Text

Radiation Environ Monitoring Program Rept 1989
	ML20042E811
Person / Time
Site:	Prairie Island
Issue date:	12/31/1989
From:	Huebner L; TELEDYNE ISOTOPES MIDWEST LABORATORY
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O-W TELEDYNE l

lSOTOPES MIDWEST LADOAATORY i

700 LANDWEHR ROAD NORTHS 400K,,ILLINOt8 000a2 2310 (10m 964 0700 FAX (/04 944 4517 l.

i NORTHERN STATES POWER COMPANY

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MINNEAPOLIS, MINNESOTA _.

l PRAIRIE. ISLAND NUCLEAR-GENERATING PLANT Docket No~

50-282 License No. DPR-42 '

50-306 DPR,

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 IS0 TOPES MIDWEST LABORATORY Project No. 8010 h ':

Approved by:

/A l

" 'd.G.Huebner j

General Manager 1

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28 February 1990 l.

~9005030162 900427 PDR ADOCK 05000282 l

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A.

o-LIST OF TABLES e

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Title Page 5.1 Sample Collection and Analysis Program,1989...... -..._

13-5.2 Sampl ing Locati ons......................,

15 5.3 Missed Collections and Analyses,1989 17:

5.4 Environmental Radiological Monitoring Program Summary _....-

18 5.5

'Special Well, Ground and' Surface Water Analysis 25 In addition, the following-tables are in the Appendices:

Appendix A YE*-

A-1 Interlaboratory Comparison' Program Results, 1986-1989 A-3 A-2 Interlaboratory Comparison Program Results (TLDs)

A-16

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A-3 In-house Spi ked Sampl es A-20 A-3 In-house "Bl ank" Sampl es.................... -..

A-26_

Attachment B:

Acceptance criteria for spiked samples A-31 Addendum to Appendix A:

Explanation of the Results:

A 82 2

Outside of Control Limits Appendix C C-1 Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in,

Unrestricted Areas.....................

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9 TABLE OF CONTENTS Section Page Preface 11

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Li s t of Tabl es...................... :..

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1.0 I NTR ODUCT I ON.........................

1 2.0

SUMMARY

2 3.0 RADI ATION ENVIRONMENTAL-MONITORING PROGRAM (REMP) 3 3.1 Program Design-and Data Interpretation 3

3.2 Program Description............-....-...

=4-3.3 Program Execution..,.....-.....--...-....

5 3.4 Laboratory Procedures...,..............

6L 3.5 Program Modifications..................

7 3.6 Land Use Census.....'.-...

?7 4.0 RESULTS AND DI SCUSSION,............. -.......

8 4.1 Atmospheric Nuclear Detonations-and Nuclear Accidents.........-.........-.

8 4.2 Program Findings

- 8 5.0 TABLES 12

6.0 REFERENCES

CITED................:......

27-APPENDICES A

Interlaboratory Comparison Program Results.......~.... A-1 B

Data Reporting Conventions.................. B-1 C

Maximum Permissible Concentrations of Radio-activity in Air and Water Above Natural Background in Unrestricted Areas............_..

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d PREFACE The staff of Teledyne Isotopes Midwest Laboratory was responsible for the acquisition of data presented in this report.-. Samples were' collected by members of the staff of the 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.. The report.was _ prepared by L. G. Huebner, General Manager, Teledyne I.t9 topes Midwest Laboratory.

He was ' assisted in the report preparation by other. staff members of this laboratory.

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1.0 INTRODUCTION

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This report summarizes. and interprets results of the Radiation Environmental Monitoring Program (REMP) conducted by Teledyne Isotopes Midwest-Laboratory at the Prairie Island Nuclear-Generating Plant, Red Wing, Minnesota, during-the period January - December,1989.

This -program monitors the levelt of radioactivity' in the ' air, terrestrial, and aquatic environments in order to assess the impact of the plant _ on its surroundings.

i Tabulations of the individual analyses made during the year are not included fn* this report..

These, data are included in a reference document- (Teledyne j

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Isotopes Midwest Laboratory, 1989) available at Northern States Power Company, i

I Nuclear Generation Department..

Prairie Island Nuclear Generating Plant is located on the Mississippi-River in Goodhue County, Minnesota, and operated by Northern States Power Company. The

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plant has two 550 MWc pressurized water reactors.

Unit 1 echieved initial-criticality on 1 December 1973.

Commercial operation at full power began on 3

16 December 1973.

Unit 2 achieved initial criticality on -17 December.1974.

Commercial operation at full power began on 21 December 1974.

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2.0

SUMMARY

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

Nuclear Regulatory Commission (NRC)- Technical Specifications for the Prairie Island Nuclear Generating Plant is described.- Results for 1989 are summarized-and discussed.-

Program findings show-background levels of radioactivity in the environmental samples collectedEin the vicinity ofs the Prairie Island Nuclear Generating -

Plant, with the exception of some of the additional special ground water, well water, and surface water samples.

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m 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 Prairie Island Nuclear Generating Plant is to assess the impact ~ of-the plant on_ its environment.

For this purpose, samples are collected from the air, terrestrial, and ' aquatic environments and analyzed for radioactive content.

In addition, ambient gamma -radiation levels are:

monitored by thermoluminescent dosimeters-(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 Prairie Island Plant which is based'on the indicator-control concept.

Most types of samples are collected both at indicatcr locations (nearby, doo wind, 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 the environmental samples. collected from the plant site. The plant's monitoring program includes analyses for tritium and iodine-131.

Most samples are also analyzed for gamma-emitting' isotopes with results for the following groups quantified:

zi rconi um-95, i

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

The first three gamma-emitting isotopes were selected as radiological impact. indicators i

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

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duced by a nuclear detonation. Each of the three isotopes is produced in roughly equivalent amounts by a reactor:

each constitutes about 10% of the total activity of fission products 10 days after reactor shutdown.

On the other hand,10 days after a nuclear explosion, the contributions of-zirconium-95, cerium-144, and cesium-137 to the activity of the resulting debris are in the approximate ratio 4:1:0,03 (Eisenbud,1963).

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

They were chosen as calibratinNmonitors and should l

not be considered radiological impact indicators. #

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

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

These isotopes are released in small quantities 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 f rom activation of corrosion products. - They are typical components of a nuclear power plant's effluents, but are not prodaced in significant-quantities by nuclear detonations.

Other means of distinguishing sources of environmental radiation can be I

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.

l 3.2 Program Description The sampling and analysis schedule for the environmental radiation monitoring program at Prairie Island is summarized in Table 5.1 and briefly reviewed below.

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

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

To monitor the air environment, airborne particulates are collected on i

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

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of these locations.

Filters are changed and counted weekly.

Particulate filters are analyzed for gross beta activity and charcoal filters for 4

4 iodine-131.

A monthly composite of all particulate filters is gamma-scanned on an HP Ge or Ge(L1) detector.

One of the five locations is a control- (P-1), and four. are indicator (P-2, P-3, P-4, and P-6).

As a " Lessons Learned" commitment, ambient gamma ' radiation is monitored-at thirty-two (32) locations, using(10) in an inner ring in the general.

CaSo4:Dy dosimeter - with four sensi-tive areas at each location:

ten area of the site boundary, fifteen (15), in the outer ring within 4-5. mile radius,- six (6) at special interest locations and one control location, 11.1 miles distant f rom the plant.

They are replaced and measured quarterly. Also, a complete emergency set of. TLDs for allt 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), because the milk animals may be on pasture. - All samples are analyzed for iodine-131 and gamma-emitting isotopes.

For additional monitoring of the terrestrial environment - leafy " green w

vegetables (cabbage) are collected annually from the h'ighest D/Q garden-and a control location (P-25) and analyzed for iodine-131.

Corn.is collected annually only from fields irrigated with river water and a control -location (P-25) and analyzed for gamma-emitting.1sotopes.

Also, well water is collected quarterly from four: locations and analyzed for tritium and gamma-emitting isotopes.

Additional special well water and ground water is collected monthly -from six locations and quarterly from three locations near the plant and analyzed for tritium and gamma-emitting isotopes.

River water is collected weekly at two locations, one upstream of the plant (P-5) and one downstream (P-6, Lock and Dam No. 3).

Monthlv composites are analyzed for gamma-emitting isotopes.

Quarterly compo-sites are analyzed for tritium.

Drinking water is collected weekly from the. City of Red Wing well.

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

The aquatic environment is also monitored by - semi-annual' upstream and downstream collections 6f fish, periphyton or invertebrates, and, bottom sediments.

Shoreline sediment is collected' semi-annua 11y' from one location. All samples are analyzed for gamma-emitting isotopes. -

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

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No milk data was available for location P-17 for the l

collection date 07-05-89 because milk was not available.

2 No' air particulate and 1-131 data was available for location P-3 for the collection period ending 07-24-89 l

because filter paper was not seated properly.

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No air particulate and I-131 data was available for location P-2 for the period ending 08-22-89 because - of.

pump failure.

4 No ait particulate and I-131 data was. available for location P-6 for the collection period ending 09-25-89 i

because they were lost during collection. -

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The TLD data for the second quarter of 1989, for Location -

P-13B was not available because TLD was lost in the field.

t Deviations from the program are summarized in Table 5.3.

The responsibil-ities 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 TLD holders will be investigated, replaced, or relocated which are similar to the actions that have been taken in. the past.

3.4 Laboratory Procedures All iodine-131 analyses in milk and drinking water were made by using. a sensitive radiochemical procedure which involves separation of the element by use of an ion-exchange ' resin and subsequent beta counting.

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

Levels of iodine-131 in cabbage were determined by HP Ge or Ge(L1) spectrometry.

Levels of airborne iodine-131 in' charcoal samples were measured by HP Ge or Ge(L1) spectrometry.

l Tritium levels were determined by liquid scintillation technique.

Analytical procedures used by the Teledyne -Isotopes Midwest Laboratory are specified in detail elsewhere (Teledyne Isotopes Midwest Laboratory, 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 4.aboratory of the U. S. Atomic Energy Commission (U.

S. Atomic Energy Commission, 1972).

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Teledyne Isotopes Midwest Laboratory has a comprehensive quality control /

I quality assurance program designed to assure the reliability of data elsewhere (Teledyne Isotopes Midwest Laboratory,1990) gram are presented obtained.

Details of TIML's Quality Assurance Pro The TIML Quality Assurance Program includes ' participation in Interlaboratory Comparison (Crosscheck) Programs.

Results obtained in crosscheck programs are i

presented in Appendix A.

D 3.5 Program Modifications i

During the growing season, milk producers were monitored to determinel when the' dairy animals were. on pasture or fresh. cut feed.

The frequency of milk samples was increased to semimonthly during the grazing period because animals were on pasture or fresh cut feed.

The State $f Minnesota i

detected tritium above background at a local residence near the plant site therefore additional well water and ground water sample points were. in-cluded into the program toward the end.of the year.

3.6 Land Use Census In accordance with Technical Specification 4.10, paragraph B1, a land-use census is conducted in order' to identify the location of the nearest milk animal the nearest residence, and the nearest -garden of greater. than I producing fresh leafy vegetables in each'of'the 16 meteorological 500 ft sectors within a distance of 5 miles.

This census is: conducted at least once per 12 months between the dates of May 1 and October -31.-

- New locations are added to the radiological 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.

This land use census insures the updating of thet radiation environmental monitoring program should sampling locations change within the 5. mile radius from the plant.

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

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i Census.

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

All results are summarized in Table 5.4 in a format' recommended by= the Nuclear,

.t 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

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f 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 on October 16, 1980 by the People's Republic of China.

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

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

4.2 Prograni Findings

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Results.obtained show background levels of radioactivity in the environ-j mental samples collected in the vicinity of the Prairie Island ~ Nuclear Generating Plant in 1989, with the exception of some of the additional s

i special ground water samples and well water sa'nples.

Ambient Radiation (TLD_s) l Ambient radiation was measured in the general area of site boundary, at outer ring 4 - 5 mi distant -from the Plant l,. at special interest. areas',

i and at one control location ' The means ranged from.15.7 mR/91 days-at inner _ ring locations to 17.0 mR/91' days' at outer ring locations.

The mean at special locations.was 15.2 mR/91 days and 16.7 mR/91: days at" the control location.

The_ differences are not statistically significant.

The dose rates measured at all indicator and control locations were.

1 similar to those observed in 1978-(12.1 and 15.1 mR/91 days, respec-tively); in 1979 (12.6 and 15.3 nR/91 days, respectively); in 1980 (11.2 and 13.5 mR/91 days, respectively),; in 1981 (13.0 and 14.5 mR/91 days, respectively); in 1982 (12.0 and 13.0 mR/91 days, respectively),;. in l

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1983 (13.0 and 14.9 mR/91 days, respectively); in 1984 (13.9 and '15.3 mR/91 days, respectively); in 1985 (13.9 and 15.3 mR/91 days, respec-(15.4 and 16.0 mR/91 days, respectively) and in1986 (16.6 and 17.0 mR/91 days, re tively); in 1988. 16.2 and 16.7 mR/91 days, respectively).

No plant effect-on ambient gamma radiation was indicated.

Airborne Particulates The average annual gross beta concentration in airborne particulates was-

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noarly) identical at both indicator and-control locations,(0.028 and-0.027 pC1/m3, respectively.and was slightly higher than:the levels obser ed 3

(0.024 pCi/m ),

in 1982 (0.026 pC1/m3), 1983 (0.023 p rCi/mgi/m ),1984 1985 (0.025 pC1/m3),1986 - (0.025

), and 1987 (0.024 pCi/m ).

It was slightly lower than in 1988 (0.030 pCi/m3 at both indicator-and 3

control locations)

The average of 0.025 pC1/m. for 1986 does not in-clude the results from May 19. to June 9,1986 which were influenced by the accident at Chernobyl.

A spring peak in beta activity had been observed almost. annually for many years (Wilson et al., 19 69 ).

It had been attributed to f allout of nirclides from tFei stratosphere (Gold et al.,1964).

_It was pronounced-in 1981, occurred to a lesser degree 1T1982,- end did not occur in 1983,1984,1985,1987 or 1988. _ In 1986, the spring peak could not be identified because it was overshadowed by the reld4ses of-radioactivity from Chernobyl.

The highest averages for gross beta-were for the month of January and the first quarter.

The increase of-beta activity during winter months.were also observed 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 simultaneotJsly at both indicator and control locations.

Secondly, an identical pattern was observed at: the Monticello Nuclear Generating Plant, about 100 miles distant from the Prairie Island Nuclear Generating Plant (NorthernStatesPowerCompany,1989).

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Gamma spectroscopic analysis of quarterlyE composites _ ofg air-particulate -

filters yielded similar results for indicator and ' control locations.

Bery111um-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 detection (LLD) of 0.07 pCi/m3 in all samples.

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lodine-131 results were below the detection -limit of 1.0 pC1/1' in all-sampl es.

l Cs-137 results were below the LLD level of 15 pC1/1 in all samples.

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other gams-emitting isotopes, except potassium-40, were detected in any milk samples.

This is consistent with the finding of the National Center i

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 the 1989 show. no radiological effects of the plant operation.

Drinking Water In drinking water-from the City of Red Wing well, tritium ~ activity was i

telow the LLD level of 330 pC1/1 in 211 sedes.

Iodine-131 activity was also below the:LLD level at l'.0 pC1/1 in all samples.- As with the.other!

well water samples, all analyses for gamma-emitting isotopes yielded' results below detection limits.

Gross beta ' averaged 7.5 pCi/l - and -was similar to the levels observed in.'1979 (10.5' pCi/l),1980 (11.8 pC1/1),.

1981 (10.7 pC1/1),1982 (8.9 pC1/1),- 1983 (8.0 pC1/1),1984- (7.9 pCi/1),

1985 (7.1 pCi/1),1986 (6.8 pC1/l),1987 (7.9 pCi/1)j and 1988 (8.0 pC1/1).

River Water At the upstream and-downstream collection sites', quarterly composite tritium levels were below the LLD level of 330 -pC1/1 in all samples.

River water was also andi1Ted for gamma-emitting isotopes.

All gamma-emitting isotopes were below their respective detection limits..

There was no indication of a plant effect.

Well Water _

i At the control well P-25, Kinneman Farm and three indicator wells (P-8, Community Center; P-10, Lock and Dam No. 3; and P-9, Plant Well No. 2) no tritium was detected above LLD lev 1 of 3,30 pC1/1 in all samples.

Gamma-emitting isotopes were below the detection limits in all samples.

Special Well Water, Ground Water and Surface Water At four additional wells (P-27, Nauer Residence; P-28, Perkins Residence; P-29, Childs Residence; and P-6, Lock and Dain No. 3 Well, no tritium was detected above LLD level of 190 pC1/1.

At the well P-24d, Suter's Deep Well, the level detected was 1430 pC1/1; at the well P-24s, Suter's Shallow Well, the level detected was 1070 pCi/1; at the well P-26. Prairie Island Training Center, the level detected was 300 pC1/1.

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I At three surface water sites near the plant (P-33, Pickerel Slough; P-34, Duck Pond; and P-35, Refuge Pond) no tritium was detected. above LLD level of 190 pC1/1.

At two ground water seepage points the results were: for P-31, Birch Lake

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Seepage No.1, the level was 820 pCi/1; and fo? '. -32, Birch Lake Seepage No. 2, the level was 540 pC1/1.

Gamma-emitting isotopes were below the detection limits in all samples.

The Special Well, Ground, and Surface Water results are contained in. Table.

5.5.

Crops Two samples of cabbage were collected in September and -analyzed for ~I-131.-

i The I-131 level was below 0.047 pC1/g wet weight in both samples.~ There 3

was no indication.of a plant effect, i

The field sampling personnel. conducted a survey and found that there was no river water taken for irrigation into fields within 5 miles down stream

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fonn Prairie Island Plant.

Therefore, it was not necessary to collect-and analyze corn samples.

Fish Fish samples were collected in May and September,1989.- The only isotope detected was naturally-occuring potassium-40 and there was; no significant.

difference between upstream and downstrean resultt.

There was no indic-l ation of a plant effect.

Aquatic Insects or Periphyton Aquatic insects (invertebrates) or periphyton were collected in May and September, 1989.

The samples were analyzed for gamma-emitting isotopes.

All gamma-emitting isotopes were below their respective LLDs.

No plant effect was indicated.

Bottom and Shoreline Sediments Sediment collections were made in May and September,- 1989.

The samples were analyzed for gamma-emitting isotopes.

et Cs-137 was detected in one bottom sediment upstream sample (0.077 'pci/g dry weight) and one shoreline sediment sample (0.0281 pCl/ dry weight).

All other gamma-emitting isotopes, except naturally-occurring potassium-40, were below their respective LLDs.

No plant effect was indicated.

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5.0 TABLES P

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.1 Tabic 5.1 Sampic collection and analysis program,1989.

Prairia-Islrnd Collection

. Analysis Locations Type and Type and Medium No.

Codes (and Type)a Frequencyb Frequencyc Ambient radiation 32 P-01A - P-10A C/Q Ambient gamma (TLDs)

P-018 --P-ISB P-01S - P-06S P-01C Airborne particulates 5

P-1(C),P-2, C/W GB, GS (QC of

P-3, P-4, P-6 each location)

Airborne iodine 5

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

P-16 to P-18,

- G/Md I-131, GS P-25(C),P-14 g

River water 2

P-5(C),P-6 G/W GS(MC),H-3(00)

Drinking water 1

P-11 G/W GB(MC),1-131(MC)

GS(MC),H-3(QC)

Well water 4

- P-25(C),P-6,

. G/Q H-3, GS P-8, P-9 Edible cultivated 2

P-25(C),P-24 G/A-I-131 crops - leafy green vegetables Special Well Water 3

P-27, P-28, P-29 G/Q H-3, GS Special Ground Water.

3 P-24d, P-24s, P-26 G/M H-3, GS 2-P-31, P-32 G/M LH-3, GS Special Surface Water 3

P-33, P-34, P-35

.G

- H-3, GS

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Table 5.1.

Sample collection and analysis program,1989-(continued)

Prairie Island Collection Analysis Locations Type and Type and Medium No.

Codes (and Type)a Frequencyb Frequencyc j

Edible cultivated 2

P-25(C),P-20 G/A GS crops - corn Fish (one species 2

P-5(C),P-6 G/SA GS-edible portion)

Periphyton or 2

P-5(C),P-6 G/SA GS invertebrates Bottom sediment 2

P-5(C),P-6

. G/SA GS Shoreline sediment 1

P-12 G/SA GS i

Location codes are defined in Table 5.2.

' Control stations are indicated by (C). All other b stations are indicators.

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

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

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

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

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'f Table 5.2.

Sampling locations.

Prairie Island 1

Code Type" Name Location l

i P-1 C

Air Station P-1 11.8 mi 9 316 */NW P-2 Air Station P-2 0.5 mi 9 294 */WNW P-3 Air Station P-3 0.8 mi 9 313 */NW l~ 4 -

Air Station P-4 0.4 mi 9 359'/N-P-5 C

Upstream of Plant 1.8 mi 9 11*/N P-6 Lock & Dam #3 & Air Station P-6

1. 6 mi-9 12 9 '/SE P-8 Community Center 1.0 mi 9 321*/WNW P-9 Plant Well'#2

0. 3 mi 9 3 06 * /NW P-11 City.of Red Wing 3.3 mi 9158'/SSE P-12 Recreational Area 3.0 mi 9116'/ESE P-14 Gustafson Farm 2.2 mi 0173 */SSE P-16 Johnson Farm "2. 6 mi 9 60'/ENE I

P-17 Place Farm 3.5 mi e 25'/NNE P-18 Christensen Farm 3.7 mi 9 88'/E P-20 River Irrigated Corn Field

P-24

~ Highest D/Q Garden **

P-24d Suter's Deep Well 0.6 mi 9158'/SSE P-24s Suter's Shallow Well 0.6 mi 9158'/SSE l

P-25 C

Kinneman Farm 11.1 mi 0 331*/NNW P-26 PINGP Training Center 0.4 mi 9 258*/WSW P-27 Nauer Residence 0.9 mi 9154 */SSE P-28 Per. kins Residence 1.0 mi 9152 */SSE P-29 Childs Residence 1.2 mi 0149'/SSE -

P-31 Birch Lake Seepage No. 1 0.8 mi 9169'/SSE P-32 Birch Lake Seepage No.-2 0.7 mi 9-179*/S P-33 Pickerel Slough No. 1

1. 4 mi 9 14 0 */SE P-34 Duck Pond No. 1 0.4 mi 9169'/SSE P-35 Refuge Slough

1. 2 mi 9 14 0 */SE P-01A Proparty Line 0.4 mi 9 359'/N P-02A Property Line 0.3 mi 0 10*/N P-03A Property Line 0.5 mi 9.183*/S P-04A Property Line 0.4 mi 9 204 */SSW P-05A Property Line O. 4 mi-9' 225 '/SW P-06A Property Line

0. 4 mi 9 249 */WSW P-07A Property Line 0.4 mi 9 268'/W P-OSA Property Line 0.4 mi 9 291*/NNW P-09A Property Line O '. 7 mi 9 317 * /NW P-10A Property Line 0.5 mi 9 333 */NNW P-01B Thomas Killian Residence 4.7 mi 0 355'/N P-02B Roy Kinneman Farm

4. 8 mi 9 17 '/NNE 9d

"C' denotes control location.

All other-locations are indicators.

i Collected only if river water is used to irrigate the cornfields (Technical Specification Revision No. 80, effective 11-14-86).

- This location is not predetermined 15 I'

1 i

i i

Table 5.2.

Sampling locations.

Prairie-Island Code Type' Name Location P-03B Wayne Anderson Farm 4.9 mi 9 46'/NE-P-04B Nelson Drive-(Road) 4.2 mi 9 61*/ENE P-05B County Road E and Coulee 4.1 mi 0 102*/ESE P-06B William Houschildt Residence 4.4 mi 9 112'/ESE P-07B Red Wing Service Center 4.7 mi 9 140*/SE P-08B David Wnuk Residence 4.1 mi-0 165'/SSE P-09B Highway 19 South 4.2 mi-9 187'/S P-10B Cannondale Farm 4.9 mi 9 200'/SSW P-11B Wallace Weberg Farm 4.5 mi 9 221*/SW P-12B Roy Gergen-Farm 4.5 mi 9 247'/WSW i

P-13B Thomas O'Rourke Farm 4.4 mi 9 270'/W P-14B David J. Anderson Farm 4.9 mi 9-306*/NW.

P-15B Holst Farms 4.2 mi 9 347'/NNW P-01S Federal Lock in Dam #3 1.6 mi 9 129*/SE-P-02S Charles Suter Residence 0.6 mi 9 158'/SSE P-03S Carl Gustafson Farm 2.2 mi 0-173'/S P-04S Richard Burt Residence 2.0 mi 9 202'/SSW P-05S Kenney Store 2.0 mi 9 270*/W P-06S Earl Flynn Farm 2.5 mi 9 299'/WNW P-01C Robert Kinneman Farm 11.1. mi 9 331'/NNW "C" denotes control location.

All other locations are indicators.

16 1

i e

r n

p

)

I s

Table 5.3.

Missed collections and analyses,1989. Prairie Island Nuclear Generating Plant. All required samples were collected and analyzed as scheduled except the following.

Collection Date Sample Analysis location or Period Comments Thermoluminescent Ambient P-13B 2nd Qtr.~1989

' Lost in the Dosimeters (TLDs)

Radiation field.

Mil k deb' I-131, Gamma P-17 07-05-89,,,

Samples not available.

Air Particulates Gr. beta P-3 07-24-89 Improper and Charcoal I-131 mounting.

Air Particulates Gr. beta P-2 08-22-89 Pump failure.

and Charcoal I-131 Air Particulates Gr. beta P-6' 09-25-89 Lost in the-and Charcoal I-3'1 Field.

er0TC i

j 17 i

Table 5.4.

Environmental Radiological Monitoring Program Summery.

Name of Facility Prairie Island Nuclear Generating Plant Docket No._ _,_,,_50-282. 50-306 Location of Factitty _

Goodhue. Minnesota Reporting Period _ January, December,1989 (County State)

Indicator Location with Hfghest Lontrol Sample Type and Locations Annual Mian Locations W r of Type Number of Mean (F)C fira TF1 -

Mesa (r)

Non-routine a

(Units)

Analysesa LLDb Ranget Locationd Range Range Results' TLD Gamma 40 3.0 15.7 (40/40)

P-03A Property Line 17.4 (4/4)

($ee control 0

(sR/91 days)

(12.0-19.4) 0.5 mi 9 183*/S (13.6-19.1) below)

(Inner Ring.

General Area at

$lte Boundary)

TLD Ganma 59 3.0 17.0 (59/59)

P-028 R. Kinneman 19.0 (4/4) 0-(mR/91 days)

(11.7 22.7)

Farm. 4.8 mi e 17*/NNE (14.5-21.0)

(Outer Ring.

P-038 li. Andersos 19.0 (4/4)

(See control 0

Farm. 4.9 mi 9 46*/NE (15.3-21.8)-

below)

P-048. Nelson Drive 19.0 (4/4) r*

4-5 miles 4.2 al 9 61*/ENE (15.6-20.8) distant)

TLD Gamma 23 3.0 15.2 (24/24)

P-035. C. Gustafson 17.4 (4/4)

(See control 0

m (mR/91 days)

(11.0-20.6)

Farm. 2.2 mi 9 (12.4-20.6) below)

(Special 168'/SSE Interest Areas)

TLD Gamma 4

3.0 Mone P-01C. R. Kinneman 16.7 (4/4) 16.7 (4/4) 0 (sR/91 days)

Farm, 11.1 mi 9 (15.4-18.5)

(15.4-18.5)

(control) 331*/Nfed Airborne G8 ~

252 0.002 0.028(201/201)

.P-2. Station P-2

-0.029 (50/50) 0.027(51/51)

O Partic lates -

(0.006-0.092) 0.5 mt 3 294*/Wed -

(0.006-0.075)

(0.011-0.062)

(pCl/m )

Gs 20 1

8e-7 0.022-0.067(16/16)

P-2. Station P-2

-0.073 (4/4) 0.064 (4/4) 0

.(0.046-0.099) 0.5 mi e 294*/Wei (0.056-0.092)

-(0.053-0.077) m-54

~0.0017

<tLD

<tLD 0

Co-58 0.0019

<tLD

<tLD 0

i Co-60 0.0014

<tLD

<tLD 0

2n-65

- 0.0034

- <LLD

<LLD 0

2r-Mb-95 0.0034

<tLD

<tLD 0

Ru-103 0.0017 (LLD

<LLD 0

Ru-106 0.014

<LLD

<tLD 0

Cs-134 0.0014

<LLD

<tLD 0

1

.,x

e AJuumM s

g

I i

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ojo j

jo o o o

o o o o o o o o o o o o g

o; 3,

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v 3~

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. 24 E

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(*

12 3" i

i Talb

. l s l2 a y

~

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a M

s: s e elu-r t

6 g

egese e

es e.e g Y M v -

a - e

~"g v Vjv 2 :

E D TW V v v

~g # # # O*

Wv vvv R=-

.A r5 b

~

1 ac

=.

9

=

8 n==

n esecue 3 &

l a

ee 1

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d-bt

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=

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OO3 3SSS$d

{ "I O

=g :t t hkhh 1

?a l 6bi ygakibbkkI

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[ge O

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~8. u34 2

2

{t:5 I1Y 21 31

'I n :.:

2--

1-x-

19

(

~

.y Table 5.4.

Environmental Redfological Mirnitoring Program Swamery (coetteved)

Name of Facility Prairie Island leuclear Generatins Plant Docket he.

._50-282. 50-306 Location of Facility,

Goodhue. Mtanesets

_ _ _, Reporting Period _ January - December 1999 (County, State)

Indicator Location with Highest Centrol Sample Type and Locations

~ Annual foren Locations Wr of Type number of g Mean (F)C Me~en M pteen (F) hen-routine (Units)

Analysesa I LLDb aanget tec,tteed Range Range ses::1t s Isone 0

Drinktg Water Cs-134 10 4LS (pCf/l) none 0

(continued)

Cs-137 10 ALD mene 0

to-La-140 15 4LD

_,,,,,e,,,,,,,

,0,,,,,,,

w 4 144 64

_4tD River Water H-3 8

330 4LD ALD 0

(PCf/1)

C5 24 ALD 0

pm-54 15 4LD 4LD 0

ro Fe-59 30 4LD o

4LD 0

Co-58 15 4LD (LD 0

Co-60 15 4LD 4LD 0

Zn-65 30 4LD Cs-134 15 (LD ALD 0

4LD 0

Cs-137 18 4LD Ba-La-140 15 4LD 4LD 0

Ce-144 67 (LD

..-... 4LD..._

0 Well Water M-3 16 330 4LD 4LD 0

(pCtfl}

G5 16 4LD 0

Mn-54 15 4LD Fe-59 30 4LD 4LD 0

4LD 0

Co 58 15 4LD 4LD 0

Co-60 15 4LD ALD 0

Zn-65 30 4LD 4LD 0

Zr-Nb-95 15 4LD ALD 0

Cs.134 10 4LD

a s

Table 5.4 Environmental indiological Monitoring Progree Summary (coattamed) b ee of Facility Prairie Islead hciear Generetten Plant Decket no.

_50-282. 50-306 Location of Factitty Goodawe. Minnesota

__,, Reporting Period _ January -_ December 1949 _

(County. State)

Indica *.or Location with Highest Centrol Sample Type and Locations Annual mean Lecettens number of Type.

hweer of farea (F)c W.a Tr) ne (F) a

-r ts.e (Units)

Analysesa LLDb mangec Locatioed Range Range Results

=.

Well Water Co-60 15 4LD 4LD 0

(pCl/1)

(continued)

Zn 65 30 4LD ALD 0

Zr-mt>-95 15 4LD 4LD 0

Cs-134 10 (LLD ALD 0

Cs-137 10 ALD

<tLD 0

84-La-140 15 4LD 4LD 0

Ce-144 71 4LD 4LD 0

to Crops-Cabbe9e 1-131 2

0.047 4LD ALD 0

(pCl/g wet)

- -.... ~..

Fish - Flesh GS 4

K-40 0.1 3.58 (2/2)

P-6. Lock and Dam 3.58 (2/2) 3.11 (2/2) 0 (3.27-3.88)

No. 3. 1.6 et c (3.21-3.88)

(2.37-3.85) 129'/5E m-54 0.046 (LD

<tLD 0

Fe 0.15 (LD 4LD 0

Co-58 0.042 4LD 4LD 0

Co-60 0.031 g

_<tLD

<LLD 0

Zn-65 0.089 4LC 4LD 0

2r-18>-95 0.065 (LD 4LD 0

Cs.134 0.030 4LD

<LLD 0

Cs-137 0.035 4LD

<t t D 0

~ Be-La-140 0.21

<LLD

<LLD 0

<- ---.~ _.--..

A mm_ _.,

(*

Table 5.4.

instronmental Radfological nonitoring Program Sasumary (contini d) thune of Facility Prafrie Island hetear Generettan Plant Docket No._,,,,

50-282. 50-306 Location of Facility Goodhue. Minnesota Reporting Period Janvery - December 1969 (Coenty. State)

Indicator Locatten with Nighest Control Sample Type and Locations Annual Iteen Locations ths6er of Type As6er of nean (F)C pl7eT~ ' feras (F) Non-routine (Units) Analysesa LLDb RangeC Location 4 Ran9e Ran9e Resultse Invertebrates G5 4 (pC1/g met) Be-7 4.34 4LD 4LD 0 E-40 0.5 2.66 (2/2) P-6. Lock and Das 2.M (2/2) 0.85 (2/2) 0 (0.66-4.66) No. 31.6 el 9 (0.66-4.M) (0.79-0.11) 129*/5E 843-54 0.16 ALD ALD 0 Co-58 0.49 4LD (LD 0 Co-60 0.095 4LD ALD 0 In-65 0.33 ALD (LD 0 m N Zr-Ib-95 1.03 4LD 4LD 0 Re-103 1.09 4LD ALD 0 Re-106 1.09 4LD 4LD 0 Cs-134 t3.10 ALD - ALD 0 Cs-137 0.11 4LD ALD 0 Ba-La-140 0.36 4LD 4LD 0 Ce-141 2.65 4LD 4LD 0 Ce-144 0.69 4LD 4LD 0 Bottom and G5 6 Shoreline l 4LD 0 5ediments Be-T 0.38 4LD (pct /s dry) K-40 1.0 8.66 (4/4) P-12. Recreational 9.47 (2/2) 8.75 (2/2) 0 (7.S3-9.56) Aree 3.4 si 9 (9.39-9.56).

(8.37-9.14) 116*/ESE h 54 29 (LD ALD 0

ALD y, O Co-58 30 - 4LD

O - Table 5.4. Environmental Radiological Monitoring Pro 9 ram Sasumary (continued) New of Factitty Pref rie Island hvetear Generetteg 71ont Docket Iso. 50-?S2. 50-306 Location of Factitty Goo ese. Mfanesota Reporting Period January - Deceeer 1999 (County State) Indicator Location with Highest Control Sample T.y and Loc 6t1ons Annual Mean Locat1ons Ilumber of Type huder of fleen (F)C Mese (F) Mese (F) Non-routtne (Units) Analysesa ttob yangge Locationd Range Ran9e Results* e, - Special H-3 6 190 993 (3/7) P-24d Suter's Deep 1430 (1/1) <tLD 3 Well Weter (300-1430) th:ll 0.6 et 158* (pCf/1) G5 6 4LD <tLD 0 Special Ground H-3 2 190 -680(2/2) P-31 Strch Ishe are (1/3) <tLD 2 Water (540-820) S w 1 0.7 et 179* m (pCl/l) W G5 2 < LLC <tLD 0 Special Serface H-3 3 190 <tLD <tLD 0 Water (pCf/1) G5 3 <LL.D <tLD G .o

Table 5.4. Eastreamental Radtelegical Montterlag Program Summery (continued) Name of Factitty _Protrie 1ste N #wclear Generating Plant Dechet No._ _ _50-282. 50-306 _,,,,_, Location of facility Goodhoe. Minnesete Reporting Perled _ Jaavery - December 1993,, (County State) Indicator Locatten with Mfghest Centrol Sample Type and Lacettons Anavel neon Type haber of Meae (F)C WeMYF~' Locettens h r of Meen (F) hen-rowttae (Units) Amelyses* LLDb manget Lecettend aange aanse meeelts* Sottom and Co-60 0.03g ALD 4t0 0 Sheretine Sediment s la-65 0.073 <tLD ALD 0 (pct /gdry) (conttaved) 2r-ub-35 0.061 4LD 4LD 0 au-103 0.018 4LD ALS 8 pu-106 0.25 4LD 4tB e Cs-us 0.023 <tto 4to e Cs-137 0.021 0.028 (1/4) 7-5(C). Upstream of 0.077(I/2) 0.877(1/2) e Plant. 0.6 et 3 60*fEnt to A Se-La-140 0.12 (LD 4tB 8 Ce-141 0.064 4LD

cLLD, 9

Ce-144 0.17 4 10 <ttt 8 e gg = Gross bete; G5

gamme scen.

b LLD = Nest.sel louer llett of detection based en 4.66 signe error for bochground semple. C Mese and range based spea detectable meesurements only. Fraction of detectable meeserements at specified locetten is fadicated la parentheses (F). 4 tocat$ ens are specified (1) by name and code (Tetle 2) and (2) distence. directies, and sector relettee to reacter site.

hen-routine results are these which eaceed ten times the centrol stetten valve.

If no centrol stetten value is evelle61e the result is considered neo-rowtIne if it enceeds ten times the preeperettenal velse for the lecettee. w,p.,.-w-w v.- 9 ve+++-e~--e-

- - "**-1*

'-*4 - * " ~ " -* ^^ ~

-l Table 5.5 Special Well, Ground, and Surface Water Analysis. Sample Description and Concentration (pCf/1) location P-24d P-24s P-26 P-27 P-28 P-29 Sutter's Sutter's Training Re:. No.1 Res. No. 2 Res. No. 3 Deep Shallow Center Mauer Perkins Childs Well Well Well Weil Well Date Collected 11-21-8'4 11-21-89 12-07-89 12-07-89 12-11-89 12-07-89 Lab Code SPW-7691 SPW-7692 SPW-7820 SPW-7815 SPW-7816 SPW-7817 H-3 1430i140 10701130 300 100 <190 <190 <190 M Mn-54 <1.9 <2.8 <4.8 <5.6 <2.6 <4.0 Fe-59 <4.5 <5.6 <10.2 <11.5 <6.0 <7.8 Co-58 <2.0 <2,8 <4.4 <5.4 <2.5 <4.5 Co-60 <2.2 <2.5 <4.7 <5.3 <2.8 <3.7 Z n-65 <4.9 <6.6 <14.6 <12.7 <5.2 <9.5 Zr-Nb-95 <2.1 <2.8 <5.3 - <5.8 <3.0 <5.0 Cs-134 <2.1 <3.2 <6.5 <7.0 <2.2 <5.2 Cs-137 <2.1 <2.8 <5.2 <5.7 <3.0 <4.4 Ba-La-140 <3.2 <3.1 <10.1 <9.9 <3.5 <7.5 Ce-144 <13.6 <26.9 <41.3 <43.5 <19.9 <30.9 4 . ~,

Table 5.5 Special Well, Ground, and Surface Water Analysis (continued) Sample Description and Concentration (pC1/1) Location P-31 P-32 P-33 P-34 P-35 Birch Birch Pickerel Duck Refuge-Lake Lake Slough Pond Slough Seepage No. 1 Seepage No. 2 No. I No. 1 Date Collected 12-07-89 12-07-89 12-07-89 12-07-89 12-07-89 e Lab Code SPW-7813 SPW-7814 'SPW-7818 -SPW-7821 SPW-7822 H-3 8201120 540 110 <190 <190 <190 Mn-54 <7.8 <4.9 <8.0 <5.5 <3.4 Fe-59 <13.9 <11.5 <15.9 <12.1 <7.5 Co-58 <7.0 <4.8 <7.6 <6.0 <3.5 Co-60 <7.0 <5.7 <7.2 <5.7 <3.0 'Zn <16.6 <13.9 <18.0 <11.1 <6.1 Zr-Mb-95 <7.8 <5.5- <8.4 <6.0 <3.9 Cs-134 <8.1 .<7.1 <9.1 <5.8 <3.0 . 8.4 <5.4 <3.5 Cs-137 <7.7.. <5.0 Ba-La-140 <9.5.

<10.6'

<10.1 . 6.1 <3.2 Ce-144 .<59.1 <38.9 <65.1- <40.7- <29.4

4

6.0 REFERENCES

CITED Arnold, J. R. and H. A. Al-Salih. 1955. Bery111um-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 Natu-rally Occuring Radionuclides in Air, in the Natural Radiation Environ-ment, University of Chicago Press, Chicago, Illinois, 369-382. Hazleton Environmental Sciences Corporation. 1979a. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete An61ysis 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. ~ Radiation Environmental Monitoring for Prairie 1980b. Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1979. 1981a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - ? December 1980. 1981b. Radiation Environmental Monitoring for Prarie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1980. 19826. Radiation Environmental Monitoring for Mnnticello 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. 27

4 l Hohenemser, C.M. Deicher, A. Ernst, H. Hofsass, G. Lindner, E. Racknagel. I 1986. "Chernobyl," Chemtech, October 19M, pp. 596-605. i National Center for Radiological Health,1968. Radiological Health and Data Reports, Vol. 9, Number 12, 730-746. i Northern States Power Company. 197G. Prairie Isiand Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. l Nuclear Regulatory Commission, January 1,1978 to December 31, 1978 l (prepared by Hazleton Environmental Sciences). Minneapolis, Minnesota. i I 1980. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to tne U.S. Nuclear Regulatory 31, 1979_(prepared by Hazleton Commission, January 1,)1979 to DecemberMinnaapolis, Minnesota. l Environmental Sciences. 1981. Prairie Island Nuclear Generating Plant, Annual Radtation Environmental Monitoring Report to the U.S. Nuclear Regulatory 31, 1980 (prepared by Hazleton Commission, January 1,)1980 to DecemberMinneapolis, Minnesota. Environmental Sciences. 1982. Prairie Island Nuclear Generating Plant, Annual f Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, Jar.uary 1,1981 to December 31,1981 (prepared by Hazleton Environmental Sciences). Minneapolis, Minnesota.. t 1983. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory 7 Commission, January 1,1982 to December 31,1982 (prepared by Hazleton Environmental Sciences). Minneapolis, Minnesota. l 1984. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1,1983 to December 31, 1983 (prepa ed by Teledyne Isotopes Midwest Laboratory). Minneapolis, Minnesota. 1985. Prairie Is' land Nuclear Generating Plant, Annual Radiatiori Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1, 1984 to December 31,1984 (prepared by Teledyne Isotopes Midwest Laboratory). Minneapolis, Minnesota. 1986. Prairie Island Nuclear Generating Plant, Annual. Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1,1985 to December 31, 1985 (prepared by Teledyne e isotopes Midwest Laboratory). Minneapolis, Minnesota, j 1987. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1, 1986 to December 31,1986 (prepared by Teledyne IsotopesMidwestLaboratory). Minneapolis, Minnesota. l 28

1988. Prairie Island Nuclear Generating Plant Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1,1987 to December 31,1987(preparedbyTeledyne Isotopes Midwest Laboratory). Minneapolis, Minnesota. Teledyne Isotopes Hidwest Laboratory. 1971a. Quality Control Program, Revision 7. 20, November 1984. 1989. Quality Control Procedures Manual. Revision 10, 30 November 1989, l 1990. Quality Assurance Program Manual Revision 2, 08 January 1990. 1985. Analytical Procedures Manual. Revision 5, 29 July 1985. 1984a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1983. 1984b. Radiation Environmental Monitoring for Prairie Island ( Nuclear Generating Plant. Complete Analysis Data Tables, January - December 1983. 1985a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analyses Data Tables, January - December 1984. 1985b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant,- Complete Analyses Data Tables, January - December 1984. 1986a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analyses Data Tables, January - December 1985. 1986b. Radiation Environmental Monitoring _for Prairie Island Nuclear Generating Plant, Complete Analyses Data Tables, January - December 1985. 1987. Sampling Procedures, Prairie Island Nuclear Generating Plant, Revision 16,18 December 1987. 1987a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analyses Data Tables, January - em December 1986. 1987b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analyses Data Tables, January - December 1986. 29

l l 1988a. Radiation Environmental Monitoring for Monticello Nuclear 6enerating Plant, Complete Analyses Data Tables, January - December 1987. 1988b. Radiation Environmental Monitoring for Prairie Island NuclearTenerating Plant, Complete Analyses Data Tables, January - December 1987. 1989a. Radiation Environmental-Monitoring for Monticello Nuclear'6enerating Plant, Complete Analyses Data Tables, January - December 1988. 1989b. R6diation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analyses Data Tables, January - December 1988. 1990a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analyses Data Tables, January - December 1989. 1990b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analyses Data Tables, January - December 1989. U. S. Atomic Energy Commission. 1972. HASL Procedures Manual, Health and Safety Laboratory, New York, NY., 10014. U. S. Public Health Service. 1967. Radioassay Procedures for Environmental Samples, National Center for Radiological Health, Rockville, Maryland (Public Health Service Publication No. 999-RH-27). Wilson, D. W., G. M. Ward and J. E. Johnson. 1969. In Environmental Contam-ination by Radioactive Materials, International Atomic Energy Agency.

p. 125.

V l 30

q WTEUEDYNE i l lSOTOPES wowest u on.rony l 700 LA40wtH4 moAD E 8eomTHemoon, n.Lasoes escat 2310 con u.co taxa = eu. it 1 1 l I i i I Appendix A f Interlaboratory Comparison Program Results i I I i -? i i t 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 updnted twice a year and the i complete Appendix is included in January and July monthly reports only. Please refer to January and July Reports for infomation. l l January 1990. t l A-1

Appendix A Interlaboratory Comparison Program Results Teledyne Isotopes Midwest Laboratory (formerly Hazleton Environmental Sciences) has participated in interleboratory 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 i 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 l 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, j Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used, e The results in Table A-1 were obtained through participation in the environmental i sample crosscheck program for milk, water, air filters,.and food samples during l 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 1970, 1977, 1979, 1980,1984, and 1985-1986 through partici-l pation in the Secotid, 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. l J l 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. 1 Attachment B lists acceptance criteria for " spiked" samples. l Addendum to Appendix A provides explanation for out of limit results. A-2

e Table A-1. U.S. Envircnmental Protecticn Agency's crosscheck prograJ, coc-parison of EPA and Teledyne Isotopes Midwest Laboratory results for milk, water, air filters, and food samples, 1986 through 1989.a Concentration in pC1/lb Lab Sample Date TIML Result EPA Resultd Code Type Collected Analysis 12cC 1s, N=1 Control Limits STF-447 Food Jan 1986 Sr-89 24.312.5 25.015.0 16.3-33.7 Sr-90 17.310.6 10.011.5 7.4-12.6 I-131 22.712.3 20.010.6 9.6-30.4 Cs-137 16.310.6 15.015.0 6.3-23.7 K 927146 9501144 701-1199 STW-448 Water Feb 1986 Cr-51 45.013.6 38.015.0 29.3-46.7 Co-60 19.711.5 18.015.0 9.3-26.7 Zn-65 44.013.5 40.015.0 31.3-48.7 Ru-106 <9.0 0.015.0 0.0-8.7 Cs-134 28.312.3 30.015.0 21.3-38.7 Cs-137 23.710.6 22.015.0 13.3-30.7 STW-449 Water Feb 1986 H-3 5176148 52271525 4317<6137 STW-450 Water Feb 1986 U total 8.010.0 9.016.0 0.0-19.4 STM-451 Milk Feb 1986 1-131 7.010.0 9.016.0 0.0-19.4 l STW-452 Water Mar 1986 Ra-226 3.810.1 4.110.6 3.0-5.2 Ra-228 11.010.5 12.411.8 9.2-15.5 STW-453 Water Har 1986 Gr. alpha 6.710.6 15.015.0 6.3-23.7 Gr. beta 7.310.6 8.015.0 0.0-16.7 l l STH 454 Water Apr 1986 I-131 7.010.0 9.016.0 0.0-19.4 STW-455 Water Apr 1986 456 (Blind) Sample A Gr. alpha 15.011.0 17.015.0 8.3-25.7 Ra-226 3.110.1 2.910.4 2.1-3.7 Ra-228 1.5*0.2 2.010.3 1.5-2.5 Uranium 4.710.6 5.016.0

0.0-15.4 Sample B Gr. beta 28.711.2 35.015.0 26.3-43.7 Sr-89 5.710.6 7.015.0 0.0-15.7 Sr-90 7.010.0 7.011.5 4.4-9.6 Co-60 10.711.5 10.015.0 1.3-18.7 Cs-134 4.011.7 5.015.0 0.0-13.7 Cs-137 5.310.6 5.015.0 0.0-13.7 A-3

4 Table A-1. (continued) [ b l Con:3ntration in pC1/l l Lab Sample Date TIML Result EPA P.esultd Code Type Collected Analysis f20c is,N=1 Control Limits l STAF-457 Air April 1986 Gr. alpha 13.710.6 15.015.0 6.3-23.7 Filter Gr. beta 46.3i0.6 47.0i5.0 38.3-55.7 i Sr-90 14.710.6 18.011.5 15.4-20.6 l Cs-137 10.7i0.6 10.0i5.0 1.3-18.7 STU-458 Urine April 1985 Tritium 4313t70 4423i189 4096-4750 STW-459 Water May 1986 Sr-89 4.3i0.6 5.Di5.0 0.0-13.7 Sr-90 5.010.0 5.011.5 2.4-7.6 STW-460 Water May 1986 Gr. alpha 5.310.6 8.Di5.0 0.0-16.7 Gr. beta 11.311.2 15.0i5.0. 6.3-23.7 STW-461 Water June 1986 Cr-51 <9.0 0.015.0 0.0-8.7 l Co-60 66.Dil.0 66.0t5.0 57.3-74.7 In-65 87.311.5

86. Di5. 0 77.3-94.7 l

Ru-106 39.712.5 50.0t5.0 41.3-58.7 l Cs-134 49.3i2.5 49.0i5.0 40.3-57.7 Cs-137 10.3tl.5 10.Di5.0 1.3-18.7 STW-462 Water June 1986 Tritium 3427125 31251361 2499-3751 l l STM-464 Milk June 1986 Sr-89 <1.0 0.015.0 0.0-8.7 I Sr-90 15.310.6 16.0il.5 13.4-18.6 I-131 48.312.3 41.016.0 30.6-51.4 Cs-137 43.7tl.5 31.015. 0 22.3-39.7 K 15671114 1600i80 1461-1739 STW-465 Water July 1986 Gr. alpha 4.7t0.6 6.015.0 0.0-14.7 Gr. beta 18.711.2 18.Di5.0 9.3-26.7 STW-467 Water August 1986 l-131 30.310.6 45.016.0 34.4-55.4 STW-468 Water August 1986 Pu-239 11.310.6 10.111.0 8.3-11.9 STW-469 Water August 1986 Uranium 4.0f0.0 4,016.0 0.0-14.4 STAF-470 Air Sept 1986 Gr. alpha 19.311.5 22.0t5.0 13.3-30.7 l 471 Filter Gr. beta 64.012.6 66.0i5.0 57.3-74.7 472 Sr-90 22.0tl.0 22.015.0 19.4-24.6 Cs-137 25.7tl.5 22.015.0 13.3-30.7 STW-473 Water Sept 1986 Ra-226 6.010.1 6.110.9 4.5-7.7 Ra-228 8.711.1 9 lil.4 6.7-11.5 A-4

Table A-1. (continued). Concentration in pCf/lb Lab Sample Date TIML Result EPA Resultd Code Type Collected Analysis

2ac Is, N=1 Control Limits STW-474 Water Sept 1986 Gr. alpha 16.313.2 15.0t5.0 6.3-23.7 i

Gr. beta 9.0tl.0 8.0t5.0 0.0-16.7 j STW-475 Water Oct 1986 Cr-51 63.315.5 59.015.0 50.3-67.7 l Co-60 31.0t2.0 31.015.0 22.3-39.7 87:$' 5.9 85.0t5.0 76.3-93.7 i Zn 65 t Ru-106 74.717.4 74.0t5.0 65.3-82.7-05-134 25.7i0.6 28.0t5.0 19.3-36.7 Cs-137 46.311.5 44.015.0 35.3-52.7 STW-476 Water Oct 1986 H-3 5918160 59731597 4938-7008 SPW-477 Water Oct 1986 478 (Blind) Sample A Gr. alpha 34.0t6.0 40.015.0 31.3-48.7 l Ra-226 5.810.2 6.010.9 4.4-7.6 l Ra-228 2.711.0 5.0i0.8 3.7-6.3 Uranium 11.010.0 10.015.0 0.0-20.4 Sample B Gr. beta 38.711.2 51.0i5.0 42.3-59.7 Sr-89 5.0t0.0 10.015.0 1,3-18.7 SP-90 3.0t0.0 4.0tl.5 1.4-6.6 Co-60 24.7*1.2 24.0t5.0 15.3-32.7 Cs-134 11.0t2.0 12.015.0 3.3-20.7 Cs-137 9.311.2 8.0t5.0 0.0-16.7 STM-479 Milk Nov 1986 Sr-89 7.711.2 9.0t5.0 0.3-17.7 1 Sr-90 1.010.0 0.011.5 4,0-2.6 1-131 52.313.1 49.016.0 38.6-59.4 Cs-137 45.713.1 39.0i5.0 30.3-47.7 K 14891104 1565t78 1430-1700 STU-480 Urine Nov 1986 H-3 5540126 52571912 4345-6169 STW-481 Water Nov 1986 Gr. alpha 12.0*4.0 20.015.0 11.3-28.7 Gr. beta 20.0*3.5 20.015.0 11.3-28.7 STW-482 Water Dec 1986 Ra-226 6.710.2 6.8tl.0 5.0-8.6 Ra-228 5.210.2 11.111.7 8.2-14.0 STW-483 Water Jan 1987 Sr-89 19.715.0 25.0i5.0 16.3-33.7 Sr-90 21.0i2.0 25.0*1.5 22.4-27.6 6 A-5 t -a,

e Table A-1. (continued). Concentration in pCi/lb Lab Sample Date TIML Result EPA Resultd ] Code Type Collected Analysis i2aC 1s, N=1 Control Liraits ) STW-484 Water Jan 1987 Pu-239 17.012.3 16.711.7 13.8-19.6 STF-486 Food Jan 1987 Sr-90 36.014.0 49.0110.0 31.7-66.3 1-131 78.013.4 78.018.0 64.1-91. 9 Cs-137 89.713.0 84.015.0 75.3-92.7 K 942156 980149 895-1065 l STF-487 Food Jan 1987 SR-90 2.0i0.0 (Blank) I-131 <3 -~ Cs-137 <2 K 9931102 STW-488 Water Feb 1987 Co-60 49.010.0 50.015.0 41.3-58.7 Zn-65 96.017.2 91.015.0 82.3-99.7 Ru-106 92.0120.2 100.015.0 91.3-108.7 Cs-134 53.0t3.4 59.015.0 50.3'67.7 Cs-137 83.314.6 87.015.0 78.3-95.i i r STW-489 Water Feb 1987 H-3 41301140 4209i420 3479-4939 STW-490 Water Feb 1987 Uranium 8.311.2 8.016.0 0.0-18.4 STM-491 Milk Feb 1987 I-131 10.010.0 9.0f0.9 7.4-10.6 STW-492 Water Mar 1987 Gr. alpha 3.7tl.2 3.015.0 0.0-11.7 Gr. beta 11.311.2 13.015.0 4.3-21.7 STW.493 Water Mar 1987 Ra-226 7.0f0.1 7.3tl.1 5.4-9.2 Ra-228 7.1*2.3 7.Sil.1 5.5-9.5 STW-494 Water Apr 1987 I-131 8.010.0 7.0io.7 5.8-8.2 STAF-495 Air Apr 1987 Gr. alpha 15.0f0.0 14.015.0 5.3-22.7. Filter Gr. beta 41.012.0 43.0i5.0 34.3-51.7 Sr-90 16.311.2 17.011.5 14.4-19.6 Cs-137 7.0f0.0 8.015.0 0.0-16.7 STW-496 Water Apr 1987 497 (Blind) Sample A Gr. alpha 30.711.2 30.0t8.0 16.1-43.9 Ra-226 3.910.2 3.910.6 2.9-4.9 Ra-228 4.910.9 4.010.6 3.0-5.0 Uranium 5.010.0 5.016.0 0.0-15.4 A-6

Table A-1. (continued) l Concentration in pCi/lb Lab Sample Date TIML Result EPA Resultd Code Type Collected Analysis 120C 1s, N=1 Control Limits STW-496 Water Apr 1987 497 (Blind) Sample 8 Gr. Beta 69.3t9.4 66.015.0 57.3-74.7 Sr-89 16.313.0 19.015.0 10.3-27.7 Sr-90 10.0t0. 0 10.0*1.5 7.4-12.6 l Co-60 8.313.0 8.0i5.0 0.0-16.7 Cs-134 19.012.0 20.015.0 11.3-28.7 Cs-137 14.7tl.2 15.015.0 6.3-23.7 STU-498 Urine Apr 1987 H-3 6017i494 56201795 4647-6593 STW-499 Water May 1987 Sr-89 38.016.0 41.015.0 32.3-49.7 Sr-90 21.012.0 20.0il.5 17.4-22.6 STW-500 Water May 1987 Gr. alpha 9.0t3.4 11.015.0 2.3-19.7 i Gr. beta 10.311.2 7.015.0 0.0-15.7 l STW-501 Water June 1987 Cr-51 40.018.0 41.015.0 32.3-49.7 Co-60 60.313.0 64.015.0 55.3-72.7 Zn-65 11.315.0 10.015.0 1.3-18.7 Ru-106 78.316.4 75.015.0 66.3-83.7 Cs-134 36.713.0 40.015.0 31.3-48.7 Cs-137 80.314.2 80 ')i5.0 71.3-88.7 STW-502 Water June 1987 H-3 2906186 28951357 2277-3513 STW-503 Water June 1987 Ra-226 6.910.1 7.311.1 5.4-9.2 Ra-228 13.311.0 15.212.3 11.2-19.2 STM-504 Mfik June 1987 Sr-89 57.014.3 69.0t5.0 60.3 77.7 Sr-90 32.0*1.0 35.011.5 32.4-37.6 I-131 64.0i2.0 59.016.0 48.6-69.4 Cs-137 77.710.6 74.015.0 65.3-82.7 K 1383117 1525t76 1393-1657 STW-505 Water July 1987 Gr. alpha 2.310.7 5.015.0 0.0-13.7 Gr. beta 4.0il.0 5.015.0 0.0-13.7 STF-506 Food July 1987 1-131 82.714.6 80.018.0 66.1-93.9 Cs-137 53.7i3.0 50.015.0 41.3-58.7 K 1548157 1680184 1534-1826 STW-507 Water Aug 1987 I-131 45.714.2 48.0*6.0 37.6-58.4 STW-508 Water Aug 1987 Pu-239 5.810.2 5.310.5 4.4-6.2 A-7

Table A-1. (continued) g. Concentration in pCi/lb L ab Sample Date TIM. Result EPA Resultd Code Type Collected 4nalysis 22cc Is, N=1 Control Limits STW-509 Water Aug 1987 Uranium 13.3s0.3 13.O s6.0 2.6-23.4 I STAF-510 Air Aug 1987 Gr. alpha 9.780.4 10.025.0 1.3-18.7 F11ter Gr. beta 28.380.6 30.025.0 21.3-38.7 S o90 10.020.9 10.011.5 7.4-12.6 ~ Cs-137 10.011.0 10.025.0 1.3-18.7 STW-511 Water Sept 1987 Ra-226 9.9 so.1 9.7 21.5 7.2-12.2 Ra-228 8.111.4 6.3 11.0 4.6-8.0 STW-512 Water Sept 1987 Go, alpha 2.0 s0.6 4.025.0 0.0-12.7 Gr. beta 11.311.3 12.025.0 3.3-20.7 STW-513 Water Oct 1987 H-3 44731100 44922449 3714-5270 STW-514 Water Oct 1987 (Blind) Sampie A Gr. alpha 29.322.6 28.017.0 15.9-40.1 Ra-226 4.920.1 4.820.7 3.6-6.1 R a-228 4.211.0 3.680.5 2.7-4.5 Uranium 3.020.1 3.0 26.0 0.0-13.4 Sampie B Sn 89 14.311.3 16.025.0 7.3-24.7 [ S rw90 9.720.4 - 10.011.5 7.4-12.6 ~ C o-60 16.713.0 16.025.0 7.3-24.7 C s-134 16.722.3 16.025.0 7.3-24.7 C s-137 24.323.3 24.025.0 15.3-32.7 STW-516 Water Oct 1987 C r-51 80.3217.5 70.025.0 61.3-78.7 C o-60 16.012.3 15.025.0 6.3-23.7 Zn 65 46.325.6 46.025.0 37.3-54.7 R u-106 57.3215.4 61.0 *5.0 52.3-69.7 C s-134 23.722.5 25.025.0 16.3-33.7 C s-137 51.713.2 51.025.0 42.3-59.7 STU-517 U rine Nov 1987 H-3 72671100 74321743 6145-8719 STW-518 Water Nov 1987 Gr. alpha 3.022.0 7.0 25.0 0.0-15.7 Gr. beta 15.722.3 19.025.0 10.3-27.7 STW-519 Water Dec 1987 l-131 26.013.0 26.026.0 15.6-36.4 A-8

Table A-1. (continued) Concentration in pC1/1b Lab Sample Date T1ML Result EPA Resultd Code Type Collected Analysis 12sc is, y.1 Control Limits 1 SDd-520 Water Dec 1987 Ra-226 5.110.8 4.8t0.7 3.6-6.0 Ra-228 3.410.1 5.310.8 3.9-6.7 I I STW-521 Water Jan 1988 Sr-89 27.315.0 30.015.0 21.3-38.7 Sr-90 15.311.2 15.0tl.5 12.4-17.6 l t STW-523 Water Jan 1988 Gr. alpha 2.311.2 4.015.0 0.0-12.7 Gr. beta 7.711.2 8.015.0 0.0-16.7 1 STF-524 Fned Jan 1988 Sr-89 44.0t4.0 46.015.0 37.3-54.7 i Sr-90 0 0t2.0 55.0t2.8 50.2-59.8 1-131 'tff.3t4.2 102.0t10.2 84.3-119.7 i Cs-137 95.716.4 91.015.0 82.3-99.7 i K 1011t158 1230t62 1124-1336 STW-525 Water Feb 1983 Co-60 69.312.3 69.0t5.0 60.3-77.7 J Zn-65 99.0 *3.4 94.0t9.4 77.7-110.3 Ru-106 92.7114.4 105.0t10.5 86.8-123.2 l Cs-134 61.718.0 64.0t5.0 55.3-72.7 Cs-137 99.7t3.0 94.015.0 85.3-102.7 j STW-526 Water Feb 1988 H-3 3453t103 33271362 2700-3954 STW-527 Water Feb 1988 Uranium 3.0t0.0 3.016.0 0.0-13,4 l STM-528 Milk Feb 1988 1-131 4.7tl.2 4.0t0.4 3.3-4.7 STW-529 Water Mar 1988 Ra-226 7.110.6 7.611.1 5.6-9.6 Ra-228 NA' 7.7tl.2 5.7-9.7 STW-530 Water Mar 1988 Gr. alpha 4.321.2 6.015.0 0.0-14.7 Gr. beta 13.311.3 13.015.0 4.3-21.7 i i STAF-531 Air Mar 1988 Gr. alpha 21.012.0 20.015.0 11.3-28.7 Filter Gr. beta 48.0t0.0 50.025.0 41.3-58.7 1 Sr-90 16.721.2 17.011.5 14.4x & 6 Cs-137 18.7tl.3 16.015.0 7.3-2F.7 q STW-532 Water Apr 1988 I-131 9.012.0 7.St0.8 6.2-8.8 i i i A-9 1

O Table A-1. (continued) ConcentrejfoninpC1/lb Lab Sample Date TIML Result EPf. Resultd Code Type Collected Analysis ibc Is, Nel Control Limits STW-533 Water Apr 1988 534 (Blind) Sample A Gr. alpha N0f 46.0111.0 27.0-65.0 Ra-226 ND 6.411.0 4.7-8.1 Ra-228 ND 5.6*0.8 4.2-7.0 Uranium 6.010.0 6.016.0 0.0-16.4 Sample B Gr. beta ND 57.015.0 48.3-65.7 Sr-89 3.321.2 5.0t5.0 0.0-13.7 Sr-90 5.311.2 5.0tl.5 2.4-7.6 Co-60 63.311.3 50.015.0 41.3-58.7 Cs-134 7.7tl.2 7.015.0 0.0-15.7 Cs-137 8.311.2 7.015.0 0.0-15.7 l STU-535 Urine Apr 1988 H-3 6483t155 6202t620 5128-7276 STW-536 Water Apr 1988 Sr-89 14.711.3 20.045.0 11.3-28.7 Sr-90 20.042.0 20.011.5 17.4-22.6 SIW-538 Water June 1988 Cr-51 331.7t13.0 302.0130.0 250.0-354.0 Co-60 16.0t2.0 M S.015.0 6.3-23.7 Zn-65 107.7t11.4 101.0t10.0 83.7-118.3 Ru-106 191.3t11.0 195.0t20.0 160.4-229.6 Cs-134 18.314.6 20.015.0 11.3-28.7 Cs-137 26.3tl.2 25.015.0 16.3-33.7 STW-539 Water June 1988 H-3 5586192 55652557 4600-6530 l STM-541 Milk June 1988 Sr-89 33.7111.4 40.015.0 31.3-48.7 Sr-90 55.315.8 60.013.0 54.8-65.2 1-131 103.723.1 94.019.0 78.4-109.6 Cs-137 52.713.1 51.015.0 42.3-59.7 K 1587123 1600180 1461-1739 STW-542 Water July 1988 Gr. alpha 8.714.2 15.0t5.0 6.3-23.7 l Gr. beta 5.311.2 4.015.0 0.0-12.7 l STF-543 Food July 1988 Sr-89 N0 33.015.0 24.3-41.7 Sr-90 ND 34.012.0 30.5-37.5 1-131 115.015.3 107.0t11.0 88.0-126.0 Cs-137 52.716.4 49.015,0 40.3-57.7 K 1190166 1240162 1133-1347 i A-10

.oemt Table A-1. (continued) Concentration in pCi/lb Lab Sample Date TIML Result _ EPA Resultd Code Type Collected Analysis 22cc 15, N=1 Control Limits STW-544 Water Aug 1988 1-131 80.020.0 76.018.0 62.1-89.9 STW-545 Water Aug 1988 Pu-239 11.020.2 10.211.0 8.5-11.9 STW-546 Water Aeg 1988 Uranium 6.010.0 6.016.0 0.0-16.4 STAF-547 Air Aug 1988 Gr. alpha 8.010.0 8.015.0 0.0-16.7 Filter Gr. beta 26.311.2 29.015.0 20.3-37.7 Sr-90 8.012.0 8.021.5 5.4-10.6 Cs-137 13.012.0 12.015.0 3.3-20.7 STW-548 Water Sep 1988 Ra-226 9.320.5 8.412.6 6.2-10.6 Ra-228 5.810.4 5.411.6 4.0-6.8 STW-549 Water Sep 1988 Gr. alpha 7.012.0 8.015.0 0.0-16.7 Gr. beta 11.311.2 10.015.0 1.3-18.7 STW-550 Water Oct 1988 Cr-51 252.0114.0 251.0t25.0 207.7-294.3 C9-60 26.012.0 25.015.0 16.3-33.7 Zn-65 158.3t10.2 151.0115.0 125.0-177.0 Ru-106 153.0t9.2 152.0115.0 126.0-178.0 Cs-134 28.71b.0 25.015.0 16.3-33.7 Cs-137 16.311.2 15.015.0 6.3-23.7 STW-551 Water Oct 1988 fh3 2333t127 23161350 1710-2927 STW-552 Water Oct 1988 553 (Blind) Sample A Gr. alpha 38.318.0 41.0110.0 23.7-58.3 Ra-226 4.510.5 5.020.8 3.6-6.4 Ra-228 4.410.6 5.210.8 3.6-6.4 Uranium 4.7tl.2 5.016.0 0.0-15.4 . Sample B Gr. beta 51.313.0 54.015.0 45.3-62.7 Sr-09 3.7tl.2 11.015.0 2.3-15.7 Sr-90 10.711.2 10.011.5 7.4-12.6 Cs-134 15.312.3 15.015.0 6.3-23.7 Cs-137 16.711.2 15.015.0 6.3-23.7 4 A-11 4

Table A-1. (continued) Concentration in pCi/lb Lab Sampl e Date TIML Result EPA Resultd Code Type Collected Analysis 1 83C 1s, N=1 Control Limits t STM-554 Milk Oct 1988 Sr-89 40.317.0 40.0t5.0 31.3-48.7 Sr-90 51.012.0 60.013.0 54.8 -6 5.2 1-131 94.013.4 91.0t9.0 75.4-106.6 Cs-137 45.014.0 50.015.0 41.3-58.7 K 1500145 1600180 1461-1739 + STU-555 Urine Nov 1988 H-3 3030t209 3025t359 2403-3647 I STW-556 Water Nov 1988 Gr. alpha 9.0t3.5 9.015.0 0.3-17.7 Gr. beta 9.7tl.2 9.015.0 0.3-17.7 STW-557 Water Dec 1988 1-131 108.7t3.0 115.0112.0 94.2-135.8 l STW-559 Water Jan 1989 Sr-89 40.018.7 40.015.0 31.3-48.7 Sr-90 24.3t3.1 25.0tl.5 22.4-27.6 STW-560 Water Jan 1989 Pu-239 5.811.1 4.2t0.4 3.5-4.9 STW-561 Water Jan 1989 Gr. alpha 7.311.2 8.0t5.0 0.0-16.7 Gr. beta 5.311.2 4.015.0 0.0-12.7 l STW-562 Water Feb 1989 Cr-51 245t46 235124 193.4-276.6 Co-60 10.012.0 10.015.0 1.3-18.7 Zn-65 170110 159115 139.2-186.7-Ru-106 18117.6 178118~ 146.8-209.2 Cs-134 9.7t3.0 10.015.0 1.3-18.7 Cs-137 11.711.2 10.015.0 1.3-18.7 l i 6 l l l A-12 s n

Table A-1. (continued) Concentration in pC1/lb Lab Sample Date TIML Result EPA Resultd Code Type Collected Analysis 12 C 1s, N=1 Control Limits STW-563 Water Feb 1989 I-131 109.014.0 106.0t11.0 86.9-125.1 STW-564 Water Feb 1989 H-3 2820t20 27541356 2137-3371 STW-565 Water Mar 1989 Ra-226 4.210.3 4.910.7 3.7-6.1 Ra-228 1.9tl.0 1.7t0.3 1.2-2.2 STW-566 Water Mar 1989 U 5.010.0 5.0t6.0 0.0-15.4 STW-567 Air Mar 1989 Gr. alpha 21.7tl.2 21.015.0 12.3-29.7 Filter Gr. beta 68.314.2 62.015.0 53.3-70.7 Sr-90 20.012.0 20.0tl.5 17.4-22.6 Cs-137 21.311.2 20.015.0 11.3-28.7 STW-568 Water Apr 1989 569 (Blind) Sample A Gr. alpha 22.712.3 29.0t7.0 16.9-41.2 Ra-226 3.610.6 3.5*0.5 2.6-4.4 Ra-228 2.6tl.0 3.610.5 2.7-4.5 U 3.010.0 3.016.0 0.0-13.4 Sample B Gr. beta 52.316.1 57.0i5.0 43.3-65.7 Sr-89 9.315.4 8.015.0 0.0-16.7 Sr-90 7.0t0.0 8.0tl.5 5.4-10.6 Cs-134 21.015.2 20.015.0 11.3-28.7 Cs-137 23.0i2.0 20.015.0 11.3-28.7 STW-570 Milk Apr 1989 Sr-89 26.0110.0 39.015.0 30.3-47.7 Sr-90 45.714.2 55.023.0 49.8-60.2 l Cs-137 54.016.9 50.015.0 41.3-58.7 K-40 1521t208 1600t80 1461-1739 A-13

Table A-1. (continued) Concentration in pC1/lb Lab Sample Date TIML Result EPA Respitd Code Type Collected Analysis t 2cc Is, N=1 Control Limits 9 STW-571 Water May 1989 Sr-89 40.7 6.015.0 0.0-14.7 Sr-90 5.0tl.0 6.021.5 3.4-8.6 STW-572 Water May 1989 Gr. alpha 24.012.0 30.018.0 16.1-43.9 Gr. beta 49.3115.6 50.015.0 41.3-58.7 STW-573 Water Jun 1989 8a-133 50.7tl.2 49.015.0. 40.3-57.7 Co-60 31.312.3 31.0t5.0 22.3-39.7 Zn-65 167t10 165117 135.6-194.4 Ru-106 123t9.2 128113 105.5-150.5 Cs-134 40.3t1.2 39tS 30.3-47.7 Cs-137 22.311.2 2015 11.3-28.7 STW-574 Water Jun 1989 H -3 4513t136 4503t450 3724'5282 STW-575 Water Jul 1989 Ra-226 16.813.1 17.7t2.7 13.0-22.4 Ra-228 13.813.7 18.312.7 13.6-23.0 STW-576 Water Jul 1989 U 40.311.2 41.0t6.0 30.6-51.4 STW-577 Water Aug 1989 l-131 84.7t5.8 '83.018.0 69.1-96.9 STW-579 Air Aug 1989 Gr. pipha 6.010.0 6.015.0 0.0-14.7 Filter Cs-137 10.312.3 10.015.0 1.3-18.7 STW-580 Water Sep 1989 Sr-89 14.711.2 14.015.0 5.3-22.7 Sr-90 9.7t1.2 10.0tl.5 7.4-12.6 STW-581 Water Sep 1989 Gr. alpha 5.0t0.0 4.0t5.0 0.0-12.7 Gr. Beta 8.7t2.3 6.015.0 0.0-14.7 6 A-14

Table A-1. (continued) Concentration in pC1/lb Lab Sample Date TIML Result EPA Resulta Code Type Collected Analysis 12ac Is, N=1 Control Limits STW-583 Water Oct 1989 Ba-133 60.3t10.0 59.016.0 48.6-69.4 Co-60 29.0 4.0 30.015.0 21.3-38.7 2 Zn-65 132.31 0 129.0113.0 106.5-151.5 6 Ru-106 155.326.1 161.0116.0 133.3-188.7 Cs-134 30.726.1 29.015.0 20.3-3/.7 Cs-137 66.31 6 59.015.0 50.3-67.7 4 STW-584 Water Oct 1989 H-3 3407i150 34961364 2866-4126 STW-585 Water Oct 1989 586 (Blind) Sample A Gr. Alpha 41.7i9.4 49.0112.0 28.2-69.8 Ra-226 7.910.4 8.411.3 6.2-10.6 Ra-228 4.4 0.8 4.110.6 3.1-5.1 U 12.0 0.0 12.026.0 1.6-22.4 Sample B Gr. Beta 31.712.3 32.015.0 23.3-40.7 Sr-89 13.314.2 15.015.0 6.3-23.7 Sr-90 7.012.0 7.013.0 4.4-9.6 Cs-134 5.0 0.0 5.015.0 0.0-13.7 Cs-137 7.010.0 5.015.0 0.0-13.7 STW-587 Water Nov 1989 Ra-226 7.910.4 8.711.3 6.4-11.0 Ra-228 8.911.2 9.311.2 6.9-11.7 STW-588 Water Nov 1989 U 15.020.09 15.016.0 4.6-25.4 4 Results obtained by Teledyne 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 Ve b All results are in the pCi/1, except for elemental potassium (K) gas, Nevada, data in milk, which are in mg/1; air filter samples, which are in pCi/ filter; and food, which is in og/kg. c Unless otherwise indicated, the TIML*results are given as the mean i 2 standard dcviations for three deteminations, d USEPA results are presented as the known values and expected laboratory precision (1s,1 deteminatien) and control limits as defined by EPA. 8 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

I Table A-2. Crosscheck program results, thermoluminescent dosimeters (TLDs). mR d Teledyne Average 12 o Lab TLD Result Known (all Code ' Type Measurement iZoa ValueC participants) 2nd International Intercomparisonb 115-2 CaFg:Mn Field 17.011.9 17.1 16.417.7 Bulb Lab 20.814.1 21.3 18.817.6 3rd International Intercomparisone CaF :Mn Field 30.713.2 34.924.8 31.513.0 115-3 2 Bulb Lab 89.616.4 91.7114.6 86.2124.0 2.. b 4th International Intercomparisonf 115-4 CaFg:Mn Field 14.111.1 14.111.4 16.019.0 Bulb Lab (Low) 9.311.3 12.212.4 12.017.6 Lab (liigh) 40.411.4 45.819.2 43.9113.2 Sth International Intercomparison9 CaF :Mn Field 31.411.8 30.016.0 30.2114.6 115-5A 2 Bulb Lab at 77.415.8 75.217.6 75.8140.4 beginning Lab at 96.615.8 88.418.8 90.7131.2 end

Table A-2. (Continued) mR Teledyne Average 120 d Lab TLD Result Known (al1 Code Type Measurement 12oa valuec participants) 115-5B LIF-100 Field 30.314.8 30.016.0 30.2114.6 Chips Lab at 81.117.4 75.217.6. 75.8140.4 beginning Lab at 85.4111.7 88.418.8-90.7131.2 the end 7th International Intercomparisonh 115-7A LIF-100 Field 75.412.6 75.816.0 75.1129.8 .T Chips O Lab (Co-60) 80.013.5 79.914.0 77.9127.6- . Lab (Cs-137) 66.612.5 75.013.8 73.0122.2 'CaF :Mn Field 71.512.6 75.816.0 75.1129.8 -115-78 2 Bulbs Lab (C0-60) 84.816.4 79.914.0 77.9127.6 Lab (Cs-137)-- 78.811.6 75.013.8 73.0122.2 115-7C CaSO :Dy Field 76.812.7 75.816.0 75.1129.8 4 -Lab (Co-60) 82$513.7 79.914.0' 77.9127.6 Lab (Cs-137 79.013.2 75.013.8 73.0122.2

Table A-2. (Ccntinued) aft Teledyne Average 22o d Lab TLD Result Known (all Code Type Measurement 22ca ValueC participants) 1 8th International Intercomparisoni 115-8A LiF-100 Field Site 1 29.511.4 29.711.5 28.9112.4 Chips Field Site 2 11.320.8 10.410.5 10.119.06 Lab (Cs-137) 13.710.9 17.210.9 16.216.8 CaF :Mn Field Site 1 32.311.2 29.711.5 28.9 12.4 115-8B 2 Bulbs Field Site 2 9.011.0 10.410.5 10.119.0 Lab (Cs-137) 15.810.9 17.210.9 16.226.8 115-8C CaSO :Dy Field Site 1 32.310.7 29.711.5 28.9112.4 4 Cards Field Site 2 10.610.6 10.410.5 10.119.0 h Lab (Cs-137 18.110.8 17.210.9 16.226.8 Teledyne Testingd 89-1 LiF-100 Lab 21.Ct0.4 22.4 Chips 89-2 Teledyne Lab 20.911.0 20.3 CaSO :Dy 4 Cards a Lab result given is the mean 12 s.tandard deviations of three determinations. b Second International Intercomparison of Environmental Dosimeters conducted in April of 1976 by the Health and Safety Laboratory (GASL), New Yort, New Yort, and the School of Public Health of the Uni-t versity of Texas, Houston, Texas. c Value determined by sponur of the 'intercomparison using continously operated pressurized ion chamber. d Mean 32 standard deviations of results obtained by all laboratories participating in the program.

Table A-2. (continu::d) mR d Teledyne Average 12o Lab TLD Resul t Known (all Code Type Measurement 2aa Valuec participants) Footnotes continued e Third International Intercomparison of Environmental Dosimeters conducted in sunner 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 Irternational 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 nvironmental Measurements Laboratory, New York, New York, U.S. Department of Energy. h Seventh International Intercomparison of Environmental Dosimeters conducted in the spring and saamer of 1984 at Las Vegas, Nevada, and sponsored by the U.S. Department of Energy, the U.S. Nuclear Regulatory Commission, and the U.S. Environmental Protection Agency. g 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. d Chips were submitted in September,1989 and cards were submitted in November,1989 to Teledyne Isotopes, Inc., Westwood, NJ for irradiation. e

7 I i Table h-3. In-house spiked samples, i Concentration in pC1/1' Lab Sample Date TIML Result Known Expect ed Code Type Collected Analysis n=3 . Activity Precision f 1s, n=38 QC-MI-6 Milk Feb. 1986 Sr-89 6.0*1.9 6.4*3.0 8.7 Sr-90 14.211.7 12.912.0 5.2 1-131 34.2*3.8-35.2i3;5 10.4 i Cs-134 32.011.8-27.3i5.0 8.7 Cs-137 35.8*2.1 35.015.0 8.7 QC-W-14 Water Mar. 1986 Sr-89 1.6*0.4 1.611.0 7.1 Sr-90 2.410.2 2.4t2.0 4.2' QC-W-15 Water Apr. 1986 I-131 44.912.4 41.5*7.0 10.6 Co-60 10.6*1.7 12.1*5.0 7.lb b Cs-134 30.2t2.4 25.8*8.0 7.l. Cs-137 21.911.9 19.9*5.0 7.lb QC-MI-7 Milk Apr. 1986 I-131 39.713.3 41.5t7.0 10.4 Cs-134-28.7*2.8 25.818.0-8.7 Cs-137 21.2*2.8 19.9*5.0 8.7 SPW-1 Water May 1986 Gross alpha 15.8tl.8 18.0*5.0 Sc QC-W-16 Water June 1986 Gross alpha 16.2*0.7 16.9*2.5 8.7 Gross beta 38.4t3.5 30.2i5.0 8.7 QC-MI-9 Milk June 1986 Sr-89 <1.0 0.0-7.lb b Sr-90 12.6*1.8 13.313.0 4.2 - I-131 38.9*7.0

34. 8i 7.0 10;4 Cs-134 33.013.4 36.115.0 8.7~

Cs-137 38.512.8 39.0*5.0 8.7 SPW-2 Water June 1986 - Gross alpha 16.811.8 18.015.0 Sc SPW-3 -Water June 1986 Gross alpha 17.7i0.8 18.0i5.0 Sc-QC-W-18 Water Sep. 1986 Cs-134 34.715.6 11.3*5.0 8.7 Cs-137 51.li7.0 '43.3i8.0 8.7 QC-W-19 Water Sep. 1986 Sr-89 13.6i4.1 15.6i3.5-7.lb 'Sr-90 6.411.6 6.2i2.0 4.2b A-20

l Thble-A-3. In-house spiked samples-(continued) Concentration in pCi/1 Lab Sample Date TIML Result Known - Expeitiil ' Code Type Collected Analysis n=3 Activity Precision is, n=3a QC-W-21 Water Oct.1986 C -60 19.2t2.2 18.513.0-8.7 Cs-134 31.725.2 25.618.0 8.7-Cs-137 '23.811.0 21.625.0 8.7 QC-MI-11 Milk Oct 1986 Sr-89 12.311.8 14.313.0-8.7 QC-W-20 Water Nov. 1986 H-3 .38552180 39601350- 520b QC-W-22 Water Dec. 1986 Gross alpha 9.8tl.4-11.214.0 8.7 Gross beta 21.7t2.0 23.815.0 8.7-QC-W-23 Water Jan. 1987 -I-131 29.8t2.5 27.923.0 10.4 QC-MI-12 Milk Jan. 1987 I-131 36.511.3 32.615.0 10.4 Cs-137 32.614.2 27.418.0 '8.7 QC-MI-13 Milk JadM987 Sr-89 10.4t2.1 12.2t4.0-

8. 7-Sr-90 14,6tl.6 12.623.0 5.2 1-131 49.511.2~

54.918.0-10.4 vc Cs-134 <1.6 - 0.0 '8.7 Cs-137 33.3t0.6 27.4t8.0 8.7 QC-W-24 Water Mar 1987 Sr-89 24.723.6 25.925.0 3.7 Sr-90 23.923.8 22.8t8.0 5.2 QC-W-25 Water Apr 1987 I-131 28.021.9 29.325.0 10.6 QC-MI-14 Milk Apr 1987 I-131 25.022.2 23.925.0 10.4 Cs-134 42.1 O.0 8.7 Cs-137 34.222.0 27.227.0 8.7 QC-W-26 Water Jun 1987 H-3 3422t100 3362t300 520 Co-60 24.821.4 26.527.0, 8.7 Cs-134 42,0 -0.0 8.7 Cs-137 21.220.5 21.617.0L 8.7 QC-W-27 Water Jun 1987 Gr. alpha 8.511.9 10.114.0 _8.7 Gr. beta 22.611.9 21.215.0 8.7 QC-W-28 Water Jun 1987 Gr. alpha 8.7tl.3 10.124.0 8.7 Gr. beta 12.215.2 9.413.0: 8.7 1 A-21 1

-Table A-3. In-house spiked samples (continued) Concentration in pC1/1-i Lab Sample Date TIML Result Known. Expected Code Type Collected Analysis n=3 Activity Precision 1s, n=3a QC-N-29 Water Jun 1987 Gr. alpha.16.411.3 18.915.0' 8.7 Gr. beta 15.914.0 11.814.0 8.7 l QC-MI-15' Milk Jul 1987 Sr-90 19.411.6 18.813.5 5.2 I-131 43.5i0.7 45.3t7.0 10.4 Cs-134 17.912.2 16.025.3 8.7 Cs-137 25.411.8 22.715.0 8.7-QC-W-30 Water Sep 1987 Sr-89 17.5t3.0 14.3i5.0 8.7 Sr-90 18.4*2.2 17.Si2.2 5.2 QC-W-31 Water Oct 1987. H-3 20531939 20592306 520 QC-W-32 Water-Dec 1987 Gr. alpha 8.621.0 '10.125.0 8.7 Gr. beta 15.210.1 ~13.123.0 8.7 QC-W-33 Water Dec 1987 Gr. alpha ~7.721.4 10.li5.0-8.7. Gr. beta 10.9*1.0 -7.9t3.0 8.7 QC-W-34 Water Dec 1987 Gr. alpha ~ 4.0 0.9-5.113.0 '8.7 Gr. beta'- 9.410.9 7.913.0-8.7 QC-MI-16 Milk Feb 1988 Sr 31.814.7 31.716.0 8.7 Sr-90 25.5i2.7 27.813.5 5.2 I-131-26.4 0.5' 23.215.0 10.4 Cs-134 23.812.3 24.226.0 8.7 Cs-137 26.5*0.8 25.116.0 8.7 QC-MI-17 Milk Feb 1988-I-131 10.6tl.2 14.321.6 10.4 QC-W-35 Water Feb 1988 I-131 9.711.1-11.6*1.1 10.4 QC-W-36 Water Feb 1988 I-131 10.511.3 11.611.0 10.4 QC-W-37 . ater Mar 1988 Sr-89 17.112.0 19.818.0. 8.7 W Sr-90 18.720.9 17.315.0 5.2 QC-MI-18 Milk Mar 1988 'I-131 33.212.3 26.715.0 10.4 Cs-134 31.322.1 30.215.0 8.7 Cs-137 29.921.4 26.225.0 8.7 A-22

. o/ ' j Table A-3. In-house spiked samples (continued) %)ncentration in pC1/1 l Lab Sample Date TIML Result Known E:pected Code Type Collected Analysis n=3 Activity Precision 1s, n=3a QC-W-38 Water Apr 1988 I-131 17.111.1 14.215.0 10.4 QC-W-39 Water Apr 1988 H-3 4439231 41761500 -724 QC-W-40 Water Apr 1988 Co-60 23.710.5 26.1*4.0 8.7 Cs-134 25.412.6 29.224.5 8~ 7 Cs-137-26.612.3' 26.214.0 8.7. QC-W-41 Water Jun 1988 Gr. alpha 12.310.4 13.115.0

8. 7.-

Gr beta-22.611.0 20.115.0' 8.7 QC-MI-19 Milk Jul 1988 Sr-89 -15.111.6 16.415.0-8.7 Sr-90 18.020.6 18.325.0 5.2 I-131 88.414.9 86.618.0-10.4 Cs-137 22.710.8 20.816.0-8.7 QC-W-42 Water Sep 1986 Sr-89 48.513.3 50.828.0 ~8.7-Sr-90 10.921.0 11.4i3.5 5.2 QC-W-43 Water Oct 1988 Co-60 20.923.2 21.413.5 8.7-Cs-134 38.7*1.6 38.016.0 8.7 Cs-137 19.012.4 21.013.5 8.7 QC-W-44 Water Oct 1988 I-131 22.210.6 23.3i3.5 10.4 QC-W-45 Water Oct 1988 H-3 4109143-41531500 724 QC-MI-20 Mil k Oct 1988 I-131 59.810.9 60.619.0 10.4 Cs-134 49.611.8 -48.617.5 8.7 Cs-137 25.824.6 24.7t4.0 8.7 QC-W-46 Water Dec 1988 Gr. alpha 11.512.3 15.215.0 8.7 Gr. beta 26.512.0 25.715.0 8.7 QC-MI-21 Milk Jan 1989 Sr-89 25.5110.3 34.0210.0 817 Sr-90 28.313.2 27.113.0 5.2 1-131 540213 550120 10.4 Cs-134 24.5 2.6 22.615.5 8.7 Cs-137 24.020.6 20.515.0 8.7 i A-23

Table A-3. In-house spik;d-samples (ccntinu;d) Concentration in p.1/1 Lab Sample Date TIML Result Known Expected Code - Type' Collected Analysis n=3 Activity Precision 1s,'n=3a- -QC-W-47 Water . Mar 1989 Sr-89' 15.223.8 16.115.0-8.7 St-90 16.421.7 16.923.0 5.2 QC-MI-22 Milk Apr 1989 I-131 36.311.1 37.225.0 .10.4 Cs-134 20.812.8 20.718.0 8.7 Cs-137 22.212.4 20.428.0 8.7 QC-W-48 Water Apr 1989 Co-60 23.512.0 25.118.0 8.7 Cs-134 24.211.1 25.918.0 8.7 i Cs-137 23.611.2 23.018.0 8.7 QC-W-49 Water Apr 1989 I-131 37.213.7-37.215.0 .10.4 QC-W-50 Water Apr 1989 H-3 3011159 30891500 724 QC-W-51 Water Jun 1989 Gr. alpha 13.011.8 15.015.0 8.7 Gr. beta 26.011.2 25.528.0 8.7 QC-MI-23 Milk Jul 1989 Sr-89 19.416.5 22.0110.0 8.7 Sr-90 27.613.5 28.613.0 5.2 1-131 46.823.2 43.415.0 10.4 Cs-131 27.411.8 28.316.0 8.7' Cs-137 24.111.8 ~20.826.0 8.7 QC-MI-24 Milk Aug 1989. Sr-89 25.422.7 27.2210.0 8.7 Sr-90 46.011.1-47.819.6 8.3 QC-W-52 Water Sep 1989 l-131 9.620.3 9.721.9 10.4 _ ater Sep 1989 I-131 19.0 0.2 ~20.924.2 -10.4 QC-W-53 W QC-W-54 Water Sep 1989 Sr-89 25.824.6 24.724.0 8.7 Sr-90 26.5 5.3' 29.7 5.0 5.2 a n=3 unless noted otherwise. b n=2. c n=1. A-24

e -o Table A-3. In-house spiked samples (continued) Concentration in pC1/1 Lab Sample Date TIML Result Known Expected Code Type Collected Analysis n=3 Activity Precision 15, n=3a, QC-MI-25 Milk Oct 1989 I-131 70.013.3 73.Si20.0-10.4-Cs-134 22.112.6 22.6t8.0 8.7 Cs-137 29.411.5 27.518.0 8.7 QC-W-55 Water Oct 1989 I-131 33.311.3-35.3210.0 10.4 QC-W-56 Water Oct 1989-Co-60 15.210.9 17.415.0 8.7 Cs-134 22.124.4= 18.918.0 8.7 Cs-137 27.211.2 22.918.0-8.7 QC-W-57 Water Oct 1989 H-3 3334122 3379tS00: 724 QC-W-58 Water Nov 1989 -Sr-89 -10.911.4d 11.1tl.0d 8.7 d Sr-90 10.421.0 ~ 10.3tl.0d 5.2 d QC-W-59 Water Nov 1989 Sr 101.016.0 - 104.lt10.5d -17.5 Sr-90 98.013.0d 95.0t10.0d 17,0 QC-W-60 Water Dec 1989 Gr. alpha 10.8*1.1 10.6t4;0 8.7 Gr. beta 11.610.5 11.414.0:- 8.7-a n=3 unless noted otherwise. b n=2. c n=1. d Concentration in pC1/ml-A-25 -l i l

Table A-4. In-house " blank" samples. Concentration in pC1/1 Acceptance Lab Sample Date Results Criteria Code Type Collected Analysi s (4.660-) (4.66o ) BL-1 D.I. Water Nov. 1985 - Gross alpha <0.1 <1 Gross beta <0.4 <4 BL-2 D.I. Water Nov. 1985 Cs-137 (gamma) <1.9 (10 BL-3 D.I. Water Nov. 1985 Sr-89 <0. 5 <5 Sr-90 <0.6 .1 BL-5 D.I. Water Nov. 1985 Ra-226 <0.4 <1 Ra-228 <0.4 <1 --SPW-2265 .D.I. Water-- Apr. 1985 Gross alpha <0.6 <1 Gross beta <2.2 <4 Sr-89 <0. 2 <5 Sr-90 <0.4 <1 1-131 <0.2 <1 Cs-137 (gamma) <7 4 <10 BL-6 D.I. Water Apr 1986 Gross alpha- ,<0.4 <1 BL-7 D.I. Water Apr. 1986 Gross-alpha <0.4- <1 BL-B D.I. Water June 1986 Gross alpha <0.4 <1 BL-9 D.I. Water June 1986 Gross alpha <0.3 <1

SPW-3185 D.I. Water Jan 1987 Ra-226

<0.1 <1 Ra-228 <0.9 <1 SPS-3292 Milk Jan 1987 I-131 < 0.1 '- <1 Cs-134 <6.2 <10 Cs-137 -<6.4 <10 SPW-3554 0.I. Water Feb 1987 H-3 <180 <300 Gross beta- <2.6 <4 - SPS-3555 Milk Feb 1987 Sr-89 '<0.6 <5 Sr-90 1.9 0.4a- - <1 SPS-3731 Milk Mar 1987 Cs-134 <2.2 <10 - Cs-137 <2.5 <10 a low level (1 - 5 pCi/1) of Sr-90 concentration in milk is not unusual, td A-26

Table A-4. In-house ' blank" samples (continu:d). Concentration in pC1/1 i Acceptance .) Results Criteria Lab Sample Date _ Analysi s (4.660 ) (4.66o ) i Code Type Coll ected SPS-3732

0. I. Wa ter Mar 1987 Sr-89

<0.9 <5 I Sr-90 <0.8 <1 l-131 -<0.3 <1 1 Co-60 <2.3 <10 1 Cs-134 <2.2 <10 Cs-137 - <2.4 <10 Ra-226 <0.1 1 Ra-228 <1.0 <1 Np-237 <0.04 <1 Th-230 (0.05 <0.1 i Th-232 <0.02 <0.1 U-234 <0.05 (0.1 U-235 <0.03 <0.1 U-238 <0.03 <0.1 ' SPS-4023 Milk May 1987 I-131 <0.1 <1 SPS-4203 D.I. Water May 1987 Gross alpha <0.7 <1 Gross beta <1.7 4 SPS-4204 Milk May 1987 Sr-89 . 0.5_ (5 Sr-90 2.4 0.6a <1 l SPS-4390 Milk Jun 1907 Cs-134 <4.7 <10 Cs-137 <5.2 <10 SPS-4391 0.I. Water Jun 1987 Sr-89 <0.4 <5 Sr-90 <0.4 <1 1-121 <0.1 <1 Co-60 <3.8 <10 Cs-137 <5.7- <10 Ra-226 <0.1 <1 Ra-228 <0.9 <1 SPW-4627 D.I. Water Aug 1987 Gross alpha <0.6 <1 Gross beta <1.4 <4 Tritium <150 SPS-4628 Milk Aug 1987 Sr-89 <0.6 <5 Sr-90

2. 4t 0.6 a

<1 SPS-4847 Milk Sep 1987 Cs-134 <4.4 <10 Cs-137 <5.3 <10 a Low level (1 - 5 pCi/1) of Sr-90 concentration in milk is not unusual. A-27

Table A-4. - In-house " blank" samples (continued). Concentration in pCi/1 Acceptance Lab b,mpl e Date Results Criteria Code ~fype Collected Analysis -(4.663 ) (4.66o ) l SPS-4848-D.I. Water Sep 1987 I-131 (0.2 <1 SPW-4849 D.I. Water Sep 1987 Co-60 <4.1 = <10 Cs-134 <4. 8 <10 Cs-137 <4.0 <10-Sr <0. 7 <5 Sr-90 <0.7 <1 .SPW-4850 0.1. Water Sep 1987 Th-228 <0.04 <1 Th-232 <0.8 <1 U-234 -<0.03 <1-U-235- <0.03 <1 U-238 <0.02- <1 Am-241 <0.06 <1 Cm-242 <0.04 <1 Ra-226 <0.1 <1 Ra-228 <1.0 <2 - SPW-4859 D.I. Water Oct 1987 Fe-55 <0. 5 <1 SPS-5348 Milk Dec 1987 Cs-134 <2.3 <10 Cs-137- <2.5 <10 SPW-5384 D.I. Water Dec 1987 Cc-60 <2.8 <10; Cs-134 <2.6 <10 Cs-137 <2.8 <10 I-131 <0. 2 <1 Ra-226 <0.1 - <1 Ra-228 <1.2 <2-Sr-89 <0.5' <1 Sr-90 <0.4 <1 SPW-5385 D.I. Water Nov 1987 Gr. alpha- <0.4 <1 Gr. beta <2. 2 <4 Fe-55 <0.3 <1 SPS-5386 Milk Jan 1988 I-131' <0.1 <1 1 SPW-5448 " Dead" Water Jan 1988 H-3 <177 <300 l A-28

W Table A-4. In-house " blank" samples (continued). Concentration-in pC1/1 Acceptance Lab Sample Date Results Criteria Code Type Collected Analysis (4.66a ) (4.66a.) SPS-5615 Milk Mar 1988 Cs-134 <2.4 <10 Cs-137 <2.5 s10 1-131 <0. 3 <1 Sr-89 <0. 4 <5 Sr-90 2.410.Sa <1 SPS-5650 0.I. Water Mar 1988 Th-228 (0. 3 - >1 Th-230 <0.04 <1 Th-232 (0.05 <1 U-234- <0.03 <1 U-235 <0.03 <1 U-238 <0.03 <1 An-241 (0.06 -<1 Cm-242 <0.01- <1 Pu-238 <0.08' <1 Pu-240 (0.02 <1 SPS-6090 Milk Jul 1988 Sr-89 <0. 5 <1 Sr-90 1.8 0.Sa <1-I-131 <0.4 <1 Cs-137 <0. 4. <10 SPW-6209 Water Jul 1988 Fe-55 <0.8 <1 SPW-6292 Water Sep 1988 Sr-89 <0.7 <1 Sr-90 <0.7 '1 SPS-6477 Milk Oct 1988 I-131 <0.2 <1-Cs-134 <6.1 <10 Cs-137 <5.9 <10 SPW-6478 Water Oct 1988 I-131 (0. 2 <1 SPW-6479 Water Oct 1988 Co-60 <5. 7 <10 Cs-134 <3.7 <10 Cs-137 <4. 3 <10 SPW-6480 Water Oct 1988 H-3 <170 <300 SPW-6625 Water Dec 1988 Gr. alpha <0.7 <1 Gr. beta <1.9 <4 j a low level (1 - 5 pC1/1) of Sr-90 concentration in milk is not unusual. A-29 4 m

Table A-4. In-house

blank" samples (contin:ed).

Concentration in pCi/1 Acceptance f Lab Sample Date Results Criteria i Code Type Collected Analysis (4.660 ) (4.660 ) i i SPS-6723 Milk Jan 1989 Sr-89 <0.6 (5 Sr-90 1.9 0.5a <1 1-131 <0.2- <1 Cs-134 <4. 3 <10 Cs-137 <4.4 (10 SPW-6877 Water Mar 1989 Sr-89 <0.4 <5 Sr-90 <0. 6 <1 ^ SPS-6963-Milk Apr 1989 I-131 <0.3 <1 'Cs-134 <5.9 <10 . 10 Cs-137 <6.2-SPW-7561-Water Apr 1989 H-3 <150 <300 SPW-7207 Water Jun 1989 Ra-226 <0.2 <1 Ra-228 <0.6 <1 'SPS-7208 Milk Jun 1989 'Sr-89 <0.6 <5 Sr-90 2.1 0.5a <1 1-131 <0.3 <1 Cs-134- <6.4 <10 3 Cs-137 <7.2 <10 SPW-7558 Water Jun 1989 Gr. alpha <0.2 <1-Gr. beta <1. 0 '. <4 SPS-7322 Milk Aug 1989 Sr-89 <1.4 <5, Sr-90 4.8tl.0a <1 I-131 <0.2- <1 Cs-134' <6.9 <10 Cs-137 <8.2 <10 SPW-7559 Water - Sep 1989 Sr-89 <2.0 <5 Sr-90 <0. 7, <1 SPW-7560 Water Oct 1989 I-131 <0.1 <1.0 SPW-7562 Water Oct 1989 H-3 <140 <300 SPS-7605 Mil k Nov 1989 I-131 <0.2 <1 Cs-134 <8. 6 <10 Cs-137 <10 <10 SPW-7971 Water Dec 1989 Gr. alpha <0.4 <1 Gr. beta <0.8 <4 a tow level (15 pC1/1) of Sr-90 concentration in milk is not unusual. A-30

TIML. BLIND-01 Revision 0,-12-29-86 ATTACHMENT B ACCEPTANCE CRITERIA FOR " SPIKED" SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION YALUES FOR VARIOUS ANALYSESa One Standard Deviation Analysis Level for Single Determination Gamma Emitters 5 to 100 pCi/ liter or kg 5 pCi/ liter >100 pC1/ liter oi' kg 5% of,known value Strontium-89b 5 to 50 pCi/ liter or kg 5 pCi/ liter >50 pCi/ liter or kg 10% of known value Strontium-90b 2 to 30 pCi/ liter or kg 3.0 pC1/ liter >30 pC1/ liter of kg 10% of known value Potassium >0.1 g/ liter or kg 5% of known value Gross Alpha <20 pC1/ liter 5 pCi/ liter >20 pCi/ liter 25% of known value Gross Beta <100 pCi/ liter 5 pCi/ liter >100 pCi/ liter 5% of known value Tritium <4,000 pCi/ liter is=(pci/ liter).'=- 169.85 x (known).0933 >4,000 pCi/ liter 10% of-known yalue Radium-226, <0.1 pCi/ liter 15% of known value Radium-228 Plutonium 0.1 pCi/ liter, gram, 10% of known value or sample Iodine-131, b <55 pCi/ liter 6 pCi/ liter Iodine-129 >55 pCi/ liter 10% of known value Uranium-238, <35 pCi/ liter 6 pCi/ liter Nickel-630, >35 pCi/ liter 15% of known value Technetium-99b Iron-55b 50 to 100 pCY/ liter 10 pCi/ liter 10% of known value a From EPA publication, " Environmental Radioactivity Laboratory Intercompari-4 s n Studies Program, Fiscal Year 1981-1982, EPA-600/4-81-004. b TIML limit. I A-31 1

4 ADDEllDull TO APPEll0lX A The following is an explanation of-the reasons why certain samples were outside the control -limit specified by the Environmental Protection Agency for the Interlabora-tory Comparison Program starting January 1987. EPA Lab Code Analysis _ T!!!L Result Control Limit Explanation STil-504 Sr-89 57.024.3 60.3-77.7 flilk had high-fat content which Sr-90 32.011.0 32.4-37.6 made analyses difficult. Ad-dition of errors to TIllL result would put values within EPA control limits. EPA also had, the same problem in analyzing its own sample. STW-511 Ra-228 8.121.4 4.6-8.0 TIllt results are usually within EPA control limits. Analysis of the next sample was within EPA control limits, tio fur:her action is planned. STW-516 Cr-51 80.3217.5 61.3-78.7 Results-in the past have been within EPA control limits and TIttL will. monitor the situation in the future. ST F-524 K 1010.71158.5 1123.5-1336.5 Error in transferrance of data. Correct data was 1105133. Results in the past have been within the limits and TIllt will monitor the situation -in the future. STW-532 1-131 9.012.0 6.2-8.8

Sample recounted af ter 12 days.

The average result was 8.821.7 (within EPA control limits). The sample was recounted in order to check _ _the decay. Results in the past have been within the limits and TIHL will continue to monitor the situ-ation in the future. STW-534 Co-60 63.321.3 41.3-58.7 High level M Co-60 was due to contamination of beaker. Beaker was discarded upon dis-cove ry of contamination and sampie was recounted. _ Recount results were 53.223.6 and 50.9 2.4. i i ) A-32

t ADDENDUM T0 APPENDIX A (continued) i EPA Lab Code Analysis TIML Result Control Limit Explanation-j i STM-554 Sr-90 51.022.0 54.8-65.2 The cause of low result was due to very high fat content in the mil k. It should be noted that 63% of L all participants failed this test. Also, the average for al1 participants was-54.0 pCi/1 -before the Grubb_ and 55.8.pCf /1 af ter the Grubb., STW-560 Pu-239 5.811.1 3.5-4.9 The-cause of high results is ~ not known. It is suspected that t the standard was not properly-calibrated by supplier and is- .under investigation. New Pu-236 standard was obtained 4 and will be used for the next test. STW-568 Ra-228 2.6tl.0 2.7-4.5 The cause of low results is not known. Next EPA crosscheck ' re suits were' within the-- control limits. No further action is planned. j STM-570 Sr-89 26.0210.0 30.3-47.7 The cause of low ' results was Sr-90 46.724.2 49.8-60.2 falsely high recovery-due to suspected i ncompl ete calcium -removal. Since EPA sample was ~ used up, internal spike was pre-i pared and analyzed. The results were within control limits (See table A-3, sample -QC-MI-24). No further action is. planned. u d A-33 l q

+ 1 f I 4 P . t .r ? Appendix B Data Reporting Conventions W t e w D B-1 w m

Data Reporting Conventions t 1.0. All activities,except gross alpha and gross beta, are decay corrected to collection time or the end of the collection period. 2.0. Single Measurements Each single measurement is reported as follows: x t-s where x = value of the measurement; s = 2a counting uncertainty.(corresponding to the 95% confidence level). In cases where the activity is found to be below the lower limit of detection L it is reported as <L 5 where L = is the lower limit of detection based on 4.66o uncertainty for a background sample. 3.0. Duplicate Analyses 185 3.1. Individual results: x1 i si x2 i s2 Reported resuit: 'x i s where x = (1/2) (x1 + x2) 2, 3l s=(1/2) s 3.2. Individual results: <ll <l2 Reported result:. <L where L = lower of L1 and L2 3.3. Individual results: xis y <L 4 Reported result: x i s if x > L; <L otherwise B-2

s 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 li and sttndard deviation (s) of a set of n numbers x1, x2 Xn are defined as follows: n Xu {X I(x-li)2 3, 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 on'e if it is an odd number or it is kept unchanged if an even number. As an example, 11.435 is rounded off to 11.44, while 11.425 is rounded off to 11.42. B-3 1 l j

9 is s Appendix C Maximum Permissible Concentrations of Radioactivity in Air and Water Above Background -in Unrestricted Areas e 'f C-1 1

4 l Table C-1. Maximum permissible concentrations of radioactivity in air and water above natural background in unrestricted areas.a i Air Water Gross alpha 3 pCi/m3 Strontium-89 3,000 pCi/1 - Gross beta 100-pC1/m3 Strontium-90 300 pCi/1 Iodine-131b 0.14 pCi/m3 Cesium-137 20,000 pCi/1 Barium-140 20,000 pCi/1-Iodine-131 300 pC1/1 Potassium-40c 3,000 pCi/1 Gross alpha 30 pCi/1 Gross beta 100 pCi/1 Tritium 3-xl106 pCi/1 " Taken f rom Code of Federal Regulations Title 10, Part 20, Table 11 and appro-- priate footnotes. Concentrations may be averaged over a period not greater than one year. b ? From 10 CFR 20 but adjusted' by a f actor of 700 to reduce the dose resulting from the air-grass-cow-milk-child pathway. c A natural radionuclide. t 9 4 h 9 i j i ~ C-2

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'4 i I H4 Rev.'ll Page 66. -j FIGURE 5.1-1 SITE BOUNDARY TLD LOCATIONS l .I 4 i A-R- O \\ dt STUR DN I O C 0' = j. j. ma a k_ Ib N Y-N y._ _ "I II OREST SOY. . eq . 10A I ( cle-D- p. ,l, y lI0 A n.n / s 15 w / I i suesTan yyx w> gg < y.,* r ay l Y h' g ;$(a7A g- },"au ' " 1" ./- l1; on, = E N \\ 4 ~- 25 I , 06A [' \\ I %9 l l 5A, 1 + west ... _._ M g g F LAKE _. s g q, g "-- N e ( o 09 792 5%( [ a G L c,, O K 'n O H I \\ J PLANT AREA ENLARGED PLAN (1.00 MILE RADIUS) (NO SCALE) NL-99P!739-1

l- .o FIGURE 5.1, RADIOLOGICAL - ENVIRONMENTAL. SAMPLE-POINTS - WITHIN Rev. 11 Page 67 10 - MILE RADIUS \\ \\ q, h928 ( 91B s s q 1 s, s -i$ .:.....asJ c . q. m;y i, q ~ /- ~ 6r $ .g s .t 1, ] b tP 18 pts f 85S( o L 1:5.0 1 j. r-858-t c 43 .Z " l. 045 ?, n -g L g p/ '* P ,,83S 12e P g 3 1 i yg 118 w r u / IBB h BBS

== [k[ MONITORING LEGDO 890 @ CULTIVATED CROP SAMPLING POINT g l 4 [ NATER & MILK SAMPLING POINTS h river SECIMENT. FISH AND PERJPMYTON CR INVERTEBRATES N.S.P. TLD PO!NTS G s.s.P. ala McNITmING Pc:nts l NL-99P1739-2

o-H4 FIGURE 5.1-3 Rev.:-11 Page 68 RADIOLOGICAL ENVIRONMENTAL SAMPLE POINTS 4 OUTSIDE 10 MILE RADIUS gnseATT AWE-til 23 *- i_- 1 7 ~ 8 O P25 ,? g I E5 / P1 3 ( CONTROL POINTS PRESCOTT, WISCONSIN .0 MONIT(R!NO LEGEM) Q CULTIVATED CROP SAPPLING POINT [ VATER & MILK SMfLING POINTS h R1vER SEDIMENT.F1SH AND PERIPHYTON OR INYERTEBRATES h N.S.P. TLD POINTS h N.S.P. AIR MONITCRING POINTS ' NL-99P1739-3 1 i - _ _ _ _ _ _ _ _ _ _ - _}}

ML20042E811

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