ML20028G788

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Semiannual Radioactive Effluent Rept for Jan-June 1990 for Dresden Nuclear Power Station
ML20028G788
Person / Time
Site: Dresden  
Issue date: 06/30/1990
From: Eenigenburg E
COMMONWEALTH EDISON CO.
To: Bradley Davis
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
NUDOCS 9009040156
Download: ML20028G788 (58)
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Text

{{#Wiki_filter:- - -..........,, O Commonwealth Edison Dr*Sdsn Nuclear Power Station RA #1 Morris, it!inois 60450 Tekphorw B15/942-2920 August 15, 1990 EDE LTR # 90-517 Mr. Bert Davis Administrator U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn. Illinois 60137 Subject Dresden Nuclear Power Station Operating Report NRC_Ilacket s 50-10. 50-237. 50-26,3 Enclosed is the Radioactive Effluent Report for January through June 1990 for Dresden Nuclear Power Station. A copy of this report will be furnished to the NRC Senior Resident Inspector. Sincerely Yours, i E.D.Eenigenbur! Station Manager Commonwealth Edison Dresden Nuclear Power Station EDE SKlala Enclosure cet S. Kova11 File /NRC File / Numerical Attached Distribution List 002C7 ZR18/116 / 9009040156 900630 ADOCK0500gG DR g

Semi Annual R: port Distribution All St;tions I Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Station P1-137 Washington D.C. 20555 (Original plus one copy) - or - One White Flint North

  • 11555 Rockville Pike Rockville, MD 20852 Illinois Department of Nuclear Safety Office of Nuclear Facility Safety 1035 Outer Park Drive Springfield. IL 62704 ANI Librarian I - Tech Processing The Exchange, Suite 245 270 Farmington Ave Farmington, CT 06032 B.P.I 109 North Dearborn St.

Suite 1001 l Chicago, IL 60602 American Electric Power Service Corp. I Nuclear Operations Division 1 Riverside Plaza Columbus, Ohio 43216 (2 copies) U.S. Environmental Protection Agency Air and Radiation Branch, Region V ilealth Physicist 230 S. Dearborn St. Chicago, IL 60606 Illinois Environmental Protection Agency Region III - DWPC/F05 5415 North University Peoria IL 61614 Illinois Environmental Protection Agency Division of Water Pollution Control Environmental Protection Specialist 2200 Churchill Rd Springfield IL 62706 If delivered by private carrier (i.e. Federal Express) l direct carrier to the lower back area of the One White Flint North Bldg, Mail Station P1-137 ZR18/116

Semi Annual R: port Distribution All Stations (Cont'd) Illinois Power Company Clinton Power Station Plant Radiation Protection R.R. #3 Box 228 Clinton, IL 61727 Murray & Trettel Inc Environmental Meteorologist 414 West Frontage Rd Northfield, IL 60093 Teledyne Isotopes Midwest Laboratory General Manager 700 Landwehr-Rd Northbrook, IL 60062 Chemistry Services Chemistry Services Director 1237E Emergency Preparedness Emergency Preparedness Director 1237E Nuclear Quality Programs and Assessments General Manager Suite 300 Opus III West i ZR18/116

Semi Annual R: port Distrib: tion Dresden i Station Manager Dresden Health Physics Services Supervisor l realth Physics Services Dresden NRC Senior Resident Inspector i Dresden General Electric Co Services Project Manager Mail Code 881 175 Curtner Ave San Jose, CA 95125 General Electric Co Plant Manager 7555 E. Collins Road Morris, IL 60450 U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Rd. Glen Ellyn, IL 60137 (1vo Copies) Berline Ferguson Emergency Preparedness 1237E Nuclear Quality Programs Nuclear Quality Programs Eng.ineer Dresden ZR18/116 1

DRESDEN NUCLEAR POWER STATION DOCKET NOS. 50-10, 50-237, 50-249 REGULATORY LIMITS Gaseous Effluents - Dose This Specification is provided to ensure that the dose at the unrestricted area boundary f rom gaseous ef fluents f rom the units on site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. The annual dose limits are the doses associated with ;he concentrations of 10 CFR Part 20, Appendix B. Table II. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area to annual average concentrations exceeding the limits specified in Appendix B. Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)). The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the unrestricted area boundary to less than or equal to 500 mrem / year to the total body or to not less than or equal to 3000 arem/ year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to not less than or equal to 1500 mrem / year. For purposes of calculating doses resulting from airborne relentes, the main chimney is considered to be an elevated release point and the reactor building vent stack is considered to be a mixed mode release point. Dose. Noble Gases This Specification is provided to implement the requirements of Sections 11.B. III.A and IV.A of Appendix 1, 10 CFR Part 50. The Limiting Conditions For Operation implement the guides set forth in Section II.3 of Appendix 1. The statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated. The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents will be conciatent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111 " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1. July 1977. The ODCM equations provide for determining the air doses at the unrestricted boundary based upon the historical average atmospheric conditions. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111. ZR18/116 1 of 32

.DRESDEN NUCLEAR POWER SIATION DOCKET NOSo 50-10, 50-237 50-249-Dose, Radioiodines, Radioactive Material in Particulate Form and Radionuclides Other than Noble Gases This specification is provided to implement the requirements of; Sections 11.0, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Conditions for Operation are the guides set forth in Section II.C of Appendix I. The statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the relt.ses of radioactive materials in gaseous effluents will be'kept "as low as reasonably achievable." The ODCM calculational methods specified in the surveillance requirements implement the requirements in Section III.A . of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the 1 actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational m%chods approved by NRC for calculating the doses due to the actual - release rates of the subject materials are required to be consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for g I the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric' Transport and Dispersion of Gaseous Effluents'in Routine Releases from Light-Water-Cooled Reactors," Revision l', July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for radioiodines, radioactive material in particulate form and radionuclides other than noble gases are dependent on the' existing radionuclide pathways to man, in the unrestricted area. The pathways which were examined in the development of these specificationv were

1) individual int alation of airborne radionuclides,,) deposition of radio aclides onto green leafy vegetation wl:

subsequent consur-e ion by man and 3) deposition onto c grassy areas wnere milk animals graze with consumption of the milk by - man. o i + i-i i L l L r l l - ZR18/116 2 of 32

'DRESDEN NUCLEAR POWER STATION DOCKET NOS. 50-10. 50-237, 50-249 . Gaseous Waste Treatment The OPERABILITY of the gaseous waste treatment which reduces amounts or concentrations of radioactive materials ensures.that the system will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of-this system be operable when specified provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as reasonably achievable". This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and design objective Section II.D of Appendix I to 10 CFR Part 50. LIMID EFFLUD1IS Concentration l This specification is provided to ensure the concentration of l radioactive materials released in liquid waste effluents from the site to unrestricted areas will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2. The concentration limit for noble gases, MPC in air (submersion), was j converted to an equivalent concentration in water using the l International Commission on Radiological Protection (ICRP) Publication f 2. Dose 1 This specification is provided to imple.ent the requirements of j Sections II.A. III.A and IV.A of Appendix I, 10 CFP Part 50. The -l Limiting Condition for Operation implements the guides set forth in l [ Section II.A of Appendix I. The statements provide the required operating flexibility and at the same time implement the guides set forth in Se.: tion IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as reasonably achievable". The dose calculations in the ODCM implement L the requirements in Section III.A of Appendix I that conformance with L the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to 'i the actual release rates of radioactive materials in liquid effluents will 1e consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor ECfluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", Revision 1, October 1977 and Regulatory Guide 1.113. " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Deactor Releases for the Purpose of Impicmenting Appendix I", April '971. NUREG-0113 provides methods for dose calculations with Reg Guide. 109 and 1.113. I: ZR18/116 3 of 32

DRESDEN-NUCLEAR POWER STATION DOCKET NOS. 50-10, 50-237, 50-249-q .y Liquid Waste Treatment The operability of the liquid radwaste treatment system' ensures that this system s' " Le available for use whenever liquid effluents require . treatment prio, t4 release to the environment. The requirement that -the appropriate ;ortions of this system be used when specified provides assurance that the releases of radioactive materials in liquid l ef fluents will be A*pt "as low as reasonably achievable". This specification implemeni; the -aa,uirements of 10 CFR Part 50 and design objective-Section II.D of Appendix I to 10 CFR Part 50. 1 i i f l l ZR18/116 4 of 32 i I.

DRESDEN NUCLEAR POWER STATION DOCKET NOS, 50-10, 50-237, 50-249 MAXIMUM PERMISSIBLE CONCENTRATIONS (MPC) The concentration of radioactive materials released in gaseous and liquid effluents from the site to unrestricted areas will be less than the concentration levels specified in 10 CFR Part 20 Appendix B, Columns 1 and 2. The concentration limit for noble gases, MPC in air (submersion), was converted to an equivalent concentration in water using. the International Commission on Radiological Protection (ICRP) Publication 2. MAXIMUM PERMISSIBLE CONCENTRATION OF DISSOLVED OR ENTRAINED NOBLE GASES RELEASED FROM THE SITE TO UNRESTRICTED AREAS IN LIQUID WASTE NUCLIDE MPC(uci/ml)* Kr-85m 2.0E-04 Kr-85 .5.0E-04 Kr-87 4.0E-05 Kr-88 9.0E-05 Ar-41 7.0E-05 Xe-131m 7.0E-04. Xe-133m 5.0E-04 Xe-133 6.0E-04 Xe-135m 2.0E-04 Xe-135 2.0E-04 Com'mted from Equation 20 of ICRP Publication 2 (1959), aJjusted for infinite cloud submersion in water, and R = 0.01 rem / week, density = 1.0 g/cc and Pw/Pt = 1.0. l l l 2R18/116 5 of 32

^ 'DRESDEN NUCLEAR POWER STATION DOCKET NOSa 50-10, 50-237, 50-249 AVERAGE ENERGY The average energy of fisdion and activation gases was calculated for the gaseous effluents released from the site.. The average energy is based on the percentage of each fission gas nuclide present.and its average energy per disintegration (E in MeV/ dis) for gamma and beta emissions separately. Eg = 3.85E-01 MeV/ dis EB = 3.05E-01 MeV/ dis 1 'I 4 'l 'l 4 i o I ZR18/116 6 of 32

DRESDEN NUCLEAREPOWER STATION DOCKET NOS. 50-10, 50-237.-50-249 MEASUREMENTS AND APPROXIMATIONS A. Fission and activation gases: The D-1 chimney, D2/3 chimney and D2/3 Reactor Building Vent are sampled weekly via a grab sample.- The samples are analyzed for specific isotopes present in the release using a Hyper-Pure Germanium (HP Ge) Spectrometry System. Tritium is sampled monthly via a grab sample on the D-1 chimney, D2/3 Chimney, and D2/3 Reactor Building vent and analyzed using a Liquid Scintillation Counter. Krypton-85 is estimated in the D2/3 chimney using a recoil or non-recoil calculation using the fission per second plot and the sum of Kr-85m, Kr-87 Kr-88, Xe-133, Xe-135, and Xe 138 activities present in Reactor.0ff-Gas. B. Iodine and Particulate: Iodine and particulate samples from the D-1 Chimney, D2/3 Chimney and the D2/3 Reactor Building Vents are collected for a maximum seven day period. These samples are analyzed for specific nuclides present in the release using a HP Ge spectrometry system. When iodine or particulate samples are not used for reporting the release rate due to management decision that the sample may not be representative, an average of the preceding sample and the following sample is used.to calculate the release. A monthly composite of the particulate samples is sent to a vendor to be analyzed for Fe-55, Sr-89, Sr-90, and Gross Alpha activity. C. Liquid Effluents: Analyzed for specific isotopes present in the release using a HP Ge spectrometry system. A composite of all batches for the month is sent to a vendor to be analyzed for l Sr-89, Sr-90, Fe-55, H-3, and Gross Alpha activity. A sample of l1 each Containment Cooling Service Water (CCSW) system is analyzed each month for specific isotopes present in the release using a HP Ge spectrometry system. A sample of each CCSW system is sent each month to a vendor to be analyzed for Sr-89, Sr-90, Fe-55, H-3, and Gross Alpha activity. l D. Estimation of Overall Errors: The methods used for estimating L overall errors associated with radioactivity measurements vary with discharge path and form of isotopes. Factors that contribute to the error include such items as calibration of counting equipment,-counting statistics, sampling error, discharge volume, and flow rate monitors. E. Estimation of Vendor Analyzed Information: The vendor analyzed data for Sr-89, Sr-90, Fe-55. H-3, and Gross Alpha was projected, where applicable, for the months of May and June using April data for liquid effluents. The vendor analyzed data for gaseous effluents was projected, where applicable, for the months of April, May, and June using March data. A corrected Effluent Report will be submitted with the next Semi-Annual Effluent Report. ZR18/116 7 of 32

DRESDEN NUCLEAR POWER STATION UNITS 1,2, AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January Through June 192D GASEOUS EFFLUENTS Docket Numberst 50-10 50-237 SUMMATION OF ALL RELEASES 50-249 EST. TOTAL TYPE OF RELEASE UNITS 111 QUARTER 2nd QUARTER ERROR,% FISSION AND ACTIVATION GASES 1. Total Release Ci 3.48E+00 9.06E+00 7.31 2. Average Release Rate for Period uCi/sec 4.48E-01 1.15E+00 3. Percent of Technical Specification Limit A A at. 103INES 1. Total' Iodine-131 Ci 4.66E-04 1.18E-03 9.51 2. Average Release Rate of I-131 for Period uCi/sec 5.99E-01 1.50E-04 3. Percent of Technical Specification Limit A A 4. Total Iodine-131, Iodine-133.and Iodine-135 Ci 6.27E-03 2.31E-02 C2_._fARTICM1ATES 1. Particulates with half-lives > 8 days Ci 7.39E-02 1.31E-02 8.09 2. Average Release Rate for Period uCi/sec 9.50E-03 1.67E-03 3. Percent of Technical Specification Limit A A 4. Gross Alpha Radioactivity Ci 4.18E-06 5.13E-07 D. TRITIUM 1. Total Release Ci 3.19E+00 4.05E+00 7.89 2. Average Release Rate for Period uC1/sec 4.10E-01 5.15E-01 3. Percent of Technical Specification Limit A A A The information is contained in the Radiological Impact on Man section of the report. Total airborne release data is provided which includes fission and activation gases, iodines, particulates, and tritium. ZR18/116 8 of 32

DRESDEN NUCLEAR POWER STATION = UNITS 1,2, AND 3 -EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January Through June 1920 GASEOUS EFFLUENTS Docket Numbers: 50-10 50-237 SUMMATION OF ALL RELEASES' 50-249 LLD (uCi/cc) 1. FISSION GASES Kg-118 1.47E-07~ Ke-135m 6.36E-08 Kr-87 3.62E-08 Kr-88 5.80E-08 Kr-85m 1.RQE-08 Kr-85 4.36E-06 Ke-135 1.63E-08 Xe-133= 4.0BE-08 Ar-41 2.29E-08 2. 10 DINES I-131 8.08E-13 1-133 5.19E-12 1-135 9.32E-10 3. PARTICULATES St-89 5.00E-15 Sr-90 1.70E-15 Cr-51 6.21E-13 Mn-54 7.77E-14 Co-58 6.37E-14 Fe-55 1.10E-13 Fe-59 1.38E-13 Co-60 1.94E-13 Zr-95 1.37E-13 Nb-95 7.65E-14 30-99 1.02E-12 Rn-103 7.71E-14 An-110m 7.Q6E-14 Sb-124 7.70E-14 1-131 9.38E-14 Cs-134 7 21E-14 Cs-136 7.67E-14 CA-137 8.52E-14 Ba-140 3.11E-13 La-lhQ 1.17E-13 Ce-141 1,13E-13 ge-144 4.47E-13 Zn-65 1 11E-13 2 Da-133 9.51E-14 Sb-125 1 93E-13 Others: Gross Alpha 3.00E-15 ZR18/116 9 of 32 l

P DRESDEN NUCLEAR POWER STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January Through June 1910 D1 Chimney GASEOUS EFFLUENTS GROUND LEVEL RELEASES Docket Number: 50-10 s SEMI-ELEVATED RELEASES XX ELEVATED RELEASES s CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT ist QUARTER 2nd QUARTER ISI QUARTER 2nd QUARTER FISSION GASES __. Xe-138 C1 I Xe_135m .C1 Kr-87 Ci Kr-88 Ci Kr-85m C1 Kr-85 C1. Xg-1.35 Ci Xe-133 Ci 'TOIAL Ci NQHE NONE IO111HES I-131 Ji I-133 Ci ._I-135 Ci TOTAL Ci NONE NONE PARTICULATES SI-89 Ci Sr-90 01 2 42E-07 Cr-51 C1 Mn-54 01 i Co-58 C1 Fe-59 C1 Co-60 Ci 5 1t'E-06 9.47E-06 2r-95 Ci_ Nb-95 C1 Ru-103 Ci Ag-110m .C1 Sb-124 Ci I-131-C1 _ CB-L34 AL_ P -136 C1 A CA-137 .Ci 9.91E-06 8.08E-06 Ba-140 Ci Ce-141 Ci Ce-144 Ci Zn-65 C1 Ea-133 Ci Sb-125 Ci Fs-55 Ji .___IDIAL Ji 1.55E-05 1.76E-05 NONE NDRE

  • The activity of this nuclide is less than the LLD listed on the appropriate table.

ZR18/116 10.-i 32

DRESDEN NUCLEAR POWER STATION LM.lT 1 EFFLUENT AND kASTE DIbPOSAL SEMIANNUAL REPORT _ January __._ Through March 19.20 D1 Chimnev GASE0US EFFLUENTS GROUND LEVEL RELEASES 9 Docket Number: 50-10 i SEMI-ELEVATED RELEASES XX ELEVATED RELEASES CONTINUOUS MODE NUCLIDES RELEASED UNIT JANUARY FEBRUARY MARCH 1s1 QUARTER TOTAL FISSlDtLEASES .Xc-138 C1 Xe-135m ._Ci_ i Kr-87 __ C 1 Kr-88 C1 Kr-85m ._C1._ Kr-85 C1 l Xe.135 C1 Xe-133 C1 TOTAL 01_ 10 DINES I-131 .Ci__ I-133 C1 1:135 _ C1 IQIbL Ji PARI 1CULATES Sr-89 01 Sr-90 C1 2.A2E-07 2.42E-07 ~ -fr-51 _C1 11n-54 _Ci_ ,____fo C1 Fe-59 01 Gn-60 01 6.26E-07 6.04E-06 2.80E-06 9.4ZE-06 l Zr-95 Ci Nb-95 _Ci_ Ru-103 Ci Ag-110m Ci_ Sb-124-31_ l _13.1 Ci Ca:L34 Ci Cg_136 C1 CR-137 Ci 2.87E-06 4.30E-v6 9.05E-07 8.08E-06 Ea-140 Ci Ce-141 _01 qe-144 Ci Zn-65 C1 Ba-133 _ Ci Sh:125 Cl-Ee:55 ._C1._ _;._T0IAL - C1 3.74E-06 _1.03E-05 3.71E-06 1.78E-05

  • The activity of this nuclide is less than the LLD listed on the appropriate table.

i ZR18/116 11 of 32

DRESDEN NUCLEAR POWER STATION UNIT 1-EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT April Through June 192Q p1 Chimnev. GASEOUS EFFLUENTS-GROUND LEVEL RELEASES Docket Number: 50-10 SEMI-ELEVATED RELEASES XX ELEVATED RELEASES CONTINU0US MODE NUCLIDES RELEASED UNIT APRIL MAY JUNE 2.nd QUARTER TOTAL FISS.10R_ CASES _ Xe-138 _EL Je _125m Ci Kr-87 Ci Kr-88 Ci Kr-85m C1 Kr-85 _Ci_ Xe-135 C1 Xe-133 li_ TQIAL Ci 10D1HE.S 1-131 _Ci_ I-133 _.01 I-135 C1 TQIAL C1 PARTLCUMIES Sr-89 Ci Sr-90 Ci Cr-51 Ci Mn-54 Ci Co-58 01 Fe-59 C1 Co-10 C1 4.73E-06 _S_.36E-08 5.04E-07 5.381-06 Zr-95 Ci Nb-95 Ci En-103 C1 Ag-110m Ci Sb-l_24 .Ci 1-131-Ci Ca-134 ,_qi_ Cs-136 C1 Ca-137 JL 2.32E-06 6.92E-06 6.73E-07 9.91E-06 Ba-Ut0 _C1 1e-141 Ci Xe-144 C1 Zn-65 Ci ___Da_l33 _CL Sh-125 _CL, Fe-55 C1 TOTAL,_, Ci 7 11E-Q6_ 7.00E-06 1.18E-06 1.53E-05

  • The activity of this nuclide is less than the LLD listed on the appropriate table.

ZR18/116 12 of 32

E I DRESDEN NUCLEAR POWER STATION-

+'

UNITS.2 AND 3 l p EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT .'_ January Through -Junt_ _ 1910 1 H1/3 Chimney GASEOUS EFFLUENTS GROUND LEVEL RELEASES Docket Numbers:. 50-237 SEMI-ELEVATED RELEASES 50-249 XX ELEVATED RELEASES CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT 111 QUARTER 2nd QUARTER 131 QUARTER 2nd QUARTER -FISSION GASES 1c-118 Ci Ke-135m _Ci 8.18E-01 Kr-87 Ci Kr-88 Ci 8.76E-01 Kr-85m Ci 'Kt:85 Ci Xe-135 Ci 2.66E+00 8.12E+00 Xe-133 Ji Ar-41 Ci 6.22E-02 -TOTAL C1 3.48E400 9.06E+00 NONE NONE IDDINES 1-111 C1 3.79E-04 1.08E-03 I-133 Ci_ 2.20E-03 6.15E-03 I-135 C1 2.27E-03 1.32E-02 IQIAL _Ci_ 4.85E-03 2.04E-02 NONE NONE PARTICULATES Sr-89 _Ci_ 1.37E-04 2.74E-04 Sr-90 _Ci_ 2.19E-06 4.87E-06 Cr-51 C1 fin-54 _Ci_ 2.73E-05 8.16E-06 00-58 _Ci_ F.g-59 C1._ Co-60 01 1.83E-04 1.30E-04 l At-15 Ci l ' Ru-103 Ci Nb-95 JL_ _Ag.-llQm C1 Sb-124 Ci J_111 C1 4.23E-05 1.56E-04 Cs-134 J1._ Cs-136 Ji Cs-137' C1 4.64E-06 8.43E-05 fa-140 C1 2.40E-02 8.57E-04 La-140-C1 2.93E-03 1.45E-03 Ce-141 Ci _. Z.n-65 _Ci_ Ba-133 Ci Sb-115 Ji_ Fe-55~ _Di_ 4.83E-04 2.39E-04 TOI6L' C1 2.78E-02 3.21E-03 NONE N0llE

  • The activity of this nuclide is less than the LLD listed on the appropriate table.

ZR18/116 13 of 32

DRESDEN NUCLEAR POWER STATION UNITS 2 AND 3 EFFLUFET AND WASTE DISPOSAL SEMIANNUAL REPORT _ January Through __ March __ 191Q D2/3 Chimney GASEOUS EFFLUENTS GROUND LEVEL RELEASES Docket Numbers: 50-237 SEMI-ELEVATED RELEASES 50-249 XX ELEVATED RELEASES CDHIH RQMS MODE NUCLIDES RELEASED UNIT JANUARY FEBRUARY MARCH ls_t QUARTER TOTAL-FISSION GASES Xe-138 01 He-135m. C2 8.18E-01 8.18E-01 Kr-87 C1 Kr-88 Ci Kr-85m Ci Kr-85 C1 Xe-135 Ci_ 2.66E+00 2.66E+00 Xe-133 Ci Ar-415 C1 TOTAL C1 3.48E+00 3.48E+00 10DR ES 1-131 _C1 4.01E-05 2.54E-05 3.13E-04 3.79E-04 I-133 C1 2.14E-04 4.14E-04 1.57E-03 2.20E-03 1-13L_ Ci 2.27E-03 2.27E-03 IQIAlu Ci 2.55E-04 4.39E-04 4.15E-03 4.85E 03 EhEIlCUlATES __ SI-39 C1 1.86E-05 2.24E-05 9.58E-05 1.37E-04 SI;.20 _Ci 4.96E-07 1.69E-06 2.19E-06 C_r-51 C1 _Mn-54 C1 2.31E-05 4.16E-06 2.73E-05 Co-58 _C1 Fe-59 C1 _Co-60 Ci 5.14E-05 5.24E-05 7.94E-05 1.83E-04 Zr-95 C1 Nh-95 _C_1 Ru-103 C1 Ag-110m Ci__ Sb-124 _QL 1-131 Ci L!iQE-06 3.99E-05 4.23E-05 Cs-134 Ci Cs-136 _Ci L itE-06 Cs-13.7 Ci 4.64E-06 t _ __Da-140 _.C1_ 4.73E-05 1.13E-04 2 38E-02 2.40E-02 ____La-140 ,_CL 4.73E-05 1.58E-04 2.72E-03 1.93E-03 Ce-141 Ci Zn-65 __ Ci Ba-133 _Ci_ ___Sb_l25 _CL Fe_55 Ci 2.73E-04 1.27E-04 8.31E-05 4.33E-04 TQIAL C1 4.68E-04 4.73E-04 2.68E-02 2.78E-02

  • .he activity of this nuclide is less than the LLD listed on the appropriate table.

ZRl8/116 14 of 32

DRESDEN NUCLEAR POWER STATION UNITS 2 AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT- __APJtil____ Through _Junn___1910 D2/3 Chimney GASEOUS EFFLUENTS GROUND LEVEL RELEASES Dochet Numbers: 50-237 SEMI-ELEVATED RELEASES 50-249 XX ELTVATED RELEASES CONIINUOUS MODE NUCLIDES RELEASED UNIT APRIL MAY JUNE 2nd QUARTER TOTAL FISSION GASES Xe:138 Ci Xerl35m Ci Kr-87 Ci 1(r-88 Ci 8.76E-01 8.76E-01 Kr:85m Ci Kc-85 _Ci_ Xe-111_ Ci 3.48E+00 1.81E+00 2.83E+00 8.12E+00 _Ke-133 _Ci _ _Ar-41 - 01 6 22E-Q' 6.22E:02 IQIAL _Ci_ 4.36E+00 ld7EtDR 2 83E+00 9.06E+00 10 DINES I-131 __ C i 3.22E-04 4.27E-04 3.34E-04 1.08E-03 1:133 Ci 1.84E-03 2 50E-03 1.81E-03 6.15E-03 L l35 li_ 6.08E-03 4.43E-03 2.69E-03 1112E-02 TOTAL 01-8.24E-03 7.36E-03 4.83E-03 2.04E-02 EARTICULATES Sr-89 Ci 8.50E-05 9.89E-QS 9.15E-Qi__ 2.75E-04 Sr-90 Ci 125DE-06 1.75E-06 1 6.2E-06 4187E-06 Cr-51 C1 tin-54 _C.i - 8.16E-06 8.16E-06 C -58 Ci 9 Fe-59 C1 Co-60 Ci 7.99E-05 3.23E-05 1.76E-05 1.30E-04 Er-95 Ci_ Nb_-95 _ _Qi_ Runiq3 Ci Ag llDm ._Ci_ _Sh:124 ._C1._ .1:131 ._C i 3d5E-95 8.89E-05 3.05E-05 1.56E-04 0s-134 Ci ..._.Ca:116 _Ci _ _ Ce-137 _Qi 2.78E-05 4.67E-05 9.75E-06 8.43E-05 Ba-1A0 Ci 2 52E-04 ldSE-04 2 6]E-D4 8.57E-04 La-140 Ci_ 4.82E-04 6.17E-04 3.48E-04 1.45E-03 Cc-141 Ci 2n-65 Ci h-133 _C1_ Sh:L25 Ci Fe-55 Ci L.38E-Q5 J JSE-05 7 9AE-05 2 d2E-04 ,_.IQIAL _Ci_ 1,.Q5E-03 1.31E-03 8.45E-04 3.21E-03

  • The activity of this nuclide is less than the LLD listed on the appropriate table.

ZR18/116 15 of 32 l 1

DRESDEN NUCLEAR POWER STATION' UNITS'2 AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January Through-March 1920 D2/3 Reactor Building _Ynnt GASEOUS EFFLUENTS GROUND LEVEL RELEASES Docket Numbers: 50-237 XX SEMI-ELEVATED RELEASES 50-249-ELEVATED' RELEASES CONTINU0UG MODE EATCH MODE NUCLIDES RELEASED UNIT ljtt QUARTER 2nd QUARTER la.t QUARTER 2nd QUARTER FISSION GASES Xe-138 Ci-Te-135m _Ci_ Kr Ci Kr-88 C1 Kr-85m Ci Kr-85 C1 Ke-135 _.CL Xe-133 C1-TQIAL Ci NONE NONE 10 DINES I-131. C1 8.66E-05 1,.03E-04 I-133 Ci 8.36E-04 4.43E-04 1-135 C1 4.99E-04 2.11E-03 TOTAL __C1 1.42E-03 2.66E-03 NONE NONE PARTICULATES Sr.-89 C1 5.87E-05 3.23E-05 Er-90 Ci 5.93E-06 1.lhE-04 Cr-51 _Ci_ 7.32E-03 t Mn-54 C1 2.81E-03 7.54E-04 C0-58_ _CL 8.53E-04 ldBE-04 Fe-59 _fi l'.58E-03 1.66E-04 Co-60 C1 6'74E-03 2.0SE-03 Zr-95 C1 Nb-95 C1 Ju-103 C1 Ag-110m _C1 1.25E-04 1.l0E-04 Sb-124 _Ci t I-131 C1 1.41E-05 Ca-13ti C1. Qa-L36 Ci Cs-137 _CL Ba-140-01 4.18E-04 1.51E-05 l _1,a-140 Ci 5.43E-04 1.51E-05 Cc-lsl _.Ci_ 7,n-65 01 2.85E-04 No-99 Ci_ 2.97E-03 8.59E-04 Sh-125 Ci Ee-55 _CL 2.20E-02 5.66E-03 i. _IQIAL C1 _h5HE-02 9.93E-03 NONE NONE

  • The activity of this nuclide is less than the LLD listed on the appropriate table.

ZR18/116 16 of 32

DRESDEN NUCLEAR POWER STATION UNIT 2 AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January Through._Jatch___. 1910 D2/3 Raaetor Buildine Vent GASEOUS EFFLUENTS GROUND LEVEL RELEASES Docket Numbers: 50-237 i XX SEMI-ELEVATED RELEASES 50-249 i ELEVATED RELEASES CONTINUOUS MODE NUCLIDES RELEASED UNIT JANUARY FEBRUARY MARCH 111 QUARTER TOTAL FISSION GASES Xc:138 _Ci_. Xe-135m C1 Kr-87 C1 Kt-88 C1 Kr-85m .C1 Kr-85 _Ci_ Xc-135 Ci Xe-133 C1 TOTAL Ci .1@IES I-131 _C1 3.08E-05 4.18E-05 1.40E-05 8.66E-05 I-133 _.C1 4.17E-04 3JhE-04 5.52E-05 8.36E-04 I-135 Ci 4.99E-04 4.99E-04 TQTAL _Ci._ 9.47E-04 4.06E-04 6.92E-05 1.42E-03 EARI1CilLATES Sr-89 01 4.80E-05 1.07E-05 5.87E-05 Sr-90 Ci 5.70E-06 2.26E-07 5.93E-06 Cr-51 C1 3.52E 3.75E-03 5.02E-05 7.32E-03 Mn-54 C1 1.83E-03 7.23E-04 2 5BE-04 2.81E-03 Co-58 . C1. 4.92E-04 2.78E-04 8.26E-05 8.53E-04 Fe-59 Ci 9.80E-04 5.73E-04 2.54E-05 1.58E-03 Co-60 C1 3.55E-03 2.37E-03 8.L8E-04 6.74E-03 Zr-95 Ci Jb-95 C1 Ru-103 C1 An-110m Ci 6.30E-05 6.23E-05 1.25E-04 Sh-124 C1 1,1pE-04 1.40E-04 I-131 _Ci Cs-134 C1 Cs-136 Ci CS-137 Ci 13a-lh0 C1 1 d3E-04 3.,91E-04 4dHE_Q4 __,.._La-140 Ci_ 1 l3E-04 4.30E-04 5.43E-04 I;e-1A1 Ci 2n-65 C1 1.75E-04 1.10E-04 2.85E-04 Mq 99 C1 6.44E-04 2 11E-03 2.13E-04 2.97E-03 Sb-125 C1 Fe-55 . _.01. 1 2hE-02 7.h8E-03 1.89E-03 2.20E-02 _._.IllIAL C1 2.40E-02 1.8AE-02 3.35E-03 4 5BE-02

  • The activity of this nuclide is less than the LLD listed on the appropriate table.

ZR18/116 17 of 32

W DRESDEN NUCLEAR POWER STATION UNITS 2 AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT C April Through June 1910 D2/3 Reactor Buildinn Vent GASEOUS EFFLUENTS GROUND LEVEL RELEASES Docket Numbers: 50 237 XX SEMI-ELEVATED RELEASES 50-249 ELEVATED RELEASES CONTINUOUS MODE NUCLIDES RELEASED UNIT APRIL MAY JUNE 2nd QUARTER TOTAL FISS10H_DASIS Ke-138 _.01 Xe-135m-31. Kr-B1 _Ci Kr-88 _Ci i Kr-83HL._ Ci _ J r-85 _Ci__ Xe-135 Ci Xe-133 C i _. _ _IDIAL Ci 10I!INES 1-131 CL_ 2.89E-05 2.40E-05 5.01E-05 1.03E-Oh I-133__ Ci 8.98E-05 1.05E-04 2 d8E-04 4.43E-04 I-135 _Ci 1.88E-03 2.32E-04 2.11E-03 TQIAL .-._Ci__ 1.19E-04 2 d1E-03 5.30E-04

2. 66 E-03 PARTICULATES Sr-89 01 1.04E-05 1.17E-05 1.02E-05 3.23E-05 Sr-90 C1 Cr-51 Ji_

1.44E-04 1.4lE-04 t Mn-54 _, 01 2.06E-04 1.51E-04 3.97E-04 7 5hE-04 00-58 01 5.55E-05 6.24E-05 6.99E-05 13BE-04 Fe-59 Ci 2.89E-05 6.00E-10 1 37E-04

1. 66 E-04 0 _,C.L 7.58E-04 6.42E-04 6.78E-04
2. 08 E-03 9

Zr-95' Ci Nb-95 Ci Ru 103 Ci 'Ag-llDm Ci Sb-liLIt 01 __-_l-13.1 _Ci_ 1.41E-05 1.41E-05 On-134 Ci CD:l36 Ci .fa-137 01 Ila-lljD_. ' _Ci_. 1 51E-05 1 51E-05 2 La-140 C1 1.J1E05

1. 51E-05 CA-lhl Ci Zn-65 Ci Mo-99 Ci 2.64E-04
2. 7 3E'"

1 21E-04

8. 59E-04 Sb_-125 C1 l-Eg-55 C1 1,.82E-03 2 06E-J3 1,lBE-03 5.66E-03 l

TDJAL Ci_ 3.17E-03 3.20E-03 3.55E-03 9.93E-03 l

  • The activity of this nuclide is less than the LLD listed on the appropriate table.

ZR18/116 i 18 of 32 l l l

DRESDEN NUCLEAR POWER STATION UNIT 2 i, EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT hpuary.. Through June 192.0 D2_Isslation Condenser GASEOUS EFFLUENTS XX GROUND LEVEL RELEASES Docket Number 50-237 SEMI-ELEVATED RELEASES ELEVATED RELEASES CONIIH110MS MODE BATCH MODE NUCLIDES RELEASED UNIT lal QUARTER' 2nd QUARTER lal QUARTER 2nd QUARTER EISSION_ GASES _ Xe-138-Ci Kt-133m __C i Kr-87 .Ci_ Kr-8&, Ci Kr-85m Ji_ Kr-85 C1 Xe-135 _01 )(e-133 _C i_. _IQIAL __ C1_ NONE NDHE NONE 10 DINES 1-131 __C.i_ I-133 C1 I-135 Ci TOTAL _ C1 NONE NONE NONE MRI1CUJAIES_._. SI-R9 C1 S t-90 ~ - C1 Cr-51 _Ci_ Mn-54 C1 00-58 _Ci_ Fe-39 Ci Co-60 C1 4.99E-05 2r-95 _Ci Nb-95 Ci 4 Ru-103 C1 Ag-110m Ci_ _.__Stt-124 Ci I-131 _Ci Gs-134 Ci Cs-13h C1 Ca-131 Ci-Ra-1AD C1 ____La-14.t0 Ci Ce-141-Ci_ Zn_-fi5 C1 ___._Da-113 _01 Sh-l25. Ci Ft-di5__ _Ci_ IQIAL _01 NONE NONE 4.99E-Q5 NONE

  • The activity of this nuclide is less than the LLD listed on the appropriate table.

ZR18/116 l 19 of 32 i l

DRESDEN NUCLEAR' POWER STATION UNIT 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT _. January Through June 1910 t D3 Isolation condenan GASEOUS EFFLUENTS XX .__ GROUND LEVEL RELEASES Docket Number 50-249 SEMI-ELEVATED RELEASES ELEVATED RELEASES C0HIINE0ES_ MODE ._JAIC}l MODE NUCLIDES RELEASED UNIT 1s1 QUARTER 2nd QUARTER ist QUARTER 2nd QUARTER __.__EISSION. GASES _ Xe-138 Cl Xe-135m Ci l Kr-82 Ci Kr-88_. 01 Kr-85m _C1 Kr-85 Ci Xe-135 _C1 _ Xe-133 Ji_ 10JAL C1 NONE NONE NONE 10 DINES I I-131 C1 l:133 J1_ I-135 C1 j TOTAL C1 NONE NONE NONE TARIICULATES Sr-89 C1 Sr-90 Ci f Cr-51 Ci Mn-54 C1 1.48E-05 C0-18 C1 I fe-59 C1 09-60 Ji 4.35E-05 ) l Zr-95 Ci Nb-95 _fi. j j Ru-103 Ji_. _Ag.110m C1 l Sh-124 _fi. I-131 _.Ci_ 18-134 C1 j Gs-136 C1._ i Cs-137 Ci Ba-140 _C1_. La-1A0 C1 _C.e-141 Ci i Ztt-65 _Hi_ . _ _fa-24 C1 2.71E-06 Sb-125 C1 Ee-55 C1 1.32E-04 I0IAL C1 NONE NONE 1.93E-04 NONE

  • The activity of this nuclide is less than the LLD listed on the appropriate table.

ZR18/116 20 of 32 l I i a

DRESDEN NUCLEAR POWER STATION UNITS 1, a, AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT _Januar.y_ Through June 1920 LIQUID EFFLUENTS SIM4ATION OF ALL RELEASES Docket Numbers: 50-10 50-237 50-249 EST. TOTAL UNIT llLt QUARTER 2nd QUARTER ERROR,%. A. FISS10H_AND_ACTIVAT1.QN PRODUCTS

1. Total Release Ci 1.03E-01 1.31E-01 5.58 (not incl. tritium, gases, alpha) 2 Average Diluted Conc. During Period uCi/mL 1.62E-08 9.56E-09

~ 3. Percent of Applicable Limit A A L TRITIUM

1. Total Release Ci 4.74E+00 4.40E+00 7.75
2. Average Diluted Conc. During Period uCi/mL 7.45E-07 3.21E-07
3. Porcent of Applicable Limit A

A CdlSSDLVED_AND ENTRAINED GASES

1. Total Release Ci 0.00E+00 0.00E+00 5.58
2. Average Diluted Conc. During Period uCi/mL 0.00E+00 0.00E+00
3. Percent of Applicable Limit A

A R,_ _ GROSS._ALEllA RADIOACTIVITY

1. Total Release Ci LLD LLD 15.1 E.

VOLUME OF WASTE RELEASED (prior to dilution) liters 9.04E+06 7.11E+06 5.00 . E VOLUME OF DILUTION WATER USED DURING PERIOD liters 6.36E+09 1.37E+10 5.00 A The information is contained in the Radiological Impact on Man section of this report. Total liquid release data is provided which includes fission and activation products, tritium, and dissolved and entrained gases. ZR18/116 21 of 32

n~ DRESDEN NUCLEAR POWER STATION UNITS 1, 2. AND-3 __ January Thrsugh June 191Q TABLE OF LOWER LIMITS OF.DETECTABILITY Docket Numbers: 50 FOR LIQUID EFFLUENTS 50-237 50-249-LLD (uCi/mL) Er-89 2.00E-08 Sr-90 4.00E-09 Mn-54 5.82E-08 0o-58 4.73E-08 [ Fe-59 8.07E-08 Co-60 1 49E-07 Zn-65 1.40E-07 Sb-122 7.35E-08 -Eh-32h 1.09E-07 I-131 5.57E-08 Cs-134 6.74E-08 Cs-137 6.90E-08 Ba-140 2.35E-07 La-140 5.66E-08 Cs-141 -1.00E-07 Xe-133 1.59E-06 Xe-135 6.01E-08 L Cr-51 4.92E-07 Fe-55 3.00E-07 Cs-138 2.28E-07 c' H-3 7.00E-07 Gross Aloha 1.01E-08 a -i } l E f l l l l ZR18/116 22 of 32

DRESDEN NUCLEAR POWER STATION UNITS 1, 2, AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January Through June _ 191Q .__Radwaste LIQUID EFFLUENTS Docket Numbers: 50-10 50-237 1. Number of Batch Releases: 1.98E+02 50-249 - i 2. Total Time Period for Batch Releases: 5.43E+04 min 3. Maximum Time Period for a Batch Release: 4.77E+02 min 4. Average Time Period for Batch Releases: 2.75E+02 min 5. Minimum Time Period for a Batch Release: 1.00E+00 min-6. Average Stream Flow During Periods of Release of Effluent into a Flowing Stream: 3.68E+05 L/ min CONTINUQUS MODE BAIClLMODE NUCLIDES RELEASED UNIT lal QUARTER 2nd QUARTER lat QUARTER 2nd QUARTER Sr-89 Ci 2,13E-04 Sr-90 C1 1.02E-04 Ar-41 Ci i Mn-M _Ci_ 1 2fiE-02 4.25E-03 __ 09-58 Ci 1.20E-04 Fe-59 _CL 9.85E-04 1.20E Co-60 Ci 4.69E-02 1 31E 2n-65 C1_ Sb.-122 01 Sb-124 fi_ 4.80E-06_ i I-131 C1 I-133 _C1_ I-135 _ Ci_ fa-134 C1 8.05E-05 9.45E-04 Cs-137 _Ci 2.58E-02 1.10E-01 Ba-140 Ci La-140 01 Ce-141 _Ci_ Cu-64 Ci Rb-88 C1 Ca-138 01 Fe-55 Ci 1.63E-02 2.64E-03 Zr-95 Ci 5.62E-06 C1 C1 Ci (above) i .101 AL.fpI_Enr.ind__.. _31 NONE NONE 1.03E-01 1 31E-01 Xe-133 l Ci_ Xe-135 -- 01_

  • The activity of this nuclide is less than the LLD listed on the appropriate table.

2Rl8/116 23 of 32

DRESDEN NUCLEAR POWER STATION UNITS 1, 2, AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT _. January _._ Through March 192.Q __.Raiwasle LIQUID EFFLUENTS Docket Numbers: 50-10 50-237 50-2'49 BATCH MODE NUCLIDES RELEASED UNIT JANUARY FEBRUARY MARCH ist QUARTER TOTAL ^ St-E9 _C1 2.131-04 2.13E-04 Sr-9Q _C i ___ 8.19E-05 1.98E-05 1.02E-04 Ar-41 C1 Mn-54 CJ _. 7.58E-03 3.11E-03 1.89E-03 1.26E-02 C0-58 _Ci 8.54E-05 3.48E-05 IJQE-04 fe-59 C1 3.83E-04 5.02E-04 1.00E-04 9.85E-04 Co-60 _C1 3.22E-02 7.97E-03 6.72E-03 4.69E-02 Zn-65 CL Sb-122 _C1 Sh-124 01 4.80E-06 4.80E-06 1-131 _ni_ I-133 _qi_ 1-135 ___ C i Ca-134 _Ci_ 3.24E-05 4 11E-05

8. die-05 Cs-137 CL_

1.64E-02 7.55E-03 1.83E-03 2.58E-02 Ba-JAD_._ _CL La-140 Ci Ce-141 Ci Cu-64 Ji_ Rb-3.8 01 J g-J38 _Ci_ Fe-55 C1 1.37E-02 1.46E-03 1.11E-03 1.63E-02 C i _. . _Ci C1 C1 (above) Intal For Period C1 7.06E-02 2,DHE-02 1.1ZE-02 1.03E-01 Xc-133 Ci Xe-135 Ci The activity of this nuclide is less than the LLD listed on the appropriate table. ZR18/ll6 24 of 32

DRESDEN NUCLEAR POWER STATION UNITS le 2, AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT __ April Through June 191Q _Badwaste LIQUID EFFLUENTS Docket Numbers: 50-10 50-237 50-249 BATCH MODE NUCLIDES RELEASED UNIT APRIL MAY JUNE 2nd QUARTER TOTAL Er-89 C1 Sr-90 Ci At-41 31_ Mn-54 Ci i dQE-03_ 2.22E-03 7.27E-04 4.25E-03 Co-58 Ci Fe-59 Ji_., 7.36E-05 3.73E-05 8.70E-06 1 2QE-04 Co-40 31_ 4.42E-03 6.02E-03 3.09E-03 1.31E-02 Zn-45 _Ci_. Sb-112 gL Sb-124 C1 l-131 Ci 1-133 _Ci_ I-135 _ CL Cs-134 C1 1.19E-04 5.53E-04 2.73E-04 9.45E-04 Cs-137 C1 1.82E-02 5.93E-02 3.24E-02 1.10E-01 \\ Da-140 Ci La-140 C1 w Ce-141

Ji_,

Cu-64 C1 ... Rb-88 C1 Cs-138 Ci Fe-55 Ci 1.DBE-03 1.02E-03 5.43E-04 2.64E-03 Zr-95 Ci 5.62E-06 5.62E-06 C1 C1 _.Ci_ (above) Total For PerioIL__ _C1 2.48E-02 6.92E-02 3,70E-02 1.31E-01 Xe-133 Ji_ Xe:135 ---C1_. The activity of this nuclide is less than the LLD listed on the appropriate tabic. ZR18/116 25 of 32 l l

DRESDEN NUCLEAR POWER STATION UNITS 2 AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT l' January Through June _ _ ly1Q CCSW LIQb1D EFFLUENTS Docket' Numbers: 50-237 50-249 1. Number of Batch Releases: 4.60E+01 l 2. Total Time Period for Batch Releases: 5.70E+01 min-3. Maximum Time Period for a Batch Release: 1.24E+00 min 4. Average Time Period for Batch Releases: 1.24E+00 min 5. Minimum Time Period for a Batch Release: 1.24E+00 min 6. Average Stream Flow During Periods of Release of Effluent into a Flowing Stream: 3.68E+05 L/ min I i CONTINU0HS MODE BATCH MODE-l NUCLIDES RELEASED UNIT 131 QUARTER 2nd QUARTER 1si QUARTER 2nd QUARTER [ l SI-89 01_ Sr-90 C1 { Ar-41 Ci Mn-54 C1 1.21E-05 7.91E-07 Co-58 Ci -l Fe-59 Ci ^ t 00 Ci_. 4.llidd 7.58E-06 1 In-65 __ci_ Sb-122 _gi I 'Sb-124 C1 I-131 C1 ,{ I-133 C1 ._._ 1-135 01 Cs-134 C1 3.21E 1.50E-16 j Cs-137 01 4.68E-06 7.52E-06 Ba-140 Ci La-140 Ci Ce-141 Ci Cu-64 Cl Rb-88 C1 gs-138 __C1 Fe-55 C1 6.79E-05 1 f Ci -C1 C1 _ CL_ (above) l Iolol_f_0I_Eeriod Ci NORE NONE 1.29E-04 1.74E-Q5 { Xc.133 __Cl 3 Xe-135 C1

  • The activity of this nuclide is less than the LLD listed on the appropriate table.

ZR18/116 26 of 32 J )

DRESDEN NUCLEAR POWER STATION UNITS 2 AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT _ January __ ThrouBh March 193D CCSW LIQUID EFFLUENTS Docket Numbers: 50-237 50-249 BATCH MODE NUCLIDES RELEASED UNIT JANUARY FEBRUARY MARCH id QUARTER TOTAL SnS9 01 Sr-90 .01 Ar-41 C1. Mp-54 C1 8.23E-06 3.89E-06 1.21E-05 0o-58 _Ci_ Fe-12 Ci Ho-10 C1 1.73E-05 1,99E-05 2.95E-06 4 11 E-05 19-65 Ci-Sb-122 Ji Sh-124 Ci I-131 Ci I-L33 Ci I-115 C1 Ca-L34 C1 2.79E-06 4 14E-07 _L21E-03 ..__,,_C g-13 7 01 1.90E-06 2.78E-06 4.68E-06 Ba-140 01 La.-JA0 _C1_ Ce-lhi C1 Cn-64 Ci Rb-88 C1 _Ga.-138 Ci Fe-55 C1 3 12E-06 6.54E-06 5.80E-05 6.79E-05 .01 C1 J.1_. C1 (above) . Intel For Period C1 3.08E-05 3.41E-Q5 6.42E-05 1.29E-04 Ke-133 Ji_ _Xe-135 C1

  • The activity of this nuclide is less than the LLD listed on the appropriate table.

1 i. ZR18/116 27 of 32

I DRESDEN NUCLEAR POWER STATION UNITS 2 AND 3 ' EFFLUENT AND WASTE DISPOSAL ~ SEMIANNUAL REPORT-April Through June 1920 i CCSW-LIQUID EFFLUENTS Docket Numbers: 50-237 50-249 BAICH M0llE NUCLIDES RELEASED UNIT APRIL MAY JUNE 2nd QUARTER TOTAL ___Er-89 01 Sr-90 Ci Ar-41 Ci Mn-54 Ci 7.91E-07 7.91E-07 i 00-58 Ci Fe-59 Ci Co-60 C1 2.25E-06 4.09E-06 1.24E-06 7.58E-06 .Zn-65 _Ci_ ____Sb-122 C1 'Sb-124 C1 I-131 C1 1-133 Ci 1-135 C1 Cs-134 Ci 1.97E-07 1.30E-06 1.50E-06 Cs-137 01 1.39E-06 3.52E-06 2.61E-06 7.52E-06 Ba-140 01 La-lh0 01 Ce-141 C1 Cu-64 Ci Rb-88 C1 Cs-138 01 Fe-55 Ci Ci _Ci _.Ci -- C1 (above) Ioln1_Enr_Eerind C1 3.84E-06 9.70E-06 3.85E-06 1.74E Xe-133 Ci Xe-135 _Ci The activity of this nuclide is less than the LLD listed on the appropriate table, i ZR18/116 28 of 32

DRESDEN NUCLEAR POWER STATION UNITS 1, 2 AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January Through June 191Q Docket Numbers: 50-10 50-237 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 50-249 Est Tot. Am. SOLID WASTE SRIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) Error.%

1. Type of Waste Unit 6-month period m3 1.35E+02 a.

Spent resins, filter sludges, evaporator bottoms, etc. 01 2.31E+02 12.4 3 m 1.02E+03 b. Dry compressible waste, contaminated equip., etc. 01 2.51E+01 16.6 3 m o c. Irradiated components, control rods, etc. Ci 0 16.6 3 m 0 d. Other (describe) Ci 0

2. Estimate of Major Nuclide Composition (by type of waste) 1 Ci-n.

Co-60 45.1 1.04Eiq2_ Fe-55 18.0 4.16EiD1_ Mn-54 16.5 3.81E+01 _Ds-137 11.3 2.61E+01 Ni-63 5. 41_. 1.25E+01 Co-58 L 17 5.DlEtDQ_ Other 1.52 5.51E+00 b. Co-60 25.4 6.38E+00 Fe-55 62,D. _L.56E+01 Mn-54 6.59 1.65E+00 Cs-137_ 4.65 1.17E+00 Other 1.36 3.41E-01 c. Co-60 0 0.00E+00 Fe.-55 0 0.00E+00 Mn-54 0 0.00E+00-Cs-137 0 0.00E+00 Other 0 0.00E+00 3.. Solid Waste Disposition NUMBER OF SHIIMERIS MODE OF TRANSPORTATLQE DESTINATION 49 Motor freight (exclusive use only) Barnwell, SC 9 Motor freight (exclusive uee only) SEG, Oak Ridge, TN 6 Motor freight (exclusive use only) CNSI, Channahon, IL 3 Motor freight (exclusive use only) Westinghouse DDR, Madison, PA 1 Motor freight (exclusive use only) Quadrex, Oak Ridge, TN B. IRRADIATED FUEL SilIPMENTS (Disposition) HUMBER OF SIIIPMENIS tiODE OF TRANSIDKIATIDE DESTINATIQB None ZR18/116 29 of 32

-3 c DRESDEN NUCLEAR POWER STATION UNITS 1, 2, AND 3 j EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT I lanuary_ Through June 191Q -j Docket Numbers: 50-10 ) 50-237 50-249 ABNORMAL RELEASES 1 i A. LIQUID j t l 1. Number of Releases: 0 l 2. Total Act.'vity Released: 0 Y B. GASEOUS 1. Number of Releases: 3 One on 5 January 90. LER 90-001-050237 (Unit 2) i One on 16 January 90, LER 90-002-050237 (Unit 2) One on 10 March 90, LER 90-005-050249 (Unit 3) f Use of the Isolation Condenser to cool the reactor subsequent to a reactor l scram resulted in a release of steam in all three events. The steam contained trace amounts of radioactivity from previous uses of contaminated domineralized water as makeup water. In all of the above i L cases, clean domineralized water was used as makeup water. 2. Total Activfty Released __Huclide Activity (Ci}_ Mn-54 1.48E-05 L Fe-55 1.32E-04 l vn.) 9.34E-05

l Na-24 2.71E-06 Total 2.43E-04 l

l ZR18/116 30 of 32

DRESDEN NUCLEAR POWER STATION DOCKET NOS. 50-10, 50-237. 50-249 RADIOLOGICAL IMPACT ON MAN ZR18/116 31 of 32 ~

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INFANT RECEPTOR-1

.g a 3 1 <.. 'J x ( LIST 2ND 3RD: 4TH, '. &F % gH Q Q YPEC '00ARTER - QUARTER = OUARTER ';GUARTER 0 l ANNUAL: 4~ "J 'b JAN-HAR - APR JUN-JUL-SEP'

0CT-DEC ~

1 y; bISAMMA AIRr -0 00Ef00! 0.00E400 -0.00E400: 0.00E400 -'0.00'Es001' ~3' Y M MRAti) .(: ): L -( )

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. LIVER 1 LIVER' l LIVER

'l ,p ,t' _, ~ ' O,,, JTHIS/ IS! A ' REPORT. FOR : THE CALENDAR-YE AR.1990 - .+ j; + pt ' r

f. 3 y

? ~ i 1 g g,". COMPLIANCE STATUS 10"CFR 50' APP.c ( _..._ );

( N E, 4 );

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);

71OTC BODY 2.58E-06 1.55E-05 0 00E+00= 0.00Ef00i 1'80E-05E T (MREM) (NE. :) -(NE- ) (- )- ( ) ( ( N E. '); e s sU 1 SKIN '5.~24E 2.77E-05 .0 00E400 0.00E+00 .3 29E-05) p.' -(MREM); <(NE -)- (NE ) ( -) ('- - )-~ L ( NE ; i)- ~ hd i % l0RGANi, r6 26E-02 3.04E 0.00E400 0 00Ef00; 16.62E.02l )- - ~(NNEf):9 'N 3 '(NNE=) (NNE ) ( )' -('

(MREM)J C

lLUND- = THYROID L'U N G ' 7-w,, K,TH1'S'[IS A: REPORT FOR'THE.! CALENDAR YEAR '1990' + 1. M. + 1 i Je + -COMPLIANCE: STATUS - 10/CFR 50 APP. 'I H INFANT. RECEPTOR y .j' ..... - %-0F'APPil' N----------- 4 QTRLY JIST QTR 2ND OTR 3RD OTR. J4TH'GTR .YRLYs %:0F- ? I' i 0BJl JAN-MAR APR-JUN' JUL-SEP-OCT-NOV OBJ

APP,IL 1

es a . ~... -. '0.00

GAMMA, AIR t. (MRAD)-

5.0 0.00 0.00 .0 00-0.00 10.0' 'l u. tBETATAIR-(HRAD) 10 05 -0. 00 - -0.00 0.00 0 00 20,0 10.'00-r b P LTOTMBODY!(MREM). 2. 5. -0 00 0.00 ,0 00- '0.00 50' -0 00 4 ,':SKINMMRCM)- 7.5: 0 00 -0 00 O.00 0.00 15.01 10.00? ~ '? ORGAN 6(HREM) 7.5 0.83 0.05 0 00 0.00 15 0 = 0. 4 4, ]; en i d,, . LUNG THYROID LUN0 0 + fg, UI, .l MT.x RESULTS BASED UPON~i ODCM REVISION 11.: 3y UPDATE CS204 H FEBRUARY 1986 _ ;g m; g i 1

i

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I DRESDEN UIT TWO 1990 ANNUAL REPORT MAXIMUM DDSES RESULTING FROM AIRBORNE RELEASES PERIOD OF RELEASE - 01/01/90 TO 12/31/90 CALCULATED 08/03/90 ADULT RECEP10R 1ST 2ND 3RD 4TH TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC OAMMA AIR 5 91E-06 3.17E-05 0.00E400 0.00E+00 3.76E-05 (HRAD) (NE ) (NE ) ( ) ( ) (NE ) BETA AIR 9.49E-07 4.52E-06 0.00E400 0.00E+00 5.47E-06 (MRAD) (N (N ) ( ) ( ) (N ) TOT. BODY 2 58E-06 1.55E-05 0.00E+00 0.00E400 1.80E-05 (MREM) (NE ) (NE ) ( ) ( ) (NE ) SKIN 5.24E-06 2.77E-05 0.00Et00 0.00E+00 3.29E-05 (MREM) (NE ) (NE ) ( ) ( ) (NE ) ORGAN 6.36E-02 4.30E-03 ( 00E+00 0.00E400 6.76E-02 (MREM) (NNE ) (NNE ) ( i ( ) (NNE ) LUNG THYROID LUNG THIS IS A REPORT FOR THE CALENDAR YEAR 1990 COMFLIANCE STATUS - 10 CFR 50 APP. I ADULT RECEPTOR '. OF APP 1. 01RLY iS1 GTR 2ND OTR 3RD OTR 4TH OTR YRLY % OF OBJ JAN-MAR APF-JUN JUL-SEP OCT-NOV OBJ APP.I GAMMA AIR (MRAD) 5.0 0.00 3.00 0.00 0 00 10.0 0.00 BETA AIR.(MRAD) 10.0 0.00 0.00 0.00 0 00 20.0 0.00 TOT. BODY (MREM) 2.5 0.00 0 00 0.00 0.00 5.0 0.00 SKIN (MREM) 7.5 0 00 0 00 0.00 0.00 15.0 0.00 ORGAN (MREM) 75 0.85 0 06 0.00 0.00 15 0 0.45 LUNG THYROID LUNG RESULTS BASED UPON ODCM REVISION 11 UPDATE CS204 FEBRUARY 1986 I

- *tw, I e DRESDEN UNIT TWO INFANT RECEPTOR 1990 ANNUAL REPORT MAXIMUM DOSES (MREM) RESULTING FROM LIQUID EFFLUENTS PERIOD OF RELEASE - 01/01/90 TO 12/31/90 CALCULATED 08/03/90-1ST 2ND 3RD 4TH ' DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP .0CT-DEC. L I' TOTAL 2.44E-05 7.66E-05 0.00Ef00 0 00E+00 1 01E-04 -BODY INTERNAL 1.69E-04 1.01E~~03 0.00E+00 0.00E+00 1.17E-03 ORGAN LIVER LIVER LIVER-f- THIS IS A REPORT FOR THE CALENDAR 4 EAR 1990 COMPLIANCE STATUS - 10 CFR 50 APP. I

 % OF APP I.

1 y QTRLY iST OTR 2ND OTR 3RD OTR 4TH QTR YRLY '% OF l: OBJ JAN-MAR APR-JUN' JU;-SEP OCT-NOV OBJ APP.I TOTAL BODY (MREM) -15 0.00 0.01 0.00 0.00 30 0 00-CRIT. ORGAN (MREM) 5.0 0.00 0.02 0.00 0.00 10.0 0.01 l LIVER LIVER LIVER' RESULTS BASED UPON ODCM REVISION 11 UPDATE CS204 FEBRUARY 1986 3 'I

DRESDEN UNIT TWO INFANT RECEPTOR 1990 ANNUAL REPORT PROJECTED DOSE AT NEAREST COMMUNITY WATER SYSTEM 4 PERIOD OF RELEASE - 01/01/90 TO 12/31/90 CALCULATED 08/03/90 1ST 2ND 3RD 41H DOSE TYPE QUARTER QUARTER OUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC TOTAL 2.44E-05 7.66E-05 0.00E400 0.00E+00 1.01E-04 D0DY IN1ERNAL 1.69E-04 1.01E-03 0.00E+00 0.00E400 1.17E-03 ORGAN LIVER LIVER LIVER THIS IS A REPORT FOR THE CALENDAR YEAR 1990 COMPLIANCE STATUS - 40 CFR 141 TYPE ANNUAL LIMIT % OF LIMIT TUTAL 4.0 (MREM) 0.003 It0DY INTERNAL 4.0 (MREM) 0.029 ORGAN LIVER THIS CALCULATION OF DOSE IS BASED ON TECHNIQUES DESCRIBED IN THE COMMONLEALTH EDISDN OFFSITE DOSE CALCULATION MANUAL. THESE TECHNIQUES DIFFER FROM THOSE DESCRIBED IN 40 CFR 141. RESULTS BASED UPON ODCM REVISION 11 UPDATE CS204 FEDRUARY 1986

D,,ESDEN UNIT TWO ADULT RECEFTOR 1990 ANNUAL REFORT MAXIMUM DOBES (MREM) RESULTING FROM LIQUID EFFLUENTS PERIOD OF RELEASE - 01/01/90 TO 12/31/90 CALCULATED 08/03/90 IST 2ND 3RD 4TH DOSE TYPE DUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC 10TAL 2.95E-04 1.83E-03 0.00E400 0 00E400 2.12E-03 BODY INTERNAL 4.40E-04 2.78E-03 0 00E+00 0.00E+00 3.23E-03 ORGAN LIVER LIVER LIVER THIS IS A REFORT FOR THE CALENDAR YEAR 1990 COMPLIANCE STATUS - 10 CFR 50 APP. I

 % OF APP I.

QTRLY IST OTR 2ND OTR 3RD OTR 4TH QTR YRLY % OF OBJ JAN-MAR APR-JUN JUL-SEP OCT-NOV OBJ APP.I 10TAL BODY (MREM) 1.5 0.02 0 12 0.00 0.00 30 0.07 CRIT. OROAN(MREM) 5.0 0.01 0.06 0.00 0.00 10.0 0.03 LIVER LIVER LIVER RESULTS BASED UPON ODCM REVISION 11 UPDATE CS204 FEBRUARY 1986

gm d a 4: V- .a-f ,f ' n - j-DRESDEN UNIT TWO y ADULT RECEPTOR R 1990 ANNUAL REPORT.

PROJECTED DOSE AT NEAREST COMMUNITY UATER SYSTEM
  • PERIOD OF. RELEASE - 01/01/90 TO 12/31/90 CALCULATED ~00/03/90-1ST 2ND 3RD ATH DOSE TYPE QUARTER QUARTER QUARTER QUARTER-ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC TOTAL 2.12E-05 1.19E-04 0 00E400 0.00E+00 1.40E ~ It 0 DY hl:

INTERNAL 3 04E-05 1.80E-04 0.00E400 0.00E+00 '2.10E-04 l-ORGAN ~ LIVER' i.IVER LIVER THIS IS A REPORT FOR THE~ CALENDAR YEAR 1990 t COMPLIANCE STATUS - 40 CFR 141 ~ TYPE ANNUAL LIMIT % OF. LIMIT I TOTAL 4.0 (MREM) 0.003 ~ BODY INTERNAL 4.0-(MREM) 0 005' ORGAN-g LIVER.

  • .THIS CALCULATION OF DOSE IS BASED ON TECHNIQUES DESCRIBED IN THE g

' COMMONWEALTH EDISON OFFSITE DOSE CALCULATION MANUAL.;THESE TECHNIQUES DIFFER FROM THOSE DESCRIBED IN 40 CFR 141. RESULTS BASED UPON-ODCM REVISION 11 UPDATE CS204 FEBRUARY 1986-1 i

DRESDEN UNIT THREE 1990 ANNUAL REPORT MAXIMUM DOSES RESULTING FROM AIRBORNE RELEASES PERIOD OF RELEASE - 01/01/90 TO 12/31/90 CALCULATED 08/03/90 INFANT RECEPTOR iST 2ND 3RD 4TH TYPE QUARTER DUARTER QUARTER OUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP 001-DEC GAMMA AIR 4.73E-05 1.03E-04 0.00E400 0 00Ef00 2 30E-04 (MRAD) (NE ) (NE ) ( ) ( ) (NE F BETA AIR 7.59E-06 2.32E-05 0.00E+00 0.00Ef00 3.00E-05 (MR.',0) (N ) (N ) ( ) ( ) (N ) 10T. BODY 2.07E-05 9.21E-0U 0.00E+00 0.00Ef00 1.13E-04 l (MREM) (NE ) (NE ) ( ) ( ) (NE ) f S$1 N 4.19E-05 1.50E-04 0.00C400 0 00EiOO 2 00E-04 (MREM) (NE ) (NE ) ( ) ( ) (NE ) ORGAN 8.34E-03 1 92E-02 0.00E400 0.00E+00 2.71E-02 (MREM) (NNE ) (NNE ) ( ) ( ) (NNE ) l LUND THYROID THYROID THIS IS A REPORT FOR THE CALENDAR YEAR 1990 s COMPLIANCE STATUS - 10 CFR 50 APP. I INFANT RECEPTOR

 % OF APP I.

QTRLY iST OTR 2ND OTR 3RD OTR 4TH QTR YRLY % OF ODJ JAN-MAR APR-JUN JUL-SEP OCT-NOV OBJ APP.I GAMMA AIR (MRAD) 5.0 0.00 0.00 0.00 0.00 10 0 0.00 BETA AIR (MRAD) 10.0 0 00 0 00 0.00 0.00 20 0 0.00 TOT. BODY (MREM) 2.5 0.00 0.00 0.00 0 00 5.0 0.00 SKIN (MREM) 7.5 0.00 0.00 0.00 0.00 15.0 0.00 ORGAN (MREM) 7.5 0.11 0.26 0.00 0.00 15.0 0.18 LUNG THYROID THYRDID { l RESULTS BASED UPON ODCH REVISION 11 I UPDATE CS204 l FEBRUARY 1986 l ---a

DREdDEN UNIT THREE 1990 ANNUAL REPORT MAXIMUM DOSES RESULTING FROM AIRBORNE RELEASES PERIOD OF RELEASE - 01/01/90 TO 12/31/90 C AL CUL ATED 08/03/90 ADULT RECEPTOR 1ST 2ND 3RD 4TH TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC UAMMA AIR 4.73E-05 1.83E-04 0.00E400 0.00E100 2.30E-04 (MRAD) (NE ) (NE ) ( ) ( ) (NE ) DETA AIR 7.59E-06 2 32E-05 0.00E+00 0.00E400 3.08E-05 (MRAD) (N ) (N ) ( ) ( ) (N ) TOT. D0ltY 2.07E-05 9.21E-05 0 00E400 0.00E+00 1.13E-04 (MREM) (NE ) (NE ) ( ) ( ) (NE ) SKIN 4.19E-05 1.EBE-04 0 00E+00 0.00E+00 2.00E-04 (MREM) (NE ) (NE ) ( ) ( ) (NE ) ORGAN 8.42E-03 2.18E-02 0 00Ef00 0.00Ef00 2.97E-02 (MREM) (NNE ) (NNE ) ( ) ( ) (NNE ) LUNG THYROID THYROID THIS IS A REPORT FOR THE CALENDAR YEAR 1990 COMPLIANCE STATUS - 10 CFT: 50 APP. I ADULT RECEPTOR

 % OF APP I.

GTRLY IST OTR 2ND OTR 3RD QTR 4TH.OTR YRLY % OF ODJ JAN-MAR APR-JUN JUL-SEP OCT-NOV OBJ APP.I GAMMA AIR (MRAD) S.0 0.00 0.00 0.00 0.00 10.0 0400 -DETA AIR (MRAD) 10.0 0.00 0.00 0.00 0.00 20.0 0.00 101. BODY (MREM) 2.5 0.00 0.00 0.00 0.00 5.0 0.00 ECKIN (MREM) 7.5 0.00 0 00 0.00 0.00 15.0 0.00 ORGAN (MREM) 7.5 0.11 0 29 0.00 0.00 15.0 0.20 LUNG THYROID THYROID RESULTS BASED UPON ODCM REVISION 11 UPDATE CS204 FEBRUARY 1986

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( - }; ', ^ i 7 s w l\\~ q n- , m oc + 4. 1 d* g .{ -.,.) 7 ( g DRESDEN UNIT 1THREE; + 4 t .y ' INFANT RECEPTOR', D L. ~ 1 (199.00ANNUAb REPORT. 1 tMAXIMUMf DOSES (MREM)E RESULTING 'FROM: LIQUID EFFLUENTS l PERIOD 10F= RELEASE 2-uo1/01/90 T0-12/31/90f. CALCULATED 708/03/90 n I q g' 4 ,i, g e l. - 1 ST,. . 2ND '3RD. M _ 4TH8 + E" 1DOSECTYPEJ l00ARTERi '0UARTER. QUARTER., c0UARTER( 9 ANNU AL::, ' t j 1-CJA M AR 'APR-JUN: -lJULrSEP!

OCT-DECl n.

m y b;TOTAON M 4i63E-05; L7.66E-051 b.'00Ef00.. 'O.00E+00l f1'.23E0k[kg i i EBODYJ i 1

3.22E-04J

'1401E 03L 0.00Ef00'- 0,00Ef00l 41.33E-031 Y [IINTERHAI.i 2 4 CORGANh b s

LIVERL

' LIVER SLIVER h./. y, ITHIBi18I.ALREfD'R FOR:THE? CALENDAR YEAR;1990f [ i >!r E, ", ;- '.- CONPLI ANCE 'ST ATUS -110: CFR 50 : APP. f1 m o g@f; i %40F APP Iif------------; ...... - ~ ~ ~ - A '.YRLY "%:OF5 N, ' ;QTRLYl'1ST-QTRi 2ND-QTR 3RD?OTR! -4TH-QTR ' i iOBJ) - JAN-MARL lAPR-JUNs

JUL-SEPJ OCT-NOV

'0BJ JAPPil h.; e 0 002

0 01:

0 00? l 0100: 1 3.'01 J0;0d.[ / iTOTAC BODY NMRE h 11'.5! ~ yp ..5 0-. 0.01

0 '. 02

, 0.00r -0.00 110.0; . 0_. 013 ' " i " CRIT.10 ROAN (MREM): T-LI'VER LIVER LIVER l, 1 + b 4 a j s, o f% E '

RESULTS%BASEDiUPON f

ODCM" REVISION?11T UPDATEfCS204L' 4 ":- FEBRUARYL19,8651 # s 4 e ;! ' y k Fr-9 e m w 'v h - 3 m (" %:; ;_ a a m - -^ j

l l' DRESDEN UNIT THREE INFANT RECEPTOR 1990 ANNUAL REPORT PROJECTED DOSE AT NEAREST COMMUNITY WATER SYSTEM

  • PERIOD OF RELEASE - 01/01/90 TO 12/31/90 CALCULATED 03/03/90 1ST 2ND 3RD 4TH IiOSE TYPE QUARTER QUARTER 00AR1ER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC TOTAL 4.63E-05 7.66E-05 0.00E400 0.00E+00 1.23E-04 D oliY INTERNAL 3.22E-04 1.01E-03 0.00E400 0 00E+00 1 33E-03 ORGAN LIVER LIVER LIVER THIS IS A REPORT FOR THE CALENDAR YEAR 1990 COMPLIANCE STATUS - 40 CFR 141 TYPE ANNUAL LIMIT

% OF LIMIT 10TAL 4.0 (MREM) 0.003 BODY INTERNAL 4.0 (MREM) 0.033 UROAN LIVER THIS CALCULATION OF DOSE IS BASED ON TECHNIQUES DESCRIBED IN THE COMMUNWEALTH EDISON OFFSITE DOSE CALCUL(iTION MANUAL. THESE TECHNIQUES DIFFER FROM THOSE DESCRIltEli IN 40 CFR 141. RESULTS BASED UPON ODCM REVISION 11 UPDATE CS204 FEBRUARY 1986

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Jg a u y,w g +,- +y ,;1990-ANNUAL;R'EPORT~ a. ,m51- - 2 g j;J, . + n.HAXIMUM DOSES _~(MREM) RESULTING FROM. LIQUID EFFLUENTS?. w %w,' PE,R,IODI0FLRELEASE. ' ,i e, <,. j rl, m '.: 01/01/90 TO 12/31/901 CALCULATED-CS/03/90?, y',y y., g t 3 .,4 ta e u 6.h ' M,

L1STl, 2ND

?3RD? ,b

  • Lo.,

'4TH, .y ' O DOBEETYPEt o00ARTER) -QUARTER- '00ARTER' ?QUARTERJ, LANNUAll W 1 M' C: 'JAN-MAR LAPR?JUN= lJUL-SEPL,< 0CT-DEC _,p I _ f L,. m' h t <V c. i.) ;*, q. ;, , 'f ( Witt.TOTAk 5.63E-041 11 83E.031 10.00E4001 LO.00E400: 2i39ELO30!G p ng t wf BODY L., s-2 TINTERNALL !845'6E-04' ~.2i70E-03 'O.00Ef00 " 10.00E+00' ~ 3 63E-03K. Y k i:0RU AN : [' ' 4, _. N'

  • f, LIVER <

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- t p, ' ' s yh?f '-THIS'ISiA-REPORTTFOR THE CALENDAR-: YEAR.1990< m y: we o,' n w o I:i? ; ' s.a. .- 4 ,:>-t.. p 1:. i r [ s. t 4 .je! 5. ? .h W. =,4;E 4

COMPLIANCE,STA1US 10'CFR.50LAPPf.11-

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JUL-SEP,

'OCT-NOV. JOBJ ' APP.IL 4 p." ... n ~ 0.04! 10.'12; .0.00= '0.00= -1310: ' L01,081 in i V10 TAB BODY 1(HREM) ~ 1'. 5 m ;Q i-il t s J !J e d t,sCRIT.f0RGAN(NREH);:5.0. 0 027 0 061 -:0 00-(0.00 ',.1040- ' 0.04r mfg -- n. 3M LIVER LIVER JLIVER Of, n r s y: 4 3y; L' i,14'p. / 4 l c $ &:l ; s' ' T

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DRESDEN UNIT THREE ADULT RECEPTOR 1990 ANNUAL REPORT PROJECTED DOSE AT NEAREST COMMUNITY WATER SYSTEM

  • PERIOD OF RELEASE - 01/01/90 TO 12/31/90 CALCULATED 08/03/90 IST 2ND 3RII 41H IiOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC TOTAL 4.05E-05 1.19E-04 0.00E+00 0 00E400 1.59E-04 UUDY INTERNAL 5.80E-OS 1 80E-04 0.00E400 0 00E400 2.30E-04 ORGAN LIVLR LIVER LIVER 1HIS IS A REPORT FOR THE CALENDAR YEAR 1990 COMPLIANCE STATUS - 40 CFR 141 TYPE ANNUAL LIMIT

% OF LIMIT TOIAL-4.0 (MREM) 0.004 DODY INTERNAL 4.0 (MREM) 0.006 ORGAN LIVER THIS CALCULATION OF ItOSE IS BASED ON TECHNIQUES DESCRIBED IN THE COMMONWEALTH EDISON OFFSITE DOSE CALCULATION MANUAL. THESE TECHNIQUES D1FFER FROM'THOSE DE3CRIBED IN 40 CFR 141. RESULTS BASEli UPON ODCM REVISION 11 ) UPDATE CS204 FEBRUARY 1986 i

.'. aV. . I t !*ESDEN NUCLEAR POWER STATION DOCKET NOS. 50-10. 50-237, 50-249 j t .f METEOROLOGICAL DATA j r t (Includes hourly data for Abnormal Release dates on January 5. January 16, and March 10, 1990.) i .p . I i i. ..n. t t a I f i t i s ',}, l J i ZR18/116 32 of 32 'I d { ,.'-)

Tw 8 + s 4 qs. gy x..

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  • tits DRistin stat:On

,;isify 1990 sett 1990 300 f t. ht LPill att 4:tt t:Ritt104 200 35 f t. O!filliti!4. 7188184'J1 Still 0:ll0t!060Lall listLIffCit!! (;&ll n hnt kl thi I (Il !! lli i 15l 11 (15 g tht H hhl 'O'4L IV NJ l'J k $$ R$ ll 1074L IU.00.00.00 .00 .00.00.00.00.00 .00 .00.00.00.00.C0.00 .00.00 3 NV.00.01.00.00.00.00.00.00.00.00 .00.00 .00 .00 .00.00 .00 .00 t lu.00.00.00 .00 .00 00.00.00.t0.00 .00.00 .t3.00.00.00 .00 .00 n.00.00.00.00.00.t0.00.00 14 .19 .33.00 .24 .tl .24 8 1.51 t.ll 3 18.00.00.00.00.00.00.00 .14 .24 .05.09 14.lt.01.05.Ct 1.32 1.3! ' I al.00.00.00.00.00.00.00.00.00 .00.tt.00.00 .W .00.00 .00 .00 II.00.00.00.00.00.00 .00.00.00.00.00.00.00.00.00.00 .00 .00 2.68 10.00.00.00.00.t0.00 00.00.00.00.00.00 .00 .00.00.00 .00.00 3 #V.t0 .00.00.00.00.00 .80 .00 .00 .00.00.00 .00.00 .1 .t0 .t0 .00 l 3* 00 .00 00.00.00.00.tl.00.00.00.tl.00.00.00.00.00 .00 .00 4.00.00.00.tl.00.00.00.00.00.05.05 .24 .00.00.tl .38 .31 4 la .50 .00 .00.00 .t0.00.00.tl.tl .h .tl.00.t0 .00 .00.01 .26 .!I I NI.00.00.00.00.00.00.00.00 .00 .08 .00.00.00 .00.00.00 .00 .00 !!.03.00.00.00.00.00 *.00.II0.00.00.00.00 .00.00.0t .00 .00 .tl .ll EU.00.00.00.00.00.00.00.00.00 .00 .00.00.00.00.00.00 .00.00 4 WJ.00.00 .00.t0 .00 .00.00.00.00 .00.00.00.00.00.00 !0 .00 .00 1 SU .00.00 .00 .00 .t0.00 .00.00 .00.00.00.00 .00.00.00 .00 .0* .00 h.00.00 .00.00.00 .00 .00.00.00 .00.00 .00.00.00.00.00 .00 .00 4 II.00.00.00 .00 .00.00.00.00 00 .00.00.00 .00.00.00.00 .t0 .00 i #1.00.00 .00.00.00.00.00.00.00 .00 .00 .00.It .00 .00.00 .50 .00 18.00.00.00.t0.00.00.00.00.00 .00.C0.00 .00.00.00 .00 .00 .00 00 (U.00.00.00.00.00.00 .00.00.00.00.00.00 .50.00.00.Ct .00.00

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_10

25. !11 '

24.2; 1.4 .I L 22.5 999.0' 21.0i J.00 I 4 l , # F90j l - 5.5': 10.1-: 11.0 117 f 204; 106 -6 6; ~8c',;23.7~t 1.0 1.6 !!.1"999.0 '21.1 ~.00f <. (N lt 5:90.I !.i~ f.1 7.4; 133t.til?!!0: il' 11 11 - '13.3 1.7: :2.5; ' 21.1 til.0 21.0 .00 r, ..s y cjil-8057' 3.f..:8.3 ' l.8 ; ; 174, 201. 204 o 19'

  • 7-5' s

24.3 < 1. 7 ; !!.i? 199.0. /20.8 L .00 ?,

23.8T. c 1.1

, Elk 5-90= Si. f.6 .6.8; 8.31 1142; 204 !1991 ;!! ; !! ' 6 L 1.4 7 t 2.5 ~ !!.4 nitt.0L i20.7 ,00 L ?tf 5 90 f.. 5,4* 9.! - 11.8 : til - 183 : til 16

4

.5 '25.24 E.0 ' 1.4 123.4 999.0 t l 20.8 i .00 s 5 6.5; 7.5 ;6.t Ill. 190 i193'. ~7. '5. 5 28.1 1.0 et.5 - 24.4 s. lli,0 - 2!.5. .00 : b)M ~ 5-CP10 ' L 1{ 000 L 11)9.4J 11.1 11.6 T1ll 1 91i Ttil " 8 6 4-30.4 1-1.2 ..'!.1 ~ fl.0 999.0 - 22.!c 6 00 " l~ F 10 12 1.1'i10.3110.7.- Ill ' 20lj m . 20 0 -12 : I' -.i-31.1 1;)

2. f.

. 25.2L 999.0= ;!!.7'. ~ 00 " ,n. o m g .3, ,,f. iA.d fliFl0:, 13

1.0-10.3 1 10.8 197 ;Ill i200' V 12 I1 9

333.5' 1,3 !$6.l!l.0 23.3, .00' f i c 4 Q16FIO.14y.f.) 10.1~'11.3' 206 ~205.206-14 : < 11 1 . 35.0 - -1,3 -!.2 '28,1: Bil.0 23.f: 1.00i E 1>; E90 15t '10. F 12.0. ilt.7 til' lll J Ills 9 7' '5: ,35.3 91.1: -2.0: - 26.6 999.0l 124.5 26.6.~ 999.0: . 00; 4 fikF90lIl 8.7 10.91 : 12.3 208 20fL !Oli 12-10 l i35.2-4.8 - -1.6) 25.01 1.00k 4 ,,1*E90ilf

6.2' 10.1' 12.!l 198:,203 201 6

4'

3 33.7. '

.1-- .4-c21.!.'999.0 125.8 ".00 f p b E90 /18 ' 6.3. 10.5 14.9 ~175. 187 lit 7 '5 3 . 32.3 - .3 ' l - 27.4 199.0 : L,26.0 '. .00<

y 7

u ,a hE !6.0 111.1,.16.2, 184-tilL 202 " ;4 !! L2: 31.2 .6 1.1l ? 26.0l. 999.0 : - 26.4i

.0'0x '

f FIO;18 5 I e z f y.' t; ' tD 5tt0 ' 20 .6.67'12;l: 17.5-183 191202 6 5 4 <30.2 .6. 1.1: '!7.3" lit.0. 26.7 l. 00 :,

1+ E90121' 5.9 - 11.5: :16.6 ~187 til 205 5

3- 't !$.9 ' .5 .t" .27.5 $99.0 ?!6.6= .00T d !It F90 L!!! 4.6 :9.5:-15.11 '201.'205 212 11'

5'4 21.9l

.5 .i 17.7ilit.0 26.3 c'.00 a $14.F$0g 23 L s5.1 -10.3=_16.0; til 218 - !!4f '6J L3 5 l30.1 L.5 --.I 27.0195.05 e t5.6 1.00 7 Lis bl0,; t41, :6.1 11.3 ~18.!,!!6: !!! '. 240~ 4r 3 != 21.4 1.4: !.3 -26.1.~lli.0 '!4.6- - 001 t4 i N .00 ~ I I/. ! TOTAL w 1 a. s, ~l -g % :q

l:

1 3 (;9 A W 1. ^ Q r r..'_+ A. 6

{ y hh

@,f

r i

+ a '4;. ? i I,I f ( l ) x m . i 'l 6h g ~; 'Ib' g l - } ,, -i i!.[> ~ - 3 d[, [ ((hw .[ X l q g<

ggip , y m; i .O i ' ,y; ~ + g%;b, , w [ h. '3: 4 y-y j g 1 J.. ' _1 n.i :3 _ m P$9009tilatNNudLIARPOWERSTAi!00 ~ ' Ntif0ROL ICAL DATAT kAIt (( ..a.n!kDSPEED...'. [.t!ND0!Rt0110N....WINDSIGMA.... TEMP ...DIFFt... .......Div POINT.=....T : PRICIP' X NN40 YY WW. 0;15, 150 300. ;35< 150' 300 '35. 150 300 3! 40 300 35 '150 300 '10 n? :. :L ? 6 M 1216 902'1" _: 4.8, 0.1 13.! 106: 134 175 t '5 5 3 . 35.4 2.1 't.9 35.4 17.5' -40.7 .00 : i yif16i,1!(! 4.8 11.1 14.4 120 'til til 12 9 5 35.9?

  • 4.0 -

6.9~ '35.9-39.9 41.6 -

00 t

'tittl G 3-5.3' 9.2 136. !!9 236 :226 18 il - 46 40.2, 't.1 ' 2.5 '40.2 41.3 !41.9' '.00 J1:16G C4 ; e 3.6 4.0,'5.1

52. J5 254 40 71 45i

.38.!- N 1.8 3.5' ?38 ! '40.0 41.0 1 00: ;' e' h 1-1940 L 5 --3.9 L 5.3 ' 6.6 97 133 200 16 19 11 39,2 2.9 3.9s 19.2 42.1 4!.51 -.00 pdt.:18C 6 14.9.'.7.! 9;I ~108 144'.Ill~n~4 '7 2-40.9 ' !.6' .,.3.5 ?40.9:,,43.5 43.8) .00, 4.3 l8.8)111.3 113 169, 205 < 7 9-7' 43.3' 1.7 ' !.9 d.345.05 2 ,45.5 .00 ' i Idt-90_ D7? % 14.0("6.0 1 1640 6.- 10.2.118) Ill 205 : 10 - 12 = I . 45.! .8 - i.7, : 45.2 ' 41.0 46.3.. 00 ? nisil40L-9s c 3.8 8.4 10.2 138 180Lr206 '14 9 91 = 46.8 .2 .l. 46.l? 47.0 * '46,9, 100 ; ?' y 1-1640 10.. = 4.1 e1.3-10.4 til 168 18! 18 12 17-47.8 .0" 47.8' 47.6 47.1f,.00l t $ 1 16j90 > 11 -: -3.8' 6.7 ~10.3 166 1 181.194 91 11 11 -48.9 ,0 c.3 48.9 48.9',48.6 s.02 K1pil4.0{ 12 - 3.2, 6,1 ' I.5 153 176 :193L 28 13 10 50.4 .4 .1: 50.4'50.0 49.I ' ' '.10,

  • L 8.1

'? p.'t 164093 :. 2.7 ' 5.3 183 193. 201 44 ' 34t ' 23 51.8 - .2 .2 51.8~ 51.6 ' 51.0 ~ .20L B1f 640J 14 6.9 L11,0 15.3-163-173!'188 15 11 a t 5t,8 .0 4 52.8' L 52.81 52,4, .01 4 s ' 1 1 FAl-1840 15 : 7.2J 10.0, 14.4 158 - 167 til ' I i ~~ 6 - 55.3 .4 41 55.! 54.7, L 53.6, .00;, ' o M1640 ll: 7.4 11.2 14.9: Ill 168.176; ~4 4 4 '57.1 .1 .2

58.! 56.8: !!4.9-. 00-

<j " 1416f90 170 7.3 -11.5 ill.1 150 til til 12-9, 8 57.0 .5 .6-55.6 55.8 - 54.9., '.00 ' I

1 1640 J18 8.3 '13.5 20.0 177 180 114

,19 6 5 57.2 4 .9: '54.8 54.8' '54.0 .00, c fIvl640?19 17.6 13.3' 19.1 165 ;172 177 l' 3-3 56.8 .3 .5

  • 54~.9,5I.8' 53.6)

. 0'0 = 4 y 8,1 -14.0 19.9 165 170 tif -6 4 2 ~56.7 .4 .7

53.8'53.6 52.5.

.00 ? 1

,1>1840 ? 20 L1?16-90"21 l11.C:

16.6 22.4' 179 183 187 9 7 6 55.2- . 0; .1.: j l!.19 5!.~l; 50.9 -.00; n,,; E11690a!! -11.7/.18.0 24,1 :187-190 192 4=

3. _ 3 -

54.7- .1 .2 ~ 52.0.'51.9. 50.5- .00' 1-11<90 e23L '13.5~219.7 25.4 191 ' 193 198 4-3*3 53.6 : .0 - .0 - 50.5 :50.5'. 50.5 .00 - R,118490124;,14.9!21.1 26.6 190 192 195 -4 3 3=

55.0

-;1 %! -51.0l 51.8i 50.5 .00L n hb, . TOTAL ~ .,33 7 7 L a ,~ 'i $ i 1

1 1

Up;E i ; a. i h3 ~ 'k Y.. J: J -4 -f I 3.(j y { I i g s

___h,

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l l L tt00 DRi$0!N KUC!!AR P0ttR liATICk !NEfl0ROLOG10AL0414 0 A 1i. ....WlAD5Pito.... .VikDDIREC110N....Vlh051PA...- itNP ...DIFF i... ......D!WPOINT...... PRICIP Ng40-TV M 15 150 300 35 150 300 35 150 00 35 150 300 35 150 300 to 3-1090 1 5.6 10.7 16.2 114 Ill 178 18 7 4 52.6 1.5 2.0 51.5 !!.0 51.5 .01 3-1090 2 6.8 10.8 15.9 Ill 177 til 14 10 7 53.8 .3 .3 52.6 52.7 51.6 .00 3-1040 3 7.5 11.1 15.3 Ill 201 204 11 1 6 54.3 .0 .3 54.1 53.8 !!.5 .00 3-1040 4 6.5 9.7 13.5 tot 110 210 9 7 5 55,6 .0 .3 55.6 55.4 54.1 .00 3-1040 5-7.9 12.5 !!.5 241 239 240 14 9 9 55.9 .3 .3 55.1 56.1 54.8 .10 3-10-00 6 11.6 16.9 20.0 'llt 181 112 Il 21 56.5 .2 .6 56.5 56.! 54.5 .11 3-1040 7-12.3 18.3 24.7 til Ill 197 11 6 6 57.1 .4 1.5 55.4 54.6 52.5 .00 3 1040 6 7.3 10.8 15.4 114 195 194-11 6 5 57.1 .1 '55.1 54.4 52.8 .00 3-1040 9 6.9 10.1 14.1 164 167 188 12 6 5 59.6 .B 56.4 55.4 53.8 -.00 3 1040 10 12.8 17.3 21.9 ill 194 193 13 11 1 60.4 .2 .6 58.6 56.5 57.4 .01 3 1040 11 7.5 9.6 11.9 210 210 211 14 13 14 61.7 .3 -1.! 10.3 !!.7 58.4 .00 3-10 90 12 5.! 8.4 10.1 !!! 249 247 37 27 21 60.7 .9 .4 59.6 69.5 58.3 .04 3 1040 13 6.1 11.4 12.5 il 68 il 12 97 99 60.2 .5 .I El.8 59.5 57.9 .16 31040 14 6.1 9.2 10.3 163 til lif 49 31 24 60.2 .7 .8 10.2 60.2 !8.0 .18- '3 1040 15 10.3 13.9 18.3 154 155 153 15 10 60.9 .0 .4 10.6 10.0 58.5 .01 3 10-90 16 8.5 11.2 14.1 172 173 til 10 10 9 61.5 .4 -1.3 60.3 59.5 58.0 .00 3 10-90 17 4.4 6.0 8.0 ill 188 187 34 21 16 61.5 .1 .5 51.7 51.0 57.1 .00 31040 il 3.1 4.0 4.2 241 245 242 42 41 33 60.5 .I .1 59.4 59.0 57.3 .00 31010 19 4.6 6.3 6.1 Ill til 183 11. 10 59.8 .6 58.7 56.1 56.7 .00 3 10 90 20 2.! 3.4 4.0 148 251 245 il 36 ft 58.8 .7. - 57.9 57.5 56.1 .00 3 10 90 21 3.8 5.0 5.1 lif 327 325 f3 74 73 58.2 1.2 1.2 57.8 57.4 55.9 .01 3 10-90 22 6.4 12.! 12.7 138 139 144 14 17 14 57.5 1.4 1.2 57.4 57.4 56.1 .00 3-1040 23 5.7 8.3 11,4 147 157 163 10 6 4 57.6 .0 6 57.1 17 55.5 .00 3 1040 24 2.2 4,7 l.8 133 150 Ill 40 16 11 57.6 4 57.3 61.1 55.1 .00 707AL .63 ..}}

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