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Radiation Environ Monitoring Program 1989
	ML113190497
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Site:	Monticello
Issue date:	12/31/1989
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'WTELEDYNE ISOTOPES MIDWEST LABORATORY 700 LANDWEHR ROAD NORTHBROOK, ILLINOIS 60062-2310 (708) 564-0700 FAX (708) 564-4517 NORTHERN STATES POWER COMPANY MINNEAPOLIS, MINNESOTA MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO.

50-263 LICENSE NO. DPR-22 ANNUAL REPORT TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION Radiation Environmental Monitoring Program January 1, 1989 to December 31, 1989 Prepared Under Contract by TELEDYNE ISOTOPES MIDWEST LABORATORY Project No. 8010 Approved by:

. G. Huebner General Manager 28 February 1990 PDR ADOCK 05000263 R

PDC C(\\

PREFACE The staff of Teledyne Isotopes Midwest Laboratory was responsible for the acquisition of the data presented in this report.

Samples were collected by members of the staff of the Environmental and Regulatory Activities Department from January 1 to July 16, and then by the contractor Interpoll Laboratories Inc.

from July 17 to December 31.

ii 9

I TABLE OF CONTENTS No.

Preface List of Tables..

INTRODUCTION.

SUMMARY

RADIATION ENVIRONMENTAL MONITORING PROGRAM (REMP) 3.1 Program Design and Data Interpretation 3.2 Program Description.

3.3 Program Execution.

3.4 Laboratory Procedures...........

3.5 Program Modifications......

3.6 Land Use Census........

RESULTS AND DISCUSSION.

4.1 Atmospheric Nuclear Detonations and Nuclear Accidents.

4.2 Program Findings....

TABLES...

REFERENCES CITED........

APPENDICES A

Interlaboratory Comparison Program Results.....

B Data Reporting Conventions...

C Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Area......

11i 1.0 2.0 3.0 4.0 5.0 6.0 1

2 3

3 4

5 6

6 7

8 8

8 12 24 A-1 B-1 C-1

LIST OF TABLES No.

Title 5.1 Sample Collection and Analysis Program, 1989........

5.2 Sampling Locations...........

5.3 Missed Collections and Analyses, 1989.

5.4 Environmental Radiological Monitoring Program Summary In addition, the following tables are in the Appendices:

Appendix A A-1 Interlaboratory Comparison Program Results, 1986-1989.

A-2 Interlaboratory Comparison Program Results, (TLDs).

A-3 In-house Spiked Samples A-4 In-house "Blank" Samples.

Attachment B:

Acceptance Criteria for Spiked Samples Addendum to Appendix A:

Explanation of the Results Outside of Control Limits Page 13 15 17 18 A-3 A-16 A-20 A-26 A-31 A-32 Appendix C C-1 Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas..........

C-2 iv

1.0 INTRODUCTION

This report summarizes and interprets results of the Radiation Environmental Monitoring Program (REMP) conducted by Teledyne Isotopes Midwest Laboratory at the Monticello Nuclear Generating Plant, Monticello, Minnesota, during the period January -

December, 1989.

This Program monitors. the levels of radio activity in the air, terrestrial, and aquatic environments in order to assess the impact of the Plant on its surroundings.

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

These data are included in a reference document (Teledyne Isotopes Midwest Laboratory, 1989) available at Northern States Power Company, Nuclear Generation Department.

Monticello Nuclear Generating Plant is a 545 MWe boiling water reactor located on the Mississippi River in Wright County, Minnesota, and operated by Northern States Power Company.

Initial criticality was achieved on 10 December 1970.

Full power was achieved on 5 March 1971 and commercial operation began on 30 June 1971.

1

2.0

SUMMARY

The Radiation Environmental Monitoring Program (REMP) required by the U.S.

Nuclear Regulatory Commission (NRC)

Technical Specifications for the Monticello Nuclear Generating Plant is described.

Results for 1989 are summarized and discussed.

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

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

2

3.0. RADIATION ENVIRONMENTAL MONITORING PROGRAM (REMP) 3.1 Program Design and Data Interpretation The purpose of the Radiation Environmental Monitoring -Program (REMP) at the Monticello Nuclear Generating Plant is to. assess the -impact of the Plant on its environment.

For this purpose, samples are collected from the air, terrestrial, and aquatic environments and analyzed for radio

-active content.

In addition, ambient gamma radiation levels are monitored by thermoluminescent dosimeters (TLDs).

Sources of environmental radiation include the following:

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

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

A major interpretive aid in assessment of these effects is the design of the monitoring program at the Monticello Plant which is based on the indicator-control concept.

Most types of samples are collected both at indicator locations (nearby, downwind, or downstream) and at control locations (distant,

upwind, or upstream).

A plant effect would be indicated if the radiation level at an indicator location was signifi cantly larger than that at the control location.

The difference would have to be greater than could be accounted for by typical fluctuations in radiation levels arising from other sources.

An additional interpretive technique involves analyses for specific radionuclides present in environmental samples collected from the Plant site.

The Plant's monitoring program includes analyses for tritium and iodine-131.

Most samples are also analyzed for gamma-emitting

"i-sotopes,-,with -results for the.-followi ng groups. quanti.f.ied.:_

zirconium-95, cesium-137, cerium-144, beryllium-7, and potassium-40.

The first three gamma-emitting' isotopes were selected as radiological impact indicators 3

because of the different characteristic proportions in which they appear in the fission product mix produced by a nuclear reactor and that pro duced by a nuclear detonation.

Each of the three isotopes is produced in

-'roughty..equivalent, amounts by a reactor.:

.each. cons.titutes,.about 10% of the total activity of fission products 10 days after reactor shutdown.

On the other hand, 10 days after a nuclear explosion, the contributions of zirconium-95, cerium-144, and cesium-137 to the activity of the resulting debris are in the approximate ratio 4:1:0.03 (Eisenbud, 1963).

Beryllium-7 is of cosmogenic origin and potassium-40 is a naturally

-occurring isotope.

They were chosen as calibration monitors and should not be considered as radiological impact indicators.

The other group -quantified consists of niobium-95,ruthenium-103 and

-106, cesium-134, barium-lanthanum-140, and cerium-141.

These isotopes are released in small quantities by nuclear power plants, but to date their major source of injection into the general environment has been atmospheric nuclear testing.

Nuclides of the final group, manganese-54, iron-59, cobalt-58 and -60, and zinc-65, are activation products and arise from activation of corrosion products.

They are typical components of nuclear power plant's effluents, but are not produced in significant quantities by nuclear detonations.

Other means of distinguishing sources of environmental radiation can be employed in interpreting the data.

Current radiation levels can be compared with previous levels, including those measured before the plant became operational..

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

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

3.2 Program Description The sampling and analysis schedule for the Radiation Environmental Monitoring Program (REMP) at the Monticello Plant is summarized in Table 5.1 and briefly reviewed below.

Table 5.2 defines the sampling location codes used in Table 5.1 and specifies for each location its type (indi cator or control) and its distance, direction, and sector relative to the reactor site.

To assure that sampling is carried out in a reproducible manner, detailed sampling procedures have been prescribed (Teledyne Isotopes Midwest Laboratotry, 1987).

To monitor the air environment, airborne particulates are collected on membrane filters by continuous pumping at five locations.

- Also, airborne iodine is collected by continuous pumping through charcoal filters at all of these locations.

Filters are changed and counted weekly.

Particulate filters are analyzed for gross beta activity and charcoal filters for iodine-131.

Quarterly composites -of particulate filters from each location are gamma-scanned on a HP Ge or Ge(Li) detector.

One of 4

the five locations is a control (M-1),

and four are indicators (M-2, M-3, M-4, M-5).

One of the indicators is located in the geographical sector expected to be most susceptible to any atmospheric emissions from the Plant (-highest'D/Q sector).

As a "Lessons Learned" commitment, ambient gamma radiation is monitored at thirty-seven (37) locations using CaSo4:Dy dosimeter with four sensi tive areas at each location: fourteen (14) in an inner ring in the general area of the site boundary, sixteen (16) in the outer ring within 4-5 mi radius, six (6) at special interest locations. and one control location, 11.1 mi distant from the plant.

They are replaced and measured quarterly.

Also, a complete emergency set of TLDs for all locations is placed in the field -at-the same'time-as regular sets.

The emergency -set is returned to TIML quarterly for annealing and repackaging.

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

The milk is collected biweekly during the growing season (June -

September).

All samples are analyzed for iodine-131 and gamma

. emitting isotopes.

Leafy green vegetables (cabbage) are collected annually from the highest D/Q garden and a control location (M-10) and analyzed for iodine-131.

Corn and potatoes are collected annually only if the plant discharges radioactive effluent into the river.

Analysis is for gamma-emitting isotopes.

The terrestrial environment is also monitored by collection of well -water from four locations on a quarterly basis.

All samples are analyzed for tritium and gamma-emitting isotopes.

River water is collected weekly at two locations, one upstream of the Plant and one downstream.

Monthly composites are analyzed for gamma emitting isotopes. Quarterly composites are analyzed for tritium.

Drinking water is collected weekly from the City of Minneapolis water s'upply, which is taken from the Mississippi River downstream of the Plant.

Monthly composites are analyzed for gross beta, iodine-131, and gamma-emitting isotopes.

Quarterly composites are analyzed for tritium.

The aquatic environment is also monitored by semi-annual upstream and downstream collections of fish, algae or aquatic insects, and bottom sediments.

Shoreline sediment is collected semi-annually from one location. All samples are analyzed for gamma-emitting isotopes.

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

5

(1)

There were no milk data for Location M-24 for collection date 10-11-89 because milk was not available, farm went out of business.

(2) There were no milk data for Location M-24 for collection dates 11-08-89 and 12-07-89 because

,Holthaus Dairy went out of business.

-Deviations from the -program are summarized in Table 5.3.

The responsibi lities of collecting and shipping samples were transferred to Nuclear Radiological Services (NRS) effective January 1.,

1990.

An additional person has been added to NRS since March 1, 1990.

Additional effort will be made to collect any missed milk sample if milk will become available shortly; damaged or missed TLO holders will be investigated, replaced, or relocated which are similar to the actions that have been taken in the past.

3.4 Laboratory Procedures The iodine-131 analyses in milk and drinking water were made using a sensitive.radiochemical procedure which involves separation of the iodine, using an ion-exchange method and solvent extraction and finally beta counting.

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

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

Tritium was determined by a liquid scintillation technique.

Analytical procedures used by the Teledyne Isotopes Midwest Laboratory are specified in detail elsewhere (Teledyne Isotopes Midwest Laboratory, 1985).

Procedures are based on those prescribed by the National Center for Radiological Health of the U.S.

Public Health Service (U.S.

Public Health Service, 1967) and by the Health and Safety Laboratory of the U.S.

Atomic Energy Commission (U.S. Atomic Energy Commission, 1972).

Teledyne Isotopes Midwest Laboratory has a comprehensive quality control/

quality assurance program designed to assure the reliability of data obtained. Details of TIML's QA Program are presented elsewhere (Teledyne Isotopes Midwest Laboratory, 1990).

The TIML QA Program includes parti cipation in Interlaboratory Comparison (crosscheck) Programs.

Results obtained in crosscheck programs are presented in Appendix A.

3.5 Program Modifications During the growing season, milk producers were monitored to determine when the dai'ry 'animals were on.pasture.or fresh, cut.- feed.

The frequency of milk samples was increased to semimonthly at four indicator locations (Peterson,

Hoglund, Witschen, and Holthaus),

plus the control location (Kirchenbauer), at various times during the period because animals were on pasture or fresh cut feed.

6

3.6 Land Use Census In accordance with the Technical Specifications 4.16 Paragraph B1 a land

-- use-censusshall be conducted and ashall Jidentify-the..ocation.of the near est milk animal, the nearest residence, and the nearest garden of greater than 500 ft 2 producing fresh leafy vegetables, in each of the 16 meteor ological sectors within a distance of 5 miles.

The censu shall also identify the locations of all milk animals and all 500 ft 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 1989 land use census was completed on July 29, 1989.

This census did not identify any locations of exposure pathways different from those

-used in the program during the first six months of the year.

Milk and garden sample locations did not change due to the requirements of the land use census.

7

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

All results are summarized in Table 5.4 in a format recommended by the Nuclear Regulatory Commission in Regulatory Guide 4.8.

For each type of analysis of each sampled medium, this table lists the mean and range for all indicator locations and for all control locations.

The locations with the highest mean and range are also shown.

4.1 Atmospheric Nuclear Detonations and Nuclear Accidents There were no reported atmospheric nuclear tests in 1989.

The last reported test was conducted by the People's Republic of China on October 16, 1980.

The reported yield was in the 200 kiloton to 1 megaton range.

There were no reported accidents at nuclear reactor facilities in 1989.

4.2 Program Findings Results obtained show background levels of radioactivity in the environ mental samples collected in the -vicinity of the Monticello Nuclear Generating Plant in 1989.

Ambient Radiation (TLDs)

Ambient radiation was measured in the general area of site boundary, at outer ring 4 -

5 mi distant from the Plant, at special interest areas, and at one control location.

The means were nearly identical at both inner and outer rings (15.0 and 15.4 mR/91 days, respectively).

The mean at special locations was 15.0 mR/91 days.

The mean at the control location was 14.1 mR/91 days.

The differences are not statistically significant.

The dose rates measured were similar to those observed in 1978, 1983, 1984, 1985, 1986, 1987 and 1988 (12.3, 12.5, 13.6, 14.2, 15.3, 15.4 and 15.2 mR/91 days, respectively).

No Plant effect on ambient gamma radiation was indicated.

8

Airborne Particulates The average annual gross beta concentration in airborne particulates was nearly identical at indicator and control locations (0.027 and 0.026 pCi/

dm3,.ervespectively) and was -nearly, identical,.orn.simila r.to the levels observed in 1982 (0.026 pCi/m 3), 1983 (0.023 pCi/m 3 ),

1984 (0.024 pCi/

m3 ), 1985 (0.025 pCi/m 3), and 1986 (0.026 pCi/m 3 ), 1987 (0.026 pCi/

m3 ) and 1988 (0.030 pCi/m 3 ).

The average of 0.026 pCi/m 3 for 1986 does not include the results from May 19 to June 9, 1986, which were influ enced by the accident at Chernobyl.

A-spring peak in beta activity had been observed almost annually for many years (Wilson et al.,,1969).

It had been attributed to fallout of nuclides from the stratosphere (Gold et al., 1964).

It was-pronounced in 1981, occurred to a lesser degree in 1982, and did not occur in 1983,

1984, 1985, or 1987.

In 1986, the spring peak could not be identified because it was overshadowed by the releases of radioactivity from Chernobyl.

The highest averages for gross beta were for the months of

January, February and December and the first and fourth quarter, as in

1983, 1984,

1985, 1986 (exclusive of the period between May 19, 1986 and June 9, 1986), 1987 and 1988.

Two pieces of evidence indicate conclusively that the elevated activity observed during the fourth quarter was not attributable to the Plant op eration.

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, 1990).

Gamma spectroscopic analysis of quarterly composites of air particulate filters yielded similar results for indicator and control locations.

Beryllium-7, which is produced continously in the upper atmosphere by cosmic radiation (Arnold and Al-Salih, 1955),

was detected in all samples.

All other gamma-emitting isotopes were below their respective LLD limits.

Airborne Iodine Weekly levels of airborne iodine-131 were below the lower limit of de tection (LLD) of 0.07 pCi/m 3 in all samples.

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

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

No other gamma-emitting isotopes except naturally-occurring potassium-40 were detected in any of the milk samples.

This is consistent with the finding of the National Center for Radiological Health that most radio-9

contaminants in feed do not find their way into milk due to the selective metabolism of the cow.

The common exceptions are radioisotopes of potassium,

cesium, strontium,

barium, and iodine (National Center for

Radiological Health,,.1968.

In summary, the milk data for 1989 show no radiological effects of the plant operation.

River Water and Drinking Water Tritium was below the LLD of 330 pCi/1 in all samples.

Gross beta in Minneapolis drinking water averaged 2.6 pCi/1. and was-identical or similar to the average level observed in 1977 (3.4 pCi/1),

in 1978 (3.8 pCi/1),

in 1979 (3.4 pCi/1),

in 1980 (3.2 pCi/1),

in 1981 (3.5 pCi/1),

and in 1982 (2.9 pCi/1),

in 1983 (3.3 pCi/1),

in 1984 (2.8 pCi/1),

in

-1985 (2.8 pCi/1),

in 1986 (2.5 pCi/1),

in 1987 (2.4 pCi/1) and in 1988 (2.7 pCi/1).

Comparisons with gross beta data reported by EPA for Minnea polis drinkingwater sample collected in 1975,

1976, 1977, and 1978 indic ates that concentrations of these nuclides are remaining fairly constant and are in the range of drinking water levels in other parts of the country (U.S.

Environmental Protection Agency,

1975, 1976,

1977, 1978).

Gamma emitting isotopes were below detection limits in all surface water samples.

There was no indication of a plant effect.

Well Water The tritium level was below the LLD level of 330 pCi/1 in all samples.

All of the gamma scan results were below detection limits.

There was no indication of a plant effect.

Crops Two (2) samples of cabbage were collected in September and analyzed for iodine-131.

The 1-131 level was below 0.023 pCi/g wet weight in both samples.

There was no indication of a plant effect.

The field sampling personnel conducted a survey at Monticello Plant and found that there were no radioactive liquid effluents released into Mississippi River.

There fore, it was not necessary to collect and analyze corn or potatoe samples.

Fish Fish samples were collected in May and October.

Flesh.was separated.from the bones and gamma scanned. Potassium-40, the naturally-occuring isotope, was found to be similar in upstream and downstream samples (3.16 and 2.48 pCi/g wet weight, respectively).

All gamma-emitting isotopes were below

-their-respective LLD levels.

There' was no-indication of a. plant effect.

10

Invertebrates Two samples were collected in May and two in September.

The samples were analayzed for.gamma-,emitting isotopes.

All..of the isotopes, except naturally-occurring K-40, were below detection limits.

Potassium-40 measured 4.60 pCi/g wet weight at the control location and was below the level of detection at the control location.

There was no indication of a plant effect.

Bottom and Shoreline Sediments Bottom and shoreline sediment collections were made in May and September and analyzed for gamma-emitting isotopes.

Cesium-137 was detected in two upstream and one downstream bottom sediment samples, averaging 0.12 pCi/g dry weight, and in two shoreline sediment samples, averaging 0.16 pCi/g dry weight, indicating the influence of fallout deposition. Similar levels of -activities and distribution were observed in 1978-1988.

The only other gamma-emitting isotope detected was naturally-occurring potassium-40. There was no indication of a plant effect.

11

5.0 TABLES 12

Table 5.1.

Sample collection and analysis program, 1989.

Collection Analysis Locations Type and Type (and Medium No.

Codes and TypeTd Frequencyb Frequency)c Ambient Radiation 37 M-01A - M-14A (TLDs)

M-O1B - M-16B M-01S - M-06S M-01C C/Q Ambient Gamma Airborne Particulates 5

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

Airborne Iodine 5

M-1(C), M-2, M-3, M-4, M-5 C/W 1-131 Milk 5

M-10(C), M-18, M-24, M-26, M-28 G/Md 1-131, GS 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 to M--13 G/Q H-3, GS Edible Cultivated 2

M-10(C), M-27 G/A 1-131 Crops - Cabbage Edible Cultivated 2

M-10(C), M-19 G/A GS Crops - Corne

Table 5.1.

Sample collection and analysis program, 1989 (continued)

Collection Analysis Locations Type and Type (and Medium No.

Codes (and Type)a Frequencyb Frequency)c Edible Cultivated Crops - Potatoese 2

M-10(C), M-21 G/A GS Fish (One Species, Edible Portion) 2 M-8(C), M-9 G/SA GS Algae or Aquatic Insects 2

M-8(C), M-9 G/SA GS Bottom Sediment 2

M-8(C), M-9 G/SA GS Shoreline Sediment 1

M-15 G/SA GS a Location codes are defined in Table 5.2.

Control stations are indicated by (C).

All other stations b are indicators.

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

Analysis type is coded as follows:

GB = gross beta, GS = Gamma spectroscopy, H-3 = tritium, 1-131 = iodine-131.

Frequency is coded as follows: MC = monthly composite, QC = quarterly composite.

d Milk is collected biweekly during the grazing season (May - November) if e milch animals are on pasture.

Collected only if the plant discharges radioactive effluent into the river.

Table 5.2. Sampling locations.

Distance and Direction Code Typea Location Description from Site Stack M-1 M-3 M-2 M-4 M-5 M-8 M-9 M-10 M-11 M-12 M-13 M-14 M-15 M-18 M-19 M-21 M-24 M-26 M-27 M-28 M-O1A M-02A M-03A M-04A M-05A M-06A M-07A M-08A M-09A M-10A M-11A M-12A M-13A M-14A C

Air Station M-1 Air Station M-3 Air Station M-2 Air Station M-4 Air Station M-5 C

Upstream of Plant Downstream of Plant C

Kirchenbauer Farm City of Monticello Plant Well #1 Biegert Residence City of Minneapolis Montisippi Park Witschen Farm River Irrigated Corn Field*

River Irrigated Potato Field*

Holthaus Farm Peterson Farm Wise Residence Hoglund Farm.

North Boundary Road North Boundary Road North Boundary Road Biology Station Road Biology Station Road Biology Station Road County Road 75 County Road 75 County Road 75 County Road 75 County Road 75 County Road 75 North Boundary Road North Boundary Road 11.1 0.8 0.6 0.9 2.7 0.19 0.19 11.5 3.2 0.2 0.5 36 1.6 3.0 4.1 2.5 0.6 3.7 0.7 0.8 1.0 0.7 0.6 0.6 0.5 0.5 0.4 0.3 0.4 0.7 1.1 0.8 mi mi mi mi mi mi mi mi mi mi mi mi mi mi mi mi mi mi mi mi mi mi mi mi mi mi mi mi mi mi mi mi 15 306 0/NW 140 0/SE 1040/ESE 150 0/SSE 136 0/SE 285 0/WNW 620 /ENE 3230/NW 1280/SE 2670/W 2000/SSW 128 0/SE 117 0/ESE 260 0/W 1730/S 111 0 /ESE 2080/SSW 300 0/WNW 3530/N 230/NNE 430/NE 920/E 112 0/ESE 133 0/SE 1580/SSE 1830/S 203 0/SSW 225 0/SW 250 0/WSW 273 0/W 317 0/NW 3380/NNW

Collected only if Plant discharges liquid radioactive effluent into the river.

Monticello

Sampling locations (continued)

Distance and Direction Code Typea Location Description from Site Stack M-01B Sherco #1 Air Station 4.6 Wi @ 02'/N M-02B County Road 11 4.4 mi @ 179/NNE M-03B Intersection of County Road and 81 4.Smi @,49*/NE M-04B Sherco #6 Air Station 4.2 mi @ 67*/ENE M-05B City of Big Lake 4.4 Wi @ 87*/E M-06B County Road #14 and 196th Street 4.3 mi @ 116'/ESE M-07B Monte Industrial Drive 4.4 mi @ 1350/SE M-08B Dale K. Larson Residence 4.6 mi @ 162*/SSE M-09B Norbert Weinand Farm 4.7 mi @ 1800/S M-1OB

-John-Reisewitz Farm 4.4 Wi @ 206'/SSW M-11B Clifford Vanlith Farm 4.2 mi @ 225*/SW M-12B Lake Maria State Park 4.4 mi @ 2530/WSW M-13B Bridgewater Station 4.1 mi @ 271'/W M-14B Richard K Anderson Residence 4.5 mi @ 228*/WNW M-15B Gary Williamson.Residence 4.5 mi @ 308 0/NW M-16B Sand Plain Research Farm 4.3 mi @ 338/NNW M-01S Former Dickson Residence 0.5 mi @ 1720/S M-02S Edgar Klucas Residence 0.7 mi @ 142*/SE M-03S Big Oaks Park 1.3 mi @ 890/E M-04S Pinewood School 2.3 mi @ 1320/SE M-05S Roman Greener Residence 2.5 mi @ 112'/ESE M-06S Monte Service Center 2.7 mi @ 1360/SE M-41C C

Kirchenbauer Farm 11.5 mi @ 323'/NW a VC denotes control location.

All other locations are indicators.

16 Monti cell1o Table 5.2

Table 5.3.

Missed collections and analyses for 1989 at Monticello Nuclear Generating Plant.

All required samples were collected and analyzed -except the following:

Collection Date Sample Location or Period Comments Milk M-24 10-11-89 Holthaus Dairy went 11-03-89 out of business.

12-07-89 17

Table 5.4. Environmental Radiological Monitoring Program Summary.

Name of Facility Monticello Nuclear Generating Plant Docket No.

50-263 Location of Facility Wright, Minnesota Reporting Period January - December 1989 (County, State)

Sample Type (Units)

TLD (mR/91 days)

(Inner Ring.

General Area of Site Boundary)

TLD (mR/91 days)

(Outer ring, 4 5 miles distant)

TLD (mR/91 days)

(Special Interest Areas)

TLD (mR/91 days)

(control)

Airborne Partcilates (pCi/m )

00.

Type and Number of Analysesa Gamma 56 Gamma 64 Gamma Gamma 24 4

LLDb 3.0 3.0 3.0 3.0 GB 255 0.003 GS Be-7 20 Mn-54 Co-58 Co-60 Zn-65 Zr-Nb-95 Ru-103 Ru-106 Cs-134 0.028 0.0018 0.0020 0.0018 0.0043 0.0035 0.0018 0.012 0.0014 Indicator Locations Mean (F)c Rangec 15.0 (56/56)

(11.4-18.2) 15.4 (64/64)

(11.4-23.5) 15.0 (24/24)

(12.9-17.5)

None 0.027 (204/204)

(0.009-0.071) 0.058 (16/16)

(0.042-0.074)

<LLD

<LLD Location with Highest Annual Mean RageF Locationd M-01A, North Boundary Road, 0.7 mi @

353*/N M-05B, City of Big Lake, 4.4 mi @

87*/E M-04S, Pinewood School 2.3 mi @ 132*/SE M-01C, Kirchenbauer Farm, 11.5 mi @

323 0/NW f

M-3, Station M-3 0.6 mi @ 104*/ESE H-3, Station M-3 0.6 mi @ 104 0/ESE Range 16.1 (4/4)

(13.8-18.2) 21.1 (4/4)

(18.3-23.5) 15.7 (4/4)

(14.6-17.1) 14.1 (4/4)

(13.0-15.3) 0.027 (51/51)

(0.012-0.071) 0.066 (4/4)

(0.058-0.074)

Control Locations mean (F)

Range (See control below)

(See control below)

(See control below) 14.1 (4/4)

(13.0-15.3) 0.026 (51/51)

(0.008-0.066 0.058 (4/4)

(0.049-0.066

<LLD

<LLD Number of Non-routine Resultse 0

0 0

0

Table 5.4.

Environmental Radiological Monitoring Program Summary (continued)

Name of Facility Monticello Nuclear Generating Plant Docket No.

50-263 Location of Facility Wright, Minnesota

~Reporting Period January - December 1989 (County, State)

Sampl e Type (Units)

Ai rborne Particulates (continued)

Airborne Iodine (pCi/m 3)

Milk (pCi/1)

River Water (pCi/1)

I ko Type and Number of Analysesa Cs-137 Ba-La-140 Ce-141 Ce-144 1-131 255 1-131 78 GS 78 K-40 Cs-134 Cs-137 Ba-La-140 H-3 8

GS 24 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 LLDb 0.0016 0.0095 0.0030 0.0081 0.07 Indicator Locations Mean (F)c Rangec

<LLD

<LLD 1.0

<LLD 200 15 15 15 330 15 30 15 15 30 15 15 1260 (62/62)

(1090-1480)

<LLD

<LID

<LLD

<LLD Location with Highest Annual Mean Mean FT Locationd Range M-26, Peterson Farm 2.3 mi @ 111 0/ESE 1280 (16/16)

(1140-1450)

Control Locations Mean (F)

Range

<LLD

<LID

<LLDO -- 1 O

1280 (16/16)

(1110-1490)

<LLD

<LID

<LLD

<LLD Number of Non-routine Resultse 0

0 0

Table 5.4.

Environmental Radiological Monitoring Program Sunmary (continued)

Name of Facility Location of Facility Monticello Nuclear Generating Plant Wright, Minnesota (County, State)

Docket No.

50263 Reporting Period _January - December 1989 Sample Ty pe (Units)

River Water (pCi/ 1)

(continued)

Drinking Water (pCi/1)

Well Water (pCi/1)

Type and Number of Analysesa Cs-137 Ba-La-140 Ce-144 GB 12 1-131 12 H-3 4

GS 12 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Ce-144 H-3 16 GS 16 Mn-54 Fe-59 Co-58 Co-60

-t r

LLDb 18 15 64 1.0 1.0 330 15 30 15 15 30 15 10 10 15 61 330 15 30 15 15 Indicator Locations Mean (F)c Rangec

<LLD

<LLD 2.6 (12/12)

(1.1-4.3)

<LLD

<LLD Location with Highest Annual Mean Mean F

Locationd Range M-14, Minneapolis 36 mi @ 128 0/SE 2.6 (12/12)1 (1.1-4.3)

Control Locations Mean (F Range

<LLD

<LLD None None None None None None None None None None None None None

<LLD

<LLD Mumber of Non-routine Resultse 0

0 0

Table 5.4.

Environmental Radiological Monitoring Program Summary (continued)

Name of Facility Location of Facility Sample Type (Units)

Well Water (pCi/I)

(continued)

Crops-Cabbage (pCi/g wet)

Fish (pCi/g wet)

Invertebrates (pCi/g wet)

Type and Number of Analysesa Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Ce-144 1-131 2

GS K-40 Monticello Nuclear Generating Plant Wright, Minnesota (County, State)

Indicator L

Locations Mean (F)c LLDb Rangec Loc 30 15 10 10 15 67 0.023

<LLD

<LLD Docket No.

50-263 Reporting Period January - December 1989 ocation with Highest Annual Mean mean (F) ationd Range

-4

-l

--I*

I 4

Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-La-140 GS 4

Be-7 0.1 0.025 0.071 0.030 0.024 0.055 0.051 0.040 0.022 0.025 0.10 1.15 2.48 (2/2)

(1.90-3.06)

<LLD

<LLD M-8, Upstream of Plant, 0.19 mi

@ 285 WNW 3.16 (2/2)

(3.13-3.19)

Control Locations Mean (F)

Range

<LLD

<LLD 3.16 (2/2)

(3.13-3.19)

<LLD

<LLD N)3 Number of Mon-routine Resultse 0

0 0

t

Table 5.4.

Environmental Radiological Monitoring Program Summary (continued)

Name of Facility Location of Facility Monticello Nuclear Generating Plant Wright, Minnesota (County, State)

Docket No.

50-263 Reporting Period January - December 1989 Sample Type (Units)

Invertebrates (pCi/g wet)

(continued)

Bottom and Shoreline Sediments (pCi/g dry)

Type and Number of Analysesa K-40 Mn-54 Co-58 Co-60 Zn-65 Zr-Nb-95 Ru-103 Ru-106 Cs-134 Cs-137 Ba-La-140 Ce-141 Ce-144 GS 6

Be-7 K-40 Mn-54 Co-58 Co-60 LLDb 1.98 0.17 0.16 0.14 0.28 0.28 0.14 1.11 0.11 0.14 0.25 0.27 0.90 0.83 0.5 0.048 0.088 0.050 Indicator Locations Mean (F)c Rangec

<LLD

<LLD c

<LLD

<LLD 10.56 (4/4)

(10.22-11.10)

<LLD

<LLD Location with Highest Annual Mean Mean (F)

Locationd Range N-8, Upstream of 4.60 (1/2)

Plant, 0.19 mi @

285*/WNW 4-8, Upstream of Plant, 0.19 mi @

2850/WNW 11.30 (2/2)

(11.10-11.50)

Control Locations Mean (F)

Range 4.60 (1/2)

<LLD

<LLD 11.30 (2/2)

(11.10-11.50)

<LLOD

<LLD

<LLD Number of Non-routine Resultse 0

0 0

0

Table 5.4.

Environmental Radiological Monitoring Program Summary (continued)

Name of Facility Monticello Nuclear Generating Plant_ Docket No.

50-263 Location of Facility Wright Minnesota Reporting Period January - December 1989 (County, State)

Indicator Location with Highest Control Sample Type and Locations Annual Mean Locations Type Number of Mean (F)c Mean Mean (F)

(Units)

Analysesa LLDb Rangec Locationd Range Range Bottom and Zn-65 0.13

<LLD

<LLD Shoreline Sediments Zr-95 0.17

<LLD

-<LD (pCi/g dry)

(continued)

Nb-95 0.22

<LLD

-<LD Ru-103 0.16

<LLD

<LLD Ru-106 0.41

<LLD

<LLD Cs-134 0.034

<LLD

<LLD Cs-137 0.037 0.14 (3/4)

M-15, Montissippi 0.16 (2/2) 0.13 (2/2)

(0.10-0.19)

Park 1.6 mi @

(0.13-0.19)

(0.11-0.15) 117./ESE Ba-La-140 8.63

<LLD

<LLD Ce-141 0.32

<LLD

<LLD Ce-144 0.24

<LLD

<LLD Number of Non-routine Resultse 0

0 0

0 a GB Gross beta; GS = gamma scan.

b LLD

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

c Mean and range based upon detectable measurements only.

Fraction of detectable measurements at specified location is indicated in parentheses (F).

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

e Non-routine results are those which exceed ten times the control station value.

If no control station value is available, the result Is considered non-routine if it exceeds ten times the preoperational value for the location.

f Locations M-3, M-4, M-5 all have annual means of 0.027 pCi/m 3.

Only M-3 (0.027 pCi/m 3) is detailed in summary table.

I~3

6.0 REFERENCES

CITED

..Arnold, J. R. and H. A. Al-Salih.. 1955.

Beryllium-7 Produced by Cosmic Rays.

Science 121:

451-453.

Eisenbud, M. 1963. Environmental Radioactivity, McGraw-Hill, New York, New York, pp. 213, 275, and 276.

Hazleton Environmental Sciences Corporation. 1979a. Radiation Environ mental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1978.

1979b. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January December 1978.

1980a.

Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January December 1979.

1980b.

Radiation Environmental Monitoring for Prairie

'sland-Nuclear-Generating Plant, Complete Analysis Data Tables, January December 1979.

1981a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January December 1980.

1981b.

Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January December 1980.

1982a.

Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January December 1981.

1982b.

Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January December 1981.

1983a.

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

1983b.

Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January December 1982.

2d1

National.Center for Radiological Health, 1968. Radiological Health and j

Data Reports, Vol. 9, Number 12, 730-746.

Northern States Power Company. 1977.

Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission,.January 1, 1976 - December 31,,,19,6.(prepared by NALCO Environmental Sciences), Minneapolis, Minnesota.

1978.

Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report-to the U.S. Nuclear Regu latory Commission, January 1, 1977 - December 31, 1977 (prepared by NALCO Environmental Sciences), Minneapolis, Minnesota.

1979.

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

1980.

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

1981.

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

1982.

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

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

1984. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regu latory Commission, January 1, 1983 - December 31, 1983 (prepared by Teledyne Isotopes Midwest Laboratory)., Minneapolis, Minnesota.

1985.

Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regu latory Commission, January 1, 1984 - December 31, 1984 (prepared by Teledyne Isotopes Midwest Laboratory), Minneapolis, Minnesota.

1986.

Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regu lYatory Commission, January 1,-1985 - December. 31,.1985,prepared by Teledyne Isotopes Midwest Laboratory), Minneapolis, Minnesota.

25

1987.

Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regu latory Commission, January 1, 1986 - December 31, 1986 (prepared by Teledyne Isotopes Midwest Laboratory), Minneapolis, Minnesota.

1988. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regu latory Commission, January 1, 1987 - December 31, 1987 (prepared by Teledyne, Isotopes Midwest Laboratory), Minneapolis,.Minnesota.

1989.

Monticello Nuclear Generating.Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regu latory Commission, January 1, 1988 - December 31, 1988 (prepared by Teledyne Isotopes Midwest Laboratory), Minneapolis, Minnesota.

Teledyne -Isotopes Midwest Laboratory. 1985.

Analytical Procedures Manual, Revision 5, 29 July 1985.

1990.

Quality Assurance Program Manual, Revision 2, 08.J.anuary.1990.

1989. Quality Control Procedures Manual, Revision 10, 30 November 1989.

1989. Quality Control Program, Revision 11, 5 April 1989.

1984a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January December 1983.

1984b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete.Analysis.Data Tbles,...January December 1983.

1985a.

Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January December 1984.

1985b.

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

1986a.

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

1986b.

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

1987.

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

26

1987a.

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

1987b.

Radiation EnvironmentalbMonitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January December 1986.

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

1988b.

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

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

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

1990a.

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

1990b.

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

U. S. Atomic Energy Commission.

1972.. HASL Procedures Manual, Health and Safety Laboratory, New York, New York.

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

Wilson, D. W., G. M. Ward and J. E. Johnson, 1969.

In Environmental Contami nation of Radioactive Materials, International Atomic Energy Agency,

p. 125.

27

'WTELEDYNE ISOTOPES MIDWEST LABORATORY 700 LANDWEHR ROAD NORTHBROOK, ILLINOIS 60062-2310 (708) 564-0700 FAX (708) 564-4517 Appendix A Interlaboratory Comparison Program Results NOTE:

TIML participates in intercomparison studies administered by U.S. EPA Environmental Monitoring.Systems Laboratory, Las Vegas, Nevada. The results are reported in Appendix A. Also reported-are results of in house spikes and blanks. Appendix A is updated twice a year and the complete Appendix is included in January and July monthly reports only.

Please refer to January and July Reports for information.

January 1990.

A-1

Appendix A Interlaboratory Comparison Program Results Teledyne Isotopes Midwest Laboratory (formerly Hazleton Environmental Sciences) has participated in interlaboratory -comparison (crosscheck) programs since the formulation of its quality control program in December 1971.

These programs are operated by agencies which supply environmental-type samples (e.g., milk or water) containing concentrations of radionuclides known to the issuing agency but not to participant laboratories.

The purpose of such a program is to provide an independent check on the laboratory's analytical procedures and to alert it to any possible.problems.

Participant laboratories measure the concentrations of specified radionuclides and report them to the issuing agency.

Several months later, the agency reports the known values to the participant laboratories and specifies control limits.

Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used.

The results in Table A-1 were obtained through participation in the environmental sample crosscheck program for milk, water, air filters, and food samples during

-the-period:January ^1986" through November, 1989.

This program has been conducted by the U.S.

Environmental Protection Agency Intercomparison and Calibration

Section, Quality Assurance Branch, Environmental Monitoring and Support Labora tory, Las Vegas, Nevada.

The results in Table A-2 were obtained for thermoluminescent dosimeters (TLD's) during the period.1976,

1977, 1979,

1980, 1984, and 1985-1986 through partici pation in the Second,

Third, Fourth,

Fifth, Seventh, and Eighth International Intercomparison of Environmental Dosimeters under the sponsorships listed in Table A-2. Also Teledyne testing results are listed.

Table A-3 lists results of the analyses on in-house spiked samples.

Table A-4 lists results of the analyses on in-house "blank" samples. lists acceptance criteria for "spiked" samples.

Addendum to Appendix A provides explanation for out of limit results.

A-2

Table A-1.

U.S. Environmental Protection Agency's crosscheck program, com parison of EPA and Teledyne Isotopes Midwest Laboratory results

'for milk, eater, air filters, and food samples, 1986 through 19 89.a Concentration in pCi/lb Lab Sample Date TIML Result EPA Resultd Code Type Collected Analysis

+/-2 c Is, N=1 Control Limits STF-447 Food Jan 1986 STW-448 Water Feb 1986 STW-449 Water Feb 1986 STW-450 Water Feb 1986 STM-451 Milk Feb 1986 STW-452

.Water Mar 1986 STW-453 Water Mar 1986 STW-454 Water Apr 1986 STW-455 Water 456 (Blind)

Sample A Sample B Sr-89 Sr-90 1-131 Cs-137 K

Cr-51 Co-60 Zn-65 Ru-106 Cs-134 Cs-137 H-3 U total 1-131 Ra-226 Ra-228 Gr. alpha Gr. beta 1-131 24.3+/-2.5 17.3+/-0.6 22.7+/-2.3 16.3+/-0.6 927+/-46 45.0+/-3.6 19.7+/-1.5 44.0+/-3.5

<9.0 28.3+/-2.3 23.7+/-0.6 5176+/-48 8.0+/-0.0 7.0+/-0.0 25.0+/-5.0 10.0+/-1.5 20.0+/-0.6 15.0+/-5.0 950+/-144 38.0+/-5.0 18.0+/-5.01 40.0+/-5.0!

0 *0+5 01 30.0+/-5.01 22.0+/-5.0 1 5227+/-525 9.0+/-6.01 9.0+/-6.0 3.8+/-0.1 4.1+/-0.6 11.0+/-0.5 12.4+/-1.8 6.7+/-0.6 7.3+/-0.6 7.0+/-0.0 15.0+/-5.0 8.0+/-5.0 9.0+/-6.0 Apr 1986 Gr. alpha Ra-226 Ra-228 Uranium Gr. beta Sr-89 Sr-90 Co-60 Cs-134 Cs-137 15.0+/-1.0 3.1+/-0.1 1.5+/-0.2 4.7+/-0.6 28.7+/-1.2 5.7+/-0.6 7.0+/-0.0 10.7+/-1.5 4.0+/-1.7 5.3+/-0.6 17.0+/-5.0 2.9+/-0.4 2.0+/-0.3 5.0+/-6.0 35.0+/-5.0 7.0+/-5.0 7.0+/-1.5 10.0+/-5.0 5.0+/-5.0 5.0+/-5.0 A-3 16.3-33.7 7.4-12.6 9.6-30.4 6.3-23.7 701-1199 29.3-46.7 9.3-26.7 31.3-48.7 0.0-8.7 21.3-38.7 13.3-30.7 4317 <6137 0.0-19.4 0.0-19.4 3.0-5.2 9.2-15.5 6.3-23.7 0.0-16.7 0.0-19.4 8.3-25.7 2.1-3.7 1.5-2.5 0.0-15.4 26.3-43.7 0.0-15.7 4.4-9.6 1.3-18.7 0.0-13.7 0.0-13.7

Table A-1.

(continued)

Concentration in pCi/lu Sample Date Type Collected Analysis TIML Result

+/-2 C EPA Result 0 1s, N=1 Control Limits STAF-457 Air Filter April 1986 STU-458 Urine April 1986 STW-459 Water May 1986 STW-460 Water May 1986 STW-461 Water June 1986 STW-462 Water STM-464 Milk June 1986 June 1986 STW-465 Water July 1986 STW-467 Water August 1986 STW-468 Water August 1986 STW-469 Water August 1986 STAF-470 471 472 Air Filter Sept 1986 Gr. alpha Gr. beta Sr-90 Cs-137 Tritium Sr-89 Sr-90 Gr. alpha Gr. beta Cr-51 Co-60 Zn-65 Ru-106 Cs-134 Cs-137 Tritium Sr-89 Sr-90 1-131 Cs-137 K

Gr. alpha Gr. beta 1-131 Pu-239 Uran i um Gr. alpha Gr. beta Sr-90 Cs-137 13.7+/-0.6 46.3+/-0.6

14. 7+/-0.6

10. 7+/-0.6 4313+/-70 4.3+/-0.6 5.0+/-0.0 5.3+/-0.6 11.3+/-1.2

<9.0 66.0+/-1.0 87.3+/-1.5 39.7+/-2.5 49.3+/-2.5 10.3+/-1.5 3427+/-25

<1.0 15.3+/-0.6 48.3+/-2.3 43.7+/-1.5 1567+/-114 4.7+/-0.6

18. 7+/-1.2 30.3+/-0.6 11.3+/-0. 6 4.0+/-0.0 19.3+/-1.5 64.0+/-2.6 22.0+/-1.0

25. 7+/-1.5 15.0+/-5.0 47.0+/-5.0 18.0+/-1.5 10.0+/-5.0 6.3-23.7 38.3-55.7 15.4-20.6 1.3-18.7 4423+/-189 4096-4750 5.0+/-5.0 0.0-13.7 5.0+/-1.5 2.4-7.6 8.0+/-5.0 0.0-16.7 15.0+/-5.0 6.3-23.7 0.0+/-5.0 66.0+/-5.0 86.0+/-5.0 50.0+/-5.0 49.0+/-5.0 10.0+/-5.0 0.0-8.7 57.3-74.7 77.3-94.7 41.3-58.7 40.3-57.7 1.3-18.7 3125+/-361 2499-3751 0.0+/-5.0 16.0+/-1. 5 41.0+/-6.0 31.0+/-5.0 1600+/-80 0.0-8.7 13.4-18.6 30.6-51.4 22.3-39.7 1461-1739 6.0+/-5.0 0.0-14.7 18.0+/-5.0 9.3-26.7 45.0+/-6.0 34.4-55.4 10.1+/-1.0 8.3-11.9 4.0+/-6.0 0.0-14.4 22.0+/-5.0 66.0+/-5.0 22.0+/-5.0 22.0+/-5.0 13.3-30.7 57.3-74.7 19.4-24.6 13.3-30.7 STW-473 Water Sept 1986 Ra-226 Ra-228 6.0+/-0.1 8.7+/-1.1 6.1+/-0.9 4.5-7.7 9.1+/-1.4 6.7-11.5 A-4 Lab Code

Table A-1.

(continued).

Concentration in pCi/lb Lab Sample Date TIML Result EPA Resultd Code

-Type Collected Analysis

+/-2oc Is,"N=1 Control Limits STW-474 Water Sept 1986 STW-475 Water Oct 1986 STW-476 Water Oct 1986 SPW-477 Water Oct 1986 478 (Blind)

Gr. alpha Gr. beta Cr-51 Co-60 Zn-65 Ru-106 Cs-134 Cs-137 H-3 16.3+/-3.2 9.0+/-1.0 63.3+/-5.5 31.0+/-2.0 87.3+/-5.9 74.7+/-7.4

25. 7+/-0. 6 46.3+/-1.5 5918+/-60 15.0+/-5.0 6.3-23.7 8.0+/-5.0 0.0-16.7 59.0+/-5.0 31.0+/-5.0 85.0+/-5.0 74.0+/-5.0 28.0+/-5.0 44.0+/-5.0 50.3-67.7 22.3-39.7 76.3-93.7 65.3-82.7 19.3-36.7 35.3-52.7 5973+/-597 4938-7008 Sample A Sample B STM-479 Milk Nov '1986 STU-480 Urine Nov 1986 STW-481 Water Nov 1986 STW-482 Water Dec 1986 STW-483

.,Water

,Jan 1987 Gr. alpha Ra-226 Ra-228 Uranium Gr. beta Sr-89 Sr-90 Co-60 Cs-134 Cs-137 Sr-89 Sr-90 1-131 Cs-137 K

H-3 Gr. alpha Gr. beta Ra-226 Ra-228

,Sr-89 Sr-90 34.0+/-6.0 5.8+/-0.2 2.7+/-1.0 11.0+/-0.0 38.7+/-1.2 5.0+/-0.0 3.0+/-0.0 24.7+/-1.2 11.0+/-2.0 9.3+/-1.2 7.7+/-1.2 1.0+/-0.0 52.3+/-3.1 45.7+/-3.1 1489+/-104 5540+/-26 12.0+/-4.0 20.0+/-3.5

6.

7+/-0. 2 5.2+/-0.2 19.7+/-5.0 21.0+/-2.0 40.0+/-5.0 6.0+/-0.9 5.0+/-0.8 10.0+/-6.0 51.0+/-5.0 10.0+/-5.0 4.0+/-1. 5 24.0+/-5.0 12.0+/-5.0 8.0+/-5.0 9.0+/-5.0 0.0+/-1.5 49.0+/-6.0 39.0+/-5.0 1565+/-78 31.3-48.7 4.4-7.6 3.7-6.3 0.0-20.4 42.3-59.7 1.3-18.7 1.4-6.6 15.3-32.7 3.3-20.7 0.0-16.7 0.3-17.7 0.0-2.6 38.6-59.4 30.3-47.7 1430-1700 5257+/-912 4345-6169 20.0+/-5.0 11.3-28.7 20.0+/-5.0 11.3-28.7 6.8+/-1.0 5.0-8.6 11.1+/-1.7 8.2-14.0 25.0+/-5.0 16.3-33.7 25.0+/-1.5 22.4-27.6 A-- 5

T&ble A-1.

(continued).

Concentration in pCi/lb Lab Sample Date TIML Result EPA Resultd

'Code

'Type Collected Analysis

+/-2oc 1s,-N=1 Control Limits STW-484 Water Jan 1987 STF-486 Food STF-487 Food (Blank)

Jan 1987 Jan 1987 STW-488 Water Feb 1987 STW-489 Water Feb 1987 STW-490 Water Feb 1987 STM-491 Milk Feb 1987 STW-492 Water Mar 1987 STW-493 Water

'Mar 1987 STW-494 Water Apr 1987 STAF-495 Air Filter Apr 1987 Pu-239 Sr-90 1-131 Cs-137 K

SR-90 1-131 Cs-137 K

Co-60 Zn-65 Ru-106 Cs-134 Cs-137 H-3 Uranium 1-131 Gr. alpha Gr. beta Ra-226 Ra-228 I-131 Gr. alpha Gr. beta Sr-90 Cs-137 17.0+/-2.3 36.0+/-4.0 78.0+/-3.4 89.7+/-3.0 942+/-56 2.0+/-0.0

<3

<2 993+/-102 49.0+/-0.0 96.0+/-7.2 92.0+/-20.2 53.0+/-3.4 89.3+/-4.6 4130+/-140 8.3+/-1.2 10.0+/-0.0 3.7+/-1. 2 11.3+/-1.2 7.0+/-0.1 7.1+/-2.3 8.0+/-0.0 15.0+/-0.+/-0 41.0+/-2.0 16.3+/-1.2 7.0+/-0.0

16. 7+/-1. 7 49.0+/-10.0 78.0+/-8.0 84.0+/-5.0 980+/-49 50.0+/-5.0 91.0+/-5.0 100.0+/-5.0 59.0+/-5.0 87.0+/-5.0 13.8-19.6 31.7-66.3 64.1-91.9 75.3-92.7 895-1065 41.3-58.7 82.3-99.7 91.3-108.7 50.3-67.7 78.3-95.7 4209+/-420 3479-4939 8.0+/-6.0 0.0-18.4 9.0+/-0.9 7.4-10.6 3.0+/-5.0 0.0-11.7 13.0+/-5.0 4.3-21.7 7.3+/-1.1 5.4-9.2 7.5+/-1.1 5.5-9.5 7.0+/-0.7 5.8-8.2 14.0+/-5.0 43.0+/-5.0 17.0+/-1.5 8.0+/-5.0 5.3-22.7 34.3-51.7 14.4-19.6 0.0-16.7 STW-496. Water 497 (Blind)

Sample A Apr 1987 Gr. alpha Ra-226 Ra-228 Uranium

30. 7+/-1. 2 3.9+/-0. 2 4.9+/-0.9 5.0+/-0.0 30.0+/-8.0 3.9+/-0.6 4.0+/-0.6 5.0+/-6.0 16.1-43.9 2.9-4.9 3.0-5.0 0.0-15.4 A-6

Table A-1.

(continued)

Concentration in pCi/lb Lab Sample Date TIML Result EPA Resultd Code Type Collected Analysis

+/-20c Is, N=1 Control Limits STW-496 Water 497 (Blind)

Sample B Apr 1987 Gr. Beta Sr-89 Sr-90 Co-60 Cs-134 Cs-137 STU-498 Urine Apr 1987 STW-499 Water May 1987 STW-500 Water May 1987 STW-501 Water June 1987 STW-502 Water June 1987 STW-503 Water June 1987 STM-504 Milk June 1987 STW-505 Water July 1987 STF-506 Food July 1987 STW-507 Water Aug 1987 l

STW-508 Water Aug 1987 H-3 Sr-89 Sr-90 Gr. alpha Gr. beta Cr-51 Co-60 Zn-65 Ru-106 Cs-134 Cs-137 H-3 Ra-226 Ra-228 Sr-89 Sr-90 1-131 Cs-137 K

Gr. alpha Gr. beta 1-131 Cs-137 K

1-131 Pu-239 69.3+/-9.4

16. 3+/-3.0 10.0+/-0.0 8.3+/-3.0 19.0+/-2.0

14. 7+/-1.2 6017+/-494 38.0+/-6.0 21.0+/-2.0 9.0+/-3.4 10.3+/-1. 2 40.0+/-8.0 60.3+/-3.0

11. 3+/-5.0 78.3+/-6.4

36. 7+/-3.0 80.3+/-4.2 2906+/-86 6.9+/-0.1 13.3+/-1.0 57.0+/-4.3

32. 0+/-1.0 64.0+/-2.0 77.7+/-0.6 1383+/- 17

2. 3+/-0. 7 4.0+/-1.0 82.7+/-4.6

53. 7+/-3.0 1548+/-57 45.7+/-4.2,

5.8+/-0.2 66.0+/-5.0 19.0+/-5.0 10.0+/-1.5 8.0+/-5.0 20.0+/-5.0 15.0+/-5.0 57.3-74.7 10.3-27.7 7.4-12.6 0.0-16.7 11.3-28.7 6.3-23.7 5620+/-795 4647-6593 41.0+/-5.0 32.3-49.7 20.0+/-1.5 17.4-22.6 11.0+/-5.0 2.3-19.7 7.0+/-5.0 0.0-15.7 41.0+/-5.0 64.0+/-5.0 10.0+/-5.0 75.0+/-5.0 40.0+/-5.0 80.0+/-5.0 32.3-49.7 55.3-72.7 1.3-18.7 66.3-83.7 31.3-48.7 71.3-88.7 2895+/-357 2277-3513 7.3+/-1.1 5.4-9.2 15.2+/-2.3 11.2-19.2 69.0+/-5.0 35.0+/-1.5 59.+/-6.0+/-

74.0+/-5.0 1525+/-76 60.3-77.7 32.4-37.6 48.6-69.4 65.3-82.7 1393-1657 5.0+/-5.0 0.0-13.7 5.0+/-5.0 0.0-13.7 80.0+/-8.0 50.0+/-5.0 1680+/-84 "48.0+/-6.0 66.1-93.9 41.3-58.7 1534-1826 37.6-58.4 5.3+/-0.5 4.4-6.2 A-7

Table A-1.

(continued)

Concentration in pCi/lb Lab Sample Date TIML Result EPA Resultd Code Type Collected Analysis

+/-2ac Is, N=1 Control Limits STW-509 Water Aug 1987 STAF-510 Air Filter STW-511

Water, Aug 1987 Sept 1987 STW-512 Water Sept 1987 STW-513 Water Oct 1987 Uranium Gr. alpha Gr. beta Sr-90 C s-137 R a-2 26 Ra-228 Gr. alpha Gr. beta H-3 13.3+/-0.3 9.7+/-0 28.3+/-0 10.0+/-0 10.0 +/-1 13.0+/-6.0, 2.6-23.4

.4

.6

.9

.0 9.9+/-0.1 8.1+/-1.4 2.0+/-0.6 11.3+/-1.3 4473 +/-100 10.0+/-5.0 30.0+/-5.0 10.0+/-1.5 10.0+/-5.0 1.3-18.7 21.3-38.7 7.4-12.6 1.3-18.7 9.7+/-1.5 7.2-12.2 6.3+/-1.0 4.6-8.0 4.0+/-5.0 0.0-12.7 12.0+/-5.0 3.3-20.7 4492+/-449 3714-5270 STW-514 Water (Blind)

Gr. alpha Ra-226 R a-2 28 U rani um Sr-89 Sr-90 C o-60 Cs-134 Cs-137 STW-516 Water Oct 1987 STU-517 Urine Nov 1987 STW-518 Water Nov 1987 STW-519 Water Dec 1987.

Cr-51 C o-60 Zn-65 Ru-106 Cs-1 34 C s-137 H-3 Gr. alpha Gr. beta 1-131 29.3+/-2.6 4.9+/-0.1 4.2+/-11.0 3.0 +/-0.1 14.3+/-1.3 9.7+/-0.4 16.7+/-3.0 16.7+/-2.3 24.3+/-3.3 80.3+/-17.5 16.0+/-2.3 46.3+/-5.6 57.3 +/-15.4 23.7+/-2.5 51.7+/-3.2 7267 +/-100 3.0+/-2.0 15.7+/-2.3 26.0t3.0 28.0+/-7.0 4.8 +/-0.7 3.6 +/-0.5 3.0+/-6.0 16.0 +/-5.0 10.0+/-1.5 16.0+/-5.0 16.0+/-5.0 24.0+/-5.0 70.0+/-5.0 15.0+/-5.0 46.0+/-5.0 61.0+/-5.0 25.0+/-5.0 51.0+/-5.0 15.9-40.1 3.6-6.1 2.7-4.5 0.0-13.4 7.3-24.7 7.4-12.6 7.3-24.7 7.3-24.7 15.3-32.7 61.3-78.7 6.3-23.7 37.3-54.7 52.3-69.7 16.3-33.7 42.3-59.7 7432+/-743 6145-8719 7.0+/-5.0 19.0+/-5.0

.26.0+/-6.0 0.0-15.7 10.3-27.7 15.6-36.4 A-8 Oct 1987 Sample A Sample B

Table A-1.

(continued)

Concentration in pCi/lb Lab Sample Date TIML Result EPA Resultd

,Code

..Type Collected Analysis

+/-2ac 1s, N=1,.

Control Limits STW-520 Water STW-521 Water STW-523 Water STF-524 Faod STW-525 Water STW-526 STW-527 STM-528 STW-529 Water Water Milk Water STW-530 Water STAF-531 Air Filter STW-532 Water Dec 1987 Jan 1988 Jan 1988 Jan 1988 Feb 1988 Feb Feb Feb Mar Ra-226 Ra-228 Sr-89 Sr-90 Gr. alpha Gr. beta Sr-89 Sr-90 1-131 Cs-137 K

Co-60 Zn-65 Ru-106 Cs-134 Cs-137 H-3 Uranium 1-131 Ra-226 Ra-228 Gr. alpha Gr. beta Gr. alpha Gr. beta Sr-90 Cs-137 1-131 1988 1988 1988 1988 Mar 1988 Mar 1988 Apr 1988 5.1+/-0.8 3.4+/-0.1 27.3+/-5.0

15. 3+/-1.2 2.3t1.2 7.7+/-1.2 44.0+/-4.0 53.0+/-2.0 102.3+/-4.2 95.7+/-6.4 1011t158 69.3+/-2.3 99.0+/-3.4 92.7+/-14.4 61.7t8.0 99.7t3.0 3453t103 3.0+/-0.0

4. 71.2

7. 1+/-0.6 NAe 4.3+/-1.2 13.3+/-1.3 21.0+/-2.0 48.0+/-0.0 16.71.2 18.71.3 9.02.0 4.8+/-0.7 5.3+/-0.8 30.0+/-5.0 15.0+/-1.5 4.0+/-5.0 8.0+/-5.0 46.0+/-5.0 55.0+/-2.8 102.0+/-10.2 91.0+/-5.0 1230+/-62 69.0+/-5.0 94.0+/-9.4 105.0+/-10.5 64.0+/-5.0 94.0+/-5.0 3327+/-362 3.0+/-6.0 4.0+/-0.4 7.6+/-1.1 7.7+/-1.2 6.0+/-5.0 13.0t5.0 20.0+/-5.0 50.0+/-5.0 17.0+/-1.5 16.0+/-5.0 7.5+/-0.8 3.6-6.0

.3.9-6.7 21.3-38.7 12.4-17.6 0.0-12.7 0.0-16.7 37.3-54.7 50.2-59.8 84.3-119.7 82.3-99.7 1124-1336 60.3-77.7 77.7-110.3 86.8-123.2 55.3-72.7 85.3-102.7 2700-3954 0.0-13.4 3.3-4.7 5.6-9.6 5.7-9.7 0.0-14.7 4.3-21.7 11.3-28.7 41.3-58.7 14.4-19.6 7.3-24.7 6.2-8.8 A-9

Table A-1.

(continued)

Concentration in pCi/lb Lab Sample Date TIML Result EPA Resultd Code Type Collected Analysis

+/-2yc is, N=1 Control Limits STW-533 Water 534 (Blind)

Apr 1988 Sample A Sample B Gr. alpha Ra-226 Ra-228 Uranium Gr. beta Sr-89 Sr-90 Co-60 Cs-134 Cs-137 STU-535 Urine Apr 1988 STW-536 Water Apr 1988 STW-538 Water June.1988 H-3 Sr-89 Sr-90 Cr-51 Co-60 Zn-65 Ru-106 Cs-134 Cs-137 NDf ND ND 6.0+/-0.0 ND 3.3+/-1.2 5.3+/-1.2 63.31.3 7.71.2 8.3+/-1.2 6483t155 14.7+/-1.3 20.0+/-2.0 331.7+/-13.0 16.0+/-2.0 107.7t11.4 191.3+/-11.0 18.3t4.6 26.3+/-1.2 46.0+/-11.0 6.4+/-1.0 5.6+/-0.8 6.0+/-6.0 57.0+/-5.0 5.0+/-5.0 5.0+/-1.5 50.0+/-5.0 7.0+/-5.0 7.0+/-5.0 27.0-65.0 4.7-8.1 4.2-7.0 0.0-16.4 48.3-65.7 0.0-13.7 2.4-7.6 41.3-58.7 0.0-15.7 0.0-15.7 6202+/-620 5128-7276 20.0+/-5.0 11.3-28.7 20.0+/-1.5 17.4-22.6 302.0+/-30.0 15.0+/-5.0 101.0t10.0 195.0+/-20.0 20.0+/-5.0 25.0+/-5.0 250.0-354.0 6.3-23.7 83.7-118.3 160.4-229.6 11.3-28.7 16.3-33.7 STW-539 Water June 1988 H-3 5586+/-92 5565+/-557 4600-6530 STM-541 Milk June 1988 STW-542 Water July 1988 STF-543 Food July 1988 Sr-89 Sr-90 1-131 Cs-137 K

Gr. alpha Gr. beta Sr-89 Sr-90 1-131 Cs-137 K

33.7+/-11.4 55.3t5.8 103.7t3.1 52.7t3.1 1587t23 8.7t4.2 5.3tl.2 ND ND 115.0+/-5.3 52.7t6.4 1190+/-66 40.0+/-5.0 60.0t3.0 94.0+/-9.0 51.0t5.0 1600+/-80 15.0+/-5.0 4.0+/-5.0 33.0t5.0 34.0+/-2.0 107.0+/-11.0 49.0+/-5.0 1240t62 31.3-48.7 54.8-65.2 78.4-109.6 42.3-59.7 1461-1739 6.3-23.7 0.0-12.7 24.3-41.7 30.5-37.5 88.0-126.0 40.3-57.7 1133-1347 A-10

Table A-1.

(continued)

Concentration in pCi/lb Lab Sample Date TIML Result EPA Resultd Code Type Collected Analysis

+/-2 cc 1s, N=1 Control Limits STW-544 Water Aug 1988 STW-545 Water Aug 1988 STW-546 Water

'Aug 1988 STAF-547 Air Filter Aug 1988 STW-548 Water Sep 1988 STW-549 Water Sep 1988 STW-550 Water Oct 1988 STW-551 Water Oct 1988 1-131 Pu-239 Uranjum

-Gr. alpha Gr. beta Sr-90 Cs-137 Ra-226 Ra-228 Gr. alpha Gr. beta Cr-51 CP-60 Zn-65 Ru-106 Cs-134 Cs-137 H-3 80.0t0.0 11.0+/-0.2 6.0+/-0.0 8.0+/-0.0 26.3+/-1.2

8. 0+/-2.0 13.0+/-2.0 9.3+/-0.5 5.8+/-0.4

7. 0+/-2.0 11.3+/-1.2 252.014.0 26.0+/-2.0 158.3+/-10.2 153.0+/-9.2 28.7+/-5.0 16.3+/-1.2 2333t127 76.0+/-8.0 10.2+/-1.0

6. 06.0 8.0+/-5.0 29.0+/-5.0 8.0+/-1.5 12.0t5.0 8.4t2.6 5.4+/-1.6 8.0+/-5.0 10.0+/-5.0 251.0+/-25.0 25.0+/-5.0 151.0+/-15.0 152.0+/-15.0 25.0+/-5.0 15.0+/-5.0 2316+/-350 62.1-89.9 8.5-11.9 0.0-16.4 0.0-16.7 20.3-37.7 5.4-10.6 3.3-20.7 6.2-10.6 4.0-6.8 0.0-16.7 1.3-18.7 207.7-294.3 16.3-33.7 125.0-177.0 126.0-178.0 16.3-33.7 6.3-23.7 1710-2927 STW-552 Water 553 (Blind)

Sample A Sample B Oct 1988 Gr. alpha Ra-226 Ra-228 Uranium Gr. beta Sr-89.

Sr-90 Cs-134 Cs-137 38.3+/-8.0 4.5+/-0.5 4.4+/-0.6

4.

71.2 51.3t3.0 3.7+/-1.2 10.7+/-1.2 15.3+/-2.3 16.7+/-1.2 41.0+/-10.0 5.0+/-0.8 5.2+/-0.8 5.0+/-6.0 54.0+/-5.0 11.0+/-5.0 10.0+/-1.5 15.0+/-5.0

15. 05.0 23.7-58.3 3.6-6.4 3.6-6.4 0.0-15.4 45.3-62.7 2.3-19.7 7.4-12.6 6.3-23.7 6.3-23.7 A-11

Table A-1.

(continued)

Concentration in pCi/lb Lab Code Sample Type STM-554 Milk Date Collected Oct 1988 STU-555 Urine Nov 1988 STW-556 Water Nov 1988 STW-557 Water Dec 1988

,STW-559 Water

.an

.1989 STW-560 Water Jan 1989 STW-561 Water Jan 1989 STW-562 Water Feb 1989 Analysis Sr-89 Sr-90 1-131 Cs-137 K

H-3 Gr. alpha Gr. beta 1-131 Sr-89 Sr-90 Pu-239 Gr. alpha Gr. beta Cr-51 Co-60 Zn-65 Ru-106 Cs-134 Cs-137 TIML Result

+/-22c 40.3+/-7.0

51. 02.0 94.0+/-3.4 45.0+/-4.0 1500+/-45 3030+/-209 9.0+/-3.5 9.7+/-1.2 108.7t3.0 40.0t8.7 24.3t3.1 5.8+/-1.1 7.3+/-1.2 5.3t1.2 245t46 10.0+/-2.0 170+/-10 181t7.6 9.7t3.0 11.7+/-1.2 1s, N=1 40.0+/-5.0 60.0+/-3.0 91.0+/-9.0 50.0+/-5.0 1600t80 3025+/-359 9.0+/-5.0 9.0+/-5.0 115.0+/-12.0 40.0+/-5.0 25.0+/-1.5, 4.2+/-0.4 8.0+/-5.0 4.0+/-5.0 235t24 10.0+/-5.0 159+/-16 178+/-18 10.0+/-5.0 10.0+/-5.0 EPA Resultd.

Control Limits 31.3-48.7 54.8-65.2 75.4-106.6 41.3-58.7 1461-1739 2403-3647 0.3-17.7 0.3-17.7 94.2-135.8 31.3-48.7 22.4-27.6 3.5-4.9 0.0-16.7 0.0-12.7 193.4-276.6 1.3-18.7 139.2-186.7 146.8-209.2 1.3-18.7 1.3-18.7 A-12

Table A-1., (continued)

Concentration in pCi/lb Lab Sample Date TIML Result EPA Resultd Code Type Collected Analysis

+/-2 c 1s, N=1 Control Limits STW-563 Water STW-564 Water STW-565 Water STW-566 Water STW-567 Air Filter STW-568 Water 569 (Blind)

Feb 1989 Feb 1989 Mar 1989 Mar 1989 Mar 1989 1-131 H-3 Ra-226 Ra-228 U

Gr. alpha Gr. beta Sr-90 Cs-137 109.0+/-4.0 2820+/-20 4.2+/-0.3' 1.9+/-1.0 5.0+/-0.0 21.7+/-1.2 68.3+/-4.2 20.0+/-2.0 21.3+/-1.2 106.011.0 86.9-125.1 2754+/-356 2137-3371 4.9+/-0.7 1.7+/-0.3 5.0+/-6.0 21.0+/-5.0 62.0+/-5.0 20.0+/-1.5 20.0+/-5.0 3.7-6.1 1.2-2.2 0.0-15.4 12.3-29.7 53.3-70.7 17.4-22.6 11.3-28.7 Apr 1989 Sample A Sample B STW-570 Milk Apr 1989 Gr. alpha Ra-226 Ra-228 U

Gr. beta Sr-89 Sr-90 Cs-134 Cs-137 Sr-89 Sr-90 Cs-137 K-40 22.7+/-2.3 3.6+/-0.6 2.6+/-1.0 3.0+/-0.0 52.3+/-6.1 9.3+/-5.4 7.0+/-0.0 21.0+/-5.2 23.0+/-2.0 26.0+/-10.0 45.7+/-4.2 54.0+/-6.9 1521+/-208 29.0+/-7.0 3.5+/-0.5 3.6+/-0.5 3.0+/-6.0 57.0+/-5.0

8. 05.0 8.0+/-1.5 20.0+/-5.0 20.0+/-5.0 39.0+/-5.0 55.0+/-3.0 50.0+/-5.0 1600+/-80 16.9-41.2 2.6-4.4 2.7-4.5 0.0-13.4 43.3-65.7 0.0-16.7 5.4-10.6 11.3-28.7 11.3-28.7 30.3-47.7 49.8-60.2 41.3-58.7 1461-1739 A-13

Table A-1.

(continued)

Concentration in pCi/lb Lab Sample

-Date TIML Result EPA Resultd Code Type Collected Analysis i2c 1s, N=1 Control Limits STW-571 Water.

May 1989 Sr-89 40.7 6.0t5.0 0.0-14.7 Sr-90 5.0+/-1.0 6.0+/-1.5 3.4-8.6 STW-572 Water May 1989 Gr. alpha 24.0+/-2.0 30.0+/-8.0 16.1-43.9 Gr. beta 49.3+/-15.6 50.0+/-5.0 41.3-58.7 STW-573 Water Jun 1989 Ba-133 50.7tl..2 49.0+/-5.0.

40.3-57.7 Co-60 31.3+/-2.3 31.0+/-5.0 22.3-39.7 Zn-65 167+/-10 1651l7 135.6-194.4 Ru-106 123+/-9.2 128+/-13 105.5-150.5 Cs-134 40.3+/-1.2 39t5 30.3-47.7 Cs-137 22.3+/-1.2 20t5 11.3-28.7 STW-574 Water Jun 1989 H-3 4513+/-136 4503+/-450 3724-5282 STW-575 Water Jul 1989 Ra-226 16.8+/-3.1 17.7+/-2.7 13.0-22.4 Ra-228 13.8t3.7 18.3+/-2.7 13.6-23.0 STW-576 Water Jul 1989 U

40.3+/-1.2 41.0+/-6.0 30.6-51.4 STW-577 Water Aug 1989 1-131 84.7+/-5.8 83.0+/-8.0 69.1-96.9 STW-579 Air Aug 1989 Gr. alpha 6.0+/-0.0 6.0+/-5.0 0.0-14.7 Filter Cs-137 10.3+/-2.3 10.0+/-5.0 1.3-18.7 STW-580 Water Sep 1989 Sr-89 14.71.2 14.0+/-5.0 5.3-22.7 Sr-90 9.7+/-1.2 10.0+/-1.5 7.4-12.6 STW-581 Water Sep 1989 Gr. alpha 5.0+/-0.0 4.0+/-5.0 0.0-12.7 Gr. Beta 8.7+/-2.3 6.0+/-5.0 0.0-14.7 A-14

Table A-1.

(continued)

Concentration in pCi/lb Lab Sample Date TIML Result EPA Resultd Code Type Collected Analysis

+/-2oc 1s, N=1 Control Limits STW-583 Water Oct 1989 Ba-133 60.3+/-10.0 59.0+/-6.0 48.6-69.4 Co-60 29.0+4.0 30.0+/-5.0 21.3-38.7 Zn-65 132.3+6.0 129.0+/-13.0 106.5-151.5 Ru-106 155.3+6.1 161.0+/-16.0 133.3-188.7 Cs-134 30.7+6.1 29.0+/-5.0 20.3-37.7 Cs-137 66.3+4.6 59.0+/-5.0 50.3-67.7 STW-584 Water Oct 1989 H-3 3407+/-150

.3496+/-364 2866-4126 STW-585 Water Oct 1989 586 (Blind)

Sample A Gr. Alpha 41.7+/-9.4 49.0+/-12.0 28.2-69.8 Ra-226 7.9+/-0.4 8.4+/-1.3 6.2-10.6 Ra-228 4.4+/-0.8 4.1+/-0.6 3.1-5.1 U

12.0+/-0.0 12.0+/-6.0 1.6-22.4 Sample B Gr. Beta 31.7+/-2.3 32.0+/-5.0 23.3-40.7 Sr-89 13.3+/-4.2 15.0+/-5.0 6.3-23.7 Sr-90 7.0+/-2.0 7.0+/-3.0 4.4-9.6 Cs-134 5.0+/-0.0 5.0+/-5.0 0.0-13.7 Cs-137 7.0+/-0.0 5.0+/-5.0 0.0-13.7 STW-587 Water Nov 1989 Ra-226 7.9+/-0.4 8.7+1.3 6.4-11.0 Ra-228 8.9+/-1.2 9.3+/-1.2 6.9-11.7 STW-588 Water Nov 1989 U

15.0+/-0.09 15.0+/-6.0 4.6-25.4 a Results obtained-bydTeledyne Isotopes Midwest Laboratory as a participant in the environmental sample crosscheck program operated by the Intercomparison and Cali bration Section, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, U.S.

Environmental Protection Agency (EPA),

Las Vegas, Nevada.

b All results are in the pCi/l, except for elemental potassium (K) data in milk, which are in mg/l; air filter samples, which are in pCi/filter; and food, which is in mg/kg.

c Unless otherwise indicated, the TIML resultsare given as the mean +/- 2 standard deviations for three determinations.

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

e NA = Not analyzed.

f ND = No data. Not analyzed due to relocation of the lab.

9 Sample was analyzed but the results not submitted to EPA because deadline was missed.

A-15

Table A-2. Crosscheck program results, thermoluminescent dosimeters (TLDs).

mR Teledyne Average 12 ad Lab TLD Result Known (all Code Type Measurement

+/-20 a Valuec part ic ipants) 2nd International Intercomparisonb 115-2 CaF 2 :Mn Field Bulb Lab 3rd International Intercomparisone 115-3 CaF 2 :Mn Field Bulb Lab 4th International Intercomparisonf 115-4 CaF 2 :Mn Field Bulb Lab (Low)

Lab (High) 5th International Intercomparison9 115-5A CaF 2 :Mn Field Bulb Lab at beginning Lab at end 17.0+/-1.9 20.8+/-4.1

30. 7+/-3. 2 89.6+/-6.4

14. 1+/-1.1

9.

3+/-1. 3 40.4+/-1.4 31.4+/-1.8

77. 4+/-5.8

96. 6+/-5.8 17.1 21.3 34.9+/-4.8 91.7+/-14.6

14. 1+/-1.4

12. 2+/-2.4 45.8+/-9.2 30.0+/-6.0

75. 2+/-7. 6 88.4+/-8.8 16.4+/-7.7 18.8+/-7.6 31.513.0 86.2+/-24.0 16.0+/-9.0 12.0+/-7. 6 43.9+/-13.2 30.2+/-14.6 75.8+/-40.4 90.7+/-31.2 I-.

Table A-2.

(Continued) mR Teledyne Average +/-20 d Lab TLD Result Known (all Code Type Measurement

+/-2,a Valuec participants)

LiF-100 Chips Field Lab at beginning Lab at the end 7th International Intercomparisonh 115-7A LiF-100 Field Chips Lab (Co-60)

Lab (Cs-137)

CaF 2 :Mn Bulbs CaSO 4 :Dy Cards Field Lab (Co-60)

Lab (Cs-137)

Field Lab (Co-60)

Lab (Cs-137

30. 3+/-4.8

81. 1+/-7.4 85.4+/-11.7 75.4+/-2.6 80.0+/-3.5

66. 6+/-2. 5

71. 5+/-2. 6 84.8+/-6.4 78.8+/-1. 6 76.8+/-2. 7 82.5+/-3.7 79.0+/-3.2 30.0+/-6.0

75. 2+/-7. 6 88.4+/-8.8 75.8+/-6.0 79.9+/-4.0 75.0+/-3.8 75.8+/-6.0 79.9+/-4.0 75.0+/-3.8 75.8+/-6.0 79.9+/-4.0 75.0+/-3.8

30. 2+/-14.6 75.8+/-40.4

90. 7+/-31. 2

75. 1+/-29.8 77.9127.6 73.0+/-22. 2 75.1+/-29.8 77.9+/-27.6 73.0+/-22.2 75.1+/-29.8 77.9+/-27.6 73.0+/-22. 2 115-5B

-4 115-7B 115-7C

le A-2.

(Continued) mR Teledyne Average +/-2a d Lab TLD Result Known (all Code Type Measurement 120a Valuec participants) 8th International Intercomparisoni 115-8A LiF-100 Field Site 1 29.5+/-1.4 29.711.5 28.9+/-12.4 Chips Field Site 2 11.3+/-0.8 10.4t0.5 10.1t9.06 Lab (Cs-137) 13.7+/-0.9 17.2+/-0.9 16.2+/-6.8 115-8B CaF 2:Mn Field Site 1 32.3+/-1.2 29.7t1.5 28.9+/-12.4 Bulbs Field Site 2 9.0+/-1.0 10.4+/-0.5 10.1+/-9.0 Lab (Cs-137) 15.8+/-0.9 17.2+/-0.9 16.2t6.8 115-8C CaSO 4 :Dy Field Site 1 32.3+/-0.7 29.7+/-l.5 28.9t12.4 Cards Field Site 2 10.6+/-0.6 10.4t0.5 10.1t9.0 Lab (Cs-137 18.1+/-0.8 17.2+/-0.9 16.2t6.8 Teledyne TestingJ 89-1 LiF-100 Lab 21.040.4 22.4 Chips 89-2 Teledyne Lab 20.9+/-1.0 20.3 CaSO 4 :Dy Cards a

b c

d Lab result given is the mean 12 standard deviations of three determinations.

Second International Intercomparison of Environmental Dosimeters conducted in April of 1976 by the Health and Safety Laboratory (GASL),

New York, New York, and the School of Public Health of the Uni versity of Texas, Houston, Texas.

Value determined by sponsor of the intercomparison using continously operated pressurized ion chamber.

Mean +/-2 standard deviations of results obtained by all laboratories participating in the program.

I-.

A-2.

(continued) mR Teledyne Average +20d Lab TLD Result Known (all Code Type Measurement

+/-20 a Valuec participants)

Footnotes continued e Third International Intercomparison of Environmental Dosimeters conducted in summer of 1977 by Oak Ridge National Laboratory and the School of Public Health of the University of Texas, Houston,.Texas.

f Fourth International Intercomparison of Environmental Dosimeters conducted in summer of 1979 by the School of Public Health of the University of Texas, Houston, Texas.

9 Fifth International Intercomparison of Environmental Dosimeter conducted in fall of 1980 at Idaho Falls, Idaho and sponsored by the School of Public Health of the University of Texas, Houston, Texas and Environmental Measurements Laboratory, New York, New York, U.S. Department of Energy.

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

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.

Chips were submitted in September, 1989 and cards were submitted in November, 1989 to Teledyne Isotopes, Inc., Westwood, NJ for irradiation.

Table A-3.

In-house spiked samples.

Concentration in pCi/l Analysis Feb. 1986 Sr-89 Sr-90 1-131 Cs-134 Cs-137 Mar. 1986 Sr-89 Sr-90 Apr. 1986 1-131 Co-60 Cs-134 Cs-137 Apr. 1986 1-131 Cs-134 Cs-137 May 1986 Gross alpha QC-MI-6 QC-W-14 QC-W-15 QC-MI-7 SPW -1 QC-W-16 QC-MI-9 SPW-2 SPW-3 QC-W-18 QC-W-19 Milk Water Water Milk Water Water Milk Water Water Water Water TIML Result n=3 6.0+/-1.9 14.2+/-1.7 34.2+/-3.8 32.0+/-1.8 35.8+/-2.1

1.

6+/-0.4 2.4+/-0.2 44.9+/-2.4

10. 6+/-1. 7 30.2+/-2.4 21.9+/-1.9

39. 7+/-3.3 28.7+/-2.8 21.2+/-2.8 15.8+/-1.8 16.2+/-0.7 38.4+/-3.5

<1.0

12. 6+/-1.8 38.9+/-7.0 33.0+/-3.4 38.5+/-2.8 16.8+/-1..8

17. 7+/-0.8 34.7+/-5.6

51. 1+/-7.0 13.6+/-4.1 6.4+/-1.6 Known Activity 6.4+/-3.0 12.9+/-2.0

35. 2+/-3.5

27. 3+/-5.0 35.0+/-5.0

1.

6+/-1.0 2.4+/-2.0

41. 5+/-7.0

12. 1+/-5.0 25.8+/-8.0 19.9+/-5.0 41.5+/-7.0 25.8+/-8.0

19. 9+/-5.0 18.0+/-5.0

16. 9+/-2.5 30.2+/-5.0 0.0 13.3+/-3.0 34.8+/-7.0 36.1+/-5.0 39.0+/-5.0 18.0+/-5.0 18.0+/-5.0

31. 3+/-5.0 43.3+/-8.0 15.6+/-3.5

6.

2+/-2.0 Expected Precision 1s, n=3a 8.7 5.2 10.4 8.7 8.7 7.1 4.2 10.6 7.1l 7.1lb 7.1b 10.4 8.7 8.7 8c 8.7 8.7 7.1lb 4.2b 10.4 8.7 8.7 Sc Sc 8.7 8.7 7.lb 4.2b A-20 Date Collected Lab Code June 1986 June 1986 June 1986 June 1986 Sep. 1986 Sep. 1986 Sample Type Gross alpha Gross beta Sr-89 Sr-90 1-131 Cs-134 Cs-137 Gross.alpha Gross alpha Cs-134 Cs-137 Sr-89 Sr-90

Table A-3.

In-house spiked samples (continued)

Concentration in pCi/1 Date Collected Analysis TIMLResult..,Known Expected n=3 Activity Precision is, n=3a QC-W-21 Water QC-MI-11 Milk QC-W-20 QC-W-22 QC-W-23 Water Water Water QC-MI-12 Milk QC-MI-13 Milk QC-W-24 QC-W-25 Water Water QC-MI-14 Milk QC-W-26 QC-W-27 QC-W-28 Water Water Water Oct. 1986 Oct 1986 Nov.

1986 Dec.

1986 Jan. 1987 Jan. 1987 Jan 1987 Mar 1987 Apr 1987 Apr 1987 Jun 1987 Jun 1987 Jun 1987 C -60 Cs-134 Cs-137 Sr-89 H-3 Gross alpha Gross beta 1-131 1-131 Cs-137 Sr-89 Sr-90 1-131 Cs-134 Cs-137 Sr-89 Sr-90 1-131 1-131 Cs-134 Cs-137 H-3 Co-60 Cs-134 Cs-137 Gr. alpha Gr. beta Gr. alpha Gr. beta

.19.2+/-2.2 31.7+/-5.2 23.8+/-1.0 12.3+/-1.8 3855+/-180 9.8+/-1.4 21.7+/-2.0 29.8+/-2.5 36.5+/-1.3 32.6+/-4.2 10.4+/-2.1 14.6+/-1.6 49.5+/-1.2 41.6 33.3+/-0.6 24.7+/-3.6 23.9+/-3.8 28.0+/-1.9 25.0+/-2.2 42.1 34.2+/-2.0 3422+/-100 24.81.4 42.0 21.2+/-0.5 8.5t1.9 22.6+/-1.9

8.

7+/-1.3 12.2+/-5.2 18.5+/-3.0 25.6+/-8.0 21.6+/-5.0 14.3+/-3.0 8.7 8.7 8.7 8.7 3960+/-350 520b 11.2+/-4.0 23.8+/-5.0 8.7 8.7 27.9+/-3.0 10.4 32.6+/-5.0 10.4 27.4t8.0 8.7 12.2+/-4.0 12.6t3.0 54.9+/-8.0 0.0 27.4+/-8.0 25.9+/-5.0 22.8t8.0 8.7 5.2 10.4 8.7 8.7 8.7 5.2 29.3+/-5.0 10.6 23.9+/-5.0 0.0 27.2+/-7.0 3362+/-300 26.5+/-7.0 0.0 21.6+/-7.0 10.1+/-4.0 21.2+/-5.0 10.1+/-4.0 9.4t3.0 10.4 8.7 8.7 520 8.7 8.7 8.7 8.7 8.7 8.7 8.7 A-21

..Lab Code Sample Type

In-house spiked samples (continued)

Concentration in pCi/l Lab Sample Date TIML Result Known Expected Code Type

-Collected Analysis n=3 Activity Precision is, n=3a QC-W-29 Water QC-MI-15 Milk QC-W-30 QC-W-31 QC-W-32 QC-W-33 QC-W-34 Water Water Water Water Water QC-MI-16 Milk QC-MI-17 Milk QC-W-35 QC-W-36 QC-W-37 Water Water Water QC-MI-18 Milk Jun 1987 Jul 1987 Sep 1987 Oct 1987 Dec 1987 Dec 1987 Dec 1987 Feb 1988 Feb 1988 Feb 1988 Feb 1988 Mar 1988 Mar 1988 Gr. alpha Gr. beta Sr-90 1-131 Cs-134 Cs-137 Sr-89 Sr-90 H-3 Gr. alpha Gr. beta Gr. alpha Gr. beta Gr. alpha Gr. beta Sr-89 Sr-90 1-131 Cs-134 Cs-137 1-131 1-131 1-131 Sr-89 Sr-90

.1-131 Cs-134 Cs-137 16.4+/-1.3 15.9+/-4.0 19.4+/-1.6 43.5+/-0.7 17.9+/-2.2 25.4+/-1.8 17.5+/-3.0 18.4+/-2.2 2053+/-939 8.6+/-1.0 15.2+/-0.1 7.7+/-1.4 10.9+/-1.0 4.0+/-0.9 9.4+/-0.9 31.8+/-4.7 25.5+/-2.7 26.4+/-0.5 23.8+/-2.3 26.5+/-0.8 10.6+/-1.2 9.7+/-1.1 10.5+/-1.3 17.1+/-2.0 18.7+/-0.9 33.2+/-2.3 31.3+/-2.1 29.9+/-1.4 18.9+/-5.0 11.8+/-4.0 18.8+/-3.5 45.3+/-7.0 16.0+/-5.3 22.7+/-5.0 14.3+/-5.0 17.5+/-2.2 2059+/-306 10.1+/-5.0 13.1+/-3.0 10.1+/-5.0 7.9+/-3.0 5.1+/-3.0 7.9+/-3.0 31.7+/-6.0 27.8+/-3.5 23.2+/-5.0 24.2+/-6.0 25.1+/-6.0 8.7 8.7 5.2 10.4 8.7 8.7 8.7 5.2 520 8.7 8.7 8.7 8.7 8.7 8.7 8.7 5.2 10.4 8.7 8.7 14.3+/-1.6 10.4 11.6+/-1.1 10.4 11.6+/-1.0 10.4 19.8+/-8.0 17.3+/-5.0 26.7+/-5.0 30.2+/-5.0 26.2+/-5.0 8.7 5.2 10.4 8.7 8.7 A-22 Tabl e A-3.

In-house spiked samples (continued)

Concentration in pCi/l Lab Sample Date TIML Result Known Expected

.Code

.Type

.-Collected Analysis n=3

.Activity Precision is, n=3a QC-W-38 QC-W-39 QC-W-40 QC-W-41 Water Water Water Water QC-MI-19 Milk QC-W-42 QC-W-43 QC-W-44 QC-W-45 Water Water Water Water QC-MI-20 Milk QC-W-46 Water QC-MI-21 Milk Apr 1988 Apr 1988 Apr 1988 Jun 1988 Jul 1988 Sep 1988 Oct 1988 Oct 1988 Oct 1988 Oct 1988 Dec 1988 Jan 1989 1-131 H-3 Co-60 Cs-134 Cs-137 Gr. alpha Gr. beta Sr-89 Sr-90 1-131 Cs-137 Sr-89 Sr-90 Co-60 Cs-134 Cs-137 1-131 H-3 1-131 Cs-134 Cs-137 Gr. alpha Gr. beta Sr-89 Sr-90 1-131 Cs-134 Cs-137 17.1+/-1.1 4439+/-31 23.7+/-0.5

.25.4+/-2.6 26.6+/-2.3 12.3+/-0.4 22.6+/-1.0 15.1+/-1.6 18.0+/-0.6 88.4+/-4.9 22.7+/-0.8 48.5+/-3.3 10.9+/-1.0

.20.9+/-3.2 38.7+/-1.6 19.0+/-2.4 22.2+/-0.6 4109+/-43 59.8+/-0.9 49.6+/-1.8 25.8+/-4.6 11.5+/-2.3 26.5+/-2.0 25.5+/-10.3 28.3+/-3.2 540+/-13 24.5+/-2.6 24.0+/-0.6 14.2+/-5.0 10.4 4176+/-500 26.1+/-4.0 29.2+/-4.5 26.2+/-4.0 13.1+/-5.0 20.1+/-5.0 16.4+/-5.0 18.3+/-5.0 86.6+/-8.0 20.8+/-6.0 50.8+/-8.0 11.4+/-3.5 21.4+/-3.5 38.0+/-6.0 21.0+/-3.5 23.3+/-3.5 10.4 4153+/-500 60.6+/-9.0 48.6+/-7.5

24. 7+/-4.0 15.2+/-5.0 25.7+/-5.0 34.0+/-10.0 27.1+/-3.0 550+/-20 22.6+/-5.5 20.5+/-5.0 A-23 724 8.7 8.7 8.7 8.7 8.7 8.7 5.2 10.4 8.7 8.7 5.2 8.7 8.7 8.7 724 10.4 8.7 8.7 8.7 8.7 8.7 5.2 10.4 8.7 8.7 Table A-3.

In-house spiked samples (continued)

Concentration in pCi/1 Lab Sample Date TIML Result Known Expected Code Type Collected Analysis n=3 Activity Precision is, n=3a QC-W-47 QC-MI-22 QC-W-48 QC-W-49 QC-W-50 QC-W-51 QC-MI-23 Water Milk Water Water Water Water Milk QC-MI-24 Milk QC-W'52 QC-W-53 QC-W-54

,Water Water Water Mar 1989 Apr 1989 Apr 1989 Apr 1989 Apr 1989 Jun 1989 Jul 1989 Aug 1989 Sep 1989 Sep 1989 Sep 1989 Sr-89 Sr-90 1-131 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 1-131 H-3 Gr. alpha Gr. beta Sr-89 Sr-90 1-131 Cs-134 Cs-137 Sr-89 Sr-90 1-131 1-131 Sr-89 Sr-90 15.2+/-3.8 16.4+/-1.7 36.3+/-1.1 20.8+/-2.8 22.2+/-2.4 23.5+/-2.0 24.2+/-1.1 23.6+/-1.2 37.2+/-3.7 3011+/-59 13.0+/-1.8 26.0+/-1.2 19.4+/-6.5 27.6+/-3.5 46.8+/-3.2 27.4+/-1.8 24.1+/-1.8 25.4+/-2.7 46.0+/-1.1 9.6+/-0.3 19.0+/-0.2 25.8+/-4.6 26.5+/-5.3 16.1+/-5.0 16.9+/-3.0 37.2+/-5.0 20.7+/-8.0 20.4+/-8.0 25.1+/-8.0 25.9+/-8.0 23.0+/-8.0 8.7 5.2 10.4 8.7 8.7 8.7 8.7 8.7 37.2+/-5.0 10.4 3089+/-500 724 15.0+/-5.0 8.7 25.5+/-8.0 8.7 22.0+/-10.0 8.7 28.6+/-3.0 5.2 43.4+/-5.0 10.4 28.3+/-6.0 8.7 20.8+/-6.0 8.7 27.2+/-10.0 8.7 47.8+/-9.6 8.3 9.7+/-1.9 10.4 20.9+/-4.2 10.4 24.7+/-4.0 29.7+/-5.0 8.7 5.2 a n=3 unless noted otherwise.

b n=2.

c n=1.

A-24 Table A-3.

In-house spiked samples (continued)

Concentration in pCi/l Lab Sample Date TIML Result Known Expected Code Type Collected Analysis n=3 Activity Precision 1s, n=3a QC-MI-25 Milk Oct 1989 1-131 70.0+/-3.3 73.5+/-20.0 10.4 Cs-134 22.1+/-2.6 22.6+/-8.0 8.7 Cs-137 29.4+/-1.5 27.5+/-8.0 8.7 QC-W-55 Water Oct 1989 1-131 33.3+/-1.3 35.3+/-10.0 10.4 QC-W-56 Water Oct 1989 Co-60 15.2+/-0.9 17.4+/-5.0 8.7 Cs-134 22.1+/-4.4 18.9+/-8.0 8.7 Cs-137 27.2+/-1.2 22.9+/-8.0 8.7 QC-W-57 Water Oct 1989 H-3 3334+/-22 3379+/-500 724 QC-W-58 Water Nov 1989 Sr-89 10.9+/-1. 4d 11.1+/-1.

0d 8.7 Sr-90 10.4+/- 1. 0d 10.3+/-1.

0d 5.2 QC-W-59 Water Nov 1989 Sr-89 10 1.0+/-6. 0d 104.1+/-10. 5d 17.5 Sr-90 98.0+/-3.0d 9 5.0+/-10.0d 17.0 QC-W-60 Water Dec 1989 Gr. alpha 10.8+/-1.1 10.6+/-4.0 8.7 Gr. beta.

11.6+/-0.5 11.4+/-4.0 8.7 a

b c

d n=3 unless noted otherwise.

n=2.

n=1.

Concentration in pCi/m1 A-25 Table A-3.

Table A-4.

In-house "blank" samples.

Concentration in pCi/1 Acceptance Lab Sample Date Results Criteria Code Type Collected Analysis (4.66a )

(4.66a )

D.I. Water D.I. Water D.I. Water D.I. Water

.SPW-2265.D.:L.Water BL-6 BL-7 BL-8 BL-9 SPW-3185 SPS -3292 D.I.

D.I.

D1.

Water Water Water Water Water Mil k SPW-3554 D.I. Water SPS-3555 Milk SPS-3731 Milk Nov. 1985 Nov.

Nov.

1985 1985 BL-1 BL-2 BL-3 BL-5 Gross alpha Gross beta Cs-137.(gamma)

Sr-89 Sr-90 Ra-226 Ra-228 Gross alpha Gross beta Sr-89 Sr-90 1-131 Cs-137 (gamma)

Gross alpha Gross alpha Gross alpha Gross alpha Ra-226 Ra-228 1-131 Cs-134 Cs-137 H-3 Gross beta Sr-89 Sr-90 Cs-134 Cs-137 A-26 Nov. 1985 Apr.

1985 Apr. 1986 Apr. 1986 June 1986 June 1986 Jan 1987 Jan 1987 Feb 1987 Feb 1987 Mar 1987

<0.4

'<1.9

<0.5

<0.6

<0.4

<0.6

<2.2

<0.2

<0.4

<0.2

<7.4

<0.4

<0.3

<0.1

<0.9

<0. 1

<6. 2

<6.4

<180

<2.6

<0.6

1. 9+0.4a

<2. 2

<2. 5

<1

<4

<10

<5

<1

<4

<5

<1

<10

<1

<10

<300

<4

<5

<1

<10

<10 a Low level (1 - 5 pCi/1) of Sr-90 concentration in milk is not unusual.

Table A-4.

In-house "blank" samples (continued).

Concentration in pCi/l Acceptance Lab Sample Date Results Criteria Code Type Colected Analysis (4.66a )

(4.66d )

SPS-3732 D.I. Water SPS-4023 Milk SPS-4203 D.I. Water SPS-4204 SPS-4390 Milk Mil k SPS-4391 SPW-4627 D.I.

Water SPS-4628 SPS -4847 Milk Milk Mar 1987 May 1987 May 1987 May 1987 Jun 1987 Jun 1987 Aug 1987 Aug 1987 Sep 1987 Sr-89 Sr-90 1-131 Co-60 Cs-134 Cs-137 Ra-226 Ra-228 Np-237 Th-230 Th-232 U-234 U-235 U-238 1-131 Gross alpha Gross beta Sr-89 Sr-90 Cs-134 Cs-137 Sr-89 Sr-90 1-121 Co-60 Cs-137 Ra-226 Ra-228 Gross alpha Gross beta Tritium Sr-89 Sr-90 Cs-134 Cs-137 A-27

<0.9

<0.8

<0.3

<2.3

<2.2

<2.4

'0.1

<1.0

<0.04

<0.05

<0.02

<0.05

<0.03

<5

<1

<10

<1

<0. 1

<0.1

<0. 1

<0.1

<0. 1

<1

<0.7

<1.7

<0.5 2.4+/-0.6a

<4.7

<5. 2

<1

<4

<5

<1

<10

<5

<1

<10

<1

<0.4

<0.1

<3.8

<0. 1

<0.9

<0.6

<1.4

<150

<1

<4

<5

<1

<0.6 a

<4.4

<5. 3 a Low level (1 - 5 pCi/1) of Sr-90 concentration in milk is not unusual.

<10

<10 I.D..I.. -Water

In-house "blank" samples (continued).

Concentration in pCi/i Acceptance Lab Sample Date Results Criteria Code Type Collected Analysis (4.66a )

(4.66a )

SPS-4848 D.I. Water SPW-4849 D.I. Water SPW-4850 D.I. Water SPW-4859 D.I. Water SPS-5348 Milk SPW-5384 D.I. Water SPW-5385 D.I. Water SPS-5386 Mi 1 k SPW-5448 "Dead" Water

<1 Sep 1987 Sep 1987 Sep 1987 Oct 1987 Dec 1987 Dec 1987 1-131 Co-60 Cs-134 Cs-137 Sr-89 Sr-90 Th-228 Th-232 U-234 U-235 U-238 Am-241 Cm-242 Ra-226 Ra-228 Fe-55 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 1-131 Ra-226 Ra-228 Sr-89 Sr-90

<4. 1

<4.8

<4.0

<0.7

<0.04

<0.8

<0.03

<0.02

<0.06

<0.04

'0.

1

<1.0

<0. 5

<2.3

<2.5

<2.8

<2.6

<2.8

<0.2

<0.1

<1.2

<0.5

<0.4

<10

<5

<1.

<1

<2

<1

<10

<1

'1

<2

<1

<1 Nov 1987 Jan 1988 Jan 1988 Gr. alpha Gr. beta Fe-55 1-131 H-3

<0.4

<2.2

<0.3

<0. 1

<177

<1

<4

<1

<300 A-28 Tabl e A-4.

In-house "blank" samples (continued).

Concentration in pCi/1 Acceptance Lab Sample Date Results Criteria

-Code Type Collected Analysis (4.66a )

(4.66a )

SPS-5615 Milk SPS-5650 D.I. Water SPS-6090 SPW-6209 SPW-6292 SPS-6477 SPW-6478 SPW-6479 SPW-6480 SPW-6625 Milk Water Water Mil k Water Water Water Water Mar 1988 Mar 1988 Jul 1988 Jul 1988 Sep 1988 Oct 1988 Oct 1988 Oct 1988 Oct 1988 Dec 1988 Cs-134 Cs-137 1-131 Sr-89 Sr-90 Th-228 Th-230 Th-232 U-234 U-235 U-238 Am-241 Cm-242 Pu-238 Pu-240 Sr-89 Sr-90 1-131 Cs-137 Fe-55 Sr-89 Sr-90 1-131 Cs-134 Cs-137 1-131 Co-60 Cs-134 Cs-137 H-3 Gr. alpha Gr. beta

<2.4

<2.5

<0. 3

<0.4 2.4+/-0.5 a

<0.3

<0.04

<0.05

<0.03

'0.03

<0.03

<0.06

<0.01

<0.08

<0.02

<0.5 1.8+0.5a

<0.4

<0.8

<0.7

<0.2

<6. 1

<5.9

<0.2

<5. 7

<3. 7

<4. 3

<170

<0.7

<1.9

<10

<1

<5

<1

<10

<1

<10

<1

<10

<300

<1

<4 A-29 a Low level (1 - 5 pCi/l) of Sr-90-concentration in milk is not unusual.

Tabl e A-4.

In-house "blank" samples (continued).

Concentration in pCi/1 Date Collected Jan 1989 Mar 1989 Apr 1989 Apr 1989 Jun 1989 Jun 1989 Jun 1989 Aug 1989 Sep 1989 Oct 1989 Oct 1989 Nov 1989 Dec 1989 Analysis Sr-89 Sr-90 1-131 Cs-134 Cs-137 Sr-89 Sr-90 1-131 Cs-134 Cs-137 H-3 Ra-226 Ra-228 Sr-89 Sr-90 1-131 Cs-134 Cs-137 Gr. alpha Gr. beta Sr-89 Sr-90 1-131 Cs-134 Cs-137 Sr-89 Sr-90 1-131 H-3 1-131 Cs-134 Cs-137 Gr. alpha Gr. beta Results (4.66a )

<0.6 1.9+/-0.5a

<0.2

<4. 3

<4.4

<0.4

<0.6

<0.3

<5. 9

<6.2

<150

<0. 2

<0.6 SPS-6723 SPW-6877 SPS-6963 ASPW-7561 SPW-7207 SPS-7208 Acceptance Criteria (4.66a )

<5

<1

<10

<5

<1

<10

<300 Milk.

Water Milk Water Water Milk

<5

<1

<10

<0.2

<1.0

<1.4 4. 8+/-1.0a

<0.2

<6.9

<8.2

<1

<4

<5

<1

<10

<5

<1

<0.7

<0. 1

<140

<0.2

<8.6

<10

<0.4

<0.8

<1.0

<300

<1

<10

<1

<4 a Low level A-30 Lab Code

<0.6 2.1+/-0.5a

<0.3

<6. 4

<7. 2 SPW-7558 SPS-7322 SPW-7559 SPW-7560 SPW-7562 SPS-7605 SPW-7971 Sample Type

<1

<1 Water Milk Water Water Water Mi 1 k Water (1-S pCi/1) of Sr-90 concentration in milk is not unusual.

Tabl e A-4.

Revision 0, 12-29-86 ATTACHMENT B ACCEPTANCE CRITERIA FOR "SPIKED" SAMPLES LABORATORY PRECISION:

ONE 'STANDARD DEVIATION VALUES FOR VARIOUS ANALYSESa One Standard Deviation Analysis Level for Single Determination Gamma Emitters Strontium-89b Strontium-90b Potassium Gross Alpha Gross Beta Tritium Radium-226, Radium-228 Plutonium lodine-131, lodine-129b Uranium-238, Nickel-6 3b, Technetium-99b Iron-55b 5 to 100 pCi/liter or kg

>100 pCi/liter or kg 5 to 50 pCi/liter or kg

>50 pCi/liter or kg 2 to 30 pCi/liter or kg

>30 pCi/liter of kg

>0.1 g/liter or kg

<20 pCi/liter

>20 pCi/liter

<100 pCi/liter

>100 pCi/liter

<4,000 pCi/liter

>4,000 pCi/liter

<0.1 pCi/liter 0.1 pCi/liter, gram, or sample

<55 pCi/liter

>55 pCi/liter

<35 pCi/liter

>35 pCi/liter 50 to 100 pCi/liter 5 pCi/liter 5% of known value 5 pCi/liter 10% of known value 3.0 pCi/liter 10% of known value 5% of known value 5 pCi/liter 25% of known value 5 pCi/liter 5% of known value 1s = (pCi/liter) =

169.85 x (known).0 933 10% of known value 15% of known value 10% of known value 6 pCi/liter 10% of known value 6 pCi/liter 15% of known value 10 pCi/liter 10% of known value A-31 a From EPA publication, "Environmental Radioactivity Laboratory Intercompari b son Studies Program, Fiscal Year 1981-1982, EPA-600/4-81-004.

TIML limit.

TIML-8LIND-01

ADDENDUM TO APPENDIX A The following is an explanation of the reasons why certain samples were outside the Icontrol limit specified by the Environmental Protection Agency for the Interlabora tory-Comparison Program starting January 1987.

EPA Lab Code Analysis TI1L Result Control Limit Explanation STM-504 Sr-89 Sr-90 STW-511 Ra-228 STW-516 Cr-51 STF-524 K

STW-532 1-131 STW-534 Co-60

57. 0+/-4. 3

32. 0+/- 1.0

8. 1+/-1.4 80.3+/- 17.5 1010.7+/-158.5 9.0+/-2.0 63.3+/-1.3 60.3-77.7 32.4-37.6 4.6-8.0 61.3-78.7 1123.5-1336.5 6.2-8.8 41.3-58.7 Milk had high fat content which made analyses difficult.

Ad dition of errors to TIML result would put values within EPA control limits.

EPA also had the same problem in analyzing its own sample.

TIML results are usually within EPA control limits.

Analysis of the next sample was within EPA control limits.

No further action is planned.

Results in the past have been within EPA control limits and TIML will monitor the situation in the future.

Error in transferrance of data.

Correct data was 1105+/-33.

Results in the past have been within.the limits and TIML will monitor the situation in the future.

Sample recounted after 12 days.

The average result was 8.8+/-1.7 (within EPA control limits).

The sample was recounted in order to check the decay.

Results in the past have been within the limits and TIML will continue to monitor the situ ation in the future.

High level of Co-60 was due to contamination of beaker.

Beaker was discarded upon dis covery of contamination and sample was recounted.

Recount results were 53.2+/-3.6 and 50.9+/-2.4.

A-32

ADDENDUM TO APPENDIX A (continued)

EPA Lab Code Analysis TIML Result Control Limit Explanation STM-554 Sr-90 51.0+/-2.0 54.8-65.2 The cause of low result was due to very high fat content in the milk.

It should be noted that 63% of all participants failed this test.

Also, the average for all participants was 54.0 pCi/l before the Grubb and 55.8 pCi/l after the Grubb.

STW-560 Pu-239 5.8+/-1.1 3.5-4.9 The cause of high results is not known.

It is suspected that the standard was not properly calibrated by supplier and is under investigation.

New Pu-236 standard was obtained and will be used for the next test.

STW-568 Ra-228 2.6+/-1.0 2.7-4.5 The cause of low results is not known.

Next EPA crosscheck re sults were within the control limits.

No further action is planned.

STM-570 Sr-89 26.0+/-10.0 30.3-47.7 The cause of low results was Sr-90 45.7+/-4.2 49.8-60.2 falsely high recovery. due to suspected incomplete calcium removal.

Since EPA sample was used up, internal spike was pre pared and analyzed.

The results were within control limits (See table A-3, sample QC-MI-24).

No further action is planned.

A-33

Appendix B Data Reporting Conventions B-1

4 Data Reporting Conventions 1.0.

Al.1;activities. except gross alpha and gross beta, are decay corrected to collection time or the end of the collection period.

2.0. Single Measurements Each single measurement is reported as follows:

x+/- 5 where x = value of the measurement; s = 2a counting uncertainty (corresponding to the 95% confidence level).

In cases where the activity is found to be below the lower limit of detection L it J.s.;eported as

<L where L = is the lower limit of detection based on 4.660 uncertainty for a background sample.

3.0. Duplicate Analyses 3.1.

Individual results: x1 +/-s x2 s2 Reported result:

x s where x = (1/2) (xl + x2)

's = (1/2) Fs2 + sF 1

2 3.2.

Individual results: <L1

<L2 Reported result:

<L where L = lower of L1 and L2 3.3.

Individual results:

x+/- s Reported result:

x +/- s if x > L;

<L otherwise B-2

4.0.

"'Computation of

-Averages--and

'Standard Deviations 4.1 Averages and-standard deviations listed in 'the tables are computed from all of the individual measurements over the period averaged; for example, an annual standard deviation would not be the average of.quarterly standard deviations. The average i and standard deviation(s) of a set of n numbers x1, x2,.

xn are defined as follows:

-- 1 n

s

( x - _ 2 n-1 4.2 Values below the highest lower limit of detection are not included in the average.

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

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

4.5. In rounding off, the following rules are followed:

4.5.1. If the figure following those to be retained is less than 5, the figure is dropped, and the retained figures are kept unchanged. As an example, 11.443 is rounded off to 11.44.

4.5.2 If the figure following those to be retained is greater than 5, the figure is dropped, and the last retained figure is raised by 1. As an example, 11.446 is rounded off to 11.45.

4.5.3. If the figure following those to be retained is 5, and if there are no figures other than zeros beyond-*the five, the figure 5 is dropped, and the last-place figure retained is increased by one if it is an odd number or it is kept unchanged if an even number. As an example, 11.435 is rounded off to 11.44, while 11.425 is rounded off to 11.42.

8-3

.1 Appendix C Maximum Permissible Concentrations of Radioactivity in Air and Water Above Background in Unrestricted Areas C-1

P'Table C-1. Maximum permissible concentrations of radioactivity in air and water-above'natural background in unrestricted areas.a

.v~

Air Water Gross alpha Gross beta Iodine-131b 3

100 0.14 pCi/m 3 pCi/m 3 pCi/m 3 Strontium-89 Strontium-90 Cesium-137 Barium-140 lodine-131 Potassium-40c Gross alpha Gross beta Tritium 3,000 300 20,000 20,000 300 3,000 30 100 3 x 106 pCi pCI pCi pCi pCi pCi pCi pCi pCi a Taken from Code of Federal Regulations Title 10, Part 20, Table II and appro priate footnotes. Concentrations may be averaged over a period not greater b than one year.

From 10 CFR 20 but adjusted by a factor.of.700 to reduce the dose.resulting.

from the air-grass-cow-milk-child pathway.

CA natural radionuclide.

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ML113190497

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