ML20127C758
| ML20127C758 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 06/30/1992 |
| From: | Berg W DAIRYLAND POWER COOPERATIVE |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LAC-13203, NUDOCS 9209100098 | |
| Download: ML20127C758 (17) | |
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7, ijll;/DA/RYLAND
'hhh[ COOPERATIVEa 3200 EAST AVE SO
- PO BOX 817
- LACROSSE WISCONSt. 44602-0817 (50 % 788-4000 FAX NO. (608) 787-1420
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WILLl'AM L BE AG ocenera! Manager August 24, 1992 In reply, please refer to LAC-13203 DOCKET No. S0-409
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Document: Control Desk.
-U. S. Nuclear Regulatory Commission Washington,- D.C.-
- 20555' Gentlemen:
~
SUBJECT:
.Dairyland Power Co> perative
. La Crosse Boiling-Water Reactor (LACBWR)
Possession-Only License No. DPR-45
'SemiaAnnual Rad? fig vive Effluent Report
REFERENCES:
' -(1) NRC Letter, Keppler to Linder, dated August 12, 1983, Inspection Report 50-409/83-10 (DRMSP)
.'(2)
IACBWR Technical Specifications 6.8.1.1.c and 6.8.1.2
'In'accordance with 10 CFR 50.36a(a)(2), this letter serves to transmit S-7
.to;you the Radioactive Efflunt Report for the.La Crosse Boiling Wa*.er Reactor
.(LACBWR) fc: the period-January 1 through June 30, 1992.
IfLyou have any questions, please contact us.
f6
- Sincerely, q.
DA1RYLAND POWER COOPERATIVE hNb9 (.
William L. Berg, General ianager 7_ -
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' WLB': LLN : dh --
jy Enclosure ll
-cc/eceJ :
A'.' Bert Dcvis, U.S. NRC Region:III NRC Project Manager (L. Bell)
D.,Sherman,.ANI-Library
- b.. -ils-Don Hendrikse,' Wisc. Div. of Health 4 " i;f g
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9209100098 920b?O0500040W
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-RADIOACTIVE EFFLUENT REPORT
'FOR THE LA CROSSE DOILING WATER REACTOR (LACBWR)
(January 1 to June 30, 1992)
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DAIRYLAND' POWER' COOPERATIVE Docket No. 50-409
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l'ABLE OF CONTENTS ILTLE Ib_GE Radioactive Effluent Renom
- Introduction 1
Regulatory Limits 2
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Maximum Permissible Concentration 4
Average Energy 4
i Analytical Methods 4
Batch Releases 6
Abnormal Releases 7
Estimated Total Analytical Error 7
Offsite Dose Calculation Summary 14 se 11
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TABLES i
- ~
- IABLE No.
nng aqg 7
- 1A:
Effluent and Waste Disposal Gasen as
-,N-Effluent Release Summaries 8
... +.
1B Gaseous Effluents - Elevated Release 9
- 2A- '
Liquid Release Sumrary 10' 2B Liquid Effluents 11
'3 Solid ~ Waste and' Irradiated Fuel Shipments 12
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W INiRODUCTION:
The La Crosse Boiling Water Reactor (LACBWR), alsc, known as Genoa Station No.'2, is_ located on the east bank of the Mississippi River near
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- Genoa, Vernon. County, Wisconsin. The plant was designed and constructed by 4
- the Allis-Chalmers Manufacturing Company.
It was completed in 1967 and had a generation capacity-of'50 MW (165 MW(th)).
The reactor is owned by Dairyland k
Power Cooperetive (DPC).
3 The reactor vent critical in July 1967 and iirst contrRuted electricity
. to DPC's system'in April-1968.
After completing full _ power tests in August.
1969, the plant operated between 60% and 100% full power, with the exception e
- of plant shutdowns for maintenance and repair.
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
^
JAugust of 1987.a possession-only-license was received.
In accordance with LACBWR " schaical Specifications 6.8.1.2 and in 4
compliance with 10 CFR 50.36a(a)(2)..this document is the Radioactive
- Ef fluent Report f or.tbe porlod January 1 through June 30, 1992.
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-2FFLUENT AND WASTE D1SPOSAL REPORT (Supplemental Information) s
- FACILITY: Lacrosse Boiling Water Roactor LICENSEE: DAIRYLAND POWER COOPERATIVE DOCKET Nd. 50-409
- 1.
REGULATORY LIMITS y
a.-
Gaseous' Effluent Release Limits:
LACBWR's Technical Specificatiou for gaseous effluent releases of radioactive materia 1' limit the release rates of the sum of the individual radionuclides,Lin. Curies per second, so that the dose cates to members of the public beyond tha Effluent Release Boundary do not exceed = 500 mrem / year to the whole body, 3000 mrem / year to the skin from noble gases, and' 1500 mlhui/ year-to a critical organ from 11-3. I-131/133 L
and particuintes.rith half-lives greeter than 8 days.
Also, in accordance with 10 CFR 50, Appendh I, the Technical
- Specifications for gaseous offluent radioactive material limit the air dose.to a member of the public from noble gases in areas beyond the i c.
EffluentfReleaseiBoundary to less than 5' mrad gamma and 10 mrad beta per calendar quarter, and lees than 10 mrad ;;amma and 20 mrad beta per
[
nalendar year. The dos' limits : from 11-3, I-131/133 and particulates with hnif-lives greater than 8 days are less than 7.5 mrem per calendar
. quarter,-and-less than 15 mRcm per calendar year to any organ.
Cumt M ive dose contributions from gaseous effluent relvases are s
= determined in a'ecordance with the LACBWR Offsite Dose Calculations Manual.
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.b.
Liquid Effluent Release Limits:
LACBWR's Technical Specifications limits for liquid effluent sx releenes aru limited to those concentrations of individual radiocuclides such that the diluted discharge does not exceed 1 MPC in a 168-hour week' av2 raged over the calendar year.
For dissolved
<>r entrained no!1e gases, e concentration is limited to a total activity concentration of 6'x 10*".pCi/m1, For alpha emitting radionuclides, the concentration is
-limited-to a total activit).s a oc ntration of 4.9 x 10*' pCi/ml, based
. upon: an actual alpha emitting radionuclide analysis performed on a representative water sample. The values reported in tables 2A and 2B, I
Liquid Effluents, are based on dilution with the combination of LACBWR and Genoa Station No. 3' condenser cooling water flow prior to discharge tc'the Mississippi River.- No credit is tuken fo further dilution in-the mixing aone of the Mississippi River.
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Also, in accordance with 10 CFR 50 Apperdix I, the dose commitment
. to a member.of the public froc radioactive materials released in liquid effluents to areas:beyond the Effluent Release Boundary are limited to i
lens than.1.5 mrem whole body and 5.0 mrem organ. dose per calendar squarter, and less-than-3.0 mrem whole--bedy and 10 mrem organ-dose per calendar year via the critical ingesti.cn pathway, p
y ow Cumulative quarterly and annual dose contributions from liquid qN j;
. ef fluent releases are determined for the adult ' fish ingestien pathway in
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S accordance with the LACBWR=0ffsite Dose Calculation Manual.
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Solid Radioactive Waste m
All solid radJoactive wastes are handle'd~in accordance with a-
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Process Centrol Pregram as defined-by LACBWR procedures in order to assure that all applicable transportation and burial site disposal requirements are met.
- 2. -MAXIMUM PERMISSIBLE CONCENTRATION (MPC) 7
'Tho'HPC used'~to calculate permissible release rates are obtained from In addition, the following. values 10 CFR 20 Appendix B. Tables I and II.
w are used:-
3 x 10'8 pCi/ml.
' Tritium in' Wat
- =
~1Jitism in Air
' 2.x 10 pCi/ce.
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3.
AVERAGE ENERGY-The release rate limits for LAC 3WR are not base. on average energy.
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- 4. ! ANALYTICAL METHODS-ta; Liquid Sffluents
[Liquideffluentmeasurementsforgrossradiosctivityareperformed Lby Go-Li gacr a isotopic analysis of a representative sample from _each s
-tank _ discharged. ?In addition, eac'n' batch discharged tank is analyzed for alpha and tritium activity concentration. A composite sample is created:by' collecting representative aliquots from eac's tar.k batch
-discharged -and ir analyzed quarterly fo:- Iron-55 and Strontium 89 & 90
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Airborne Particulates Airborne particulate releases are determined by Ge-Li gamma Q
isotopic analysis. This analysis is performci by analyzing a glass fiber filter paper taken from the stack monitor (Eberline SPING) which continuously isokineticall-samples and monitors the stack effluent.
y This filter is changed and analyzed on an approximate weeki> basis and i
analyzed uithin 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.
Radiciodines Sinca the plant shutdown in April 1987, the I-131/I-:33 have decayed completely to stable elements. Amendment 66 co the LACBWR Technical Specifications, Table 5.7.2.2, no longer requires monitoring
)
for iodine.
d.
Fission arid Activat d on Gases
}
The gaseous releases converted into concentration (pCi/cc) are continuourly sampled from the stack release flow by two stack monitors, which are in-litie monitors. Thase gas concentrations (pCi/cc) are averaged-by the monitors microprocessor and flovrate/ pressure compen-sated to obtain the daily gueous release of the plant.
Since the plant shutdown in April 1987, gaseous releases have been immeasurable. All fission gases excepe. Kr-85 have dceayed completaly to stable elements.
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. Tritium Tritium releases are determined by taking a grab sample of the
-stack atmosphere at the ef' fluent of the stack monitor. Tritium, as i
tritiated-water.fis removed'from the sample stream by condensation,
-using ancold trap containing an organic compoorid and dry ice.
The condensed water' vapor is then distilled and the distillate is analyzed
,for H-3 ccncentration, pCi/ce, by internal liquid scintillation spectrophotometry and the'results are expresse-in terms of tritium
' release rates. The tritium grab samples ar.
Stained on at least a once/ month basis unless'the upper reactor cavisy is flooded, at which time.tha' sampling frcquency is increased to at least once per 7 days.
5.
RATCH RELEASES
- y
- a.
Airborne All airborne effluent releases at LACBWR are from.a single
- Continuous-Elevated Releace Point.
~
Lb.- Liquid All liquid effluent releases r.t LACBWR are batch releases.
This is-sumatarized as folleust (1)' Number of Batch Releases:
6 (2) Total Time Period for Batch Releaces:
93.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (3) Mexikam. Time Period for a Batch Relaase:
21.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (4). Average Time Period for a Batch Release:
15.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
( 5)' Minimum Time Period for a Batch Relecse:
11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />
-(6) Average Stream Flow Rate During Periods-2 of_ Release of Effluent into a Flowing Stream:
43,817 ft /sec i
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. ABNORMAI,' RE!;EASf.S1..
There'were no abnormal releases ~of radioactivity-in plant effluents as
. summa:lzad as followst.
- a.
- Liquid E
-(1) Number of' Releases: None (2)1 Total Activity Felmsed: N/A
=b.
Gaseous
~
'(1)Numbar oS-Releases: None
--(2)- Total Activity Released: N/A 7.
ESTIMATED TOTAL' ANALYTICAL ERROR
'The reputed analytical results contain the f allowing estimated errors:
Counting Error t 1-Standard Deviation
..s..
Sampling Volume Error t 5%.
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- p TheTlower limits of detection,(LLD) are expressed in terms of a 4.66 o
.as.. defined -in Technical Specificatio'ns.
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TABLE 1A EFFLUENT MD WASTE DISPOSAL SEMI-ANNUAL REPORT - 1992 CASEOUS REfl13ENTS..JUMMATION Of ALL RELEASES j{
l UNIT l OTR I OTR l OTR I OTW l *OTAL l A.
FISSIC4 6 ACTIVATION CASES l 1. TOTAL RELEASE l
l l
l l
l I
ci 1
0.00 1 0.00 I I 0.00 l
- 2. AVERAGE RELEASE RATE l.
l l
FOR PERIOD
__l_1ci/Sec 0.00 0.00 l
l B.
10DICJ I-131 - No longer analyzed for.
C.
PARTICULATES 1 PARTICULATES W/ HALF--l l
l l
LIVES > 8 DAYS l
Ci 2.68E-711.92E-7:
I 4.60E-7l l 2. AVERACE RELEASE RATE l
FOR PEP.IOD ici/Sec 3.53E-8 2.42E 8 1
- 3. CROSS ALPHA l
l F.ADIDACTIVITY Ci 7.07E-81 0.00 '
l D.-
TRITIUM-
- 1. TOTAL RELEASE l
' 8.42E-2 3.02E-2 l
11.14S-1l l
l l
l Ci i 2. AVERACE RELEASE RATE l l
l 4
FOR PERIOD 1 1C1/Sec L 19F-2 3.86E-3 L l
l E.
PERCENTAGE OF (APPENDIX I) TECHNICAL SPECIFICATION LIMITS 1.
NOBLE CAS RELEASE N
I OTR l OTR I OTR I OTR lYEARLY GAMMA i
'l _0.00 1 0.00 l I
i -0.00 l
l 0.00 1 0.00 l 1
1 0.00 l x
i BETA' e
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'2.
11-3 AND ALL RADIONUCLIDES IN PARTICUIATE FORM WITH HALF-LIVES GREATER E
THAN 8 DAYS l
OTR _ _ J QE I OTP l OTF lYEARLY l l HIGHEST ORGAN-l 13'. 05E-5 f l.14E-S I l
12.102-5l t
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TABLE IB EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT - 1992 CASE 00S EFFLUENTS - ELEVATED RELEASE CONTINUOUS MCDE l E CLIDES RELEASED
.i UNIT 1
OTR I OTP l OTR I OTR l TOTAL l
- 1.
FISSION CASES s
.l KRYPTQii-85 l
Ci i O.00 1 0.00 l
1 1 0.00 l
2.
10 DINES-'- No-longer analyzed for.
3.
FArl;1CUIATES g _i l
STRONTIUM-89 I
Ci 1 0.00 1 0.00 l
I
! 0.00 l
Ci 1 0 00 1 0.00 l
I l 0.00 CESIUM-134 I
Ci 1 0.00 11.26E-71 I
ll,2(E-7 CESIUM-137 l
Ci 14.90E2812.22E-81 1
17.12E-8 BARIUM-1ANTMANUM-140 1 Ci I 0.00 1 0.00 i
l 1 0.00 COBALT-60 I
Ci 12.17E 714.40E-81 1
12.61E-7L g
MANCANESE-54 l-Ci l _,0. 00 - l-0.00 I
I I 0.00 i
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TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT - 1992 LIQUID EFFLUENTS - SUMMATION, OF ALL REIEASES l
l UNIT j
QTR l QTR l QTR l QTP l TOTAL l A.
FISL?uN & ACTIVATION PRODUCTS l 1. TOTAL RELEASE (NOT INCL l
~l l
l l
l l
.l TRITIUM, GASES, AI. Pila) l CL l9.90E-319.87E-3!
j l1.98E-2l l 2. AVERAGE DILUTED CONCEN-l l
l l
l l
l TPATION DURING PERIOD lpC1/ml l7.86E-9l6.67E-9l l
l B.
TRITIUM l 1. 'iOTAL RELEASE l
l l
l l
l l
! Ci l4.516_216.42E-2l l
_ 1 09E-1l l 2. AVERAGE DILUTED CONCEN-l l
l l
l l
l_
TRATION DURING PERIOD \\pci/ml 6.48E-1012.33E-10 l
l
.C.
DISSOLVED AND ENTRAINED GASES
~
- 4. TOTAL RELEASE l
l l
l l
l Ci 0.00 l 0.00 l l
0.00 l l_
j 2. AVERAGE DlLUTED CONCL.b '
l l
l l
l l
TRATION DURING PERIOD luCi/ml l 0.00 1 0.00 l
_l D.
GROSS ALPHA RADIOACTIVITY l 1. TOTAL RELEASE l
l l
l l
l
_l l
Ci l8.42E-618.1CX-6!
l1.65E-5l
.lE. VOLUME OF WASTE RELEASED l l
l l
l l
l l
(PRIOR TO DILUTION) l Liters 15.62E4 16.80E4 l l1.24E5 l lF. VOLUME OF DILUTICN WATER l l
l l
l l
l l
USED DURING PERIOD lLiters 13.03ES l1.48E9 !
l1.78E9 l G. PERCENTAGE OF (APPENDIX I) TECHNICAL SPECIFICATION LIMITS FOR LIQUID RELEASES
! QTR lYEAj?LY l l IIIGHEST ORGAN l _
!A.96h-2l1.50E-2l l
!3.23E-2l l W110LE BODY l
i 0.11 l3.30E-2l l
!7.08E-2l.- - - --_ - -- __ - -___ - -______ - __ __ _ _ _ _ - _ _ _ _ _ _ _
'I ABLE 2B EFFI)JENT AND WASTE DISPOSAL, SEMI-ANNUAL REPORT - 1992 LIQUID EFF,1USNTS
)
l NUCL1 DES RELEASED l UNIT'~j QUARTER 1 QUARTER l QUARTER
- QUARTER _._l l STRONTIUM-89 l
Ci l
l l
,_l l STRONTIUM-90 l Ci l 6.09E-5 l 6.5o E-5 l l
l l CESIUM-134 l Ci l
l l
l l
l CESIUM-137 i Ci l 2.47E-3 i 3.40E-3 l
l l
l IODINE-131 l Ci l
l l
_l l COBALT-58 l Ci l
i l
l COBALT-60 l
Ci l 4.36E-3 l 3.97E-3 l
l l
l IRON-55 l Ci l 2.98E-3 l 2.43E-3 l
l l
l TRON-59 l Ci l
l l
l l
l ZINC-65 l Ci l
1 l
l l
l MANGANESE-54 i
Ci 1 2.46E-5 l
l l
l l CHkOMIUM-51 l
Ci l
l l
l l
l ZIRCONIUM-NIOBIUM-95 l
Ci l
l l
l l
l MOLYBDENUM-99 l
Ci l
l l
l l
l TECHNETIUM-99M l Ci l
l l
l l BARIu.4-1.ANTHANUM-140 l
Ci l
l l
l l
l _CERIL"4-141 l. Ci l
l l
l l SILVER,-IICH l
Ci l
l l
l l
l C1 l
t l
l l
l l
C1 l
l l
1 l
~
l i ci l
1 l
l TOTAL FOR PERIOD (ABOVE)l Ci l 9.90E-3 l 9.P7E-3 l
l l
j ER-85 l
Ci l
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TABLE 3
.EEFLUENT AND WASTE DISPOSAL-SEMI-ANM)AL REPORT - 1992
- S01.1D WASTE AND JRRADI ATED FUEL SillPMENTS A.
SOLID VASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) l 6-MONTil l 6 MONTil l l
- 1. TYEE OF WASJE I UNIT PF4LQD l PERIOD l TOTAL l a.-SPENT RESINS, FILTER SLUDCES, l_
m3 1
0 l
1 0
l-l EVAPORATOR ~ BOTTOMS. ETC.
I Ci 'l 0
(
l 0
l
.b.-DRY COMPRESSIBLE WASTE, l
m3 1
0 l
l 0
j CONTAMINATED EQlijffiERL _ ETC.
I Ci l
_0 l
l 0
- c. IRRADIATED COMPONENTS, l
m3
-)
0 Q_ _z _
l 0
-l'__
CONTROL RODS. FIQ.
I Ci i
0 l
i O
..l d.~0THER (DESCRIBE) l m3 1
0 I
I O
l
. l__
l Ci l
0
_j l
0 l-2.
ESTIMATE OF PA10R NUCLIDE COMPOSITION.
l 6 MONTH 6-MONTil (BY TYPE OF WASTE) l PEFCF.NT[ PERIOD PERIOD
.a.
I I
I I
l l
1 1
I I
I I
I I
I l
l I
i I
I I
i I
(
)
- 3. SOLID WASTE DISPOSITION NO. OF SHIPMENIE MODE OF TRANSPORTATION DESTINATION B,
. IRRADIATED FUEL SillPMENTS (DISPOSITION)
NO. OF SHIPMENTS
- EODE OF TRANSPORTATIO_N DESTINATION
_. 7.
4 8.
'0FFSITE DOSE CALC'2.ATIONS
SUMMARY
AND CONCl,USIONS:
a.
Caseous F.ffluent Releases The maximum quarterly offsite gamma dose due to noble gases was 0.00 naad. The cumulative 1992 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 1992 annual offsite beta dose due to noble gases was 0.00 mrad.
The maxinum <;uarterly offsite dose to any organ f rom the release of
~
!!-3 and all radionuclides in particulate form with half-lives greater than 8 days was approximately 2.29E-6 mrem.
The cumulative 1992 annual maxinnmi organ dose from these radionuclides was approximately 3.15E-6 mrem.
The highest historical monthly and annual average X/Q's for the period-1985-1987 for the worst case offsite receptor location, in 5
accordance with the ODCM, were used to calculate these offsite dose values.
b.
Liquid Effluent Releases, The maximun quarterly organ dose from liquid releases was approximately 2.48E-3 mrem. The maximum cumulative 1992 annual organ 4
dose was approximately 3.23E-3 mrem. The maximum quarterly whole body dose for liquid releases was approximately 1.65E-3 mrem, and the cumulative 1992 annual whole body dose was approximately 2.12E-3 mrem.
c.
Conclusion All calculated offsite doses were below Technical Specification limits.
/ %
. - _ _ _ _ _ _ _ _ _ - _ _ - - _ _ _ _ _ _ _ _ - - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _