ML20028G792

Semiannual Radioactive Effluent Rept for LACBWR,Jan-June 1990

ML20028G792
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	06/30/1990
From:	Berg W DAIRYLAND POWER COOPERATIVE
To:	Davis A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
LAC-12958, NUDOCS 9009040167
Download: ML20028G792 (17)

Text

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• 3200EASMVE.SO.
• RO. BOX 817
• LACROSSE, WISCO (608) 788-4000 FAX NO. (608) 7871420 WILLIAM L. BEHG Generamanager August 14, 1990 In reply, please refer to LAC-12958 DOCKET NO. 50-409 L

) Mr. A. Bert Davis, Regional-Administrator U. S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137

SUBJECT:

Dairyland Power Cooperative La Crosse Boiling Water Reactor (LACBWR) l Possession-only License No. DPR-45 Semi-Annual Radioactive Effluent Report For the period January 1 tk. rough a2ne 30, 1990 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, 1990. i If you have any questions, please contact us. Sincerely, DAIRYLAND POWER COOPERATIVE NWb l-William L. Berg, neral Manager l WLB:LLNidh Enclosure cc - Mr. James M. Taylor (10 copies) Document Control Desk (3 copies) NRC Project Manager (P. Erickson) D. Sherman, ANI Library Don llendrikse, Wisc. Div. of !!calth 03103 l 00,o40167 900530, //j eDs nDocx 0s00040 R PDC 1

d. mm r. RADIOACTIVE EFFLUENT REPORT FOR THE-LA CROSSE BOILING WATER REACTOR ~ (JANUARY 1, 1990 TO JUNE 30, 1990) DAIRYLAND POWER COOPERATIVE Docket No. 50-409 5 ' " ' ' ' ' = =

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.'7 TABLE OF CONTENTS j TITLE PAGE Radioactive Effluent Repon Introduction 1 Regulatory Limits 2 Maximum Permissible Concentration 4 4 Average Energy Analytical Methods 4 Batch Releases 6 Abnormal Releases 7 Estimated Total Analytical Error 7 Offsite Dose Calculation Summary 13 l I -l l [ 11 i I

- 4 t .3. 'i 4 TABLES ' TABLE No. TITLE PAGE 1A Effluent and Waste Disposal Gaseous Effluent Release Summaries 8 ' Gaseous Effluents - Elevated Release .9 1B .i 10-2A Liquid Release Summary 2B Liquid Effluents 11 3 Solid Waste and Irradiated fuel 12-Shipments i-m l 1 111 l l l 2 a

I 4 7 r i INTRODUCTION: 1 The La Crosse Boiling Water Reactor (LACBWR), also known as Genoa Station No. 2. is 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 had a generation capacity of 50 MW (165 MW(th)). The react',r is owned by Dairyland Power Cooperative (DPC). 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 t 1969, the plant operated between 60% and 100% full power, with the exception of plant shutdowns for maintenance and repair. i In April of 1987 plant operation was ceased. The reactor is presently defueled and work is progressing to place the plant'into a SAFSTOR mode. In August of 1987 a possession-only license was received. In accordance with LACBWR Technical Specifications 6.9.3.a & 6.9.3.b and in compliance with 10 CFR 50.36a(n)(2), this document is the Radioactive Effluent Report for the period January 1 through June 30, 1990.. - -

EFFLUENT AND WASTE DISPOSAL REPORT -(Supplemental Information) FACILITY: Lacrosse Boiling Water Reactor LICENSEE: DAIRYLAND POWER COOPERATIVE DOCKET NO. 50-409 t 1. REGULATORY LIMITS a. Gaseous Effluent Release Limits: LACBWR's Technical Specifications for gaseous effluet ; 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 H-3. I-131/133 and particulates with half-lives greater than 8 days. Also, in accordance with 10 CFR 50, Appendix I, the Technical Specifications for gaseous effluent radioactive material limit the air dose to a mcaber of the public from noble gases in areas beyond the Eff1.uer.c Release Boundary to less 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 H-3 I-131/133 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. Cumulative dose contributions from gaseous effluent releases are determined in accordance with the LACBWR Offsite Dose Calculations Manual. 2

T. -b. 1.iquid Ef fluent Release Limits: LACBWR's Technical Specifications limits for liquid effluent releases are limited to those concer.trations of individual radionuclides such that the diluted discharge does not exceed 1 HPC in aE168-hour week averaged over the calendar year. Fe-dissolved or entrained noble. gases, the concentration is limited to a total activity concentration of 2 x 10'" pC1/ml. For alpha emitting radionuclides, the concentration.is limited.to a total activity concentration of 4.9 x 10 pCi/ml, based upon an actual alpha emitting reiionuclide 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 Station 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. Also, in accordance with 10 CFR 50, Appendix I, the dose commitment 3 member of the public from radioactive materials released in liquid. o. effluents to areas beyond the Effluent 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. c. Solid Radioactive Waste All solid radioactive wasten are handled in accordance with a Process Control Program as defined by LACBWR proceduros in order to assure that all applicable transtortation and burial site disposal requirements are mot. 2. MAXIMUM PERMISSIBLE CONCENTRATION (MPC) The MPC used to calculate permissible release rates atti obtained from 10 CFR 20. Appendix B. Tables I and II. In addition. the following values are used: Tritium in Water = 3 x 10'8 pC1/ml. Tritium in Air = 2 x 10*' pCi/cc. 3. AVERAGE ENERGY The releasn rate limits for LACBWR are not based on average energy. l i l 4. ANALYTICAL METil0DS a. Liquid Effluents Liquid effluent measurements for gross radioactivity are performed by Go-Li gamma isotopic analysis of a representative sample from each tank discharged. A composite sample is created by collecting representative aliquots of each sample from each tank batch discharged, and is analyzed nionthly 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. --

bb-l b. Airborne particulates Airborne particulate releases are determined by Go-Li gamma isotopic analysis. This analysis is performed by analyzing a glass i 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 i analyzed within 7 days after removsl. 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. Radiofocines Radiciodine releases are detertined by Ge-Li gamma analysis of a TEDA impregnated activated charcoal cartridge taken from the stack i monitor which continuously isokinetically samples and monitors the stack effluent. This charcoal cartridge is changed approximately weekly and analyzed within 48 hours after removal. Since the plant shutdown in l April 1987, the I-131/I-133 have decayed completely to stable elements, d. Fission and Activation Gasos The 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/ce) are averaged by the monitors microprocessor and flowrate/ pressure compen-sated to obtain the daily gaseous release of the plant. Since the plant shutdown in April 1987. gaseous releases have been immeasurable. All fission gases except Kr-85 have decayed completely to stabic elements. - -

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 H-3 concentration, pCi/cc, 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 l 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. l l 5. RATCH RELEASF4 a. Airborne All airborne effluent releases at LACBWR are from a single Continuous-Elevated Release Point. b. Liquid 1 All liquid effluent releases at LACBWR are batch releases. This is summarized as follows: l l i 1 l l l i ? 1

-{ L-i (1) Number of Batch Releases: 17 i (2) Total Time Period for Batch Releases: 120.9 hours j i (3) Maximum Time Period for a Batch Palease: 15 hours (4) Average Time Period for Batch Releases: 7.07 hours (5) Minimum Time Period for a Batch Release 3.0 hours (6) Average Stream Flow Rate During Periods 8 of Release of Effluent into a Flowing Stream: 32.233 ft /sec l 6. gNORMAL REs. EASES There were no abnormal releases of radioactivity in plant effluents as sununarized as follows: a.- Licuid (1) Number of Releases: None (2) Total Activity Released: N/A b. Gaseous (1) Number of Releases None (2) Total Activity Released: N/A 7. ESTIMATED TOTAL ANALYTICAL ERROR The reported analytical results contain the following estimated errors: Counting Error i 1 Standard Deviation Sampling Volume Error 1 5%. The lower limits of detection (LLD) are expressed in terms of a 4.66 o l as defined in Technical Specifications. i

TABLE 1A EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT - 1990 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES UNIT QTR QTR ! QTR ! QTR ! TOTAL l A. FISSION & ACTIVATION GASES

1. TOTAL RELEASE j

l Ci 0.00 0.00 ' O.00 l

2. AVERAGE RELEASE RATE l

[ FOR PERIOD pCi/Sec i 0.00 ' O.00 B. IODINE I-131 l 1. TOTAL 10 DINE-131 l l l l l Ci O.00 0.00 ! 0.00 l 2. AVERAGE RELEASE RATE l l l FOR PERIOD 1 pCi/See ', 0.00 1 0.00 ! j i C. PARTICULATES l 1. PARTICULATES W/KALF-l l l L j l l LIVES > 8 DAYS Ci '1.77E-4' 9.59E-7' l1.78E-4l l 2. AVERAGE RELEASE RATE l l l FOR PERIOD ! pC1/See l 2.25E-Si l.22E-7l l l l 3. GROSS ALPHA l ' S.91E-7' 1.79E-7! i j RADIOACTIVITY Ci D. TRITIUM l l l 1. TOTAL RELEASE l l 1 .t l Ci !9.16E-2 4.82E-2 1.40E-lj l 2. AVERAGE RELEASE RATE l l l l FOR PERIOD ! pC1/Sec 11.18E-2! 6.13E-3' l E. PERCENTAGE OF (APPENDIX I) TECHNICAL SPECIFICATION LIMITS 1. NOBLE GAS RELEASE QTR QTR l QTR ! QTR YEARLY l l GAMMA 0.00 0.00 1 0.00 l l BETA 1 1 0.00 l 0.00 l l 0.00 l 2. I-131, I-133. H-3. AND ALL RADIONUCLIDES IN PARTICULATE FORM WITH HALF-LIVES GREATER THAN 8 DAYS QTR OTR l QTR ! QTR ! YEARLY l l HIGHEST ORGAN l !1.21E-2!1.79E-31 l6.96E-3l.

l I I TABLE 1B EFFLUENT AND WASTE DISPOSAL SD41-ANNUAL REPORT - 1990 1 GASEOUS EFFLUENTS - ELEVATE 1; RELEASE i 1 l CONTINUOUS MODE l NUCLIDES RELEASED ! INIT ! QTR ! QTR ! QTR QTR ! TOTAL l 1. FISSION GASES 0.00 l KRYPTON-85 C1 l KRYPTON-85M Ci 0.00 l KRYPTON-87 Ci O.00 l KRYPTON 88 Ci O.00 l XENON-133 Ci O.00 l XENON-135 C1 0.00 l. XFRON-135M l Ci 0.00 XENON-138 Ci 1 O.00 ( Ci l 1 i Ci Ci Ci i T0_TAj d OR PERIOD Ci ! 0.00 ! 0.00 t O.00 2. 10 DINES l IODINE-131 Ci } ' O.00 10 DINE-133 Ci O.00 I 10 DINE-135 Ci O.00 TOTAL FOR PERIOD Ci ! 0.00 0.00 0.00 0.00 0.00 3. PARTICULATES l l STRONTIlN-89 Ci 1.75E-4' l_ STRONTIlN ! Ci l CESIlN-134 C1 l l l l CESIIN-137 Ci 1.05E-7 1.00E-7 { BARIlN-LANTHANIN-140 ! Ci l COBALT-60 Ci 1.087E-6,8.59E-7 l MANGANESE-54 Ci 12.15E-81 l l_ COBALT-58 l Ci ! 1 E-8 ! i j ZINC-65 Ci ll.73E-7! Ci l l l l Ci l l l l Ci l l l .g.

4 e L TABLE 2A EFFLUENT AND WASTE DISPOSAL SFNI-ANNUAL REPORT - 1990 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES l UNIT QTR l QTR QTR QTR ! TOTAL _l l _ A. FISSION & ACTIVATION PRODUCTS l 1. TOTAL RELEASE (NOT INCL l l l l l l l TRITIUM, GASES. ALPHA) ! Ci 1.30E-2!2.28E-2! 13.31E-2l l l l l l 2. AVERAGE DILUTED CONCEN-! l TRATION DURING PERIOD lpci/ml !7.52E-9!1.56E-8! l B. TRITIUM

1. TOTAL RELEASE l

l l l l l l ' Ci !9.99E-2! 1.07 11.17E0 l

2. AVERAGE DILUTED CONCEN.

j j j j i TRATION DURING PERIOD ;pCi/ml !7.29E-8!7.33E-7', l C. DISSOLVED AND ENTRAINED GASES l

1. TOTAL RELEASE l

j j Ci 0.00 0.00 ! O.00 ) 2. AVERAGE DILUTED CONCEN i l j i j TRATION DURING PERIOD fpCi/ml ! 0.00 ! 0.00 ! D. GROSS ALPHA RADI0 ACTIVITY l

1. TOTAL RELEASE l

l l l l l ! _ Ci 6.28E-6!7.81E-61 !1.41E-5' j }E. VOLUME OF WASTE RELEASEDj l l l l l l (PRIOR TO DILUTION) !Litors 19.52E+4!1.08E+5! '2.03E5 l l-lF. VOLUME OF DILUTION WATER l l l l l l l l USED DURING PERIOD ! Liters 11.37E+9!1.46E+9! 12.S3E9 l G. PERCENTAGE OF ( APPENDIX I) TECHNICAL SPECIFICATION LIMITS FOR LIQUID RELEASES 1 ! QTh QTR ! QTR QTR l YEARLY l l HIGHEST ORGAN 1 0.051 0.073 l l ! 0.061 l l WHOLE BODY l ! 0.11 .0088 l l l 0.145 l _

l TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT - 1990 LIQUID EFFLUENTS l NUCLIDES RELEASED l UNIT ' QUARTER ' QUARTER ' QUARTER ! QUARTER f 3.5 E-5 l l l STRONTItM-89 ? Ci f STRONTIUM-90 Ci 1.23E-4 1.04E-4 l CESIUM-134 Cl 1.17E-5 8.53E-6 1 l CESItM-137 l Ci , 2.55E-3 3.14E-3 1 I10 DINE-131 Ci ? l COBALT-58 Ci l COBALT-60 C1 4.50E-3 1.01E-2 l l IRON-55 C1 2.81E-3 9.10E-3 1 l IRON-59 ! Ci ZINC-65 C1 MANGANESE-54 Ci ) 2.76E-4 2.87E-4 1 t , CHROMItM-51 l C1 1 l 1 j ZIRCONIlM-NIOBIUM-95 ! Ci l j MOLYBDENUM-99 1 Ci l l TECHNETIUM-99M 1 Ci t l BARIUM-LANTHANUM-140 1 Ci l CERIUM-141 ! Ci j' SILVER-110M t Ct' Ci l Ci l TOTAL FOR PERIOD (ABOVE)! Ci ! 1.0'3E-2 ! 2.28E-2 l l XENON-133 Ci O.00 0.00 l XENON-135 C1 0.00 0.00 i 1 j Ci i l Ci l t j

Ci l

t Ci t l

~ TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT - 1990 SOLID WASTE AND IRRADIATED FUEL SHIINENTS A. SOLID WASTE SHIPPED OFFSITE POR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) l l l 6-MONTH j 6-MONTH l l l 1. TYPE OF WASTE ' UNIT, PERIOD ? PERIOD TOTAL l 3 l

a. SPENT RESINS, FILTER SLUDGES.

m i EVAPORATOR BOTTOMS. ETC. Cl l l

b. DRY COMPRESSIBLE WASTE, m

4.10

4.10 L

3 i CONTAMINATED EQUIPMENT. ETC. Ci 2.88E-1 i 2.88E-1 4 8

c. IRRADIATED COMPONENTS,

. m CONTROL RODS. ETC. ? Ci u l

d. OTHER (DESCRIBE) m' j

Ci I t ~ 2. ESTIKATE OF KAJOR NUCLIDE COMPOSITION l l 6-MONTH l 6-MONTH l (BY TYPE OF WASTE) l PERCENT' PERIOD PERIOD j I j a. e i i F i i b. Co-60 42.7 1.23E-1 Cn-137 2.1 6.06E-3 Mn-54 1.4 5.42E-3 l Fe-55 47.3 1.360-1 L Ni-63 5.6 1.61E-2 Pu-241 0.4 1.14E-1 i i

3. SOLID WASTE DISPOSITION NO. OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION 5

Sole Use Barnwell, S.C. B. IRRADIATED FUEL SHIPMENTS (DISPOSITION) NO. OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION l,' 8. OFFSITE DOSE CA1,CU1ATIONS StMMARY AND CONCLUSIONS: a. Gaseous Effluent Releases The maximum quarterly offsite gamma doae due to noble gases was 0.00 mrad. The cumulative 1990 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 mrad. The cumulative 1990 annual offsite beta dose due to noble games was 0.00 mrad. The maximum quarterly offsite dose to any organ from the release of I-131. 1-133. H-3 and all radionuclides in particulate form with half-lives greater than 8 days was approximately 9.09E-4 mrem. The cumulative 1990 annual maximum organ dose from these radionuclides was approximately 1.04E-3 mrem. The highest historical monthly and annual average X/Q's for the period 1985-1987 for the worst case offsite receptor location, in accordance with the ODCM were used to calculate these offsite dose values. b. 1,lauld Effluent Releases The maximum quarterly organ dose from liquid releases was i approximately 3.65E-3 mrem. The maximum cumulative 1990 annual organ l dose was approximately 6.1E-3 mrem. The maximum quarterly whole body dose for liquid releases was approximately 1.65E-3 mrem, and the i cumulative 1990 annual whole body dose was approximately 4.83 E-4 mrem. c. Conclusion i All calculated offsite doses were below Technical Specification 1 limits. - . -}}