ML20214L506

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Radioactive Effluent Rept for Jan-June 1986
ML20214L506
Person / Time
Site: La Crosse File:Dairyland Power Cooperative icon.png
Issue date: 06/30/1986
From: Taylor J
DAIRYLAND POWER COOPERATIVE
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
LAC-11796, NUDOCS 8609100205
Download: ML20214L506 (18)
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e RADIOACTIVE EFFLUENT REPORT FOR THE

-LA CROSSE BOIL 1NG WATER REACTOR (JANUARY 1, 1986 TO JUNE 30, 1986)

DAIRYLAND POWER COOPERATIVE Docket No. 50-409 i

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/k'V 9s WP4.17 8609100205 860630 PDR ADOCK 05000409 R PDR

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INTRODUCTION:

The La Crosse Boiling Water Reactor, also known as Genoa No. 2, is

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located on the east bank of the Mississippi River near Genoa, Vernon County, Wisconsin. The plant was designed and constructed by the Allis-Chalmers Manufacturing Company. It was completed in 1967 and has a generation capacity of 50 MW (165 MW (th)). The reactor is owned and operated by Dairyland Power Cooperative (DPC).

For the first half of 1986, the plant has had a maximum dependable capacity factor (MDC net) of 41.6%, which included a 69-day refueling outage in March / April.

The reactor went critical in July 1967 and first contributed electricity 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.

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, 1986.

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TABLE OF CONTENTS SECTION TITLE PAGE(S)

Radioactive Effluent Report 1.0 Regulatory Limits 1&2 2.0 Maximum Permissible Concentration 3 3.0 Average Energy 3 4.0 Analytical Methods 3 thru 5 5.0 Batch Releases 5&6 6.0 Abnormal Releases 6 7.0 Estimated Total Analytical Error 6 8.0 Offsite Dose Calculation Summary 14 11 WP4.17

TABLES TABLE NO TITLE PAGE(S) 1A Effluent and Waste Disposal Gaseous Effluent Release Summaries 7 IB Gaseous Effluents - Elevated Release 8&9 2A Liquid Release Summary 10 2B Liquid Effluents 11 3 Solid Waste and Irradiated Fuel Shipments 12 iii WP4.17

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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:

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 Effluent 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 3g, 131/1331 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 public from noble gases in areas beyond the Effluent Release Boundary to less than 5 mrad gamma and 10 mrad beta per calendar quarter, and less than 10 mrad l

gamma and 20 mrad beta per calendar year. The dose limits from 3H, 13I/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.

l Cumulative dose contributions from gaseous effluent releases are determined in accordance with the LACBWR Offsite Dose Calculations Manual at least once 1

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 MPC in a 168 hour0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> 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 28, 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 Effluent Release Boundary are limited to less than 1.5 mRes 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 l All solid radioactive wastes are handled in accordance with a Process Control Program as defined by LACBWR procedures in order to assure that all f applicable transportation and burial site disposal requirements are met.
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 l

used:

Tritium in Water = 3 x 10-3 pCi/ml.

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

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3. AVERAGE ENERGY l

The release rate limits for LACBWR are not based on average energy.

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4. ANALYTICAL METHODS (a) Liquid Effluents i

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

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' A composite sample is created by collecting representative aliquots of each sample from each tank batch discharged, and is analyzed monthly for Tritium, and quarterly for Iron-55 and Strontium 89 & 90. The iron and 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 Ge-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) Radiolodines Radiolodine releases are determined by Ge-Li gamma analysis of a TEDA 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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after removal.

(d) Fission and Activation Gases he gaseous releases converted into concentration (pCi/cc) are continuously sampled from the stack release flow by two stack monitors, which are inline monitors. These gas concentrations (pCi/cc) are averaged by the i 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 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 monitors indicated 1

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

(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 3H 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.

5. BATCH RELEASES (a) All airborne effluent releases at LACBWR are from a single 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: 146 (2) Total Time Period for Batch Releases: 898.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (3) Maximum Time Period for a Batch Release: 14.38 hours4.398148e-4 days <br />0.0106 hours <br />6.283069e-5 weeks <br />1.4459e-5 months <br /> (4) Average Time Period for Batch Releases: 6.17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br /> (5) Minimum Time Period for a Batch Release: 1.35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br /> (6) Average Stream Flow Rate During Periods of Release of Effluent j 3

into a Flowing Stream: 63,805 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 (b) Gaseous (1) Number of Releases: None (2) Total Activity Released: NA

7. ESTIMATED TOTAL ANALYTICAL ERROR The reported analytical results contain the following estimated errors:

Counting Error i 1 Standard Deviation Sampling Volume Error i 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 (1986)

CASEOUS EFFLUENTS - SUMMATION OF ALL R7 LEASES i

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

. 1. TOTAL RELEASE I

C1 1.67E3 8.32E2 2.50E3 j 2. AVERAGE RELEASE RATE

FOR PERIOD UCi/Sec 2.09E2 1.06E2 B. IODINE I-131
1. TOTAL 10 DINE-131 Ci 9.89E-4 6.93E-4 1.68E'3
2. AVERAGE RELEASE RATE FOR PERIOD I-131 pCi/Sec 1.26E*4 8.82E'S C. PARTICULATES
1. PARTICULATES W/ HALF-LIVES > 8 DAYS Ci 1.90E-4 1.32E34 3.22E24
2. AVERAGE RELEASE RATE FOR PERIOD UCi/Sec 2.49E*5 1.67E'S

! 3. GROSS ALPHA RADIOACTIVITY Ci 1.09E-6 7.81E-6' D. TRITIUM

1. TOTAL RELEASE Ci 4.14E0 2.56E0 6.70E0

. 2. AVERAGE RELEASE RATE FOR PERIOD UCi/Sec 5.27E*1 3.25E'1

! E. PERCE,ITACE OF TECHNICAL SPECIFICATION LIMITS I 1. NOBLE CAS RELEASE *

  • QTR QTR QTR QTR YEARLY GAMMA  % 2.94 1.89 3.80 BETA  % 1.41 0.90 1.82 l
2. 1-131, 1-133, H-3 AND ALL RADIONUCLIDES IN PARTICULATE FORM l WITH HALF-LIVES GREATER THAN 8 DAYS QTR QTR QTR QTR YEARLY l l HIGHEST ORGAN l  % 1.06 0.82 1 0.94 3
  • Totals do not include SR-89/90 results
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l TABLE IB i

EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1986)

CASEOUS EFFLUENTS - ELEVATED RELEASE CONTINUOUS MODE lNUCLIDESRELEASED l UNIT l QTR l QTR l QTR l QTR l TOTAL l 4

1. FISSION GASES i'

l- KRYPTON-85 CI - - -

KRYPTON-85M CI 8.33E1 6.01El 1.43E2 l KRYPTON-87 CI 8.39El 5.74E1 1.41E2

! KRYPTON-88 CI 1.91E2 1.15E2 3.06E2 XENON-133 C1 1.99E2 2.17E2 4.16E2 l

XENON-135 C1 1.04E3 2.94E2 1.33E3 i XENON-135M CI 8.44E0 5.68E1 6.52E1 XENON-138 CI 2.71El 2.65El 5.36El KR-89 CI - - -

l 4.25E-2

XE-133M CI 2.05E-2 2.20E-2 XE-131M C1 1.14E0 -- 1.14E0 XE-137 CI 5.95E0 5.02E0 1.10E1 AR-41 CI 3.00E1 2.93E1 5.93E1 q

CI CI TOTAL FOR PERIOD CI 1.67E3 8.61E2 2.50E3

2. 10 DINES 10 DINE-131 CI 9.89E-4 6.93E-4 1.66E-3 f 3.26E-4 9.25E-4 l' 10 DINE-133 CI 5.99E-4

, 10 DINE-135 C1 1.34E-4 9.98E-5 2.34E-4 l TOTAL FOR PERIOD CI 1.72E-3 1.12E-3 2.84E-3

, 3. SEE FOLLOWING PAGE FOR PARTICULATES.

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l TABLE IB - EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1986)

GASEOUS EFFLUENTS - ELEVATED RELEASE - (cont'd)

CONTINUOUS MODE  ;

l lNUCLIDESRELEASED l UNIT l QTR l QTR l QTR l QTR l TOTAL l

3. PARTICULATES CI 1.3.23E-6
  • CESIUM-134 CI -- 7.90E-7 7.90E-7 I CESIUM-137 CI 1.67E-5 7.21E-6 2.39E-5 BARIUM-LANTHANUM-140 C1 1.35E-4 4.23E-5 1.77E-4 l

i CO-57 C1 1.53E-6 2.09E-7 1.74E-6

, CO-58 C1 2.10E-6 6.97E-6 9.07E'6 CO-60 CI 1.62E-5 4.07E-5 5.69E-5 CE-144 C1 -- 1.52E-6 1.52E-6 CE-141 CI 1.06E-6 -- 1.06E-6 CR-51 CI -- --

MN-54 CI 5.41E-6 1.53E-5 2.07E65 J

FE-59 CI 1.01E-5 4.82E-6 1.49E-5

ZN-65 CI 8.80E-7 2.96E-6 3.84E-6 Z R-95 C1 --

NB-95 C1 2.50E-7 1.70E-6 1.9 5E-6 l

i RU-RH-106 CI 6.20E*6 4.88E-6 1.11E-5 RU-103 C1 2.20E-7 2.27E-6 2.49E-6 l '

CI l

CI CI r

l CI CI I

  • SR-89/90 analysis results are not available at this time. This report will  !

be resubmitted when these results are obtained. ,

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TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1986)

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

1. TOTAL RELEASE (NOT INCL.

TRITIUM, GASES, ALPHA) Ci 2.63E0 1.12E0 3.75E0

2. AVERAGE DILUTED CONCEN-TRATION DURING PERIOD pCi/ml 2.96E-7 1.38E-7 B. TRITIUM
1. TOTAL RELEASE Ci 3.33E1 5.14E0 3.84E1
2. AVERAGE DILUTED CONCEN-TRATION DURING PERIOD UCi/mi 3.74E-6 6.29E-7 C. DISSOLVED AND El. TRAINED CASES
1. TOTAL RELEASE Ci 1.42E-1 3.98E-2 1.82E-1
2. AVERAGE DILUTED CONCEN-TRATION DURING PERIOD DCi/mi 1.59E-8 3.64E*9 D. CROSS ALPHA RADIOACTIVITY
1. TOTAL RELEASE.-

C1 1.15E-3 1.07E-3 2.25E-3 E. VOLUME OF WASTE RELEASED Liters 9.42E5 9.92E5 1 93E6 (PRIOR TO DILUTION)

F. VOLUME OF DILUTION WATER USED DURING PERIOD Liters 8.89E9 8.139 1.71E10 G. PERCENTAGE OF TECHNICAL SPECIFICATION LIMITS FOR LIQUID RELEASES QTR QTR QTR QTR YEARLY HIGHEST ORGAN  % 29.76 24.36 27.10 WHOLE BODY  % 64.22 52.13 58.17 i

  • Does not have SR-89/90 or Fe-55 included in totals.

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TABLE 2B t

- ~ EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1986)

} LIQUID EFFLUENTS T UNIT QUARTER QUARTER QUARTER CUARTER NUCLIDES RELEASED i

$ STRONTIUM-89 CI 1.98E-3

  • CZSIUM-134 CI 1.00E-4 2.06E-4

) CI 3.62E-2 3.79E-2 CESIUM-137 10 DINE-131 CI 2.32E-2 5.26E-3 COBALT-58 CI 9.03E-2 5.82E-2 COBALT-60 CI 8.27E-1 6.78E-1 IRON-59 CI 1.01E-1 6.30E-2 ZINC-65 C1 1.48E-2 1.26E-2 MANGANESE-54 CI 2.21E-1 1.87E-1 CHROMIUM-51 CI 6.88E-2 2.12E-2 Z IRCONIUM-NIOBIUM-95 CI 1.35E-2 7.88E-3 MOLYBDENUM-99 CI 2.51E-2 6.21E-3

) TECHNETIUM-99M CI 6.05E-2 8.02E-3 BARIUM-LANTHANUM *140 CI 5.30E-2 8.08E-3 j

j CERIUM-141 C1 4.29E-3 1.54E-3 CE-144 CI 4.58E-3 2.25E-3 CO-57 C1 1.07E-3 4.27E-4 1-133 CI 6.02E-2 9.40E*3 1 1-135 C1 3.35E*2 1.85E-3 NP-239 C1 3.32E-2 2.49E-3 J

RU-103 C1 1.42E-2 4.28E'3 RU-RH-105 CI 3.59E-2 5.86E-3 RU-RH-106 CI 4.74E-3 6.46E*4 SR-91 CI 1.97E-2 1.03E-3 SR-92 C1 4.41E-3 3.06E-4 AG-110M CI 3.66E-3 7.72E-4 i NB-97 CI 6.27E-3 1.78E-4 NA-24 CI 9.26E-4 4.00E-5 Z R-9 7 C1 1.19E-4 --

MN-56 CI 5.12E-5 --

! I-132 CI 9.55E-4 --

! W-187 C1 1.70E-2 --

Y-92 CI 9.11E-2 --

) CI 1.09E-3 --

CE-143 CS-136 CI 4.54E-3 --

CI 7.54E-1 *

' FE-55 TOTAL FOR PERIOD (ABOVE) CI 2.63E0 1.12E0 l

XENON-133 CI 1.21E-2 2.23E-3 l 2.12E-3 XENON-135 CI 3.03E'2 XE-131M CI 3.74E-2 7.82E*3 XE-133M CI 9.77E-5 3.54E-5 1

XE-135M CI 7.89E-3 --

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) KR-85M CI 5 17E-5 9.51E*6 -

I KR-87 CI -- 1.17E-5 CI

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  • SR-89/90 and Fe-55 analysis results are not available at this time. The report will be resubmitted when these rseults are obtained.

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l TM LE 3 EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1986)

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

1. TYPE OF WASTE UNIT PERIOD PERIOD TOTAL i a. SPENT RESINS, FILTER SLUDGES, m3 4.81 4.81 j EVAPORATOR BOTTOMS, ETC. Ci 7.78 El 7.78 E1

! b. DRY COMPRESSIBLE WASTE,CONTAMI- m3 NATED EQUIPMENT, ETC. Ci

c. IRRADIATED COMPONENTS, CONTROL m3 RODS, ETC. Ci
d. OTHER (DESCRIBE) m3 Ci 4

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2. ESTIMATE OF MAJOR NUCLIDE COMPOSITION Activity (Ci)

(BY TYPE OF WASTE) 6-MONTH 6-MONTH PERCENT PERIOD PERIOD I= 5.93 4.61

a. Mn-54 Fe-59 5.36E-1 4.17E-1 Co-58 1.17 9.07E-1
Co-60 6.00E+1 4.67El l Zn-65 5.28E-1 4.llE-1 Cs-137 9.27E-1 7.21E-1 H-3 5.28E-3 4.llE-3 C-14 1.29E-2 1.00E-2 ,

i Fe-55 2.49El 1.94El l Ni-59 5.66E-2 4.40E-2 i Ni-63 4.95 3.85 i S r-89 1.74E-1 1.35E-1 Sr-90 4.llE-1 3.20E-1

! Tc-99 5.99E-5 4.66E-5

! I-129 2.92E-3 2.27E-3 U-235 2.43E-6 1.89E-6

. U-238 2.06E-6 1.60E-6

Pu-239/240 4.45E-3 3.46E-3 Pu-241 3.53E-1 2.75E-1 An-241 3.20E-3 2.49E-3 l Co-242 1.79E-2 1.39E-2 j Co-243/244 1.40E-3 1.09E-3 j Pu 238 7.92E-3 6.16E-3 1

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TABLE 3 - (cont'd)

EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT (1986) 1 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS

3. SOLID WASTE DISPOSITION NO. OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION 4

1 SOLE TRANSPORT BARNWELL, SC i

B. IRRADIATED FUEL SHIPMENTS (DISPOSITION)

NO. OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION NONE i

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D DA/RYLAhfD hh/a/[ COOPERATIVE . P O box 817 2615 EAST AVE. SO . LA CRO (608) 788-4000 JAMES W. TAYLOR August 27, 1986 General Manager In reply, please refer to LAC-11796 DOCKET No. 50-409 PRIORITY sculleE jrtrat SJti1RL

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Jii5 ML Mr. James G. Keppler, Regional Administrator eg' f / -dss DRRA oi 0:

U. S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137

SUBJECT:

DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)

PROVISIONAL OPERATING LICENSE NO. DPR-45 RADI0 ACTIVE EFFLUENT REPORT FOR THE PERIOD JANUARY THROUGH JUNE 30, 1986

Dear Mr. Keppler:

In accordance with 10 CFR 50,36a(a)(2), this letter serves to transmit to you the Radioactive Effluent Report for the La Crosse Boiling Water Reactor (LACBWR) for the period January 1 through June 30, 1986.

If you have any additional questions, please contact us.

Sincerely, 4kl. 'U2D r

JWT:LLN:dh Enclosures

/

cc - Mr. James M. Taylor (10 copies) /

Document Control Desk (3 copies)

NRC Resident Inspector NRC Project Manager (J. Stang) hg D. Sherman, ANI Library I WP4.17 t

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