ML20245C628

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Annual Rept to NRC Radiation Environ Monitoring Program 1988
ML20245C628
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 02/18/1989
From: Huebner L
TELEDYNE ISOTOPES MIDWEST LABORATORY
To:
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ML20245C626 List:
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NUDOCS 8904270300
Download: ML20245C628 (69)


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' " W TELEDYNE ISOTOPES 1 MIDWEST LABORATORY ro0 LAnowesR RoAo NORTHBROOK, ILLINOIS 80062 P310 (312) 664-0700 Ft.X (312) 564 617 -

NORTHERN STATES POWER C&:PANY MINNEAPOLIS, MINilES0TA ,

PRAIRIE ISLAND NUCLEAR GENERATING PLANT

  • Docket No. 50-282 Licensc No, DPR-42 50-306 DPR-60 ANNUAL REPORT to the UNITED STATES NUCLEAR REGULATORY COMMISSION Radiation Environmental Monitoring Program January 1,1988 to December 31, 1988 Prepared Under Contract by TELEDYNE ISOTOPES MIDWEST LABORATORY Project No. 8010 l

Approved by: uh6

[5..G.Huebner General Manager 18 February 1989

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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 members of this laboratory.

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l TABLE OF C0flTENTS Section Page Preface ........................... ii Li s t of T abl es . . . . . . . . . . . . . . . . . . . . . . . . iv 1.0 I NT R O D U CT I O N . . . . . . . . . . . . . . . . . . . . . . . . . 1 2.0 SUtif1ARY ........................... 2

3. 0 RADIATI0fl EflVIR0ftf1 ENTAL fl0flITORIllG PROGRAF 1 (REf1P) ...... .3 3.1 Program Design and Data Interpretation ......... 3 3.2 Prog ram Desc ri pti on . . . . . . . . . . . . . . . . . . . .4 3.3 Program Execution . . . . . . . . . . . . . . . . . . . . 5 3.4 Laborato ry Procedu res . . . . . . . . . . . . . . . . . . 6 3.5 Program flodi fic ations . . . . . . . . . . . . . . . . . . 6 3.6 ' Land Use Census . . . . . . . . . . . . . . . . . . . . . 6
4. 0 RESULTS AtlD DISCUSS 10fl . . . ................. 8 4.1 Atmospheric fluclear Detonations and flu c l e a r Ac ci d ent s . . . . . . . . . . . . . . . . . . . 8 4.2 Program Findings ..... ...,.,,....... 8 5.0 TABLES . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12

6.0 REFERENCES

CITED . . . . . . . . . . . . . . . . . . . . . . . 24 APPEtlDICES A Interlaboratory Comparison Program Results . . . . . . . . . . A-1 B Data Reporting Conventions . . . . . . . . . . . . . . . . . . B-1 C flaximum Permissible Concentrations of Radio-activity in Air and Water Above flatural Background in Unrestricted Areas . . . . . . . . . . . . . . C-1 iii

LIST OF TABLES flo,. Title Page 5.1 Sample Collection and Analysis Program,1988 . . . . . . . . . 13 S.2 Sampl i ng Locati ons . . . . . . . . . . . . . . . . . . . . . . 15 5.3 flissed . Collections and Analyses,1988 .......,,,.. 17 5.4 Environmental Radiological fionitoring Program Summary .... 18 In addition, the following tables are in the Appendices:

Appendix A A-1 Interlaboratory Comparison Program Results, 1984-1988 .... A-3 A-2 Interlaboratory Comparison Program Results (TLDs) ...... A-17 A-3 In-house Spiked Samples ................... A-20 A-3 In-hou se "Bl ank " Sampl es . . . . . . . . . . . . . . . . . . . A-24 Attachment B: Acceptance criteria for spiked samples .... A-28 Addendum to Appendix A: Explanation of the Results Outside of Control Limits ................. A-29 Appendix C C-1 itaximum Permissible Concentrations of Radioactivity in Air and llater Above Natural Background in Unrestricted Areas . . . . . . . . . . . . . . . . . . . . . C-2 iv i

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1.0 INTRODUCTION

This report summarizes and interprets results of the Radiation Environmental Monitoring Program (RD4P) conducted by Teledyne Isotopes Midwest Laboratory at the Prairie Island Nuclear Generating Plant, Red Wing, Minnesota, during i the period January - December, 1988. This program monitors the levels of radioactivity in the cir, terrestrial, and aquatic environments in order to assess the $mpact of the plant on its surroundings.

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,1988) available at Northern States Power Company, 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 plant has two 550 MWe pressurized water reactors. Unit 1 achieved initial criticality on 1 December 1973. Commercial operation at full power began on 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 SUMMA _R_Y The Radiation Environmental Monitoring Program (REMP) required ty the U.S.

Nuclear Regulatory Commission (NRC) Technical Specifications for the Prairie Island Nuclear Generating Plant is described. Results for 1988 are summarized and discussed.

Program findings show background levels of radioactivity in the environmental samples collected in the vicinity of the Prairie Island Nuclear Generating Plant. No effect on the environment due to the operation of the plant is indicated.

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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 (Ti.Ds). ,

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-cdnlly Idrger than that at the control l ocation. The difference would have to be greater than could be accounted for by typical fluctuations in radiation levels arising fron 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 iodi ne-131. Most samples are also analyzed for gamma-emitting isotopes with resJlts for the following groups quantified: zirconium-95, 3

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cesium-137, cerium-144, beryll i um-7, and potassium-40. The first three 1 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, cobal t-58, and -60, and zi nc-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 i became operational. Results of the plant's monitoring program can be '

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

3.2 Program Description The sampling and analysis schedule for the 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 particulate are collected on membrane filters by continuous pumping at five locations. Also, airborne iodine is collected by continuous pumping through charcoal filters at all of these locations. Filters are changed and counted weekly. Particulate filters are analyzed for gross beta activity and charcoal filters for 4

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i i odi ne-131. A monthly composite of all particulate filters is gamma-scanned on an 'HP Ge or Ge(Li.) detector. One of the five locations is a control (P-1), a'nd 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 (highest D/Q residence).

As' a " Lessons Learned" commitment, ambient gamma radiation is monitored at thirty-two (32) locations, using CaSo4:Dy dosimeter with four sensi-tive areas at each location: ten (10) in an inner "ing in the general 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' niles distant from the plant. They are replaced and measured quarterly. Al so , a complete . emergency set of TLDs for all locations is placed in the field at the same time as regular sets. The emergency set

.is returned to TIML quarterly for annealing and repackaging.

Milk samples are collected monthly from five farms (four indicator and one controi). 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-emitting isotopes.

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

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-sites are analyzed for tritium.

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

Monthly composites are analyzed for gross beta, i odi ne-131, and gamma-emitting isotopes. Quarterly composites are analyzed for tritium, The aquatic environment is also nonitored 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.

3. 3 Program Execution The Program was executed as described in the preceding section with the following exceptions:

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1. The TLD data for the first quarter' of 1988 for. Location P-05S was not available because TLD was lost in the fiel d.

P 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(Li) spectrometry. Levels of airborne iodine-131 in charcoal sampl es. j 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 i are specified in detail elsewhere (Teledync Isotopes Midwest Laboratory,  !

1985). Procedures are. based on those prescribed by the National Center for Radiological Health of the U. S. Public Health Service (U. S. Public Health Service, 1967 ) and by the Health and Safety Laboratory of the U. S. Atomic Energy Commission (U. S. Atomic Energy Commission, 1972).

Teledyne Isotopes Midwest Laboratory has a comprehensive quality control /

quality assurance program designed to assure the reliability of data obtained. Details of TIML's Quality Assurance Program are presented elsewhere (Teledyne Isotopes Midwest Laboratory,1988). 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 During the growi ng season, milk producers were monitored to determine when the dairy animals were on pasture or fresh cut feed. The frequency of milk samples was increased to semimonthly at one indicator location (Gustafson) and one control location (Kinneman) during the period because animals were on pasture or fresh cut feed.

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 i

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i animal the nearest residence, and the nearest garden of greater than 3 500 ft$ producing fresh leafy vegetables in eacn of the 16 meteorological j sectors within a distance of 5 miles. This census is conducted at least I l once per 12 months between the dates of May 1 and October 31. New- i 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. i 1

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.

The 1988 Land Use Census was completed on July 8,1988. This census did not identify any locations of exposure pathways different from those used in the program during the first six months of the year. Milk and garden sample locations did not change due to the requirements of the land use Census.

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

4.1 Atmospheric Nuclear Detonations and Nuclear Accidents There were no reported atmospheric nuclear tests'in 1988. 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 1988.

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 1988.

Ambient Radiation (TLDs) h Ambient radiation was measured in the general area of site boundary, at l outer ring 4 - 5 mi distant from the Plant, at special interest areas, l~ and at one control l ocation. The means ranged from 14.9 mR/91 days at inner ring locations to 15.8 mR/91 days at outer ring locations. The mean at special locations was 14.4 mR/91 days and 16.0 mR/91 days at the control location. The dif ferences 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 8

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1983 (13.0 and 14.9 mR/91 days, respectively); in 1984 (13.9 and 15.3 i mR/91 days, respectively); in 1985 (13.9 and 15.3 mR/91 days, respec-tively); in 1986 (16.6 and 17.0 mR/91 days, respectively) and in 1987 (15.4 and 16.0 mR/91 days, respectively). No plant effect on ambient gamma radiation was indicated.

l Airborne Particulate The average annual gross beta concentration in airborne particulate was identical at both indicator and control locations (0.030 pCi/m3) and was slightly higher than the levels observed in 1982 (0.026 1983 l

(0.023 1984 (0.024 pC1/m3), 1985 (0.025 pCi/m3) 1986 ,pCi/m3)

(0.025, pC1/m3) ,pC1/m3) ,and 1987 (0.024 pCi/m3).

The average of 0.025 pCi/m3 for 1986 does not include the results from May 19 to June 9, 1986, which were influenced by the accident at Chernobyl.

A spring peak in beta activity had been observed almost annually for many years (Wilson et al., 1969). It had been attributed to fallout of nuclides from tFe stratosphere (Gold et al., 1964). It was pronounced in 1981, occurred to a lesser degreT f51982, and 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 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, 1985, 1986 (ex-clusive of the period between May 19, 1986 and June 9, 1986) and 1987.

Two pieces of evidence indicate conclusively that the elevated cctivity observed during the fourth quarter was not attributable to the Plant op-eration. In the first place, elevated activity of similar size occurred simultaneously at both indicator and control locations. Secondly, an identical pattern was observed at the Monticello Nuclear Generating Plant, about 100 miles distant from the Prairie Island Nuclear Generating Plant (Northern States Power Company,1988).

Gamma spectroscopic analysis of quarterly mmoosites of air particulate filters yiel ded similar results for inu. ator and control locations.

Berylliun-7, which is produced continuously in the upper atmosphere by cosmic radi atic'1 ( Arnol d and Al-Sal i h, 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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Milk Iodine-131 results were below the detection limit of 1.0 pCi/l in all sempl es.

Cs-137 results were below the LLD level of 15 pCi/l in all samples. 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 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 1988 show no radiological effects of  !

the plant operation.

Drinking Water In drinking water from the City of Red Wing well, tritium activity was below the LLD level of 330 pCi/l in all camples. Iodine-131 activity was  ;

also below the LLD level at 1.0 pCi/l in all samples. As with the other well water sampl es , all analyses for gamma-emitting isotopes yielded results below detection limits. Gross beta averaged 8.0 pCi/1 and was similar to the levels observed in 1979 (10.5 pCi/1),1980 (11.8 pCi/1),

1981 (10.7 pCi/1),1982 (8.9 pCi/1),1983 (8.0 pCi/1),1984 (7.9 pCi/1), i 1985 (7.1 pCi/1), 1986 (6.8 pCi/1) and 1987 (7.9 pCi/1). I I

i River Water At the upstream and downstream collection sites, quarterly composite i tritium levels were below the LLD level of 330 pCi/1 in all sampl es.

River water was also analyzed for gamma-emitting isotopes. All gamma-emitting isotopes were below their respective detection limits. There was no indication of a plant effect.

Well Water 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 level of 330 pC1/1 in all samples.

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

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a Crops Two samples of cabbage were collected in August and analyzed for I-131.

The I-131 level was below 0.034 pCi/g wet weight in both samples. There was no indication of a plant.effect.

Fish Fish samples were collected in June, September, and October,1988. The only isotope detected was naturally-occuring potassium-40 and there was no significant difference between upstream and downstream results. There was no indication of a plant effect.

Aquatic Insects or Periphyton Aquatic insects (invertebrates) or periphyton were collected in June, May, and September,198G. 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 April and September,1988. The samples were analyzed for gamma-emitting isotopes.

Cs-137 was detected in two bottom sediment upstream samples and averaged 0.083 pC1/g 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 12

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) C ( C e a f n Q 1Q i c m oo ( 3(

r y m i 3 13 i sd c a Ct - - -

a i n n g Qa S H 1H r s a e ( c G P y u t o , ,, S l e q n Sl , ) )) G a p e e G 1 1 C CC 1 n yr i

,h 3 3 M MM , 3 A T F b c 1 1 ( (( 3 1 m S a - - S BS - -

A C e I I G GG H I n b o y i d c t n n d.

c a e Q W W t W W Q A e e qu / / / / / / / /

l C C C G G G G G l p e o y r C T F 8

8 9 a 1 l 3 ep

, P m y ABS ,6- ,4 , 4 a T 0S6 ,

81 6 2 r 1I0 2P 2 1 - 6 - -

g s d - - - - .

- - P - P P o n n PPP P , P P P r o a ,4- ,6- , ,9 ,

p i( - - - o) , ) - )

t ) P ) P tC ) CP C s a s AB5C C C ( C ( (

i c e 1111 ( , ( ,

65 ( 1 5 , 5 s od 0000 13 14 12 5 1 28 2 y L o - - - - - - - - - - - - - - -

l C PPPP PP PP PP P P PP P a

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d o n N 2 5 5 5 2 1 4 2 a 3 n

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l s

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_ a e e n l d e l o u er p i c e t g m t i n r a a a t i e vy S i r d t if m d a o r a t a u a p i e w r l es 1 i r t e ul e

. d e e a g t c l 5 e t n n w n a b M n) r r i w e a

_ e es o o r k l st l iD b b k e n l b pe r r v b bL l i l i og

_ a mT i i i i r e d re T A( A A M R D W E cv sw

d ee t r n =iu a st l 1 os s 3 pa I d 1 mp e e - o d I cn i

r o o r c ,y i e ml e a c h s urr r y t i iea P sd c o tt i n n y irs s a e l c .ral y u l nyt ua l e q A el qm a p e S S S S S ul = i n y r G G G G G qa = n A T F . eu3 a

) rn C C f nHQh

( a c n , ,l y o= yei b i pt m tAoi n b d c ,csf o y e e soi i d c t l yop t n n A A A A a l l rm) c a e A S S S S c ol tor e e qu / / / / / i C acce

) l p e G G G G G d ue b d l n npym e o y r i . nsl e u C T F b a h v n e a - at o i r rimnN t a gmmo n eam-o s = sg c n = y

( o /= = a i G CM 8

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a ASM(

,S G 9 t s  : n 1 a s u , ,so

) oyaws e l ul toa m p o nrel e a y 0 r i ebl s r T 2 t tt o g - 6 6 6 n nrsf g o s d P - - - o oas n r n n P P P C cuosi p o a , qraz i ( ) , , ,

= g e s t C ) ) ) . = d r i a s ( C C C 2 / =eg s c e 5 ( ( ( 2 CQ d y od 2 5 5 5 1 5 Boe l L o - - - - -  : ,Gch a C P P P P P e sy t n l wl  : s a b oh sig a l t w n d . T l n o yi n o ool cr a N 2 2 2 2 1 n f ml nu i oed n s= f u o d a qy i e Msel t n .d ark c i se , f e e f rd yd e l eool esw l dt ckdii o a eosb c ecsecy riiw l d e t ad sae l d s n ne* int p e e e sip - A c m t i ) t m e yW e e a a cn n i d et p l S v eo rs e d or  : y .l i n pi oe m e canst 1 o m t r st r na t i s ow 3 c

. u l o d nsios1 1 i uc eo np or e e ontl i s

. d c tb s n i ocl sei 5 e - o ye i ti eoyn M e ( e ht m l atl fl ik e l s l pr o e cal adl l b p hb i e t r ot osnoi b i o si rv t o L sC aAiM a d r i d en o h T Ec F e Pi B S a b c d l

l Table 5.2. Sampling locations. Prairie Island Code Typea Name Location P-1 C Air Station P-1 16.5 mi 0 348'/NNW P-2 Air Station P-2 0.5 mi 0 294'/WNW P-3 Air Station P-3 0.8 mi 0 313*/NW P-4 Air Station P-4 0.4 mi 0 359'/N l P-5 C Upstream of Plant 0.6 mi 0 60*/ENE P-6 Lock & Dam #3 & Air Station P-6 1.6 mi 0 129'/SE P-8 Community Center 1.0 mi 0 304*/NW P-9 Plant Well #2 0.3 mi 0 306*/NW P-11 City of Red Wing 7.1 mi 0 135'/SE P-12 Recreational Area 3.4 mi 0 116*/ESE P-14 Gustafson Farm 2.2 mi 0 168'/SSE P-16 Johnson Farm 2.6 mi 0 60*/ENE P-17 Place Farm 3.5 mi-0 25'/NNE P-18 Christensen Farm 3.7 mi 0 88'/E P-20 River Irrigated Corn Field

  • P-24 Highest D/Q Garden **

P-25 C Kinneman Farm 11.1 mi 0 331*/NNW P-01A Property Line 0.4 mi 0 359'/N P-02A Property Line 0.3 mi 0 19*/NNE P-03A Property Line 0.5 mi 0 183*/S P-04A Property Line 0.4 mi 0 204*/SSW P-05A Property Line 0.4 mi 0 225*/SW P-06A Property Line 0.4 mi 0 249*/WSW P-07A Property Line 0.4 mi 0 268'/W P-08A Property Line 0.4 mi 0 291*/NNW P-09A Property Line 0.7 mi 0 317'/NW P-10A Property Line 0.5 mi 0 333*/NNW P-01B Thomas Killian Residence 4.7 mi 0 355'/N P-02B Roy Kinneman Farm 4.8 mi 0 17'/NNE P-03B Wayne Anderson Farm 4.9 mi 0 46*/NE P-04B Nelson Drive (Road) 4.2 mi 0 61*/ENE P-05B County Road E and Coulee 4.1 mi 0 97*/E P-06B William Houschildt Residence 4.4 mi 0 112*/ESE P-07B Red Wing Service Center 4.7 mi 0 140*/SE P-08B David Wnuk Residence 4.1 mi 0 165'/SSE P-09B Highway 19 South 4.2 mi 0 187'/S P-10B Cannondale Farm 4.9 mi 0 200*/SSW a

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

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

i 15 t

Table 5.2. Sam,nling locations (continued) Prairie Island Code Typea Name Location P-11B Wallace Weberg Farm 4.5 mi 0 221*/SW I P-12B Roy Gergen Farm 4.5 mi 0 247*/WSW P-13B 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-02S Charles Suter Residence 0.6 mi 0 158*/SSE P-03S Carl Gustafson Farm 2.2 mi 0 168'/SSE P-04S Richard Burt Residence J.0 mi 0 228'/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 a

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

16 .

p i

o t TRLE 5.2

. FRAIR!E 15LANO NUCL AR GENERA 7:NG .:LANT f.

q RACIAT CN ENVIRON M ENTA L MONITCR!NG 'FROGR AM- .ve5w -

(il

~

-lLu--- -

e N

\ IFRE3CCTT

~

s s l

  1. , 'C - -V

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f  !.

p/ *

'%  %.T v,J(,) \ f ,s s!

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w; .j

.=. .,

h,p Ap bl

+ l-

o. /= w/

J.3

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w .

< s 3: ,g

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. = 11 mi e ,77@ ,1., 'l

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l \ t l 1 5- , _

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p,cg t .

i.i 8 x 2, e. s.

sis

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code numbers without the prefix P -

\

/

a q SCI LE IN MILES , f J

ifa

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+

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8

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0 1 2 3 a 5 s 7 5 9 10 5 C#%L.J. .i 4e 4" t

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16 c

Table 5.3. Missed collections and analyses,1988. Prairie Island Nuclear Generating Plant. All required samples were collected and analyzed as scheduled except the following.

Collection Date Sampl e Analysis Location or Period Comments Thermoluminescent Ambient P-05S 1st Qtr. 1988 Lost in the Dosimeters (TLDs) Radiation fi el d.

I 1

17 I

e' f n' ois tt rul -

eou 0 0 9 0 O O 0 0 0 0 0 0 0 O brs me unR ho N

8 _

))

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ri n n n 50 b

e tt nn naaa o) cwo o) cwo o) cw

/6 41

( -

( -

4 (40 6

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L L

L D

L D D D L L 6 m oceR o 01 L L L L 9 83 < < ( < < < < <

0 e CoM el el el 30 90 3 c

- e

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( (Sb (

Sb 61 0( 0. 0 5

1( 0(

- 6 2 y 8 r )

2 a

u ) ) )

)

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nn aa 41

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42

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0(

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g hM e t n n n N n il i a o n W W t

i wa L m s a N N t u S e f n l' 2 6N 1W e r nn ~

y/ n9 a9 e - - / /

k o p

on d t* n t ni P P* P*

c iA n r3 ii si nm 9 4 o e t o e8 K m um n n2 n9 D R c

a it p1 o y8 G

2 iK1 o o1 o2 o a r9 o i i i c P

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1 t c f TNA m m m m e n o o n r u n a o a a a a B S B M C C Z Z R e F G G G G G G

_ m n n f o o

r o i t

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_ b L mI ei L mO - i L mSn L mc iP(

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8 3 )

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5 2, y 8 r 2 a

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) c p iA n o*

d o e o s8 ft e D R t

a f6 om u

n c

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t a

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- - - y1 - - - - - - -

i _ c s9 t t

L u i7E n t

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c a 42 I , ng'5

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1 Ii 3 y 2 W1 r g P P a n m

m it u c )

S r a e e t t rsC r o a m

a r

e s t ton o) e

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)

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n ct(FC ai ia nn g D L

D D L

D D D

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r a

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L L

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L L

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2 (19 i

L

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L L

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g lc ,nu IL M 02 81 4

n u e o 31 0. 6 i N u C 1( 8(

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n a o 9 9 7 G

o ls b 1

0 7

0 0 4 1 1 7 f M I o 0 0 0 0 3 0 0 0 t

l e ( 0 0 0 0 0 1 0 5 5 5 1 1 0 5 0 5 5 a i 0 1 1 1 3 3 r 1 1 1 ic i 1 3 g a ,

o r l P y 5 4 4 2 t fa 2 4 2 io i d os 0 6

2 7 7 0

1 1 1 d l n e 4 4 a y i a rs 1 1 R t c ey 7 - 1 4 4 7 -

i a e bl 3 a 4 4 3 3 a l l F p ma 1 L 1 1 1 1 0 1 1 4 9 8 0 a y un L 1 5 5 5 6 t

i - - - - 3 3 4 - - - 3 - - - - -

c f T NA s a e e s n a o C B C C 1

1

- S K C C s

B a

D 1

3 n eF o Co n e F 1 G G 5 M C m n 1 l H G n f o o o r it i e a v

n m

a o c r E H L s e t

e ) a

) t d e s W

. a e 4

lp et pi e u3) n l u e 3) ) g) 5 myn ncmi nem rn/

1

/

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/

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b b rco rapc bdC rop lkCp nC p

a il( i( ir(

T iP( ( A M D A

li' "O'

l i!

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3 C

9 s) 1 l nF r

oo( e g ri e e e e D D D D D D D e tt nn n n n n D D D D D D D D D D D L L L L L L L L L L L L L L L L naaa o o o o v, be t

m oceR C oM N N N N L

(

t L L L L

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L L t t L

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L L L

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L

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L 3 c L

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2, y 8 r 2

0 n

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)

F 5 a ( e J g nn - - - - - - - - - - - - - - - - - - - - -

aa t eR s M d e h

io ig n r

e H a P e 1{

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n N

t t i il wau e r nn k

c p o cn d

)

iA n d o e t e e D R a u c it - - - - - - - - - - - - - - - - - - - - -

n o a itn L c t

o L

o n c a

( l P

y r g a n m

e it u a )

S r a e e t t rsC m n o a on a

r e s t G eS tai o) e g

o r

r n ,

a i y n

ict(Fc a nn d c aa g D L

L D D D L

L L L D

L D

L D

L D D L L D

L D

I D

L D

L D

L D

L D

L D

L D

L D D D D L L L L L t L t L L L L L L L L t L L L P e M t no eR < ( < ( ( < ( < ( ( ( ( < ( < < < < < <

g l

c .nu I L M n u e o i N uC r h (

o d d t n o i a o n G o ls b 5 0 5 5 0 N I D 1 3 1 '. 3 L

l e L 0 0 5 6 0 5 0 5 5 0 5 8 5 9 0 a i 1 1 1 4 3 1 3 1 1 3 1 1 1 7 3 r 3 ic 3 g ia o r P y 8 4 lo t fa 2 6

1 6

1 i i d o, 0 d l n e 4 0

4 a y i a rs 1 1 R t ey i ca e bl p ma 4

3 7

3 a

- 4 4 4 9 8 0 5 4

3 7

3 a

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1 5 6 6 1 1 L 1 5 5 5 6 6 t

n ic f T NA s s a e 3 n e o o n s s a e 3 n e o o n r a o C C B C - 5 M F C C Z C C B C - 5 M F C C Z e F H G H 6 m e n f o o o i

r e a ft l v

n m c r a o e E N L t )

a d r

) W e e r e s u t e 4 et g) n a) lppi n1 i W1 t) al 5 myn i/t / W/

aT U k1 n rl i S ( nC o eC le ipc v p l C p

b r(( i( le(

a D R W T

Il

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8 8

9 s) )

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oo(

ri eg D D D D D D D D

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/

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t L

L L

L

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L t

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L L

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3(

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. h M o g t f N n il o w a t it u m9 e r n n a k o o n d ei

) c p A n rm d o e it o t e D R a s6 u c it - - - - - - - p - - - e - - - - -

n o a U0 L c it n t o , .E N

L ) tE o n .

Cn/

c a a*

( l P

(5l 0 y P6 r g P a n i I m t ru a )

S r a e e t t r sC m n o a o n) )

a e s t t oFc r

g G eS n

ai( e c t g D D D D D D D D

)29

/

5 D D D o r n , ann D D D D D D (22 i L L L L L L L L L L L L L L L r a i y d caa t L L L L t L t - L t t L

t L L L t

L t P e M t n oep < < < < < < < < 8 ( < < < ( ( ( ( <

n I LM 26 g lcu .o u i

n h u C e 8.

2(

2 r h (

o d d t n o i a o n l G 4 0 6 4 7 4 3 2 o s b 3 4 7 8 3 1 7 3 4 1 M I D 0 l 0 0 0 0 1 0 0 0 1 L

l e L 5 0 5 0 0 5 1 0 Go 0 0 0 0 0 0 0 0 0 a

c ir 1 3 1 1 1 1 8 ig ia o r l P y 2 4 lo t fa i i d os 0 0 d l n e 5 4 5 4 a

y ic ars 9 1 9 1 R t ey - 4 7 - 4 - 4 7 -

i a ebl 0 5 b 3 3 a 4 4 9 8 0 5 b 3 3 a l l F pma 6 6 N 1 1 L 1 1 0 5 5 5 6 6 N 1 1 L a i yun - - - - - - - 3 4 - - - - - - - - -

t c f TNA o n r s s a e 1 - n e o o n r s s a n a o C Z Z C C B C - S K M F C C Z Z C C B e F 1 G m n n f o o o r it i e a v

n m

a o c

L N e

L J) t h)

) et st

) r d b e ee

. s e e b w l w 4 leppi et t) u a F a1 n Cg g 5 myn W/i / i aTU it si l e S ( l C n pc hC l po op sp b

a le( c r( i(

W ( C F T

b

e f n' ois tt rul eou 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 b rs 0 0 me 7 -

unR N o N

8 8

9 s) 1 l nF )

oo( e )

r e

ri tt nn g

D D L D DL D D D U D D D D D D /

2 )22

/

7 D D L L L L L L L L L L L b naaa L L L L L t L L L L L L t L

L 1

(29 L L 6 m oceR ( ( < < < < ( ( < ( ( (

( - t L 0 e CoM < < - 4 < <

3 c l 9 62

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9(

9

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( eg 5 a ) )7 J 2 22 nn - - - - - / /

aa - - - - - - - - - 1 - 29 - -

t eR ( ( -

s N 4 d e 9 62 o h 4 i

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0

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. P e o g ht M

N n il f f i w a o o t t u e r n n m0 m0 k o o n d a a

) c p A n ei ei d o e it o rm rm e D R a i t t u c t - - - - - s6 s6 n o a - - - - - - - - - p p - -

i L c U0 U0 t

n t L o , .EN , ,E N

o n )tE ) tE c a C n/ C n/

( l a* a*

y P (5l 0 (5l 0 P6 P6 r g P P a

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a e s t t oFc 0 r G e S a i( e )1 g n g 4 o r n .y c t D D D O DL D D D D D D D D D D r a i ann L L L L L L L L L L

/0 D D P e i M t d caa n oeR L

(

L t L L

(

t L L

(

L

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L

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L L

L L

t L

L

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L t

(41 -

L L

L L

g l

c ,nu I LM 25 5 < (

n u e o i N uC 5. 7 r h ( 8(

o d d t n o i

n a o l G o s b 3 6 9 7 6 1 4 3 6 9 9 2 6 1 M I D 0 4 2 3 9 8 6 3 5 2 7 5 4 5 2 2 5 6 5 4 0 0 0 L

l e L 3 7 0 0 0 0 0 0 2 0 0 0 a i 1 1 0 1 0 0 r

ic g

i a

o r l P y 4 t fa 6 io i dos d l n e 0 a 5 4 R t y i c

ars ey 9 1

- 3 6 4 7 - 1 4 i a ebl 4 8 0 l l F pma 7 0 5 5 b 0 0 3 3 a 4 4 4 8 a yun 5 6 6 N 1 1 1 1 L 1 1 7 0 5 5 ic f TNA

- 4 - - - - - - - - - - - - - - -

t n a o e - n o o n r u u s s a e e e 4

- n o 5 B K M C C Z Z R R C C B C C S B e F G K M C m n G n f o o

r o it e a ivn ma c o s E N L e)

)

t t ae )y

. s r w d esr 4 le et b nntd ain ppi eg 5 myn t/ l eg aTU rf mem/

e S ( eC orii l

vP t odC b t h ep T

a In( oSS(

B r ,l

i IiIlll1 i!

e f n8 ois n tt d i rul e e eou brs 0 0 0 0 0 0 0 0 0 0 t h y a t a ne unR c l i , e No d e d N n .l i eb m s

ta o -

il r i si f 8 a 8 ) n rv d 9 s) )2 o oa e 1 l nF 21 i t t r oo(

ri eg / t cs l e D D D D D D 20 D D D a ai u ttnn L L L L L L ( - L L L c e s b naaa L L L L L L 6 t t L o re e 6 m oceR < < ( ( ( < 34 < < < l u r 0 e CoM 80 ol 3 c L d ta s .

- e 0. 0 e v 0 0 D 0( i e L 5 f vn L

- i i o y c ti 2

8 r e p

at .d e 2 a l ant

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) s etoa n )2 rsiv 0 F 21 t te 5 a ( e / a rl al J g nn 20 oocE aa

- - - - - - ( - - - - s tro 6 t ctl t eR 34 n en .

s M 80 e soek d e m chl i

o h g 00 0(

. e er d

no m ti r i n l u anr e Ha ps on P e ma ,ffi o g hM t ae nI N n il f

o sm o e1 u3 t t i wau de i

t .l1 e r nn m9 nl cea -

a ub euvI k

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6.0 REFERENCES

CITED Arnol d, J. R. and H. A. Al-Sali h . 1955. Beryllium-7 Produced by Cosmic Rays. Science 121: 451-453.

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

Gold, S. , H. W. Barkhau, B. Shiein, 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 Analysis Data Tables, January - December 1978.

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

December 1978.

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

December 1979.

. 1980b. Radiation Environmental Monitoring for Prairie 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.

. 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 Dat.* Tables, January -

December 1981.

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

December 1982.

24

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

1986. "Chernobyl," Chemtech, October 1986, pp. 596-605.

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

Northern States Power Company. 1979. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S.

Nuclear Regulatory Commission, January 1, 1978 to December 31, 1978 (prepared by Hazleton Environmental Sciences). Minneapolis, Minnesota.

. 1980. Prairie Island Nuclear Generating Plant, Annual Radiation environmental Monitoring Report to the U.S. Nuclear Regulatory .

Commission, January 1,1979 to Decerrber 31,1979 (prepared by Hazleton j Environmental Sciences). Minneapolis, Minnesota.

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

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

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

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

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

l l

l 25 l

. 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 (prepared by Teledyne Isotopes Midwest Laboratory). Minneapolis, Minnesota.

Teledyne Isotopes Midwest Laboratory. 1971a. Quality Control Program, Revision 7. 20, November 1984.

. 1985. Quality Control Procedures Manual, Revision 6, 09 August 1985.

. 1985. Quality Assurance Program Manual, Revision 1,15 April 1985.

. 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. l l

. 1986a. Radiation Environmental Monitoring for Monticello i 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. l l

. 1987. Sampling Procedures, Prairie Island Nuclear Generating l Plant, Revision 16, 18 December 1987.

l . 1987a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analyses Data Tables, January - I December 1986. j 1

~

. 1987b. Radiation Environmental Monitoring for ' airie Island Nuclear Generating Plant, Complete Analyses Data Tablu, January - .

Dr.cember 1986.

l 26 L _-___ _ _-

F~

]

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

. 1988b. Radiation. Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analyses Data' Tables, January. -

December 1987.

l

. 1989a. Radiation Environmental Monitoring for Monticello "

t Nuclear Generating Plant, Complete Analyses Data Tables, January -

December 1988.

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

December 1988.

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).

Wil son, D.L W. , G. M. Ward _ and J. E. Johnson. 1969. In Environmental Contam-ination by Radioactive Materials, International Atomic Energy Agency,

p. 125.

i 9

27

Appendix A Interlaboratory Comparison Program Results NOTE: T!flL participates in intercomparison studies administered by U.S. EPA Envi ronment al flonitoring Systems Laboratory, Las Vegas, Nevada. The results are reported in Appendix A. Also reported are results of in-house spikes and blanks. Appendix A is updated twice a year and the complete Appendix is included in January and July monthly reports only.

Please refer to January and July Reports for information.

J anu ary, 1989 A-1

x

. .7 *,

Appendix A Interlaboratory Comparison Program Results Teledyne Isotopes Midwest Laboratory (formerly Hazleton Environmental Sciences)

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

Participant laboratories measure the concentrations of specified radionuclides and report them to the issuing agency. Several months later, the agency reports the known values to the participant laboratories and specifies control limits.

Results consistently higher or lower than the known values or outside the control

. limits indicate a need to check the instruments or procedures used.

The results in Table A-1 were obtained through participation in the environmental sample crosscheck program for milk, water, air filters, and food samples during the period May 1984 through November,1988. 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 1976,1977,1979,1980,1984, and 1985-1986 through partici-pation in the Second, Third, Fourth, Fifth, Seventh, and Eighth International Intercomparison of Environmental Dosimeters under the sponsorships listed in Table A-2.

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.

Attachment B lists acceptance criteria for " spiked" samples.

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

A-2

E e e'

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 1988.a Concentration in pCi/lb Lab Sample Date TIML Result EPA Resultd Code Type Collec ted Analysis 12ac Is, N=1 Control Limits STW-358 Water May 1984 Gr. alpha 3.0i0.6 315.0 0.0-11.7 Gr. beta 6.711.2 6i5.0 0.0-14.7 STM-366 Milk June 1984 Sr-89 21i3.1 2515.0 16.3-33.7 Sr-90 1312.0 17tl.5 14.4-19.6 I-131 4615.3 4316.0 32.6-53.4 Cs-137 38i4.0 3515.0 26.3-43.7 K 15771172 1496175 1336-1626 STW-368 Water July 1984 Gr. alpha 5.lil.1 6i5.0 0.0-14.7 Gr. beta 11.912.4 1315.0 4.3-21.7 STW-369 Water August 1984 I-131 34.315.0 34.0i6.0 23.6-44.4 STW-370 Water August 1984 H-3 3003i253 2817*356 2200-3434 STF-371 Food July 1984 Sr-89 22.015.3 25.0i5.0 14.3-33.7 Sr-S3 14.7*3.1 20. Dil . 5 17.4-22.6 I-131 <172 39.016.0 28.6-49.4 Cs-137 24.0i5.3 25.0i5.0 14.3-33.7 K 25031132 2605t130 2379-2831 STAF-372 _ Air August 1984 Gr. alpha 15.311.2 1715.0 8.3-25.7 Filter Gr. beta 56.0f0.0 51t5.0 42.3-59.7 Sr-90 14.3tl.2 1811.5 15.6-20.4 Cs-137 21.0i2.0 1515.0 6.3-23.7 1

STW-375 Water Sept 1984 Ra-226 5.110.4 4.910.7 3.6-6.2 {

Ra-228 2.210.1 2.310.4 1.7-2.9 STW-377 Water Sept 1984 Gr. alpha 3.311.2 5.015.0 0.0-13.7 Gr. beta 12.7i2.3 16.Di5.0 7.3-24.7 STW-379 Water Oct 1984 H-3 28601312 2810i205 2454-3166 STW-380 Water Oct 1984 Cr-51 <36 40i5.0 31.3-48.7 Co-60 20.311.2 2015.0 11.3-28.7 Zn-65 150i8.1 14715.0 138.3-155.7 Ru-106 <30 47i5.0 36.3-55.7 Cs-134 31.317.0 31i5.0 22.3-39.7 Cs-137 26.711.2 2415.0 15.3-32.7 A-3 I

o Table A-1. (continued)

Concentration in pCi/lb l Lab: Sample Date TIML Result EPA Resultd Code Type Collected Analysis *2ac Is, N=1 Control Limits STM-382 Milk Oct 1984 Sr-89 15.714.2 22i5.0 13.3-30.7 Sr-90 12.7tl.2 16fl.5 13.4-18.6 I-131 41.7i3.1 42i6.0 31.6-42.4 Cs-137 31.316.1 3215.0 23.3-40.7 K 1447i66 1517i76 1386-1648 STW-384 Water Oct 1984 Gr. alpha 9.7tl.2 1415.0 5.3-22.7 (81ind) Sample A Ra-226 3.310.2 3.0f0.5 2.2-3.8 Ra-228 3.4fl.6 2.110.3 1.6-2.6 Uranium nae 5.0 6.0 0.0-15.4 Sample 8 Gr. beta 48.315.0 6415.0 55.3-72.7 Sr-89 10.7i4.6 11i5.0 2.3-19.7 Sr-90 7.3fl.2 12il.5 9.4-14.6 Co-60 16.311.2 14i5.0 5.3-22.7 Cs-134 <2 215.0 0.0-10.7 Cs-137 16.711.2 1415.0 5.3-22.7 STAF-387 Air Nov 1984 Gr. alpha 18.7tl.2 1515.0 6.3-23.7 Filter Gr. beta 59.0i5.3 52i5.0 43.3-60.7 Sr-90 18.3tl.2 2111.5 18.4-23.6 Cs-137 10.311.2 1015.0 1.3-18.7 STW-388 Water Dec 1984 I-131 28.0t2.0 3616.0 25.6-36.4 STW-389 Water- Dec 1984 H-3 3583fl10 3182i360 2558-3806 STW-391 Water Dec 1984 Ra-226 8.411.7 8.6il.3 6.4-10.8 Ra-228 3.li0.2 4.110.6 3.0-5.2 STW-392 Water Jan 1985 Sr-89 <3.0 3.015.0 0.0-11.7 Sr-90 27.315.2 30.0il.5 27.4-32.6 STW-393 Water Jan 1985 Gr. alpha 3.311.2 515.0 0.0-13.7 Gr. beta 17.3i3.0 15i5.0 6.3-23.7 STF-395 Food Jan 1985 Gr. alpha 4.7i2.3 6.015.0 0.0-14.7 Gr. beta 11.311.2 15.015.0 6.3-23.7 Sr-89 25.3i6.4 34.015.0 25.3-42.8 Sr-90 27.Di8.8 26.011.5 23.4-28.6 I-131 38.012.0 35.016.0 24.6-45.4 Cs-137 32.712.4 29.015.0 20.3-37.7 K 1410 212 13821120 1174-1590 i

A-4

g, , j A ]

)

I Table A-1. (continued)

Concentration in pCi/lb j Lab Sample Date TIML Result EPA Resultd Code Type Collec ted Analysis 12ac Is, N=1 Control Limits l STW-397 Water Feb 1985 Cr-51 <29 4815.0 39.3-56.7 l Co-60 21.313.0 2015.0 11.3-28.7 j Zn-65 53.7i5.0 5515.0 46.3-63.7 Ru-106 <23 2515.0 16.3-33.7  ;

Cs-134 32.311.2 3515.0 26.3-43.7 L Cs-137 25.3i3.0 2515.0 16.3-33.7 STW-398 Water Feb 1985 H-3 3869f319 3796i634 3162-4430 STM-400 Milk March 1985 I-131 7.312.4 9.0i0.9 7.4-10.6 STW-402 Water March 1985 Ra-226 4.6i0.6 5.0i0.8 3.7-6.3 Ra-228 <0.8 9.0il.4 6.7-11.3 Reanalysis Ra-228 9.0i0.4 STW-404 Water March 1985 Gr. alpha 4.712.3 6i5.0 0.0-14.7 Gr. beta 11.311.2 15i5.0 6.3-23.7 STAF-405 Air March 1985 Gr. alpha 9.311.0 10.015.0 1.3-18.7 Filter Gr. beta 42.0il.1 36.0i5.0 27.3-44.7 Sr-90 13.311.0 15.0il.5 12.4 17.6 Cs-137 6.311.0 6.015.0 0.0-14.7 STW-407 Water April 1985 I-131 8.010.0 7.!a0.8 6.2-8.8 STW-408 Water April 1985 H-3 3399t150 35591630 2929-4189 STW-409 Water April 1985 (Blind) Gr. alpha 29.711.8 32.015.0 23.3-40.7 Sample A Ra-226 4.410.2 4.110.6 3.1-5.1 Ra-228 nae 6.210.9 4.6-7.8 Uranium NA8 7.0i6.0 0.0-17.4 Sample B Gr. beta 74.3fil.8 72.015.0 63.3-80.7 Sr-89 12.317.6 10.015.0 1.3-18.7 Sr-90 14.712.4 15.0il.5 12.4-17.6 Co-60 14.7i2.4 15.0 5.0 6.3-23.7 Cs-134 12.012.0 15.0i5.0 6.3-23.7 Cs-137 14.012.0 12.015.0 3.3 20.7 A-5

fg Table A-1. (continued)

"~

Concentration in pCi/lb Lab' ' Sample Date TIML Result EPA Resultd Code Type Collected Analysis 12ac 15, N=1 Control Limits STW-413 Water May 1985 Sr-89 36.0t12.4 39.0i5.0 30.3-47.7 Sr-90 14.314.2 15.011.5 12.4-17.6 STW-414 Water May.1985 Gr. alpha 8.314.1 12.0i5.0 3.3-20.7 Gr. beta 8.7tl.2 11.015.0 2.3-19.7 STW-416 Water June 1985 Cr-51 44.716.0 44.0i5.0 45.3-52.7 Co-60 14.3fl.2 14.0i5.0 5.3-22.7 Zn-65 50.3i7.0 47.0i5.0 38.3-55.7 Ru-106 55.315.8 62.015.0 53.3-70.7 Cs-134 32.7tl.2 35.015.0 26.3-43.7 Cs-137 22.712.4 20.015.0 11.3-28.7 STW-418 Water June 1985 H-3 24461132 2416i351 1807-3025 STM-421 Milk June 1985 Sr-89 10.314.6 11.015.0 2.3-19.7 Sr-90 9.9.t2.0 11.0il.5 8.4-13.6 I-131 11.7tl.2 11.016.0 0.6-21.4 Cs-137 12.7tl.2 11.015.0 2.3-19.7 K 1512162 1525t132 1393-1657 STW-423 Water . July 1985 Gr. alpha 5.010.0 11.0f5.0 2.3-19.7 Gr. beta 5.012.0 8.0i5.0 0.0-16.7 STW-425 Water August 1985 I-131 25.7t3.0 33.016.0 22.6-43.4 STW-416 Water August 1985 H-3 4363183 44801447 3704-5256 STAF-427 Ai- August 1985 Gr. alpha 11.310.6 13.015.0 4.3-21.7 Filter Gr. beta 46.011.0 44.015.0 36.3-52.7 Sr-90 17.7t0.6 18.0fl.5 15.4-20.6 Cs-137 10.310.6 8.015.0 0.0e16.7 STW-429 Water Sept 1985 Sr-89 15.710.6 20.015.0 11.1-28.7 Sr-90 7.010.0 7.011.5 4 -9.6 STW-430 Water Sept 1985 Ra-226 8.210.3 8.911.3 6.6-11.1 Ra-228 4.110.3 4.610.7 3.4-5.8 STW-431 Water Sept 1985 Gr. alpha 4.710.6 8.015.0 0.0-16.7 Gr. beta 4.7 1.2 8.015.0 0.0-16.7 A-6

- _ _ _ _ - _ _ - _ - - . _ = _ _ _ _ _ _ _ = _ _ _ _ _ _ _ - _ _ - _ - _ _ _ - -

Table A-1. (continued)

Concentration in pCi/lb Lab Sample Date TIML Result EPA Resultd Code Type Collected Analysis t20c Is, N=1 Control Limits STW-433 Water Oct'1985 Cr-51 <13 21.0t5.0 12.3-29.7 Co-60 19.310.6 20.015.0 11.3-28.7 Zn-65 19.710.6 19.0*5.0 10.3-27.7 Ru-106 <19 20.015.0 11.3-28.7 Cs-134 17.0il.0 20.015.0 11.3-28.7 Cs-137 ~19.3fl.2 20.0*5.0 11.3-28.7 STW-435 Water. Oct 1985 H-3 1957t50 19741345 1376-2572 STW-436 Water Oct 1985 437 (311nd)

Sample A Gr. alpha 53.011.0 52.0113 29.4-74.6 Ra-226 5.910.1 6.3fl.0 4.1-7.9 Ra-228 8.210.1 10.lil.5 7.5-12.7 Uranium nae 8.0110.4 0.0-18.4 Sample B Gr. beta 85.7f2.5 75.0i5.0 76.3-83.7 Sr-89 21.311.5 27.0i5.0 18.3-35.7 Sr-90 10.310.6 9.0il.5 6.4-11.6 Co-60 18.311.2 18.0i5.0 9.3-26.7 Cs-134 16.311.2 18.0 5.0 9.3-26.7 Cs-137 19.0il.0 18.0i5.0 9.3-26.7 STM-439 Milk Oct 1985 Sr-89 50.310.6 48.015.0 39.3-56.7 l

Sr-90 23.310.6 26.011.5 23.4-28.6 I-131 45.7t3.2 42.016.0 31.6-52.4 Cs-137 60.7f0.6 56.0i5.0 47.3-64.7 K 1547i29 1540i77 1406-1674 STW-441 Water Nov 1985 Gr. alpha 5.3i0.6 10.0i5.0 1.3-18.7 Gr. beta 11.7tl.2 13.0i5.0 4.3-21.7 STW-443 Water Dec 1985 I-131 46.712.1 45.0i6.0 34.6-55.4 STW-444 Water 2ec 1985 Ra-226 6.5i0.1 7.111.1 5.2-9.0 Ra-228 6.li0.1 7.3t1.1 5.4-9.2 STW-445 Water Jan 1986 Sr-89 29.712.5 31.0i5.0 22.3-39.7 Sr-90 13.710.6 15.0il.5 12.4-17.6 STW-446 Water Jan 1986 Gr. alpha 3.010.0 3.015.0 0.0-11.7 Gr. beta 5.310.6 7.Di5.0 0.0-15.7 A-7

-Table A-1. (continued)

Concentration in pCi/lb Lab Sample .Date TIML Result EPA Resultd Code. Type Collected Analysis f20c Is, N=1 Control Limits STF-447 Food- Jan 1986 Sr-89 24.312.5 25.0i5.0 16.3-33.7 Sr-90 17.310.6 10.0il.5 7.4-12.6 I-131 22.712.3 20.0i6.0 9.6-30.4 Cs-137 16.310.6 15.0i5.0 6.3-23.7 K 927146 950t144 701-1199 STW-448- Water Feb 1986 Cr-51 45.0f3.6 38.0i5.0 29.3-46.7 Co-60 19.711.5' 18.Di5.0 9..-26.7 Zn-65 44.0i3.5 40.0i5.0 31.: 448.7 Ru-106 <9.0 0.Di5.0 0.0-8.7 Cs-134 28.3i2.3 3'.0i5.0 0 21.3 38.7 Cs-137 23.7i0.6 22.015.0 13.5-30.7 STW-449 Water Feb 1986 H-3 5176148 5227tS25 4317-6137 STW-450 Water Feb 1986 U total 8.Di0.0 9.016.0 0.0-19.4 STM-451 Milk Feb 1986 I-131 7.0i0.0 9.016.0 0.0-19.4 STW-452 Water March 1986 Ra-226 3.810.1 4.li0.6 3.0-5.2 Ra-228 11.0f0.5 12.4tl.8 9.2-15.5 STW-453 Water March 1986 Gr. alpha 6.7f0.6 15.015.0 6.3-23.7 Gr. beta 7.310.6 8.015.0 0.0-16.7 STW-454 Water April 1986 I-131 7.0f0.0 9.016.0 0.0-19.4 STW-455 Water -April 1986 456 (Blind)

Sample A Gr. alpha 15.0il.0 17.015.0 8.3-25.7 Ra-226 3.110.1 2.910.4 2.1-3.7 Ra-228 1.Si0.2 2.010.3 1.5-2.5 Uranium 4.7f0.6 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 7.0 5.0 0.0-15.7  !

Sr-90 7.010.0 7.0il.5 4.4-9.6 l 10.0 5.0 1.3-18.7 Co-60 10.711.5 Cs-134 4.0il.7 5.Di5.0 0.0-13.7 Cs-137 5.3i0.6 5.0i5.0 0.0-13.7 L

A-8 i 1.

. l Table A-1. (continued)

Concentration in pCi/lb Lab Sample Date TIML Result EPA Resultd Code Type Collec ted Analysis *2ac Is, N=1 Control Limits STAF-457 Air April 1986 Gr. alpha 13.710.6 15.0i5.0 6.3-23.7 Filter Gr. beta 46.310.6 47.015.0 38.3-55.7 Sr-90 14.710.6 18.0il.5 15.4-20.6 Cs-137 10.710.6 10.Di5.0 1.3-18.7 3TU-458 Urine April 1986 Tritium 4313170 44231189 4096-4750 STW-459 Water May 1986 Sr-89 4.310.6 5.015.0 0.0-13.7 Sr-90 5.010.0 5.0il.5 2.4-7.6 STW-460 Water May 1986 Gr. alpha 5.310.6 8.015.0 0.0-16.7 Gr. beta 11.3tl.2 15.015.0 6.3-23.7 STW-461 Water June 1986 Cr-51 <9.0 0.015.0 0.0-8.7 Co-60 66.0il.0 66.015.0 57.3-74.7 Zn-65 87.311.5 86.015.0 77.3-94.7 Ru-106 39.7i2.5 50.015.0 41.3-58.7 Cs-134 49.312.5 49.015.0 40.3-57.7 Cs-137 10.3tl.5 10.015.0 1.3-18.7 STW-462 Water June 1986 Tritium 3427125 31251361 2499-3751 STM-464 Milk June 1986 Sr-89 <1.0 0.0i5.0 0.9-8.7 Sr-90 15.3i0.6 16.011.5 13.4-18.6 I-131 48.312.3 41.016.0 30.6-51.4 Cs-137 43.711.5 31.015.0 22.3-33.7 K 15671114 1600i80 1461-1739 STW-465 Water July 1986 Gr. alpha 4.710.6 6.0i5.0 0.0-14.7 Gr. beta 18.7tl.2 18.015.0 9.3-26.7 STW-467 Water August 1986 I-131 30.310.6 45.016.0 34.4-55.4 STW-468 Water August 1986 Pu-239 11.3i0.6 10.lil.0 8.3-11.9 STW-469 Water August 1986 Uranium 4.010.0 4.016.0 0.0-14.4 STAF-470 Air Sept 1986 Gr. alpha 19.311.5 22.0i5.0 13.3-30.7 I 471 Filter Gr. beta 64.012.6 66.015.0 57.3-74.7 472 Sr-90 22.011.0 22.015.0 19.4-24.6 j Cs-137 25.711.5 22.015.0 13.3-30.7 )

1 STW-473 Water Sept 1986 Ra-226 6.010.1 6.110.9 4.5-7.7 l Ra-228 8.711.1 9.111.4 6.7-11.5 l

l l

A-9 l

I i

Table A-1. (continued).

Concentration in pCi/lb Lab Sample Date TIML Result EPA Resultd Code Type Collected Analysis i2ac Is, N=1 Control Limits STW-474 Water Sept 1986 Gr. alpha 16.313.2 15.015.0 6.3-23.7 Gr. beta 9.011.0 8.015.0 0.0-16.7 STW-475 Water Oct 1986 Cr-51 63.315.5 59.0i5.0 50.3-67.7 Co-60 31.Di2.0 31.0i5.0 22.3-39.7 Zn-65 87.3i5.9 85.015.0 76.3-93.7 Ru-106 74.717.4 74.015.0 65.3-82.7 Cs-134 25.710.6 28.015.0 19.3-36.7 Cs-137 46.311.5 44.015.0 35.3-52.7 STW-476 Cater Oct 1986 H-3 6918160 59731597 4938-7008 SPW-477 Water Oct 1986 478 (Blind)

Sample A Gr. alpha 34.016.0 40.0f5.0 31.3-48.7 Ra-226 5.8i0.2 6.0i0.9 4.4-7.6 Ra-228 2.7tl.0 5.010.8 3.7-6.3 Uranium 11.0f0.0 10.016.0 0.0-20.4 Sample B Gr. beta 38.711.2 51.015.0 42.3-59.7 Sr-89 5.010.0 10.015.0 1.3-18.7 Sr-90 3.010.0 4.011.5 1.4-6.6 Co-60 24.711.2 24.015.0 15.3-32.7 Cs-134 11.012.0 12.015.0 3.3-20.7 Cs-137 9.311.2 8.015.0 0.0-16.7 STM-479 Milk Nov 1986 Sr-89 7.7tl.2 9.015.0 0.3-17.7 Sr-90 1.010.0 0.011.5 0.0-2.6 4 I-131 52.3t3.1 49.016.0 38.6-59.4 Cs-137 45.7i3.1 39.015.0 30.3-47.7 K 14891104 1565t78 1430-1700 STU-480 Urine Nov 1986 H-3 5540126 52571912 4345-6169 i

STW-481 Water Nov 1986 Gr. alpha 12.014.0 20.015.0 11.3-28.7 Gr. beta 20.0t3.5 20.015.0 11.3-28.7 STW-482 Water Dec 198f Ra-226 6.710.2 6.8 1.0 5.0-8.6 l Ra-228 5.210.2 11.111.7 8.2-14.0 l STW-483 Water Jan 1987 Sr-89 19.715.0 25.015.0 16.3-33.7 Sr-90 21.012.0 25.011.5 22.4-27.6 i

1 A-10

I Table A-1. (continued).

I Concentration in pCi/lb l Lab Sample Date TIML Result EPA Resultd i Code Type Collec ted Analysis f2ac 15, N=1 Control Limits STW-484 Water Jan 1987 Pu-239 17.0i2.3 16.7tl.7 13.8-19.6 SIF-486 Food ,lan 1987 Sr-90 36.0i4.0 49.0i10.0 31.7-66.3 i I-131 78.0f3.4 78.0i8.0 64.1-91.9 l Cs-137 89.7t3.0 84.015.0 75.3-92.7 '

K 942iS6 980149 895-1065 STF-487 Food Jan 1987 SR-90 2.Di0.0 ---

l (Blank) 1-131 <3 ---

Cs-137 <2 ---

K 9931102 ---

STW-488 Water Feb 1987 Co-60 49.0i0.0 50.015.0 41.3-58.7 Zn-65 96.0i7.2 91.015.0 82.3-99.7 Ru-106 92.0i20.2 100.015.0 91.3-108.7 Cs-134 53.013.4 59.015.0 50.3-67.7 Cs-137 89.3i4.6 87.015.0 78.3-95.7 STW-489 Water Feb 1987 H-3 4130i140 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 10.0i0.0 9.0i0.9 7.4-10.6 STW-492 Water Mar 1987 Gr. alpha 3.711.2 3.015.0 0.0-11.7 Gr. beta 11.3tl.2 13.015.0 4.3-21.7 STW-493 Water Mar 1987 Ra-226 7.0i0.1 7.311.1 5.4-9.2 Ra-228 7.112.3 7.511.1 5.5-9.5 '

STW-4.'s Water Apr 1987 I-131 8.Di0.0 7.010.7 5.8-8.2 STAF-495 Air Apr 1987 Gr. alpha 15.0t0.0 14.015.0 5.3-22.7 Filter Gr. beta 41.012.0 43.015.0 34.3-51.7 '

Sr-90 16.311.2 17.011.5 14.4-19.6 Cs-137 7.010.0 8.0i5.0 0.0-16.7 STW-496 Water Apr 1987 I 497 (Blind) '

Sample A Gr. alpha 30.711.2 30.0i8.0 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 5.0f0.0 5.016.0 0.0-15.4 A-11

Table A-1. (continued)

Concentration in pCi/lb Lab Sample Date TIML Result EPA Resultd Code Type Collected Analysis t2cc Is, N=1 Control Limits STW-496 Water Apr 1987 497 (Blind)

Sample B Gr. Beta 69.319.4 66.015.0 57.3-74.7 Sr-89 16.313.0 19.015.0 10.3-27.7 Sr-90 10.010.0 10.0tl.5 7.4-12.6 Co-60 8.3t3.0 8.015.0 0.0-16.7 Cs-134 19.012.0 20.015.0 11.3-28.7 Cs-137 14.711.2 15.0i5.0 6.3-23.7 STU-498 Urine Apr 1987 H-3 60171494 5620f795 4647-6593 j STW-499 Water May 1987 Sr-89 38.016.0 41.015.0 32.3-49.7 Sr-90 21.0i2.0 20.0il.5 17.4-22.6 STW-500 Water May 1987 Gr. alpha 9.013.4 11.0i5.0 2.3-19.7 Gr. beta 10.311.2 7.015.0 0.0-15.7 STW-501 Water June 1987 Cr-51 40.018.0 41.0i5.0 32.3-49.7 Co-60 60.313.0 64.0i5. 2 55.3-72.7 Zn-65 11.315.0 10.015.0 1.3-18.7 Ru-106 78.316.4 75.0i5.0 66.3-83.7 Cs-134 36.713.0 40.015.0 31.3-48.7 Cs-137 80.314.2 80.015.0 71.3-88.7 STW-502 Water June 1987 H-3 2906186 28951357 2277-3513 STW-503 Water June 1987 Ra-226 6.9i0.1 7.311.1 5.4-9.2 Ra-228 13.311.0 15.2i2.3 11.2-19.2 STM-504 Milk June 1987 Sr-89 57.014.3 69.015.0 60.3-77.7 Sr-90 32.0il.0 35.011.5 32.4-37.6 l I-131 64.0i2.0 59.0i6.0 48.6-69.4 Cs-137 77.710.6 74.015.0 65.3-82.7 K 1383117 1525176 1393-1657 STW-505 Water July 1987 Gr. alpha 2.310.7 5.015.0 0.0-13.7 j Gr. beta 4.0fl.0 5.015.0 0.0-13.7 l STF-506 Food July 1987 I-131 82.714.6 80.018.0 66.1-93.9 Cs-137 53.713.0 50.015.0 41.3-58.7 K 1548157 1680184 1534-1826 STW-507 Water Aug 1987 I-131 45.714.2 48.016.0 37.6-58.4 STW-508 Water Aug 1987 Pu-239 5.810.2 5.310.5 4.4-6.2 A-12 L________.___

V .

i Table A-1. (continued)

Concentration in pC1/lb L ab Sample Date TIML Result EPA Resultd Code Type Collected Analysis *2ac Is, N=1 Control Limits STW-509 Water Aug 1987 U ranium 13.320.3 13.026.0 2.6-23.4 STAF-510 Air Aug 1987 Gr. alpha 9.720.4 10.0 5.0 1.3-18.7 Filter G r. beta 28.320.6 30.025.0 21.3-38.7 S r-90 10.020.9 10.011.5 7.4-12.6 C s-137 10.021 .0 '10.025.0 1.3-18.7 STW 511 Water Sept 1987 R a-226 9 .9 20 .1 9.711.5 7.2-12.2 R ar228 8 .1 22 .4 6 .3 21 .0 4.6-8.0 L STW-512 Water Sept 1987 G r. alpha 2.020.6 4 .0 25 .0 0.0-12.7 G r. beta 11.311.3 12.0 5.0 3.3-20.7 STW-513 Water Oct 1987 H-3 44732100 4492 2449 3714-5270 STW-514 Water Oct 1987 (Blind)

Sample A G r. alpha 29.322.6 28.017.0 15.9-40.1 R ar226 4 .9 20 .1 4 .8 20 .7 3.6-6.1 R a-228 4 . 2 23 .0 3 ,6 20 .5 2.7-4.5' Uranium 3 .0 20 .1 3.0 6.0 0.0-13.4 Sample B S r-89 14 .3 21 .3 16.025.0 7.3-24.7 S r-90 9.720.4 10.021 .5 7.4-12.6 C o-60 16.723.0 16.025.0 7.3-24.7 C s-134 16.722.3 16 .025 .0 7.3-24.7 C s-137 24 .3 23 .3 24 .0 25 .0 15.3-32.7 STW-516 Water Oct 1987 C r-51 80.3 17.5 70.0 5.0 61.3-78.7 C o-60 16.022.3 15.0 5.0 6.3-23.7 i Z n-65 46.325.6 46.025.0 37.3-54.7 I RLF196 57.3 15.4 61.0 5.0 52.3-69.7 C s-134 23.722.5 25.025.0 16.3-33.7 Cs-137 51.723.2 51.0 5.0 42.3-59.7 STU-517 U rine Nov 1987 H-3 72672100 74321743 6145-8719 i

STW-518 Water Nov 1987 G r. alpha 3 .0 22 .0 7.025.0 0.0-15.7 G r. beta 15.722.1 19.0 5.0 10.3-27.7 STW-519 Water Dec 1987 I-131 26.0 3.0 26.0 6.0 15.6-36.4 A-13

  1. t l- .,,

l '

Table A-1. (continued)!

Concentration in pCi/lb l Lab Sample 'Date TIML Result EPA Resultd Code Type Collected Analysis 22ac I s, N=1 Control Limits-STW-520 Water Dec 1987 R a-226 5 .1 20 .8 4 .8 20 .7 3.6-6.0 R a-228 3 .4 20 .1 5 .3 20 .8 3.9-6.7 STW-521 Water J an 1988 S r-89 27.325.0 . 30.025.0 21.3-38.7 S r-90 15.311 .2 15.021.5 12.4-17.6 STW-523 Water J an 1988 G r. alpha 2 .3 21 .2 4.025.0 0.0-12.7 G r. beta 7.711.2 8.0 5.0 0.0-16.7 STF-524 Food J an 1988 S r-89 44.014.0 46.025.0 37.3-54.7-S r-90 53.022 .0 55.022.8 50.2-59.8 I-131 102.314.2 102.0110.2 84.3-119.7 C s-137 95.726.4 91.025.0 82.3-99.7 K 1010.7 158.5. 1230.0261 .5 1123.5-1336.5 STW-525 Water Feb 1988 C o-60 69.312.3 69.025.0 60.3-77.7 Z n-65 99.013.4 94 .0 29 .4 77.7-110.3 Ru-106 92.7114.4 105.0110.5 86.8-123.2 C s-134 61.718.0- 64 .0 25 .0 55.3-72.7 C s-137 99.713.0 94.0 5.0 85.3-102.7 STW-526 Water Feb 1988 H-3 34531103 33272362 2700-3954 STW-527 Water Feb 1988 U ranium 3 .0 20 .0 3 .0 26 .0 0.0-13.4 STM-538 Milk Feb 1988 I-131 4.7 1.2 4.020.4 3.3-4.7 STW-529 Water Mar 1988 R a-226 ' 7.120.6 7.611.1 5.6-9.6 R a-228 NA8 7.711.2 5.7-9.7 STW-530 Water Mar 1988 G r. alpha 4 .3 21 .2 6 .0 25 .0 0.0-14.7 G r. beta 13.311.3 13.0 5.0 4.3-21.7 STAF-531 Air Mar 1988 Gr. alpha 21.012.0 20.0 5.0 11.3-28.7 Filter G r. beta 48.020.0 50.0 25 .0 41.3-58.7 S r-90 16.711.2 17.011.5 14.4-19.6 C s-137 18.711.3 16.015.0 7.3-24.7 STW-532 Water Apr 1988 I-131 9 .0 22 .0 7.5 0.8 6.2-8.8 l l

A-14 i

, _ i.  !

Table.A-1.. (continued)'

. Concentration in pCi/lb Lab ' Sample- Date .T1HL Result EPA Resultd Code -Type Collected Analysis 22ac Is,-N=1 Control Limits STW-533 Water Apr 1988 534 (Blind)-

Sample A . Gr. alpha NDf ' 46.0111.0 27.0-65.0-Ra-226 ND 6.411.0 4.7-8.1-Ra-228 ND 5.610.8 4.2-7.0 Uranium 6.010.0 6.016.0- 0.0-16.4 Sample B Gr. beta ND . 57.025.0 48.3-65.7 Sr-89 3.311.2 5.015.0 0.0-13.7 Sr 5.311.2 5.021.5 2.4-7.6 Co-60 63.321.3 50.025.0 41.3-58.7 Cs-134 7.711.2 7.025.0 0.0-15.7 Cs-137 8.321.2 7.015.0 0.0-15.7 STU-535 Urine Apr 1988 H-3 6483 155 62021620 5128-7276 STW-536 Water Apr 1988 Sr-89 14.721.3 20.015.0 11.3-28.7 Sr-90 20.012.0 20.011.5 17.4-22.6 STW-538 Water June 1988 Cr-51 331.7t13.0- 302.0 30.0 250.0-354.0 Co-60 16.0 2.0 15.015.0 6.3-23.7 Zn-65 107.7t11.4- 101.0 10.0 83.7-118.3 Ru-106 191.3211.0 195.0120.0 160.4-229.6 Cs-134 18.324.6 20.025.0 11.3-28.7 Cs-137 26.3 1.2 25.015.0 16.3-33.7 STW-539 Water June 1988 H-3 5586192 55652657 4600-6530-STH-541 Milk June 1988 Sr-89 33.7111.4 40.0t5.0 31.3-48.7 Sr-90 55.325.8 60.023.0 54.8-65.2 I-131 103.723.1 94.029.0 78.4-109.6 Cs-137 52.723.1 51.025.0 42.3-59.7 K 1586.7 23.1 1600.0180.0 1461.4-1738.6 STW-542 Water July 1988 Gr. alpha 8.724.2 15.025.0 6.3-23.7 Gr. beta 5.321.2 4.015.0 0.0-12.7 ST F-543 Food July 1988 Sr-89 HD 33.015.0 24.3-41.7 Sr-90 HD 34.022.0 30.5-37.5 I-131 115.025.3 107.0 11.0 88.0-126.0 Cs-137 52.7 6.4 49.015.0 40.3-57.7 K 1190.0166.1 1240.0 62.0 1132.6-1347.4 A-15 1

.. L, e.

i Table A-1. (continued)

']

q Concentration'in pCi/lb l Lab- Sample Date TIML Result EPA Resultd_ i Code Type Collected Analysis 220c Is, fl=1 Control Limits

'STW-544 Water Aug 1988 1-131 80.0i0.0 76.028.0 62.1-89.9 STW-545 Water Aug 1988 Pu-239- 11.020.2 10.221.0 8.5-11.9 l k

STW-546 Water- Aug 1988 Uranium 6.0 0.0' 6.016.0 0.0-16.4 j 1

STAF-547 Air Aug 1988 Gr. alpha 8.020.0 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 8.011.5 5.4-10.6 Cs-137 13.012.0 12.025.0 3.3-20.7 STW-548 Water Sep 1988 Ra-226 9.310.5 8.422.6 6.2-10.6 Ra-228 5.8 0.4 5.4 1.6 4.0-6.8 STW-549 Water Sep 1988 Gr. alpha 7.012.0 8.025.0 0,0-16.7 Gr. beta 11.3 1.2 10.0i5.0 1.3-18.7 STW-550 Water Oct 1988 Cr-51 252.0214.0 251.0125.0 207.7-294.3 Co-60 26.022.0 25.025.0 16.3-33.7 Zn-65 158.3210.2 151.0215.0 125.0-177.0 Ru-106 153.029.2 152.0 15.0 126.0-178.0 Cs-134 28.715.0 25.015.0 16.3-33.7 Cs-137 16.321.2 15.025.0 6.3-23.7 STW-551 Water Oct 1988 H-3 2333.32127.0 2316.01350.0 1709.8-2927.2 STU-555 Urine flov 1988 H-3 3030.0 208.8 3025.02359.0 2403.2-3646.8 STW-556 Water Nov 1988 Gr. alpha 9.013.5 9.015.0 0.3-17.7 Gr. beta 9.711.2 9.025.0 0.3-17.7 a Results obtained by Teledyne Isotopes flidwest Laboratory as a participant in the environmental sample crosscheck program operated by the Intercomparison and Cali-bration Section, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, U. S. Environmental Protection Agency (EPA), Las Vegas, Nevada, b All results are in the pCi/1, except for elemental potassium (K) data in milk, which are in ag/1; air filter samples, which are in pCi/ filter; and food, which is in ag/kg.

c Unless otherwise indicated, the TIf1L results are given as the mean 2 standard deviations for three determinations.

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

e f1A = flot analyzed.

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

A-16

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nbtt nsthNe enS o nl eant ,mUn i mk sd eamxel n t nr i emenemak oein aoo rnnHoT nerrht od i rY aio r oHoit cre vi parcif r Y v evw mtii voic n yt d ne ob vl n viwEb ons EN conbE ynl e d r E u tEbNfdP rf ,

es ttf Pfi osfP u ,oe d

aok r nl of ro ynoa rl nno i u one f rost nd 1 2 ) 1 2 ) 1 2 aoY sn ovnoos nnon t 7 7 7 t s eeol si o ti oesa n e e 3 e e 3 e e 3 siw h rsoinsl arpmi e i t t 1 t t 1 t t 1 re t i orUiorasnr roop m n i i - i i - i i - 2 aN f rh a e o S S s S S s S S s 1 p f oacpeahb md r pr

_ r s C C C m ,

o pS mh pcaonimo u i d d ( d d ( d d ( no) sm ot m SL c a v oY rnoec o r

_ s r l l l l l l acL a a e e b e e b e e b erS ooch rf cese mea

_ e p i i a i i a i i a sirt eorhtt a M tG nt e m F F L F F L F F L t et nnd en(

_ o oatd nht pi nnI t nym eI a

v c hI ,

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_ n I y oat d noo nraist o n D ,d roti i s M cooet a i 0 nir

_ t l 0 M  : et o eaiati a gd t e

_ n a 1 s  : s 4s vab nndt ral t n n e n o e n p 2b Od i naoinaonb aol rV an grLt manb runpae C Dp o Fi Fl S r

_ ( L y i ih au aa e srt raeP rstt s ,ea TT t LC CB CC tt yueseLt e nnant a l nt ot t nftd eI L on6

_ . n uI eH e s

nl I onnm I anht s

_ 2 r f ,d 12I anhl

_ - e ed a ot ash

_ A t rnS se d ot oh orn

_ n A B C o t unrirothi e4 mh5 e I 8 8 8 b cd xl ait uhf avv8 m g8

_ l e - - - aeneaeh aocidne9oi9 b bd h 5 5 5 LS aTVMTNFSFI ES1CE1

_ a ao t 1 1 1 h

_ T LC 8 1 1 1 ab cd e f 9

- 3h

- 11!l l

7 4 ,. _

l 6

l

. Table A-3. In-house spiked samples.

l- Concentration in pCi/1 Lab. Sample Date TIMi. 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 14.2tl.7 12.9f2.0 5.2 I-131 34.2i3.8 35.2t3.5' 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 1.6t0.4 1.6fl.0 7.1 Sr-90 2.4i0.2 2.412.0 4.2 QC-W-15 Water Apr. 1986 I-131 44.9i2.4 41.517.0 10.6 Co-60 10.6tl.7 12.115.0 7.lb Cs-134 30.212.4 25.8i8.0 7.lb Cs-137 21.9tl.9 19.9i5.0 7.lb QC-MI-7 Milk Apr. 1986 I-131 39.7*3.3 41.Si7.0 10.4 Cs-134 28.7t?.8 25.8i8.0 8.7 Cs-137 21.2i2.8 19.915.0 8.7 SPW-1 Water May 1986 Gross alpha 15.811.8 18.015.0 Sc

.QC-W-16 Water . June 1986 Gross alpha 16.2i0.7 16.912.5 8.7 Gross beta 38.413.5 30.2t5.0 8.7 QC-MI-9 Milk June 1986 Sr-89 <1.0 0.0 7.lb Sr-90 12.6fl.8 13.3i3.0 4.2b q I-131 38.9t7.0 34.8i7.0 10.4 i Cs-134 33.0i3.4 36.115.0 8.7 Cs-137 38.Si2.8 39.015.0' 8.7 SPW-2 Water June 1986 Gross alpha' 16.811.8 18.015.0 Sc SPW-3 Water June 1986 Gross alpha 17.7f0.8 18.015.0 Sc j QC-W-18 Water Sep. 1986 Cs-134 34.715.6 31.315.0 8.7 Cs-137 51.117.0 43.318.0 8.7 QC-W-19 Water Sep. 1986 Sr-89 13.6*4.1 15.6f3.5 7.lb  ;

Sr-90 6.411.6 6.212.0 4.2b A-20 l

s

-s.

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

Concentration in pCi/1 Lab Sample Date TIML Result Known Expec ted Code Type- Collected Analysis .n=3 Activity - Precision 1s, n=3a QC-W-21 Water Oct. 1986 Co-60 19.2*2.2 18.513.0 8.7 Cs-134 31.715.2 25.6i8.0 8.7 Cs-137 23.811.0 21.6i5.0 8.7 QC-MI-11 Milk Oct 1986 Sr-89 12.311.8 14.3i3.0 8.7 QC-W-20 Water Nov . 1986 H-3 3855f180 3960i350 520b QC-W-22 Water Dec. 1986 Gross ' alpha 9. 811.4 11.214.0 8.7 Gross beta 21.7f2.0 23.815.0 8.7 QC-W-23 Water Jan. 1987 I-131 29.812.5 27 913.0 10.4 QC-MI-12 Milk Jan. 1987 I-131 36.5fl.3 32.615.0 10.4 Cs-137 32.614.2 27.418.0 8.7 SPM-13 Milk Jan 1987 Sr-89 10.4f2.1 12.214.0 8.7 Sr-90 14.6tl.6 12.613.0 5.2 I-131 49.511.2 54.918.0 10.4

.Cs-134 <1.6 0.0 8.7 Cs-137- 33.310.6 27.418.0 8.7 SPW-24 Water Mar 1987 Sr-89 24.7i3.6 25.915.0 8.7 Sr-90 23.913.8 22.818.0 5.2 SPW-25 Water Apr 1987 I-131 28.Dil.9 29.315.0 10.6 SPM-14 Milk Apr 1987 I-131 25.012.2 23.9i5.0 10.4 Cs-134 <2.1 0.0 8.7 Cs-137 34.212.0 27.217.0 8.7 SPW-26 Water Jun 1987 H-3 34221100 3362i300 520 Co-60 24.8tl.4 26.5i7.0 8.7 Cs-134 <2.0 0.0 8.7 Cs-137 11.210.5 21.617.0 8.7 l

SPW-27 Water Jun 1987 Gr. alpha 8.Sil.9 10.114.0 8.7 Gr. beta 22.611.9 21.215.0 8.7 SPW-28 Water Jun 1987 Gr. alpha 8.711.3 10.114.0 8.7 Gr. beta 12.215.2 9.4i3.0 8.7 l

A-21

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

Concentration in pC1/1 Lab Sampl e Date TIML Result K nown Expected Code Type Collected Analysis n=3 Activity P recision 1 s , n=3 a SPW-29 Water Jun 1987 Gr. alpha 16.411.3 18.925.0 8.7 G r. beta 15.914.0 11.824.0 8.7 SPM-15 Milk J ul 1987 S r-89 19.411.6 18.813.5 5.2 1-131 43.520.7 45.317.0 10.4 C s-134 17.9 2.2 16.025.3 8.7 C s-137 25.411.8 22.715.0 8.7 SPW-30 Water Sep 1987 Sn 89 17.513.0 14.325.0 8.7 S r-90 18.422.2 17.512.2 5.2 SPW-31 Water Oct 1987 H-3 20531939 20591306 520 SPW-32 Water Dec 1987 G r. alpha 8.611.0 10.125.0 8.7 G r. beta 15.220.1 13.113.0 8.7 SPW-33 Water Dec 1987 G r. alpha 7.711.4 10.1.*5.0 8.7 Gr. beta 10.911.0 7.913.0 8.7 SPW-34 Water' Dec 1987 G r. alpha 4.020.9 5.113.0 8.7 i Gr. beta 9.420.9 7.913.0 8.7 SPM-16 Milk J an 1988 S r-89 31.726.0 31.8 t4.7 8.7 S r-90 27.8 3.5 25.512.7 8.7 I-131 23.215.0 26.420.5 10.4 C s-134 24.226.0 23.812.3 8.7 C s-137 25.1 6.0 26.520.8 8.7 SPM-17 Milk Feb 1988 I-131 10.611.2 14.311.6 10.4 SPW-35 Water Feb 1988 I-131 9.7 1.1 11.6 1.1 10.4 1

SPW-36 Water Feb 1988 I-131 10.5 1.3 11.611.0 10.4 SPW-37 Water Mar 1988 S r-89 19.8 8.0 17.1 2.0 8.7 S r-90 17.3 5.0 18.720.9 5.2 j i

Milk Apr 1988 SPM-18 I-131 26.715.0 33.2 2.3 10.4 Cs-134 30.2 5.0 31.3 2.1 8.7 C s-137 26.215.0 29.911.4 8.7 3 A-22

_ _ - _ _ - _ _ _ - _ _ _ _ _ - _ - - _ _ _ - - - - - _ - - - - _ _ - - - _ - _ - - _ - _ _ = . - - - - - - - - - - - - - - - - - - E

R

~

v ,n

. c. . ,  ;

.l 1

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

. U l

?

Concentration in pC1/l' Lab ~ Sample Date ~ TIML Result Known Expected  ;

l Code Type Collected Analysis n=3 ' Activity Precision j 1 s , n =3 a .

SPW-38 Water Apr 1988 I-131 14.225.0 17.121.1 10.4 SPW-39 Water Apr 1988 H-3 41761500 '4439231 724' SPW-40 Water Apr 1988 Co-60 26.114.0 23.720.5 8.7 'j Cs-134 29.224.5' 25.412.6 8.7 Cs-137 26.214.0 26.6t2.3 8.7 l

-f SPW-41 Water Jun 1988 Gr. alpha 13.115.0 12.310.4 8.7 3 Gr. beta 20.115.0 22.611.0 8.7 l s

SPS-42 Milk Jul 1988 Sr-89 15.111.6 16.425.0 8.7 -)

Sr-90 18.020.6 18.315.0 8.7 I-131 88.4 4.9 86.618.0 10.4  ;

Cs-137 22.7 0.8 20.816.0 51 . 7 1 i

SPW-43 Water. Sep 1988 Sr-89 40.523.3 50.8i8.0 8.7  !

Sr-90 10.921.0 11.413.5 5.2 i SPW-44 Water -Oct 1988 Co-60 20.9 3.2 21.423.5 8.7 1 Cs-134 38.721.6 38.016.0 8.7 J Cs-137 19.012.4 21.023.5 8.7 j SPW-45 Water Oct 1988 I-131 22.220.6 23.323.5 10.4 SPW-46 Water Oct 1988 H-3 4109243 41531500 724.

SPS-46 flilk Oct 1988 1-131 59.8 0.9 60.619.0 10.4 4 Cs-134 49.621.8 48.6 7.5 8.7 Cs-137 25.824.6 24.7t4.0 8.7 i SPV 47 Water Dec 1988 Gr. alpha 11.522.3 15.225.0 8.7 Gr. beta 26.5 2.0 25.725.0 8.7 a n=3 unless noted otherwise.

b n=2.

c n=1.

4 A-23

L .

i 9 Table A-4. In-house " blank" samples.

Concentration in pCi/1 Acceptance Lab Sample Date Results Criteria Code Type Collected Analysis (4.66o) (4.660) 8L D.I. Water Nov. 1985 Gross alpha <0.1 <1 Gross beta <0.4 <4

.BL-2 0.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-?26 <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-8 D.I. Water June 1986 Gross alpha <0.4 <1 BL-9 0.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 D.I. Water Feb 1987 H-3 <180 <300 Gross beta <2.6 <4 SPS-3555 Milk i-eb 1987 Sr-89 <0.6 <5 Sr-90 1.910.4a <1 SPS-3731 Milk Mar 1987 Cs-134 <2.2 <10 .

Cs-137 <2.5 <10 j l

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

I l

1 A-24

J J

Table A-4. In-house " blank" samples (continued).

Concentration -in pCi/l Acceptance l Lab Sample Date Results Criteria I Code Type Collected Analysis (4.66o) (4.66a ) j l

l SPS-3732 D.I. Water Mar 1987 Sr-89 <0.9 <5 i Sr-90 <0.8 <1 j I-131 <0.3 <1 I Co-60 <2.3 <10 l Cs-134 (gama) <2.2 <10 Cs-137 (gamma) <2.4 <10 Ra-226 <0.1 <1 Ra-228 <1.0 <1 Np-237 <0.04 <1 Th-230 <0.05 <0.1 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 2.410.6a <1 SPS-4390 Milk Jun 1987 Cs-134 <4.7 <10 Cs-137 <5.2 <10 SPS-4391 D.I. Water Jun 1987 Sr-89 <0.4 <5 Sr-90 <0.4 <1 I-121 <0.1 <1 l Co-60 <3.8 <10 l 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 i Gross beta <1.4 <4 l Tritium <150 SPS-4628 Milk Aug 1987 Sr-89 <0.6 <5 Sr-90 2.410.6a <1 SPS-4847 Milk Sep 1987 Cs-134 <4.4 <10 Cs-137 <5.3 <10 a Low level (1 - 4 pCi/l) of Sr-90 concentration in milk is not unusual.

A-25 l

I-Data Reporting Conventions i

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 mea'surement is reported as follows:

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

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

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

3.0. Duplicate Analyses 3.1. Individual results: x1 i s1 x2

  • 52 Reported result: xis where x = (1/2)'(x1 + x2) s=(1/2) s 2+sf 3.2. Individual results: <L1

<L2 Reported retult: <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

- __ - _ _ _ _ _ - _ _ -____--__ -__ _ -_ _- - ___ _ -- _ __-_----- - ---__-_. - - - _-_ -_-_--_ -_--- _----- - ----- - A

l l

  • 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 x and standard deviation (s) of a set of n numbers x1, x2 Xn are defined as follows:

x= hex s= E (*~ )2 n-1 4.2 Values below the highest lower limit of detection are not included in the average.

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

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

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

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

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

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

increased by one if it is an odd number or it is kept unchanged if an even number. As an example, 11.435 is rounded off to 11.44, while 11.425 is rounded off to 11.42.

B-3

Table A-4. In-house " blank" samples . (continued).

' Concentration in pC1/1 Acceptance Lab Sample Date. :Results Criteri a '

Code Type . Collect ed . Analysis (4.66 -)- '(4.66^f)

SPS-5615 -Milk' Mar 1988 Cs-134 <2.4 -<10 Cs-137 <2.5 <10 1-131 <0.3' . <1 ,

Sr-89 <0.4- <5 Sr-90 2.410.5a <1 l SPS-5650 D.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 Am-241 <0.06 <1 Cm-242 '0.01

< . <1 D Pu-238 <0.08 <1 Pu-240 <0.02 <1 SPS-6090 flil k Jul 1988 Sr-89 <0.5 <1 a

.Sr-90 1.810.5 <3 l

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 l

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

A-27 L _ _ _ - . . . _ _ -- -- - - _ - - - - - - - - - - - - - _ - _ _ - - . _ _ _ - _ - _ _ - - - - - _ - _ - - - - - - -__

~

l TIML-BLIND-01 Ravision 0, 12-29-86 ATTACHMENT 8 ACCEPTANCE CRITERIA FOR " SPIKED" SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSESa One Standard Deviation

p. Analysis Level for Single Determination l

i Gamma Emitters 5 to 100 pCi/ liter or kg 5 pCi/ liter

>100 oCi/ liter or 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 pCi/ liter

>30 pCi/ liter of kg 10% of known value Potassium >0.1 g/ liter or kg 5% of known value Gross Alpha <20 pCi/ liter 5 pCi/ liter

>20 pCi/ liter 25% of known value Gross Beta <100 pCi/li,er 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 value 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 i Nickel-63D, >35 pCi/ liter 15% of known value Technetium-99b Iron-55b 50 to 100 pC1/ liter 10 pC1/ liter 10% of known value ,

a From EPA publication, " Environmental Radioactivity Laboratory Intercompari-b s n Studies Program, Fiscal Year 1981-1982, EPA-600/4-81-004.

TIML limit.

i A-28

E, ,-.

+

n ' Table A-4. In-house " blank" samples (continued). j Concentration in pC1/1 Acceptance Lab. ~

Sample Date Results C riteria '

C ode - Type Collected Analysis (4.66 a ) (4.66 a )

I

> SPS-4848 D.I . Water S ep- 1987 - I-131 <0 .2 <1 i SPW-4849 D.I. Water Sep 1987 C o-60 <4 .1 <10 C s-134 <4 .8 <10 -

C s-137 (4.0 (10 '

S r-89 <0 .7 <5 S r-90 <0 .7 <1 SPW-4850 D.I. Water Sep 1987 Th-228 <0.04 <1 T h-232 (0.8 <1 U-234 <0.03 <1 U-235 <0.03 <1 U-238 <0 .02 <1 AnF241 <0.06 <1 Cnw242 <0.04 <1 R a-226 <0 .1 <1 R a-228 <1.0 <2 SPW-4859 D.I. Water Oct 1987 F e-55 <0.5 <1 SPS-5348 Milk Dec 1987 C s-134 <2 .3 <10 C s-137 <2 .5 <10 '

SPW-5384 D.I. Water Dec 1987 C o-60 <2 .8 <10 C s-134 <2 .6 (10 C s-137 <2.8 <10 1-131 <0 .2 <1 R a-226 <0.1 <1 R a-228 <1.2 <2 S r-89 <0 .5 <1 S rw90 <0 .4 <1 SPW-5385 D.I. Water Nov 1987 Gr. alpha <0 .4 <1 Gr. beta <2 .2 <4 F e-55 <0 .3 <1 SPS-5386 Milk J an 1988 I-131 <0 .1 <1 SPW-5448 1)ead" W ater J an 1988 H-3 <177 <300 A-26

_ = _ _ - - _ _ _ _ _ - - _ - _ _ - _ - _ _ _ _ _ -

ADDENDUM TO APPENDIX A l

l The following is an explanation of the reasons why certain samples were outside the I

control limit specified by the Environmental Protection Agency for the Interlabora-

' tory Comparison Program starting January 1987.

EPA Lab Code Analysis TIML Result Control Limit Explanation STit-504 Sr-89 - 57.024.3 60.3-77.7 Milk had high fat content which Sr-90 32.011.0 32.4-37.6 made analyses difficult. Ad-dition of errors to TIML result would put values within EPA control limits. EPA also hed the same problem in analyzing its own sample.

STW-511 Ra-228 8.121.4 4.6-8.0 TIML results are usually within EPA control limits. Analysis of the next sample was within '

EPA control limits. No further action is planned.

STW-516 Cr-51 is.3217.5 61.3-78.7 Results in the past have been within EPA control limits and TIML will monitor the situation in the future.

ST F-524 K 1010.72158.5 1123.5-1336.5 Error in transferrance of data.

Correct data was 1105233.

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

STW-532 I-131 9.012.0 6.2-8.8 Sample recounted after 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 j continue to monitor the situ-ation in the future.

STW-534 Co-60 63.3 1.3 41.3-58.7 High level of Co-60 was due to contamination of beaker.

Beaker was discarded upon dis-c ove ry of cont ami nation and sample was recounted. Recount results were 53.223.6 and 50.922.4.

i l

A-29

=

Appendix B Data Reporting Conventions I

\

)

k i

B-1 i

.4

,,f.:

L Appendix C Maximum Permissible Concentrations of Radica'ctivity in Air and Water-Above Background in Unrestricted Areas

'i 1

l 1

4 1

1 I

C-1

T Table C-1. Maximum pennissible concentrations of radioactiv'ty in air and water above natural background in unrestrictcJ 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 pCi/m3 Cesium-137 20,000 pC1/1 Barium-140 20,000 pC1/1 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 pCi/1 a

Taken from 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 radionuclides.

l l

l C-2

1 TRANSMITTAL MANIFEST.

NORTHERN STATES: POWER COMPANY i NUCLEAR GENERATION DEPARTMENT. ,

PRAIRIE ISLAND NUCLEAR GENERATING PLANT 1988 Annual Radiological Environmental Monitorina Reoort Manifest Date: April 12, 1989 USNRC 3 DCD Regional Admin - III Resident Inspector L R Eliason 1 P H Kamman 1 ,

Monticello Plant Manager 2 Prairie Island Plant Manager 1 ERAD' Dept. _

1 Attn: Records Clerk Media Services 1 NSP (Wisconsin) 6 NRS File 1 NSS' File 1 MDH~ 1 Attn: Commissioner of Health MPCA 1 Attn: J W Ferman ANI Library 1 Shaw Pittman Potts & Trowbridge 1 G Charnoff Safety Audit Committee 9 D M Musolf K J Albrecht C W Giesler D E Gilberts F W Hartley '

H S Isbin J A Thie T P Tierney E L Watzl File-(Manifest Only)

O

- - - - _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ . _ - _ _ . . - - - - . _ . - - - . - . - . _ - - __ .__ _ _ _ _ _ . - - - - _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _