,822.5000 i 188.0000 1,921.3000 i 117.8007 VE - 3839,3840 Jun,1997 Gr. Alpha 0.2489 i 0.0857 0.1876 0.0698 0.2183 0.0553 VE - 3839,3840 Jun,1997 Gr. Beta 4.4859 1 0.4451 4.1281 1 0.4123 4.3070 0.3034 VE - 3839,3840 Jun,1997 K-40 5.4016 0.3360 4.6783 0.4282 5.0400 0.2721 F - 3928,3929 Jun,1997 Co-60 -0.0025 i 0.0121 0.0045 0.0034 0.0010 0.0063 F - 3928,3929 Jun,1997 Cs-134 0.0050 0.0115 -0.0030 0.0114 0.0010 i 0.0081 F - 3928,3929 Jun,1997 Cs-137 0.0841 1 0 4225 0.0796 0.0286 0.0818 0.0182 F - 3928,3929 Jun,1997 Gr. Beta 2.7146 0.0950 2.6357 0.0977 2.6752 0.0651 1 F - 3928,3929 Jun,1997 I-131(g) 0.0206 i 0.0449 0.0158 0.0458 0.0182 0.0321 F - 3928,3929 Jun,1997 K-40 1.8883 i 0.3970 1.4854 1 0.3780 1.6869 0.2741 SWU - 3980,3981 Jun,1997 Gr. Beta 2.1443 0.6206 2.3149 i 0.6407 2.2296 0.4460 SWU - 3980, 3981 Jun,1997 H-3 221.0233 i 89.9165 105.6271 85.0852 163.3252 61.8960 CW - 3948,3949 Jun,1997 Gr. Beta -0.4402 1.0747 -0.3764 1.1259 -0.4083 0.7782 SW - 4150. 4151 Jun,1997 H-3 30.4430 i 77.1886 56.0152 78.3895 43.2291 55.0068 MI - 4091,4092 Jun,1997 I-131 -0.0475 i 0.1439 -0.0071 0.1516 -0.0273 0.1045 SWT - 4240,4241 Jun,1997 Gr. Beta 2.1204 0.6338 2.8553 0.6330 2.4879 0.4479 SW - 5186,5187 Jun,1997 H-3 190.3311 1 89.7491 192.1730 89.8246 191.2521 63.4889 DW - 4280, 4281 Jun,1997 Gr. Alpha -0.4934 i 0.7635 -0.4930 0.7640 -0.4932 0.5401 DW - 4280, 4281 Jun,1997 Gr. Beta 2.0633 1 0.8600 2.0630 0.8700 2.0631 '0.6117 WW - 4811,4812 Jun,1997 H-3 48.4888 83.6998 50.3302 83.7808 49.4095 59.2133 l

CW - 5207,5208 Jun,1997 H-3 151.5810 88.1060 135.0114 i 87 4113 143.2962 i 62.0552 SW - 4364,4365 Jun,1997 H-3 83.4415 i 83.9269 94.4046 84.4029 88.9230 59.5138 AP - 4983,4984 Jun,1997 Co-60 -0.0002 i 0.0009 0.0001 0.0007 -0.000J 0.0006 AP - 4983,4984 Jun,1997 Cs-137 0.0003 i 0.0004 -0 0001 1 0.0007 0.0001 0.0004 AP - 5004,5005 Jun,1997 Co-60 0.0002 0.0002 0.0003 i 0.0008 0.0002 0.0004 AP - 5004,5005 Jun,1997 Cs-137 -0.0002 1 0.0004 0.0002 0.0006 -0.0000 0.0004 DW - 4484,4485 Jun,1997 Gr. Beta 2.0708 1 0.6272 1.9172 1 0.5805 1.9940 0.4273 i

l l A5-6 l

V 1 l

Table A-5. In house duplicate" sampler.

Concentration in pCi/L' Lab Sample First Second Averaged l Codes

  • Date Analysis Result Result Result DW - 4484,4485 Jun,1997 H-3 39.2579 1 83.2425 66.8612 84.4541 53.0596 59.2913 SW - 4460, 4461 Jul,1997 Gr. Beta 1.8471 0.7685 2.2801 0.7788 2.0636 0.5471 l DW - 4510,4511 Jul,1997 H-3 1.2216 i 80.7150 21.3772 81.6249 11.2994 57.3967 l AP - 4917,4918 Jul,1997 Co-60 0.0002 0.0003 0.0002 1 0 0006 0.0002 0.0003 AP - 4917,4918 Jul,1997 Cs-134 0.0002 i 0.0003 0.0002 0.0052 0.0002 0.0026 AP - 4917,4918 Jul,1997 Cs-137 0.0005 i 0.0004 0.0002 0.0004 0.0003 1 0.0003 AP - 4917,4918 Jul,1997 I-131(g) -0.0009 i 0.0017 0.0022 1 0.0762 0.0006 0.0381 l

! AP - 4917,4918 Jul,1997 K-40 0.0239 0.0081 0.0305 0.0086 0.0272 0.0059 SP - 5024,5025 Jul,1997 Gr. Alpha 0.4224 0.9602 1.7836 1.2429 1.1030 0.7853 SP - 5024,5025 Jul,1997 Sr-90 65.8931 i 7.2660 61.7118 6.1959 63.8024 i 4.7745 BS - 4573, 4574 Jul,1997 K-40 11.9570 i 0.5550 12.0610 0 5170 12.00 +. 0.3792 l

WW - 4535, 4536 Jul,1997 Co-60 -0.0955 1 0.4620 1.0800 1.5100 0.4923 0.7895 WW - 4535, 4536 Jul,1997 Cs-137 -0.7200 t 2.3500 0.1650 i 3.3100 -0.2775 2.0297 WW - 4535,4536 Jul,1997 H3 565.2121 103.8753 524.7523 102.4326 544.9822 i 72.9426 i

G - 4745 4746 Jut,1997 Co-60 -0.0147 i 0.1270 -0.0016 0.0036 -0.0082 i 0.0635 l G - 4745,4746 Jul,1997 Cs-134 0.0055 0.0386 -0.0118 0.0963 -0.0032 0.0519 l G - 4745,4746 Jul,1997 Cs-137 0.0057 0.0186 0.0132 0.0180 0.0095 0.0129 G 4745,4746 Jul,1997 Gr. Beta 5.0148 0.1659 4.7792 0.1700 4.8970 0.1188 G - 4745,4746 Jul,1997 .-131(g) 0.0040 0.0078 0.0104 0.0269 0.0072 0.0140 l

C - 4745,4746 Jul,1997 K-40 4.5596 0.5840 4.1530 i 0.6150 4.3563 0.4241 SWU - 4832,4833 Jul,1997 Gr. Beta 2.7683 i 0.6756 3.4254 0.6591 3.0968 0.4719 LW - 4782,4783 Jul,1997 Co-60 2.8200 t 20.3000 -1.9900 1 6.6500 0.4150 i 10.6807 l LW - 4782,4783 Jul,1997 Cs-137 0.6730 i 3.2000 -0.6030 2.2500 0.0350 1.9559 l LW - 4782, 4783 Jul,1997 Gr. Beta 4.0046 1.0458 3.5274 0.9990 3.7660 0.7232 MI - 4897,4898 Jul,1997 I-131 -0.0412 0.2182 0.0463 0.2335 0.0026 0.1598 l MI - 4897,4898 Jul,1997 K-40 1,531.3000 i 123.0000 1,270.5000 i 152.0000 1,400.9000 97.7663 I- CW - 5150, 5151 Jul,1997 Gr. Beta 4.7218 1.5818 4.2648 1.6666 4.4933 1.1488 l CW - 5150,5151 Jul,1997 Gr. Beta -0.2253 1.0995 0.5464 1.2464 0.1605 0.8310 l G - 5296,5297 Jul,1997 K-40 6.8000 i 0.6000 8.2000 0.8000 7.5000 0.5000 WW - 5369,5370 Jul,1997 H-3 18,013.8557 i 373.4409 18,133.8988 i 374.6263 18,073.8773 264.4820 CW - 5321,5322 Jul,1997 Gr. Beta 1.5612 t 1.4170 1.3507 1.2764 1.4560 0.9535 CW - 5321,5322 Jul,1997 Gr. Beta -0.6334 i 1.0849 0.5162 1.2191 -0.0586 0.8160 WW - 5348,5349 Jul,1997 H-3 1,763.0308 i 139.9964 1,813.1908 141.3214 1,788.1108 99.4620 M!- 5464,5465 Jul,1997 I-131 -0.2555 i 0.2878 -0.3511 0.2946 -0.3033 0.2059 MI- 5464,5465 Jul,1997 K-40 1,282.9000 143.0000 1,380.0000 124.0000 1,331.4500 94.6375 VE - 5506,5507 Jul,1997 Gr. Beta 7.2756 0.2197 7.0057 0.2090 7.1407 0.1516 VE - 5306,5507 Jul,1997 K-40 8.1566 i 0.3970 8.1817 0.4360 8.1692 :t 0.2948 A5-7

l

)

l Table A-5. In-house " duplicate" samples.

Concentration in pCi/L"

. Lab Sample First Second Averaged  ;

i Codes

  • Date Analysis Result Result Result j WW - 5848, 5849 Jul,1997 H-3 51.6431 83.4870 40.4434 82.9847 46.0433 58.8569 l l

WW - 5529, 5530 .Aug,1997 Gr. Beta 5.1545 t 2.1632 4.3564 1.9601 4.7555 1.4626 l WW - 5529,5530 Aug,1997 H-3 235.5502 i 91.5917 372.4741 97.6610 304.0122 66.9453 MI- 5606,5607 Aug,1997 I-131 -0.0759 0.3043 -0.1020 0.3423 -0.0889 0.2290 l SL - 5563,5564 Aug,1997 Cr. Beta 1.9301 0.2206 2.0961 0.2125 2.0131 0.1531 SL - 5563,5564 Aug,1997 K-40 1.1254 0.3530 1.3185 1 0.4050 1.2220 0.2686 SL - 5563,5564 Aug,1997 Sr-89 -0.0078 1 0.0216 0.0096 i 0.0196 0.0009 0.0146 l SL - 5563,5564 Aug,1997 Sr-90 0.0097 0.0059 0.0031 0.0048 0.0064 0.003S SW - 5584,5585 Aug,1997 Gr. Beta 2.9875 i 0.7744 2.0205 1.0326 2.5040 0.6454 LW - 5678,5679 Aug,1997 Co-60 0.4180 i l.2900 0.7270 1.4500 0.5725 0.9704 LW - 5678, 5679 Aug,1997 Cs-134 0.8140 1 0.6510 0.8340 0.4840 0.8240 0.4056 LW - 5678,5679 Aug,1997 Cs-137 1.1400 1.1800 0.7750 1.1900 0.9575 0.8379 LW - 5678, 5679 Aug,1997 Gr. Beta 2.6926 i 0.6727 2.4242 0.6023 2.5584 0.4515 LW - 5678,5679 Aug,1997 I-131 -0.1036 i 0.3234 -0.0921 0.3371 -0.0979 0.2336 LW - 5678,5679 Aug,1997 1-131(g) -10.1000 i 11.1000 -3.6000 i 5.8200 -6.8500 6.2666 LW - 5678,5679 Aug,1997 K-40 137.0000 i 16.5000 124.0000 i 17.3000 130.5000 1 11.9535 G - 5653,5654 Aug,1997 K-40 6.0419 0.5940 5.5554 1 0.5870 5.7987 0.4176 CW - 5759,5760 Aug,1997 Gr. Deta 4.3051 1.5501 2.0048 1.4570 3.1550 1.0637 CW - 5759,5760 Aug,1997 Gr. Beta -0.5S60i l.1030 -0.0177 t l.1407 -0.3018 0.7934 CW - 5708,5709 Aug,1997 Gr. Beta 1.7190 1.4125 1.8843 i l.4139 1.8017 1 0.9993 MI- 5891,5892 Aug,1997 1-131 0.00001. G.2400 0.1928 0.2253 0.0964 0.1646 MI- 5891, S892 Aug,1997 K-40 1,438.6000 i 131.0000 1,218.6000 i 175.0000 1,328.6000 109.3000 MI- 5926,5927 Aug,1997 I-131 -0.0311 1 0.1690 -0.1446 0.1748 -0.0879 0.1216 MI- 5926,5927 Aug,1997 K-40 1,577.8000 i 216.0000 1,429.9000 178.0000 1,503.8500 139.9464 SWU - 5972,5473 Aug,1997 H-3 274.7574 i 93.6817 157.2707 88.8812 216.0140 64.5681 CW - 6013, 6014 Aug,1997 Gr. Beta 4.~9501i 1.3048 4.5882 1.6114 4.7841 1.0367 CW - 6013, 6014 Aug,1997 Gr. Beta -0.5668 i 1.0528 -0.6145 1.1307 -0.5907 0.7725 SL - 6034,6035 Aug,1997 Co-60 0.0183 i 0.0235 0.0159 0.2550 0.0171 0.1280 SL - 6034,6035 Aug,1997 Cs-134 0.0046 0.0136 0.0015 0.0020 0.0030 0.0069 SL - 6034,6035 Aug,1997 Cs-137 0.0118 i 0.0097 0.0175 i 0.0098 0.0147 0.0069 SL - 6034,6035 Aug,1997 Gr. Beta 2.1826 i 0.1949 1.9837 0.1773 2.0'8 31 0.1317 SL - 6034,6035 Aug,1997 I-131(g) -0.0039 i 0.0134 0.0013 0.0060 -0.0013 0.0073 SL - 6034,6035 Aug,1997 K-40 1.6231 i 0.2940 1.4676 0.2750 1.5454 0.2013 CW - 6172, 6173 Aug,1997 Gr. Beta 3.2828 1.0951 3.7336 i 1.6212 3.5082 0.9782 CW - 6172, 6173 Aug,1997 Gr. Beta 1.2291 t l.3108 0.0271 1.1175 0.6281 0.861?

CW - 6080,6081 Aug,1997 Gr. Beta 2.4263 1.5665 4.0378 1.5325 3.2321 1.0957 CW - 6080,6081 Aug,1997 Gr. Beta 0.0198 i 1.1927 0.9870 1.1701 0.4836 0.8354 A5-8

l Table A-5. In-house " duplicate" samples.

Concentration in pCi/L' Lab Sample First Second Averaged Codes

  • Date Analysis Result Result Result VE - 6106, 6107 Av3,1997 Co-60 0.0021 0.0173 0.0019 0.0087 0.0020 0.0097 l VE - 6106,6107 Aug,1997 Cs-137 0.0017 i 0.0057 -0.0005 0.0072 0.0006 0.0046 VE - 6149,6150 Aug,1997 Co-60 0.0043 0.1740 0.0004 0.0012 0.0024 0.0870 VE - 6149,6150 Aug,1997 Cs-137 -0.0026 0.0056 0.0018 0.0060 -0.0004 0.0041  !

MI- 6203,6204 Aug,1997 Co-60 2.3200 1 83.8000 0.7940 1.9700 1.5570 41.9116 MI - 6203,6204 Aug,1997 Cs-137 0.5560 i 3.0200 1.2900 2.6500 0.9230 2.0089 MI - 6203, 6204 Aug,1997 I-131 -0.2456 0.3252 -0.1688 0.3245 -0.2072 0.2297 VE - 6224,6225 Aug,1997 Co-60 -0.0042 0.0160 0.0045 0.0078 0.0002 0.0089 z VE - 6224,6225 Aug,1997 Cs-137 -0.0057 0.0131 0.0071 0.0047 0.0007 0.0070 VE - 6251,6252 l

Aug,1997 Gr. Beta 3.4988 i 0.1337 3.5009 0.1338 3.4998 0.0946

{

VE - 6251,6252 Aug,1997 K-40 3.8744 0.5410 3.3980 0.6150 3.6362 0.4095 MI - 6335,6336 Aug,1997 I-131 0.0196 0.2826 0.0564 0.2698 0.0380 0.1953 MI - 6335,6336 Aug,1997 K-40 1,488.7000 i 128.0000 1,538.6000 116.0000 1,513.6500 86.3713 SL - 6982,6983 Aug,1997 Co-60 0.0869 i 0.0110 0.0888 0.0135 0.0879 0.0087 SL - 6982, 6983 Aug,1997 Cs-137 0.0826 0.0110 0.0993 0.0165 0.0909 0.0099 SL - 6982, 6983 Aug,1997 Gr. Beta -0.7733 t 0.1093 -0.6988 0.0989 -0.7361 0.0737 WW - 6312, 6313 Aug,1997 H-3 4,401.6798 i 200.9023 4,585.7685 204.3507 4,493.7241 143.2837 LW - 6560,6561 Aug,1997 Gr. Alpha 0.4838 0.3847 0.7647 0.3421 0.6242 0.2574 LW - 6560,6561 Aug,1997 Gr. Beta 1.6502 i 0.3609 1.6339 0.3320 1.6420 0.2452 LW - 6560, 6561 Aug,1997 H-3 164.1455 90.4249 131.5719 89.0337 147.8587 63.4501 -

LW - 6520, 6521 Sep,1997 Gr. Beta 1.9762 0.5715 2.3786 0.6284 2.1774 0.4247 LW - 6520, 6521 Sep,1997 H3 104.7304 87.8580 66.4144 86.1703 85.5724 61.5314 CW - 6489,6490 Sep,1997 Gr. Eeta 0.2448 i 1.3049 1.9046 i 1.3290 1.0747 0.9313 G - 6773,6774 Sep,1997 K-40 3.7979 i 0.2420 3.5568 i 0.3270 3.6774 0.2034 CW - 6796,6797 Sep,1997 Gr. Beta 3.3658 i 1.5585 5.0139 1.1808 4.1899 0.9777 j CW - 6796,6797 Sep,1997 Gr. Beta -1.1040 i l.0241 -0.7623 1.0723 -0.9332 0.7414 SWU - 7009, 7010 Sep,1997 Gr. Beta 3.2034 1 0.6793 3.2645 0.6681 3.2339 0.4764 SWU - 7009,7010 Sep,1997 H-3 165.8491 90.5715 150.5986 89.9273 158.2239 63.8164 C - 6820,6821 Sep,1997 K-40 4.8113 0.4160 4.7307 0.5360 4.7710 0.3392

]

MI - 6886,6887 Sep,1997 1-131 0.0177 0.1519 0.0180 0.1520 0.0179 0.1074 i MI - 6886,6887 Sep,1997 K-40 1,241.7000 155.0000 1,062.0000 156.0000 1,151.8500 109.9557 WW - 7031, 7032 Sep,1997 H-3 -38.0852 81.4466 -19.0426 82.3323 -28.5639 57.9054 CW - 690'i,6908 Sep,1997 Gr. Beta 3.8333 1.5682 4.5001 1.6814 4.1667 1.1496 CW - 6907, 6908 Sep,1997 Gr. Beta -0.0397 1.1726 -0.1621 1.1478 -0.1009 0.8204 F - 7221,7222 Sep,1997 K-40 3.0101 0.3970 2.6722 0.4720 2.8412 0.3084  ;

CW - 7177,7178 Sep,1997 Gi. Beta 0.5864 i 0.9867 2.3794 1.4286 1.4829 0.8681 CW - 7177,7178 Sep,1997 Gr. Beta -1.0971 i 1.0379 -0.1387 1 1.1507 -0.6179 0.7748 A5-9

Table A-5. In-house "dupliene" samples.

Concentration in pCi/ L' Lab Sample First Second Averaged Codes

  • Date Analysis Result Result Result LW - 7198,7199 Sep,1997 Gr. Deta 1.6523 0.6116 2.3619 i 0.6044 2.0071 1 0.4299 VE - 7141, 7142 Sep,1997 Cod.0 0.0012 0.0118 -0.0001 0.0004 0.0005 0.0059 VE - 7141,7142 Sep,1997 Cs-137 -0.0011 1 0.0090 0.0081 0.0103 0.0035 0.0068 SWU - 7364,7365 Sep,1997 Gr. Beta 2.4372 i 0.6226 2.7949 0.6153 2.6160 0.4377 SWU - 7364, 7365 Sep,1997 H-3 245.3799 i 94.1721 269.0627 95.1596 257.2213 66.9398 WW - 7408, 7409 Sep,1997 Co-60 0.4170 i 0.8010 2.0100 i 6.7100 1.2135 3.378S WW - 7408, 7409 Sep,1997 Cs 137 -0.2190 1.6500 0.8220 3.0600 0.3015 1.73S3 WW - 7408, 7409 Sep,1997 H-3 7,907.0011 264.0275 7,543.2790 258.5239 7,725.1400 184.7601 LW - 7765,7766 Sep,1997 Gr. Alpha 0.2614 0.4857 0.3882 0.5450 0.3248 0.3650 LW - 7765,7766 Sep,1997 Gr. Beta 3.6490 0.5140 2.7232 0.4728 3.1861 0.3492 LW - 7765, 7766 Sep,1997 H-3 3,168.6312 i 176.2295 3,030.6146 173.2010 3,099.6229 123.5470 AP - 8208,8209 Sep,1997 Co-60 0.0002 0.0004 0.0004 0.000S 0.0003 0.0005 AP - 8208,8209 Sep,1997 Cs-137 0.0003 0.0005 -0.0001 0.0006 -0.0000 0.0004 G - 7244,7245 Oct,1997 Gr. Beta 9.0000 0.3000 8.4000 0.3000 8.7000 0.2121 G - 7244,7245 Oct,1997 K-40 8.8853 i 0.7960 9.1594 0.7550 9.0224 0.5486 G - 7244,7245 Oct,1997 Sr-89 -0.0058 i 0.0181 -0.0036 0.0097 -0.0057 0.0103 G - 7244, 7245 Oct,1997 Sr-90 0.0053 0.0052 0.0017 0.0029 0.0035 0.0029 G - 7265,7266 Oct,1997 K-40 6.5763 0.5250 6.0640 0.6540 6.3202 0.4193 SW - 7313,7314 Oct,1997 Gr. Deta 24.5727 i 2.0773 21.9706 2.0623 23.2717 1.4636 SW - 7313, 7314 Oct,1997 K-40 114.6700 41.9000 90.9920 37.6000 102.8310 28.1486 G - 7432,7433 Oct,1997 Co-60 0.0073 0.0252 0.0041 0.0059 0.0057 0.0129 G - 7432,7433 Oct,1997 Cs-134 0.0057 0.0110 0.0009 0.0010 0.0033 0.0055 G - 7432,7433 Oct,1997 Cs-137 0.0863 0.0217 0.0835 0.0247 0.0849 0.0164 G - 7432,7433 Oct,1997 Gr. Beta 5.3675 0.2025 5.3318 0.2123 5.3496 0 1467 G - 7432,7433 Oct,1997 I-131(g) -0.0038 0.0069 0.0218 0.4830 0.0090 0.2415 G - 7432,7433 Oct,1907 K-40 4.4899 i 0.4020 4.9632 0.5470 4.7266 0.3394 CW - 7339,7340 Oct,1997 Gr. Beta 0.2969 1 1.2051 -0.2575 0.8630 0.0197 0.7411 AP - 7537,7538 Oct,1997 Sr-89 0.0006 i 0.0008 -0.0001 0.0008 0.0002 0.0006 AP - 7537,753S Oct,1997 Sr-90 -0.0001 0.0003 0.0001 0.0003 0.0000 0.0002 CW - 7560,7561 Oct,1997 Gr. Beta 3.7764 1.5088 3.7707 1.5155 3.7735 1.0692 CW - 7560, 7561 Oct,1997 Gr. Beta 0.4496 i 1.1864 0.3374 1.2009 0.3935 0.8440 F - 7474,7475 Oct,1997 Co-60 -0.0010 0.0016 0.0020 0.0058 0.0005 0.0030 F - 7474, 7475 Oct,1997 Cs-137 0.0071 t 0.0064 0.0001 0.0113 0.0036 0.0065 F - 7495, 7496 Oct,1997 Co-60 0.0025 i 0.0076 0.0086 0.1430 0.0055 0.0716 F - 7495,7496 Oct,1997 Cs-137 0.0078 1 0.0083 0.0044 0.0056 0.0061 0.0050 F - 7626, 7627 Oct,1997 K-40 2.2464 1 0.3120 1.5663 0.3',60 1.9064 0.2443 CW - 7669, 7670 Oct,1997 Gr. Deta .5 7005 1.8448 3.6801 1.7132 4.6903 1.2588 A5-10

l Table A-5. In-house " duplicate" samples, l

Concentration in pCi/L' Lab Sample First Second Averaged Codes

  • Date Analysis Result Result Result l CW - 7669,7670 Oct,1997 Gr. Deta -0.0304 1.1674 0.1259 1.1344 0.0478 0.8139 WW - 7648,7649 Oct,1997 Co-60 38.3320 i 4.3000 31.7400 3.3600 35.0360 2.7285 WW - 7648, 7649 Oct,1997 Cs-137 2.8800 2.3000 0.5180 1.9100 1.6990 1.4948 l WW - 7648, 7649 Oct,1997 H-3 241.3364 105.7031 265.5372 106.6226 253.4368 75.0692 l MI 7787,7788 Oct,1997 I-131 -0.0456 i 0.2490 0.0257 0.2696 0.0099 0.1835 MI - 7787, 7788 Oct,1997 K-40 1,514.0000 1 114.0000 1,684.0000 102.0000 1,599.0000 76.4853 S O - 8010, 8011 Oct,1997 Cs-137 0.3513 0.0712 0.3182 0.0693 0.3347 0.0497 S O - 8010,8011 Oct,1997 K-40 22.4300 1 1.3200 22.0830 1.2900 22.2565 0.9228 SL - 8123,8124 Oct,1997 Cs-137 0.0368 0.0335 0.0242 0.0137 0.0305 i 0.0181 SL - 8123,8124 Oct,1997 K-40 2.8000 0.5510 2.5777 0.2960 2.6889 0.3127 F - 7915,7916 Oct,1997 Cs-137 0.0072 0.0118 0.0031 0.0085 0.0052 0.0073 MI - 7968, 7969 Oct,1997 1-131 -0.1451 0.3579 -0.4853 0.3455 -0.3152 0.24S7 MI - 7968,7969 Oct,1997 K-40 1,324.1000 i 132.0000 1,313.0000 118.0000 1,318.5500 88.5268 M1 - 7968,7969 Oct,1997 Sr-90 1.2892 i 0.4152 1.2892 i 0.7200 1.2892 1 0.4156 VE - 7934, 7935 Oct,1997 Co-60 0.0071 0.1160 -0.0029 0.0139 0.0021 0.0584 l VE - 7934,7935 Oct,1997 Cs-137 0.0022 i 0.0110 -0.0041 i 0.0099 -0.0010 0.0074 SWU - 8946,8947 Oct,1997 Gr. Beta 2.9772 0.6530 2.2888 i 0.5953 2.6330 0.4418 1 1

SWU - 8946,8947 Oct,1997 H-3 187.7210 1 97.3682 125.5659 94.9331 156.6435 67.9943 CW - 8230, 8231 Oct,1997 Gr. Beta 3.6262 i 1.7126 4.9561 1.7933 4.2911 1 1.2400 CW - 8230,8231 Oct,1997 Gr. Deta 1.7276 1 0.9533 0.1316 1.1929 0.9296 0.7635 CW - 8100, 8101 Oct,1997 Gr. Beta 4.1481 i 1.6095 4.5744 1.5764 4.3612 1.1264 CW - 8100,8101 Oct,1997 G r. Seta -0.5655 0.6528 0.9791 i 1.2280 0.2068 0.7475 SS - 8501, 8502 Oct,1997 Gr. Alpha 7.9580 3.4566 6.5709 1 3.1487 7.2645 2.3379 SS - 8501, 8502 Oct,1997 Gr. Deta 19.4568 i 2.9472 17.6686 i 2.6664 18.5627 1.9872 l

SS - 8501, 8502 Oct,1997 K-40 12.4630 i 0.4450 13.4420 1 0.7910 12.9525 t 0.4538 CW - 8310, 8311 Oct,1997 Gr. Beta 2.1293 1.4423 2.1830 1.4550 2.1562 i 1.0243 CW - 8310,8311 Oct,1997 Gr. Beta 0.1798 1.1387 -0.0397 1.1504 0.0701 1 0.8093 CW - 8376,8377 Oct,1997 Gr. Deta 4.7932 2.0194 7.3047 1.3637 6.0490 1.2184 CW 8376,8377 Oct,1997 Gr. Beta 0.5653 1.8020 -0.0566 i 1.7632 0.2544 1.2606 MI - 8442,8443 Oct,1997 I131 -0.0290 1 0.2689 0.1059 i 0.2666 0.0384 0.1893 MI - 8442,8443 Oct,1997 K-40 1,591.7000 i 178.0000 1,456.0000 116.0000 1,523.8500 106.2309 SWU - 8543,8544 Oct,1997 Gr. Beta 2.2027 i 0.6193 2.1585 i 0.6134 2.1806 0.4358 SWU - 8543,8544 Oct,1997 H-3 120.4712 87.0152 174.9557 89.2606 147.7134 62.3280 WW - 8473, 8474 Oct,1997 H-3 -28.9600 i 77.6404 27.1500 i 80.2139 -0.9050 55.8174 WW - 8566,8567 Oct,1997 Co-60 0.4520 1.7400 0.3400 4.0500 0.3960 2.2040 WW - 8566,8567 Oct,1997 Cs-137 1.0300 i 2.2000 -0.7300 2.8600 0.1500 1.8041 LW - 8608,8609 Oct,1997 Gr. Beta 2.8483 1 0.6660 2.3035 0.6052 2.5759 0.4500 l

l A511 l

i

Table A-5. In-house " duplicate" samples. I l Concentration in pCi/ L' j l Lab Sample First Second Averaged 6 )

Codes Da te Analysis Result Result Result MI - 8587, 8588 Nov,1997 1131 -0.0013 1 0.1396 0.0109 0.1350 0.0048 0.0971 l

MI- 8587. 8588 Nov,1997 K-40 1,441.6000 i 160.0000 1,499.6000 176.0000 1,470.6000 118.9285 I l WW - 8654, 8655 Nov,1997 Gr. Beta 0.6704 0.5213 0.8560 0.5226 0.7632 0.3691 WW - 8654,8655 Nov,1997 H-3 131.2268 i 87.3749 87.6861 85.5477 109.4565 61.1408 CW - 8753, 8754 Nov,1997 Gr. Beta 5.4805 i 1.9992 4.3820 2.0409 4.9312 1.4285 CW - 8753,8754 Nov,1997 Gr. Beta 0.2821 1.7806 0.1129 1.7701 0.1975 1.2554 F - 9131,9132 Nov,1997 Cs-137 0.0576 i 0.0192 0.0568 0.0171 0.0572 0.0129 F - 9131,9132 Nov,1997 Gr. Beta 2.9445 0.0965 3.0473 0.0919 2.9959 0.0666 F - 9131,9132 Nov,1997 K-40 2.3452 i 0.3460 2.4680 i 0.3260 2.4066 0.2377 CW - 8854,8855 Nov,1997 Gr. Beta 5.6208 i 1.7991 3.5028 i 1.6326 4.5618 1.2147 l CW - 8854,8855 Nov,1997 Gr. Beta 0.0000 1.1731 0.6107 1.1604 0.3053 0.8250 WW - 9087, 9088 Nov,1997 H-3 20.1985 81.0438 73.4489 83.4219 46.8237 58.1535 WW - 9160, 9161 Nov,1997 Co-60 -0.9580 9.1800 -0.4340 4.2400 -0.6960 5.0559 WW - 9160, 9161 Nov,1997 Cs-137 -0.1440 1 2.3300 -0.5270 2.0700 -0.3355 i 1.5583 SWT - 9341, 9342 Nov,1997 Gr. Beta 1.4657 i 0.7780 2.7123 0.8202 2.0890 0.5652 l

l CW - 9410, 9411 Dec,1997 Gr. Beta 3.2958 1.5674 4.2062 1.5722 3.7510 1.1100 CW - 9410, 9411 Dec,1997 Gr. Beta 0.6244 1.1948 -0.6229 1.0939 0.0007 0.8099 CW - 9466,9467 Dec,1997 Gr. Beta 1.6082 1.6557 2.0375 i l.6921 1.8228 1.1837 CW - 9466,9467 Dec,1997 Gr. Beta -0.0563 1.7639 -1.1838 i l.6912 -0.6201 1.2218 WW - 9603,9604 Dec,1997 Co-60 1.7300 i 1.7600 -0.6190 0.7560 0.5555 0.9577 l WW - 9603, 9604 Dec,1997 Co-60 1.7300 1.7600 -0.0389 0.3420 0.8456 i 0.8965 WW - 9603, 9604 Dec,1997 Cs-137 0.4460 1 2.0800 0.0557 1.2900 0.2509 1.2238 LW - 9789,9790 Dec,1997 Co-60 0.1010 0.1080 0.1510 i 2.0300 0.1260 1.0164 LW - 9789,9790 Dec,1997 Cs-137 1.0000 i 2.1300 0.9130 2.0300 0.9565 1.4712 LW - 9789,9790 Dec,1997 Gr. Beta 5.6924 1.0952 4.5180 0.7757 5.1052 0.6711 l CW - 9947,9948 Dec,1997 Gr. Beta 0.9320 0.9447 1.5072 0.9762 1.2196 0.6792 AP - 10249,10250 Dec,1997 Co-60 0.0000 0.0001 0.0004 i 0.0016 0.0002 0.0008 AP - 10249,10250 Dec,1997 Cs-137 0.0005 0.0008 0.0002 1 0.0003 0.0004 0.0001

' All concentrations are reported in pCi/ liter, except solid samples, which are reported in pCi/ gram.  !

  • Lab codes are comprised of the sample media and the sample numbers. Client codes have been eliminated to protect client anonymity.

l l

I l

l AS-12 I

Table A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP),

comparison of MAPEP and Teledyne's Midwest Laboratory results for various sample media'.

Concentration6 Lab Sample Date Teledyne Results M APEP Result d

Control Code Type Collected Analysis Standard Deviation

  • 1s, N=1 Limits STW-751 WATER Sep,1995 Am-241 1.370 i 0.120 1.320 0.070 1.056 - 1.584 STW-751 WATER Sep,1995 Co-57 91.000 0.950 92.380 0.600 73.904 - 110.856 STW-751 WATER Sep,1995 Cs-137 55.000 0.500 58.770 i 0.730 47.016 - 70.524 STW-751 WATER Sep,1995 Mn-54 99.170 1.600 99.080 i 1.000 79.264 - 118.896 STW-751 WATER Sep,1995 Pu-238 1.700 0.040 1.830 0.080 1.464 - 2.196 STW-751 WATER Sep,1995 Pu-239 1.380 1 0.220 1.340 0.060 1.072 - 1.608 STW-751 WATER Sep,1995 $r-90 13.730 0.950 15.690 0.300 12.552 - 18.828

{

STW-751 WATER Sep,1995 U-234 0.630 i 0.070 0.650 0.050 0.520 - 0.780 STW-751 WATER Sep,1995 U-238 0.700 0.020 0.650 0.050 0.520 - 0.780 STSO-776 SOIL Sep,1996 Am-241 27.000 28.700 2.830 20.900 - 37.310 Standard deviation for three determinations not reported in Mixed Analyte Performance Evaluation Program Summary Report.

STSO-776 SOIL Sep,1996 Co-60 879.000 812.000 1 83.500 568.400 - 1,055.600 STSO-776 SOIL Sep,1996 Cs-137 1,716.000 1,531.000 193.420 1,071.700 - 1,990.300 STSO-776 SOIL Sep,1996 Pu-238 13.000 15.900 1.770 11.130 - 20.670 STSO-776 SOIL Sep,1996 Pu-239/240 18.000 19.700 1.960 13.790 - 25.610 STSO-776 SOIL Sep,1996 Sr-90 441.000 536.000 57.110 375,200 - 696.800 STSO-776 SOIL Sep,1996 U-234/233 59.000 63.900 7.270 44.730 - 83.070 STSO-776 SOIL Sep,1996 U-238 60.000 64.000 6.360 44.800 - 83.200

  • Results obtained by Teledyne Brown Engineering Environmental Services Midwest Laboratory as a participant in the Department of Energy's Mixed Analyte Performance Evaluation Program, )

Idaho Operations office, Idaho Falls, Idaho. i 6

All results are in Bq/kg cr Bq/L as requested by the Department of Energy.

Unless otherwise indicated, the TBEESML results are given as the mean 1 standard deviations for three determinations, d

MAPEP results are presented as the known values and expected laboratory precision (1 sigma,1 determination) and control limits as defined by the MAPEP.

)

l l

A6-1

I l

l Table A-7. Environmental Measurements Laboratory Quality Assessment Program (EML),

l comparison of EML and Teledyne's Midwest Laboratory results for various sample media'.

Concentration in Bq/L*

Lab Sample Date Control I l

Code Type Collected Analysis Teledyne Result' EML Result d Limits' I

STW-755 WATER Mar,1996 Am-241 0.800 1 0.100 0.766 0.013 0.660 - 1.560 STW-755 WATER Mar,1996 Co-60 33.600 1 1.000 32.800 0.580 0.870 - 1.170 STW-755 WATER Mar,1996 Cs-137 42.800 1 1.300 38.300 0.881 0.900 - 1.250 j STW-755 WATER Mar,1996 Fe-55 109.000 21.700 83.000 3.440 0.270 - 1 620 STW-755 WATER Mar,1996 H-3 434.000 1 34.100 251.000 11.400 0.690 - 1.910 STW-755 WATER Mar,1996 Mn-54 41.900 1 1.400 38.400 1.160 0.880 - 1.210 STW-755 WATER Mar,1996 Pu-238 0.900 0.100 0.982 0.074 0.680 - 1.330 STW-755 WATER Mar,1996 Pu-239 0.700.t 0.100 0.772 0.056 0.620 - 1.380 l STW-755 WATER Mar,1996 Sr-90 2.200 0.700 1.450 0.034 0.730 - 1.650 STW-756 WATER Mar,1996 Gr. Alpha 2,180.000 i 53.500 1,850.000 185.000 0.550 - 1.310 STW-756 WATER Mar,1996 Gr. Beta 872.000 27.000 744.000 74.000 0.750 - 1.650 STSO-757 SOIL Mar,1996 Am-241 6.230 2.880 3.690 0.454 0.520 - 2.410 STSO-757 SOIL Mar,1996 Cs-137 404.000 0.150 359.000 10.000 0.740 - 1.400 STSO-757 SOIL Mar,1996 K-40 525.000 23.300 465.000 30.000 0.700 - 1.590 STSO-757 SOIL Mar,1996 Pu-238 42.300 1.590 43.000 2.440 0.220 - 1.990 STSO-757 > SOIL Mar,1996 Pu-239 9.000 0.700 9.230 0.346 0.620 - 1.990 STSO-757 SOIL Mar,1996 Sr-90 1,200.000 32.300 1,340.000 113.000 0.580 - 2.960 STSO-757 SOIL Mar,1996 Uranium 68.200 1 2.400 71.700 4.150 0.270 - 1.480 i STVE-758 VEGETATION Mar,1996 Am-241 6.100 1.300 5.600 0.184 0.580 - 2.860 STVE-758 VEGETATION Mar,1996 Cm-244 6.000 1.200 4.440 0.202 0.400 - 1.870 STVE-758 VEGETATION Mar,1996 Co-60 65.600 4.000 59.700 i 0.963 0.640 - 1.490

! VEGETATION Mar,1996 Cs-137 1,100.000 12.600 STVE-758 944.000 16.200 0.750 - 1.480 STVE-758 VEGETATION Mar,1996 K-40 1,190.000 61.600 1,030.000 33.000 0.450 - 1.510 STVE-758 VEGETATION Mar,1996 Pu-239 9.200i l.300 9.820 1.220 0.600 - 1.980 STVE-758 VEGETATION Mar,1996 Sr-90 1,210.000 32.200 1,300.000 52.400 0.500 - 1.370 STAF-759 AIR FILTER Mar,1996 Am-241 0.270 0.040 0.189 0.007 0.620 - 1.930 STAF-759 AIR FILTER Mar,1996 Ce-144 23.200 1.020 33.300 3.300 0.610 - 1.310 STAF-759 AIR FILTER Mar,1996 Co-57 6.050 i 0.130 8.900 0.900 0.630 - 1.290 STAF-759 AIR FILTER Mar,1996 Co-60 26.500 0.430 29.500 i 2.900 0.740 - 1.250 STAF-759 AIR FILTER Mar,1996 Cs-134 12.900 i 0.280 14.700 1.460 0.700 - 1.210 STAF-759 AIR FILTER Mar,1996 Cs-137 6.200 0.900 6.640 0.700 0.720 - 1.320 l STAF-759 AIR FILTER Mar,1996 Mn-54 3.270 i 0.350 3.440 0.380 0.760 - 1.330 STAF-759 AIR FILTER Mar,1996 Pu-238 0.080 i 0.020 0.096 0.002 0.610 - 1.550 STAF-759 AIR FILTER Mar,1996 Pu-239 0.090 i 0.020 0.093 i 0.003 0.670 - 1.580 STAF-759 AIR FILTER Mar,1996 Ru-106 10.200 !.850 11.600 1.440 0.540 - 1.590 STAF-759 AIR FILTER Mar,1996 Sb-125 10.100 0.750 9.780 1.030 0.350 - 1.400 STAF-759 AIR FILTER Mar,1996 Sr-90 1.070 0.230 1.060 0.037 0.620 - 2.260 STAF-759 AIR FILTER Mar,1996 Uranium 0.118 0.020 0.107 1 0.003 0.790 - 2.880 A7-1 l

\ _ _ _ _ _ - _ _ _ _ _ _ -

l Table A-7. Environmental Measurements Laboratory Quality Assessment Program (EML),

, comparison of EML and Teledyne's Midwest Laboratory results for various sample  ;

media'.

j l

Concentration in Bq/ L" l l 1 l Lab Sample Date Control Type Code Collected Analysis Teledyne Result' EML Result d Limits' i l

STAF-760 AIR FILTER Mar,1996 Gr. Alpha 2.210 i 0.050 1.620 0.150 0.820 - 1.580 STAF-760 AIR FILTER Mar,1996 Gr. Beta 1.950 0.040 1.770 0.150 0.750 - 1.940 STW-770 WATER Sep,1996 Am-241 1.300 0.200 1.080 0.040 0.640 - 1.730 STW-770 WATER Sep,1996 Co-60 65.000 2.210 61.100 0.730 0.920 - 1.180 STW-770 WATER Sep,1996 Cs-137 96.100 3.010 89.500 1.360 0.900 - 1.280 STW-770 WATER Sep,1996 Gr. Alpha 993.000 1 12.200 1,210.000 i 121.000 0.500 - 1.290 STW-770 WATER Sep,1996 Gr. Beta 579.000 8.070 540.000 54.000 0.600 - 1.610 STW-770 WATER Sep,1996 H-3 488.000 34.600 587.000 58.000 0.650 - 1.910 STW-770 WATER Sep,1996 Mn-54 65.000 2.960 60.500 0.550 0.870 - 1.220 STW-770 WATER Sep,1996 Pu-238 1.320 i 0.333 L910 0.070 0.740 - 1.270 An investigation was conducted. No errors in calculations or transcription were noted. The analysis was repeated in duplicate under the observation of the Technical Lead. No discrepancies were noted in the performance of the procedure. The result of the reanalysis was 2.14 0.11 Bq/L. No further action is planned STW-770 WATER Sep,1996 Pu-239 0.698 i 0.247 0.840 0.030 0.780 - 1.420 STW 770 WATER Sep,1996 Sr-90 3.600 i 0.700 2.710 0.240 0.720 - 1.660 STW-770 WATER Sep,1996 U-234 0.517 0.196 0.480 0.040 0.770 - 1.530 STW-770 WATER Sep,1996 U-238 0.416 1 0.118 0.480 0.370 0.770 - 1.350 STSO-771 SOIL Sep,1996 Am-241 15.600 3.830 13.500 0.510 0.520 - 2.650 STSO-771 SOIL Sep,1996 Co-60 4.030 2.500 2.920 0.210 0.500 - 1.500 STSO-771 SOIL Sep,1996 Cs-137 1,'/50.000 24.400 1,550.000 22.200 0.800 - 1.340 STSO-771 SOIL Sep,1996 K-40 369.000 i S9.500 300.000 25.000 0.730 - 1.670 STSO-771 SOIL Sep,1996 Pu-238 0.770 0.360 1.130

  • 0.240 0.400 - 1.900 STSO-771 SOIL Sep,1996 Pu-239 24.000 1.940 21.800 1.080 0.660 - 1.933 STSO-771 SOIL Sep,1996 Sr-90 63.600 1 3.950 69.900 5.100 0.460 - 2.840 STSO-771 SOIL Sep,1996 U-234 37.200 3.750 39.200 2.440 0.380 - 1.260 STSO-771 SOIL Sep,1996 U-238 40.800 3.980 41.600 0.610 0.350 - 1.550 STVE-772 VEGETATION Sep,1996 Am-241 1.530 0.884 1.230 0.410 0.680 - 2.780 STVE-772 VEGETATION Sep,1996 Cm-244 0.612 i 0.495 0.830 0.120 0.490 - 1.690 STVE-772 VEGETATION Sep,1996 Co-60 14.000 4.420 10.900 i 0.710 0.620 - 1.420 STVE-772 VEGETATION Sep,1996 Cs-137 219.000 i 10.100 190.000 6.6S0 0.810 - 1.450 STVE-772 VEGETATION Sep,1996 K-40 1,160.000 99.400 992.000 29.000 0.790 - 1.500 STVE-772 VEGETATION Sep,1996 Sr-90 1,420.000 35.100 1,390.000 12.000 0.480 - 1.290 STAP-773 AIR FILTER Sep,1996 Co-57 11.800 i 0.296 14.800 0.814 0.620 - 1.220 l STAP-773 AIR FILTER Sep,1996 Co-60 9.230 0.402 8.640 0.431 0.740 - 1.240 j STAP-773 AIR FILTER Sep,1996 Cs-134 9.620 0.376 10.800 i 0.392 0.720 - 1.210 STAP-773 AlR FILTER Sep,1996 Cs-137 8.720 i 0.403 8.520 1 0.366 0.720 - 1.320 STAP-773 AIR FILTER Sep,1996 Gr. Alpha 0.731 0.037 1.150 0.110 0.830 - 1.550 An investigation was conducted and a transcription error while calculating the result was discovered. The recalculated value is 1.1510.01Bq/ filter. No further action is planned.

A7-2

Table A-7. Environmental Measurements Laboratory Quality Assessment Program (EML),

comparison of EML and Teledyne's Midwest Laboratory results for various sample media'.

6 Concentration in Bq/ L Lab Sample Date Control l Code Type Collected Analysis EML Result d Limits' '

Teledyne Result' STAP-773 AIR FILTER Sep,1996 Gr. Beta 0.540 0.037 0.500 0.050 0.730 - 1.840 STAP-773 AIR FILTER Sep,1996 Mn-M 7.060 0.472 6.350 0.270 0.750 - 1.270 STAP-773 AIR FILTER Sep,1996 Ru-106 11.500 3.190 10.800 1.140 0.580 - 1.300 STAP-773 AIR FILTER Sep,1996 Sb-125 12.400 0.965 10.800 0.540 0.600 - 1.390 STW-788 v/ATER Mar,1997 Am-241 0.840 0.220 0.837 0.028 0.640 - 1.730 STW-788 WATER Mar,1997 Co-60 96.000 3.500 90.850 1.150 0.920 - 1.180 STW-788 WATER Mar,1997 Cs-137 77.000 t 3.500 69.780 1.230 0.900 - 1.280 STW-788 WATER Mar,1997 Fe-55 175.500 25.400 235.000 20.000 0.310 - 1.540 STW-788 WA'I ER Mar,1997 Gr. Alpha 1,042.600 i 36.800 1,130.000 10.000 0.500 - 1.290 STW-788 WATER Mar,1997 Gr. Beta 591.400 23.300 744.000 10.000 0.600 - 1.640 STW-788 WATER Mar,1997 H-3 272.000 29.700 250.300 4.200 0.650 - 1.910 STW-788 WATER Mar,1997 Mn-54 23.700 3.400 20.850 0.310 0.870 - 1.220 STW-788 WATER Mar,1997 Pu-238 1.400 0.200 1.291 0.063 0.740 - 1.270 STW-788 WATER Mar,1997 Pu-239 0.900 0.100 0.850 0.050 0.780 - 1.420 l

STW-788 WATER Mar,1997 Sr-90 25.500 1.700 23.200 1.350 0.720 - 1.660 STW-788 WATER Mar,1997 U 1.500 i 0.200 1.105 0.050 0.350 - 1.420 STSO-790 SOIL Mar,1997 Am-241 6.740 3.730 5.680 0.500 0.520 - 2.650 STSO-790 SOlL Mar,1997 Co-60 2.010 1.170 1.060 1 0.120 0.500 - 1.500 The sample size was too small for an accurate measurement. The activity error overlap the known value.

Sr$0-790 SOIL Mar,1997 Cs-137 918.640 i 8.400 825.500 1 14.100 0.800 - 1.340 STSO-790 SOIL Mar,1997 K-40 359.140 32.100 334.250 7.140 0.730 - 1.670 STSO-790 SOIL Mar,1997 Pu-238 0.300 0.200 0.530 0.110 0.400 - 1.900 STSO-790 SOIL Mar,1997 Pu-239 132.420 5.170 134.930 17.100 0.660 - 1.930 STSO-790 SOIL Mar,1997 Sr-90 38.830 1 5.770 40.310 0.420 0.460 - 2.840 STSO-790 SOIL Mar,1997 U 79.260 i 3.800 81.270 i 4.830 0.270 - 1.360 STVE-791 VEGETATION Mar,1997 Am-241 1.673 0.688 1.183 0.113 0.680 - 2.780 STVE-791 VEGETATION Mar,1997 Cm-244 0.688 0.468 0.900 0.050 0.490 - 1.690 J

STVE-791 VEGETATION Mar,1997 Co-60 16.914 3.580 12.500 0.320 0.620 - 1.420 STVE-791 VEGETATION Mar,1997 Cs-137 216.667 i 9.383 189.250 7.270 0.810 - 1.450 STVE-791 VEGETATION Mar,1997 Pu-239 1.771 0.817 1.942 0.222 0.650 - 1.950 STVE-791 VEGETATION Mar,1997 Sr-90 361.130 19.715 361.000 43.300 0.480 - 1.290 STAP-792 AIR FILTER Mar,1997 Co-57 9.528 0.230 10.810 1.000 0.620 - 1.220 i STAP-792 AIR FILTER Mar,1997 Co-60 5.325 0.266 5.010 0.300 0.740 - 1.240

! STAP-792 AIR FILTER Mar,1997 Cs-134 10.767 i 0.337 10.880 i 1.000 0.720 - 1.210 l STAP-792 AIR FILTER Mar,1997 Cs-137 9.116 0.404 8.700 0.800 0.720 - 1.320 STAP-792 AIR FILTER Mar,1997 Gr. Alpha 1.199 0.045 0.960 0.050 0.830 - 1.550 STAP-792 AIR FILTER Mar,1997 Gr. Beta 0.608 0.024 0.450 0.030 0.730 - 1.840 STAP-792 AlR FILTER Mar,1997 Mn-M 8.494 0.429 7.620 0.600 0.750 - 1.270 A7-3 N____________________________._____

7 Table A-7. Environmental Measurements Laboratory Quality Assessment Program (EML),

comparison of EML and Teledyne's Midwest Laboratory results for various sample media'.

Concentration in Bq/ L" Lab Sample Date Control d

Code Type Collected Analysis Teledyne Result

  • EML Result IJ mit s' STAP-792 Ant FILTER Mar,1997 Pu-238 0.022 0.016 0.100 i 0.006 0.620 - 1.460 The cause of the deviation for the transuranic analysis (Pu-238, 2M, U) is unknown. A dilution error is suspected.The analysis is being repeated. .

STAP-792 AIR FILTER Mar,1997 Pu-239 0.031 0.010 0.119 0.006 0.500 - 1.500 STAP-792 AIR FILTER Mar,1997 Sb-125 14.118 1.099 12.330 1.000 0.600 - 1.390 l STAP-792 AlR FILTER Mar,1997 Sr-90 1.291 1 0.275 1.450 0.149 0.660 - 2.650 l STAP-792 AIR FILTER Mar,1997 U 0.150 0.020 0.211 0.008 0.808 - 3.360 l STW-805 WATER Sep,1997 Co-60 23.630 1.450 23.300 1.200 0.920 - 1.180 STW-805 WATER Sep,1997 Cs-134 63.500 2.600 66.000 2.600 0.500 - 1.500 STW-805 WATER Sep,1997 Cs-137 34.880 2.430 34.300 1.700 0.900 - 1.280 STW-805 WATER Sep,1997 Fe-55 101.730 33.530 115.000 10.000 0.310 1.540 STW-805 WATER Sep,1997 Gr. Alpha 597.000 12.000 557.000 60.000 0.500 - 1.290 l STW-805 WATER Sep,1997 Gr. Beta 985.000 i 13.000 712.000 70.000 0.600 - 1.640

( STW-805 WATER Sep,1997 H-3 227.600 i l.800 115.000 6.000 0.650 - 1.910 i The sample was acidic, causing a breakdown of resin in the tritium column. The sample was neutralized to l pH 7 and reanalyzed. Results of reanalysis: 116.2 3.6 Bq/L.

l STW-805 WATER Sep,1997 Mn-54 38.480 3.230 37.800 1.900 0.870 - 1.220 l STW-805 WATER Sep,1997 Sr-90 3.460 i 0.690 2.940 0.180 0.720 - 1.660 l STVE-806 VEGETATION Sep,1997 Co-60 32.330 5.560 32.400 1.600 0.620 - 1.420 STVE-806 VEGETATION Sep,1997 Cs-137 627.330 z 16.670 624.000 31.000 0.810 - 1.450 j S fVE-806 VEGETATION Sep,1997 K-40 1,091.670 95.180 1,130.000 70.000 0.790 - 1.500 l

STVE-306 VEGETATION Sep,1997 Sr-90 1,335.000 32.000 1,434.000 75.000 0.4S0 - 1.290 STSO-807 SOIL Sep,1997 Cs-137 1,239.440 22A60 810.000 i 40.000 0.800 - 1.340 l

The sample size was not standard. The sample was reanalyzed using a different geometry. Results of reanalysis: Cs-137 - 813.li9.0 Bq/kg; K 275.9134.6 Bq/kg.

STSO-807 SOIL Sep,1997 K-40 478.000 29.000 315.000 i 70.020 0.730 - 1.670 STSO-807 SOIL Sep,1997 Pu-239 10.800 0.400 10.160 0.370 0.660 - 1.930 STSO-807 SOIL Sep,1997 Sr-90 31.480 1 0.560 34.750 1.000 0.460 - 2.840 l STSO-807 SOIL Sep,1997 13 57.000 1 1.100 72.900 0.850 0.270 - 1.360 l STAP-808 AIR FILTER Sep,1997 Gr. Alpha 1.820 0.080 1.490 0.090 0.830 - 1.550 l STAP-808 AIR FILTER Sep,1997 Gr. Beta 3.250 1 0.080 3.000 0.140 0.730 - 1.840 l

STAP-808 AIR FILTER Sep,1997 Pu-238 0.230 0.100 0.210 0.007 0.620' 1.460 STAP-808 AIR FILTER Sep,1997 U 0.130 0.1t,0 0.110 0.004 0.800 - 3.360 STAP-809 AIR FILTER Sep,1997 Cc-144 16.250 1.670 19.120 0.700 0.500 - 1.500 STAP-809 AIR FILTER Sep,1997 Co-57 10.570 0.270 12.640 1 0.430 0.620 - 1.220 STAP-809 AIR FILTER Sep,19')7 Co-60 9.820 0.270 10.730 10.900 0.740 - 1.240 STAP-809 AIR FILTER Sep,1997 Cs-134 24.700 0.490 28.170 0.730 0.720 - 1.210 STAP-809 AlR FILTER Sep,1997 Cs-137 7.240 i 0.370 7.310 i 0.250 0.720 - 1.320 STAP-809 AIR FILTER Sep,1997 Mn-S4 6.800 i 0.430 6.720 0.270 0.750 - 1.270 A7-4

\

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{

, Table A-7. Environmental Measurements Laboratory Quality Assessment Program (EML), '

comparison of EML and Teledyne's Midwest Laboratory results for various sample media'.

Concentration in Bq/L" Lab Sample Date Control Code Type Collected Analysis Teledyne Result

  • EML Result d Limits' STAP-809 AIR FILTER Sep,1997 Sb-125 17.980 1.270 16.120 0.790 0.600 - 1.390 STAP-809 A1R FILTER Sep,1997 Sr-90 2.830 0.370 2.760 0.100 0.660 - 2.650
  • The Environmental Measurements Laboratory provides the following nuclear species : Air Filters, Soil, Tissue, Vegetation and Water. Teledyne does not participate in the Tissue program.

6 l Results are reported in Bq/L with the following exceptions: Air Filter results are reported in Bq/ Filter, Soil results are reported in Bq/Kg, Vegetation results are reported in Bq/Kg. ,

  • Teledyne results are reported as the mean of three determinations standard deviation.

d The EML result listed is the mean of replicate determinations for each nuclide the standard error of the mean.

l l ' The controllimits are reported by EML as the ratio of Reported Value / EML Value and are established from I percentiles of historic data distributions (19821992). The evaluation of this historic data and the development of the control limits is presented in DOE report EML-564.

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A7-5 f

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APPENDIX B DATA REPORTING CONVENTIONS i

1 1

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l B-1 I l l

t i

I Data Reporting Conventions I

1.0. All activities except gross alpha and gross beta are decay corrected to collection time or i the end of the collection period.

2.0. ,c'ngle Measurements l

l Each single measurement is reported as follows:

xis l

where x = value of the measurement; s = 2a counting uncertainty (corresponding to the 95% confidence l level).

1 In cases where the activity is found to be below the lower limit of detection L it is reported as

<L where L = the lower limit of detection based on 4.66a uncertainty for a l background sample.

]

3.0. Dunlicate analyses 3.1 Individual results: x1 st  ;

x2 s2 Reported result: xis j where x = (1/2)(x1 + x2) 2 s = (1/2) s + s$

3.2. Individual results: <L1

<L2 Reported result: <L ,

where L = lower of L1and L2 3.3. Individual results: x s l

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

<L othenvise B. 2 l

l I

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 i and standard deviation s of a set of n numbers x3, x2 . xnare defined as follows:

x=fEx l 3 EJx-s)2 s _~

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

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

l 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 l retained figures are kept unchanged. As an example,11.443 is rounded off to 11.44.

4.5.2. If the figure following those to be retained is equal to or greater than 5, the figure is dropped and the last retained figure is raised by 1. As an example,11.445 is rounded off to 11.45.

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l APPENDIX C Maximum Permissible Concentrations 1

of Radioactivity in Air and Water Above Background in Unrestricted Areas f

l l

l C-1

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l Table C-1. Maximum permissible concentrations of radioactivity in air and water above l natural background in unrestricted areasa, j I

Air Water Gross alpha 3 pCi/m 3 Strontium-89 3,000 pCi/L Gross beta 100 pCi/m3 Strontium-90 300 pCi/L Jodine-131b 0.14 pCi/m 3 Cesium-137 20,000 pCi/L Barium-140 20,000 pCi/L

~

I Iodine-131 300 pCi/L Potassium-40C 3,000 pCi/L Gross alpha 30 pCi/L Gross beta 100 pCi/L Tritium 3 x 106 pCi/L a Taken from Table II of Appendix B to Code of Federal Regulations Title 10, Part 20.1-20.601, and appropriate footnotes. Concentrations may be averaged over a period not greater than one year. ,

b From 10 CFR 20.1-20.601 but adjusted by a factor of 700 to reduce the dose resulting from I the air-grass-cow-milk-child pathway.

c A natural radionuclides.

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