ML20202H622

Radioactive Effluent Rept & Radiological Environmental Monitoring Rept from 970101-970131

ML20202H622
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	12/31/1997
From:	Berg W DAIRYLAND POWER COOPERATIVE
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LAC-13626, NUDOCS 9802200427
Download: ML20202H622 (40)

Text

_ _ . . . _ . _ . _ _ _ . -

1

p }DAMYLAND hh/M[ COOPERATlVE e 3200 EAST AVE.SO.

• PO. BOX 817

• LA (608) 788 4000

, FAX NO. (608) 7871420 EnI.Yu'an".$r Februmy 12,1998

}

i in reply, please .

refer to LAC 13626 DOCKET NO. 50-409 Document Control Desk i U. S. Nuclear Regulatory Commission 1 l Washington, DC 20555

SUBJECT:

Dairyland Power Cooperative j La Crosse Boiling Water Reactor i

Possession Only License No. DPR-45 j Annual Radioactive Efiluent Report arid Radinlogical Environmental Monitoring Repr11

REFERENCES:

(1) NRC Letter, Keppler to Linder, dated August 12,1983, 4

Inspection Report 50-409/83 10 (DRMSP)

(2) LACBWR Technical Specifications 6.6.4.2,6.8.1.1.c & d In accordance with 10 CFR 50.36a(a)(2), this letter serves to transmit to you the Radioactive Efiluent Report and Radiological Environmental Monitoring Report for the La Crosse Boiling Water Reactor (LACBWR) for 1997.

i If you have any questions, please contact us.

- Sincerely, DAIRYLAND POWER COOPERATIVE R

ADO K O 409 [g) (

PDR

' , ,3 William L. Berg, General h anager WLB:LLN:dh ' ' ' *d 8 b

Enclosures

[ j cc/ enc: David Nelson, NRC Region 111 Paul W. Ilarris, NRC Project Manager D. Sherman, ANI Library Don llendrikse, Wisc. Div. ofIlealth lll ll ll llllllll ll

1

.O RADIOACTIVE EFFLUENT REPORT AND  ;

RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT FOR TliE LA CROSSE BOILING WATER REACTOR (LACBWR)

(January I to December 31,1997)

DAIRYl.AND POWER COOPERATIVE 3200 EAST AVENUE SOUTil LA CROSSE, WI 54602 0817 k

TAllLE OF CONTENTS i

O SECTION At RADIOACTIVE EFFLUENT REPORT Section litic bgc Introduction 1 1.0 Regulatory Limits 2 2.0 Efiluent Release Concentration Limit 4 3.0 Average Energy 4 4.0 Analytical Methods 4 5.0 Datch Releases 6 6.0 Abnormal Releases 7 7.0 Estimated Total Analytical Error 7 8.0 Offsite Dose Calculation Summary and Conclusions 13 SECTION B: RADIOLOGICAL, ENVIRONMENTAL MONITORING REPORT Section Iitic bgc Introduction 1 1.0 Sample Collection 2 2.0 Results of the 1997 Radio Environmental Monitoring Survey 2 3.0 Conclusions 5 4,0 Interlaboratory Comparison Program Results 5 O

i

TAllLE OF CONTENTS O TABLES SECTION At RADIOACTIVE EFFLUENT REPORT Table No. Iide hgg 1A Efiluent and Waste Disposal - Gascous Efiluents 8 Summation of All Releases 1B Efiluent and Waste Disposal Gaseous Efiluents 9 Elevated Release 2A Efiluent and Waste Disposal - Liquid Ellluents 10 Summation of All Releases 2B Elliuent and Waste Disposal- Liquid Efiluents 11 3 Solid Waste and Irradiated Fuel Shipments 12 s SECTION H: RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT Table No. Ijde Eage 5 Sample Frequency and Analysis of Radio-Environmental 10 Samples 6 Permanent Em'ironmental Monitoring Station Locations 11 7 Emironmental TLD Locations 12 8 Radio-Emironmental Samples Collected 13 January-December 1991 9 Quarterly Thermoluminescent Dosimeter Dose Measurements 14 in the LACBWR Vicinity 10 Weekly Gross Beta Air Particulates in the LACBWR Vicinity 15 11 Air Particulate Composite Results 19 12 Results of Analysis of Mississippi River Water in the Vicinity of 25 LACBWR O

il

TAllLE 05 CONTENTS O r^ ='es - (ce#i d>

SECTION H: RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT Table No. 1i00 DE 13 Results of Analysis of Mississippi River Sediment in the 31 Vicinity of LACBWR 14 Results of Analysis of Milk Samples in the Vicinity of 32 LACBWR 15 Fish Sample Activity in the Vicinity of LACBWR 33 16 Vegetation Sample Activity in the Vicinity of LACBWR 35 FIGURES O

Nct Iitic bu FIGURE 1 LACBWR Property Map 6 FIGURE 2 Permanent Environmental Monitoring Station Locations 7 FIGURE 3 'LACBWR Environmental Dose Assessment Locations 8 FIGURE 4 LACBWR Environmental Dose Assessment Locations 9 O

v

O SECTION A RADIOACTIVE EFFLUENT REPORT O

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O l IN1RODUC110N:

i The La Crosse Holling Water Reactor (IACBWd), also known as Genoa Station No. 2. is locatedon the east bank of the Mississippi Riwr near Germa, Vernon County, Wisconsin. The plant was designed arulconstructed by the Allis-ChalmersManufacturing Company. It uns completed in 1967 arulhad a generation capacity of 30 MW (163 MW m ). The reactor is owned by DalrylarulPower Ccwperattw (DPC).

The reactor went criticalin July 1967 aruffirst contributed electricity to DPC's ystem in April 1968. After completingfullpower tests in August 1969, the plant operated between 60%

O ana ivousu wah the e-a~ni-a n +wn >< ~~~e ar+a*

In April of1987 plant operation was ceased. The reactor ispresenth* defueled arulin a SAFS10R mode. In August of1987 apossession-ordy license was recclwd.

In accordance with IACBWR Technical Specifications 6.3.1.1.d and in compliar:e with .

10 CFR 30,36a(a)(2), this document is the Radioactiw Effluent Reportfor the periodJanuary I through December 31,1997.

O

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!O EFFI,UENT AND WASTE DISPOSAI, REPORT (SupplementalInformation)

FACILITY: La Crosse _ Boiling WatstEcAgtpL LICENSEE: pairvland Power _ Cooperative 4 DOCKET NO. 50-409 i

1.0 REGJLATORY LIMlIS >

l l

a. Gaseous Emuent Release Litnits:

l: LACBWR's stack emuent release limitations for gaseous emuent releasea of i radioactive material limits the release rate of the sum of the individual radionuclides, so s

that the dose rates to members of the public beyond the Emuent Release Boundary do not

]

1 exceed 500 mrenVycar to the whole body,3000 mrenVyear to the skin from noble gases, i

} and 1500 mrenVycar to a critical organ from H 3 and particulates with half lives greater than 8 days as per the requirements of the OITsite Dose Calculation Manual (ODCM).

4 i Also, in accordance with 10 CFR 50, Appendix 1, the ODCM limitations for i

gaseous emuent radioactive material limit the air dose to a member of the public from noble gases in areas beyond the Emuent Release Boundary to less than 5 mrad gamma and

! 10 mrad beta per calendar quaner, and less than 10 mrad gamma and 20 mrad beta per calendar year. The dose limits from H.3 and particulates with half lives greater than 8 days are less than 7.5 mrem per calendar quarter, and less than 15 mrem per calendar

, year to any organ. 1 Cumulative dose contributions from gaseous emuent releases are determined in accordance with the LACBWR Offsite Dose Calculations Manual.

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EFFLUENT AND WASTE DISPOSAL REPORT -(cont'd)  !

a O '

b. LiquidffRutDLRelease Limits:

LACBWR's liquid emuent release limitations for liquid emuent releases are those concentrations specified in 10 CFR 20 Appendix H Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration is limited to a total activity concentration of 6 E-4 pCl/ml, For alpha emitting radionuclides, the concentration is limited to a total actkity concentration of 4.9 E 9 pCi/ml, based upon an actual alpha emitting radionuclide analysis performed on a representative water sample, The values reported in tables 2A and 2B, Liquid Emuents, are based on dilution with the combination of LACBWR and Genoa Statbn No. 3 condenser cooling water flow prior to discharge to the Mississippi River. No credit is taken for further dilution in the mixing zone of the Mississippi River.

O ^ise. ia accerda#ce -iih io cra so. ^rneedix i. the dose commiimeet to a member of the public from radioactive materials released in liquid emuents to areas beyond the Emuent Release Boundary are limited to less than 1.5 mrem whole body and 5.0 mrem organ dose per calendar quarter, and less than 3.0 mrem whole body and 10 mrem organ dose per calendar year via the crikal ingestion pathway, Cumulative quarterly and annual dose contributions from liquid emuent releases are determined for the adult fish ingestion pathway in accordance with the LACBWR Offsite Dose Calculation Manual.

l i

O

EFFLUENT AND WASTE DISPOSAL REPORT -(cont'd) i O

! c. Solidhdioactive Wasic All solid radioactive wastes are handled in accordance with a Process Control

\

Program as defined by LACBWR procedures in order to assure that all applicable transportation and burial site disposal requirements are met.

2.0 EFFLUENT RELEASE CONCENTRATION LIMIT l

! The Efiluent Release Concentration used to calculate permissible release rates are obtained from 10 CFR 20, Appendix B, Table 2, Columns 1 and 2. In addition, the following values are used:

Tritium in Water = 1 E.3 pCi/ml.

! Tritiumin Air = 1 E.7 pCi/cc.

!O 3.0 AVERAGE ENERGY The release rate limits for LACBWR are not based on average energy.

l 3

4.0 ANALYTICAL METl[QQS

a. Liquid Efiluents Liquid effluent measurements for gross radioactivity are performed by 11PGe 4

gamma isotopic analysis of a representative sample from each tank discharged. In addition, each batch discharged tank is analyzed for alpha and tritium activity concentration. A composite sample is created by collecting representative aliquots from each tank batch discharged and is analyzed quarterly for Iron 55 and Strontium 90 by a contractor, ,

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EFFLUENT AND WASTE DISPOSAL REPORT -(cont'd) n U

b. Ahborne Particulates Airborne particulate releases are determined by HPGe gamma isotopic analysis.

This analysis is performed by analyzing a glass fiber filter paper taken from the stack monitor which continuously isokinetically san.'ples and monitors the stack efiluent. This filter is changed and analyzed on an approximate weekly basis and analyzed within 7 days aller removal. This filter is also analyzed for alpha activity. A quarterly composite of these fil:ars is sent to a contractor for Sr 90 analysis.

c. Radiolodines Since the plant shutdown in April 1987, the 1 131/I-133 have decayed completely j to stable (lements. Amendmant 66 to the LACBWR Technical Specifications, deleted the requirement for monitoring for iodine.

d. Fission and Activation Gases The concentration of radioactivity (pCi/cc) in gaseous releases from the stack is continuously monitored by two stack monitors, which are in-line monitors. These gas concentrations (pCi/cc) are corrected for pressure loss in the sampling system and averaged by the monitors microprocessor. The results are used along with the stack flow rate to obtain the daily gaseous release from the plant. Since the plant shutdown in April 1987, gaseous releases have been immeasurable. All fission gases except Kr-85 have decayed completely to stable elements.

EFFLUENT AND WASTE DISPOSAL REPORT -(cont'd)

O

c. ~hilium Tritium releases are determined by taking a grab sample of the stack atmosphere at the eilluent of the stack monitor. Tritium, as tritiated water, is removed from the sample stream by condensation, using a cold trap. The condensed water vapor is then distilled and the distillate is analyzed for 113 concentration, pCi/ce, by internal liquid scintillation spectrophotometry and the results are expressed in terms of tritium release rates. The tritium grab samples are obtained on at least a once/ month basis unless the upper reactor cavity is flooded, at which time the sampling frequency is increased to at least once per 7 days.

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5.0 BATCil RELEASES

a. Al+orne O ^:i eirbe,ne eiiieent reieeses at L^CBwR are from a siesie Coetineees Eieveted Release Point,

b. Liauld All liquid ellluent releases at LACBWR are batch releases. This is summarized as follows:

(1) Number of Batch Releases: 32 (2) Total Time Period for Batch Releases: 224.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> (3) hiaximum Time Period for a Batch Release: 16.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> (4) Average Time Period for a Batch Release: 7.03 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> (5) hiinimum Time Period for a Batch Release: 0.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> (6) Average Stream Flow Rate During Periods of Release of Efiluait into a Flowing Stream: 94,700 fP/sec

.~ .

EFFLUENT AND WASTE DISPOSAL REPORT . (cont'd)

O 6.0 ABNORMAL RELEASES There were no abnormat releases of radioactivity in plant effluents as summarized as follows:

a. Liquid l

(1) Number of Releases: None (2) Total Activity Released: N/A

b. GAatous l

(1) Number ofReleasos: None (2) Total Activity Released: N/A

)

1 7.0 ESTIMATED TOTAL ANALYTICAL ERROR O The reported analytical results contain the following estimated errors:

Counting Error i 1 Standard Deviation Sampling Volume Error

• 5%.

The lower limits of detection (LLD) are expressed in terms of a 4.66 c.-

O 7

_ _ _ _ ._ _ _ _ _ . - - . .. - _ _ _ _ ___ _ _ . - . _ ._. . _ ~.- . _ _ _ __

EFFLUENT AND WASTE DISPOSAL REPORT -(cont'd)

TAHLElA EFFLilENT AND WASTE DISPOSAL ANNtlAL REPORT 1997 GASEOtfS EFFLliENTS - St1MMATION OF ALL RELEASES E

I UNIT QTR QTR QTR QTR TOTAL A. FISSION & ACTIVATION GASES 1 l

1. TOTAL RELEASE Ci 0.00E400 0.00E+00 0.00E+00 0.00E+00 0.00E400 i

2. AVERAGE RELEASE RATE FOR pCi/ 0.00E+00 0.00E400 0.00E400 0.00E+00 PERIOD Sec B. IODINE I 131 - No longer analyzed for.

C. PARTICULATES

1. PARTICULATES WITil C1 2.70E 7 6.50E 7 7.28E 7 5.34E 7 2.18E-6 IIALF LIVES > 8 DAYS

2. AVERAGE RELEASE RATE FOR pCi/ 3.48E 8 8.27E 8 9.16E.8 6.72E-8 PERIOD Sec

3. GROSS ALPilA RADIOACTIVITY Ci 0.00E+00 8.00E 7 0.00E+00 0.00E+00 8.OnE 7 D. TRITIUM

1. TOTAL RELEASE Ci 2.24E 2 1.97E 2 4.81E 3 2.39E 2 7.08E 2

2. AVERAGb KELEASE RATE FOR pCi/ 2.88E 3 2.51E 3 6.05E 4 3.01E 3 PERIOD gee E. PERCENTAGE OF STACK EFFLUENT RELEASE LIMITS QTR QTR QTR QTR YEARLY

1. NOBLE GAS RELEASE GAMMA  % 0.00E+00 0.00E+00 0.00E400 0.00E+00 0.00E+00 BETA  % 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+(0

2. 113 AND ALL RADIONUCLIDES IN PARTICULATE FORM WITil liALF LIVES GREATER TilAN 8 DAYS 111GIIEST ORGAN  % 1.36E-4 1.27E-4 4.10E 5 1.40E-4 2.16E-4 EFFLUENT AND WASTE DISPOSAL REPORT -(cont'd) l O .

TABLE 1H i EFFLUENT AND WASTE DISPOSAL ANNilAL REPORT 1997 GASEOUS EFFLUENTS . ELEVATED RELEASE 4

CONTINU0S MODE UNIT QTR QTR QTR QTR TOTAL NUCLIDES RELEASED

1. FISSION GASES KRYPTON 85 Ci 0.00E+00 0.00EKK) 0.00E+00 0.00E+00 01K)E+00

2. IODINE l 131 No longer analyzed for.

3. PARTICULATES STRONTIUM 90 Ci 4.33E 8 0.00E+00 0.00E40 0.00E+00 4.33E 8 CESIUM 134 Ci 0.00 EMF) 0.00E+00 0.00E+00 0.00E+00 0.(CEK)0 CESIUM 137 Ci 1.12E 7 3.40E 7 8.80E 8 0.00E+00 5.40E 7 COBALT 60 Ci 1.15E 7 3.10E 7 6.40E 7 3.34E 7 140E-6 Ci Ci Ci Ci Ci Ci TOTALS Ci 2.70E 7 6.50E 7 7.28E 7 5.34E 7 2.18E 6 l

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i EFFLUENT AND WASTE DISPOSAL REPORT -(cont'd)

TABLE 2A 1

j EFFLtfENT AND WASTE DISPOSAL ANNtfAL REPORT 1997 LIOlllD EFFLllENTS - StiMM ATION OF All, RELEASES UNIT QTR QTR QTR QTR TdTAL A. FISSION & ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCL. Ci 9.99E-4 6.94E 2 9.82E 3 3,71E 3 8.40E 2 TRITIUM. GASES, ALPilA)

2. AVERAGE DILUTED CONCEN. Ci/ 1.42E 9 1.13E-8 9.52E.9 4.01E 9 TRATION DURING PERIOD ml i

Y B. TRITIUM l TOTALRELEASE Ci 3.43E 3 3.52E 3 6 80E 3 5.0lE 3 1.88E 2

2. AVERAGE DILUTED CONCSN. Ci/ 4.88E 9 5.75E 10 6.59E 9 5.43E 9 TRATION DURING PERIOD ml i C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE Ci 0.00 0.00 0.00 0.00 0.00 I

2. AVERAGE DILUTED CONCEN- pCi/ 0.00 0.00 0.00 0.00

. TRATION DURING PERIOD ml D. GROSS ALPilA RADIOACTIVITY

1. TOTAL RELEASE Ci 4.69E-6 1.85E 5 3.95E 6 8.12E 6 3.53E 5 E. VOLUME OF WASTE RELEASED Liters 3.26E+4 3.04E+5 5.53E44 4.31E+4 4.35E+5 (PRIOR TO DILUTION)

F. VOLUME OF DILUTION WATER Liters 7.04E+ 8 6.12E+9 1.03E+9 9.23E+ 8 8.78E+9 USED DURING PERIOD

, G. PERCENTAGE OF ODCM LIMITS FOR LIQUID RELEASES QTR QTR QTR QTR YEARLY lilGIIEST ORGAN  % 0.16 17.70 2.74 0.72 10.66 WilOLE BODY  % 0.34 37.29 5,78 1.52 22.46 4

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EFFLUENT AND WASTE DISPOSAL REPORT -(cont'd) ,

O TAELE2E EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1997 LIOUID EFFLUENTS NUCLIDES RELEASED UNIT QTR QTR QTR QTR MANGANESE 54 Ci 0.00E400 0.00E+00 0.00E+00 0.00E+00 '

IRON 55 Cl 2.17E-5 0.00E+00 6.41E 3 1.14E-4 COBALT 60 Ci 3.96E-4 1.44E 3 1.16E-3 1.32E 3 STRONTIUM 90 Ci 1.76E 5 8.08E 4 1.46E-4 8.44E 5 l CESIUM 134 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 CESIUM 137 Ci 3.63E-4 6.72E 2 8.45E 3 2.19E-3 TOTAL FOR PERIOD Ci 9.99E-4 6.94E 2 9.82E-3 3.71E 3 (ABOVE)

KRYPTON 85 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4

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EFFLUE14T AND WASTE DISPOSAL REPORT -(cont'd) i TABl.E 3 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT - 1997 I SOLIQ WASTE AND IRRADIATED FUEL SIIIPMENTS i A. SOLID WASTE SillPPED OFFSITE FOP DISPOSAL (Not Irradiated Fuel) -

6 MONTil 6 MONTil

1. TYPE OF WASTE UNIT ~

PERIOD PERIOD TOTAL ~ '

, a. SPENT RESINS, FILTER SLUDGES, m' 0 0 0 EVAPORATOR BOTTOMS. ETC. Ci

0 0 0

b. DRY COMPRESSIBLE WASTE, m' 36.25 72.50 108.75 CONTAMINATED EQUIPMENT, ETC. Ci 0.014 0.034 0.048 l c. IRRADIATED COMPONENTS, CONTROL n? O O O ,

RODS, ETC- Ci 0 0 0 i d. OTitu.R(DESCRIBE) m' 0 0 0 Ci 0 0 0

2. ESTIMATE OF MAJOR NUCLIDE 6 MON 1h 6-MONTH COMPOSITION (BY TYPE OF WASTE) PERCENT PERIOD PERIOD 9

Co-60 35.3 4.94E-3 1.20E 2 Cs 137 8.9 1.25E-3 3.03E 3 Fe 55 28.3 3.96E.3 9.62E 3 Ni 59 4.9 6.86E-4 1.67E-3 Ni-63 22.2 3.I 1 E-3 7.55E 3 i

3. SOLID WASTE DISPOSITION NO. OF SillPMENTS MODE OF TRANSPORTATION DESTINATION i

3 Sole Use American Ecology

> (Oak Ridge, TN)

H. IRRADIATED FUEL SIIIPMENTS (DISPOSITION)

NO. OF StilPMENTS MODE OF TRANSPORTATION DESTINATION O sose ,

12 l

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EFFLUFNT AND WASTE DISPOSAL REPORT -(cont'd)

O

8. O OFFSITE DOSE CALCULATIONS

SUMMARY

AND CONCLUSIQJ'S:

a. Gaispys EfiluenLBskassa The maximum quarterly offsite gamma dose due to noble gases was 0.00 mrad.

i The cumulative 1997 annual offsite gamma dose due to noble gases was 0.00 mrad.

The maximum quarterly offsite beta dose due to noble gases was 0.00 mrui. The cumulative 1997 annual olisite beta dose due to noble gases was 0.00 mrad.

The maximum quarterly offsite dose to any organ from the release of H 3 and all radionuclides in particulate form with half lives greater than 8 days was approximately 1.05 E 5 mrem. The cumulative 1997 annual maximum organ dose from these radionuclides was also approximately 3.24 E-5 mrem.

The highest historical annurj average X/Q equal to 1.82 E-6 sec/m' for the period 1985 1987 for the worst case offsite receptor location, in accordance with the ODCM, wu used to calculate these ofTsite dose values,

b. Liquid Efiluent Releases The maximum quarterly organ dose from liquid relesses was approximately 8.85 E-1 mrem. The maximum cumulative 1997 annual organ dose was approximately 1.07 E+00 mrem. The maximum quarterly total body dose for liquid releases -

was approximately 5.59 E-1 mrem, and the cumulative 1997 annual total body dose was approximately 6.74 E-1 mrem.

c. Conclusion All calculated offsite doses were below ODCM limits.

O 13

O

. SECTION B L

I ANNUAL RADIOLOGICAL g, ENVIRONMENTAL MONITORING RFsPORT K. January 1 - December 31,1997 O

O_ -IN7RODUCTION:

The Radiological EnvironmentalMoniwring (REM) Program is conducted to comply with the requirements of the ODCMardin accordance with 10 CFR 30 Apperdix1. The IWM Program provides measurements ofradiation ard ofradioactive materials in those expos"~.e

- pathways andfor those radionuclides which couldpotentially lead to radiation doses to Members of the Public resultingfrom plant effuents. Environmental samples are taken within -

the surrounding areas of the plant and in selected control or backgrourd locations.

The monitoringprogram at the IACBWRfacility includes monitoring ofliquid and gaseous releasesfrom the plant, as well as environmental samples ofsurface air, river water, 0 river sediment, milk, fish, andpenetrating radiation.

The REMprogram theory supplements the Radioactive Effluent analyses by venfying that the measurable concentrations ofradioactive materials and levels ofradiation are not higher than expected on the basis of the effuent measurements a.,d modeling of the .

environmental expostire pathways usin;; the methodology of the Offsite Dose Calculation Manual (ODCM).'

An Interlaboratory Comparison Program isprovided to ensure that independent checks on the precision arut accuracy of the measurements ofradioactive materialin environmental samples areperformed.

RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT - (cont'd) 1.0 SAMPLE COLLECTION Environmental samples are collected from the area surrounding LACBWR at the frequencies outlined in the ODCM. A series of figurea a .i tables are included in this report to s

better show LACBWR's environmental program.

FIGURE 1 This map includes the plant boundary, roads, other generation plants, and the relationship of the p' ant to the nearest local community.

IIGURE 2 This map shows the location of LACBWR's permanent environmental monitoring stations.

FIGU~RES 3&4 These maps show the location of LACBWR's TLDs.

TABLE 5 This table shows the sampling frequency of the various environmental samples and the analyses performed on these samples TABLE 6 This table shows the permanent monitoring stations used in LACBWR's environmental program.

O TABLE 7 This tebie shows the TtD iocetions.

TABLE 8 This table shows the number of various samples collected and analyzed during 1997.

2.0 RESULTS OF THE 1997 RADIO-ENVIRONMENTAL MONITORING SURVEYS During 1997, activity levels in the local environment were normal, indicating no significant plant attributed radioactivity.

2.1 PENETRATING RADIATION The environmental penetrating radiation dose is meast . by thermoluminescent dosimeters consisting of four lithium fluoride (LiF) chips. These TLD's are changed on a quarterly basis and are sent to an outside contractor for reading. The TLD results for 1997 are shown on Table 9.

RADIOLOGICitL ENVIRONMENTAL MONITORING REPORT - (cont'd)

O 2.2 AIR PARTICULATE Air samples are collected continuously from various sites (see Table 6) around LACBWR. An air sampler is also located 18 miles north of the plant in La Crosse, Wisconsin, to act as a control station.

Particulate air samples are collected at the rate of approximately 30-60 Ipm with a Gelman Air Sampler. The air filter consists of a glass fiber filter with an associated pore size of approximately 0.C pm. The particulate filters are analyzed weekly for gross beta activity with an internal r oportional counter, and the monthly particulate composites are gamma analyzed for individual isotopic concentration.

TABLE 10 This table shows the weekly gross beta gamma activity concentration from the air particulate filters.

O V TABLE 11 This table shows the composite air particulate isotopic analysis.

Comparison between the control station at La Crosse and the other stations near LACBWR indicate that there was no significant plant attributable airborne particulate activity.

2.3 RIVER WATER River water is collected monthly. Rh er water samples above, at, and below the plant site are collected and are gamma analyzed for isotopic concentration. The river water gamma isotopic analysis results are shown in Table 12. The results indicate that there is insignificant plant-attributable radionuclides in the river water.

O RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT - (cont'd)

O 2.4 sEolmEsrsAMetEs Sediment samples were collected twice per year above, at, and below the plant outfall. These samples were gamma analyzed and these results appear on Table 13. They indicated that small amounts of plant attributed radionuclides have accumulated in river sediments near the outfall.

2.5 MILK SAMPLES Milk samples were collected monthly from two dairy farms in the vicinity of LACBWR (see Table 6) and gamma analyzed. These samples are listed in Table 14.

There has been no significant accumulation of plant attributed radionuclides in milk in the vicinity of LACBWR.

2.6 EISJJ O rish sempies were ceiiected aeerterir abeve eed beiow the giant discherse. The results of gamma spectral analysis of edible portions of fish samples appear in Table 15.

There has been no significant accumulation of plant attributed radionuclides in fish in the vicinity of LACBWR.

2.7 VEGETATION Vegetation samples were collected from local gardens at the time of harvest. The results of the gamma spectral analysis of the vegetation samples appear on Table 16.

There has been no significant accumulation of plant attributed radionuclides in the vegetation.

RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT - (cont'd) h 3.0 CGNCLtISIONS All environmental sar4ples collected and analyzed during 1997 exhibited no significant contribution from LACBWR.

s 4.0 INTERLABORATORY COMPARISON PROGRAM REStiLTS During 1997, interlaboratory comparison samples were obtained from an outside contractor. The equipment used to analyze the environmental samples was tested against the contractors' results. The following is the result of this comparison.

LACBWR CONTRACTOR g ANALYSIS RESULTS (pCi/cc) RESULTS (pCi/cc)-

b GROSS DETA 5.90 E-3 6.63 E-3 GROSS ALPHA 3.38 E-3 3.14 E-3 TRITIUM 2.44 E-3 1.56 E-3 CS-137 5.30 E-3 5.27 E-3 CO-60 4.71 E-3 4.75 E-3 0

Imuce or f

l - . .?E".*.^... i 6

o Li I

~ ~ ./,eh -

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O O O !

TABLE 5 i I

SAMPLE FREOUENCY AND ANALYSIS OF RADIO-ENVIRONMENTAL SAMPLES  !

I SAMPLE FREOUENCY ANALYSIS PERFORMED TLD (LiF) Dosimeters Quarterly Dose in mrem Particulate Air Glass Fiber Filters Weekly Gross Beta and Gamma Spectroscopy of Composites Monthly (HPGe-MCA)

Milk Monthly during grazing season Gamma Spectroscopy Sediment Twice peryear Gamma Spectroscopy Fish Quarterly Gamma Spectroscopy River Monthly Gamma isotopic analysis and tritium (Liquid Scintillation Analyzer)

Vegetation At time of harvest Gamma Spectroscopy l

O raste.

PERMANENT ENVIRONMENTAI, MONITORING STATION 1,0 CATIONS (Refer to Figure 2)

LOCATION AIR

. NO. - LOCATION SAMPLE- MILK' 1 Pedretti Farm x 2 P. Malin Farm x 3 Radio Tower x 4 Dam No. 8 x 5 Trailer Court x 6 Cdb House x 7 Main Office x 0

RADIOLOGICAL ENVIRONMENTAL MONITORING RRPORT - (cont'd)

O r^= Lev ENVIRONMENTAL TLD LOCATIONS LOCATION -

' NO. . LOCATION 1 LA CROSSE MAIN OFFICE AIR SAMPLER BOX 2 DAM #8 AIR SAMPLER BOX 3 RADIO TOWER BUILDING AT AIR SAMPLER 4 TRAILER COURT AIR SAMPLER BOX 5 CRIBHOUSE AIR SAMPLER BOX 6 G-3 CONTROL ROOM 7 SW GATEPOST AT END OF G-3 DIKE 8 ON FENCE N. SIDE OF FISHERMAN'S ROAD 9 SITE ENTRANCE GUARD AREA O to ou rsuce ^T "8 co*"8n o8 T"e swirc"v^no 11 ON N. SITE AREA FENCE GATE =

12 G 1 CRIBHOUSE 13 ON MOORING WALKWAY WEST OF LACBWR #2 WAREHOUSE 14 G-3 COAL UNLOADING CRANE 15 POWER POLE ON BLUFF SIDE EAST OF PLANT 16 RESTRICTED AREA FENCE N. SIDE 17 RESTRICTED AREA FENCE E. SIDE 18 RESTRICTED AREA FENCE S. SIDE 19= RESTRICTED AREA FENCE SW CORNER 20 RESTRICTED AREA FENCE W. SIDE 21 RESTRICTED AREA FENCE NW CORNER O

RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT - (cont'd)

O TABLE 8 RADIO-ENVIRONMENTA1, SAMPLES COJAECTED, JANUARY-DECEMBER 1997 NUMBER OF TYPE OF SAMPLE SAMPL,ES Penetrating Radiation (TLD's) 82 Air Particulate 247 River Water 36 l Sediment 6 Milk 12 Fish 8 J

Vegetation 2 O

RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT - (cont'd)

O r^='e' OUARTERLY TilERMOLUMINESCENT DOSIMETER DOSE MEASUREMENT.S IN Tile LACBWR VICINITY 1997

, STATION ist QUARTER - 2nd QUARTER 3rd QUARTER 4tl' VUARTER NO. mrem .. mrem mrem mrem 1 14.8

• 3.6 12.2

• 5.9 18.0

• 6.9 13,8

• 3.3 2 17.6

• 1.1 12.4

• 5.9 20.2

• 5.7 18.0 2.8 4 3 16.2

• 3.3 14.8

• 1.7 21.2

• 12.2 17.0 4.5 4 18.0 1.4 15.0

• 8.1 24.6 i 7.2 22.2 5.2 5 20.7 2.3 21.8 3.6 23.8

• 4.8 21.6

• 5.9 6 21.8

• 2.6 14.6

• 5.4 18.0

• 2.4 15.0

• 4.5 7 18.0

• 3.7 19.4

• 3.0 24.6

• 6.9 18.4

• 1.8 8 19.8

• 6.5 19.2

• 3.3 22.2

• 7.0 21.4 3.0 9 18.4 3.0 20.6

• 4.6 27.0

• 6.2 22.2

• 4.3

< C. 10 17.0

• 3.7 17.4 3,0 22.2

• 4.I 17.8

• 3.6 18.4 i 1.I 4

11 19.0

• 2.0 26.0

• 7.1 22.2

• 5.5 12 21.0 * [0 16.8

• 6.1 29.8

• 6.8 20.4 3.9 13 20.0

• 3.7 MISSING 24.4 3.9 20.4

• 3.6 j 14 13.2

• 2.6 14.4

• 3.0 MISSING 17.0 + 5.I 15 21.4 + 1.8 23.0 3.9 34.0

• 10.0 26.2

• 5.7 16 38.6

• 10.8 39.6

• 6.9 44.0 13.3 42.6

• 4.6 17 50.4

• 12.2 50.6 19.5 66.0 14.5 53.4

• 19.1

~

18 48.4 7.9 48.4 14.7 58.4

• 23.3 54.0 18.1 19 31.6 6.7 31.6 2.3 47,0 17.5 33.8 i 11.3

, 20 28.4 5.2 27.6 2.3 34.4 9.4 30.2 6.7 21 34.4

• 4.6 32.2

• 14.2 39.8

• 6.5 39.6

• 10.6 Station #1 (La Crosse Main Office) located approximately 16 miles north ofLACBWit is considered the Control TLD.

(3 p (~

/

TABLE 10 WEEKLY GROSS BETA AIR PARTICULATES IN THE LACBWR VICINITY (Reporting Level = 10 times Control Value)

COLLECTION LACBWR PLANT TRAILER COURT DAM #8 RADIO TOWER LA CROSSE DATE pCi/m' pCi/m' pCi/m' pCi/m' CONTROL 1/7/97 .046 .004 .042 i .003 .043 i.004 .017 i .002 .045 .003 1/14/97 .036 .004 .037 i.003 .052 .004 .022 1.002 .043 .003 1/21/97 .029 1.004 .027 .003 .036 i .004 .016 1.002 .03I i .003 1/28/97 .032 .003 .028 i.003 .038 .004 .014 i .002 .033 i .003 2/4/97 .041 f.003 ,037 .003 .027 .003 .015 .002 .043 .003 2/11/97 .027 .004 .025 .003 .029 i.004 .012 .003 .030 1 .003 2/18/97 .028 .003 .028 .003 .033 .004 .010 i.003 .034 .003 2/25/97 .035 .004 .026 i .003 .037 i.004 .025 .004 .034 1.003 3/4/97 .027 i.003 .025 .003 .039 .004 No Sample Pump .039 .005 OOC 3/11/97 .033 .003 .028 .003 .036 .004 .031 i .004 .016 .002 3/18/97 .030 .003 .027 t.003 .033 .004 .040 i .01 .048 i .004 3/25/97 .024 .003 .017 .002 .031 .004 .025 i.003 .020 .002 4/1/97 .018 1.003 .017 .002 .024 i.003 .018 1.003 .016 .002 4/8/97 .014 .002 .016 .002 .021 .003 .018 .003 .015 i .002 4/15/97 .027 .003 .025 .003 .038 .004 .038 .004 .024 .002 4/22/97 .025 .003 .029 .003 .039 .004 .033 .004 .026 .003 4/29/97 .019 .003 .015 .002 .026 .003 .021 1.003 .050 .002

- - . _ . . . _ - _ _ _ _ _.m _. ._. __- - - . - - - . - . _ ~ . _ _ _ - _ . _ . _ _ _ - . -

O O O

' TABLE 10 i WEEKLY GROSS BETA AIR PARTICULATES IN THE LACBWR VICINITY (Reporting Level = 10 times Control Value) -

COLLECTION LACBWR PLANT TRAILER COURT DAM #8 RADIO TOWER LA CROSSE .

.DATE L pCi/m' pCi/m' pCi/m' lpCi/m' CONTROL 5/6/97 .019 1.003 No Sample Pump 0?? M4 .027 i .003 No Sample Pump OOC OOC j r

5/13/97 .016 .003 .0101.002 .02i .003 .016 i.003 No Sample Pump OOC 5/20/97 .014 .002 .013 i .002 .020 i.003 .016 1.003 No Sample Pump OOC i

5/27/97 .012 .002 No Sample Pump .013 i .002 .015 i.003 No Sample Pump OOC OOC 6/3/97 .016 .002 .016 i .002 .019 1.003 .020 i .003 .018 i.003 6/10/97 ' .017 .002 .016 .002 .022 i .003 .015 .003 No Sample Pump OOC 6/17/97 .014 i .002 .017 i.002 .017 .002 .023. 007 .011 .002 6/24/97 .017 1.002 .022 i.003 .030 i .004 .022 i.003 No Sample Pump OOC 7/1/97 .019 .002 .020 .003 .015 i.003 .017 i.002 No Sample Pump OOC .

l 7/8/9' .017 i .002 .021 .002 .017 .004 .019 i .002 .019 1.002  ;

1 7/l5/97 .013 .002 .023 i.003 .021 .003 .017 .003 .019 1.002 .

i 7/22/97 .007 .002 .028 .003 .027 .003 .020 i .003 .024 i.003 i 7/29/97 No Sample Pump .028 .003 .023 .003 .018 i .004 .020 1.002 i OOC  :

I

O O O TABLE 10 WEEF1Y GROSS BETA AIR PARTICULATES IN THE LACBWR VICINriY (Reporting Level = 10 time- Control Value)

COLLECTION LACBWR PLANT TRAILER COURT- DAM #8 RADIO TOWER LA CROSSE DATE pCi/m' pCi/m' pCi/m' pCi/m' COhTROL 8/5/97 No Sample Pump .025 .003 .024 i .003 .015 .003 .023 1 .002 OOC 8/12/97 No Sample Pump .024 .003 .02I .003 .020 i .003 .022 i .002 OOC 8/19/97 .025 i.003 .017 .002 .019 i .003 .016 i .002 .016 i.002 8/26/97 .018 i.003 017 .002 .018 1.003 .015 i .002 . 016 i.002 -

9/2/97 .024 i .003 .026 i.002 .028 i .003 .022 .002 .023 i.002 9/9/97 .021 1.003 .017 .002 .016 .002 .021 i.002 .016 i.002 9/16/97 .032 .003 .026 i.002 .034 1.003 .024 i .002 .025 .002 9/23/97 .022 * .003 .017 i.002 .016 i.003 .018 i .002 .018 .002 9/30/97 .021 i .003 .017 .002 .022 .003 .016 .002 .017 .002 10/7/97 .028 .003 .024 1.002 .032 .003 .026 .002 .029 1 .00; 10/14/97 .027 i .003 .022 i.002 .026 .003 .025 .002 .025 i .002 10/21/97 .025 i .003 .024 .002 .030 .003 .019 .002 .021 .002 10/28/97 .017 .003 .018 .002 .021 .003 .015 i.002 .018 i.002 11/4/97 .025 .003 .019 .002 .024 i .003 .020 1.002 .021 1.002 11/10/97 .012 .002 .012 .002 .014 .002 .012 i .002 .016 .002 11/18/97 .024 i .003 .024 i.003 .024 .002 .021 i .002 .023 .002 11/25/97 .063 i.003 .052 .003 .055 1.004 .051 .003 .056 i.003 4

O O O TABLE 10 WEEKLY GROSS BETA AIR PARTICULATES IN THE LACBWR VICINITY ,

(Reporting Level = 10 times Control Value) i COLLECTION - lLACBWR PLANT TRAILER COURT- DAM #8 RADIO TOWER - LA CROSSE '

DATE i pCi/m' . 'pCi/m . pCi/m' ' -

pCi/m'. . CONTROL {

12/2/97 .037 .004 .035 .003 .038 1 .003 .029 i.003 .035 i.003 12/9/97 .016 .003 .015 i.002 .017 .002 .014 i.002 .014 i.002 12/16/97 .035 .003 .027 i.003 .034 .003 .028 i.003 .030 i.003 i 12/23/97 .025 i.003 .030 i.003 .033 i .003 .021 i.003 .028 1.003 i 12/30/97 .028 i .003 .025 i.003 .027 i.003 .023 i.002 .027 i.003 t

2 I

e L

I r

M b.

O O O TABLE 11 AIR PARTICULATE COMPOSITE RESULTS (Concentrations in pCi/m')

LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE START DATE 12-30-96 12-30-96 12-36-96 12-30-96 12-30-96 END DATE l-28-97 1-28-97 1-28-97 1-28-97 1-28-97 ISOTOPES /RL*

Cs-134/10 <2. I 1 E-3 <2.52E-3 <2.04E-3 <2.70E-3 <l .83 E-3 l Cs-137/20 < l .96E-3 <2.36E-3 <2.16E-3 <2.57E-3 <l .71 E-3

• RL = REPORTING LEVEL LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE l

START DATE l-28-97 1-28-97 1-28-97 1-28-97 1-28-97 END DATE 3-04-97 3-04-97 3-04-97 3-04-97 3-04-97 ISOTOPES /RL*

Cs-134/10 <2.65E-3 <2.06E-3 < l .69E-3 <2.2 ! E-3 <l .62E-3 Cs-137/20 <2.62E-3 <l .99E-3 < l .62E-3 <2.13 E-3 <l .61 E-3

• RL = REPORTING LEVEL

O O O TABLE 11 AIR PARTICULATE COMPOSITE RESULTS (Concentrations in pCi/m') .

LOCATI RADIOTOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE START 1 3-04-97 3-04-97 3-04-97 3-04-97 3-04-97 END DNIL 4-01-97 4-01-97 4-01-97 4-01-97 4-01-97 ISOTOPES /RL*

Cs-134/10 <3.34E <2.5P.E-3 <2.01 E-3 <2.88E-3 <1.92E-3 Cs-137/20 <3.84E-3 <l .61E-3 <l.92E-3 <2.84E-3 <l.%E-3 Co-60 2.12E-3 9.62E-4

• RL = REPORTING LEVEL l

LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE START DATE 4-01-97 4-01-97 4-01-97 4-01-97 4-01-97 END DATE 4-29-97 4-29-97 4-29-97 4-29-97 4-29-97 ISOTOPES /RL*

Cs-134/10 - <3.05E-3 <2.60E-3 <2.08E-3 <2.94E-3 <2.38E-3 Cs-137/20 <2.99E-3 <2.49E-3 <2.10E-3 <3.14E-3 <2.47E-3

• RL = REPORTING LEVEL L -

O O O TABLE 11 AIR PARTICULATE COMPOSITE RESULTS (Concentrations in pCi/m')

RADIO TOWER. LACBWR TRAILER COURT DAM NO. 8 LA CROSSE LOCATION 4-29-97 4-29-97 4-29-97 4-29-97 4-29-97 START DATE 6-03-97 6-03-97 6-03-97 6-03-97 6-03-97 END DATE ISOTOPES /RL*

<l .73 E-3 <l.35E-3 <2.10E-3 <l .61E-3 <6.90E-3 )

Cs-134/10

<l .63 E-3 <l .31E-3 <l .99E-3 <1.50E-3 <6.99E-3 Cs-137/20

\

i

• RL = REPORTING LEVEL RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE LOCATION 6-03-97 6-03-97 6-03-97 6-03-97 6-03-97 START DATE 7-01-97 7-01-97 7-01-97 7-01-97 7-01-97 END DATE ISOTOPES /RL*

<2.33 E-3 <l .44E-3 <l.66E-3 <1.%E-3 <8.16E-3 Cs-134/10

<2.27E-3 <l .03E-3 <l .72E-3 <l .91E-3 <5.00E-3 Cs-137/20

• RL = REPORTING LEVEL

O O O TABLE II AIR PARTICULATE COMPOSITE RESULTS .

(Concentrationsin pCi/m')

LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE START DATE 7-01-97 7-01-97 7-01-97 7-01-97 7-01-97 END DATE 7-29-97 7-29-97 7-29-97 7-29-97 7-29-97 ISOTOPES /RL' Cs-134/10 <2.19E-3 <2.65E-3 <3.01 E-3 <l.98E-3 <l .38E-3 Cs-137/20 <l .16E-3 <l .58E-3 <3.07E-3 <l .46E-3 <l .36E-3

• RL = REPORTING LEVEL LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE START DATE 7-29-97 7-29-97 7-29-97 7-29-97 7-29-97 END DATE 9-2-97 9-2-97 9-2-97 9-2-97 9-2-97 ISOTOPES /RL*

Cs-134/10 <l .25E-3 <l.58E-3 <l .16E-3 <l .33E-3 <l .06E-3 Cs-137/20 <8.28E-4 <1.53E-3 <l .10E-3 <l .36E-3 <l .07E-3 Co-60 1.39E-3 4.75E-4 1.26E-3 i 5.97E-4

• RL = REPORTING LEVEL i

i

O O .O TABLE 11 AIR PARTICULATE COMPOSITE RESULTS (Concentrations in pCi/m')

LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE START DATE 9-02-97 9-02-97 9-02-97 9-02-97 9-02-97 END DATE 9-30-97 9-30-97 9-30-97 9-30-97 9-30-97 ISOTOPES /RL*

Cs-134/10 <l .13 E-3 <l.82E-3 <l .31 E-3 <l.66E-3 <l.31E-3 Cs-137/20 <l .10E-3 <l.70E-3 <l .22E-3 <l .67E-3 <133E-3 Co-60 2.00E-3 6.82E-4

• RL = REPORTING LEVEL LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 L.A CROSSE START DATE - 9-30-97 9-30-97 9-30-97 1 30-97 9-30-97 END DATE 10-28-97 10-28-97 10-28-97 10-28-97 10-28-97 ISOTOPES /RL*

Cs-134/10 <L 10E-3 <l .68E-3 <l .22E-3 <l.65E-3 <131E 3 Cs-137/20 <7.58E-4 <l .28E-3 <l .71 E-3 <l .61E-3 <l .32E-3 Co-60 1.69E-3 6.97E-4 L66E-316.40E-4 1. ISE-3 4.82E-4

• RL = REPORTING LEVEL

m p , , .

s TABLE 11 AIR PARTICULATE COMPOSITE RESULTS (Concentrations in pCi/m')

LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE START DATE 10-28-97 10-28-97 10-28-97 10-28-97 10-28-97 END DATE 12-02-97 12-02-97 12-02-97 12-02-97 12-02-97 j ISOTOPES /RL Cs-134/10 < l .12E-3 <l .65E-3 <1.25E-3 <l.51 E-3 <l .26E-3 Cs-137/20 <7.21 E-3 < l .70E-3 <l .18E-3 <l .43E-3 <l .19E-3 Co-60 1.42E-3 i 1.14E-3 .

• RL = REPORTING LEVEL LOCATION RADIO TOWER LACBWR TRAILER COURT DAM NO. 8 LA CROSSE l

START DATE 12-02-97 12-02-97 12-02-97 12-02-97 12-02-97 END DATE 12-31-97 12-31-97 12-31-97 12-31-97 12-31-97 ISOTOPES /RL*

l Cs-134/10 <1.46E-3 <2.10E-3 <l .56E-3 <l .77E-3 <l .55 E-3 Cs-137/20 < l .47E-3 <2.14E-3 <l .60E-3 <l .87E-3 <l .47E-3 Co-60 1.97E-3 6.68E-4 1.54E-3 i 6.74E-4

• RL = REPORTING LEVEL

O O. O TABLE 12 RESULTS OF ANALYSIS OF MISSISSIPPI RIVER WATER IN THE VICINITY OF LACBWR (Concentrations in pCi/ Liter)

~ SAMPLE #1 - SAMPLE #2' SAMPLE #3 SAMPLE #1 SAMPLE #2 SAMPLE #3 COLLECTION DATE: 'l-14-97 1-14-97 1-14-97 ~ 2-11-97 2-11-97 2-11-97 ,

I SAMPLE LOCATION: ' DAM 8- 'OUTFALL ' VICTORY DAM 8 . OUTFALL VICTORY ISOTOPES /RL

• i i

H-3/ 20000 <251 <251 <251 307 227 <275 <235 Mn-54/1000 <4.41 <4.62 <4.49 <4.40 <4.44 <4.42 Co-60/300 <4.79 <4.81 <4.94 <4.67 <5.15 <4.86 Zn-65/300 <11.5 <10.5 <11.0 <11.5 <11.0 <11.0 Cs-134/30 <4.89 <5.15 <4.92 <5.16 <4.99 <5.09 Cs-137/50 <4.93 <4.67 <4.89 <4.60 <4.68 <5.05 t

i i

i

• RL = REPORTING LEVEL '

O O O TABLE 12  !

RESULTS OF ANALYSIS OF MISSISSIPPI RIVER WATER IN THE VICINITY OF LACBWR (Concentrations in pCi/ Liter)

SAMPLE #1 - SAMPLE #2 -SAMPLE #3 SAMPLE #1 - ' SAMPLE #2 - SAMPLE #3  ;

COLLECTION DATE: 3-11-97 3-11 3-11-97 .4-8-97 4-8 4-8-97 ,

SAMPLE LOCATION: DAM 8- OUTFALL -VICTORY DAM 8 OUTFALL : . VICTORY ,

ISOTOPES /RL

• 11-3/ 20000 <240 <240 <240 <257 <257 <257 Mn-54/1000 <4.23 <4.41 <4.33 <4.06 <4.49 <4.40 Co-60/300 <4.81 <4.69 <4.84 <4.82 <5.15 <4.84 .

Zn-65/300 <9.85 <10.3 <11.4 <10.8 <10.4 <10.7 Cs-134/30 <5.10 <4.90 <4.96 <4.72 <4.84 <5.02 Cs-137/50 <4.84 <4.79 <4.60 <4.65 <4.39 <4.53 W.

• RL = REPORTING LEVEL O O O TABLE 12 i RESULTS OF ANALYSIS OF MISSISSIPPI RIVER WATER IN THE VICINITY OF LACBWR (Concentrationsin pCi/ Liter)

' SAMPLE #1 SAMPLE #2 SAMPLE #3 SAMPLE #1 SAMPLE #2 - SAMPLE #3 COLLECTION DATE- 5-13-97 5-13-97 13-97 6-10-97 6-10-97 6-10-97 SAMPLE LOCATION: DAM 8 OUTFALL. VICTORY ' DAM 8 - OUTFALL VICTORY i

ISOTOPES /RL

• H-3/ 20000 <271 <271 <271 <272 <272 <272 r

Mn-54/1000 <4.57 <4.32 <4.52 <3.02 <3.14 <3.12 i

Co-60/300 <4.89 <4.91 <4.98 <3.50 <3.50 <3.17 Zn-65/300 <10.3 <9.82 <10.4 <6.7 3 <6.88 <7.10 l Cs-134/30 <4.82 <5.03 <5.10 <3.48 <3.34 <3.47 Cs-137/50 <4.44 <5.16 <4.87 <3.24 <3.32 <3.52 L

I i

t l

• RL = REPORTING LEVEL i r

t

I O O O-TABLE 12 RESULTS OF ANALYSIS OF MISSISSIPPI RIVER WATER IN THE VICINTIY OF LACBWR (Corcenetiomin pCi/ Uter)

SAMPLE #1 SAMPLE #2 SAMPLE #3 SANIPLE #1 SAMPLE #2 L SAMPLE #3 7-8-97 7-8-97 7-8-97 8-12-97 8-12-97 8-12-97 COLLECTION DATE:

DAM 8 OUTFALL VICTORY DAM 8 OUTFALL VICTORY SAMPLE LOCATION:

ISOTOPES /RL

• l 329 247 293 246 282 i 245 <271 <271 <27I 11-3/20000

<2.90 <3.14 <3.21 <3.08 <2.99 <3.04 Mn-54/1000 Co-60/300 <333 <l.84 <3.47 <3.59 <339 <3.53

<7.08 <7.41 <7.47 <7.35 <7.40 <7.48 Zn-65/300

<335 <3.50 <3.46 <3.63 <3.45 <3.60 Cs-134/30

<3.24 <3.25 <3.00 <3.50 <3.42 <338 Cs-137/50

• RL = REPORTING LEVEL

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O O O TABLE 13 RESULTS OF ANALYSIS OF MISSISSIPPI RIVER SEDIMENT IN THE VICINITY OF LACBWR (Concentration in pCi/Kg)

(Reporting Level = 10 times Upstream Value)

COLLECTION DATE SAMPLE # 1 SAMPLE # 2 SAMPLE # 3 SAMPLE # 1 SAMPLE # 2 SAMPLE # 3 SAMPLE LOCATION 6-19-97 6-19-97 6-19-97 8-25-97 8-25-97 8-25-97 UPSTREAM DISCHARGE DOWNSTREAM UPSTREAM DISCHARGE DOw3 STEAM ISOTOPES Co-60 262 12.9 21.6 2.46 Cs-134 <5.85 <7.34 <7.74 <10.3 <4.53 <7.11 Cs-137 14.30 1 2.96 1305 1 91.7 153.5

• 12.4 119

• 10.8 128 10.0 17.7

• 3.38 MN - 54 4.45 2.10 4.85 2.% 8.42 2.99 6.1112.36 L_ _ .. . . . . . .

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

i O TABLE 14 I

RESULTS OF ANALYSIS OF MILK SAMPLES IN Tile VICINITY OF LACHWR (Concentrations in pCi/ Liter)

~

SAMPLE- COLLECTION ISOTOPES /RL

• LOCATION - DATE Cs 134/60 Cs 137/60

P. hiALIN 11497 <5.88 <$.3 8 3

PEDRETTI 21297 <5.37 <5.23 i

! PEDRETTI 31197 <S.37 <$.67 P. MALIN 4 8-97 <5.27 <5.25 ,

i PEDRETTI 51397 <5.27 <5.23 P. MALIN 6-10 97 <3.83 <3.52 O PEDRETTI 7897 <3.65 <3.78 P. MALIN 8 12-97 <3.56 <3.59 PEDRETTI 9997 <3.69 <3.80

. P. MALIN 10 14-97 <3.67 <3.77 PEDRETTI 11 12 97 <3.99 <3.69 P. MALIN 12997 <3.92 <3.62

• RL = REPORTING LEVEL

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1

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

t O O O

. TABLE 15 j FISH SAMPLE ACTIVrIY IN THE VICINITY OF LtLWR l (Concentrationsin pCi/Kg) 1  ;

1 i COLLECTION DATE: SAMPLE #1 SAh&LE #2 SAMPLE #1 SAMPLE #2 SAMPLE #1 SAMPLE #2

!' FISH SPECIES: 3-26-97 3-26-97 '6-19-97 6-19-97 8-25-97 8-25-97 CARP SHEEPHEAD WALLEYE CARP WALLEYE CARP i- ISOTOPES /RL*

I Mn-54/3E4 <16.0 <18.6 <9.16 <6.27 <5.95 <4.54 I i

Co-60/1E4 <18.1 <20.1 <10.5 <734 <6.68 <5.60 t 1

i Zn-65/2E4 <41.6 <48.0 <23.8 <l 5.8 <16.8 <13.2 Cs-134/IE3 <17.1 <19.9 <938 <6.07 <6.40 <538 i t

Cs-137/2E3 <l7.4 <19.6 <6.89 <3.56 <6.45 <5.08 i i

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