ML20034F950

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Radioactive Effluent Rept for Jul - Dec 1992 for Dresden Nuclear Power Station
ML20034F950
Person / Time
Site: Dresden  
Issue date: 02/22/1993
From: Schroeder C
COMMONWEALTH EDISON CO.
To: Davis A
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
93-0086, 93-86, NUDOCS 9303050215
Download: ML20034F950 (57)
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Text

{{#Wiki_filter:_ @ Commonwealth Edison Dresden Wt! ear Poner Station RR 1 E Morris. Ithno.s 60450 Telephone 815 942 2920 February 22, 1993 CWS PMLTR /: 93-0086 Mr. A. Bert Davis Administrator U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137

Subject:

Dresden Nuclear Power Station Radioactive Effluent Report NRC Dockets 50-10. 50-237, 50-249 Enclosed is the Radioactive Effluent Report for July through December, 1992 for Dresden Nuclear Power Station. A copy of this report will be furnished to the NRC Resident Inspector. Sincerely Yours, 1 Z&'13 J l Charles W. Schroeder Station Manager Dresden Nuclear Power Staticn i CWS:MG:dk Enclosure I cc: M. Gagnon File /NRC File / Numerical Attached Distribution List 050078 (p: \\pt ntmgr \\c ws93 \\0086.93) // ,O t ntnnoo y '( 9303050215 930222 PDR ADOCK 05000010 / 'r i PDR g

Semi Annual Report Distribution r All Stations f Director of Nuclear Reactor Regulation c U.S. Nuclear Regulatory Commission Mail Station PI-137 i Washington D.C. 20555 (Original plus one copy) P - or - One White Flint North

  • 11555 Rockville Pike Rockville, MD 20652 Illinois Department of Nuclear Safety Of fice of Nuclear racility Saf ety 1035 Outer Park Drive Springfield, IL 62704 ANI Town Center, Suite 300s 29 South Main Street West Hartford, CT 06101-2443 American Electric Fower Service Corp.

Nuclear Operations Divisien 1 Riverside Plaza Colur.bu s, Ohio 43216 (2 copies) \\ U.S. Environmental Protection Agency Air and Radiation Branch, Region V j Health Physicist 230 S. Dearborn St. Chicago, IL 60606 t Illinois Environmental Protection Agency i r Mr. Ed Marek, Acting Manager j Maywood Regional Office 1701 First Aver.ue Maywood, IL 60153 Illinois Environmental Protection Agency Division of Water Pollution Control Environmental Protection Specialist 2200 Churchill Rd Springfield, IL 62706 L I If delivered by private carrier (i.e. Federal Exprese) { 1 direct carrier to the lower back area of the one White Flint North Bldg, Mail Station F1-137 l l I 1 I i 2 (p:\\rtningr\\tvsS3\\0034.93) l I 1 l I _w, ~-

9 i Semi Annual Report Distribution [ All Stations (Cont'd) Murray G Trettel, Inc Environmental Meteorologist 414 West Trontage Rd 7 Northfield, IL 60093 i Teledynn Isotopes Midwest Laboratory General Manager 700 Landwehr Rd Northbrook, IL.60062 Chemistry Services Chemistry Services Director 2237E Emergency Preparedness Emergency Preparedness Director 5 t Downers Grove i Nuclear Quality Programs and Assessaents i General Manager Suite 650 Downers Grove i l t i i L r I i L t t l 3 (p:\\pt rategr \\c ws.73\\0 DES 3) l s

~ i i Semi Annual Report Distribution Dresden l Station Manager Dresden Health Physics Services Supervisor-Dresden i NRC Senior Resident Inspector Dresden U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Pd. Glen Ellyn, IL 60137 tho Copies) Nuclear Quality Programs Superintender.t Dresden I t [ l l [ I P I I I i J l 1 4 i (p:\\ptntrgr\\cvs93\\ DOE 6.93) j i I

I DRESDEN NUCLEAR POWER STATION DOCKET NOS. 50-10, 50-237, 50-249 REGULATORY LIMITS Gaseous Effluents - Dose i j J This Specification is provided to ensure t hat the dose at the unrestricted area boundary f rom gaseous ef fluents from the units on site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. The annual dose ILmits are the doses associated with the 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 i annual average concentrations exceeding the limite specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.lO6(b)). The specified release 1 rate limits restrict, at all times, the corresponding gamma and beta dose 3 rates above background tc an individual at or beyond the unrestricted area boundary to less than or equal to 500 mrem / year to the total body or to 1ess than or egaal to 3000 mrem / year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate j above background to a child via the inhalation pathway to less than or ~ equal to 1500 mrem / year. For purposes of calculating doses resulting from airborne releases, the main chimney is considered to be an elevated release i point and the reactor building vent stack is considered to be a mixed mode release poin+ f Dose, Noble Cases This Specification is provided to irplement the requirements of Sections II.B, III.A and IV.A cf Appendix I, IO CFR Part 50. The Limiting ccnditions For Operaticn implement the guides set forth in Section II.3 of f Appendix I. The statements provide the required operating flexibility and I at the same time inplement the guides set forth in Section IV. A of Appendix I to assure that the releases of radioactive material in gaseous ef fluents i 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 expcsure of an individual through the appropriate pathways is unlikely to be substantially l j unde re st imat ed. The dose calculations established in the ODCM for i calculating the doses due to the actual release rates of radioactive noble gases in gaseous ef fluents will be consistent with the methodology provided in Regulatory Guide 1.109,

  • Calculation of Annual Doses to Man from Routine

) Releases of Peactor Ef fluents for the Purpose of Evaluating Compliance with y 10 CFR Part 50, Appendix I,* Revision 1, October 1977 and Regulatory Guide l 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases f rom Light-Water Cooled Reactors,

  • Revisien 1, July 1977. The ODCM equations provide f or determining the air l

doses at the unrestricted boundary based upon the historical averace I atmospheric conditions. NUF.EG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111. J i i l i a A i l 2 1 (p:\\ptM %r\\c 4 3\\DC.56.93) 5 l d e

i 10-10, 50-237, 50-249 DRESDEN NUCLEAR POWER STATION DOCKET NOS. Padiciodinee, Radioactive Material in Particulate Form and Radionuclides

Dose, I

Other than Noble Cases the requirements of Sections II.C, This specification is provided to ittplement 1 III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiti.ng conditions for t The statements Operation are the guides sat forth in Section II.C of Appendix I. 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

  • as low as reasonably radioactive materials in gaseous effluents will be kept achievable."

The ODCM calculational methods specified in the surveillance in Section III.A of Appendix I that implement the requirementsI be shown by calculational procedures requirements conformance with the guides of Appendixthe actual exposure of an individual through based on c.odels and data such that The ODCM appropriate pathways is unlikely to be substantially underestimated. required to be consistent with the release rates of the subject sr.at e r i al s are " Calculation of Annual Doses to methodology provided in Regulatory Guide 1.109, Man f rom Routine Feleaces of Peactor Effluents for the Perpose of Evalucting l Cocpliance with 10 CFR Part 50, Appendix I*, Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Routine Peleases from Light Water-Cooled in Diopersion of caseous Effluents These equations also provide for determining Reactors," Fevision 1, July 1977. The the actual doses based upcn the historical average atmespheric conditione. [ l l release rate specifications for radiciodines, radioactive material in particulate form and radionuclides other than ncble gases are dependent on the existing in the unrestricted area. The pathways which were examined in the development of these specifications were:

1) individual radicnuclide pathways to man,
2) deposition of radionuelides onto green inhalation of airborne radionuclides, l

leafy vegetation with subsequent consurption by man and 3) deposition onto grassy of the milk by man. areas where milk animals graze with consumption 4 j W Gaseous Waste Treatrent The OPERABILITY of the gaceous waste treatment which reduces amounts or j 1 concentrations of radioactive materials ensures that the system will be available require treatrent prior to release to the i for use whenever gaseous effluents the apprcpriate portions of this system be i e nv i r o r. ment. The require: rent that operable when specified provides reasonable assurance that the releases of j

  • as low as reasonably radioactive materials in gaseous ef fluents will be kept This specification irr.plement s the requ2rements of 10 CFR Part 50, and design

? achievable". General Design Criterion 60 of Appendix A to 30 CFR Part 50.36a, objective Section II.D of Appendix I to 10 CFR Part 50. J i ]. 1 [ ] i 6 (p:\\pintrsr \\c.s73\\C26.93 ) r i 1 ++,

) 50-10, 50-237, 50-249 DRESDEN NUCLEAR POWER STATION DOCKET NOS. I i LIOUID EFFLUENTS i 1 2 Concentration i This specification is provided to ensure the concentration of radioactive materials released in liquid waste ef fluents from the site to unrestricted areas will be less than the concentration levels specified in 10 CFR Part 20, Appendix a B, Table II, Column 2. The concentration limit for noble gases, MPC in air (submersion), was converted to an equivalent concentration in water using the

i Publication 2.

International Commission on Radiological Protection (ICRP) Dose This specification is provided to implement the requirements cf Sections II. A, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for forth in section II. A of Appendix I. The operation implements the guides set operating flexibility and at the same time required statements provide the forth in Section IV. A of Appendix I to assure that the l irrplement the guides set releases of radioactive material in liquid effluents will be kept "as low as reasonably achievable". The doce calculations in the ODCM irr:plement the I that conformance with the guides of requirements in Section III. A of Appendixchewn by calculational procedures base 3 and data such j j that the actual expcsure of an individual through appropriate path.iays is Appendix I be i unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radicactive l with the methodology previded l r.aterials in liquid ef fluents will be consistent in Pegulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine i Feleases of Eeacter Ef fluents f er the Purpose of Evaluating Complianca with 10 CFR Part 50, Appendix I", Eevision 1, October 1977 and Fegulatory Guide 1.113,

  • tstimating Aquatic Dispersicn of Ef fluents f rom Accidental and Routine Reactor

] Releases for the Purpose of Irrplementing Appendix I*, April 1977. NUREG-0113 q provides methods for dose calculations with Reg Guide 1.109 and 1.213. Liquid Waste Treatment f The operability of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid ef fluents require treatment prior to release to the environment. The requirement that the apprcpriate portions of i this system be used when specified provides assurance that the releases of in liquid effluents will be kept "as low as reasonably 10 CFR Part 50 radioactive materials This specification implements the requirements of achievable". 50. and design objective Section II.D of Appendix I to 10 CFR Part t i t i e 1 i i i k 7 l (p:\\ptr.tegr\\c ws93\\CSM3) f i 5

l DPESDEN NUCLEAR POWER STATION DOCKET NOS. 50-10, 50-237, 50-249 KAXIMUM PERMISSIBLE CONCENTRATIONS (MPC) concentration of radioactive materials.eleased in gaseous and liquid l The ef fluents f rom the site to unrestricted areas will be less than the concentration II, Columns 1 and 2. The l levels specified in 10 CPR Part 20, Appendix B, Table concentration limit for noble gases, HPC in air (submersion), was converted to i an equivalent concentration in water using the International Commission on Radiological Protection (ICRP) Publication 2. MAXIMUM PERMISSIBLE CONCENTRATION OT DISSOLVED OR ENTRAINED NOBLE GASES PELEASED TROM THE SITE TO UNRESTRICTED AREAS IN LIQUID WASTE I 1 MPCfeci/ml)* i NUCLIDE 2.OE-04 Kr-85m 5.CE-C4 Er-85 i 4.OE-05 ] Fr-87 l 9.OE-05 Kr-88 7 -. 0E-0 5 Ar-41 7.OE-04 Xe-131m 5.OE-04 Xe-133m 6.CE-04 2 Xe-133 l 2.OE-04 Xe-135m 2.OE-04 ) Xe-135 { a

  • Corputed f rom Equation 20 of ICRP Publication 2 '(1959),

d adjusted for infinite cloud submersion in water, and 1.0. R = 0.01 rem / week, density = 1.0 g/cc and Pw/Pt = i l 4 1 l 1 d 1 i 4 I i I f 1 i l 8 l (p:\\pintmse\\ces93\\0m.93) 1 l -e

i 4 DRESOEH NUCLEAR POWER STATION DOCKET NOS. 50-10, 50-237, 50- 49 AVERAGE ENEPGY 1 m a sus -.m . w w ~...is m,. w.m m.t sv Tu.., w r a ~ m-average energy per disintegration (E in MeV/ dis) for gamma and beta .- e a w emissions separately. 1 Ec, = 2.48E-01 HeV/dia E,= 3.17E-01 HeV/ die FOUIPMENT OUT-OF-SEPVICE: The Unit 1 chimney SPING was out of service from June 30, 1952 to the end This was due to repairs and calibration of the c.onitor. The of the year. backup air sampler was used during this period. The Unit 2 Service Water Monitor was out of service from September 25, 2992 to November 13, 1992, and the Unit 3 Service W6ter Monitor was out of cervice from September 18, 1992 to Nove-ber 5, 1992. These outages were due to repairs and cicaning trapped sediment in the pipe work. f 9 (p:\\pintmgr\\c es93\\D3S6.93)

f DRESDEN NUCLEAR POWER 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 Ce) 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. is estimated in the D2/3 Chimney using a Krypton-85 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 Of f-Cas. Iodine and Particulate: Iodine and particulate samples B. from the D-1 Chimney, D2/3 Chimney and the D2/3 Reactor Vent are collected for a maximum seven day Building These samples are analyzed for specific nuclides period. 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 f ollowing 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 Ef fluents: Analyzed for specific isotopes present in the release using a HP Ce spectrometry system. A composite of all batches for the month is sent to a vendor to be analyzed for Sr-89, Sr-90, Fe-55, H-3, and Gross Alpha activity. A sample cf each Containment Cooling Servlee Wat er (CCSW) system is analyzed each c.onth 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. Estination of Overall Errors: The methods used for D. estimating 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 equipeent, counting statistics, sampling error, discharge volume, and flow rate monitors. f Estimation of Vendor Analyzed Information: The vendor E. analyzed data for Sr-89, Sr-90, re-55, H-3 and Cross for the months of Alpha was projected, where applicable, through December using August data. A Septenber corrected Ef fluent Report will be submitted with the next Semi-Annual Effluent Report. 10 (p:\\ pin rsr\\cvsS3\\0056.93)

DRESDEN NUCLEAR PO'a'ER STATION UNITS 1,2, AND 3 EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT l July Through _ December _ 1912 1 CASEOUS EFFLUENTS Docket Numbers: 50-10 i 50-237 i 50-249 SUMMATION OF ALL RELEASES i EST.TCI UNITS 3rd QUARTER 4th QUARTER ERROI TYPE OF RELEASE FISSION AND ACTIVATION C ASES 7.31 l Ci l 1.26E.00 l3.09E+00j 1. Total Release 2. Average Release Rate for Period uCi/sec j 1.61E-01 ? 3.89E-01 l l e = j ] t 3. Percent of Technical Specification Limit 1. Total Iodine-131 j Ci j 4.42E-04 j 4.67E-04 l 9.51 y. IODINES 2. Average Release Rate of I-131 for Period ' uCi/sec l5.56E-05 L 5.EBE-05 l l l t 3. Tercent of Technical Specification Limit Ci l 3.16E-03 j 2.94E-03 Total Iodine-331, Iodine-133,and Iodine-135 q 4. 1. Particulates with half-lives > 8 days j Ci j 2.30E-03 ; 2.94E-03 l 8.09-C. PARTICULATES a j n a 2. Average Pelease Rate for Period j uCi/sec j 2.69E-04 3.7DE-04 l l 3. Tercent of Technical Specification Limit l t 4. Gross Alpha Radicactivity l Ci l3.33E-06 l6.19E-06 Lf I Ci l1.20E+00 l1.E2E+00 l 7.89' D. TRITIUM 1. Total Release l uCi/sec j 1.51E-01 l 2.29E-01 j 2. Average Release Rate for Feriod l l l 1 3. Percent of Technical Specification Limit j on Man cection of the j The information is contained in the Radiological Impact i report. Total airborne release data is provided which includes fission and activation gases, iod i r.e s, particulates, and tritium. 11 (r:\\rt n:wp\\c,s;3 gocs6,93) i

t 't r DRESDEN NUCLEAR POWER STATION UNITS 1,2, AND 3 l EETLUENT AND WASTE DISPOSAL SEMI At:NUAL REPORT Through _pecember_ 1992 Julv Docket Numbers: 50-10 GASEOUS EFFLUENTS 50-237-50-249 SUMMATION OF ALL RELEASES i fl2 (uCi/cc) 1. TISSION CASES l 1.60E-07 i Xe-138 9.90E-08 Xe-135m 4.40E-08 Kr-87 5.40E-CB l Kr-88 1.BOE-08 Fr-85m 5.10E-06 Kr-85 1.60E-08 Xe-135 4.40E-08 Xe-133 2.50E-08 Ar-41 1.50E-07 Xe-133m 2. IODINEC 7.90E-13 I-131 3.40E-12 I-133 4.70E-10 1-135 P 3. PARTICULATES 6.00E-15 I Sr-89 5.00E-15 l Sr-90 5.40E-12 Cr-51 6.80E-13 Mn-54 8.00E-13 Co-58 3.00E-14 Te-55 1.60E-12 Te-59 1.40E-12 Co-60 1.40E-12 Zr-95 7.10E-13 Nb-95 7.40E-13 Mo-99 7.20E-13 Pu-303 6.30E-13 Aa-110m 5.70E-13 Sb-124 7.70E-13 I-131 6.60E-13 l Ca-134 7.30E-13 Cs-136 7.60E-13 Cs-137 3.30E-12 Ba-140 1.1CE-12 La-140 9.99E-13 ( fe-141 3.80E-12 Ce-144 1.70E-12 2n-65 7.20E-13 Ba-133 i 1.90E-12 Sb-125 Others: 1.20E-14 Cross Alpha i 12 (p:\\pintmgr\\cwsf 3\\YA6.93) i

f k 6 DRESDEN NUCLEAR POWER STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL SEM1 ANNUAL REPORT Julv Through December _1992 I p1 chimney cASEcuS ErrLUENTS GROUND LEVEL RELEASES DocketNueber: 50-10 SEMI-ELEVATED RELEASES l XX ELEVATED RELEASES il BATCH MODE CONTINUOUS MODE JI_ QUARTER l it_t1 QUARTER d NUCLIDES RELEASED lUNITj 3rd QUARTER j it.11 QUARTER l PISSION GASES 1 1 l Xe-138 ? ci ! Xe-135m ci ! 1 Er-87 Ci ! 1 Fr-88 l ci ! Kr-85m ci ! Kr-85 ci 1 Xe-135 ci ! Xe-133 ci ! TOTAL ci ! NONE NONE ICDINES i I-131 ! ci ! t I-133 ! ci ! I-135 1 ci ! TOTAL t Ci ! NONE NONE PAPTicPLATES f t Er-89 ! ci i Sr-90 t ci ! 2.12E-08 l cr-51 ! ci ! l En-54 i ci ! t co-58 1 ci ! 1 Fe-59 ! Ci ! I co-60 t ci ! Zr-95 t ci ' j 1 Nb-95 ! ci t i Mo-99 t ci ci t Pu-103 1 1 ( Ac-110m ci ! 1 Eb-124 l Ci t a I-131 ! ci Cs-134 1 ci ! cs-136 1 ci ! cs-137 ! ci ! Ba-140 t ci i La-140 t ci j ce-141 ci Ce-144 Ci Zn-65 ci 1 f Ba-133 ' Ci ! i Sb-125 ~ ci ! re-55 Ci ! 5.60E-06 1 2.53E-05 ci ! 5.(,2E-06 2.53E-OS 1 t;C'iE NONE TOTAL = The activity of this nuclide is less than the LLD listed on the appropriate table. 13 (p:\\pintmsr\\cws93\\0086,93) i i r

DRESDEN NUCLEAR POWER STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT Julv Through September _1912 p1 chimney CASEOUS EFFLUENTS GROU.?t LEVEL RELEASES Docket Nunter: 50-10 SEMI-ELEVATED RELEASES XX ELEVATED RELEASES CONTINUOUS MODE SEPTEMBER j 2Is QUARTER TOTAL NUCLIDES RELEASED l UNIT !, JULY AUGUST ? FISSION CASES ? Xe-138 Ci ! l 1 Xe-135m ci ! ~! Kr-87 ci ! 1 f Kr-88 ci ! Kr-85m Ci ! 1 Kr-85 t ci ! Xe-135 ! ci ! Xe-133 1 ci TOTAL ! ci IODINES I f t I-Ill t ci t = 1 = t I-133 1 ci ! I-135 t ci t TOTAL 1 ci ' t PARTICULATES Sr-89 1 ci ! 7.17E-0B 1 Sr-90 f ci ! 7.12E-08 cr-51 ci t 1 Mn-54 ci ! 1 Co-58

ci t 1

e Te-59 1 ci i 1 Co-60 t ci ? Ir-95 ci ! 1 Nb-95 ci i Mo-99 ' ci t e f a Ru-103 ! ci i l 1 o' Aa-110m t ci ! = t Sb-124 ! ci ; f = I-131 1 ci ! t es-134 t ci t 1 cs-136 t ci t = a l f cs-137 ' ci t Ba-140 ci ! e La-140 ci ! ce-141 1 ci ! Ce-144 1 Ci i ) In-65 ! ci t = 1 ___ Ba-133 ci t t Sb-125 ci ! 1.65E-06 5.6CE-06 Te-55 Ci ! 3.95E-06 1.65E-06 5.62E-06 TOTAL ci ! 3.97E-06

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

(p:\\pintmgr\\cws93\\D'56.93)

DRESDEN NUCLE AR POWER STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT October _ Through Decerber_ 1992 D1 chirney CASEOUS EFFLUENTS GROUND LEVEL RELEASES Docket Hunters 50-10 SEMI-ELEVATED RELEASES XX ELEVATED RELEASES CONTINUOUS MODE NUCLIDES RELEASED l UNIT; OCTOBER l NOVEMBER l DECEMBER l 4th QUARTER TOTAL. FISSION GASES ci ! Xe-138 Xe-135m ci ! Kr-87 ' Ci ! Kr-88 l ci ! Kr-85m ! c i_j Kr-85 1 ci e Xe-135 ! ci a Xe-133 ! Ci TOTAL ! Ci IODINES l I-131 ! ci ! I-133 ! ci ! I-135 ! ci ! TOTAL ! Ci ! PARTICULATES ! Sr-89 ! ci ! a Sr-90 ! ci ! cr-51 ! ci ! Mn-54 ! ci_j Co-5B ! ci ! Fe-59 ! ci ! L co-60 ! ci_j = rr-95 c i_J Nb-95 ci ' Bu-103 ci Aa-110m ! Ci Sb-124 ci l I-131 ci e cs-134 ci Cs-136 ci cs-137 Ci ! Ba-140 ci ! i La-140 ci ! ce-141 ! ci Ce-144 ! Ci In-65 ci ! Ba-133 ci ! Sb-125 ci ! Te-55 ci ! 8.53E-06 8.26E-06 8.53E-06 2.53E-05 TOTAL ! Ci ! 8.53E-06 t 8.26E-06 8.53E-06 2.53E-05

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

i 15 (p:\\ptningr\\cws93\\DG86.93)

l DRESDEN NUCLEAR POWER STATION UNITS 2 and 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Julv Through Decerter 1922 p2/3 Chimney GASEOUS EFTLUENTS GROUND LEVEL REIEASES Locket Numbers: 50-237 50-249 SEMI-ELEVATED RELEASES XX ELEVATED RELEASES r BATCH NODE CONTINUOUS MODE )_rd QUARTER j 4th QUARTER j JLdQUARTERj 4_t_t} QUARTER NUcLIDES RELEASED ' UNITL r I FISSION GASES e Xe-138 ci Xe-135m ! ci ' Kr-87 ? ci Kr-88 cij i Fr-85m ci ! Kr-85 " Ci ! 9.27E-04 1 1.01E-03 t Xe-135 ci 1 1.2BE+00 1 3.09E+00 Xc-133 ci ! TOTAL L ci ! 1.26E+00 3.09E+00 None None 10 DINES I-131 ! ci ! 4.30E-04 1 4.27E-04 l r .1 - 13 3__ _ l ci ! 2.20E-03 2.17E-03 i 1-135 t ci ! 3.96E-04 1.6CE-04 i TOTAL ! ci i 3.09E-03 1 2.76E-03 None None PARTICULATES ! Sr-89 ! Ci ! 1.28E-04 8.02E-05 Sr-90 ! ci i 2.99E-06 1.35E-06 I cr-51 ? ci ! Mn-54 ci ! 2.81E-05 i r co-58 ci ! Fe-59 ci ! co-60 t ci ! 2.33E-05 1.05E-04 i f-Tr-95 t ci ? Nb-95 ! ci ' Ru-103 ! ci 7.67E-06 An-310m ci ! ci ! Sb-124 f I-131 ci ! i Cs-134 ci ! cs-136 ! ci ! i cs-137 ci ! 5,32E-06 4.73E-05 Ba-140 ci ' l La-140 ci ce-141 ci a f cc-144 ci In-65 ci ! Ba-133 ci Sb-125 ci ' Fe-55 ci 6.32E-04 3.17E-04 TOTAL 1 ci ! 8.27E-04 5.51E-04 None None

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

4 16 (p:\\pintmgr\\cws93\\DCE6.G3) i

i I DRESDEN NUCLEAR PCNER STATION UNITS 2 AND 3 ITFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Julv Through Sept e-te r _ 1911 p2/3 chimney GASEOUS EFTLUENTS GROUND LEVEL RELEASES Docket Numbers: 50-237 l 50-249 SEMI-ELEVATED RELEASES XX ELEVATED RELEASES CONTINUOUS MODE JULY l AUGUST l SEPTEMBER 3rd QUARTER TOTA' NUCLIDES RELEASED :UNITj FISSION GASES 1 ) Xe-138 c1 1 Xe-135m ci ! 1 Kr-87 . ci ! Kr-88 ! ci ! Kr-85 ci ! 2.76E-04 1 3.13E-04 3.38E-04 9.27E-04 Kr-85m ci ! Xe-135 ci ! 6.05E-01 3.24E-01 3.5?E-01 l 1.28E+00 TOTAL ci ! 6.05E-01 3.24E-01 3.52E-01 1.28E+00 Xe-133 ci ! 10 DINES l I-131 1 ci ! 1.38E-04 1.35E-04 ? 1.57E-04 1 4.30E-04 1-133 ! ci ! 8.54E-04 1 7.3CE-04 6.70E-04 L 2.26E-03 3.96E-04 3.96E-04 TOTAL ! ci ! 9.92E-04 9.71E-04 1.22E-03 3.09E-03 I-135 ! ci ! PARTICULATES Sr-89 ci ! 5.94E-05 3.62E-05 3.20E-05 1.2BE-04 Sr-90 ci ! 2.64E-07 1.47E-06 l 1.26E-06 2.99E-06 i 2.81E-05 cr-51 ci ! 2.SIE-05 Mn-54 ci ! Co-58 ci ! 2.33E-05 Fe-59 ! ci ! co-60 ci ! 2.33E-05 Zr-95 ci ! 7.67E-06 Nb-95 ! ci ' Pu-303 Ci 7.67E-06 = Aa-110e ci ! = Sb-124 ci ! l 1 I-131 ci ! cs-134 ci ! 5.32E-06 5.32E-06 cs-136 ci ! cs-137 ci ! Ba-140 ci ! La-140 ci ! ce-141 ci t l ce-144 ci ! 1 In-65 ci ! l a a f Ba-133 ci ' Fe-55 ! ci 2.11E-04 2.2EE-04 1.95E-04 6.32E-04 Sb-125 l ci 1 l ci ! 2.76E-04 3.15E-04 2.34E-04 8.27E-04 TOTAL

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

17 (p:\\piningr\\c.ts93\\0GS6.93)

i i DRESDEN NUCLEAR POWER STATION UNITS 2 and 3 EFFLUENT AND WASTE DISPOS AL SEMI ANNUAL REPORT October Through December _ 1921 D2/3 chimnev CASEOUS EFFLUENTS CROUND LEVEL RELEASES Docket Numbers: 50-50 i SEMI-ELEVATED RELEASES XX ELEVATED RELEASES CONTINUOUS MODE OCTOBER NOVEMBER i DECEMBER lithQUARTERTL NUCLIDES RELEASED ]UNITj t FISSION CASES Xe-138 ci ! Xe-135m ci ! Kr-87 i_pi ! Fr-88 ei ! j Kr-85m Ci ! Kr-85 ci ! 3.57E-04 2.78E-04 1 3.75E-04 1.01E-03 _ Xe-135 ! Ci ! 1.68E+00 1.26E*00 1.49E-01 1 3.09E+00 Xe-133 ! ci ! TOTAL t ci ! 1.68E400 1.26E*00 1 1.49E-01 1 3.09E+00 l IODINES l-131 ci ! 1.06E-04 1.36E-04 l 1.85E-04 4.27E-04 I-133 ci ! 6.45E-04 7.71E-04 7.52E-04 2.17E-03 1.60E-04 1-135 . Ci ! 1.60E-04 TOTAL ! ci ! 9.11E-04 9.07E-04 1 9.37E-04 1 2.76E-03 PARTICULATES Sr-89 ! ci ! 2.68E-05 2.65E-05 2.69E-05 8.02E-05 Sr-90 1 ci ! 4.52E-07 4.47E-07 4.53E-07 1.35E-06 i = cr-51 1 ci ! f Mn-54 1 ci ! 1 1 Co-58 1 ci t Te-59 ! ci ! 4.34E-05 6.19F-05 1.05E-04 Co-60 ! ci ! Zr-95 ! ci ! Nb-95 ! ci ! = Fu-103 1 ci ! l Aa-110m ! ci ! Sb-124 ' ci ! I-131 ! ci ! cs-134 ! ci ! 1 cs-136 ! ci ! 1 4.73E-05 4.73E-05 cs-137 ! ci ! Ba-140 ! ci ! La-140 l ci ! Ce-141 ci ! l ce-144 ci ! l Zn-65 ! ci ! Ba-133 t ci ! ) Sb-125 ! ci ! Te-55 ! ci ! 1.06E-04 1.05E-04 1.06E-04 3.17E-04 TOTAL ! ci ! 1.33E-C4 1 1.75E-04 2.43E-04 1 5.51E-04 i

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

i l 1 18 (p:\\pintrsr \\cws93\\0GS6.93) i t i

l I DRESDEN NUCLEAR POWER STATION UNITS 2 AND 3 EFFLUENT AND WASTE DISPOS AL SEMI ANNUAL REPORT + Julv Through December 1921 D2/3 Ex Buildina Vent _ GASEOUS EFFLUENTS i GROUND LEVEL RELEASES Docket Numbers: 50-;! XX SEMI-ELEVATED RELEASES 50-:: i ELEVATED RELEASES CONTINUOUS MODE BATCH MORE l NUCLIDES RELEASED,UNITl }Id QUARTER l 4th QUARTER l 3rd QUARTERj ith QU7.RTER TISSION CASES Xe-136 ci Xe-135m I ci f f Yr-87 ci ) Kr-88 ! ci ! Kr-85m ! ci ! 1 Kr-85 ! ci ! Xe-135 t ci ! 'i 1 Xe-133 ? ci ! TOTAL i ci ! NONE NONE 8 10 DINES I-131 Ci ! 1.15E-05 l 4.00E-05 t 1-133 ci ! 5.67E-05 t 1.42E-04 I I-135 ! ci ! TO'AL ! Ci ! 6.83E-05 l 1.82E-04 i NONE 1 NO'ir FAPT1rULATES I f f I Sr-89 ! ci ! Sr-90 ! Ci ! Cr-51 ! ci ! 5.01E-05 1 1.33E-04 1 1 Hn-54 1 Ci ! 1.56E-04 1 3.02E-04 i Co-58 1 ci ! 7.72E-05 Te-59 ! ci ! 3.6]E-05 Co-60 ! Ci ! 4.23E-04 f 1.14E-03 f l Nb-95 Ci ! 1 i ~ 2r-95 ci ! Ru-303 ci ! f 1 Ci Aa-110m ST-124 ci 1-131 Ci

  • ci 1 cs-134 cs-136 ci !

Cs-137 Ci ! Ba-140 Ci 1 f f f La-140 ci 1 f co-141 1 ci ! Ce-144 ? Ci ! 2n-65 ci ! Ba-133 Ci ! Mo-99 ci ! l sb-125 ci ! ' ci B.41E-04 6.72E-04 Fe-5" TOTAL i ci 1.47E-03 2.36E-03 None None The activity of this nuclide is less than the LLD listed on the appropriate table. 19 (r:\\ptningr\\tws93\\0c86.93) f

S Y DRESDEN NUCLEAR POWER STATION UNITS 2 and '.~ EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Julv Through Sept ember _1991 p_2/3 Rx Buildina Vent _ GASEOUS EFFLUENTS GROUND LEVEL RELEASES Docket Numbers: 50-23 XX SEMI-ELEVATED RELEASES 50 ELEVATED RELEASES CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED lUNITj JULY l AUGUST SEPTEMBER JrA QUARTER FISSION CASES Xe-138 Ci Xe-135m Ci Kr-87 ! Cl Kr-B8 ! Ci L Fr-85m ! Ci Tr-85 ! Ci a Xe-135 ! Ci Xe-133 ! Ci a TOTAL ! Ci L 10 DINES l l I-131 ! Ci ! 7.34E-06 1.85E-06 2,27E-06 i.15E-05 I-133 ! Ci ! 7.01E-06 3.71E-05 1.26E-05 5.67E-05 I-135 ! Ci ! TOTAL Ci ! 1.44E-05 3.90E-05 1.49E-us 6.83E-05 PART1cVLATES I Sr-89 ! Ci ! Sr-90 ! Ci ! 4.61E-05 1 3.95E-06 5.01E-05 Cr-51 C1 Mn-54 Ci 5.29E-05 7.02E-05 3.2EE-05 1.56E-04 Co-58 Ci ! Te-59 ' Ci ! Co-60 Ci ! 1.89E-04 l 1.30E-04 1.04E-04 4.23E-04 f Zr-95 Ci ! l Nb-95 i Ci ! Fu-103 Ci ! Aa-110m Ci ! Sb-124 Ci ! I-131 Ci ! Cs-134 Ci ! Cs-136 Ci ! l Cs-137 Ci ! f I Ba-140 Ci ! l La-140 Ci ! a ce-141 Ci l Ce-144 Ci Zn-65 Ci ) Ba-133 Ci ! Mo-99 ! Ci ! Sb-125 ! Ci ! Te-55 I Ci ! 3.72E-04 1 2.06E-04 2.63E-04 8.41E-04 TOTAL l Ci ! 6.14E-04 4.52E-04 4.04E-04 1.47E-03 i The activity of this nuclide is less than the LLD listed on the appropriate table. i 20 (p:\\pintmgr \\c vs93\\DCS6.93) l

s DRESDEN NUCLEAR POWER STATION UNITS 2 and 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT October _ Through December _ 1912 D 2/3 Rx Buildino Vent GASEOUS EFFLUENTS GROUND LEVEL RELEASES Docket Numbers: 50-237 XX SEMI-ELEVATED RELEASES 50-249 ELEVATED RELEASES CONTINUOUS MODE NUCLIDES RELEASED ; UNITl OCTOBER NOVEMBER l DECEMBER 4th QUARTER TOTAL FISSION GASES Xe-138 C1 Xe-135m Ci Kr-87 Ci Kr-88 Ci a Kr-85m Ci e Kr-85 Ci Xe-135 Ci ! l l Xe-133 ! Ci ! TOTAL 1 Ci ! l IODINES I-131 ! Ci 7.61E-06 1.46E-05 1.78E-05 4.00E-05 I-133 ! Ci 3.22E-05 4.49E-05 1 6.47E-05 1.42E-04 1-135 ! Ci TOTAL ! Ci 3.9EE-05 5.95E-05 8.25E-05 1.82E-04 PAPTICULATES ! Sr-89 ! Ci ! Sr-90 ! Ci ! 2.73E-05 1.06J-04 1.33E-04 Cr-51 ! Ci ! Mn-54 ! Ci 5.37E-05 1.96E-05 2.29E-04 3.02E-04 Co-58 ! Ci 9.80E-06 L 6.74E-05 7.72E-05 3.61E-05 3.61E-05 Fe-59 ! Ci Co-60 ! Ci ! 2.14E-04 3.51E-04 7.71E-04 1.14E-03 Zr-95 ! Ci Nb-95 ! Ci Ru-103 ! Ci 1 Ea-110m ! Ci Sb-124 Ci i I-131 Ci ? 1 Cs-134 Ci Cs-136 Ci e = Cs-137 Ci i Ba-140 1 Ci La-140 ! Ci e Ce-141 ! Ci Ce-144 ! Ci Zn-65 ! Ci ! Ba-133 Ci ! Mo-99 Ci ! Sb-125 Ci ! Fe-55 Ci ! 2.38E-04 2.16E-04 2.1BE-04 6.72E-04 TOTAL ! Ci ! 5.36E-04 4.24E-04 1.42E-03 2.36E-03

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

~; appropriate table. 21 rp:\\piningr\\cvs9P oc86.93) p

DRESDEN NUCLEAR PCWER STATION UNITS 1, 2, and 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Julv Through _ December 19H LIQUID EFFLUENTS SUMMATION OF ALL RELEASES Docket Numbers: 50-10 50-237 50-249 EST. TOTS UNITS 31_d QUARTER 4th QUARTER ERROR,% A. FISSION AND ACTIVATION PRODUCTS Ci 6.41E-04 3.75E-04 5.58 no ne tritium, gases, alpha)

2. Average Diluted Conc. During Feriod uci/mL j 1.88E-10 1.03E-10 '

~ l t 3. Percent of Applicable Limit B. TRITIUM 1. Total Release Ci l 1.13E+00 l4.52E-01 !

2. Average Diluted Cone. During Feriod juCL/mL j 3.32E-07 l 1.24E-07 {
3. Percent of Applicable Limit l

C. DISSOLVED AND ENTRAINED CASES

1. Total Release l

Ci j2.16E-05 l < LLD 5.58

2. Average Diluted Conc. During Period luC1/:.L j 6.35E-12 l < LLD j

l

3. Percent of Applicable Limit j

t p. CROSS ALPHA RADIOACTIVITY

1. Total Release l

Ci j < LLD l < LLD l 15.1 1 E. VOLUME OF WASTE RELEASED (prior to dilution) l Liters l1.60E+06 l1.20E+06l 5.00J l F. VOLUME OF DILUTION WATER USED DURING TERIOD l liters j3.40E+09 l3.64E+09 l 5.00

  • The information is contained in the Radiological Impact on Fan section of this report. Total liquid release data is provided which includes fission and activation products, tritium, and dissolved and entrained gases.

l 22 (p:\\ pint egr\\c ws93\\0M6.93) l

- - ~. ~ 1 DRESDEN NUCLEAR POWER STATION UNITS 1, 2, AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT I Julv Through December 1992 TABLE OF LOWER LIMITS OF DETECTABILITY Docket Numbers: 50-10 50-237 FOR LIQUID EFFLUENTS 50-249-i NUCLIDE LLD (uC1/mL) 7.00E-08* Sr-89 2.00E-09 Sr-90 5.50E-08 Mn-54 4.20E-08 Co-58 9.30E-08 Fe-59 1.23E-07 Co-60 1.20E-07 Zn-65 4.50E-08 Sb-124 4.50E-08 I-131 4.60E-08 Cs-134 7.20E-08 Cs-137 i 2.20E-07 Ba-140 4.60E-08 L_a-140 6.90E-08 Ce-141 1.20E-07 i Xe-133 l 4.20E-08 Xe-335 i 3.70E-07 Cr-51 7.00E-08 Fe-55 3.10E-07 Cs-138 l 3.00E-07 H-3 1.00E-OB Cross Alpha 9.80E-08 Zr-95 1.50E-07 Kr-87 1.70E-07 Kr-88 I-135 2.10E-07 6.70E-OB I-332 An-110m 5.90E-08 Ba-133 6.00E-08 l ce-144 3.10E-07 5.50E-08 Cs-136 6.30E-08 I-133 1.50E-07 I-334 l 1.10E-05 Kr-85 3.90E-08 Mo-99 5.00E-081 Nb-95 3.50E-07 No-239 5.30E-08 i Po-103 1.50E-07 Sb-125 1.80E-06__ l Xe-13Jm l 3.60E-07_ Xe-133m 4.10E-06 Xe-138 This limit was reported as an MDA by the offsite vendor for the October 1992 Radwaste Discharge composite. The October 23, 1992 Unit 3 service water sample had a reported MDA of 6.00E-08 uci/mL. All other KDAs for Sr-89 were at or below 7.00E-09 uci/mL. 23 (p:\\ptntmgr\\cws93\\0086.93) J

r s DRESDEN NUCLEAR POWER STATION UNITS 1, 2, AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Julv Through December 1991 Padwaste LIQUID EFFLUENTS Docket Numbers: 50-10 4 50-237 1. Number of Batch Releases: 7 50-249 2. Total Time Period for Batch Releases: 2.07E+03 min 3. Maximum Time Period for a Batch Release: 3.34E+02 min 4. Average Time Period for Batch Releases: 2.96E+02 min 5. Minimum Time Period for a Batch Release: 2 70E+02 min 6. Average Stream Flow During Periods of Release of Effluent into a Flowing Stream: 1.66E+06 L/ min CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED LUNITi Arg QUARTER j 4th QUARTER 3rd QUARTER 4th QUARTER Sr-89 Ci Sr-90 Ci 1.35E-04 5.49E-05 Mn-54 Ci Co-58 Ci Fe-59 Ci ! 4 Co-60 Ci ! 3.51E-04 1.87E-04 Zn-65 t Ci l Ru-103 ! Ci Ao-110m ci ! Sb-124 ! Ci ! I-131 ! Ci ! Cs-114 ! Ci ! Cs-137 i Ci ! 1.15E-04 4.96E-05 Ba-140 t Ci La-140 t Ci l Ce-141 ! Ci Cs-138 1 Ci 1 Fe-55 ! Ci Zr-95 ! Ci I - 132 ! Ci ! I - 134 ! Ci Bi-214 ! Ci (abo.e) j j Tctal For Period l Ci NONE NONE l 6.01E-04 2.92E-04 ' Ci Xe-133 Xe-135 Ci ; 1 Kr-88 Ci ! The activity of this nuclide is less than the LLD listed on the appropriate table. t i 24 (p:\\pintmgr\\cws93\\DOB6.93)

DRESDEN NUCLEAR POWER STATION UNITS 1, 2, AND 3 EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT Julv Through September 1992 Radwaste LIQUID EFFLUENTS Docket Numbers: 50-10 50-237 50-249 BATCH MODE NUCLIDES RELEASED [UNITL JULY j AUGUST l SEPTEMBER l 3rd QUARTER TOTAL Sr-89 Ci Sr-90 Ci Mn-54 Ci 9.97E-05 1 '3.51E-05 1.35E-04 Co-58 Ci 1 Te-59 Ci Co-60 Ci 2.31E-04 1.20E-04 1 3.51E-04 2n-65 Ci Fu-103 Ci Aa-110m ci i Sb-124 ' Ci_j 1 I-131 Ci i 1 Cs-134 Ci ! Cs-137 Ci ! 6.84E-05 4.69E-05 1.15E-04 Ba-140 Ci ! l La-140 Ci ! 1 t Cs-138 Ci ! Fe-55 Ci ! I-132 ci ! I-134 1 ci ! (above) l 1 3.99E-04 2.02E-04 6.01E-04 _otal For_Eeriod Ci T Xe-133 Ci Xe-135 ! Ci 1 The activity of this nuclide is less than the LLD listed on the appropriate tabl There were no Radwaste liquid discharges in July, 1992. + 25 (p: \\ pint mst \\c ws93\\00%.93)

l 4 DRESDEN NUCLEAR POWER STATION UNITS 1, 2, AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT october _ Through December 1992 Radwaste LIQUID EFFLUENTS Docket Numbers: 50-10 50-237 50-249 4 BATCH MODE NUCLIDES RELEASED fUNIT' OCTOBER HOVEMBER j DECEMBER l: 4th QUARTER TOTAL f Sr-89 Ci Sr-90 Ci 5.49E-05 Mn-54 ! ci 3.66E-05 1.83E-05 Co-58 l Ci Fe-59 Ci 1.87E-04 Co-60 Ci 1.41E-04 1 4.63E-OF 2n-65 ! Ci ! Sb-124 Ci ! I-131 Ci ! Cc-134 ! Ci ! 4.96E-05 Cs-137 ! Ci ! 3.26E-05 1.70E-05 l Ba-140 ! Ci ! La-140 ! Ci ! l Ce-141 ! Ci ! Cs-138 ! Ci ! Fe-55 ! ci ! J I-132 l Ci ! ! Ci ! ! Ci ! l (above) l 1 2.92E-04 Total For Feriod { Ci 2.10E-04 8.16E-05 Xe-133 ! Ci 1 Xe-135 ! Ci The activity of this nuclide is less than the LLD listed on the appropriate table. There were no Radwaste Liquid discharges in December, 1992, + i a f l i i 1 4 1, 26 (p:\\pt ntn9t\\c ws93\\0086.93)

4 DRESDEN NUCLEAR POWER STATION UNITS 2 AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Julv Through December 1991 CCSW LIQUID EFFLUENTS Docket Numbers: 50-237 i 50-249 1. Number of Batch Releases: 60 2. Total Time Period for Batch Releases: 1.44E+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: 2.83E+06 L/ min CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED jUNITj 3rd QUARTER l 4th QUARTER j 3rd QUARTER j 4th QUARTER Sr-89 Ci ! 1 Sr-90 Ci ! Mn-54 Ci ! t 1 2.80E-06 3.33E-06 Co-58 Ci ! Fe-59 ! Ci ! l Co-60 ! Ci ! 2.83E-05 3.17E-05 l 2n-65 ! Ci ! 1 l Sb-122 1 Ci ! l Sb-124 Ci l l I-131 Ci ! I-132 ! Ci ! I-135 ! Ci t t Cs-134 Ci l l l l l Cs-137 Ci ! 6.63E-06 1 4.48E-05 f t Ba-140 Ci La-140 Ci

  • Ci !

Cs-138 Fe-55 Ci Bi-214 Ci 1.18E-06 1.48E-06 Pb-232 Ci 1.32E-06 1.82E-06 Ci t l l Ci (above) l j j Total For Period l Ci i NONE NONE l 4.02E-05 8.32E-05 X e_- 13 3 Ci ! 7.70E-06 Xe-135 Ci ! 1.39E-05 The activity of this nuclide is less than the LLD listed on the appropriate table. l l l 27 (p:\\pi ntest \\cws93 \\0086.93)

4 I DRESDEN NUCLEAR POWER STATION UNITS 2 AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Julv Through September 1992 CCSW LIQUID EFFLUENTS Docket Numbers: 50-237 50-249 BATCH MODE NUCLIDES RELEASED jUNIT[ JULY AUGUST j SEPTEMBER j 3rd QUARTER TOTAL Sr-89 ! Ci e

  • Ci e

Sr-90 2.8CE-06 Pn-54 Ci 2.80E-06 a Co-58 Ci Fe-59 ! Ci Co-60 ! Ci ! 4.24E-06 2.02E-05 3.87E-06 1 2.83E-05 2n-65 ! Ci ! Sb-122 Ci ! Sb-124 Ci ! 1-131 Ci ! I-132 Ci I-135 Ci i i Cs-134 Ci 3.44E-06 3.19E-06 6.E3E-06 l C7-137 Ci_j Ba-140 Ci ! I.a-140 Ci ! Cs-138 Ci ! Fe-55 ci ! 1 1.;EE-06 1.18E-06 Bi-214 ! Ci ! 1.32E-06 1.32E-06 Pb-212 ! Ci ! ! Ci ! ! Ci ! I (above) l l 8 IQtal_For Period Ci l 4.24E-06 2.89E-05 1 7.06E-06 4.02E-05 7.70E-06 7.70E-06 Xe-133 Ci i 1.39E-05 1.39E-05 Xe-135 Ci ! The activity of this nuclide is less than the LLD listed on the approp.riate table. i i a 28 (p:\\ pint rr.gr\\c ws93\\0066.93)

I i DRESDEN NUCLEAR POWER STATION UNITS 2 AND 3 EFFL"ENT AND WASTE DISPOSAL SEMIANNUAL REPORT i October Through December _1992 CCSW LIQUID EFFLUENTS Docket Numbers: 50-237 50-249 l BATCH MODE NUCLIDES RELEASED ' UNIT.; OCTOBER j NOVEMBER l DECEMBER j 4th QUARTER TOTAL i Sr-89 ci l Sr-90 ' ci Mn-54 Ci 3.38E-07 1 2.07E-06 l 9.17E-07 3.33E-06 l Co-58 Ci L Fe-59 ci ! Co-00 Ci ! 8.42E-06 1 1.67E-05 6.62E-06 1 3.17E-05 Zn-65 ci ! i Sb-122 ci i Sb-124 Ci ! I-131 ci ! I-132 1 ci ! t I-135 ! Ci ! l f a Cs-134 1 ci ! cs-137 i ci ! 2.12E-05 1.32E-05 1 1.04E-05 1 4.46E-05 ) Ba-140 ! Ci ! La-140 t ci ! t 1 Cs-138 ! Ci i Fe-55 1 ci l 1 1.4BE-06 1.48E-C5 Bi-214 ? ci l 1 8.63E-07 9.59E-07 1 1.82E-06 i Pb-212 Ci ! Ci ! ! Ci t (above) l l j Iotal For Period Ci i 3.0DE-05 j 3.43E-05 1 89E-05 1 8.32E-05 [ t Xe-133 ! Ci i Xe-135 1 ci ! The activity of this nuclioe is less than the LLD listed on the appropriate table. t f f .h 29 (p:\\pintn$,r \\c us93\\0'J.4.53) 1

DRESDEN NUCLEAR POWER STATION UN!TS 1, 2, AND 3 EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT Julv Through December 1991 Docket Numbers: 50-10 50-237 i 50-249 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Est Tot. Error,% f SCLID WASTE SHIPPED OFFSITE FOR BURI AL OR DISPOSAL (NOT IRRADI ATED FUEL) ha "UnitL6-monthperiodj

1. Type of waste "3

3.10E+02 l l Spent resins, filter sludges, evaporator bottoms, etc. Ci j 5.90E+02 f12.4 l a. 8.65E+02 f; jm3j b. Dry compressible waste, contaminated equip., etc. Ci l 9.86E+00

16.6 '

m3 4.85E+01 i c. Irradiated components, control rods, etc. 3.09E+04 16.6 Ci j d. Other (describe) Sewage Treatment Plant dirt , Ci l 1.27E-01 l

2. Estimate of Major Nuclide Composition (by type of waste)

Ci a. Co-60 1 47.0 ! 2.77E+02 j Fe-55 1 28.6 1.6BE+02_L Mn-54 1 9.63 1 5.68E401 Ni-63 1 9.03 1 5.33E+01 Cs-137 1 4.61 ! 2.72E+01_ b. Co-60 f 21.2 ! 2.09E+00 Fe-55 1 64.4 1 6.35E+00 l Vn-54 6.15 ! 6.06E-01 l Ni-59 1.32 i 1.30E-01.! Ni-63 1 1.02 f 1.01E-01 Cs-137 1 5.14 ! 5.07E-01 j 1.64E+04 l c. Co-60 1 52.9 1 Mn-54 2.01 6.20E+02 j Fe-55 42.2 1.30E+04_j Ni-63 3.39

1.05E+03_f d.

Mn-54 1 4.40 ! 5.59E-03 Fe-55 64.3 ! 8.17E-02\\ j Fe-59 1.45 1 1.84E-03_l l i Co-60 1 24.2 1 3.07E-02 j Ni-63 1 1.13 ! 1.44E-03 i l Cs-137 1 2.84 ! 3.6]E-03_j 3. Solid Waste Disposition MODE OF TRANSPORTATION DESTINATION NUMBER OF SHIPMENTS 65 Motor freight (exclusive use only) CNSI, Barnwell, SC 9 Motor freight (exclusive use only) Quadrex, Oak Ridge, TN 6 Motor freight (exclusive use only) CNSI, Channahon, IL ID Motor freight (exclusive use only) SEG, Oak Ridge, TN IS Motor freight (exclusive use only) US Ecology, Beatty, NV B. IRRADIATED FUEL SHIPMENTS (Disposition) MODE OF TRANSPORTATION DESTINATION NUMBER OF SHIPMENTS None i 30 (p:\\ptntmgr\\cws93\\0086.93)

t i l DRESDEN NUCLEAR POWER STATION UNITS 1, 2, AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT ) July _ Through December 19,9_Z j l ABNORMAL RELEASES A. LIQUID 1. Number of Releases: __ 1 2. Total Activity Released: 9.62E-04 Ci B. caseous 1. Number of Releases: 3 I 2. Total Activity Released: 7.48E-07 Ci TOTAL 4 A. 1. Units 2/3 B Condensate Storage Tank (2/3-3303b) leaked water to the ground on! September 25, 1992. The leak started at approximately 1430 and was contained by 2030. 6 The leak rate was about 3/4 gallon per minute. The estimated acivity released ist { } Mn-54 6.73E-08 Cl Fe-59 5.79E-08 Ci f Co-60 3.11E-07 Ci Xe-133 1.65E-07 Ci Xe-135 1.84E-07 Ci H-3 9.61E-04 Ci 2 B. 1. The Unit 1 backup sampler f ailed between July 20, 1992 at 10:30 and July 21, 1992 at!t 10:53. The tritium sampler was setup and running during this period with particulate and iodine filters. The estimated activity during this period ist Fe-55 1.43E-07 Ci i Sr-90 7.71E-10 Ci Gross Alpha 1.65E-08 Ci i i l i 4 i I i 31 (p:\\pintrngr\\cws93\\DDS6.93) l i i -m-

l I h DRESDEN NUCLEAR POWER STATION UNITS 1, 2 AND 3 t EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT January Through ~ June 19.91 f ABHORMAL RELEASES i 2. On October 15, 1992 at 06:30, the Units 2/3 Chinaey SPING lost power. Power wra restcred at 08:00. A tritium sampler was running at this time. The last SPING i filters and the tritium sample particulate and iodine filters showed no gama emmitting activity. The next SPING sample was positive for iodine, therefore the i release during this period is based on the SPING sample following the lost power. [ I-131 1.12E-08 Ci Fe-55 2.13E-07 Ci Sr-89 5.37E-08 Ci Sr-90 9.05E-10 Ci y Gross Alpha 1.00E-09 Ci 3. The Unit 3 isocondenser released radioactivity on October 20, 1992. The release based on the latest analysis of isocondenser water ist j l Mn-54 4.30E-08 C1 Co-60 2.63E-07 Ci j 'l l t i f I I 1 i l l (p:\\pintnsritn93\\0066.43) 32 i r e

i I DRESDEN NUCLEAR POWER STATION DOCKET NOS. 50-20, 50-237, 50-249 i RADIO W ICAL IMPACT ON MAN i ? i I i, I d i ,b l 5 I i I r ) i t u i ti L t a L -t f i 5 i 6 f f l i f f 33 (p:\\pintmgr\\cws93\\0056.93) 6

i i l t \\ DRESDEN UNIT ONE i 1992 ANNUAL REPORT MAXIMUM DOSES RESULTING FROM AIRBORNE RELEASES PERIOD OF RELEASE - 01/01/92 TO 12/31/92 CALCULATED 02/22/93 l j INFANT RECEPTOR IST 2ND 3RD 4TH TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL l JAN-MAR APR-JUN JUL-SEP OCT-DEC j i GAMMA AIR 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 (MRAD) ( ) ( ) ( ) ( ) ( ) BETA AIR 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 (MRAD) ( ) ( ) ( ) ( ) ( ) j TOT. BODY 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 (MREM) ( ) ( ) ( ) ( ) ( ) I SKIN 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 f (MREM) ( ) ( ) ( ) ( ) ( ) ORGAN 1.07E-05 7.68E-06 1.14E-06 1.11E-06 2.04E-05 l (MREM) (SE ) (SE ) (N ) (N ) (SE ) l LIVER LIVER LUNG LIVER LIVER l } THIS IS A REPORT FOR THE CALENDAR YEAR 1992 i COMPLIANCE STATUS - 10 CFR 50 APP. I INFANT RECEPTOR -- --------- % OF APP I. QTRLY IST QTR 2ND QTR 3RD QTR 4TH QTR YRLY % OF, OBJ JAN-MAR APR-JUN JUL-SEP OCT-NOV OBJ AFF.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 0.0C 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 0.0D ORGAN (MREM) 7.5 0.00 0.00 0.00 0.00 15.0 0.00 i LIVER LIVER LUNG LIVER LIVER ! i RESULTS BASED UF ODCM ANNEX REVISION O MARCH 1989 i

DRESDEN UNIT ONE 1992 ANNUAL REPORT MAXIMUM DOSES RESULTING FROM AIRBORNE RELEASES PERIOD OF RELEASE - 01/01/92 TO 12/31/92 CALCULATED 02/22/93 ADULT RECEPTOR IST 2ND 3RD 4TH TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 (MRAD) ( ) ( ) ( ) ( ) ( ) GAMMA AIR 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 (MRAD) ( ) ( ) ( ) ( ) ( ) BETA AIR TOT. BODY 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 (MREM) ( ) ( ) ( ) ( ) ( ) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 (MREM) ( ) ( ) ( ) ( ) ( ) SKIN 9.44E-06 1.32E-05 6.78E-06 4.40E-06 3.39E-05' (MREM) (SE ) (SE ) (SE ) (SE ) (SE ) ORGAN LIVER LIVER LIVER LIVER LIVER THIS IS A REPORT FOR THE CALENDAR YEAR 1992 COMPLIANCE STATUS - 10 CFR 50 APP. I ADULT RECEPTOR - ------ -- % Or APP I. QTRLY iST QTR 2ND QTR 3RD QTR 4TH QTR YRLY % OF OBJ JAN-MAR APR-JUN JUL-SEP CCT-NOV OBJ APP.II GAMMA AIR (MRAD) 5.0 0.00 0.00 0.00 0.00 10.0 0.00l 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 0.00i SKIN (MREM) 7.5 0.00 0.00 0.00 0.00 15.0 0.00 ORGAN (MREM) 7.5 0.00 0.00 0.00 0.00 15.0 0.00l LIVER LIVER LIVER LIVER LIVER ! t RESULTS BASED UP ODCM ANNEX REVISION 0 MARCH 1989 (!P i f f v

DRESDEN UNIT TWO l 1992 ANNUAL REPORT MAXIMUM DOSES RESULTING FROM AIRBORNE RELEASES PERIOD OF RELEASE - 01/01/92 TO 12/31/92 CALCULATED 02/26/93 l INFANT RECEPTOR 1ST 2ND 3RD 4TH l TYPE QUARTER QUARTER-QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC GAMMA AIR 1.47E-04 5.95E-06 3.83E-06 1.05E-05 1.68E-04 l (MRAD) (NE ) (NE ) (NE ) (NE ) (NE ) l 2.00E-05 1.25E-06 8.07E-07 2.20E-06 2.43E-05 (MRAD) (N ) (N ) (N ) (N ) (N ) BETA AIR TOT. BODY 7.20E-05 2.50E-06 1.61E-06 4.40E-06 8.05E-05 (MREM) (NE ) (NE ) (NE ) (NE ) (NE ) l SKIN 1.30E-04 5.47E-06 3.52E-06 9.61E-06 1.48E-04 (MREM) (NE ) (NE ) (NE ) (NE ) (NE ) ORGAN 1.47E-02 8.65E-03 8.59E-04 1.72E-03 2.58E-02 I (MREM) (NNE ) (NNE ) (NNE ) (NNE ) (NNE ) { LUNG LUNG THYROID LUNG LUNG s l IS A REPORT FOR THE CALENDAR YEAR 1992 f THIS I f COMPLIANCE STATUS - 10 CFR 50 APP. I INFANT RECEPTOR % OF APP I. QTRLY IST QTR 2ND QTR 3RD QTR 4TH QTR YRLY % OF l OBJ 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 i SKIN (MREM) 7.5 0.00 0.00 0.00 0.00 15.0 0.00 ' ORGAN (MREM) 7.5 0.20 0.12 0.01 0.02 15.0 0.17 LUNG LUNG THYROID LUNG LUNG RESULTS BASED UFO:: ODCM ANNEX REVISION O MARCH 1989

I DRESDEN UNIT TWO 1992 ANNUAL REPORT RESULTING FROM AIRBORNE RELEASES i MAXIMUM DOSES PERIOD OF RELEASE - 01/01/92 TO 12/31/92 CALCULATED 02/26/93 ADULT RECEPTOR i IST 2ND 3RD 4TH TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC 1.47E-04 5.95E-06 3.83E-06 1.05E-05 1.6BE-04 i (MRAD) (NE ) (NE ) (NE ) (NE ) (NE ) ] GAMMA AIR 2.00E-05 1.25E-06 8.07E-07 2.20E-06 2.43E-05 (MRAD) (N ) (N ) (N ) (N ) (N ) BETA AIR TOT. BODY 7.20E-05 2.50E-06 1.61E-06 4.40E-06 8.05E-05 (MREM) (NE ) (NE ) (NE ) (NE ) (NE ) 1.30E-04 5.47E-06 3.52E-06 9.61E-06 1.48E-04 (MREM) (NE ) (NE ) (NE ) (NE ) (NE ) SKIN 1.50E-02 8.98E-03 1.01E-03 1.89E-03 2.67E-02 (MREM) (NNE ) (NNE ) (NNE ) (NNE ) (NNE ) ORGAN j LUNG LUNG THYROID LUNG LUNG 1992 IS A REPORT FOR THE CALENDAR YEAR THIS b J COMPLIANCE STATUS - 10 CPR 50 APP. I ADULT RECEPTOR

 % OF APP I.

QTRLY iST QTR 2ND QTR 3RD QTR 4TH QTR YRLY % OF l OBJ 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 0.001 BETA AIR (MRAD) 10.0 0.00 0.00 0.00 0.00 20.0 0.00l TOT. BODY (MREM) 2.5 0.00 0.00 0.00 0.00 5.0 0.00l SKIN (MREM) 7.5 0.00 0.00 0.00 0.00 15.0 0.00l ORGAN (MREM) 7.5 0.20 0.12 0.01 0.03 15.0 0.18: LUNG LUNG THYROID LUNG LUNG RESULTS BASED UFC ODCM ANNEX REVISION 0 MARCH 1989 [1p

DRESDEN UNIT THREE 1992 ANNUAL REPORT MAXIMUM DOSES RESULTING FROM AIRBORNE RELEASES PERIOD OF RELEASE - 01/01/92 TO 12/31/92 CALCULATED 02/26/93 I INTANT RECEPTOR 1ST 2ND 3RD 4TH TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC GAMMA AIR 0.00E+00 9.59E-06 1.45E-05 3.35E-05 5.75E-05 (MRAD) ( ) (NE ) (NE ) (NE ) (NE ) BETA AIR 0.00E+00 2.02E-06 3.05E-06 7.05E-06 1.21E-05 (MRAD) ( ) (N )- (N ) (N ) (N ) TOT. BODY 0.00E+00 4.03E-06 6.08E-06 1.41E-05 2.42E-05 (MREM) ( ) (NE ) (NE ) (NE ) (NE ) SKIN 0.00E+00 8.81E-06 1.33E-05 3.07E-05 5.28E-05 (MREM) ( ) (NE ) (NE ) (NE ) (NE ) ORGAN 6.82E-04 1.24E-02 4.32E-03 9.86E-03 2.66E-02 (MREM) (NNE ) (NNE ) (NNE ) (NNE ) (NNE-) LUNG LUNG THYROID LUNG THYROID THIS IS A REPORT FOR THE CALENDAR YEAR 1992 COMPLIANCE STATUS - 10 CFR 50 APP. I INFANT RECEPTOR -- ---- - -- % OF APP I. QTRLY IST QTR 2ND QTR 3RD QTR 4TH QTR YRLY % OF OBJ 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 0.0@ BETA AIR (MRAD) 10.0 0.00 0.00 0.00 0.00 20.0 0.0@ TOT. BODY (MREM) 2.5 0.00 0.00 0.00 0.00 5.0 0.0@ SKIN (MREM) 7.5 0.00 0.00 0.00 0.00 15.0 0.0 ORGAN (MREM) 7.5 0.01 0.16 0.06 0.13 15.0 0.1 LUNG LUNG THYROID LUNG THYROI RESULTS BASED UP@ ODCM ANNEX REVISION O MARCH 1989

i DRESDEN UNIT THREE 1992 ANNUAL REPORT MAXIMUM DOSES RESULTING TROM AIRBORNE RELEASES PERIOD OT RELEASE - 01/01/92 TO 12/31/92 CALCULATED 02/26/93 ADULT RECEPTOR IST 2ND 3RD 4TH TYPE QUARTER QUARTER QUARTER QUARTER AhNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC GAMMA AIR 0.00E+00 9.59E-06 1.45E-05 3.35E-05 5.75E-05 (MRAD) ( ) (NE ) (NE ) (NE ) (NE ) BETA AIR 0.00T+00 2.02E-06 3.05E-06 7.05E-06 1.21E-05 (MRAD) ( ) (N ) (N ) (N ) (N ) TOT. BODY 0.00E+00 4.03E-06 6.08E-06 1.41E-05 2.42E-05 (MREM) ( ) (NE ) (NE ) (NE ) (NE ) SKIN 0.00E+00 8.81E-06 1.33E-05 3.07E-05 5.28E-05 (MREM) ( ) (NE ) (NE ) (NE ) (NE ) ORGAN 6.92E-04 1.37E-02 5.04E-03 1.05E-02 2.89E-02 (MREM) (NNE ) (NNE ) (NNE ) (NNE ) (NNE ) LUNG GI-LLI THYROID LUNG GI-LLI THIS IS A REPORT FOR THE CALENDAR YEAR 1992 6 COMPLIANCE STATUS - 10 CFR 50 APP. I ADULT RECEPTOR % OF APP I. QTRLY IST QTR 2ND QTR 3RD QTR 4TH QTR YRLY % OT OBJ 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 0.01 0.18 0.07 0.14 15.0 0.19 LUNG GI-LLI THYROID LUNG GI-LLI RESULTS BASED UPO) ODCM ANNEX REVISION O MARCH 1989 (!p n

l DRESDEN UNIT TWO INFANT RECEPTOR 1992 ANNUAL REPORT MAXIMUM DOSES (MREM) RESULTING FROM LIQUID EFFLUENTS i PERIOD OF RELEASE - 01/01/92 TO 12/31/92 CALCULATED 02/24/93 t IST 2ND 3RD 4TH DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC TOTAL 1.09E-05 9.95E-06 5.41E-06 2.21E-06 2.85E-05 BODY INTERNAL 2.67E-05 2.65E-05 6.43E-06 3.22E-06 6.29E-05 ORGAN LIVER LIVER LIVER LIVER LIVER THIS IS A REPORT FOR THE CALENDAR YEAR 1992 COMPLIANCE STATUS - 10 CFR 50 APP. I i % OF AFP I. QTRLY 1ST QTR 2ND QTR 3RD QTR 4TH QTR YRLY % OF OBJ JAN-MAR APR-JUN JUL-SEP OCT-NOV OBJ APP.I TOTAL BODY (MREM) 1.5 0.00 0.00 0.00 0.00 3.0 0.00 CRIT. ORGAN (MREM) 5.0 0.00 0.00 0.00 0.00 10.0 .0.00 LIVER LIVER LIVER LIVER LIVER RESULTS BASED UPON ODCM ANNEX REVISION 0 MARCH 1989 P 1 1

t DPESDEN UNIT TWO INFANT RECEPTOR l 1992 ANNUAL REPORT l PROJECTED DOSE AT NEAREST COMMUNITY WATER SYSTEM

  • PERIOD OF RELEASE - 01/01/92 TO 12/31/92 CALCULATED 02/24/93 j

IST 2ND 3RD 4TH DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL l JAN-MAR APR-JUN JUL-SEP OCT-DEC TOTAL 1.09E-05 9.95E-06 5.41E-06 2.21E-06 2.85E-05 3 INTERNAL 2.67E-05 2.65E-05 6.43E-06 3.22E-06 6.29E-05 BODY ORGAN LIVER LIVER LIVEP LIVER LIVER THIS IS A REPORT FOR THE CALENDAR YEAR 1992 l COMPLT'PCE STATUS - 40 CFR 141 l ANNUAL LIMIT % OF LIMIT TYPE 0.001 4.0 (MREM) TOTAL BODY 0.002 4.0 (MREM) INTERNAL l ORGAN THIS CALCULATION OF DOSE IS BASED ON TECHNIQUES DESCRIBED IN THE i THESE TECHNIQUES DIFFER COMMONWEALTH EDISON OFFSITE DOSE CALCULATION MANUAL. FROM THOSE DESCRIBED IN 40 CFR 141. RESULTS BASED U ODCM ANNEX REVISION O MARCH 1989 i ) ~ l

4 i DRESDEN UNIT TWO ADULT RECEPTOR 1992 ANNUAL REPORT MAXIMUM DOSES (MREM) RESULTING FROM LIQUID EFFLUENTS PERIOD OF RELEASE - 01/01/92 TO 12/31/92 CALCULATED 02/24/93 1ST 2ND 3RD 4TH DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC 3.51E-05 3.70E-05 3.91E-06 2.76E-06 7.87E-05 TOTAL 5.23E-05 5.47E-05 5.01E-06 3.83E-06 1.16E-04 BODY INTERNAL LIVER LIVER LIVER LIVER LIVER ORGAN IS A REPORT FOR THE CALENDAR YEAR 1992 THIS COMPL' trE STATUS - 10 CFR 50 APP. I % OF AFP I. QTRLY 1ST QTR 2ND QTR 3RD QTR 4TH QTR YRLY % OF, OBJ JAN-MAR APR-JUN JUL-SEP OCT-NOV OBJ AP P. ) TOTAL BODY (MREM) 1.5 0.00 0.00 0.00 0.00 3.0 0.0( CRIT. ORGAU(MREM) 5.0 0.00 0.00 0.00 0.00 10.0

0. 0; LIVER LIVER LIVER LIVER LIVER RESULTS BASED UP, ODCM ANNEX REVISION O MARCH 1989 t

t i J i

DRESDEN UNIT TWO ADULT RECEPTOR 1992 ANNUAL REPORT PROJECTED DOSE AT NEAREST COMMUNITY WATER SYSTEM.* PERIOD OF RELEASE - 01/01/92 TO 12/31/92 CALCULATED 02/24/93 IST 2ND 3RD 4TH DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC 4.94E-06 5.00E-06 1.93E-06 8.46E-07 1.27E-05 TOTAL INTERNAL 7.03E-06 5.90E-06 2.03E-06 9.11E-07 1.48E-05 BODY GI-LLI LIVER GI-LLI LIVER LIVER ORGAN THIS IS A REPORT FOR THE CALENDAR YEAR 1992 COMPLIANCE STATUS - 40 CFR 141 % OF LIMIT ANNUAL LIMIT TYPE 0.000 4.0 (MREM) TOTAL BODY 0.000 4.0 (MREM) INTERNAL ORGAN LIVER IS BASED ON TECHNIQUES DESCRIBED IN THE THIS CALCULATION OF DOSE THESE TECHNIQUES DIFFE EDISON OFFSITE DOSE CALCULATION MANUAL. COMMONWEALTH FROM THOSE DESCRIBED IN 40 CFR 141. RESULTS BASED U ODCM ANNEX REVISION 0 MARCH 1989 [Ip

9 DRESDEN UNIT THREE INFANT RECEPTOR 1992 ANNUAL REPORT MAXIMUM DOSES (MREM) RESULTING FROM LIQUID EFFLUENTS PERIOD OF RELEASE - 01/01/92 TO 12/31/92 CALCULATED 02/24/93 IST 2ND 3RD 4TH DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC 1.19E-05 1.00E-05 5.38E-06 2.19E-06 2.95E-05 TOTAL INTERNAL 3.03E-05 2.66E-05 6.31E-06 2.69E-06 6.60E-05 BODY LIVER LIVER LIVER LIVER LIVER ORGAN 1992 THIS IS A REPORT FOR THE CALENDAR YEAR COMPLIANCE STATUS - 10 CFR 50 APP. I % OF APP I. QTRLY iST QTR 2ND QTR 3RD QTR 4TH QTR YRLY % 09 OBJ JAN-MAR APR-JUN JUL-SEP OCT-NOV OBJ APPc TOTAL BODY (MREM) 1.5 0.00 0.00 0.00 0.00 3.0 0. CRIT. ORGAN (MREM) 5.0 0.00 0.00 0.00 0.00 10.0 0.0 LIVER LIVER LIVER LIVER LIVER RESULTS BASED UL ODCM ANNEX REVISION 0

  • MARCH 1989 '

P { I 1 .1

DRESDEN UNIT THREE INFANT RECEPTOR 1992 ANNUAL REPORT PROJECTED DOSE AT NEAREST COMMUNITY WATER SYSTEM.* PERIOD OF RELEASE - 01/01/92 TO 12/31/92 CALCULATED 02/24/93 IST 2ND 3RD 4TH DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC TOTAL 1.19E-05 1.00E-05 5.38E-06 2.19E-06 2.95E-05 BODY INTERNAL 3.03E-05 2.66E-05 6.31E-06 2.69E-06 6.60E-05 ORGAN LIVER LIVER LIVER LIVER LIVER THIS IS A REPORT FOR THE CALENDAR YEAR 1992 I COMPLIANCE STATUS - 40 CFR 141 'i TYPE ANNUAL LIMIT % OF LIMIT l TOTAL 4.0 (MREM) 0.001 BODY INTERNAL 4.0 (MREM) 0.002 ORGAN LIVER THIS CALCULATION OF DOSE IS BASED ON TECHNIQUES DESCRIBED IN THE COMMONWEALTH EDISON OFFSITE DOSE CALCULATION MANUAL. THESE TECHNIQUES DIFFER FROM THOSE DESCRIBED IN 40 CFR 141. RESULTS BASED UFC! ODCM ANNEX REVISION 0 i MARCH 1989 t if

i DRESDEN UNIT THREE ADULT RECEPTOR 1992 ANNUAL REPORT MAXIMUM DOSES (MREM) RESULTING FROM LIQUID EFFLUENTS PERIOD OF RELEASE - 01/01/92 TO 12/31/92 CALCULATED 02/24/93 IST 2ND 3RD 4TH DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC TOTAL 4.13E-05 3.71E-05 3.71E-06 1.78E-06 8.39E-05 BODY INTERNAL 6.16E-05 5.49E-05 4.72E-06 2.34E-06 1.24E-04 ORGAN LIVER LIVER LIVER LIVER LIVER THIS IS A REPORT FOR THE CALENDAR YEAR 1992 COMPLIANCE STATris - 10 CFR 50 APP. I i % OF APP I. QTRLY IST QTR 2ND OTR 3RD QTR 4TH QTR YRLY % OF; OBJ JAN-MAR APR-JUN JUL-SEP OCT-NOV OBJ APP. TOTAL BODY (MREM) 1.5 0.00 0.00 0.00 0.00 3.0

0. 0' CRIT. ORGAN (MREM) 5.0 0.00 0.00 0.00 0.00 10.0 0.0!

LIVER LIVER LIVER LIVER LIVER RESULTS BASED UP ODCM ANNEX REVISION O MARCH 1989 I e i

t P I DRESDEN UNIT THREE s ADULT RECEPTOR i 1992 ANNUAL REPORT PROJECTED DOSE AT NEAREST COMMUNITY WATER SYSTEM

  • PERIOD OF RELEASE - 01/01/92 TO 12/31/92 CALCULATED 02/24/93 1ST 2ND 3RD 4TH DOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL J AN-MAR APR-JUN JUL-SEP OCT-DEC TOTAL 5.44E-06 5.03E-06 1.91E-06 7.86E-07 1.32E-05 i

BODY [ INTERNAL 8.49E-06 5.91E-06 2.00E-06 8.56E-07 1.55E-05 ORGAN GI-LLI LIVER GI-LLI GI-LLI GI-LLI THIS IS A REPORT FOR THE CALENDAR YEAR 1992 COMPLIANCE STATUS - 40 CFR 141 TYPE ANNUAL LIMIT % OF LIMIT TOTAL 4.0 (MREM) 0.000 i BODY INTERNAL 4.0 (MREM) 0.000 l ORGAN 4 GI-LLI l THIS CALCULATION OF DOSE IS BASED ON TECHNIQUES DESCRIBED IN THE ) COMMONWEALTH EDISON OFFSITE DOSE CALCULATION MANUAL. THESE TECHNIQUES DIFFER FROM THOSE DESCRIBED IN 40 CFR 141. RESULTS BASED UFO ODCM ANNEX REVISION O MARCH 1989 (!P l e i I

t t a a 1 DRESDEN NUCLEAR POWER STATION DOCKET NOS. 50-10, 50-237, 50-249 I i METEOROLOGICAL DATA I i e r t ? I f i s i 'I i i t .I I .i Y d 1 i i I r i i I l l 34 i (p:\\pintmgr\\cws93\\0086,93) i i f I

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