Text

Revised Radioactive Effluent Rept for Jan-June 1985
	ML20133D021
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	06/30/1985
From:	; DAIRYLAND POWER COOPERATIVE
To:	;
Shared Package
ML20133D011	List: ML20133D008; ML20133D021;
References
	NUDOCS 8510070562
	Download: ML20133D021 (18)
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i REVISED RADI0 ACTIVE EFFLUENT REPORT FOR THE LA CROSSE BOILING WATER REACTOR (JANUARY 1, 1985 TO JUNE 30, 1985)

DAIRYLAND POWER COOPERATIVE l Docket No. 50-409 4

I 8510070562 850925 PDR ADOCK 05000409 R PDR WP4.17 1

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INTRODUCTION:

The La Crosse Boiling Water Reactor, also known as Genoa No. 2, is l located on the east bank of the Mississippi River near Genoa, Vernon County, Wisconsin. The plant was designed and constructed by the Allis-Chalmera Manufacturing Company. It was completed in 1967 and has a 1 generation capacity of 50 MW (165 MW (th)). The reactor is owned and i

operated by Dairyland Power Cooperative (DPC).

For the first half of 1985, the plant has had a maximum dependable capacity factor (MDC net) of 64.6%, which included a 39 day refueling outage in March / April.

i The reactor went critical in July 1967 and first contributed electricity i'

to DPC's system in April 1968. After completing full power tests in August 1969, the plant has been operating between 60% and 100% full

power, with the exception of plant shutdowns for maintenance and repair.

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In accordance with LACBWR Technical Specifications 6.9.3.a. and in

} compliance with 10 CFR 50.36a(a)(2), this document is the Radioactive

] Effluent Report for the period January 1 through June 30, 1985.

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TABLE OF CONTENTS SECTION TITLE PACE (S)

Radioactive Effluent Report 1.0 Regulatory Limits 1 2.0 Maximum Permissible Concentration 2 3.0 Average Energy 2 4.0 Analytical Methods 2&3 5 .0 Batch Releases 3&4 6.0 Abnormal Releases 4 7.0 Estimated Total Analytical Error 4 11 WP4.17 ..

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QB,LJE,S, TABLE NO TITLE PACE (S)

'1A Effluent and Waste Disposal Gaseous Effluent Release Summaries 5 kB Gaseous Effluents - Elevated Release 6&7 2A Liquid Release Summary 8 2B Liquid Effluents 9 3 Solid Waste and Irradiated Fuel Shipments 10 & 11 1

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RADIDACTIVE EFFLUENT REPORT WP4.17

I i EFFLUENT AND WASTE DISPOSAL REPORT (Supplemental Information)

FACILITY Lacrosse Boiling Water Reactor LICENSEE DAIRYLAND POWER COOPERATIVE DOCKET NO. 50-409

1. REGULATORY LIMITS

a. Gaseous Effluent Release Limits:

T LACBWR's Technical Specifications for gaseous effluent releases of radioactive material limit the release rates, of the sum of the individual radionuclides, in Curies per second, so that the dose rates to members of the public beyond the Ef fluent Release Boundary do not exceed 500 mrem / year to the whole body, 3000 mrem / year to the skin from noble gases, and 1500 mrem / year to a critical organ from 3H, 131/133I and particulates with half-lives greater than 8 days.

Also, in accordance with 10CFR50, Appendix I, the Technical Specifications for gaseous effluent radioactive material limit the air dose to a member of the 3

public from noble gases in areas beyond the Effluent Release Boundary to less i

than 5 mrad gamma and 10 mrad beta per calendar quarter, and less than 10 mrad gamma and 20 mrad beta per calendar year. The dose limits from 3H, 131/1331 and particulates with half lives greater than 8 days are less than 7.5 mrem per i

calendar quarter, and less than 15 mrem per calendar year to any organ.

I Cumulative dose contributions from gaseous effluent releases are determined in accordance with the LACBWR Offsite Dose Calculations Manual at least once

, each 31 days.

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b. Liquid Effluent Release Limits:

LACBWR's Technical Specifications limits for liquid effluent releases are limited to those concentrations of individual radionuclides such that the diluted discharge does not exceed 1 MFC in a 168 hour0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months week averaged over the calendar year. For dissolved or entrained noble gases, the concentration is limited to a total activity concentration of 2 x 10-4 pCi/ml. For alpha emitting radionuclides, the concentration is limited to a total activity concentration of 4.9 x 10-9 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 Effluents, are based on dilution with the combination of LACBWR and Genoa #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.

Also, in accordance with 10CFR50, Appendix I, the dose commitment to a member of the public from radioactive materials released in liquid effluents to areas beyond the Ef fluent 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 critical ingestion pathway.

Cumulative quarterly and annual dose contributions from liquid effluent releases are determined for the adult fish ingestion pathway in accordance with the LACBWR Offsite Dose Calculation Manual at least once each 31 days.

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! c. Solid Radioactive Waste 1

i i All solid radioactive wastes are handled in accordance with a Process Control Program as defined by LACBWR procedures in order to assure that all I applicable transportation and burial site disposal requirements are met.

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, 2. MAXIMUM PERMISSIBLE CONCENTRATION (MPC)

The MPC used to calculate permissible release rates are obtained from 10 CFR 20, Appendix B Tables I and II. In addition, the following values are used:

! Tritium in Water = 3 x 10-3 Ci/ml.

Tritium in Air = 2 x 10-7 pCi/cc.

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3. AVERAGE ENERGY The release rate limits for LAC 3WR are not based on average energy.

4. ANALYTICAL METHODS (a) Liquid Effluents Liquid effluent measurements for gross radioactivity are performed by Ge-Li gamma isotopic analysis of a representative sample from each tank discharged.

A composite sample is created by collecting representative aliquots of each sample f rom each tank batch discharged, and is analyzed monthly for Tritium, and quarterly for Strontium 89 and 90. The radiostrontiums are analyzed by a contractor. In addition, each batch discharged tank is analyzed for alpha activity concentration. ,

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(b) Airborne Particulates Airborne particulate releases are determined by Ce-Li gamma isotopic analysis. This analysis is performed by analyzing a glass fiber filter paper taken from the stack monitor (Eberline SPING) which continuously isokinetically samples and monitors the stack effluent. This filter is changed and analyzed on an approximate weekly basis and analyzed within 7 days after removal. This filter is also analyzed for alpha activity. A quarterly composite of these filters is sent to a contractor for Sr 89 and 90 analysis.

(c) Radioiodines Radioiodine releases are determined by Ge-Li gamma analysis of a TEDA i

impregnated activated charcoal cartridge taken from the stack monitor which continuously isokinetically samples and monitors the stack effluent. This charcoal cartridge is changed approximately weekly and analyzed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months i

after removal.

(d) Fission and Activation Gases The gaseous releases converted into concentration (uCi/cc) are continuously sampled from the stack release flow by two stack monitors, which are inline monitors. These gas concentrations (UCi/cc) are averaged by the monitors microprocessor and flowrate/ pressure compensated to obtain the daily

! gaseous release of the plant. A monthly grab gas sample is taken from a stack monitor. This sample is collected in a 3.7 liter gas Marinelli and gamma analyzed on the Ge-Li detector to determine the isotopic composition of the gaseous release mixture and the gaseous concentration to verify the stack WP-4.17 l

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l monitors indicated gaseous concentration (uC1/cc). The Marinelli isotopic concentration fractions are then multiplied times the daily total gaseous releases to determine the individual gaseous isotopic release concentration.

4 (e) Tritium Tritium releases are determined by taking a grab sample of the stack atmosphere at the effluent of the stack monitor. Tritium, as tritiated water, is removed from the sample stream by condensation, using a cold trap containing

- an organic compound and dry ice. The condensed water vapor is then distilled and the distillate is analyzed for 3R 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.

4 5. BATCH RELEASES (a) All airborne effluent releases at LACBWR are from a single i

Continuous-Elevated Release Point.

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(b) Liquid - All liquid effluent releases at LACBWR are batch releases.

This is summarized as follows:

(1) Number of Batch Releases: 92 (2) Total Time Period for Batch Releases: 573.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (3) Maximum Time Period for a Batch Release: 15.38 hours4.398148e-4 days 0.0106 hours 6.283069e-5 weeks 1.4459e-5 months

(4) Average Time Period for Batch Releases: 6.30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months 0.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months (5) Minimum Time Period for a Batch Releass:

(6) Average Stream Flow Rate During Periods of Release of Effluent 3

i into a Flowing Stream: 57,713 ft /sec

6. ABNORMAL RELEASES - There were no abnormal releases of radioactivity in plant effluents as summarized as follows:

(a) Liquid (1) Number of Releases: None (2) Total Activity Released: NA 4

(b) . Gaseous (1) Number of Releases: None (2) Total Activity Released: NA

7. ESTIMATED TOTAL ANALYTICAL ERROR i

The reported analytical results contain the following estimated' errors:

Counting Error j;l Standard Deviation i

Sampling Volume Error j; 5%

The lower limits of detection (LLD) are expressed in terms of a 4.66 o as defined in Technical Specifications.

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TABLE 1A EFFLUENT AND WASTE DISPOSAL REPORT (1985)

GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES l l UNIT l QTR l QTR l QTR l QTR l TOTAL l A. FISSION & ACTIVATION GASES

1. TOTAL RELEASE C1 1.72E3 2.39E3 4.11E3

2. AVERAGE RELEASE RATE FOR PERIOD UCi/Sec 2.21E2 3.04E2

3. PERCENT OF TECHNICAL SPECIFICATION GAMMA DOSE LIMIT % 2.21El 2.68E1 B. IODINE I-131

1. TOTAL 10 DINE-131 Ci 6.18E-4 8.61E-4 1.48E-3

2. AVERAGE RELEASE RATE FOR PERIOD I-131 uCi/Sec 7.84E-5 1.12E-4 C. PARTICULATES

1. PARTICULATES W/ HALF-LIVES > 8 DAYS C1 2.73E-4 3.30E-4 6.03E-4

2. AVERAGE RELEASE RATE FOR PERIOD UCi/Sec 3.46E-5 4.19E-5

3. GROSS ALPHA RADIOACTIVITY C1 4.57E-6 2.19E-5 D. TRITIUM

1. TOTAL RELEASE Ci 2.72E0 5.92E0 8.64E0

2. AVERAGE RELEASE RATE FOR PERIOD UCi/Sec 3.45E-1 7.53E-1 E. H-3, I-131/133 & PARTICULATES PERCENT OF TECHNICAL SPECIFICATION DOSE LIMIT % 2.60E-1 1.49E0 WP4.17

TABLE IB EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1985)

GASEOUS EFFLUENTS - ELEVATED RELEASE CONTINUOUS MODE lNUCLIDESRELEASED I UNIT l QTR l QTR l QTR l QTR l TOTAL l

1. FISSION GASES KRYPTON-85 CI KRYPTON-85M CI 6.92E1 1.15E2 1.84E2 KRYPTON-87 CI 8.27El ,1.09E2 1.92E2 KRYPTON-88 CI 1.95E2 2.82E2 4.77E2 XENON-133 CI 2.37E2 2.40E2 4.77E2 XENON-135 CI 1.09E3 1.36E3 2.45E3 XENON-135M CI 2.31El 8.10E1 1.04E2 XENON-138 CI 2.45El 6.49El 8.94E1 KR-89 CI XE-133M CI 3.00E-2 4.92E-2 7.92E-2 XE-131M CI

3.83E2 3.83E2 XE-137 CI 2.48E0 1.44E1 1.69El AR-41 CI

1.38E1 1.38E1 CI CI TOTAL FOR PERIOD CI 1.72E3 2.66E3 4.38E3

2. 10 DINES 10 DINE-131 CI 6.18E-4 8.61E-4 1.48E-3 10 DINE-133 CI 3.71E-4 1.04E-3 1.41E-3 10 DINE-135 CI 1.48E-4 1.55E-/. -

3.03E-4 TOTAL FOR PERIOD CI 1.14E-3 2.06E-3 3.20E-3 l

3. SEE FOLLOWING PAGE FOR PARTICULATES.

Indicates none detected or less than LLD i

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I TABLE IB - EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1985)

GASEOUS EFFLUENTS - ELEVATED RELEASE - (cont'd)

CONTINUOUS MODE lNUCLIDESRELEASED l UNIT l QTR l QTR l QTR l QTR l TOTAL l

3. PARTICULATES STRONTIUM-89 CI 7.17E-6 7.14E-6 1.43E-5 STRONTIUM-90 CI

7.51E-7 7.51E-7 CESIUM-134 CI CESIUM-137 CI 2.37E-5 8.55E-6 3.23E-5 BARIUM-LANTHANUM-140 CI 1.81E-4 1.94E-4 3.75E-4 CO-57 CI 6.00E-8 2.00E-7 2.60E-7 CO-58 CI 1.00E-6 4.70E-6 5.70E-6 CO-60 CI 4.24E-5 6.48E-5 '

1.07E-4 CE-144 CI

6.80E-6 L 6.80E-6 CE-141 CI 2.42E-6 1.0 7 E-6 3.49E-6 CR-51 CI 1.93E-6

1.93E-6 MN-54 CI 9.33E-6 2.15E-5 3.08E-5 CI * *

FE-59 l ZN-65 CI

4.62E-6 4.62E-6 ZR-95 CI 1.77E-6 1.30E-6 3.07E-6 NB-95 CI 2.16E-6 3.14E-6 1 5.30E-6 RU-RH-106 CI

1.01E-5 n 1.01E-5 RU-103 CI 3.80E-7 9.30E-7 1.31E-6 CI CI CI CI CI l

Indicates none detected or less than LLD WP4.17

TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1985)

LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES l UNIT l QTR l QTR l QTR I QTR l TOTAL l A. FISSION AND ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCL.

TRITIUM, CASES, ALPRA) Ci 4.55E-1 6.36E-1 1.09

2. AVERAGE DILUTED CONCEN-TRATION DURING PERIOD UCi/mi 3.82E-10 9.45E-9

3. PERCENT OF MPC LIMIT % 5.19E-2 6.03E-2 B. TRITIUM

1. TOTAL RELEASE Ci 2.73E1 1.68E1 4.41El

2. AVERAGE DILUTED CONCEN-TRATION DURING PERIOD uCi/ml 4.56E-7 2.50E-7

3. PERCENT OF MPC LIMIT % 1.52E-2 8.33E-3 C. DISSOLVED AND ENTRAINED CASES

1. TOTAL RELEASE C1 2.29E-2 9.19E-3 3.21E-2'

2. AVERAGE DILUTED CONCEN-TRAT10N DURING PERIOD uC1/ml 3.82E-10 1.37E-10

3. PERCENT OF MPC LIMIT % 1.27E-2 4.57E-2 D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE Ci 3.02E-4 2.09E-3 2.39E-3 E. VOLUME OF WASTE RELEASED (PRIOR TO DILUTION) Liters 5.83E5 7.20E5 1.30E6 F. VOLUME OF DILUTION WATER USED DURING PERIOD Liters 6.00E10 6.71E10 1.27E11 l WP4.17 l

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TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1985)

LIQUID EFFLUENTS NUCLIDES RELEASED UNIT QUARTER QUARTER QUARTER QUARTER STRONTIUM-89 CI 7.00E-4 6.48E-4 STRONTIUM-90 CI 1.69E-3 1.22E-3 CESIUM-134 CI 9.50E-4 1.66E-3 CESIUM-137 CI 2.39E-2 3.66E-2 10 DINE-131 CI 1.27E-2 4.54E-2 COBALT-58 CI 8.33E-3 7.80E-3 COBALT-60 CI 2.50E-1 3.71E-1 IRON-59 CI 1.64E-3 4.48E-3 ZINC-65 CI 3.32E-3 3.04E-3 MANGANESE-54 CI 3.84E-2 4.67E-2 CHROMIUM-51 CI 6.71E-3 2.28E-3 ZIRCONIUM-NIOBIUM-95 CI 1.17E-3 1.73E-3 MOLYBDENUM-99 CI 4.99E-3 9.53E-4 TECHNETIUM-99M CI 1.57E-2 5.69E-3 BARIUM-LANTHANUM-140 CI 2.llE-2 5.67E-3 CERIUM-141 CI 3.91E-4 4.67E-4 CE-144 CI 1.40E-3 6.34E-4 CO-57 CI 4.42E-4 1.01E-4 I-133 C1 2.31E-2 1.31E-2 1-135 CI 1.00E-2 4.51E-3 NP-239 CI 1.36E-2 7.13E-4 RU-103 CI 9.65E-4 7.19E-2 RU-RH-105 CI 2.41E-3 1.20E-3 RU-RH-106 CI 6.40E-4 3.04E-3 SR-91 CI 5.38E-3 1.52E-3 SR-92 CI 1.09E-3 5.51E-4 I-132 CI 3.41E-4 2.21E-4 NA-24 CI 2.02E-4 1.29E-5 W-187 CI 1.99E-4

AG-110M CI 2.79E-4 1.33E-3 ZR-97 CI 2.732-5 4.89E-5 CS-136 CI 1.83E-4

CL-38 CI 1.82E-5

NB-97 CI 1.46E-3 3.24E-3 BA-139 CI 3.24E-5 l6.60E-4 MN-56 CT 3.23E-5 15.10E-5 Y-92 CI 1.50E-3 i

lTOTALFORPERIOD(ABOVE) CI 4.55E-1 16.36E-1 XENON-133 CI 7.78E-3 2.04E-3 XENON-135 CI 1.10E-2 4.60E-3 XE-131M CI

1.10E-3 XE-133M CI 3.86E-5 1.46E-5 XE-135M CI 4.60E-3 1.32E-3 KR-85M CI 3.22E-6 1.82E-5 KR-87 CI 5.62E-5 1.0 7 E-4 KR-88 CI 1.60E-5 *

Indicates none detected or less than LLD WP4.17

TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1985)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) 6-MONTH 6-MONTH UNIT PERIOD PERIOD TOTAL

1. TYPE OF WASTE

a. SPENT RESINS, FILTER SLUDGES, m 3

9.63 9.63 EVAPORATOR BOTTOMS, ETC. Ci 1.76 E2 1.76 E2

b. DRY COMPRESSIBLE WASTE,CONTAMI- m* --

NATED EQUIPMENT, ETC. Ci --

c. IRRADIATED COMPONENTS, CONTROL m* --

RODS, ETC. Ci 3 --

d. OTHER (DESCRIBE) m --

l C1 --

l l Activity (C1)

2. ESTIMATE OF HAJOR NUCLIDE COMPOSITION 6-MONTH 6-MONTH PERCENT PERIOD PERIOD (BY TYPE OF WASTE)

a. Mn-54 7.10E0 1.25El Co-57 1.18E-2 2.07E-2 Co-60 4.71El 8.29El Zn-65 1.37E0 2.41E0 Cs-137 9.20E0 1.62El Ce/Pr-144 1.78E-1 3.14E-1 H-3 5.14E-3 9.05E-3 C-14 1.22E-2 2.15E-2 Fe-55 2.64El 4.65El Ni-59 5.63E-2 9.91E-2 Ni-63 4.8150 8.46E0 Sr-90 3.87E-1 6.81E-1 Tc-99 5.91E-5 1.04E-4 U-235 7.95E-7 1.40E-6 U-238 6.70E-7 1.18E-6 Pu-238 7.50E-3 1.32E-2 Pu-239/240 4.20E-3 7.v)E-3 Pu-241 3.36E-1 5.91E-1 An-241 3.20E-3 5.63E-3 Cm-242 1.70E-2 3.00 E-2 Cm-244/243 1.48E-3 2.61E-3 Fe-59 9.83E-2 1.73E-1 N b-95 2.31E-2 4.06E-2 Ru-103 1.76E-2 3.09E-2 l

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TABLE 3 - (cont'd)

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1985)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS

2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION (BY TYPE OF WASTE)

ACTIVITY (CI) 6-MONTH 6-MONTH PERCENT PERIOD PERIOD Cs-134 5.68E-1 1.00E0 Ce-141 1.59E-2 2.80E-2 S r-89 1.64E-1 2.88E-1 1-129 2.75E-3 4.84E-3 C o-58 1.66E0 2.93E0

3. SOLID WASTED DISPOSITION NO. OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION 2 SOLE USE BARNWELL, SC B. IRRADIATED FUEL SHIPMENTS (DISPOSITION)

NO. OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION NONE l

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ML20133D021

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