ML20205Q585

Annual Radiation Environ Monitoring Program for 1986

ML20205Q585
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Site:	Prairie Island
Issue date:	12/31/1986
From:	Huebner L TELEDYNE ISOTOPES MIDWEST LABORATORY
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'E $lI7 PRAIRIEISLAND NUCLEAR GENERATING PLANT

Red Wing, Minnesota UNITS 1 AND 2 I

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aalMME APCLil e jlf, PAUL

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ANNUAL REPORT to the UNITED STATES NUCLEAR REGULATORY COMMISSION Radiation Environmental Monitoring l'rogram January 1, 1986 thru December 31, 1986 3 ',

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NORTHERN STATES POWER COMPANY Mlfit1E APOLIS. MlflflESOTA l

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NORTHBROOK, IL 60062-4197 Q12) 5644700 NORTHERN STATES POWER COMPANY MINNEAPOLIS, MINNES0TA PRAIRIE ISLAND NUCLEAR G'.NERATING PLANT Docket No. 50-282 License No. OPR-42 50-306 DPR-60 ANNUAL REPORT to the l UNITED STATES NUCLEAR REGULATORY COMMISSION Radiation Environmental Monitoring Program January 1, 1986 to December 31, 1986 l

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l Prepared Under Contract l by TELE 0YhE ISOTOPES MIDWEST LABORATORY Project No. 8010 l

Approved by: g

. G. Huebner

' [GeneralManager l

l 4 March 1987

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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 & Regulatory Activities Department.

The report was prepared by L. G. Huebner, General Manager, Teledyne Isotopes Midwest Laboratory. He was assisted in the report preparation by other staff i members of this laboratory, i

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TABLE OF CONTENTS l

l Section P_ age Preface ........................... 11 List of Tables . . . . . . . . . . . . . . . . . . . . . . . . iv

1.0 INTRODUCTION

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SUMMARY

........................... 2 3.0 RADIATION ENVIRONMENTAL MONITORING PROGRAM (REMP) ...... 4 3.1. Program Design and Data Interpretation ......... 4 3.2 Program Description . . . . . . . . . . . . . . . . . . . 5 3.3 Program Exec ut ion . . . . . . . . . . . . . . . . . . . . 7

3. 4 Laboratory Procedures . . . . . . . . . . . . . . . . . . 7 3.5 Program Modifications . . . . . . . . . . . . . . . . . . 8 3.6 Land Use Census . . . . . . . . . . . . . . . . . . . . . 8 4.0 RESULTS AND DISCUSSION . . . . . . . . . . . . . . . . . . . . 9 L 4.1 Atmospheric N9 clear Detonations and Nuclear Accidents . . . . . . . . . . . . . . . . . . . 9 4.2 Program Findings .................... 10

5. 0 TABLES . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15

6.0 REFERENCES

CITED . . . . . . . . . . . . . . . . . . . . . . . 28 APPENDICES A Interlaboratory Comparison Program Results . . . . . . . . . . A-1 i

B Data Reporting Conventions . . . . . . . . . . . . . . . . . . B-1 C Maximum Permissible Concentrations of Radio-activity in Air and Water Above Natural Background in Unrestricted Areas . . . . . . . . . . . . . . C-1 111

LIST OF TABLES No. Title P_aage 5.1 Sample Collection and Analysis Program,1986 . . . . . . . . . 16 5.2 . Sampling Locations . . . . . . . . . . . . . . . . . . . . . . 18 5.3 Missed Collections and Analyses,1986 ............ 20 5.4 Environmental Radiological Monitoring Program Summary .... 21 In addition, the following tables are in the Appendices:

Appendix A A-1 Interlaboratory Comparison Program Results, 1984-1986 .... A-3 A-2 InterlaboratoryComparisonProgramResults(TLDs) ...... A-11 A-3 In-house Spiked Samples ................... A-14 A-3 In-house " Blank" Samples . . . . . . . . . . . . . . . . . . . A-16 Appendix C C-1 Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas . . . . . . . . . . . . . . . . . . . . . C-2 iv

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1.0 INTRODUCTION

s 's; This report summarizes and interpr'e s 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, 1986. This program monitors the levels of radioactivity in the air, terrestrial, and aquatic environments in order to assess the impact of the plant on its turroundings.

Tabulations of the individual analyses made during the year are not included '

in this report. These data are included in . a reference document (Teledyne Isotopes Midwest Laboratory, 1986) available at,korthern States Power' Comps.ny, Nuclear Generation Department.

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Prairie Island Nuclear Generating Plant is located on the Mississippi River in Goodhue County, Minnesota, and operated by Northern States Power Company. The plant has two 550 MWe pressurized water reactors. Unit 1 acnieved initial criticality on 1 December 1973. Commercial operation at full power began on 16 December 1973. Unit 2 achieved initial <riticality on 17 Dece.rder 1974.

Commercial operation at full power began on 21 December 1974.

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. i j , 2.0 SUMARY u

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l . ,The Radiation EnvKieonmental Monitoring Program -(REMP) required bhthe U.S.

9 duelear Regulatory Commission (NRC) Technical--Specifications - for tha' Prairie,'

Island Nuclear Generating '

Plant ~1s described. Results. for 1986 are summarized .

and discussed. --

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PNgram findings show' background levels of radioactivity in the environmental sampics- collected in the vicinity of'the Prairie Island Nuclear. Generating. '

Plant.. No effect on the environment due to the operation of t6e p'lant is indicated. ,

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There was -3 small effect on ravironmental ' radioactivity resulting from an accident at the Chernobyl Nuclear Reactor (USSR) on April 26p 1986. The (

sampling media affected were air and milk. The effect is discussed below.

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l Air Particuides _ ,

s Gross tUta activity in air particulites collected between May 19, 1986 and Junc 9, 1986 nad elevated icvels ranging from 0.091 to 0.511 pCi/mJ and '

, s averaged u.US JCi/m3 for all locnions. In comparison,' gross I, eta activity for ??86, uc! >sive of the period between May 19, 1986 and June 9,1986, averaged 0.025 pC'/m 3 , the stae as the average for 1985.

Tamma spectroscc'pic analyrcs of the secont quarter composites * =thowed the grcsence of thr.ee is-topes: Ru-103, Cs-134, and Cs-137, - averaging 0.017, u.0068, and 0.018 pCi/m3, respective y. These isotopes were below their respective LLD levels in the " test . third, and 't'ourth quarter composites.

! Airborne,loding Iodine-131wasdetected,innine(9)samilescollectedbetweenMay 19, 1986 and

. May 27, 1996. The activity ranged. from 0.12' to 0.48 pCi/m3 and averaged 0.30 pC1/a3 for all samples. Iodine-131 was below the LLD level of- 0.07 pCi/mr in<tne rest of the samples r.011ected in 1986.

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Milk

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Of sixty-six (66) samples analyzed, seventeen (17). samples collected between-May 19 and July 15, 1986 had detectable I-131 in various concentrations. The?

-concentrations ranged' from 1.1 to 75.7 pCi/l and averaged 22.9 pCi/1 for all '

samples with detectable levels. ~ The I-131 concentrations in the rest of the samples collected in 1986 were below the LLD_ level of.1.0 pCi/1.

During the period of June 2 to July 15,1985, Cs-137 was detected in six :(6) samples. The concentrations ranged from 15.1 to 21.4 pCi/1 and averaged -

17.8 pCi/1.- In the ~ rest of _ the samples collected in 1986, the -Cs-137 concen-trations were below the LLD leve1~ of ~15 pC1/1.

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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 indicator locations (nearby, downwind, or downstream) and at control locations (distant, upwind, or upstream). A plant effect would be indicated if the radiation level at an indicator location was signifi-cantly larger than that at the control location. The difference would have to be greater than could be accounted for by typical fluctuations in radiation levels arising from other sources.

An additional interpretive technique involves analyses for specific radionuclides present in the environmental samples collected from the plant site. The plant's monitoring program includes analyses for tritium and iodine-131. Most samples are also analyzed for gamma-emitting .

isotopes with results for the following groups quantified: zirconium-95, 4

cesium-137, cerium-144, beryllium-7, and potassium-40. The first three gamma-emitting isotopes were selected as radiological impact indicators because of the different characteristic proportions in which they_ appear in the fission product mix produced by a nuclear reactor and that pro-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 calibration monitors and should not be considered radiological impact indicators.

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

-106, cesium-134, barium-lanthanum-140, and cerium-141. These isotopes are released in small quantities by nuclear power plants, but to date their major source of injection into the general environment has been

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

Other means of distinguishing sources of environmental radiation can be employed in interpreting the data. Current radiation levels can be compared with previous levels, including those measured before the Plant became operational. Results -of the plant's monitoring program can be related to those obtained in other parts of the world. Finally, results can be related to eveats known to cause elevated levels of radiation in the environment, e.g., atmospheric nuclear detonations.

3.2 Program Description

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The sampling and analysis schedule #or 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 I 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, 1986).

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

airborne iodine is collected by continuous pumping through charcoal l filters at all of these locations. Filters are changed and counted I 5

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weekly. Particulate filters are analyzed for. gross beta activity and.

charcoal filters for 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). One of the indicators (P-3) is located near the residence expected to be most susceptible to any atmospheric emissions from.the plant-(highestD/Qresidence).

As a " Lessons Learned" commitment, ambient gamma radiation is moni-tored at thirty-two . (32) locations, using three (3) LiF2 chips -at each location: ten (10) in. an inner ring in the general area of the site boundary, fifteen (15) in the outer. ring-within 4-5 mile radius,'six.(6) i at special interest locations and one control location,11.1 miles -

distant from the plant. They are replaced and measured quarterly. Also, a complete emergency set of TLDs for all locations is placed in the. field at the same time as regular sets. The emergency set is returned to TIML quarterly for annealing.and repackaging.

Milk samples are collected monthly from five farms ~ (four indicator and onecontrol). If the milch animals are on pasture; the milk is collected biweekly during . the growing season (May November). All samples- are analyzed for iodine-131 and gamma-emitti g isntnpes, In :ddition, goat's milk is occasionally collected in the vicinity of the plant arid analyzed for iodine-131.

For additional monitoring of the terrestrial- environment, leafy green vegetables (cabbage) are collected annually from the highest D/Q garden 4 and a control location (P-25) and analyzed for iodine-131. Corn is i collected annually only from fields irrigated with river water and a

! control location (P-25) and analyzed for gamma-emitting isotopes. .Also, well water is collected quarterly from four- locations and analyzed for tritium and gamma-emitting isotopes.

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

composites are analyzed for gamma-emitting isotopes. Quarterly compo-3 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.

l The aquatic environment is also monitored by semi-annual upstream and

downstream collections of fish, periphyton or invertebrates, and bottom

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

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I 3.3 Program Execution

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

1. The TLD data for the first quarter of 1986 for Locations

- P-01A and P-10A were not available because TLDs could not be collected due to high water. They were not found after the water receded.

2. The TLD data for the first quarter of 1986 for Location P-10B and the second quarter of 1986 for Location P-OSS were not available because the TLDs were lost in the field.

3. No air particulate datum was available for Location P-3 for the collection period ending 01-14-86 because the filter paper was missing from the holder.

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4. Neither air particulate nor I-131 data were available for all locations (P-1, P-2, P-3, P-4, and P-6) for the collection period ending 03-17-86 because the samples were lost in shipment. IlPS was unable tn find the package, Deviations from the program are summarized in Table 5.3.

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.

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(Li) spectrometry.

Tritium levels were determined by liquid scintillation technique.

Analytical procedures used by the Teledyne Isotopes Midwest Laboratory are specified in detail elsewhere (Teledyne Isotopes Midwest Laboratory, 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, 1%7) and by the Health and Safety Laboratory of the U. S. Atomic Energy Commission (U. S. Atomic Energy Commission, 1972).

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1 Teledyne Isotopes Midwest Laboratory has a comprehensive quality control /

quality assurance program designed to assure the reliability of data l obtained. Details of TIML's Quality Assurance Program are presented elsewhere Teledyne Isotopes Midwest Laboratory,1985). The TIML Quality Assurance Program includes participation in Interlaboratory Comparison (Crosscheck) Programs. Results obtained in crosscheck programs are presented in Appendix A.

3.5 Program Modifications Early in the 1986 growing season a " Pasturing Dairy Animal Survey" revealed that only one location, the Gustafson Farm (P-14), actually turned these animals into a pasture area for any length of time.. A decision was also made to collect biweekly milk samples from these animals if they were fed " freshly cut hay" taken from a field adjacent to the farm. This process could parallel the grazing concept for concentra-tion of radionuclides in the raw milk.

Effective July 17, 1986, well water from Location P-8 was changed from the closed Kinney Store to the Indian Community Center.

3.6 Land Use Census In accordance with Technical Specification 4.10, paragraph 81, 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 500 fth producing fresh leafy vegetables in each of the 16 meteo-rological 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 the radiation environmental monitoring program should sampling locations change within the 5 mile radius from the plant.

i The 1986 Land Use Census was completed on July 14, 1986. This census did not identify any locations of exposure pathways different from those used in the program during the first seven months of the year. Milk and garden sample locations did not change due to the requirements of the land use census.

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i j-4- 4.0 RESULTS AND DISCUSSION All of .the scheduled collections and analyses were made except those listed in Table 5.3.

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' All results are summarized in Table 5.4 in-a format recommended by the Nuclear-Regulatory Commission in Regulatory Guide 4.8. For each type of analysis of each sampled medium, this . table lists the mean and range for all .. indicator

, locations and for all control locations. The locations with the highest mean

} and range are also shown.

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! 4.1 Atmospheric Nuclear Detonations and Nuclear Accidents There were no repor'ted atmospheric nuclear tests _in 1986. The l'ast reported test was conducted by the People's Republic of China on October i 16, 1980. The reNrted yield was in the 200 kiloten to 1 megaton range.

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I There was an accident at Reactor No. 4 of :the Chernobyl Nuclear Plant complex in the U.S.S.R. The accident occurred on April 26, 1986. The l releases of radioactive isotopes continued for ten days. On May 6, 1986,

! the reactor was sealed and releases to the atmosphere were reduced to negligible amounts, l

! Because of the high temperature, gases and aerosols went straight up and reached an estimated height of 16,000 feet.- The -dispersion pattern was i

similar to that of a tall stack of a coal plant; it reduced local fallout

! while increasing deposition at distant downwind locations.

i l The following isotopes and their total estimated releases (from April 26 to May 6, 1986) were reported by the_ Soviet authorities.

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Total Total Release

• Release *

(Estimated (Estimated Isotope in mci) Isotope in mci)

Xe-133 45 Ce-141 2.8 Kr-85m -- Ce-144 2.4 Kr-86 0.9 Sr-89 2.2 I-131 7.3 Sr-90 0.22 Te-132 1.3 Pu-238 0.0008 Cs-134 0.5 Pu-239 0.0007-Cs-137 1. 0 Pu-240 0.0011 Mo-99 3. 0 Pu-241 0.14 Zr-95 3.8 Pu-242 0.000002 Ru-103 3.2 Cm-241 0.021 Ru-106 1. 6 Np-239 1.2 Ba-140 4.3 t.

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• Evaluation error i 50%.

In the midwestern states of the U.S.A., the radioactivity released during-the accident was detected about two. weeks af ter the accident. Radio-nuclides detected were Ru-103, Ru-106, I-131, Cs-134,- and Cs-137 in such media as air, milk, precipitation, and vegetation. The highest level of I-131 in milk samples collected in the Midwest and analyzed by Teledyne Isotopes Midwest Laboratory was in milk collected May 23, 1986 in Illinois (82.2 pC1/1).

From mid-June to early August, levels of I-131 (and gross beta in the air particulates) in the Midwest fell below the detection limit (I-131) or returned to the pre-Chernobyl level (gross beta). The level of cesium isotopes decreased but was still detected sporadically in grass and milk.

4.2 Program Findings Results obtained show background levels of radioactivity in the environ--

mental samples collected in the vicinity of the Prairie Island Nuclear Generating Plant in 1986, with the exception of air and milk.

There was some effect on the environmental radioactivity resulting from the nuclear accident at Chernobyl (U.S.S.R.) on April 26, 1986. Low levels of Ru-103, I-131, Cs-134, and Cs-137 were detected in aerosols; )

1-131 and Cs-137 were detected in milk samples. j i

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Ambient Radiation (TLDs)

Ambient radiation was measured in the general area of site boundary, at outer ring 4 - 5 mi distant from the Plant, at special interest areas, and at one control location. The means ranged from 16.4 mR/91 days at inner ring locations to 17.6 mR/91 days at outer ring locations. The mean at special locations was 16.9 mR/91 days and 17.3 mR/91 days at the control location. The differences are not statistically significant.

The dose rates measured at all indicator.and control locations were similar to those observed in 1978 (12.1 and 15.1 mR/91 days, respec-tively; in 1979 (12.6 and 15.3 mR/91 days, respectively); in 1980 (11.2 and 13.5 mR/91 days, respectively),; in 1981 (13.0 and 14.5 mR/91 days, respectively); in 1982 (12.0 and 13.0 mR/91 days, respectively),; in 1983 (13.0 and 14.9 mR/91 days, respectively); in 1984 (13.9 and 15.3 mR/91 days, respectively); and in 1985 (13.9 and 15.3 mR/91 days, respec-tively). No plant effect on ambient gamma radiation was indicated.

Airborne Particulates The average annual gross beta concentration in airborne particulates measured 0.039 pCi/m3 at indicator , locations and 0.049 pC1/m3 at control locations and was higher than in 1982 (0.026 (0.023 pC1/m3),1984 (0.024 pCi/m3), and 1985 (0.025 pCi/m3)pCi/m3),198 The increase in average gross beta activity is attributable to the nuclear accident at Chernobyl.

The radioactive debris was first detected in air particulates in samples collected on May 19, 1986 and the elevated levels continued through the collection period ending June 9, 1986. Analyses of air particulates collected on June 16, 1986 showed that gross beta activity returned to the pre-Chernobyl level.

Gross beta activity during this period ranged from 0.091 to 0.511 pC1/m3 and averaged 0.228 pCi/m3 In comparison, gross beta activity for 1986, exclusive of the period between May 19, 1986 and June 9, 1986, averaged 0.025 pCi/m3, the same as the average for 1985.

A spring peak in beta activity had been observed almost annually for many years (Wilson et al . , 1969) . It had been attributed to fallout of nuclides from thTsTratosphere (Gold et al.,1964). It was pronounced in 1981, occurred to a lesser degree iii 1952, and did not occur 17 1983, 1984, or 1985. In 1986, the spring peak could not be identified because it was overshadowed by the releases of radioactivity from Chernobyl. The highest averages for gross beta were for the month of December and the fourth quarter, as in 1983, 1984, and 1985 (exclusive of the period between May 19, 1986 and June 9, 1986.

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Two pieces of evidence indicate conclusively that the elevated activity observed during the fourth quarter was not attributable to the Plant op-eration. In the first place, elevated activity of similar size occurred simultaneously at both indicator and control locations. Secondly, an identical patter n was observed at the Monticello Nuclear Generating Plant, about 100 miles distant from the Prairie Island Nuclear Generating Plant (Northern States Power Company, 1987).

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

Beryllium-7, which is produced continously in the upper atmosphere by . cosmic radiation (Arnold and Al-Salih, 1955), was detected in all j samples. All. Other gamma-emitting isotopes were below their respective LLD limits during the first, third, and fourth quarters.

During the second quarter of 1986, three gamma-emitting isotopes (Ru-103, Cs-134 and Cs-137) were identified and averaged 0.017, 0.0068 and 0.018 pC1/m3, respectively. It should be noted that the ratio of Cs-134 to Cs-137 in air particulates was about 1:2, the same as in the mix of gases released at the time of the accident at Chernobyl.

Airborne Iodine 1

Weekly levels of airborne iodine-131 were below the lower limit of detection (LLD) of 0.07 pCi/m3 in 240 of 254 samples analyzed. The LLD of 0.07 pCi/m3 could not be reached in five samples (<0.12, <0.12

<0.12, <0.13, and <0.13 pCi/m3) because of delays in counting. 1 Iodine-131 levels in nine (9) samples collected between May 19 and May 27, 1986 ranged from 0.12 to 0.48 pCi/m3 and averaged 0.30 pCi/m3 for all samples with detectable levels.

The presence of airborne I-131 in the aerosols in May,1986 is attribut-able to the Chernobyl accident.

Milk A total of sixty-six (66) analyses for iodine-131 was performed during the reporting period. Forty-nine (49) samples had I-131 concentrations below the LLD level of 1.0 pCi/l.

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i Seventeen (17) samples, collected between May _19 and July 15, . : 1986,

!l contained I-131 in. various concentrations. . The . level ranged from - 1.1

! pCi/l to 75.7 pCi/1. and averaged 22.9 pCi/l for all . locations. The variability in concentration of, I-131;in milk depended on the. local -

precipitation during the deposition of I-131 on the ground.and the method of feeding the milch animals.

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' Cs-137 was detected in. six - (6) of ; sixty-six -(66) samples and averaged 17.8 pCi/l at indicator locations and 18.2 control locations. ~ No .other-gamma-emitting isotopes except potassium-40 were detected in any milk samples. This is. consistent with the finding of the -National Center for Radiological Health that most radiocontaminants in feed do not find their i

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).

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In sunsnary, the milk data for the 1986 show no radiological effects of .

j the plant operation, but the presence of-I-131 and Cs-137 in milk samples.

does exhibit the effect of the nuclear accident at Chernobyl.

Drinking Water 1

j In drinking water from the City of Red Wing well, trit _ium activity was  ;

below the LLD level of 330 pCi/1 in all samples. Iodine-131 activity.was-l also below the LLD level at 1.0 pCi/l in. all samples. As with the other well water samples, all analyses for gamma-emitting isotopes yielded' results below detection limits. Gross beta averaged 6.8 pC1/11and was 1980 (11.8 pC1/1),

3 similar to the levels observed in 1979 (10.5 pC1/1) -

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

and 1985 (7.1 pC1/1).

I River Water ,

At the upstream and downstream collection sites, quarterly composite

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tritium levels were below the LLD level of 330 pCi/l in -all samples.but-one.

River water was also analyzed for gansna-emitting isotopes. All gamma-1.

i emitting isotopes were below their respective detection limits. There.

j was no indication of a plant effect. ,

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.u-_._,_ - - - . _ . . _ - - _ - . . _ _ _ . _ _ . - _ _ . _ . . _. _ .. _ _--___._ _ _ . _._ . .~ - . . _ _ .

. . . - - - .- =- . .

l i

, Well Water i

At the control well P-25, Kinneman Farm and three indicator wells (P-8, Kinney. Store; P-10, Lock and Dam No. 3; _ and P-9 Plant' Well . No. - 2) no

tritium was detected above LLD level of 330 pCi/l in all samples but

two.

The detected concentrations were barely

above the LLD level of 330 pCi/1-in.one sample from P-8, Indian Community Center, and from P-9, Plant Well

j. No . 2. - In both cases, the activity was 370 pCi/1.

I 'Gama-emitting isotopes wert below the detection limits. in all samples.

ii Crops Cabbage samples were collected on August 12, 1986, and ' analyzed for iodine-131. Corn samples were collected on August 25,1986.and analyzed l for gama-einthing isotopes. All results, except for potassium-40, were below detection limits. There was no' indication of a plant effect.-

i Fish

Fish samples were collec'ted in May and October,1986.- The only isotope detected was naturally-occuring potassium-40 and there was no significant i difference between upstream and downstream results. There was no indica -

tion of a plant _effect.

i Aquatic Insects and Periphyton I Aquatic insects (invertebrates) and periphyton were collected in June and September, 1986. The samples were analyzed for gamma-emitting. isotopes.

All gamma-emitting isotopes, except for naturally-occuring potassium-40, '

j were below their respective LLD's. No plant effect was: indicated.

l t

j Bottom and Shoreline Sediments

Sediment collections were made in June and October,1986. The samples were analyzed for gamma-emitting isotopes.

l Cs-137 was detected in one bottom sediment. upstream sample,. P-5(C) ~ and

.- measured 0.057 pCi/g dry weight. Zn-65 was detected in one bottom I~ sediment sample collected -at P-6, Lock and Dam No. 3, and measured 0.098 pci/g dry weight, barely above the LLD level of 0.075 pCi/g dry weight.

The difference is not significant.

j I

{ All other gamma-emitting isotopes except naturally-occurring potassium-40 j were below their respective- LLDs. Except for the presence .of Zn-65 in j one sample, no plant effect was indicated.

! 14 i

V 1,

f f

1

-1

~i i

4

)

t i

I e

5.0 TABLES f

I d

i 4

a

(

i l

8 f

f e

I 1

i i

1 I

15

Table 5.1 Sample Collection and Analysis Program,1986. -Prairie' Island Collection Analysis Locations Type and Type. and Medium No. Codes (and Type)a Frequencyb Frequencyc Ambient radiation P-01A - P-10A Ambient gamma.

32 C/Q (TLDs) P-01B - P-15B P-OIS - 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-6 5

Milk 5 P-16 to P-18, G/Md I-131,'GS P-25(C),P-14 River water 2 P-5(C),P-6 G/W GS(MC),-H-3(QC)-

Drinking water 1 P-11 G/W GB(MC),I-131(MC).

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 E

1 W

Table 5.1. Sample Collection and Analysis Program, 1986. Prairie Island Collection Analysis Locations Type and Type and Medium No. Codes (and Type)a Frequencyb Frequencyc 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 y

Shoreline sediment 1 P-12 G/SA GS a

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 =

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

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

o e

. . . . _ ~ _ , _ . ._ . . _ _

i j' . .

Table 5.2 Sampling-locations. Prairie Island-L Code Typea Name Location P-1 C Air Station P-1 - 16.5 mi 8 348*/NNW P-2 Air Station P-2 0.5 mi S 294*/WNW i P-3 Air Station P-3 0.8 mi- S 313*/NW i P-4 Air Station P-4 .0.4 mi S 359*/N P-5 -C' Upstream of Plant ~ 0.6 mi S 60*/ENE -

P-6~ Lock a Dam A3 a Air Station P-6.- 1.6 mi S 129*/SE P-8 Comunity Center 1.2 mi S 304*/NW .

I P-9 . Plant Well A2 0.3 mi S 306*/NW P-11 City of Red Wing 7.1 mi S.135*/SE P-12 Recreational Area 3.4 mi S 116*/ESE P-14 Gustafson Farm 2.2 mi S 168*/SSE P-16 Johnson Farm 2.6 mi B 60*/ENE 4

P-17 Place Farm 3.5 mi S.25*/NNE P-18 Christensen Farm 3.7 mi 'S 88*/E

, P-20 River Irrigated Corn Field *

• . P-24 Highest D/Q Garden ** .

P-25 C Kinneman Farm 11.1 mi S 331*/NNW

P-01A- Property Line 0.4 mi B 359*/N -

P-02A Property Line 0.3 mi 8 19*/NNE -

P-03A Property Line - 0.5 mi S 183*/S P-04A Property Line 0.4 mi 8-204*/SSW P-05A Property Line 0.4.mi S~225*/SW P-06A Property Line 0.4 mi S 249*/WSW P-07A Property Line 0.4 mi B 268*/W.

P-08A Property Line 0.4 mi S 291*/NNW P-09A Property Line 0.7 mi S 317*/NW

, P-10A Property Line 0.5 mi S 333*/NNW P-01B Thomas Killian Residence. 4.7 mi S 355*/N

P-028 Roy Kinneman Farm 4.8 mi S 17*/NNE z P-038- Wayne Anderson Farm 4.9 mi S 46*/NE l

P-04B Nelson Drive (Road) 4.2 mi'S 61*/ENE-P-058 County Road E and Coulee 4.1 mi S 97*/E-P-068 William Houschildt Residence 4.4 mi S 112*/ESE P-078- Red Wing Service Center 4.7 mi S 140*/SE P-088 David Wnuk Residence 4.1 mi S 165*/SSE P-098 Highway 19 South 4.2 mi S 187*/S -

P-10B Cannondale Farm 4.9 mi 8 ' 200*/SSW a "C" denotes' control location. All other locations are indicators.

1

!

• Collected only if river water is used to irrigate the cornfields -l (Technical Specification Revision No. 80, effective 11-14-86). j f ** This location is not determined until after the Land Use Census is completed.

l 18 i 4

Table 5.2 Sampling locations (continued) Prairie Island Code Typea Name Location P-11B Wallace Weberg Farm 4.5 mi @ 221*/SW P-12B Roy Gergen Farm 4.5 mi @ 247*/WSW P-138 Thomas O'Rourke Farm 4.4 mi 0 270*/W P-148 David J. Anderson Farm 4.9 mi 0 306*/NW P-15B Holst Farms- 4.2 mi 0 347*/NNW P-01S Federal Lock & Dam #3 1.6 mi 0 129*/SE P-025 Charles Suter Residence 0.6 mi 0 158*/SSE P-03S Carl Gustafson Farm 2.2 mi @ 168*/SSE P-04S Richard Burt Residence 2.0 mi @ 228*/SW P-05S Kenney Store 2.0 mi 0 270*/W P-06S Earl Flynn Farm 2.5 mi 0 299*/WNW P-01C Robert Kinnemen Farm 11.1 mi 0 331*/NNW "C" denotes control location. All other locations are indicators.

T 19

k

. Table 5.3 Missed collections and analyses,1986a. 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-01A 1st Qtr. 1986 Could not be Dosimeters (TLDs) Radiation collected due to high water.

P-10A ist Qtr. 1986 Could not be collected due.to high water.

P-108 1st Qtr. 1986 Lost in the field.

2 P-05S 2nd Qtr.1986 Lost in the field.

Air Particulate Gross Beta P-3 01-14-86 Air. filter missing from holder.

Air Particulate Gross Beta P-1 03-17-86 Lost in and Charcoal I-131 shipment.b P-2 03-17-86 Lost in shipment.b P-3 03-17-86 Lost in shipment.b P-4 03-17-86 Lost in shipment.b P-6 03-17-86 Lost in shipment.b a

The 1985 REMP Annual Report, Table 5.3, failed to include the following:

the second half year invertebrate samples were not collected after at least b

three attempts.

UPS was unable to find this package in their extensive search.

20 i

Table 5.4. Environmental Radiological Monitoring Program Summary.

Name of Facility Prairie Island Nuclear Generating Plant Docket No. 50-282. 50-306 Location of Facility Goodhue. Minnesota Reporting Period January - December 1986  !

(County, State)

Indicator Location with Highest Control Sample Type and Locations Annual Mean Locations Number of Type Number of Mean (F)C Mean (F) Mean (F) Non-routine (Units) Analysesa LLob RangeC Locationd Range Range Results*

TLD Gamma 38 3.0 16.4 (38/38) P-02A, Property Line 17.1 (4/4) (See control 0 i (mR/91 days) (10.8-20.3) 0.3 mi 9 19*/NNE (10.8-20.3) below) j (InnerRing, General Area at P-04A, Property Line 17.1 (4/4)

Site Boundary) 0.4 mi 9 204*/SSW (13.3-18.7)

TLD Gamma 59 3.0 17.6 (59/59) P-048, Nelson Drive 20.4 (4/4) (See control 0 (mR/91 days) (11.0-23.3) Road (15.4-22.9) below)

(Outer ring, 4.2 mi 9 61*/ENE 4-5 miles distant)

TLD Ganna 23 3.0 15.9 (23/23) P-045, R. Burt 17.9 (4/4) (See control 0 (mR/91 days) (10.2-20.8) Residence (14.8-19.7) below) y (Special 2.0 at 9 228*/SW Interest Areas)

TLD Gamma 4 3.0 None P-01C, R. Kinneman 17.3 (4/4) 17.3 (4/4) 0 (mR/91 days) Farm (13.2-20.2) (13.2-20.2)

(control) 11.'1 mi 9 331*/NW Airborne G8 254 0.002 0.039(203/203) P- 1, Station P-1 0.049 (51/51). 0.049(51/51) O Particulates (0.006-0.325) 16.5 mi 9 348*/N W (0.011-0.511) (0.011-0.511)

(pC1/m3) a m Be-7 0.022 0.075 (16/16) P-6, Station P-6 0.089 (4/4) 0.081 (4/4) 0 (0.042-0.14) 1.6 mi 9 129*/NNW (0.071-0.107) (0.048-0.11)

Mn-54 0.0022 <LLD - - <tLD 0 Co-58 0.0041 <LLD - -

<LLD 0 Co-60 0.0018 <LLD - - <tLD 0 2n-65 0.0044 <LLD - - (LLO . 0 l

Zr-Nb-% 0.0059 <LLD - - <LLD 0

)

Table 5.4. Environmental Radiological Monitoring Progran Summary (continued)

Name of Facility Prairie Island Nuclear Generating Plant 00cket No. 50-282. 50-306 Location of Facility Goodhue. Minnesota Reporting Period January - December 1986 (County, State)

Indicator Location with Highest Control Sample Type and Locations Annual Mean Locations Nueer of Type Number of Mean (F)C nean (F) Mean (F) Non-routine (Units) Analysesa Llob RangeC Locationd Range Range Hesultse tirborne Ru-103 0.0036 0.012 (4/16) P-1. Station P-1 0.037 (1/4) 0.037 (1.4) 0 Particulates (0.008-0.017) 16.5 al 9 348*/ m - -

(pC1/mJ)

(continued) Ru-106 0.022 4LD - - GLD 0 Cs-134 0.0015 0.0058 (4/16) P-1. Station P-1 0.011 (1/4) 0.011 (1/4) 0 (0.0044-0.0078) 16.5 at 9 348*/m Cs-137 0.0014 0.016 (4/4) P-1, Station P-1 0.026 (1/4) 0.026 (1/4) 0 (0.014-0.018) 16.5 at # 348*/m _

Ba-La-140 0.083 4LD - -

<LLD 0 Q Ce-141 0.0094 4LD - -

4LD 0 Ce-144 0.012 4LO - - <LLD 0 Airborne I-131 254 0.07f 0.27 (7/203) P-1, Station P-1 0.41(2/51) 0.41 (2/51) O t Iodine (0.12-0.48) 16.5 al 9 348*/ m (0.38-0.44) (0.38-0.44)

(pC1/m3)

Milk I-131 66 1.0 23.3 (13/53) P-14, Gustafson 35.1(4/15) 21.8 (4/13) 0 i (pC1/l) (1.1-75.7) Farm (6.0-75.7) (2.1-42.6)

( 2.2 al 9 168*/SSE l

GS 66 K-40 100 1350 (53/53) P-17, Place Fars 1380 (14/14) 1320 (13/13) 0 (1170-1730) 3.5 at 9 25*/NNE (1270-1730) (1120-1580)

Cs-134 15 4LD - - <LLD 0 Cs-137 15 17.8(5/53) P-16 Johnson Fars 18.2 (1/13) 18.2 (1/13) 0 (15.1-21.4) 2.6 at # 39*/NE - -

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

..m._ . . _ __- ._.___,_.___..______._____.._m , . . _ . _ . . _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ . _ _ _ . _ . -. _ .-_._mm . . . _ .

Table 5.4. Environmental Radiological Monitoring Program Sunnary (continued)

Name of Facility Prairie Island Nuclear Generating Plant Docket No. 50-282. 50-306 Location of Facility Goodhue. Minnesota Reporting Period January - December 1966 (County. State)  ;

Indicator Location with Highest Control Sample Type and Locations Annual Mean Locations Number of Type Number of Mean (F)c Mean (F) Mean (F) Non-routine (Units) Analysesa LLDb RangeC Locationd Range Range Results*

Drinking Water G8 12 1.0 6.8 (12/12) P-11. City of Red 6.8 (12/12) None 0 (pC1/1) (5.3-8.6) Wing (5.0-9.0) 7.1 mi 9 135*/SE I-131 12 1.0 <tLD - - None 0 H-3 4 330 <tLD - - None O GS 12 b Mn-54 15 <LLD - - None 0 Fe-59 30 <LLD - - None 0 Co-58 15 (LLD - - None 0 l

ro Co-60 15 <tLD - - None 0 w

Zn-65 30 <LLD - - None 0 Zr-Nb-95 15 < lid - - None O Cs-134 10 <tLD - -

None 0 i l Cs-137 10 <tLD - - None. 0 Ba-La-140 159 <LLD - - None 0 Ce-144 93 (LLD - - None 0 ,

1 1

River Water H-3 8 330 <LLD .

- <LLD 0 (pC1/1)

, Mn-54 15 <LLD .

- <LLD 0 l

Fe-59 30 <LLD ' - - <tLD 0 l Co-58 15 <LLD - - <LLO O 1

Co-60 15 <LLD - - <LLD 0 Zn-65 15 <LLD - - <tLD 0 I l

. i

Table 5.4. Environmental Radiological Monitoring Program Sunnary (continued)

Name of Facility Prairie Island Nuclear Generating Plant Docket No. 50-282. 50-306 Location of Facility Goodhue. Minnesota Reporting Period January - December 1986 (County, State)

Indicator Location with Highest Control Sample Type and Locations Annual Mean Locations Number of Type number of Mean (F)C Mean (F) Mean (F) Non-routine (Units) Analyses 4 LLDb RangeC Locationd Range Range Results*

River Water Cs-134 15 <LLD '- - <tLD 0 (pC1/1)

(continued) Cs-137 18 4LD - - <tLD 0 Ba-La-140 15h <LLD - - <LLD 0 Ce-144 79 <LLD - - <LLD 0 Well Water H-3 16 330 370 (2/12) P-8, Indian Community 370 (1/4) GLD 0 (pC1/1) (370-370) Center -

2.0 ml 9 280*/W P-J. Plant Well No. 2 370 (1/4) 0.3 mi 9 306 */NW -

ru i A GS 16 Mn-54 15 4LD - -

<LLD 0 Fe-59 30 4LD - -

<tLD 0 Co-58 15 <LLD - - <tLD 0 Co-60 15 <LLD -- - <LLD 0 Zn-65 30 <LLD - - <LLD 0 Zr-Nb-95 15 <LLD - - <tLD 0 Cs-134 10 ELD - - <LLD 0 Cs-137 10 <LLD -. -

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

<LLD 0 Ce-144 86 <LLD - - <LLD 0 Crops-Cabbage I-131 2 0.020 GLD - -. <LLD 0 (pC1/g met)

4 Table 5.4. Environmental Radiological Monitoring Program Sumary (continued)

Name of Facility Prairie Island Nuclear Generating Plant Docket No. 50-282. 50-306 Location of Facility Goodhue. Minnesota Reporting Period January - December 1986 (County, State)

Indicator Location with Highest Control Sample Type and Locations Annual Mean Locations Number of Type Number of Mean (F)C Mean (F) Mean (F) Non-routine (Units) Analyses 8 LLDb RangeC Locationd Range Range Resultse Crops-Corn GS 2 Be-7 0.22 <LLD - - <LLD 0 K-40 0.5 2.20 (1/1) Suter Fars 2.20 (1/1) 1.63 (1/1) 0 0.6 mi 9 158*/SSE - -

Mn-54 0.020 GLD - -

<LLD 0 Co-58 0.028 <LLD - -

<tLD 0 Co-60 0.020 <LLD - -

<tLD 0 Zn-65 0.046 <LLD - -

<1I D 0 Zr-Nb-95 0.041 <LLD - -

<LLD 0

$ Ru-103 0.14 <LLD - -

<tLD 0 Ru-106 0.15 <LLD - - <LLD 0 Cs-134 0.017 <LLD - -

<tLD 0 Cs-137 0.015 <LLD - -

<LLD 0 Ba-La-140 0.25 <LLD - -

<LLD 0 Ce-141 0.077 <LLD - -

RLD 0 Ce-144 0.13 <LLD - -

<LLD 0 Fish - Flesh GS 4 9

K-40 0.1 2.98 (2/2) P-6, Lock & Com #3 2.98 (2/2) 2.74 (2/2) 0 (2.53-3.44) 1.6 at 9 129*/SE (2.53-3.44) (2.46-3.02)

Mn-54 0.032 <LLD - -

(LLD 0 Fe-59 0.50 <LLD - -

<tLD 0 Co-58 0.094 (LLD - -

<LLO O Co-60 0.041 <LLD - -

<LLO O

, m .-__ _._..___---m_. -._____._._m __ _ . _ _ _ . _ . _ _ . . - . . . _ . . _ _ _ . _ _ _ _ . .. - _ . _ . - - _ m _ . _ . . _ _ . ~ - m_.

J

-j Table 5.4 Environmental Radiological Monitoring Program Summary (continued) ,

Name of Facility Prairie Island Nuclear Generating Plant Docket No. 50-282. 50-306 Location of Facility Goodhue. Minnesota Reporting Period January - December 19:16 4 (County, State)

Indicator Location with Highest Control Sample Type and Locations Annual Mean Locations Num6er of Type Number of Mean (F)C Mean (F) Mean (F) Non-routine (Units) Analysesa LLob RangeC Locationd Range Range stesults' i

Fish - Flesh GS 4 (pC1/g met) i (continued) Zn-65 0.091 <LLD - - <LLD 0 Zr-Nb-95 0.092 (LLD - - <LLD 0 Cs-134 0.030 <tLD - - <LLD 0 Cs-137 0.038 <LLD - - <LLD 0 i Ba-La-140 0.028 <tLD - -

<LLD 0 i

., Invertebrates GS 4 (pC1/g met) g Be-7 1.31 <LLD - -

<tLD 0

• K-40 1.0 3.08 (2/2) P-6, Lock & Dam. 3.08 (2/2) 2.93 (2/2) 0 (1.00-5.17) No. 3 (1.00-5.17) (2.19-3.67) 1.6 mi 9129*/SE Mn-54 0.078 <LLD - -- <LLD 0 i Co-58 0.11 <LLD - - <LLD 0 Co-60 0.089 <LLD - - <LLD 0

'Zn-65 0.17 <LLD - - <LLD 0 Zr-Nb-95 0.11 <LLD - - <LLD 0 Ru-103 0.35 <LLD - - <LLD 0 Ru-106 0.72 <LLD - - <LLD 0 Cs-134 0.090 <LLD -- - qLD 0

> Cs-137 0.085 <LLD - - <tLD 0 Ba-La-140 0.16 <LLD - - <LLD 0 Ce-141 0.39 <LLD - - (LLD 0 Ce-144 0.38 <LLD. - - (LLD 0 I

Tabla 5.4. Environmental Radiological ibnitcring Program Sunniary (continued)

Name of Facility Prairie Island Nuclear Generating Plant Docket No. 50-282. 50-306  ;

4 Location of facility Goodhue. Minnesota Reporting Period January - December 1986 (County, State)

Indicator Location with Highest Control Sample Type and Locations Annual Mean Locations Number of Type Number of Mean (F)C Mean (F) Mean (F) Non-routine (Units) Analysesa LLDb RangeC Locationd Range Range Resultse Bottom and GS 6 Shoreline Sediments Be-7 0.48 <LLD - - <tLD 0 9

K-40 1.0 8.41 (4/4) P-5(C), Upstream of 9.69 (2/2) 9.69 (2/2) 0 (7.85-9.04) Plant. 0.6 mi 9 60*/ENE (7.72-11.65) (7.72-11.65) h 54 0.028 <LLD - -

<LLD 0 Co-58 0.054 <LLD - -

<tLD 0 Co-60 0.026 <LLD - - <tLD 0 Zn-65 0.075 0.098 (1/2) P-6, Lock & Das No. 3 0.98 (1/2) <tLD 0

- 1.6 mi 9 129*/SE -

Zr-Nb-95 0.052 (LLD - - <LLU 0 Ru-103 0.086 <LLD - - <LLU U ru

! N Ru-106 0.19 <LLD - - <LLD 0 Cs-134 0.029 <LLD - - <LLD 0 Cs-137 0.027 <LLD P-5(C),Upstreamof 0.057(1/2) 0.057(1/2) O Plant, 0.6 mi 9 60*/ENE Ba-La-140 0.021 <LLD - - <LLD 0 Ce-141 0.19 <LLD - - <LLD 0 Ce-144 0.14 <LLD - -

<tLD 0

'

• G8 = Gross beta; GS = gamma scan.

b LLD = Nominal lower limit of detection based on 4.66 signa error for background sample. ,

C Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified location is indicated in parentheses (F).

d

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

Non-routine results are those which exceed ten times the control station value. If no control station value is available, the result is considered non-routine if it exceeds ten times the preoperational value for the location.

g Five results (<0.13, <0.12, <0.12, <0.13, and <0.12 C1/m3) have been excluded from the determination of LLD for I-131. The elevated LLDs resulted from delays in counting.

)l 9 One result (<23 pC1/1) has been excluded from the determination of LLD for Ba-La-140 in water. It resulted from a delay in

! c unting.

h Three results (<19, (20, and <30 pC1/1) have been excluded from the determination of LLC for Ba-La-140 in water. The elevated LLDs resulted from delays in counting.

6.0 REFERENCES

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

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

Gold, S., H. W. Barkhau, 8. Shlein, and B. Kahn,1964. Measurement of Natu-j rally Occuring Radionuclides in Air, in the Natural Radiation Environ-ment, University of Chicago Press, Chicago, Illinois, 369-382.

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

) . 1979b. Radiation Environmental Monitoring for Monticello Island Nuclear Generating Plant, Complete Analysis Data Tables, January -

December 1978.

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

, December 1979.

. 1980b. Radiation Environmental Monitoring for Prairie i

Island Nuclear Generating Plant, Complete Analysis Data Tables, Janauary

- 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.

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

December 1981.

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

December 1981.

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

December 1982.

28

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Hohenemser, C.M. Deicher, A. Ernst, H. Hofsass, G. Lindner, E. Racknage1 ,

l 1986. "Chernobyl," Chemtech, October 1936, pp. 596-605. C l

W National Center for Radiological Health,1968. Radiological Health and Data -

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

Northern States Power Company. 1979. Prairie Island Nuclear GYn'e'ratiry .

Plant, Annual Radiation Environmental Monitoring Report to the U.S. ,.

i Nuclear Regulatory Commission, January 1, 1978 to December 31, 1913 *

(prepared by Hazleton Environmental Sciences). Minneapolis, Minnesota. '

E

. 1980. Prairie Island Nuclear Generating' Plant, Annual ',

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

{

. 1981. Prairie Island Nuclear Generating 51 ant, Annual ~ -

Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory -

Commission, January 1,1980 to December 31,1980 (prepared by Hazleton Environmental Sciences). Minneapolis, Minnesota. .

. 1982. Prairie Island Nuclear Generating Plant, h nual Radiation Environmental Monitoring Report to the U.S. Nuclear ' Regulatory Commission, January 1,1981 to December 31,1981 (prepared by Hazleton Environmental Sciences). Minneapolis, Minnesota.

, g

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

. 1984. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Repert to the U.S. Nuclear Regulatory y

y Commission, January 1,1983 to December 31,1983 (prepared by Telesyne =_

Isotopes Midwest Laboratory). Minneapolis, Minnesota.

. 1985. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory ,

Commission, January 1,1984 to December 31,1984 (prepared by Telodyne 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 Tele. dyne Isotopes Midwest Laboratory). Minneapolis, Minnesota.

~.

. 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 Isotopes Midwest Laboratory). Minneapolis, Minnesota.

I 29

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if,1, J V, y

y; x ,

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'_.- l k- Teledyne Isotop'es Midwest L boratVry. [1971a. ' Quality Control Program',

4 Revisiorr 7. 2d, No'vemb .r .984.j '-

, .,y 1,

,. N85. Qval i Control Procedures Manual, Revision 6, 09AugvTl985. ,

, c l 3 1983. Jualiti ?swNce Program / Manual, Revision 1,15 April u

1985. .,

(- ' '

.- .1985. Analytical Proce4tres Manaal, Revision 5, 29 July -

i ,1985. >

1)

. 1Wla. Radiation Environmental s Monitoring for Monticello

~C Nt. clear .Geoerating ' Plant, Complete AnalystWl Dat a Tables, January -

9adcmber 1583. '

. 1984b. Rao;ation Environmental Monitoring for' Prairie Island Nuclear Generating' Plant. Complete Analyds Data Tables, January -

3 December-1983. .

s

" ~

. 1983a.- Radiation Envirodental honitoring' for Monticello Nuclear 73enerasing P.lant.c Complete Analyses ' Data Tables, January -

December 1984. ,

1.__ . J985b. U diation Environmental Monitoring for Prairie Island Nuc ts.r Generating. f!! ant, Complete Analys<ts Data Tables, January -

Decemoer 19P,4(

( . 1936a. Rediation Enviranmental Monitoring .for Monticello Nuclear Generating Plant, Complete Analyses Data Tables, January - -

Decamber 1986.

. 1986b. Psadiation Environmental Monitoring for Prairie Island

] auclear Generating Plant, Cocplete Analyses Data Tables, January. -

Dece6 2r 1985. .

. 1986.. Sampling Procedures, ' Prairie Island Nuclear Generating l Plant, Revision 15s 30cqctober 1986. 1 i

. 1987a.- Radiation Environmental Monitoring for Monticello i Nuriear Generating Plant, Complete Analyses Data Tables, January -

09: ember 1986.

. 198R. Radiation Environ $antal Monitoring for Prairie Island s

TRuIharGeneratingPlent, Complets-Analyses Data Tables, January - '

n'ecember 1986.

~

~

. U. S. Atomic Energy Commissions 1972. HASk ' Procedures Manual, Health and Safet/ 1.aboratory, New Yoth, NY., 10014.

4

" /

l

/

30,

' r

• f ,,

N

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

U.S.S.R. ' State Committee on the Utilization of Atomic - Energy.~ 'The Accident at the Chernobyl- Nuclear Power Plant and Its Consequences._ 'Information-compiled for the I.A.E.A. Experts' Meeting,_-25 -7 29 August 1986, Vienna, Austria.

~

~ Wilson,' D. W., G.- M. Ward and J. E. ' Johnson. 'i1969. In Environmental Contam-ination by Radioactive Materials, International Jtomic Energy Agency.

p. 125. 'S i

i 5

l 31

1 l

l l

I i

l Appendix A j Interlaboratory Comparison Program Results

+

,t e

l l

l l

i l

l l

A-1

Appendix A Interlaboratory Comparison Program Results Teledyne Isotopes Midwest Laboratory (formerly Hazleton Environmental Sciences) has participated in interlaboratory comparison (crosscheck) programs since the formulation of its quality control program in December 1971. These programs are operated by agencies which supply environmental-type samples (e.g., milk or water) containing concentrations of radionuclides known to the issuing agency but not to participant laboratories. The purpose of such a program is to provide an independent check on the laboratory's analytical procedures and to alert it to any possible problems.

Participant laboratories measure the concentrations of specified radionuclides and report them to the issuing agency. Several months later, the agency reports the known values to the participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used.

The results in Table A-1 were obtained through participation in the environ-mental sample crosscheck program for milk, water, air filters, and food samples during the period May 1984 through November 1986. This program has been conducted by the U. S. Environmental Protection Agency Intercomparison and Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, Las Vegas, Nevada.

The results in Table A-2 were obtained for thermoluminescent dosimeters (TLD's) during the period 1976, 1977, 1979, 1980, and 1981 through parti-cipation in the Second, Third, Fourth, and Fifth International Intercomparison -

of Environmental Dosimeters under the sponsorships listed in Table A-2.

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.

A-2

Table A-1. U.S. Environmental Protection Agency's crosscheck program, com-parison of EPA and Teledyne Isotopes Midwest Laboratory results for milk, water, air filters, and food samples,1984 through 1986.a Concentration in )Ci/lb Lab Sample Date TIML Result EPA lesult Code Type Collected Analysis i2bc ilo, n=3d STW-358 Water May 1984 Gross alpha 3.010.6 318.7 Gross beta 6.7tl.2 6i8.7 STM-366 Milk June 1984 Sr-89 21i3.1 25i8.7 Sr-90 13i2.0 1712.6 i-131 46i5.3 43i10.4 Cs-137 3814.0 3518.7 K-40 15771172 1496i130 STW-368 Water July 1984 Gross alpha 5.lil.1 618.7 Gross beta 11.9i2.4 1318.7 STW-369 Water August 1984 I-131 34.315.0 34.0*10.4 STW-370 Water August 1984 H-3 30031253 2817i617 STF-371 Food July 1984 Sr-89 22.015.3 25.018.7 i

-1 k Oib4 Cs-137 24.0i5.3 25.018.7 K-40 2503i132 2605i226.0 STAF-372 Air August 1984 Gross alpha 15.3*1.2 1718.7 Filter Gross beta 56.010.0 5118.7 Sr-90 14.3tl.2 1812.4 Cs-137 21.0*2.0 15i8.7 STW-375 Water Sept. 1984 Ra-226 5.110.4 4.911.27 Ra-228 2.210.1 2.3i0.60 STW-377 Water Sept. 1984 Gross alpha 3.3tl.2 5.018.7 Gross beta 12.7i2.3 16.018.7 STW-379 Water Oct. 1984 H-3 2860i312 2810i356 STW-380 Water Oct. 1984 Cr-51 <36 40i8.7 Co-60 20.3*1.2 2018.7 Zn-65 150i8.1 147i8.7 Ru-106 <30 47i8.7 Cs-134 31.3i7.0 31i8.7 Cs-137 26.711.2 2418.7 A-3

1 Table A-1. (continued)

Concentration in )Ci/lb Lab Sample Date TIML Result EPA lesult Code Type Collected Analysis fasc ilo,n=3d STM-382 Milk Oct. 1984 Sr-89 15.7*4.2 22i8.7 Sr-90 12.7tl.2 16*2.6 I-131 41.7*3.1 42*10.4 Cs-137 31.3i6.1 32i8.7 K-40 1447f66 1517*131 STW-384 Water Oct . 1984 Gross alpha 9.7tl.2 1418.7 (811nd) Sample A Ra-226 3.310.2 3.010.8 Ra-228 3. 4tl. 6 2.1*0.5 Uranium nae 5i10.4 Sample 8 Gross beta 48.3i5.0 64i8.7 Sr-89 10.7i4.6 11*8.7 Sr-90 7.311.2 12i2.6 Co-60 16.3tl.2 14i8.7 Cs-134 <2 2i8.7 Cs-137 16.7*1.2 1418.7 STAF-387 Air Nov. 1984 Gross alpha 18.7tl.2 15i8.7 Filter Gross beta 59.015.3 5218.7 Sr-90 18.3tl.2 21i2.6 Cs-137 10.311.2 1018.7 STW-388 Water Dec. 1984 I-131 28.Qt2.0 36110.4 STW-389 Water Dec. 1984 H-3 3583i110 3182i624 STW-391 Water Dec. 1984 Ra-226 8.4tl.7 8.6i2.2 Ra-228 3.1i0.2 4.1*1.1 STW-392 Water Jan. 1985 Sr-89 <3.0 3.0i8.7 Sr-90 27.315.2 30.012.6 STW-393 Water Jan. 1985 Gross alpha 3.311.2 Si8.7 Gross beta 17.3i3.0- 15i8.7 '

STS-395 Food Jan. 1985 Gross alpha 4.7i2.3 6.018.7 Gross beta 11.311.2 15.018.7 Sr-89 25.316.4 34.018.7 Sr-90 27.0i8.8 26.0i2.6 I-131 38.0i2.0 35.0i10.4 Cs-137 32.7i2.4 29.018.7 K-40 1410t212 1382f208 i

l A-4

Table A-1. (continued)

Concentration in pCi/lb Lab Sample Date TIML Result EPA ,lesult Code Type Collected Analysis i?,c flo, n=3d STW-397 Water Feb. 1985 Cr-51 <29 4818.7 Co-60 21.3f3.0 20i8.7 Zn-65 53.7i5.0 55i8.7 Ru-106 <23 2518.7 Cs-134 32.3tl.2 35i8.7 Cs-137 25.3i3.0 2518.7 STW-398 Water Feb. 1985 H-3 38691319 3796i634 STM-400 Milk March 1985 I-131 7.3*2.4 9.0il.6 STW-402 Water March 1985 Ra-226 4.6i0.6 5.0tl.3 Ra-228 <0.8 9.0i2.3 Reanalysis Ra-228 9.0f0.4 STW-404 Water March 1985 Gross alpha 4.712.3 6i8.7 Gross beta 11.3tl.2 1518.7 STAF-405 Air March 1985 Gross alpha 9.3il.0 10.0t8.7 Filter Gross beta 42.0tl.1 36.0*8.7 Sr-90 13.3*1.0 15.0*2.6 Cs-137 6.3tl.0 6.0i8.7 STW-407 Water April 1985 I-131 8.010.0 7.Sil.3 STW-408 Water April 1985 H-3 3399i150 3559i630 STW-409 Water April 1985 (Blind) Gross alpha 29.7tl.8 32.0f8.7 i Sample A Ra-226 4.410.2 4.111.0 '

Ra-228 NA8 6.211.6 Uranium NA8 7.0t10.4 Sample B Gross beta 74.3til.8 72.0i8.7 Sr-89 12.3f7.6 10.0i8.7 Sr-90 14.7i2.4 15.0*2.6 Co-60 14.712.4 15.0i8.7 Cs-134 12.0i2.0 15.018.7 Cs-137 14.0i2.0 12.0i8.7 l

I A-5

l l

I I

l Table A-1. (continued) i Concentration in )Ci/lb j Lab Sample Date TIML Result EPA lesult Code Type Collected Analysis *2ac ilo, n=3d  ;

STW-413 Water May 1985 Sr-89 36.0*12.4 39.018.7 Sr-90 14.3i4.2 15.0*2.6 STW-414 Water May 1985 Gross alpha 8.3i4.1 12.018.7 Gross beta 8.711.2 11.018.7 STW-416 Water June 1985 Cr-51 44.7i6.0 44.0i8.7 Co-60 14.3fl.2 14.0i8.7 Zn-65 50.317.0 47.018.7 Ru-106 55.315.8 62.018.7 Cs-134 32.7*1.2 35.0i8.7 Cs-137 22.7*2.4 20.0i8.7 STW-418 Water June 198S H-3 2446t132 2416t609 STM-421 Milk June 1985 Sr-89 10.3t4.6 11.0i8.7 Sr-90 9.0i2.0 11.0*2.6 I-131 11.7*1.2 11.0*10.4 Cs-137 12.7tl.2 11.0i8.7 K-40 1512162 1525i132 STW-423 Water July 1985 Gross alpha 5.010.0 11.0*8.7 Gross beta 5.0f2.0 8.018.7 STW-425 Water August 1985 I-131 25.7*3.0 33.0i10.4 STW-426 Water August 1985 H-3 4363183 44801776 STAF-427 Air August 1985 Gross alpha 11.310.6 13.0i8.7 Filter Gross beta 46.0il.0 44.018.7 Sr-90 17.7i0.6 18.0i2.6 Cs-137 10.310.6 8.0t8.7 STW-429 Water Sept. 1985 Sr-89 15.7i0.6 20.018.7 Sr-90 7.0f0.0 7.0i2.6 STW-430 Water Sept. 1985 Ra-226 8.210.3 8.9i2.3 Ra-228 4.110.3 4.6*1.2 STW-431 Water Sept. 1985 Gross alpha 4.7i0.6 8.018.7 Gross beta 4.711.2 8.018.7 A-6

Table A-1. (continued)

Concentration in pCi/lb Lab Sample Date TIML Result EPA tesult Code Type Collected Analysis *2bc ilo, n=3d STW-433 Water Oct. 1985 Cr-51 <13 21.0i8.7 Co-60 19.30.6 20.0i8.7

, Zn-65 19.7*0.6 19.0*8.7

) Ru-106 <19 20.0f8.7 Cs-134 17.011.0 20.018.7 Cs-137 19.3tl.2 20.0i8.7 j STW-435 Water Oct. 1985 H-3 1957150 1974i598 STW-436 Water Oct. 1985 i

437 (811nd)

Sample A Gross alpha 53.0*1.0 52.0*22.6 Ra-226 5.910.1 6.3i1.6 Ra-228 8.210.1 10.112.6 Uranium nae 8.0i10.4 Sample 8 Gross beta 85.7i2.5 75.0i8.7 Sr-89 21.3*1.5 27.018.7 Sr-90 10.3i0.6 9.0i2.6 Co-60 18.311.2 18.0i8.7 Cs-134 16.3*1.2 18.0i8.7 Cs-137 19.0il.0 18.0*8.7 STM-439 Milk Oct. 1985 Sr-89 50.3i0.6 48.018.7 Sr-90 23.310.6 26.0*2.6 I-131 45.713.2 42.0*10.4 Cs-137 60.7i0.6 56.0i8.7 K-40 1547*29 1540i134 l l

STW-441 Water Nov. 1985 Gross alpha 5.310.6 10.0i8.7 Gross beta 11.711.2 13.018.7 STW-443 Water Dec. 1985 I-131 46.7i2.1 45.0*10.4 STW-444 Water Dec. 1985 Ra-226 6.Si0.1 7.lil.9 Ra-228 6.li0.1 7.3tl.9 STW-445 Water Jan. 1986 Sr-89 29.7*2.5 31.0i8.7 Sr-90 13.710.6 15.0*2.6 STW-446 Water Jan. 1986 Gross alpha 3.0f0.0 3.0i8.7 l Gross beta 5.3i0.6 7.018.7 l l

A-7 1

Table A-1. (continued)

Concentration in 1C1/lb Lab Sample Date TIML Result EPA Result Code Type Collected Analysis *2ac flo, n=3d

. STW-447 Food Jan. 1986 Sr-89 24.3i2.5 25.0i8.7 Sr-90 17.3*0.6 10.0*2.6 I-131 22.7*2.3 20.0i10.4 Cs-137 16.310.6 15.0i8.7 K-40 927146 950i249 STW-448 Water Feb. 1986 Cr-51 45.0t3.6 38.0t8.7 Co-60 19.7*1.5 18.0i8.7 Zn-65 44.0i3.5 40.018.7 Ru-106 <9.0 0. 0f8. 7 Cs-134 28.312.3 30.0*8.7 Cs-137 23.7i0.6 22.0i8.7 STW-449 Water Feb. 1986 H-3 5176i48 52271910 STW-450 Water Feb. 1986 U total 8.010.0 9.0*10.4 STW-451 Milk Feb . 1986 I-131 7.0f0.0 9.0i10.4 STW-452 Water March 1986 Ra-226 3.810.1 4.lil.1 Ra-228 11.010.5 12.413.2 STW-453 Water March 1986 Gross alpha 6.7i0.6 15.018.7 Gross beta 7.3i0.6 8.0i8.7 a STW-454 Water April 1986 I-131 7.010.0 9.0110.4 STW-455 Water April 1986 456 (Blind)

Sample A Gross alpha 15.0il.0 17.0i8.7 Ra-226 3.110.1 2.9i0.8 Ra-228 1.5i0.2 2.0i0.5 Uranium 4.7i0.6 5.Qt10.4 Sample 8 Gross beta 28.711.2 35.0i8.7 Sr-89 5.710.6 7. 0i8. 7 Sr-90 7.010.0 7.0f2.6 Co-60 10.7*1.5 10.0i8.7 Cs-134 4.0il.7 5.018.7 Cs-137 5.310.6 5.018.7 i

A-8

l Table A-1. (continued)

Concentration in pCi/lb Lab Sample Date TIML Result EPA Result Code Type Collected Analysis fasc ilo, n=3d STAF-457 Air April 1986 Gross alpha 13.710.6 15.0i8.7 Filter Gross beta 46.3i0.6 47.018.7 Sr-90 14.7*0.6 18.012.6 Cs-137 10.7i0.6 10.0i8.7 STU-458 Urine April 1986 Tritium 4313i70 44231327

- STW-459 Water May 1986 Sr-89 4.310.6 5.0t8.7 l Sr-90 5.0i0.0 5.0f2.6 STW-460 Water May 1986 Gross alpha 5.3*0.6 8.018.7 Gross beta 11.3i1.2 15.0i8.7 STW-461 Water June 1986 Cr-51 <9.0 0.0*8.7 Co-60 66.011.0 66.018.7 Zn-65 87.3i1.5 86.018.7 Ru-106 39.7*2.5 50.018.7 Cs-134 49.3*2.5 49.0i8.7 Cs-137 10.3fl.5 10.018.7 STW-462 Water June 1986 Tritium 3427125 3125i626 STM-464 Milk June 1986 Sr-89 <1.0 0.018.7 Sr-90 15.310.6 16.012.6 I-131 48.312.3 41.0110.4 Cs-137 43.711.5 31.0i8.7 K-40 1567i114 1600i139 STW-465 Water July 1986 Gross alpha 4.710.6 6.0i8.7 Gross beta 18.7tl.2 18.018.7 ,

STW-467 Water August 1986 I-131 30.3i0.6 45.0110.4 STW-468 Water August 1986 Pu-239 11.310.6 10.lil.8 STW-469 Water August 1986 Uranium 4.010.0 4.0110.4 STAF-470 Air September 1986 Gross alpha 19.3fl.5 22.0f8.7 471 Filter Gross beta 64.0i2.6 66.0i8.7 472 Sr-90 22.011.0 22.0i2.6 Cs-137 25.711.5 22.0i8.7 STW-473 Water September 1986 Ra-226 6.0f0.1 6.lil.6  !

Ra-228 8.7tl.1 9.1*2.4 j A-9

-i i

1 Table A-1. (continued) l Concentration in >Ci/lb ,

I l Lab Sample- Date TIML Result EPA tesult

< Code Type Collected Analysis *2ac flo, n=3d I

STW-474 Water September 1986 Gross alpha 16.3*3.2 15.0*8.7 Gross beta 9.0*1.0 8.0i8.7 j

i

-STW-475 Water October 1986 Cr-51 63.3i5.5 59.0*8.7 i Co-60 31.0*2.0 31.0*8.7 Zn-65 87.3i5.9 85.0t8. 7 Ru-106 74. 717.4 74. 0i8. 7 i Cs-134 25.7*0.6 28.0*8.7 i Cs-137 46.3*1.5 44.0*8.7' l

STW-476 Water October 1986 H-3 5918t60 5973*1035 l

! STM-479 Milk November 1986 Sr-89 7.7tl.2 9.0*8.7 Sr-90 1.0i0.0 0.0*2.6 I-131 52.3*3.1 49.0i10.4 e Cs-137 45.7*3.1 39.0t8.7 l K-40 1489*104 1565*135 4

STU-480 Urine November 1986 H-3 5540*26 5257*912 STW-481 Water November 1986 Gross alpha 12.0i4.0 20.0i8.7 Gross beta 20.0*3.5 20.0*8.7 i

a Results obtained by Teledyne Isotopes Midwest Laboratory as a participant

! in the environmental sample crosscheck program operated by the Intercom-

! parison and Calibration Section, Quality Assurance . Branch, Environmental

! Monitoring and Support Laboratory, U.S. Environmental Protection Agency, b (EPA), Las Vegas, Nevada.

All results are in pCi/1, except for elemental potassium (K) data, which are l in mg/1; air filter samples, which are in pCi/ filter; and food, which is in 4 pCi/kg.

! C Unless otherwise indicated, the TIML results are given as the mean *2 standard -

I deviations for three determinations.

d USEPA results are presented as the known values i control limits of b for

n = 3.

] e NA = Not analyzed.

i f Analyzed but not reported to the EPA.

! 9 Results after calculations corrected (error in calculations when reported to l EPA).

A-10 h

i

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

l mR Teledyne Average 120 d i

Lab TLD Result Known (all i

Code Type Measurement 12aa valuec participants) 2nd International Intercomparisonb 4

115-2 CaF2:Mn Field 17.011.9 17.1 16.417.7 I

BuTb Lab 20.814.1 21.3 18.8*7.6 3rd International Intercomparisone

, 115-3 CaF2:Mn Field 30.713.2 34.914.8 31.513.0 P Bulb

] = Lab 89.6i6.4 91.7114.6 86.2124.0 4th International Intercomparisonf 115-4 CaF2:Mn Field 14.111.1 14.111.4 16.0i9.0 BuTb Lab (Low) 9.311.3 12.212.4 12.0i7.6 Lab (High) 40.4*1.4 45.819.2 43.9*13.2 5th International Intercomparison9

' 115-5A CaF2:Mn Field 31.411.8 30.0i6.0 30.2114.6 Bulb Lab at 77.415.8 75.217.6 75.8*40.4 1 beginning Lab at 96.615.8 88.4*8.8 90.7131.2 the end

i Table A-2. (Continued) mR Teledyne Average i 20 d Lab TLD Result Known (all Code Type Measurement 12ba 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

?

O 115-7A LiF-100 Field 75.412.6 75.816.0 75.1129.8 Chips Lab (Co-60) 80.013.5 79.914.0 77.9127.6 4

Lab (Cs-137) 66.612.5 75.013.8 73.0122.2 115-78 CaF2:Mn Field 71.Si2.6 75.816.0 75.1129.8 Bulbs Lab (Co-60) 84.816.4 79.914.0 77.9127.6 Lab (Cs-137) 78.821.6 75.013.8 73.0122.2 115-7C CaSO4 :Dy Field 76.812.7 75.816.0 75.1129.8 Cards

! Lab (Co-60) 82.Si3.7 79.914.0 77.9127.6 Lab (Cs-137 79.013.2 75.013.8 73.0122.2 i

Table A-2. (Continued) mR 1

Teledyne Average i ay . d I Lab TLD Result Known (all.

j Code Type Measurement ta, a Valuec participants).

i 8th International Intercomparisoni l 115-8A LiF-100 Field Site 1 29.5tl.4 29.711.5 28.9112.4 Chips 11.310.8 10.410.5 10.119.06 Field Site 2 Lab (Cs-137) 13.710.9 17.210.9 16.216.8

, 115-88 CaF2:Mn Field Site 1 32.3tl.2 29.711.5 28.9112.4 Bulbs Field Site 2 9.0il.0 10.4i0.5 10.119.0

Lab (Cs-137) 15.810.9 17.210.9 16.216.8 y

i  ;;

1 115-8C CaSO4 :Dy Field Site 1 32.310.7 29.711.5 28.9112.4 Cards Field Site 2 .10.610.6 10.410.5 10.119.0 Lab (Cs-137 18.110.8 17.2i0.9 16.216.8

)

j a Lab result given is the mean *2 standard deviations of three determinations.

j b Second International Intercomparison of Environmental Dosimeters conducted in April of 1976 by the Health and Safety Laboratory (GASL), New York, New York, and the School of Public Health of the University of

- Texas, Houston, Texas.

c value determined by sponsor of the intercomparison using continuously operated pressurized ion chanber.'

d Mean 12 standard deviations of results obtained by all laboratories participating in the program.

e Third International. Intercomparison of Environmental Dosimeters conducted in summer of 1977 by Oak Ridge l

National Laboratory and the School of Public Health of the University of Texas, Houston, Texas.

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

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

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

Eighth International Intercomparison of Environmental Dosimeters conducted in the fall and winter of 1985-1986 at New York, New York, and sponsored by the U.S. Department of Energy.

Table A-3. In-house spiked samples.

Concentration in pC1/1 Lab Sample Date TIML Result Known Expected Code Type Collected Analysis n=3 Activity Precision 1s, n=3a QC-MI-6 Milk Feb. 1986 Sr-89 6.0il.9 6.4i3.0 8.7-Sr-90 14.211.7 12.9*2.0 5.2 I-131 34.213.8 35.2i3.5 10.4 Cs-134 32.0il.8 27.3i5.0 8.7 Cs-137 35.8i2.1 35.015.0 8.7 QC-W-14 Water Mar. 1986 Sr-89 1.610.4 1.6*1.0 7.1 Sr-90 2.410.2 2.412.0 4.2 QC-W-15 Water Apr. 1986 I-131 44.9*2.4 41.Si7.0 10.6 Co-60 10.6tl.7 12.115.0 7.lb Cs-134 30.212.4 25.818.0 7.lb Cs-137 21.9tl.9 19.9i5.0 7.lb QC-MI-7 Milk Apr. 1986 I-131 39.713.3 41.5i7.0 10.4 Cs-134 28.7i2.8 25.8i8.0 8.7 Cs-137 21.2i2.8 19.9i5.0 8.7 SPW-1 Water May 1986 Gross alpha 15.8tl.8 18.015.0 Sc QC-W-16 Water June 1986 Gross alpha 16.210.7 16.9i2.5 8.7 Gross beta 38.4i3.5 30.2*5.0 8.7 QC-MI-9 Milk June 1986 Sr-89 <1.0 0.0 7. lb

, Sr-90 12.6tl.8 13.3i3.0 4.2b I-131 38.917.0 34.8i7.0 10.4 Cs-134 33.013.4 36.li5.0 8.7 Cs-137 38.Si2.8 39.0i5.0 8.7 SPW-2 Water June 1986 Gross alpha 16.8tl.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 31.315.0 8.7 Cs-137 51.li7.0 43.318.0 8.7 QC-W-19 Water Sep. 1986 Sr-89 13.614.1 15.613.5 7.lb Sr-90 6.411.6 6.2i2.0 4.2b A-14

Table'A-3. In-house spiked samples (continued)

Concentration in pC1/1 1 Lab Sample Date TIML Result Known Expected Code Type Collected Analysis n=3 Activity Precision 1s,.n=3a QC-W-21 Water Oct. 1986 Co-60 19.2i2.2 18.513.0 8.7 Cs-134 31.7tS.2 25.6*8.0 8.7 )

Cs-137 23.811.0. 21.6i5.0 8.7 QC-MI-11 Milk Oct 1986 Sr-89 12.3i1.8 14.3i3.0 8.7 QC-W-20 Water Nov. 1986 H-3 3855i180 3960i350 520b QC-W-22 Water Dec. 1986 Gross alpha 9.8tl.4 11.214.0 8.7 Gross beta 21.7*2.0 23.815.0 8.7 QC-W-23 Water Jan. 1987 I-131 29.8i2.5 27.9i3.0 10.4 QC-MI-12 Milk Jan. 1987 I-131 36.Sil.3 32.6i5.0 10.4 Cs-137 32.614.2 27.418.0 8.7 a

b n=3 unless noted otherwise. a n=2.  ;

c n=1.

i, 1

i A-15 {

l

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

Concentration in pCi/l  !

Acceptance .

Lab Sample Date Results Criteria 1 Code Type Collected Analysis (4.660) (4.660) .

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 1

Sr-90 <0.6 <1 ,

BL-5 D.I. Water Nov. 1985 Ra-226- <0.4 <1 Ra-228 <0.4 <1 i 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  !

I-131 <0.2 <1 l Cs-137 (gamma) <7.4 <10 l BL-6 0.I. Water Apr. 1986 Gross alpha <0.4 <1 BL-7 D.I. Water Apr. 1986 Gross alpha <0.4 <1 BL-8 0.I. Water June 1986 Gross alpha <0.4 <1 a BL-9 D.I. Water June 1986 Gross alpha <0.3 <1 l t

l k

, 1 i

1 A-16 s.

4 1

Appendix B Data Reporting Conventions l

B-1

Data Reporting Conventions 1.0. All activities are decay corrected to collection time.

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

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

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

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

3.0. Duplicate Analyses 3.1. Individual results: x1 i si s

x2 i 52 l Reported result: xis where x = (1/2) (x1 + x2) s= s 2,32 3.2. Individual results: <Ll

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

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

<L otherwise

B-2

4.0. Computation of Averages and Standard Deviations

! 4.1 Averages and standard deviations listed in the tables are coguted 1

from all of the individual measurements over the period averaged; 7 for exagle, an annual standard deviation would not be the average  ;

of quarterly standard deviations. The average i and standard i

deviation (s) of a set of 'n nuders x1, x2, . . . xn are defined  ;

as follows

,

{ Y=1n Ex ,

I s= ZI*~*I2 n-1 4.2 Values below the highest lower I!mit of detection are not included in the average.

j 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 i single value x and associated two sigma error is reported.

l 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 J 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 exagle,11.446 is rounded off to 11.45. l 4.5.3. If the figure following those to be retained is 5, and if there are no figures other than zeros beyond the five, the figure 5 is dropped, and the last-place figure retained is

increased by one if it is an odd nuder or it is kept

! unchanged if an even number. As an exagle,11.435 is i, rounded off to 11.44, while 11.425 is rounded off to 11.42.

1

)

)

l B-3

r a I

t 1

Appendix C Maximum Permissible Concentrations of Radioactivity in Air and Water Above Background in Unrestricted Areas i

C-1

Table C-1. Maximum permissible concentrations of radioactivity in air and water above natural background in unrestricted areas.a Air Water Gross alpha 3 pCi/m3 Strontium-89 3,000 pCi/1 Gross beta 100 pCi/m3 Strontium-90 300 pCi/1 Iodine-131b 0.14 pC1/m3 Cesium-137 20,000 pCi/1 Barium-140 20,000 pCi/1 Iodine-131 300 pCi/1 Potassium-40c 3,000 pCi/1 Gross alpha 30 pCi/1 Gross beta 100 pCi/1 Tritium 3 x 106 pC1/1 a Taken from Code of Federal Regulations Title 10, Part 20, Table II and appro-priate footnotes. Concentrations may be averaged over a period not greater 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.

l l

l l

C-2