ML20141M551
| ML20141M551 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 06/30/1992 |
| From: | Pleniewicz R COMMONWEALTH EDISON CO. |
| To: | Bradley Davis NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| BYRON-92-0534, BYRON-92-534, NUDOCS 9209010141 | |
| Download: ML20141M551 (32) | |
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Byron G ;j" 4450 Nuclear Station North German Church Road I
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,j Byron, Illinois 61010 August 4, 1992 LTR BYRON 92-0534 FILE: 2.12.1522 Mr. Bert Davis, Administrator Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137
SUBJECT:
Semi-Annual Effluent Release Report Dyron Station Units 1 and 2 Facility Operating License Nos. NPF 37 and 66 NRC Docket Nos. 50.454 and 50.455
Dear Mr. Davis:
Enclosed is the Radioactive Effluent Release Report for January through June, 1992, for Byron Nuclear Power Station. This report is required per Technical Specification 6.9.1.7.
Two copies of the report are provided for your use. Two copies will be forwarded to the Document Control Desk and one copy to the Resident Inspector.
Sincerely, j
.- =n(ww-i R. Pleniewicz tation Manager ,/
Byron Nuclear Power SAation RP/DP/ph Enclosure cc: Distribution List Attached 010015 (3635z/VS) 9209010141 920630 4 DR ADOCK 0500 [gg la x ,
4 STATIONS SEMI-AlmUAL RADIOACTIVE EFFLUENT RELEASE REPORT DISTRIBUTION LIST r
Director of Nuclear Reactor Regulation - U.S. Nuclear Regulatory Commission Nuclear Regulatory Commission, Region III 3
Illinois Department of Nuclear Safety, Of fice of Nuclear Tacility Safety A.N.I.
American- Electric Power Service Corporation, Nuclear Operations Division U.S. Environmental Protection Agency' Air and Radiation Branch - Region V Health Physicist Illinois Environmental Protection Agency - Region III Illinois Environmental Protection Agency Division of Water Pollution Control Environmental Protection Specialist 14urray and Trettel, Inc.
Teledyne Isotopes Midwest Laboratory and General Manager Emergency Preparedness - Chemistry Services Director Station Manager _ Byron Nuclear Power Station Health Physics Services Supervisor - Byron Nuclear Power Station Radiological Effluent Monitoring Program Coordinator NRC Resident Inspector - Byron Nuclear Power Station B.P.I. Associates General Counsel-Illini State Park Site Superintendent Nuclear Quality Programs & Assessments - General Manager (36352/VS)
BYRON NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT j JANUARY through JUNE 1992 Supplemental Information
- 1. Regulatory Limits
- a. Fission and activation gases:
10CFR20 Whole Body e 500 mrem / year Skin = 3000 mrem / year 10CFR50 Gamma = 5 mrad / quarter 10 mrad / year Beta = 10 mrad / quarter; 20 mrad / year
- b. Iodine: (summed with particulate, see below) m
- c. Particulates with half-lives > 0 days:
10CFR 20 Organ = 1500 mrem /yr, 10CFR 50 Organ = 7.5 mrem / quarter; 15 mrem / year
- d. Liquid effluents:
10CFR50 Whole Body = 1.5 mrem / quarter; 3 mrem / year Organ = 5 mrem / quarter; 10 mrem / year
- 2. Maximum Permissible Concentration
- a. Fission and Activation Gases ~ 10CFR20 Appendix B Table II
- b. Iodine: 10CFR20 Appendix B' Table II
- c. Particulates: 10CFR20 Appendix B Table II
- d. Liquid Effluents: 10CFR20' Appendix B Table II y
- 3. Average Energy: This item is not applicable. Release rates are calculated using an isotopic mix rather than average energy.
- 4. Measurements and Approximations of' Total Radioactivity
- a. Fission and Activation Gases: Prior to release, the isotopic-content is determined. Released activity is calculated using volume of release, which is determined by the, change in tank or containment pressure. Additional methods of calculation utilize historical data and assign an isotopic mix which is representative of normal vent stack isotopics.
- b. Particulate, Tritium and Iodine sampling media for the plant vent stacks is collected and isotopically analyzed daily for the plant vent stacks.
(3635s/VS)
- , .- -~ . . . - . . . . - .. ._ - - -- -.- -. . - ~ - --- . ,
~ .
y J
4- BYRON NUCLEAR POWER STATICN-EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January THROUGH June 1992
[ Supplemental Information
^
(continued) i i
- c. Liquids effluents
- Batch releases are isotopically analyzed prior to release. Total release activity is calculated using volume of 3
release. Total tritium activity released is calculated from the _
j~
highest of a monthly circulating water blowdown composite activity or a sum of the input composite activities.
- d. Analysis results which are less than the lower limit of detection f' (<LLD) are reported in units of C1/M1 unless- otherwise noted. All i LLD values are listed in Attachment A.
S. Batch Releases i
i a. Liquid:
i 1. Number of batch releases = 194
- 2. Total time period for batch releases = 17,652 minutes.
- 3. Maximum time period for a batch release- = 408' minutes.
- 4. Average time period for a batch release = 91 minutes
- 5. Minimum time period for a batch release = 49 minutes i 6. Average' stream flow during periods of release of effluent into a flowing- stream = 5674 cfs, based on information from the National Weather Service or Army Corps of Engineers for the Rock River.
I l b. Gaseous
- 1. Number of batch releases =- 229
- 2. Total time period for batch releases = 73,159 minutes
- 3. Maximum time period for a-batch release = 9,099 minutes.
( 4. Average time period for batch releases = 319 minutes.
- 5. Minimum time period for a batch release == 32 minutes.
l 6. Abnormal Releases i-
- a. Liquid - none i
- b. Gaseous - none r
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BRP 1100-T7 !
Revision 0 -
Unit 1 Docket Nuc6er STN-50-45* j APPROVED err 0n wuctE>n POWtR srAr:On I
EFituENT AnD WA51E DISPOSAt StMIANPAIAL REPORT FOR January - June 1992 APR 2 R 1986 .t:0uro unuturs - sumari0n r Att RutAsts !
B. O. S. F!.
l . tmITS I Jan 1 Feb ] Mar I ?.st CUARTERI Apr i May 1 June 1 2nd OUARTEE l
I. Fission and Activation Products C1 1.74E-1 1.95E-2 1.16E-2 2.05E-1 9.41E-3 5.98E-3 1. 32E- 3 1.67E-2
- 1. Intal Acti.vity Relened uCl/mi 1.8SE-7 2.18E-8 1.66E-8 8.13E-8 1.29E-8 8.86E-9 1.69E-9 4.53E-9 ,
2f Averaoe Concentration Reigned 3 d _of_InCFR50 Limits 0.01 0.06 0.08 0.02 0.01 0.01 0.04
- a. Duarteriv Whole Bod, t1.5 oremi % 0.01
% 0.05 0.00 0.01 0.06 0.01 0.00 G.00 0.01
- b. Duarteriv Anv Oraan 15.0 mremi 0.01 0.00 Annual Whole Body f3.0 mrtal % 0.01 0.00 0.03 0.04 0.01 O_02 l c.
% 0.02 0.01 0.00 0.03 0.00 0.01 0.00 0.01 __ i
- d. Annual Anv Ornan i10.0 mremi
= J. Tritium i
Cl 6.70E+1 2.89E+1 8.00E+1 1.76E+2 4.66E+1 4.84E+1 8.72E+1 1.82E+2
- 1. Total Activity Released I uCi/ml 7.24E-5 3.23E-5 1.14E-4 6.98E-5 6. 38E-5 7.17E-5 1.1?E-4 4.9 3E-5 2- Averar. Concentration Released 2.39E0 1.64E0
% 2.41E0 1.08E0 3.PJ'E0 2.33E0 2.13E0 3.7 3E0
- 3. % of Limit f3E-3 uC1/m11
} K. Dissolved Noble Gasses * ,
t Cl 1.87E-1 3.42E-2 1.54E-1 3.75E-1 1.66E-1 2.09E-2 1.44E-2 2.01E-1 1, Total Activity Reigned I uCi/ml 2.02E-7 3.82E-8 2.20E-7 1.49E-7 2.27E-7 3.10E-8 1.85E-8 5.45E-8
- 2. Average _fsnIrnirailan Relen ed
% 1.01E-1 1.91E-2 1.10E-1 7.44E-2 1.14E-1 1.557-2 9.23E-3 2.72E-2 :
- 3. % of Limit f2E-4 uC1/ml) !
j L. Gross Alpha I
Cl <tLD <tLD <tLD <tLD <llD <tLD <LLD <LLD
- 1. intal Activity Released 0.EE+0 uCi/mi 0.'fE+0 0.9E+0 0.EE+0 0.9E+0 0.fE+0 0.7E+0 0.FE+0
- 2. Averaoe Concentration Released
~
i i
l liters 1 2.05E+6 l 1.47E+61 1.70E+61 5.22E+6 1 1.60E+r- l 9.49E+5 1 1.44E+6 1
- 99E*6 M. Volume of Liould Waste to Ditcharne '
l I liters 'I 9.25E+8 I 8.95E+81 7.00E+81 2.52E+9 1 7.30E+B I 6.75E+3 1 7.80E+8 1 2.18E+9
-N J a]ume of Dilution Water
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BRP 1100-T7 Revision 0 q
Unit 2 Docket Nunter STN-50-455 'I 3YR0ft tAKLEAR POWER STATI0f4 {
l EFFLUENT A!O WASTE DISPOSAL SEMIANNUAL REPORT F0gJanuary - June 1992 GASE0 tis EFFLUENTS - VENT STACK RELEASES -BATCH i
- j. E TOPES RFifA%fD l UNITS 1 Jan. I Feb. I Mar. 1 Is* OUARTERIApr. I t*ay I Jtme 12nd 00ARIEg !
}- F. fission and Activation Gas Ireleases xe-131m El 1.26E-1 2.E6E-1 4.19E-1 8.31E-1 3.55E-1 <tLD 9 30E-2 4_SIE-1
- xe-133m 4.3CE-2 2.0EE-1 2.21E-1 4.70E-1 1.92E-1 < fin 2_43E-2 ?_16E-1 xe_135. <llD < t_ f_D <1_ L D <t t D (f 1 n _
<1 i n <t I D et t n Xe-133 1.00E+1 2.75E+1 4_43E+1 o_1RE+1 7_77F+1 1.7eE-7 5_;1F0 ?.FSF+1 j Xe-135 2.41E-2 8_94E-1 7.47E-1 1.16FO _t61F-1 <t t n 4_6tJ.a 1 6ar 1 I K r-85m 1 BCE-d 2.82E-2 1_ t,6 E- / 3.00E-7 1.76F-7 <11 n 31In 1.76F 7 Kr-85 3 43E-I 2 54E-I S 30E-l I ilio 8 ERF-1 <1 t n 1.67F-1 6_7nF-1 f Kr-gy <f f n <t t n <t i n (f t n <t t n <t i n <t t n ci t n Kr-88 #lf U 9 MI-3 3 4EE-3 1 10F-7 8_R?F-1 <11 n <l 1 D I _ RT-1 A r - 41 I 07E-2 R_95E-5 6_ MF- 5 i_n9F-7 9_anF-5 7.9sF-1 4_19F-1 1_77F-7 1
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- 3RP I100-!7 Revision 0 .
j Unit 2 Docket Number STN-50-455 A P T' R O V E D an ou nuCttAn P0wtn stAtton Ef f LUENT AND WA51E DISPOSAL StMIANNUAL REPORT ffA January - June 1992 APR 2 8198o tinuiD Errtuturs - su marron Or Att attEAsEs B.O.S.R.
I UNITS I Jan 1 Feb I Mar I ist Og3RTERI Apr i May l June 1 2nd otvEIER 1
- I. Fission and Activation Products 2
/
- l. Total Activity Released Cl 1.74E-1 1.95E-2 1.16E-2 2.05E-1 9. 41E- 3 5.98E-3 1.67E-2 2- Averaoe Concentration Released uCi/ml 1.88E-7 2.18E-8 1.66E-8 P.13E-8 1.29E-8 8.86E-9 1.32E-3i 1.69E-9 _{ '4.53E-9 i 3. % of_10CFR50 Limits
- a. Duarteriv Whole Body f1.5 mrem) %' O.01 0.01 0.06 0.08 0.02 0.01 0.01 0.04
- b. Quarteriv Anv Organ f5.0 mrem) % 0.05 0.00 0.01 0.06 0.01 0.00 0.00 0.01 j c. Annual Whole Bodv f3.0 mrem) ; 0.01 0.00 0.03 0.04 0.01 0.01 0.00 0.02
- d. Annual Any Oroan f10.0 mrem) % 0.02 0.01 0.00 0.03 0.00 0.01 0.00 0.01
. J. Tritium l
- 1. 'otal Activity Released Cl 6.70E+1 2.89E+1 8.00E+1 1.76E+2 4.66E+1 4.84E+1 8.72E*1 1.82E+ 2 l 2- Avermoe concentration Released uti/el 7.24E-5 3.23E-5 1.14E-4 6.98E-5 6.38E-5 7.17E-5 1.12E-4 4.93E-5 3 % of Limit f3E-3 uCi/ mil % 2.41E0 1.08E0 3.80E0 1 2.33E0 u 2.13E0 2.39E0 s 3.73E0 1.64E0 l K. Dissolved Noble Gasses .
, 1. ' Total Activitv Released C; 1.87E-1 3.42E-21 1.54E-1 3.75E-1 1.66E-1 2.09E-2 1.44E-2 2.01E-1 i 2. Average Ceicentration Releasee uCi/ml 2.02E-7 3.82E-8 2.20E-7 1. 49E-7 2.27E-7 3.10E-8 1.85E-8 5.45E-8
- 3. % of Limit (2E-4 uCi/ mil % 1.01E-1 1.91E-2 1.10E-1 7.44E-2 1.14E-1 1.55E-2 9.23E-3 2.72E-2 L. Gross Alpha
- 1. Total Activity Released Ci <LLD <tLD <tLD <tLD <tLD <llD <lLD <tLD
- 2. Averaoe Concentration Released teCi/mi 0.9E+0 0.9E+0 0.9E+0 0.9E+0 0.9E+0 0.9E+0 0.9E+0 0.9E+0 i
M. Volume of tiould Waste to Discharse i liters 1 2.05E+6 1 1.47E+61 1.70E+6! 5.22E+6 l 1.60E+6 I 9.49E+5 1 1.44E+6 1 3.99E+6
] "
j N. Volume of Dilution Water ! '11ers I 9.25E+8 I 8.95E+81 7.00E+81 2.52E*9 1 7.30E+8 1 6.75E+8 I 7.80E*8 1 2.18E+9 4
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BRP 1190-T, .-
Rev hlon 0 ,
APPROVED BYROM NUClF.AR POWER STATION
" "' ^" "^5'E DISPOSAL SEMIA % AL R W U APR 2 A 1986 SOLID RADIDACTIVE WASTE B.O.S.P. MONTH Jan yEAq 1992 ,
j Disposition of Material 1 Mode of Transoort Destination Volume Per Shloment fft I Curles Per Shipment (
_DATE (Descriotion. Class . Tver Solidifvino Aaent ,
i 8 Dewatered Resin, Class C,' Cask-LSA, None Exclusive Use Barnwell.SC 132.4 556 1-20 Dewatered Resin, Class AU, Cask-LSA, None Exclusive Use Richland,W 199.4 .309 L t
, 1 - i t
4 4
t -t i .i 4 4 t
l ,
I i i ;
t i
,! t NONTHLY W Ats. 2 331.8 ss6_sn9
~21-(6566P/0387P)
-+ -
3
I l' 62P 1100 t',
'(
Jewision 0 APPROVED BYRON NUCLEAR F0WER STATION -
EFFLUENT AND WASTE DISPOSAL SEMIAWA!AL REP)RT APR 2 9 886 SOLID RADI0 ACTIVE WASTE l
B.O.S.P. aoNin Feb ytag 1992 Disposition of Material DATE IDescrlotion. Class . Tyne . Solidif wirio Ament lModtofTransnort Destination Voline Per Shinsent (f*3 I Curles Per Shinnent *; t l
2-20 DAW, Class A, Drums-LSA, None Exclusive Use Barnwell,SC 333.2 .79 !
e i-5 4 . ,
1 i f f ,
l #
- s I
- t t
i
. L e
a ; I l
t i
9 6 l
- MONTHLY TOTAL 5' 1 333.2 .79
-zz-i (6566P/0387P)
. Fli,L*.L i-
. . . . _ . . . - - . _ _ - . . . _ _ . . . . . _ _ _ _ ___.___m.....__._m_ , _ _ - . _ . _ . _ ___.- -. -. ___..m_ _
BRP 1100-T, .
Ra,4ston 0 . l 7
APPROVED i
8YRON NUCLEAR P:3WER STATION ;
i EFFitKNT AND WASTE DISPO$AL SEMIANNUAL REFORT .
APR 2 a N85 SOLID RADI0 ACTIVE WASTE
,i B.O.S.P. MONTH Mar YEAR 1992 i
Disposition of Haterial 3 ' '
l DATE IDescrintion. Class . Tyne . Solidifyina Acent Mode of Transnart Destination Volume Per Shinsment f.t i Euries Per Shlostal d
3-3 Dewatered Resin, Class AS, Cask - LSA, None Exclusive Use Barnwell,S( 202.1 18.6 3-13 Dewatered Resin, Class AS, Cask - LSA, None Exclusive Use Ba rnwe ll . St. 202.1 20.2 i 3-26 DAW, Class A, Drums - LSA, None Exclusive Use Barnwell,St 345.1 1.65
.f i
i 4
I i
t l _
l -
! i i
NONTHLY TOTALS:
3 749.3 40.45 j (6566P/0387P)
FlW.L
BRP 1100-Tk .
Re,lsion 0 -
APPROVED BY90N Nt1 CLEAR P0wtR STATION truutui ue wAsir otsPosAt stnwn;At RtPoRT .
jpg pa ggg SOLID RADI0 ACTIVE WASTE Monin Apr 1992 B.O.S.P. YEAR .
Disposition of Material 3 ,
_ Twoe . Solidifyina Aaent Mode of Transnort Destination Volume Per Shineent f f t 1 Curies Per ShinetnL DA!E (Dritriction. Class 4-27 Dewatered Resin, Class AU, Case - LSA, None Exclusive Use Richland,W 199.4 7.32 O
s e
T.
f 4
I l - ,
I I
+
I 1 .
O THLY TOTAL 5' 1 199.4 7.32 16566P/J387P)
FIMf1
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. .. . _ . ~ _ - . _ . - - . . . . - - . _-
BRP 1100-T.
aavision 0 ,
APPROVED "1
BYRON t#KLEAR POWER STATION EULMT A80 WAME DISMSAL MMIAmeAL RtmRT .
APR 2 A 1986 SOLID RADIDACTIvt WASTE I B.O.S.P. NoNTH Jun vtAm 1992 i
I Disposition of Material l SATE IDescrintion. Class . Tyne . Solidifwina Aaent Mode _ef Transacrt Destination yglume Per Shinnent Ift 1 Curles Per Shloment t
6-2 i)ewatered Resin, Class AU , Cask - LSA, None Exclusive Lte Richland,W 199.4 1.42 6-18 Filters, Class C, Cask - LSA, None Exclusive Use Bar7well,S :: 132.4 35.7 j i
2 n -
4.
r
. f I
i k
l 4
6 A
MONTHLY TOTALS: 331.8' 37.12 2 ,
(6566P/0387P) nnt.L ;
F
i i
I
- j. BYKON NUCLEAR POWER STATION l i EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT f ;
j JANUARY TO JUNE 1992 i
! ADDENDUM
' i 1
j A. The following data is the estimated composition of Byron's solid waste i streams:
i j 1. Dry Active Waste (DAW) 2. Primary Resin 3. Radwaste Resin [
C-14 1.02% Hn-54 1.36% Mn-54 1.04% .
Mn-54 1.24% Co 4.5% Co-58 4.42%
4 Fe-55 29.47% -Co-60 3.43% Co-60 8.26% ,
! Co-58 1.02% Cs-134 35.04% Cs-134 19.51%
4 Co-60 19.19% Cs-137 38.95% Cs-137 24.67% "
. Cs-134 4.58% H-3 0.00084% H-3 2.79%
! Cs-137 27.31% C-14 1.46% C-14 4.01%
l Ni-63 10.79% Fe-55 3.14% -Fe-55 4.32% >
j- Tc-99 0.84% Ni-63 7.56% Tc-99 0.0028%
i 1-129 0.21% Sr-90 0.0049% I-129 0.0035%
Cm-242 0.011% Tc-99 0.0041% Ni-63 20.03%
H-3 1.78% 1-129 0.001% Sr-90 0.08%
! St-90 0.26% Pu-239 1.9E-5% Sb-125 10.83% ,
, Sb-125 0.55% Pu-238 4.5E-5% Pu-238 0.00033%
! Pu-239 0.005% Cm-244 5.5E-5% Pu-241 0.029%
4 Pu-241 1.6% Pu-241 .0068% Am-241 0.00032%
i Am-241 0.015% Sb-125 4.5% Cm-242 ~0.00044%
- Cm-244 0.082% Cm-242 3E-5% Cm-244 0.00034% '
l l B. There were no major changes or modifications to the PCP or to sny liquid _ ;
- gaseous or solid radwaste-treatment systems for-this period.--Byron Station
! coatinues to utilize the services of Nu Pac for dewatering and solidification services, l
C. Error Analysis The following is an estimate of the errors associated-with effluent monitoring and analysis. The estimate is calculated using the square root of the sum of the squares methodology.
l
- 1. Gaseous Effluents h Sampling error = 1 to 3.5%
- Calibration error. = 10%
l Counting Statistics error- + -5%
Vent Stack F,lowrates error a 1.3%
Total erior = 11-- 12%
~27-
_ _ . _ _ . _ - ~~ .. _ _ . _ . _ , _ . . . _ , . _ . _ . . - _ _ .-____.m__.,._...__..__._.,. ,._ , . . , , .
4
- 2. Liquid effluents Sampling error = 1%
Calibration error = 10%
Sample volume error = 1%
Discharged volume error = 2%
Total error = 10%
- 3. Waste Resin Sampling error = 5%
Counting Statistics error = 7%
Weight error = 1%
Volume error = 5 %.,
Total error = 104
, 4. DAW Counting Statistics error = 7%
Calibration error = 10%
Weight error = 2%
Total error = 12.4%
D. Meterological and environmental impact information is reported in the Station Annual Radiological Environmental Operating Report as required by Technical Specifications 6.9.1.6.
E. No limits were exceeded in liquid hold up tanks as stated in Technical Specifications 3.11.1.4 or in waste gas decay tanks as stated in Technical Specifications 3.11.2.6.
F. There was no. irradiated fuel shipments during this period..
G. There was no elevated releases. All releases are considered ground level releases.
e
I !
1 i
4 ATTACHMENT A l BYRON NUCLEAR POWER STATION l
- SEMI ANNUAL EFFLUENT REPORT FOR JANUARY THROUGH JUNE 1992 i
UNIT 1 and 2 (DOCKET NUMBERS 50-454 and 50-455) ;
i LLD VALUES FOR CASEOUS RELEASES ,
i
! Isotopes LLD(Ci/M1) 1 X3-133 4.78E-12 ;
Xe-131m 2E-11 !
! Xe-133m .3.75E-12 l Xe-135m SE-013
- Xe-135 4.09E-013
- Kr-85m 2.73E-12 i Kr-85 1.1E-12 ,
Kr-87 8.31E-13 I
.Kr-88 1.54E Ar-41 4.4E-0, I-131 9.04E-19 I-132 1.07E-18 I-133 9.56E-19 1-134 9.55E-19 !
I-135 3.64E-18 Mn-54 7.4E-19 i Fe-59 1.31E-18 Co-58 7.22E-19 l
~
Co-60 1.21E-18 ?
Sr-89 2.25E-12 Sr-90 7.5E-13 Y-88 5.42E-19 7.21E-19 Ru-103 Ag-110m 8.9]E-19 Cs-134 1.19E-18 Cs-136 6.76E-19 Cs-137 1.01E-18 Ba/La-140 3.05E-18 Ce-144 4.82E-18 !
I l - 1 I
',,,-~~...,,.m 3be.. .',o.- v- w . . ,,,,-ver---,.-,e ,,,,.---,,--,w-e,.._,.w...c~,,,,c...m---~m,w.r.m.-,w-.- - - - . ..,r-- * * , .,m ..wer r c .e
1 !
' o l i 1 ,
a 1
ATTACllMENT A i (cont.)
l BYRON NUCLEAR POWER STATION .
l SEMI ANNUAL EFFLUENT REPORT FOR JANUARY THROUGH JUNE.- 1992 UNIT 1 and 2 (DOCKET NUMBERS 50-454 and 50-455) j LLD VALUES POR LIQUID RELEASES ,
i Isotope LLD (Ci/M1) I j Sr-89 9.75E-15 Sr-90 3E-15 '
l Fe-55 6E-15 Cs-134 5.32E-14 -
Cs-136 4.50E I-131 4.91E-14 1-133 5.12E-14 .)
Ba/La-140 3.37E-14 '
Xe-135 4.02E-14 4 Cr-51 3.85E-13 Mn-54 4.92E-14 4
Fe-59 8. 53 E- 14 i l Co-57 4.42E-1A Nb-95 4.87E-14 !
Zr-95 -8.9E-14 Hf-181 5.5E Sb-125 1.46E-13 Mn 56 4.8E-14 Sn-113 1.8E Xe-135m 5.5E-14
- Xe-131m 1.8E-12 Yb-169 1.~1E-13 Sn-117m 4.3E-14 Ru-103 SE-14 Zn-65 9.6E-14 '
Sb-124- 5.25E-14 Ce-144 3.51E-13 Xe-133m 3.64E-13 Ag-110m 6E-14 Ba-133 6.6E-14 Ni-65 -1.9E-13 Ru-105 9.5E-14 -
I-135 1.9E-13' Te-125m 1.26E-13 Ba-141 7.4E-14 l
, _ . , - , - , , , , - - , . . . - . . . - . , , , . . - - , - - - - - - - . , - , , . - . _ . . - . , - - - - ~ - . . _ . ~ , - - . - - . - . . ~ , . . - . , . . . - - , . -