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9,. Canwrsa EdkmOsOmn• Mocsa Power taeOvm.n famce ,aft VI

Tesoffs rifisI4am2

February 22, 1991

EDE LTRt 0: 91-072

Mr. A. Bert DavisAdminiatratorU.S. Nuclear Regulatory CommlssionRegion 11I799 loosevelt RoadGlen Ellyn, Illinois 60137

Subject: Dresden Nuclear Power StationRadfiactive Effluent Report

Enclosed is the corrected radioactive effluent report for Januarythrough June 1990 for Dresden Nuclear Power Station. The final datefor Sr-89, Sr-90, Fe-55, Tritium, and gross alpha have been included tnthis report. A copy of this report viii be furnished to the NRCResident Inspector.

Sincerely Yours,

E. D. EenigenburgStation ManagerDresden Nuclear Power Station

EDE:SK:d II

Enclosure

cc: S. KovallFile/NRCFile/NumericalAttached Distribution List

R PDR-ý fI

e4

Simi Annual Report DistributionAll Statioos

Director of Nuclear Reactor RegulationU.S. Nuclear Regulatory CammissionMail Station K1-137Washington D.C. 20555

(Original plus one copy)

or-

One White Flint North '

11555 Rockville PikeRockville, MD 20852

Illinois Department of Nuclear SafetyOffice of Nuclear Facility Safety1035 Outer Park DriveSpringfield. IL 62704

ANRLibrarian I - Tech ProcessingThe Exchange. Suite 245270 Farmington AveFarmington, CT 06032

American Electric Power Service Corp.Nuclear Operations DivisionI Riverside PlaztColumbus, Ohio 143216

(2 copies)

U.S. Envirormental Protection AgencyAir and Radiation Branch, Region VHealth Physicist230 S. Dearborn St.Chicago, IL 60606

Illinois Environmental Protection AgencyRegion III - DI1C/FO551.15 North UniversityPeoria, IL 61614

Illinois Environmental Protection AgencyDivision of Water Pollution ControlEnvironmental Protection Specialist2200 Churchill RdSpringfield* IL 62706

If delivered by private carrier (i.e. Federal Express)direct carrier to the lover back area of theOne White Flint North Bldg, "ail Station P1-137

Z£DE91/37

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I IS9mi Annual Report Distribution

All Statiores(ont'd)

Murray & Trettel, Incvirar &mental Meteorologist

414 West Frontage RdNorthfield, IL 60093

Teledyne Isotopes Midwest LaboratoryGeneral Manager700 lAndvekr AdNorthbrook, IL 60062

ChemistryChemistry1237;t

EmergencyEmergency1237E

ServicesServices Director

treparednessPreparedness Director

Nuclear Quality Programs and AssessmentsGeneral ManagerSuite 300Opus III West

ZEDE91/37

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-U

sent Annual Report Distribut ion

Dresden

Station MangerDresden

Bealth Physics Servicesleelth Physics ServicesDresden

NIC Resident InspectorDresden

General Electric CoPlant Manager7555 E. Collins RoadMorris. IL 60450

U.S. Nuclear Regulatory799 Roosevelt Rd.Glen Ellyn, IL 60137(two copies)

Supervisor

Comission Region III

Nuclear Quality ProgramsNuclear Quality Progrms EngineerDresden

ZEDWE91/37

I, of 36

-20S MUCLUR POWD = ATION Do= POS. 50-10, 0-237. 50-349 2

RICVATOSY LIlMTS

Gaseous Efluents Dose

This Specification is provided to ensure that the dose at theunrestricted area boundary from gaseous effluents from the unitson site viii be within the annual dose limits of 10 CrR Part 20for unrestricted areas. The &muat dose limits are the dosesassociated with the concentrations of 10 CrR Port 20, Appendix B,Table I. These limits provide reasonable assurance thatradioactive material discharged in gaseous effluents will notresult in the exposure of an individual in an unrestricted area toannual average concentrations exceeding the limits specified inAppendix 3, Table 11 of 10 CYR Part 20 (10 CIt Part 20.106(b)).The specified release rate limits restrict, at all times, thecorresponding g8ns and beta dose rates above background to anindividual at or beyond the unrestricted area boundary to lessthan or equal to 500 ores/year to the total body or to less thanor equal to 3000 orestyear to the skin. These release rate limitsalso restrict, at all times, the corresponding thyroid dose rateabove background to a child via the inhalation pathway to lessthan or equal to 1500 oremlyear. For purposes of calculatingdoses resulting from airborne releases, the main chimey isconsidered to be an elevated release point and the reactorbuilding vent stack is considered to be a mixed mode release point.

Dose, Noble Cases

This Specification is provided to implement the requirements ofSections 11.5, Ill.A and IV.A of Appendix 1, 10 CFR Part SO. TheLimiting Conditions For Operation Implement the gluides set forthin Section 11.3 of Appendix t. The itatements provide therequired operating flexibility and at the same time implement theguides set forth in Section lV.A of Appendix I to assure that thereleases of radioactive material in gaseous effluents will be kept"as low as is reasonably achievable." The SurveillanceRequirements implement the requirements in Section III.A ofAppendix I that conformance with the guides of Appendix I is to beshown by calculational procedures based on models and data suchthat the actual exposure of an individual through the appropriatepathways is unlikely to be substantially underestimated. The dosecalculations established in the OXa for calculating the doses dueto the sctual release rates of radioactive noble gases in gaseouseffluents will be consistent with the methodology provided inRegulatory Guide 1.109, '"alculation of Annual Doses to Kan fromRoutine Releases of Reactor Effluents for the Purpose ofEvaluating Compliance with 10 CFR Part 50, Appendix 1," Revision1, October 1977 and Regulatory Guide 1.111, '"tthods forEstimating Atmospheric Transport and Dispersion of GaseousEffluents in Routine Releases from Light-Water Cooled Reactors,"Revision 1, July 1977. The ODC0 equations provide for determiningthe air doses at the unrestricted boundary based upon thehistorical average atmospheric conditions. NUREG-0133 providesmethods for dose calculations consistent with Regulatory Cuides1.109 and 1.111.

ZEDE91/37

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WE

MW O WUCRAR MU STATION 0C0=2 M1S. 50-10. 50-237. 50-249 I

Dose, Rediolodines, Radioactive Material in Particulate Form andRadionuclides Other than Noble Gases

This specification I@ provided to implement the requirements ofSections II.Cg III.A and IV.A of Appendix I, 10 CFR Part 50. TheLimiting Conditions for Operation are the guides ast forth in SectionII.C of Appendix I. The statements provide the required operatingflexibility and at the same time implement the guides set forth inSection IV.A of Appendix I t3 assure that the releases of radioactivematerials in gseous effluents will be kept "as low as reasonablyachievable." The ODOl calculational methods specified in thesurveillance requirements implement the requirements in Section III.Aof Apesndix I that conformance with the -guides of Appendix I be shownby calculational procedures based on models and data such that theactual exposure of an individual through appropriate pathways isunlikely to be substantially underestimated. The ODIC calculationalmethods approved by NRC for calculating the doses due to the actualrelease rates of the subject materials are required to be consistentwith the methodology provided in Regulatory Guide 1.109, "Calculationof Annual Doses to Man from Routine Releases of Reactor Effluents forthe Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I",Revision 1, October 1977 and Regulatory Guide 1.111, "Methods forEstimating Atmospheric Transport and Dispersion of Gaseous Effluents inRoutine Relesse4 from Light-Vater-Cooled ReacLors." Revision 1, July1977. These equations also provide for determining the actual dosesbased upon the historical average atmospheric conditions. The releaserate specifications for radiolodines, radioactive material inparticulate Lorm and radionuclides, other than noble gases are dependenton the existing radionuclide pathways to man, in the unrestrictedarea. The pathways which were examined in the development of thesespecifications werei 1) individual inhalation of airborneradionuclides, 2) deposition of radionuclides onto green leafyvegetation with subsequent consumption ty man and 3) deposition ontograssy areas where milk animals graze with consumption of the milk by

Gaseous Waste Treatment

The OPERABILITY of the gaseous waste treatment which reduces amounts orconcentrations of radioactive materials ensures that the system will beavailable for use whenever gaseous effluents require treatment prior torelease to the environment. The requirement that the appropriateportions of this system be operable when specified provides reasonableassurance that the releases of radioactive materials in gaseouseffluents will be kept "as low as reasonably achievable". Thisspecification implements the requirements of 10 CFR Part 50.36o,General Design Criterion 60 of Appendix A to 10 CFR Part 50, and designobjective Section II.D of Appendix I to 10 CFR Part 50.

ZEDE91/37

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r mIMM NUCLSAR YO6U STATION DOCUT NOS. 30-40, 30-137, S0-2&9 I

Concentration

This specification is provided to ensure the concentration ofradioactive materials released in liquid waste effluents from the siteto unrestricted areaa' ill be less than the concentration levelsspecified in 10 Cf2 Part 20. Appendix B, Table II, Colum 2. 'Theconcentration limit for noble gases, MC in air (submersion), wasconverted to an equivalent concentration in water using theInternational Commission on Radiological Protection (ICRP) Publication2.

Dose

This specification is piovided to implement the requirements ofSections II.A. IMr.A and IV.A of Appendix 1, 10 CFR Part 50.The Limiting Condition for Operation implements the guides set forth inSection II.A of Appendix I. The statements provide the requiredoperating flexibility and at the same time implement the guides setforth In Section IV.A of Appendix I to assure that the releases ofradioactive material in liquid effluents will be kept "as low asreasonably achievable". The dose calculations in the ODCl implementthl requirements in Section 111-A o! Appendix I that conformuance saiththe guides of Appendix I be shown by calculational procedures based onmodels and data such that the actual exposure of an individual throughappropriate pathways is unlikely to be substantially underestimated.The equations specified in the OD1 for calculating the doses due tothe actual release rates of radioactive mat erlals in liquid effluentswill be consistent with the methodology provided in Regulatory Guide1.109, "Calculation of Annual Doses to Man from Routine Releases ofReactor Effluents for the Purpose of [valuating Compliance with 10 CFRFart 50. Appendix I", Revision 1, October 1977 and Regulatory Guide1.113, "Estimuatig Aquatic Dispersion of Effluents from Accidental. andRoutine Reactor Releases for the Purpose of Implementing Appendix I",April 1977. NUREG-0113 provides methods for dose calculations with RegCuide 1.109 and 1.113.

ZEOE91/37

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6

IDWZ8D NUCLEAR Yom STATION WOC=T NOS. 50-10, 50-237, 50-249

Liquid Waste Treatment

The operability of the liquid radwaste treatment system ensures thatthis system will be available for use whenever liquid effluents requiretreatment prior to release to the environment. The requirement thatthe appropriate portions of this system be used when specified providesassurance that the releases of radioactive materials in liquideffluents will be kept "as low as reasonably achievable". Thisspecification implements the requirements of 10 CFR Part 50 and designobjective Section I1.D of Appendix I to 10 CFR Fart 50.

ZEDE91I/37

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.4

0

NIB XUCLAAR POM STATION VOCUT P0G. 50-10. 50-237, 50-29

MUD=U PIRMISSZ3L1: CNCVOIMATIONS (NYC)

The concentration of radioactive materials released in gaseous andliquid effluents from the site to unrestricted areas will be less thentb ,concentration levels specified in 10 ClY Part 20, Appendix goColumn 1 and 2. The concentration limit for noble gases, 19C in air(submersion). was converted to an equivalent concentration in waterusing the International Comission on Radiological Protection (ICRP)Publication 2.

IAXIPMMI ?EMISSIBLZ CONCET3RATION OF DISSOLVEDOR ENTIRAIWD NOsLE GAss REL ED fiWI

TiE SITE TO NRE SThICD ARASIN LIQUID WASTE

I

Kr-85.Kr-S5Kr-87Kr-88

Ar-'lXe-131mXe-133mXe-133Xe-135mXe-135

MIICLuRiEiU*

2.0,Oh,5.OE-C'&.OE-059.0E-OS7.[.E-057. 0E-O-S.01F-046.0[-0C,2.014-.2.01.-04

ComputedAdjustedR - 0.01

from Equation 20 of ICiP Publication 2 (1959),for infinite cloud submersion In water. andrem/week, density - 1.0 g/cc and Pw/Pt a 1.0.

ZEDE91/37

9 of 36

I

MUM HUC A M l 5? U TAIOM DDCnT MOS. 50-10s 50-237, 50-249

AVKUAGB IU9GT

The average energy of fission and activation gases was calculated forthe Saseous affluents released from the site. The average energy iobased an the percentage of each fission Sam nuclide present and itsaverage energy per disintegration (I in NeV/dis) for Sems and betsemissions separately.

ECa 3.85E-01 M@V/dil

Es a 3.OSE-01 MeV/dis

U

ZEDE91/37

10 of 36

S 1

MU NUCLAR ?12 STTIOMN 110 1 NOS. W-10, s0-Z37, 50-249

• JMAStq1TS AND AlOIPATI(MS

A. Fishlon and activation 8as.: The D-1 chimney, D2/3 chimney andD213 Reactor building Vent are sampled weekly via a grab sample.The samples are analysed for specific Isotopes present in therelease using a Nyper-Pure Gerneinun (UP Ge) Spectrmetry System.Tritium it sampled monthly via a grab ample on the D-I chimney,02/3 Chimey. and 02/3 Reactor Building vent and analyzed uasing aLiquid Scintillation Counter. Krypton-85 is estimated in the D2/3chiamey using a recoil or con-recoil calculation using the fissionper second plot and the sam of Kr-65. r•r-87, r-88,. Xe-133,Re-133, and Xe 136 activities present in Reactor Off-Coa.

N. Iodine and Particulate: Iodine and particulate samples irom theD-1 Chimney, D2/3 Chimney and theD2/3 Reactor Building Vent arecollected for a imaimm seven day period. These samples areanalyzed for specific nuclides present in the release using a H?Ge spectrometry system. When Iodine or particulate samples arenot used for reporting the release rate due to management decisionthat the sample may not be representative, an average of thepreceding sample and the following sample is used to calculate therelease. A monthly composite of the particulate samples is sentto a vendor to be analyzed for Fe-SS, Sr-89, Sr-90, and GrossAlpha activity.

C. Liquid Effluents: Analysed for specific isotopes present in therelease using a HP Ce spectrometry system. A composite of allbatches for the month is sent to a vendor to be analyzed forSr-89l Sr-90, Fe-S5, U-3, and Gross Alpha activity. A sample ofeach Containment Cooling Service Water (CCSW) system is analyzedeach month for specific isotopes present in the release using a lHPGo spectrometry system. A sample of each CCSW system is sent eachmonth to a vendor to be analyzed for Sr-89, Sr-90, Fe-S5, 11-3, andGross Alpha activity.

D. Estimation of Overall Errors: The methods used for estimatingoverall errors associated with radioactivity measurements varywith discharge path and form of isotopes. Factors that contributeto the error include such items as calibration of countingequipment, counting statistics, sampling error, discharge volume,and flaw rate monitors.

E. Estimation of Vendor Analyzed Information: The vendor analyzeddata for Sr-89, Sr-90. Fe-55, U-3. and Gross Alpha vas projected.where applicable, for the months of May and June using April datafor liquid effluents. The vendor analyzed data for gaseouseffluents was projected, where applicable, for the months ofApril, May, and June using March data. The data in this correctedEffluent Report reflects final vendor analyzed information.

ZEDE91137

11 of 36

DRESZM1=* PUCIU rukSUTAT1WMITS 1,2, AND -

EFFDTAnD VAMT DISO6L S8IIIU4AML 1110

.1

CUE=O~ ErFLUMM

SUPMITZI~ OF ALL RELEASES

Docket Numbrss 50-105023750-249

=9? OF RZLIASZE?. TOTAL

UNTS Usta QUARTER 2a4 QIJAIIU Mfz

JrS~L(W AND ACTIVAiaI( CASEI. Total Release C1 3.49E 9.O6Z+00 7.31

I. Average Release Rate for Period uClsec 4.499-01 l.l5Z.OO

3. Percent of Technical Specification Limit .... c I 9 7

A. IODOL=.S

1. Total Iodine-131 Ci 4.664-04 2.181-03 9.51

2. Average Release Rate of 1-131 for Period uCilsec 5.99E-01 I.SOE-04

3. Percent of Technical Specification Limit - *

4. Total lodine-131,1odine-133,and Iodine-135 Ci 6.27E-03 1 2.319-02

C- PARTICUJATES1. Particulates with half-lives 1 8 days c1 6.57E-02 1.09E-02 8.092. Average Release Rate for Period uCtleec 8.45E-03 1.39E-03

3. Percen.t of Technical Specification Limit A%*

4. Gross Alpha Radioactivity CL 4.86E-06 4.19E-06

D. Total R1. Total Release Ci 3.19E+OO_ I_.05E*W0 7.89

2. Average Releaie Rate for Period uCilsec 4.10E-01 I 5.15E-01

3. Percent of Technical Specification Limit j I j * *

The information is contained in the Radiological Impact on Man section of thereport. Total airborne release data is provided which includes fission andactivation gases. iodines, particulate&, and tritiun.

ZEDE91/37

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-M NUCU~L MMI S1ATICHVXIT3 1,2. AND 3

WFWUI AND VAST DISPOSAL SIAIMflAL MOST1..2UMUiz.. Through .. m... 1920

I

Docket Numberst 50-1050-23?50-249

LW(uci/cc)SUMATION OF ALL 3.ZLASKS

1. FISSION GASKS

.

3.

Kr-S70 1.21

12-11% ..6KOa&-133 A.RKOAr-4I &9KO

RODIMK

1-131SOS-11-133 .9-21-13S932[1

PARTMMCAThS

Sr-895,0014-15Sr-90 5Cr-SI6.1K1Nna-sI 7. 771-1h

ft=55 1.10-13

Zz09i0 1. 9 3ZLI3N-9,5 1.31"-I3

-99 1.02E,42RIA-0-17. 711-14As-ips7,06ff-1i

1-131 2-3 -14

CO-136 795E1

LA-14Q 1,7-13

Others:

Gross Alpha

ZZDE91/37

3,00 "--

13 of 36

, UNmIT I

UIWIMT MDV WAIT DI8SOSALIMIWIIAL SUMT* 2*MCZ- Throtbh •J5 3.. 192e

Gt Evni

s_ GROI-,A LEM J SZLASU

_ ESUI-ELAVAID 33LZASKSDocket Number: 0-10

,~,uqwtc ~g~w U A ~U

NWULMS IZIASED UNIT Lak QWTlM zag QUTU LS? QWATES Wi QUAZ

grn-1ism €__

a.-I__ _ _ . CL. * ..... l.... cAA1* •

• _ _ _ _ _ _ _ _ -_ * .. .. "_ _.,_"_

No- 11~r 5 * * _ _ __ _ _ __ _ __ _ __ _ _ __ __"_ _

1-135 CL * *_

TOTAL 11L Rom_______________k A L...... A • ... .... ........

Zr-St -SL A_ _ _ _ _ _ _ _ _ _ _ _ _

A - 33 •- L * : .... .. ___*_.,.

• It3 cL * 0 *_ _ _ _ _ _ ________

L, L .IAZkQL,... A3I.SQ•

b- ._ CL * " 0

sR -•fl ., cL *. e -o .. ... _.___-___....

S-12&4A _______

at- t -L * *-_ _ _ _ _ _ __ _ _ _ _ _ _

.C .1 3L-59 C. * .L. * " -___

c. oL S ,.,RK..0 5,•.-o ......

k-10 Ci

S•-.124 7C1 * -* .. ......

-133L * 0 'ms a•hL...... AL 0 0 . ...

fla-111 A L 0 .....___ _ _ __ _ __ _ _

Eb-12S L .....1_ _ _

l e*-5 3CI ]"•E•76 •

TOTAL I RO- K-

0 The activity of thappropriate table.

L - M&549Z-.is nuclide is

- . a.1a. * , ..NInW NANP

leas than the LLD listed on the

ZEDE91/37

14 of 36

UNIT ISF/WPMT AD MAIM DISPOSAL S6Z*OAL SIOT

_Wm _ . l rouwb -- But& 19-I

DhL kmman cASZOUS EFnArrs

-Clio= L9V9L W*IA 93

_________5DI-(IEMATO KILEASES

ILEVATIED RELEASZS

Docket Numbr: 50-10

Reis.$# MODETT

NUCLIME RUZUAED WIT JAflAft fIRUOt V RARCB I" Q•UATE TOTALF Slim CAES CA-g,,

, a-18 • " *

ALK-MA C1I.r18 ~ CL • * •

.r-as * ...Irx-R•5 B e * .. * '0

....... _z l 3C L ____.....__ 0 ... ... 0 "

-1-il CL * U .

1 -2133 - t *... ..... . .1-131 :CL- * • -

SrCL 0 0 1 I

S- " 24z C1e

sf49 * ef E - ..... 0 _____• .... =. ,

- c ;s O c • ' • ..... • •

co•58 ....... CL• I~L.. • ' Q~.. ... . .. •i * .... L 0 ........

- . -.U 7.....* .... I •La * ..... ... a 7

oOM 3" 49=0. C-,L04-.0 ..... 2._L_-6 _____ _9 -5 _

zr•. .. .. iCL • aI*- a~S ... . o : ,:*..... L aa a*Cp-Il c ]* a.!a !a..

Ca-137 CL 2.SF-Of ,, , 1-O ..... E L. f5Qau-IBC • *a *

-______ _______ a . .. a i a_ _ _ _ -_ _ _ _ _ _ _ _* .... .... a , -

______ _____ ___ et * a *

__ -___1 ___0 __ CL • * * a

TOTAL5 el .. •.&EO ....... ..... . *SQL •J L L.

a The activity ofappropriate tabl

this nuclide is less than the LLD listed on thee.

2ZDE91137

15 of 36

.I

I

'NIT ITI"UMLS £AM yMn DISOA SUI*MUAL UMoT

• ~Winaz GASI1U SVVWDS?8tl•&grll8 csrmqb Jme 192

.I

GROMW IEM RUWEAES

________SMI1-IIZAT IL ELAS2S

Z. ILIVATWD REIZASKS

Docket Nufmbr: 50-10

IF T; TP!L26co, MOOKY - T -

UwIT AIXIL .NOT it= 4 quAmTOn TOM

.. X•135m "Ci "•*•.1Rx-88 CL A -

1K-13 CI _ _ _ 0 _Ke-lUS al * C

1-131 ,C1 , * C . 01.-113 .... ( .. * . " ,?.. -• ....__ ___ ___

TOTAL __

Sr-90 et 2,21R-08 h.)3 -08 *65[O

qa iia

• C o .. .5 - S L 0

i-IAl~a

a-SA

FIR-S9 CI _••co-so0c 4.721-0& a. 3Z-08 s.041-07 s. •8z-Ofi

2r-15 Ci * 0 0

-124Ci -_1r-13 C IA•3-5l. C1 * * * *C11-17 Ct ai 9 a0i -iz~-92E0C-14C * 4 C a1ft-13 CI * a aui...... .i na...A&-133 CL- a - a -

sb-12CL * a a a

,-3537 CL 29E--07 6.-21-9 6 " - -

mm73i a- a.9IL- ,,

..a -i.....O .... CL a -• a aSb•-12.1 Si ________ I *Fe-li S 4C21-7 62.J •~Q jjg

TOA L7.6.O ,, ,-Q , =,,K-O

a The activity of thisappropriate table.

nuclide is less than the LLD listed on the

ZEDE9l/37

16 of 36

I

.4

UNITS 2AND 3KIVWUS AXWM~ I V&t3 SOMU SfIAML4UL 31101?

DZL~cLBI ASCOUS 0FLUJUIT

I

GROUND isVmL RELA•SES

SNI-ZLEVATWD IEtLAs

AL. ELEVATED RLEAE

Docket Numbers: 50-23750-249

1U EmS RELESIR UIE T I" QUARTU 2W- qUART. Mi& QUAIT 2d Q2AMTER

1~332M CAASt_______ _______

tC1 .h--luS 22..L -2,3" -03

.- lISa .CL C.1UE-01 1. .........

" r-S8 C1 " •0,760-03 '" 323K r45m CL __ ,___ ___ __ • ........... ,

___-.8_ CL 5.2217-03 2.341-01In=15 C1 2C6614,00 3.12100 ....

• Ar-k1 CL * 6.221[-02 ....SCL 13. &914400. 9.061.OO N0141 NO91E

1-131 1___ .83E__-04_ _ 1.3R1-02 ...... .. ...........1-103 CL 2.201-03 6.C1-031.11i5 CL 2..27L-02 1.1-02.ATOT L .1351.03 2.04-02 NONE .. 4E

.... -9 ., CL _ 2.42=-02 5.927-05sI-90 2l 1.973-os ".21A-07

... r-S1 CL ,,,__ _ __ _ C _ _ _ _ _ _ _ _ _ _ _ _ _

S-L• e 2.,1-5 Z16-06024 3NONI~-5 CL. CV.-S9 . CL -___.....__ * .. ... _ __ _ __ _ __ _ _

.. r-95 CL * ......... •__

• . a-95 ".CL .. * ....__ _ _ __ _ _ _ __ _ _ _ __ _ _ _

•an-10c3 SL * * _______

5&d•...- ......" CL~c , • ....... ._

,.C,,-1ik -.C . ±,.. * ______

C.s-l36 ..CL 0Ca-1l7 • L~ 4, 641-06 I .1a21-O5 _______

Ka-I Q..O ._CL 2.401-02 8.571t-04 .______

Ba-Il~l CL * * *______ ______

4•.2 L i , * ., ..... __ __

+ " l . - 5 5[- C L 3 .6 1 1[- 0 4 ... 2 7 .4 1-0 4._ _ _ _ _ _ _ _ _ _

• TO TA L . C L 2 .7 1 1-0 2 _,_ __.-_ _N _ _ _N_ _

* The activity of thisappropriate table.

. .EDE91/37

nuelide Is less than the LLD listed on the

17 of 36

Sr

S

ZRIMM WNLEA. townR SUTATWITS 2 AND 3

97UM ANDI *W lABlEB DIBOSAL 3*IAI5EUA RUGSI . mzjvaga. Ibrough ..JI&ucL.. 192[f

DaL~h~uuGASOUS UfLJUVT

_________CROWED LEVEL RELEASES

________SzmI-ELRATV IRELESESDocket Numbers: 50-237

50-249

XX .IZVATID RELEASES

FT- a44KUCI4 MA RLAS=D UNIT JANUARY FJIRUAAT JU QUATER TOTAL

X.-131

E1-13 C1 2,141-01___ WAL_______ a,710 a. =Kr-131 .CIL a 2,7Z0 2.?a .

ErA_ .CL_ 2-a !1 a,2& a ________________

Sr-AS C1 1. 721--07 1.703E-04 7.3-0 51217-03

Xe-til L*

Sb-124 -L2CI-4414-4i 210

1OT31 -CL- 2.410E=0 3,92" A. 2 851-01

PR CUIATES - uiZQL 4.64f______

1&-140 4L1731-03 1. S E-04 2,72E-03 2. 971C2i-141L~*

_____&____ .CLZ=Q 12.02EbL06 afgC 2.731E-4CLL _Sa 3. aE0 a.2-0 .8E0 ,

a 7he activity of this nuclide is less then, the LLD listed an theappropriate table.

ZEDE9 1/37

18 of 36

-I NUMlEA POM S1ATIOWIlTS 2 AND 3

gWWUtI#T AND WASM DISPOSAL SIAMUAL REPORTazh l Through jm . 19i

D32"'ChLiM GASEUS IFTLuD•

I

GROUND LEVEL RUL[ASES

SIMI-EL..ATID RELEASESDocket imbeirs: 50-237

50-249

ELEVATED RELEASESre, ,in.Nf~i

Y-Y I

NUCLIDES REtASED UNIT APR IL . MAY 2ad QUARTER TOTAL

-a ..CL *.*.____......_____*____ ___ ____ ___ A. 161-01 ____...............-aC * -...... -

=r-S CL 6AJ6L1[Q4.- .. 111=04 7,63481[-0x1I35 C 3,48 1.0•0 .1-1M90 2.83Et±QQg J,

=t-U1 ... .... 9i * 6.2__-L 4 e-o CL _ 2.____ 3

1-133.. CL 1,84L-03 2.QL.--.. - LJL-0.I-1......... . CL 6gSL.-O.l 4.431E-03 .&[03

Ci 8.4-0 : .3fig4-4) 4. 31[-032."PAINTICUIATSM-

S_-_ _ _ CL • 2.69--S7 , S. 3E.-8 .U 0Cr-M1 CL * ________ * *£4tn-SA, ,, .•CL 8.1[.0Z ....... * _.__• FQ ___

______ _ 0! I * * __ _ _ _ _

'¥ -9CL ..... * * * __ _ _ _ _

-o.-60 . C 7.99--0 . 5 . 6-Zr-~9i..... L * _________ _______

Jibo i.......... ..C *__........_ a ,.,__ ..... *Qt-13 _eL* •*a-It& IQL.......CL .... •* , 0.. 0

C,-1l4 ..CL * * 6s-124. 2!EO 8,3 5______ _______

CuUL..:Ef Z&E:0 9,a _______aUs- ..6.. CL a * *•

.. t-140 CL 2.S2-04 3,"1[-04 a.izQ-O.W.140 .. _CL 4.823..-04_ E.0 47-04 3,481[..Gr.DA-1 1. a"__ C_ I_"__ _

re-65..*..... a a a_ a_- 33 ... 7 * * 0 a.•, bI - . _ L. * * *3

*The activity of this

appropriate table.

ZED[91/37

nuclide to less than the LLD listed or. the

19 of 36

I

DP3SDIN NUCLEAR WICR STATIONUNITS 2 AND 3

£FFL IT AND VAM DISNOSAL SEMINNUAL RNoMT. janum Through Jun 1990

D211 fleAtor Building Vent GASEOUS EFFLUM

GROUND LEVLEL RELASESDocket ?4nbere:

x] SEII-ELEVATED RELEASES

ELEVATED RELEASES

50-237SO-249

XUCL IDES RELEASED liMIT 1"t QUARTER ZUd QUARTE Jlit QUARTER 2"~ QUATER

Xe UL .....-.. ..... ...___ __ _

Xe-135LXR-133 CL *__,, .. , .,L

=L _________

....~ I n..-..7. CL ______

II AL.-8.. .CL ______......NON

K-31 CiL AEA 1.0_E_04

1-1 3S .CL -- 29*1__04.. m, CL, 2-0 hEQ3 QL . $Ot- L..

AX TIU- TS _ __ __ _ __ __ __ _ __ _

.5_r-99 . __..... .. .CL 9.391-05 6*..S-0. IIIII____

Sr-90 .. 19. 6._ 4,43[.--04 ,.,__ ___ __ _

C-3S CL Z,9E V=0k A Q• __-__

__ _ -CL- Z.8 -3 Z8Sz!... .LoQ2L.____ -__ ___ ___ 1.391-05 _______-o_"

a-o aC a S:~ 8.53-04 -1 tOAL-Ok ..F • .= 5 2 e ! . .S 8 - 0 3 1 , ( 6 E --Q 4 ..

Co--60 6.7 S-01 2.0SE-03Zr-5,D........ ...L_

... u lO.. CL .2 5 -* . __ _ _ __ _ _ _ __ __ __ __

Sb-124 CL 2 1.40E--04 , ,.-.~ J. C

CL zA* _e .... * ...... *_ _Ct=U 6 .... ___. -SL ___ ___ __ ___,____ ... .. .. ._ __ __ _

C -137 CL a *li-&O . .... CL 4. L18I L.._- . L1 LQ130 __....... ... _ "_

J -~0 -SL , -043f-0L L lO ....Ce-141. . . e. * CL..._____zn-65 C 2.959-04M=29• , Cj 2,97Z-.O3 8.59E--04

Sb-125 CL .=EC±3i -SL _.-1J._•EJL. 2A_ Q. ___03___ ___'X'M 1 "A L , , C l 3 .8 2 -- 0 2 7 7- - 3 . O E'N N

* The activity of thisappropriate table.


ZEDE91/37

20 of 36

MRSOM IncAR am B~U TTICIBUNIT I AND 3

LMUVIT AND -IMI DWSrOSAL DSMWWMAL • T8ORT....amz. Thhroub _nA_ 1920

11 Eate~tr B? l~dIA lf GASEOUS IIFLU

I

K'

GROUND LEVEL RJLEASESDocket Nu.bere: 50-231

SMI-ELEVATED RELEASES 50-2&9

ELEVATED RELEASS

NUCIDE RELEASED ýUNIT JANUARY FEBRUARY MURCH Wa QUARTER TOTAL

nC l

vunsr8 CA£l ________ _*_____ ________

1-131 -Ci- * a IXa1,m4 a_ _ __ _ __ _ -_ ______.__Er-fl . L __ __ __ __ _ * ...... * _ ___

Kr,-Sn .CL

1r-a . ..CL a ,, a, . .. .a1a-135 el 4 4 a E

TOTAL ___Ci_9__40 -

I-t33 3. 4ZS-O.- 8.66P-04

1-54 7* -7-~ 23EZOh 2..... A i2.81"....

1-115 CL 4.991[-O1. a a 4,991-Ob10ZL .. CL 9.7[0 4.06-04 __O 9ZL[ 3... 1]L&2E03_P ART! CULATYPS_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Cr-51 CL 1,52ff-0) 2.751-03 .... . . D5" •+0 7.32E-O)3

La'5 _i 4921-O4 2.7il1-O.0 8.6-0 .53£-041

, PFe-59 + -..Y 9- L..OE-04 S. 73E-04 2.54Z-O5 1.58[-O3-to-6o I I.,55 1-03 2.37 £ _-03 8 .18£ . . - O3

ZrJ- .. CL a a .

BU-103 £A•,l- 1ct 6.30-o.. 6.23_-05 1,250 4t.Sh-121. aL L4 j a a-001Jnl-t3* ..... .C * a a a.. -

_ Ci+3k el I.....L*

CE-136 - CL a . , a. s-Ia. 7..e...,........... a * a *'

J.-1t0,o .CL t.J3Zt~L.. k.0s,--0 • .. A.tt

k-140 Ct *aa a.0 a-04..- As ..CL 1.Tt-o 1.1-01 a-04 +-01s-o.4

06o.99 , Ci- 6.4bE-04 - 2.11EZ-03 2. I3[Ot+ 2 L7£-0Q3

-2-94E0 .CL * a a

SLALc ..L.oDA-o2.... 5.8-02 •.J2Jk-L. .8.2EZ.-o


this nuclide is less than the LLD listed on thees

ZEDE91/37

21 of 36

-• WUCLKAR ?f STATIOIUNITS 2 AND 3

U10IT AND WASTE DISPOSAL SEDMUA UAL RURTAgril Through .JmL.ue 1929

)2/] I.arctar Uui114n~ Vntk GASEOUS EPYLUDITS

CROUND LEVEL RELEASES

I

Docket Numbers: 50-237SEMI-ELEVATED RELEASES 50-249xx

ELEVATED RELEASES

CONTNUOUS MODENUCLIDES RELEASED UNIT APRIL MAY iUN. 2" QURTER MtAL

In-138 CL * ±..

K. -. .. . ... . .... ... . ...........-- I~r47 C • ... ., . .,

K, J-88 C1-1, 5 -CL 8, • I •

Kr-AS _.L _________,, 0 0

X.-1353 CL * * * •________

TOTAL CL .;1i . . i III

.... 2.. 2.hEIO.... 1DQ... .. 9L0.....

1-135 • 1-88E-03 232E-OL 2,H11-03TXOT~k ... = C 1 191[-Oi 2..01E:-3 S.30£- . 2,6LOL...3PART? LUIATES_______ ________

- .... s E-5 7_.-6 -1=W-O-i-6..55.L.- 9St-90 .C. -0 a a 4..49.-07r-S C *1.44E-0 1.441-04.

an-stt 2 .o6f-0 i.sK-0*i 3.a97£-o.: 7.5.&-04.co-"5 C. 551-OS- 6,21.9-OS 6. 981[-05

Co.-A0 -Mi 7.SE£-04 6 .4 21[-.0 6.76£.-0 2,09£-03

i a. . ., .....O....1Nb-.95 ai a 0 . ..... *

Ru-103 __ _ __ _ _ __ _ _A = t m...,L .0 •_,._._....._ ,,AB-1100 C1 __............ * *I. ....

Sb-Ce124 SL ... * ...... a *1-131 e. ..... * a. . -a 5

tb.-1l4 CL 0 * a aC|-1&6 CL jQ* * a

Ca-137 ,,,CL * a * ___, .. ,,___

A.-6 ... .. Ci * * *.

flo-99 Ct 26A1[.-0 2.7_3E-04 3,22E-0•,4 952&&-.4Sb-125 . L • , * aTOTAL CL 2.14E[-0 1 1.9E£Q-3 3.9d-QO3 , 7.J79LQ-L

• The activity of this nuclide is less than the L=D listed on the

appropriate table.

ZEDE91/37

22 of 36

MM= NUCLEAR MM BTATIONMNIT 2

DTWUIT AND UOUM DISPAL SENIANUK PMaT•Jinwu z Through J 1920

02 Isolation Condlnser GASEOUS EfLWDM

I

11 03013W LEVEL ULKASI

SlHI-BLEVATKD RIt LM

ELEVATED RELEASES

Docket Nuber: 50-237 .1

6&^tI U A~ ~

NUCLIDES MLEA ED UNIT [IM QUARTER 2&W QUARlE Jat QUARTER 2&d QUARTE

X e - 1 18 C L .... ....__ _......a

Xe-135M CL .. *Kr-87 .. C1 _

Kr-85 CL *

Xe-l]S¶ .CL ............ _ a _ _ __ _

Xe-2=133 C1TOTAL 1 NONE NON E NONEIODINKS-

i -il tl _ C L .... .. ... ..... ...1-131 !

-- I ... . CL .C1T O T L £ J ~ m . . .,,, O _N !,, J

CrT-1 (ML __Co58._L ______....__

-Fe-S9 C1C-60 4,, j.99E-05Zr-93 _ _ _ _ _ _ _............

_ _ _-95_, CL ,, , ,,IRu-103 CL *_______

1 QI..IIC __________ I * ..... iO

Am-lion el ISh-124 .Ci _ _* , __ ,,,

--- 1CL a13C-1360 Ci I

c,-117 .......... *L_________a_______Jd.-l ...O . CL .... a ,, ______

_ ,-IlO CL *

.__ i....l..,, ..CL __________________a______

Zn-.5 CL ..... __ __,,__, * _ _ _ _ _ _ _

Sb-125O. C •FC-5 1 ~IV=S ,, 1.,*..

a The activity of this nuclide is less than the LLappropriate table.

listed on the

ZEDE91/37

23 of 36

I

.MOM NUCIAFR PFR STATION". - UNIT 3

£FlDOT AND RASM! DISPOSAL 89IANIOAL RIRT_jIM ZO_ Throuah Jue 1920

D3 lantatiao !ondanaer GASEOUS E M

]_ _GROUND LEVEL RILASESDocket Number: 50-249

SMI-ELEVATED RELEASES

________________ELEVATED RELEASES

r4wrTIMM11C "Mr RAT"~ Wflht

NUCLIDES RELEASED UNIT: I" QUARTER 2A, QUARTER IJt QUARTEI Wad QUARTIR

FISsION CASZS__ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _

0. -138 _ __ _ ...... ..

____ _r-87 _ ___ CL a _ _ __ _

Kr..S CL ,Zx4i i3........ .. L ________ _______ _ _ _ _ _ _

Xe-133 .CL .... . ... _ _xetO ,, CL NQ L ... . { N ......................... i=•I5 -___ONZ __

1-131 CL *X-133 Z....... . * ..... ,1-135 !

PARTICUIATES.

C2S-89 Cl *Sr-90 CL -

Cr-1S Ci ..... a.. -5. ..... ....___.__e_-o____._____"

FeS.59 CL ____ ._,_..

r-g1 I NOE * -, 1,93E,4[O. C__ u 40 .. _ _.__ .. _1 ._ ........ *__ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _

he ac-ivit 2.... ... t i nis less * ...... ____nhJb-12r r.... CL ....... *Ay-l34 _CL .... ___ __* ,,__ __ _

C,,-137 CL _________

ia140 CL ________ ______

CS-lU4. . _ CL ..SaU~ ..... eL ... a

Ea-24i .. !CL 2.__ __ __1_a -_ __ __

We5 ICL, B ______-o_

TOTAL .. L .(ONL...N.. OLE 1.93~-O4 NONE

* The activity of this nuclide is less than the LW listed on theappropriate table.

ZE.9R1/37

24 of 36

nDUm NUCZAI PCIu STATIONNITS 1, 2, AND 3 .

UVLVURIT AND VASTE DISPOSAL SOMIAJ@IUA RIMOT. nCLI Tbrough f 19MLIQUIDZ"VZ

I

SIUHATIOH OF ALL RELEASS Docket Numbers: 50-1050-23750-249

UN IT la QUARTER kQd QUARTEREST.TOTALnos' s

A. ZISSICK AND ACQtVATUP* PAOWNCTS . .....1. Total Release i

(not Incl. tritium, mes, a1pha) C1 9.75-02 1.31- 5.56

2. Average Diluted Conc. During Period uCit/L 1 1.53Z-08 9.56E-09

3. Percent of Applicable Limit [ I A ,

. TRITIUM.1. Total Release Ci 4.89E+00 3.871.00 7.75j

2. Average Diluted Conc. During Period uClIaL 7.69E-07 2.82"-7.3. Percent of Applicable Limit 2 A ft

1. Total Release I Ci O.OOE*00 O.O0E*00 j 5.58

2. Average Diluted Conc. During Period uCi/,L O.OOE.OO o.00E0OO

3. Percent of Applicable Limit [ "

n. _ GOSS A lU_!OACTIV7TY1. Total Release I CIILLD ILLD I 15.1 1

I I * I

E. VOLUIE OF WASTE RELEASED (prior to dilution) l .

F. VOLUME OF DILUTION WATER USED DURING PERIOD liters 6.36£*09 _I 1.37E*10 5.00

A The Information is contained in the Radiological Impact on Kan sectionof this report. Total liquid release data is provided which includesfission and activation products, tritium, and dissolved and entrainedgases.

ZEDE9l137

25 of 36

DSZSDU6 & PWL a m ?W U TIOTD6ITS 1, 2s AND 3

TAsLa OF LowULIMITS OF IDMRICAILTT Docket Numbers: 50-10Felt LIQUID KLUDTSO 50-137

50-2819

Lm (Uia/tRL)

I

SZn:92

cn-90

Sb-14C

La-ifiCitL14xa-I1a

CrS

2.WDI=QgA affo-aa

JA.071O

-S7 1-3 __5"A____

B 6. 741-0

A 16Mh

6. 2RQL

1.591-06fSUMAMa

A4,22'Q73-OZ-0LL2.29E-0

I OfI1RCal

ZEDE91/37

26 of 36

DR&SMU NUCLEAR town STATIONUNITS 1t 2, AM 3

EFFLIUfNT AND WASTI DISAL S1EMIUAL REPORT

.IanB.. Through -- _JunL-_ 1990

Radvaste LIQUID METU Docket Numbers: 50-1050-237

Number of Batch Releases: 1.986E02 50-249Total Time Period for latch Releases: 5.459404wi mn

uMainum Time Period for a Batch Release: 4.779.02 *inAverage Time Period for Batch Releases: 2.751.02 sin11niiun Time Period for a batch Release: 1.00.00 winAverage Strem Flow During Periods ofRelease of Effluent into a Flowing Strusm: 3.68E905 LWain

1.2.

3.4..

S.6.

PEAWoWiUUiC A

NUCLIDES RELEASED UNIT ,Ia QUARTER Un QUARTER "I QUARTER Zud QUARTER

t~o-5R______ __iiii LZ.... ........

___-9_ _ _2.31E-04 A 0§1.E-4

t"InS4 ++ C[1.26£l-02 4.2.5£-=03CO-59 1 1.20E--04*FrM*S9 ci9,A5E-04 1. 20[,-04

C(6 CL 4.69E-02 1. 19 1---Zn-65 ......... .CL __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _* a ..

-C ISb-124 CL A. ".0E£-06. * "

... -13l _ ____. .... ..... __ _ _ _ __ _ _ * *1-133 .CL __

1-135 _ _ _ _ ."CM-134 Gi....... .OSE-05 9.45[-04•

2-.137 C- 2 --- " -02 11 E I-O ,Ba-IAO ____............____ ____*118-l40 - . . . ,, *14-14Q C , a

Cu-6E. .CL ,___ __....__ aEb-88 - -SL *3b-l..8 ....... CL ,_______ * a.. ',-...s . ... ... ....__ _ __ _ __ _ _ __ _ __

2 _-95____.___. ..._a.62 -06_CL

(above)Zotal For Period CL NONE NONl 9. 7Z4-02 1.31.£-01

X*-135 -Ci *il1..... .... a a+X.-i1S .CL ________ _______* a


this nuclide Seiless than the LLD listed on thete.

ZEDE91/37

27 of 36

I

VRDSDC4 NUCULwA row STATIONUNITS 1, 2, AND 3

ZrEVWDT AND wAsr DISPOSAL SNIAMOAL WORT

.1 =a ThroUgh March 1 9Q

.... dvt LIQUID EFFLUIUTS Docket Numbers: 50-1050-23750-249

JUCLIDZS RELEASED UNIT JAU .UARY MARUCH U1 QUAR71R TOTALSr-49 JL * __•_....._•

Rr-90 £L 1.56--04 ___47_-05 1.9_-"S -2.31E_-04AX- 4 1 CL * • • _

H534...L 7.m55-03 A_- Il____ 1,_9903 1._26E-____-5_ C1 8.54,1-05 ______-05 __.._1,201_-__

•ire-39 _CL .3.831[-04 5_02E_04 1._O__-__, 2_E-04Co-6O C, 3 .ZZE921-0 7.27E-03 6,Z2.1Q-.3 -4 691--02.a•5..! .. ...... ..... £L ________ * __________

b-l2l CL C ........ * 4 0 61-133 J: a a _ *

1-13S le

,-114 i .L . AJ"8i-.. a 8.0-3-OSCa-137 CL 1.64E-02 7.55E-03 1.83E-03 2.,5E-02M-140 CL I a a

..Ce-,14I t*.. *" ...

CA-138 a * a aFe-_ _ _ _ c 8 .2S[-03 1 .•38£-03 iEQ-3 1.07L-02

C1

(above)Total For Period ,CL 6.51-02 2.07E-02 11,17E-2 9.74E-02

.ZI3..-l..........CL a a a a___ -__ ___ ___ al a a a

a The activity of thisappropriate table.


ZEDE91/37

28 of 36

DMUSDD NUCLEAR town STATIONUNITS 1, 2, AND 3

£?WWDIT AND VASTI DIarOSAL UIMtAIOWAL RIPORT

Aud . Through .Iune 1920

,Advanto LIQUID EFLUTS Docket Numbers: 50-1050-23750-249

NUCLIDES RELrASED UNIT APRIL MAy JUNZ 2" QUART•R TOTAL

st*90 CL 5.441[.-05 5. 481[-05 4 o Q4j.05 !a.541-4)Ar-lCJL 0 • 0 0

In-34 Ct 1.30K-C3 2.22!-03 Z..2 11!-04 -4.=5--93Co--38 Cl & ft , • *

r,-59 -C ' 7".36.-o=5 37.'19-709 , - 1.20oL-O.Co-60 .IL -... 02.-03 6.021-03 3109-03_ 1jj -O2

Sb-122 CL 0 * * •

l. ..CL_ * * 0 *

1-133 CL * * * 01-135 ,, * 0 0 *

Ca-134 CL I..1.91Ez.-.4 5.53ZQt-4 .2,73E-.04 9,459[-02• B -4 .. CL 1A 2 Q .... .iV Q...........LZ& Q . ......... * , , .

IA-140 lCL 0 0 0 0C*-11 C1 * C * 0

Cu=-64 .. ! * 0 0 0Rb-,0 0

CM-CL . * 0 *Ire-S5,cS -a- z1,1-03 .9,3E--04 " 4,3.7E-04 2.441-,03_ zr_-95CL 0 5.62E-06 0 5.621-06

-C!___ C L _ , , , ,, ,

(above)IotalFr rim . Cl. 2.49E-02 6.91E-02 3.L70E-1E

Xea-133 .... ... .. .---* 1 SC L ........ , ...... 0

0 The activity of thappropriate table.

is nuclide is less than the LLD listed an the

ZEDE91/37

29 of 36

IWS)IN NUCLELAR MOMR STATIONUNITS 2 AND 3

VFWLMT AND WASTE DISOSAL SEMIANNUAL RIEORT

.janwz... Through .JunemL 192Q

CM LIQUID EFFLUIETS Docket Numbers: 50-23750-249

Number of Batch Releases: 6.OOEOITotal Time Period for-atch Releases: 7.44E+01 minNaxinuM Time Period for a Batch Release: 1.249+00 minAverage Time Period for batch Releases: 1.2&4,O0 mininiimum Time Period for a Batch Release: 1.24F.O0 sin

Average Stream Flaw During Periods ofRelease of Effluent into a Flowing Stream: 3.68E+05 L/main

1.2.3.4.S.6.

i'~a~ WIN SA*t~ MftY~W U*W d AAN

NUCLIDES RELEASED UNIT lI" QUARTER 2nd QUARTER i QUARTER 2n QUARTER

Lr-89 C _ _• •it-9CL 2 *

Ar- _______ •A ..... . •...2 iL i.2o-58 C * *

• e- _L l •_______ *Co-60 -4. 1... 1E=I[05- 2,619E-0

7. Ia-65 ...... .CL ........ .......... • •

Sb-11 1 . _ __ _._ _ , .Sb.134 CL _______ _______ * C3L1 -.-- - SL .... * 21*O1-133 C

CLl 5_e _______ __..____ AL Ik...... •J ECs-1 34 _C _ 3,219£-06i 4.,9r--0

Ce-1O7 _Ci. .. _....._ ___ .__.I_____*

Ln-140 .... C _ _ . .... • •

2M-14139*

(above)-a64IL.eL ..... • •

Xe-lS CI '*

* The activity of this nuclide is less then the LLDappropriate table.

listed on the

ZEDE91/37

30 of 36

DREZSDEN NUCLEAR MM~E STATIONUNITS I A"D 3

EFFLUENT ANED WASTE DISMOAL SEHLAIOEAL B.ERT

CCSV LIQUID FlLWU MT Docket Plumers: 50-23750-25.9

NUCLIDES RELEASED MNIT JAMUARY FERUARY MARCH 1st QUARTER TOTAL

Ar-Id* 1

Rb-124 C1 _______

1b-12t. -CL aa

CS*

TJAFXftliad -CL- 3.= 6.4CsU ............ ..CL _ __ _ __ __ _a

Th atiit o thi nuclid in les tan the LLD listedonthe

_ _ _orit tale

ZEDE91137

31 of 36

DKUSDD NUCLERI 1OM STATIONUNITS 2 AND 3

TLUDT AND WASTE DISPOSAL SVIIMQA REPORT

A ThrouSh Jung 1990

MyV ,, LIQUID EVFLUDETS Docket Numbers: 50-237S0-249

NUCLIDZS RRILASED UNIT APRIL MAY JUNE Ind QUARTER TOTAL

sr-89 * • ......... •St-90 , eL * * , *. ....A z - C7 * * I *no•-34 - l *7.91E,-o7 ti.ASE=-Qfi 2jffz-06

Co.58 ___* * * ,,, *,,.r.-s 9 CI** ... a

Co660 e-_l 2._251-06 4.09_-06 _.021-5 2.6Rf-O,.7-65 (!I * * *-Sb-122 4L * * l *Sq-124 . * . .*

1-133 C . *1-13S 1 * *. aCS-) 3A CI-- 1.97-07 1.30Q-06 I tO*06_C-137 (!1 1.39E=-. 6 LAME-0A I a,919-05

Ba-s C1

_.Rik... £ . a. a a

._C1-139 - !*** ...

C1

Cai CL .....~ C .. . ...........

(above)TotAl e einod.. CL I,84£-06 L,0E-05 .. Z84-0 .

Xe-d]l AU. a a a 0__ _ _ _ __ _ _- aia

SThe activity of thappropriate table.

is nuclide is less than the LLD listed on the

ZEDE91/37

32 of 36

I

RUDEN NUCLEAR MM STATIONUNITS I, 2, AND 3

EFFLUET AND WASTE DISPOSAL SDtNIXUAL RItORT

I ;

bThrough ._Jim ._ 1920

SOLID WASTE AND IRRADIATED FUEL SHIPMIETS

Docket Numbers: 50-1050-23750-249

EeL Tot.if---- 9A ai~O WW~ tJAW ~Utflb31~ 6~ifWCIW W~S aimIh~ ftS I~W~SAe8W ~hi~ *bbAh9hYWl~ W9~W9 'ap. ant.., aa ta pp. rr r.~ %IF spa At. - 2a stag ant sq a, apr La tft L. ~ Pt, A A tL *n a rn r uJr.J

1. Type of Waste Unit 6-month period

m3 1.35Ee02A. Spent resins, filter sludies, evaporator bottoms, etc. -

Ci 2.•31E.0 12.4

013 1.029*03b. Dry compressible waste. contaminated equip.* etc. L

Ci. 2.51E+O1 16.6

03 0c. Irradiated components, control rods, etc. -

ci 0 16.6

m

d. Other (describe).3

Ci

0

0'-I

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

I 'r.1f 1.0l&EO2A CO-60

M_-_4 ______J6-•. _3.aLEs1LCs-137 _1,l.3 2.61E+01ni-63 ..41 . .1.2.5E*1

_____-___._ ___ L... _5, £+00Otber L.-5J...,.3.1LQb • C0=60 ,,23.4 6i.38E+00IFP-51 62.0 1,56E+01

.n-S9 ..D.O Ot..o

ca13 L AJLOO1tO .Other. 0gEJUgQ..€. CoCO9 0 _O.1tok

S Fe-55 0 0 9-QJ

_CS -137- o • _.,Qg£±.2_

J A

3. Solid Waste Disposition

I i;NJ41 T44-14 f 61 6IP] HODLOLIM?'5MQPA1IIQM VI9,,NAT1Q10

49963

MotorMotorMotorMotor

freight (exclusive usefreight (exclusive usefreight (exclusive usefreight (exclusive use

only)only)only)only)

Barnwell, SCSEG. Oak Ridge, TICNSI, Channahon, ILWestinghouse DDR.

Madison, PAQuedrex, Oak Ridge, TNI Motor freight (exclusive use only)

S. IRRADIATED FUEL SHIPMIENTS (Disposition)

KNUI5.OLN IM huNMT 11OLQOF_•W 5•0RTATION DVE IMKTION

None

ZEDE91/37

33 of 36

I

.4

VKSESJ HUCLMA romf SATIOPUNITS 1, 2, AI(D 3

EZFLWIT AM WASM DISPOSAL SDsLjA6L MI-MT

-anul=IL- Througb jie .1920

Docket Ximbers: 50-1050-23750-249

AMIOL4AL REIJ.AS&S

A. LIQUID

1. Number of Relexues: a

2. Total Activity Released: O

S. GASEOUS

1. Nmber of Releases:

One on 5 January 90, LER 90-001-050237 (Unit 2)One on 16 January 90, LEA 90-002-050237 (Unit 2)One on 10 tlarcb 90, LER 90-005-050249 (Unit 3)

Use of the Isolation Condenser to cool the reactor subsequent to a reactorscram resulted in a release of stes= in all three events. The stemcontained trace amounts of radioactivity from previous uses ofcontaninated demineralized water as markeup water. In all of the abovecases, clean demineralised water was used as makeup water.

2. Total Activity Released: Muclide -Ac iyi__(sCLLMM-541 1.48E-05Fe-55 1.32E-04Co-60 9.34E-05NA-2. 2.71E-06

Total 2.43E04

ZEDE91/37

34 of 36

0

DSSU WLZAR POWU STATION DO~nT NOS8. 30-10, 50-237?, S0-249

RADOLGICL MlACT 0ON MAN

ZEDE91/37

35 of 36

I

DRESDEN UNIT ONE

1990 ANNUAL REPORTMAXIMUM, DOSES RESULTING PROM AIRSORNE RELEASES

PERIOD OF R3LIASE - 01/01/90 TO 12/31/90 CALCULATED 02/26/91INFANT RECEPTOR

I

ISTTYPE QUARTER

JAN-MAR

GAMMA AIR 0.003+00

BETA AIR 0.003+00(IlIAD)

TOT. BODY 0.00t+00(JMtEM) ( )SKIN 0.001+00(MIEN) ( )ORGJAN 2.21E-05

(WREN) (St)

LIVER

THIS IS A REPORT FOR THE

2ND 3RDQUARTER QUARTERAPR-JUN JUL-SEP

0.003+00 0.009+00( ) ( )0.00+00 0.00+00C ) ( )0.001+00 0.00+00C ) ( )0.001+00 0.001+00( ) ( )1.73E-05 1.903-0S(SE) (St)

LIVER LIVER

CALENDAR YEAR 1990

4THQUARTEROCT-DEC

0.002+00

0.003+00C )0,00÷+00C )0.003+00C )3.003-0S(SE

LIVER

ANNUAL

0.003+00( )0.003+00C )0.00+00C )

C )8.84t-05(SiEt

LIVER

GAMJMA AIR (CRAD)BETA AIR (MRAD)TOT. BODY (RIEN)SKIN (MRIM)ORGAN. (REN)

C

1

COMPLIANCE STATUS - 10 CrR So APP. IINFANT RECEPTOR

--------% OF APP .-------•TRLY IST OTR 2ND QTR 30D QTR 4'OB3 JAN-MAR APR-JUN JUL-SEP 0O

5.0 0.00 0.00 0.00L0.0 0.00 0.00 0.002.5 0.00 0.00 0.007.S 0.00 0.00 0.007.5 0.00 0.00 0.00

LIVER LIVER LIVER L

i"1 QTRCT-NOV

0.000.000.000.000.00

IVER

YRLYOBJ

10.020.0

5.015.015.0

% OrAPP.I

0.000.000.000.000.00

LIVER

RESULTS BASED UPONODCMA"NHEXREVISION 0MARCH 1989

n

a I

DRESDEN UNIT ONE

1990 ANNUAL REPORTMAXIMMU DOSES RESULTING FROM AIRBORNE RELEASES

PERIOD or RELEASE - 01/01/90 TO 12/31/90 CALCULATED 02/26/91ADULT RECEPTOR

1STTypE QUARTER

JAN-MlAR

GAMMA AIR 0.OOE*00(MAD) ( I

BETA AIR 0.00E.00(n.MD) I )TOT. BODY 0.OoE÷00(macm) ( )

SKIN 0.00+E00(nREN) ( I

ORGAY 2.00O-OSMe"•) (Sr.

LIVER



0.00e00 0.0O0+00( ) ( )0.00+00 0.00t+00C ) ( I

0.009+00 0.OOE.00C ) C )

2.66K-OS 4.27Z-0S(StE (SE)

BONE LIVER

CALENDAR YEAR 1990

4TBQUARTEROCT-DEC

0.009+00

0.OOE.00( I

0.009+00C )

0.00+E00( I0.O0E.00( I4.71K-OS

(SE )

BONE

ANNUAL

0.009+00

0.0OE+00

0. OoE.00

1.20E-04(SEt

LIVER

GAMMA AIR (PRAD)BETA AIR (READ)TOT. BODY (MERE)SKIN CREE)ORGAM MERN)

C

COMPLIANCE STATUS - 10 CrR s0 APP. IADULT RECEPTOR

----------% OF APP I.-------•TRLY 1ST OTR 2ND QTR 3RD QTR 4'OBJ JAN-MAR APR-JUN JUL-SEP 0O

5.0 0.00 0.00 0.00.0.0 0.00 0.00 0.002.S 0.00 0.00 0.007.5 0.00 0.00 0.007.5 0.00 0.00 0.00

LIVER BONE LIVER a'

TH QTRCT-NOV

0.000.000.000.000.00

ONE

YRLYOBJ

10.020.05.015.015.0

% OFAPP.I

0.000.000.000.000.00

LIVER

RESULTS BASED UPONODCM ANNEXREVISION 0RARCH 1989

DRESDEN UNIT TWO

1990 ANNUA REPORTMAXIMUM DOSES RESULTING FROM AIRBORNE RELIASES

PERIOD OF RELEASE - 01/01/90 TO 12/31/90 CALCULATED 02/26/91INFANT RECEPTOR

1STTYPE QUARTER

JAN-MAR

GAMMA AIR 5.913-06(mmDA) (NE )

llTA AIR 9.49E-07(READ) (N )

TOT. BODY 2.58E-06CHREM) (Ne )

SKIN 5.249-06(CREM) (NE )

ORGAŽ4 6.251-02(KrtER) (NNE)

LUNG


2ND 3RDQUARTER QUARTERAPR-JUN JUL-SaP

3.17-OS 9.65-06(NE ) (He )4.S23-06 2.03Z-06(N ) (N1.SS-05 4.063-06(HE ) (NZ )2.773-05 8.87Z-06(NE ) (NE )3.643-03 9.773-03(NNE) (NNE)

THYROID THYROID

CALENDAR YEAR 1990

4THQUARTEROCT-DEC

0.00E00( )0.00+00( )0.00z+00( )0.00E.00( )3.313-03(NNE

LUNG

ANNUAL

4.72E-OS(NE 37.503-06(N )2.213-05(NE )4.186-os(HE )7.913-02(NNE

LUNG

CONPLIANCE STATUS - 10 CFR S0 APP. IINFANT RECEPTOR

-t Or APP I.QTRLY 1ST OTR 2ND QTR 3RD QTR 4TH QTROBJ JAN-MAR APR-JUN JUL-SEP OCT-NOV

5.0 0.00 0.00 0.00 0.0010.0 0.00 0.00 0.00 0.002.5 0.00 0.00 0.00 0.007.5 0.00 0.00 0.00 0.007.S 0.83 0.05 0.13 0.04

LUNG THYROID THYROID LUNG

GAMMA AIR (MRAD)BETA AIR (NRAD)TOT. BODY (NRKM)SKIN (MENl)ORGA.I (MRUM)

YRLY03

10.020.0

5.015.o15.0

% orAPP.I

0.000.000.000.000.53

LUNG

RESULTS BASED UPONODCH ANNEXREVISION 0MARCH 1989

DRESDEN UNIT TWO

1990 ANNUAL REPORTMAXIMUM DOSES RESULTING FROM AIRBORNE RtLEASES

PERIOD OF RELEASE - 01/01/90 TO 12/31/90 CALCULATED 02/26/91ADULT RECEPTOR

TYPE

CRAM

BETA A(REAlTOT. I

(MariSKIN

(MiORGAj

(Mnnri

15TQUARTERJAN-MAR

AIR 5.919-06)) (NE )LIR 9.499-07

sODY 2.S82-06I) (NE5.243-06

I) (HE )6.35Z-02

I) (mNNE)

LUNG



3.173-05 9.65t-06(NE ) (IE )4.52Z-06 2.032-06(N ) (N )1.55-05 4.063-06(NE ) (Ne )2.773-05 8.87Z-06(NE ) (IE )4.30E-03 1.14Z-02(NNE ) (CNE )

THYROID GI-LLI

CALENDAR YEAR 1990

4THQUARTEROCT-DEC

0.003.00( )0. 003.00C )0.003+00C )0.009+00

( P)3.37E-03(NNE

LUNG

ANNUAL

4.723-05(NC )7.S03-06(N P2.213-05(NE )4.183-OS(NE )8.169-02( NNE

LUNG

GAMMA AIR (HRAD)BETA AIR (MRADPTOT. BODY (MREN)SKIN (MREM)ORGAIN (UREM)

Q

I

COMPLIANCE STATUS - 10 CPR so APP. IADULT RECEPTOR

--% OF APP I.-------TRLY 1ST QTR 2ND QTR 3RD QTR 4OBJ JAN-MAR APR-JUN JUL-SIP 0

5.0 0.00 0.00 0.000.0 0.00 0.00 0.002.S 0.00 0.00 0.007.5 0.00 0.00 0.007.5 0.85 0.06 0.15

,LUNG THYROID GI-LLI L

TH QTRCT-NOV

0.000.000.000.000.04

UNG

YPLYOBJ

10.020.05.0

15.015.0

% ofAPP.I

0.000.000.000.000.54

LUNG

RESULTS BASED UPONODCM ANNEXREVISION 0MARCH 1989

I

DRESDEN UNIT THREE

1990 ANNUAL REPORTRAXI•UM DOSESM RESULTING FROM ARBORNt RELEASES

PERIOD OF RELEASE - 01/01/90 TO 12/31/90 CALCULATED 02/26/91INFANT RECEPTOR

1STTYPE QUARTER

JAN-MhR

GARMA AIR 4.73--0S(MAD) (E )

BETA AIR 7. 59--06(RIND) (N )

TOT. BODY 2.07t-05MEN) (NE )

SKIN 4.19E-0S(OWRN) (NE )

ORGAN4 8.34E-03(HREN) (NNE

LUNG


2ND 3RDQUARTER QUARTERAPR-JUN JUL-SE?

1.83E-04 8.62E-05(NE ) (NE )2.32E-05 1.82Z-0S(N ( N )9.219-05 3.62E-0S(E ) WNE )1.58E-04 7.92E-05(NE ) (NE)1.92E-02 4.93E-02(NNE ) (INE)

THYROID LUNG

CALENDAR YEAR 1990

4THQUARTEROCT-DEC

S.SOE-05(NE )1.60E-04(lNE )2.29Z-0S(NE)1.63E-04(NNE )5.S4E-03(NINE )

THYROID

ANNUAL

3.71E-04(mE )2.07E-04(NNE )1.723-04(ME )4.41E-04(E )8.22E-02(lNE )

THYROID

GAPMM AIR (MRAD)BETA AIR (MRAD)TOT. BODY (MRZ, )SKIN (MREM)ORGA-l (HRErt)

Q

I

COMPLIANCE STATUS - 10 crR 50 APP. IINFANT RECEPTOR

------------ % OF APP I-------}TRLY 1ST QTR 2ND QTR 3RD 0TR 4083 JAN-IAR APR-JUN JUL-SEP 0

5.0 0.00 0.00 0.000.0 0.00 0.00 0.002.5 0.00 0.00 0.007.5 0.00 0.00 0.007.5 0.11 0.26 0.66

LUNG THYROID LUNG T

TO QTRCT-NOV

0.000.000.000.000.08

HYROID

YRLYOB3

10.020.0

S.015.015.0

% orAPP.I

0.000.000.000.000.55

THYROID

RESULTS BASED UPONODCR ANNEXREVISION 0MARCH 1989

I

I

DRISOEN UNIT TIUREIE

1990 ANNUAL REPORTNAXIMUM DOSES RESULTING FROM AIRBORNE RELEASES

PERIOD Or RELEASE - 01/01/90 TO 12/31/90 CALCULATED 02/26/91ADULT RECEPTOR

TIPE

GAMMA(FRLR6

BET JMAIM

TOT. I(MW0

BRIM(MW~

ORGA.'4(MWO

ISTQUARTERJAN-MAR

AIR 4.73E-05(NE )

kiR 7.59Z-06(N )IoDy 2.073z-o5

I) (NE)4.193-0S

I) (NE

8.41E-03I) (~(NE

LUNG


2ND, 32DQUARTER QUARTERAPR-JUN JUL;-SKIP

1.03e-04 8.623-05

(N ) (N )

9.212-OS 3.623-0S(Ne ) (Ne )1.583-04 7.923-05(NE ) (NE )2.18E-02 5.793-02(NNE ) (NNE )

THYROID GI-LLI

CALENDAR YEAR 1990

4T8QUARTEROCT-DEC

5.S01-os(HE )1.603-04(NME )2.292-05(NE)1.63Z-04(NNE )6.6S5-03(NNE

LUNG

ANNUAL

3.713-04(Ist )2.078-04("We )1.728-04(HE /)4.411-04(NE )9.253-02(NNE)

GI-LLI

GANMM AIR (MRAD)BElA AIR (MAD)TOT. BODY (MiEN)SKIN (MiEN)ORGANq (NREl)

C

1

COMPLIANCE STATUS - 10 CFR 50 APP. IADULT RECEPTOR

SOF APP I.-------ITRLY 1ST QTR 2ND QTR 3RD QTR 4OBJ JAN-MAR APR-JUN JUL-SEP 0

5.0 0.00 0.00 0.000.0 0.00 0.00 0.002.5 0.00 0.00 0.007.5 0.00 0.00 0.007.5 0.11 0.29 0.77

LUNG THYROID GI-LLI L

TH OTRCT-NOV

0.000.000.000.000.09

UNG

YRLYOnJ

10.020.05.0

15.015.0

% orAPP.I

0.000.000.000.000.62

GI-LLI


DOSE -T

TOTALBODYINTERN~ORGIV4

DREIDEN UNIT TWOMNFANTRECEPTOR

1990 ANNUAL REPORTMAXIMUM DOS (NREN) RESULTING FROM LIQUID EFFLUENTS

PERIOD OF RELEASE - 01/01/90 TO 12/31/90 CALCULATED 02/26/91

IST 2ND 3RD 4THtYPE QUARTER QUARTER QUARTER QUARTER ANNUAL

JAM-"A" APR-JUN JUL-SEP OCT-DEC

5.339-0S 1.05-04 2.249-04 1.16E-04 4.98E-0,

AL 1.871-04 1.02Z-03 2.193-03 9.021-04 4.31Z-0

LIVER LIVER LIVER LIVER LIVER

THIS IS A REPORT FOR THE CALENDAR YEAR 1990COiPLIANCE STATUS - 10 CFR s0 APP. I

----------- -------------- OfP APP I.OTRLY 1ST QTR 2ND QTR 3RD QTR 4TH QTR YRLY

OB3 JAN-MAR APR-JUN JUL-SEP OCT-NOV OBJ A

BODY (NRZRI 1.S 0.00 0.01 0.01 0.01 3.0

ORGAN(HREM) 5.0 0.00 0.02 0.04 0.02 10.0

LIVER LIVER LIVER LIVER LIV

4

3

TOTAL

CRIT.

orPP. 1

0.02

0.04

ER


. 0

0083

TOTALBODYUtonIORG&I

DUBDIEN UNIT TWOINFANT XICIPTOR

1990 ANNWUL REPORTPROJECTRD DOSE AT NEAREST COMMUNITY WATZR SYSTIR *

PERIOD Or RELEASE - 01/01/90 TO 12/31/90 CALCULATED 02/26/91

15T 2ND 33. 4THtYPE" QUARTER QUARTER QUARTER QUARTER AJ

JAN-MAR APR-JUN JUL-SEP OCT-DEC

5.331-05 1.059-04 2.243-04 1.163-04 4.

1AL 1.873-04 1.021-03 2.19Z-03 9.022-04 4.

LIVER LIVER LIVER LIVER LI

THIS 1S A REPORT FOR THE CALENDAR YEAR 1990

NNUAL

983-04

313-03

VER

COMPLIANCE STATUS - 40 CrR 141

TYPE ANNUAL LIMIT t OF LIMIT

TOTAL 4.0 (MREN) 0.012BODYINTERNAL 4.0 (MiEN) 0.100ORGAN

LIVER

* T31 CALCULATION OF DOSE IS BASED ON TECHNIQUES DESCRIBED IN THECOMMONWEALTH EDISON OFFSITE DOSE CALCULATION MANUXL. THESE TECHNIQUES DIFFERFROM THOSE DESCRIBED IN 40 CFR 141.

RESULTS BASED UPONODCN ANNEXREVISION 0MARCH 1989

4.

I

DRESDEN UNIT TWOADULT RECEPTOR

1990 ANNUAL REPORTRAXIMRU DOSZS (KREM) RESULTING FROm LIQUID ErrLuENTS


15T 2ND 3RD 4THDOSE TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL

JAN-tAR APR-JUN JUL-SEP OCT-DEC

TOTAL 3.063-04 1.84E-03 4.01Z-03 1.61Z-03 7.76Z-03BODYINTERNAL 4.543-04 2.783-03 6.063-03 2.44Z-03 1.173-02ORGA-


THIS IS A REPORT FOR THE CALENDAR YEAR 1990

COMPLIANCE STATUS - 10 CrR S0 APP. I

- -- - or APP I.

QTRLY 1ST QTR 2ND OTR 3RD OTR 4TH 0TROBJ JAN-KAR APR-JUN JUL-SEP OCT-NOV

1.5 0.02 0.12 0.27 0.11

5.0 0.01 0.06 0.12 0.05

LIVER LIVER LIVER LIVER

YRLY083

3.0

10.0

TOTAr. BODY (KRE,)

CRIT. ORGAN(NREMI)

I OFAPP. I

0.26

0.12

LIVER

RESULTS BASED UPONODCMH ANEXREVISION 0MARCH 1989

I

S.

DOSS

TOTALBODYINTERI.ORCA-14

DRESDEN UNIT TWOADULT RECEPTOR

1990 ANNUAL REPORTPROJECTED DOSS AT NEAREST COMMUNITY WATER SYSTEM *

PERIOD O1' RELEASE - 01/01/90 TO 12/31/90 CALCULATED 02/26/91

IST 2ND 3RD 4TH.YPs QUARTER QUARTER QUARTER. QUARTER A

JAN-NAN APR-JUN JUL-SEP OCT-DEC

3.16E-05 1.293-04 2.803-04 1.16E-04 S.

AL 3.883-05 1.861-04 3.932-04 1.623-04 7.

BONE LIVER LIVER LIVER LI

THIS 1 A REPORT FOR THE CALENDAR YEAR 1990

NNUAL

563-04

77E-04

VER

COMPLIANCE STATUS - 40 CFR 141

TYPE ANNUAL LIMIT % OF LIMIT

WOTAL 4.0 (HREM) 0.0143ODYINTERNAL 4.0 (MREN) 0.019IRGAN

LIVER

* T31S CALCULATION OF DOSE IS BASED ON TECHNIQUES DESCRIBED IN THECORM3NWEALTH EDISON OFFSITE DOSE CALCULATION MANUAL. THESE TECHNIQUES DIFFERFROK THOSE DESCRIBED IN 40 CFR 141.


DOSE I

TOTALBODYINTERNORGA.'4

DRESDEN UNIT ThREEINFANT RECEPTOR

1990 ANNUAL REPORTmAXImUm DOSES (RREm) RESULTING FROM LIQUID EFFLUENTS

PERIOD.Or RELEASE - 01/01/90 TO 12/31/90 CALCULATED 02/26/91

1ST 2ND 3RD 4THtYP QUARTER QUARTER QUARTER QUARTER ANNUAL


9.45-0$ 1.059-04 2.13E-04 7.773-OS 4.90Z-0

[AL 3.51E-04 1.023-03 2.12E-03 6.02E-04 4.09Z-0


THIS IS A REPORT FOR THE CALENDAR YEAR 1990COMPLIANCE STATUS - 10 CFR so APP. I

----.------- %O AlPP I - -------QTRLY 1ST QTR 2ND QTR 3RD QTR 4TH QTR YRLY t

OBJ JAN-MAR APR-JUN JUL-SEP OCT-NOV O0J Al

BODY (CREK) 1.S 0.01 0.01 0.01 0.01 3.0

ORGAN(MREM) 5.0 0.01 0.02 0.04 0.01 10.0

LIVER LIVER LIVER LIVER LIVI

4

3

TOTAL

CRIT.

orPP. I

D.02

0.04

ER


DOSE '

TOTALBODYIN?! R3OacA&.

DK*SD0E UNIT TKRE!INFANT RECEPTOR

1990 ANNUAL REPORTPROJECTED DOSE AT NEAREST CORMUNITY WATER SYSTEM *


1ST 2ND 3RD 4THIYPE QUARTER QUARTER QUARTER QUARTER Al


9.45E-0S 1.0SE-04 2.13E-04 7.77E-OS 4.!

IAL 3.51E-04 1.02E-03 2.12E-03 6.02E-04 4.1

LIVER LIVER LIVER LIVER LI•


WNUAL

9OE-04

09Z-03

IrER



TOTAL 4.0 (MREM) 0.01230DYINTERNAL 4.0 (IREI) 0.102JRGAN

LIVER

* T3IS CALCULATION OF DOSE IS BASED ON TECHNIQUES DESCRIBED IN THECOXmtNWEALTH EDISON O01sIT DOSE CALCULATION MANUAL. THESE TECHNIQUES DIFFERFROM THOSE DESCRIBED IN 40 CFR 141.


DOSE T

TOTA L,BODYINTE.*'ORGA:4

DRESDEN UNIT THREEADULT RECEPTOR

.1990 ANNUAL REPORTMAXIMUM DOSES (JMER) RESULTING rROM LIQUID EFFLUENTS

PERIOD or RELEASE - 01/01/90 TO 12/31/90 CALCULATED 02/26/91

1ST 2ND 3RD 4THWYPE QUARTER QUARTER QUARTER QUARTER

JAN-KAR APR-JUN JUL-SEP OCT-DEC

5.831-04 1.84E-03 3.861-03 1.07E-03 7.

iL 8.66E-04 2.78E-03 5.841-03 1.631-03 1.1

LIVER LIVER LIVER LIVER LI


4NUAL

36E-03

llc-02

VER

COMPLIANCE STATUS - 10 CFR SO APP. I

2-- - -Or APP I.- ------------QTRLY IST QTR 2ND QTR 3RD OTR 4TH QTR

OB3 JAN-MAR APR-JUN JUL-SEP OCT-NOV

1.5 0.04 0.12 0.26 0.07

S.0 0.02 0.06 0.12 0.03

LIVER LIVER LIVER LIVER

YRLYOBj

3.0

10.0

TOTAL BODY (MREM)

CRIT. ORGAN(MREM)

% orAPP.1

0.25

0.11

LIVER


I

DOSE I

TOTALBODYINTERNORGA.A

DRESDEN UNIT THREEADULT RECEPTOR

1990 ANMUAL REPORTPROJECTED DOSE AT NEAREST COMMUNITY WATER SYSTEM


IST 2ND 3RD 4THYPE QUARTER QUARTER QUARTER QUARTER A


s.801-OS 1.29E-04 2.69E-04 7.749-0S S.

[AL 7.461-05 1.86E-04 3.78E-04 1.08E-04 7.

BONE LIVER LIVER LIVER LX


NNUAL

339-04

401-04

VER



T'OTAL 4.0 (HREM) 0.0133ODYINTERNAL 4.0 (MREM) 0.018ORGAN

LIVER

T3IS CALCULATION OF DOSE IS BASED ON TECHNIQUES DESCRIBED IN THECOMMO3NWEALTH EDISON OFFSITE DOSE CALCULATION MANUAL. THESE TECHNIQUES DIFFERFROM THOSE DESCRIBED IN 40 CFR 141.


DRJSDDE WJCLE. ?WOER STATION DOCUT NOS. 50-10, 50-237o 50-249

METZORLOGICAL DATA

(Includes hourly data for Abnormal Release dates on January 5. January 16. radMarch 10, 1990.)

ZUE991/37

36 of 36

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f

CIII 111M ri M, 49I•Jsp- ft. 113 * 1 ;ll t"313 It e,. 1:0 10 / r12 it" aI s•-U : It. Ma

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s!hI:~:h c~ans~ ~ a is is as ?:?&~

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Canwrsa Edkm OsOmn• Mocsa Power tae Ovm.n aft VI rifisI4am2 … · 2014. 5. 1. · *0 9,. Canwrsa...

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Transcript of Canwrsa Edkm OsOmn• Mocsa Power tae Ovm.n aft VI rifisI4am2 … · 2014. 5. 1. · *0 9,. Canwrsa...