Text

Semiannual Radioactive Effluent Rept for Jul-Dec 1989
	ML20011F342
Person / Time
Site:	Dresden
Issue date:	12/31/1989
From:	Eenigenburg E; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	90-158, NUDOCS 9003050173
	Download: ML20011F342 (54)
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',z f's7 jCom'monwealth Edison

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. 1 -1 1 Dresden Nuclear P;mr St tion'

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'.N i Morris, lilinois 60450

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February 28, 1990' L

'EDE LTR #90-158-i

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U.S. Nuclear Regulatory Conunission Document Control Desk Washington,.DC 20555 7-

Subject:

Dresden Nuclear. Power Station 0perating Report NRC' Dockets ~ 50-10. 50-237. 50-249 Enclosed is the. rad'ioactive effluent' report for July through December 1989 for'Dresden Nuclear Power Station.

l:

--A copy of this report will be furnished to the NRC Senior Resident 4

Inspector.

l Sincerely Yours, y

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E..D. Eenigenburg Station Manager Dresden Nuclear Power Station b

EDE:SK:ade Enclosure cc: S. Kova11-J.C. Golden.

File /NRC File / Numerical Attached Distribution List (6 '

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--9003050173 891231

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Semi Annual Report Distribution All Stations'

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Director of Nuclear Reactor Regulation U.S.~ Nuclear Regulatory Commission Mail Station F1-137 Washington D.C.-20555'

-(Original) j

- or -

One White Flint North

11555 Rockville Pike

-Rockville, MD 20852-j Illinois Department of Nuclear Safety u

Office of Nuclear Facility Safety F

1035 Outer Park Drive L

Springfield, IL 62704 ANI The Exchange, Suite 245 270'Farmington Ave Farmington, CT 06032 B.P.I 109 North ~ Dearborn St.

Suite 1001 Chicago, IL 60602 American Electric Power Service Corp.

-Nuclear Operations Division 1 Riverside Plaza Columbus,10hio 43216 (2 copies)

U.S.'Environmenta1' Protection Agency

. 230 S. Dearborn St.

Chicago, IL 60606 Illinois Environmental Protection Agency Region III - DWPC/F05 5415 North University Peoria, IL 61614 U

Illinois Environmental Protection Agency Division of Water Pollution Control Field Operation Manager 2200 Churchill Rd Springfield, IL 62706 If delivered by private carrier (1.g. Federal Express) direct carrier to the lower back area of the One White Flint North Bldg, Mail Station P1-137 ZEDE/108 2 of 32 e:

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s Semi Annual Report Distribution pi:

-All Stations (Cont'd) ils

-Illinois Power Company Clinton Power Station-Plant Radiation Protection L'

R.R. #3 Box 228

-Clinton, IL. 61727 i

-Murray &.Trettel. Inc-

- Environmental Meteorologist 414 West Frontage Rd

- Northfield, IL 60093

- Teledyne' Isotopes Midwest Laboratory i

General Manager

.700 Landwehr Rd-

- Northbrook, IL 60062 Radiochemistry Services Group Chemistry Services Director Room 1237E-Emergency Preparedness-Supervisor ~ of Emergency Preparedness Room 1237E i

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. Semi ~ Annual Report Distribution l

Dresden Station Manager l

Dresden l

l Health Physics Services ~ Supervisor Dresden 3y NRC Senior Resident Inspector Dresden General Electric Co.

Services Project. Manager.

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Mail Code 881 175 Curtner Ave i.

-San Jose, CA'. 95125 General Electric Co R.R. #1' t

Morris IL 60450

(2 copies)

.A. Bert Davis Regional' Administrator Region-III U.S. Nuclear Regulatory Commission 799 Roosevelt'Rd.

Glen Ellyn,-IL:60137 l

.Berline Ferguson L

Emergency Preparedness 1237E r

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?c DRESDEN NUCLEAR POWER STATION DOCKET NOS. 50-10, 50-237, 50-249 I

l REGULATORY LIMITS.

Gaseous Effluents - Dose This Specification is provided to ensure that the dose at the unrestricted area boundary from gaseous effluents from the units on-site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. The annual dose limits are the doses associat'd e

with the concentrations of 10 CFR Part 20, Appendix B,. Table II.

t These' limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an-individual in an unrestricted area to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)).

In the one case ~where effluent monitoring equipment is not used, i.e., the burning of contaminated i-L oil in thel heating boilers, administrative controls are imposed to limit concentration in the heating boiler stack to less than 10 CFR l

Part 20-Appendix B, Table II, Column 1 and the contribution to L

overall dose to less than 0.1 percent of the total station annual release. The specified release rate limits restrict, at all. times, the corresponding gamma and beta dose rates above background to an

. individual at or beyond the unrestricted area boundary to less than or equal to 500 mrem / year to the total body or to not less than or 4

equal to 3000 mrem / year to the skin. These release rate limits also-restrict, at all times, the corresponding thyroid dose rate above background to an inf ant via the cow-milk-inf ant pathway to not less than or equal to 1500 mrem / year for the nearest cow to the plant.

For purposes of calculating doses resulting from airborne releases, the main chimney is considered to be an elevated release point and the reactor building vent stack is considered to be a mixed mode release point.

Dose, Noble Cases

.i This Specification is provided to implement the requirements of Sections.II.B. III.A and IV.A of Appendix I, 10 CFR Part 50.

The Limiting Conditions For Operation implement the guides set forth in l

Section II.3 of Appendix I.

The statements provide the required l

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 i

[

radioactive material in gaseous effluents will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially l-underestimated. The dose calculations established in the ODCM for l

calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents will be consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of L

ZEDE/108 5 of 32

f l-DRESDEN NUCLEAR-POWER STATION DOCKET NOS. 50-10, 50-237, 50-249 y

i

' Annual Doses to Man from Routine Releases of-Reactor Effluents for i

the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111 " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents 1

in Routine Releases from Light-Water Cooled Reactors," Revision 1,.

July 1977. The ODCM equations' provide for determining the air doses at the unrestricted boundary based upon the historical average atmospheric conditions. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111.

Dose,.Radioiodines, Radioactive Material in Particulate Form and Radionuclides Other than Noble Gases This specification is provided to implement the requirements of Sections II.C. III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Conditions for Operation are the guides set forth in Section II.C of Appendix I.

The statements provide the required operating j

flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as reasonably achievable." The ODCM calculational methods specified in the surveillance requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown l

by calculational procedures based on models and data such that the l-actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational.

methods approved by NRC for calculating the doses due to the actual I

release rates of the subject waterials are required to be consistent f

ll with the methodology provided in Regulatory Guide 1.109, " Calculation l

of Annual Doses to Man from Routine Releases of Reactor Effluents for L

the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix j,

I", Revision 1, October 1977 and Regulatory Guide 1.111. " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for radiolodines, radioactive material in l

particulate form and radionuclides other than noble gases are E

dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which were examined in e

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DRESDEN NUCLEAR POWER STATION DOCKET NOS. 50-10, 50-237 50-249

'the development of these specifications weret

1) individua15 inhalation of airborne radionuclides, 2)-deposition of radionuclides onto green leafy vegetation with subsequent consumption by man and 3):

deposition onto grassy areas where milk animals graze with consumption of the milk by man.

Gaseous Waste Treatment The OPERABILITY of the gaseous waste treatment which reduces amounts

'i

, or concentrations of radioactive materials ensures that the' system :

will be available,for use whenever-gaseous effluents require treatment prior to release to the environment.

The requirement that the appropriate portions of this system be operable when specified provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as reasonably achievable". This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion.60 of Appendix A to 10 CFR 1

L Part 50, and design objective Section II.D of Appendix I to.1'O CFR Part 50.

Explosive Gas Mixture J

t This specification is provided to ensure that the concentration of potentially explosf.ve 8as mixtures contained in the off gas system is j

minimized in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.

LIQUID EFFLUENIS Concentration j

This specification is provided to ensure the concentration of radioactive materials released in liquid waste effluents from the site to unrestricted areas will be less than the concentration levels i

L specified in 10 CFR Part 20. Appendix B, Table II, Column 2.

The l-concentration limit for noble gases, MPC in air (submersion), was converted to an equivalent concentration in water using the International Commission on Radiological Protection (ICRP)

Publication 2.

l l

Dose This specification is provided to implement the requirements of Sections II.A III.A and IV.A of Appendix I, 10 CFR Part 50.

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-DRESDEN NUCLEAR' POWER-STATION DOCKET NOS. 50-10, 50-237, 50-249 The' Limiting Condition for Operation implements the guides set forth in Section II.A of' Appendix I.

The statements provide the required 4

operating flexibility,and at the same' time implement the guides set forth.in Section IV.A of Appendix I to assure that~the releases of radioactive material in liquid effluents will be kept "as low as reasonably achievable".

The dose calculations in the ODCM implement the requirements in Section III.A of Appendix I that'conformance with the guides of Appendix'I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be'substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents will be consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", Revision 1. October'1977 and Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I", April 1977. NUREG-0113 provides methods for dose calculations with Reg Guide 1.109 and 1.113.

Liquid Waste Treatment The operability of-the liquid radwaste treatment system ensures that this system will be available for use-whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as reasonably achievable". This specification implements the requirements of 10 CFR Part 50 and design objective Section II.D of Appendix I to 10 CFR Part 50.

Mechanical Vacyum-Pump The purpose of isolating the mechanical vacuum line is-to limit release of activity from the main condenser. During an-accident, fission products would be transported from the reactor through the main steam line to the main condenser. The fission product radioactivity would be sensed by the main steamline radioactivity monitors which initiate isolation.

ZEDE/108 8 of 32 I

e-1 DRESDEN NUCLEAR POWER STATION DOCKET NOS. 50-10, 50-237, 50-249 MAXIMUM PERMISSIBLE CONCENTRATIONS (MPC)

The concentration of radioactive materials released in gaseous and liquid effluents from the site to unrestricted areas will be less than the concentration levels specified in 10 CTR Part 20 Appendix B, Columns 1 and i

2.

The concentration limit for noble gases MPC in air (submersion), was converted to an equivalent concentration in water using the International j

Commission on Radiological Protection (ICRP) Publication 2.

L MAXIMUM PERMISSIBLE CONCENTRATION OF DISSOLVED l

OR ENTRAINED NOBLE CASES RELEASED FROM THE SITE TO UNRESTRICTED AREAS IN LIQUID WASTE 4

NUCLIDE MPC(uci/ml)*

Kr-85m 2 X 10-0 Kr-85 5 X 10-0 Kr-87 4 X 10-5 Kr-88 9 X 10-5 Ar-41 7 X 10-3 Xe-131m 7 X 10-4 Xe-133m 5 X 10-4 Xe-133 6 X 10'O Xe-135m 2 X 10~'

Xe-135 2 X 10'4 l

Computed from Equation 20 of ICRP Publication 2 (1959),

l' adjusted for infinite cloud submersion in water, and R = 0.01 rem / week, density = 1.0 g/cc abd Pw/Pt = 1.0.

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DRESDEN NUCLEAR POWER STATION DOCKET NOS. 50-10. 50-237, 50-249 j

AVERAGE ENERGY I

The average energy of fission and activation gases was calculated for the.

)

gaseous effluents released from the site. The average energy is based on j

the percentage of each fission gas nuclide present and its respective average energy per disintegration (E in MeV/ dis) for gamma and beta emissions separately.

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Eg=

2.72E-01 MeV/ dis Eg =

2.87E-01 MeV/ dis

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L DRESDEN NUCLEAR POWER STATION DOCKET NOS. 50-10, 50-237, 50-249 I

i MEASUREMENTS AND APPROXIMATIONS

]

A.

Fission and activation gases:

The D-1 chimney, D2/3 chimney and D2/3 i

Reactor Building Vent are sampled weekly via a grab sample. The samples are analyzed for specific isotopes present in the release using a Hyper-Pure Germanium (HP Ge) Spectrometry System.

Tritium is sampled monthly via a grab sample on the D-1 chimney, D2/3 Chimney, l

and D2/3 Reactor vent and analyzed using a Liquid Scintillation Counter. Krypton-85 is estimated in the D2/3 chimney using a recoil l

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 Off-Gas.

B.

Iodine and Particulate:

Iodine and particulate samples from the D-1 Chimney, D2/3 Chimney and the D2/3 Reactor Building Vents are collected for a maximum seven day period.

These samples are analyzed for specific nuclides present in the release using a HP Ce spectrometry system. When iodine or particulate samples are not used for reporting the release rate due to management decision that the sample may not be representative, an average of the preceding sample and the following sample is used to calculate the release. A monthly composite of the particulate samples is sent to a vendor to be analyzed for Sr-89, Sr-90, and Cross Alpha activity.

C.

Liquid Effluents:

Prior to a release, duplicate grab samples are collected from each batch and analyzed for gross activity using a gas flow proportional counter. Radioactive waste batch discharges are also 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. Te-55. H-3, and Gross Alpha activity. A sample of each Containment Cooling Service Water (CCSW) system is analyzed each month for specific isotopes present in the release using a HP Ge spectrometry system. A sample of each CCSW system is sent each month to a vendor to be analyzed for Sr-89, Sr-90, Fe-55 H-3, and Gross Alpha activity.

D.

Estimation of Overall Errors:

The methods used for 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 equipment, counting statistics, sampling error, discharge volume, and flow rate l-monitors.

E.

Estimation of Vendor Analyzed Information: The vendor analyzed data for Sr-89, Sr-90, Fe-55, H-3, and Gross Alpha was projected, where applicable, for the months of November and December using October data. A corrected Effluent Report will be submitted when the data l

becomes available.

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ZEDE/108 11 of 32 l

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DRESDEN NUCLEAR POWER STATION UNITS 1,2, AND 3 l

p EFFLUENT AND WASTE DISPOSAL SIMIANNUAL' REPORT l

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_ July _ __ Through Dessahar _ 1989 i

GASEOUS EFFLUENTS Docket Numbers: 50-10 l

50-237 I

SUttiATION OF ALL RELEASES 50-249

)

i EST. TOTAL f

TYPE OF RELEASE UNITS 3r.d QUARTER Mb QUARTER ERROR.1 i

EISSION_ANDJCTIVATION GASES 1.

Total Release ci 2.25E+00 9.75E+00 7.31 2.

Average Release Rate for Period uCi/sec 2.83E-01 1.23E+00 3.

Percent of Technical Specification Limit A

A B2__10 DINES 1.

Total Iodine-131 Ci 1.58E-03 9.15E-04 9.51 2.

Average Release kate of I-131 for Period uCi/see 1.99E-04 1.15E-04 3.

Percent of Technical Specification Limit A

A 4.

Total Iodine-131, Iodine-133.and Iodine-135 C1 2.32E-02 1.54E-02 C.. PARIICUMTES 1.

Particulates with half-lives > 8 days Ci 4.09E-02 4.10E-02 8.09 2.

Average Release Rate for Period uci/sec 5.15E-03 5.16E-03 3.

Percent of Technical Specification Limit A

A 4.

Cross Alpha Radioactivity Ci 1.16E-05 LLD Di__.TRlI1Uti 1.

Total Release Ci 3.07E+00 4.45E+00 7.89 2.

Avetage Release Rate for Period uC1/sec 3.86E-01 5.60E-01 3.

Percent of Technical Specification Limit 1

A A

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A The information is contained in the Radiological Impact on Man section of the report. Total airborne release data is provided which includes fissjon and activation gases, iodines, particulates, and tritium.

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ZEDE/108 12 of 32 l

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i' DRESDEN NUCLEAR POWER STATION i

IL

'l UNITS 1,2, AND 3

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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT l

g

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_Julv Through Decembat_ 1982 j

Docket Number-50.

L TABLE OF LOWER LIMITS OF DETECTABILITY 50-237 FOR GASEOUS EFFLUENTS 50-249

[

L LLD (uCi/cc) f i-1.

FISSION GASES t

Xe-138 1.62E-07 Xe-135m 7.18E-08 Kr-87 4.25E-08 Kr-88 6.09E-08 Kr-85m 2.08E-08 "L

Kr-85 4.91E-06 l

Xe+135 1.66E-08 Xe-133 4.53E-08 Others:

2.

10 DINES 1-131 1.33E-13 1-133 7.00E-12 I-135 1.84E 07 3.

PARTICULATES Sr-89 6.00E-16 Sr-90 6.00E-16 Cr-51 7.21E-13 Mn-54 8.76E-14 00-58 7.52E-14 Fe-59 1.40E-13 Co-60 1.93E-13 Zr-95 1.38E-13 l '

Nb-95 8.36E-14 l

Ru-103 8.09E-14 Ag-110m 7.42E-14 Sb-124 6.66E-14 I-131 1.25E-13 Cs-134 8.50E-14 Cg-136 1.21E-13 Cs-137 8.77E-14 Ba-140 3.68E-13 l -

Ce-141 1.28E-13

't Ce-144 4.85E-13 l

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Zn-65 1.43E-13 l

Ba-133 9.89E-14 Sb-125 2.22E-13 Others:

l Gross Alpha 4.00E-15 Fe-55 1.20E-14 ZEDE/108 13 of 32

i DRESDEN NUCLEAR POWER STATION o,

UNIT 1 f

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Julv Through Deca =her 1982 DI Chianty_ GASEOUS EFFLUENTS GROUND LEVEL RELEASES Docket Number 50-10 SEMI-ELEVATED RELEASES xx ELEVATED RELEASES CONTINUQUS_MDEE BAICE.}{QDE NUCLIDES RELEASED UNIT 3rd QUARTER Aih QUARTER at.d QUARTER h.t.h QUARTER-FlSSIOR_ GASES Xe-138 Ci_

Ke-135m Ci Kr-87 Ci XI.-88 01

_Kr-85m C1 Kr-85

__ Ci Xe-135 Ci Xe-133 Ci TQJAL Ci None None IODINES I-131 Ci

__,_.1-133 Ci-1-135

_Ci_

TOTAL Ci_

None None PidI1CUIATES Sr-89 C1 1.76E-05 Sr-90 Ci_

8.75E-08 Cr-51 Ci Mn-54 C1 3.71E-07 Co-58 01 Fe-59

_Qi C0-60 Ci 5.0$E-06 5.78E-06 2r-95 01-Nb-95 Ci Ru-103 Ci Ag-llQm

_Ci Sb-124 Ci I-131 C1 Og-134 Ci Cs-136 Ci i

Cs-137 Ci 2,10E-06 2aD2E-06 Ba-140 01 Ce-141 Ci Ce-144 01 2n-65 C1 l

Ba-133 C1 Sb-125 Ci fe-55 C1 5.08E-06

_.IQIAL Ci 3.Q7E-05 7 83E-06 None None

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

ZEDE/108 14 of 32 I

DRESDEN NUCLEAR POWER STATION Unit 1 EFFLUENT AND'JASTE DISPOSAL SEMIANNUAL REPORT July Through _Segtembtr 1982 D1 Chimnev GASEOUS EFFLUENTS GROUND LEVEL RELEASES Docket Numbers: 50-10 SEMI-ELEVATED RELEASES xx ELEVATED RELEASES CONIINUQUS_ MODE NUCL1 DES RELEASED UNIT JULY AUGUST SEPTEMBER ltd QUARTER TOTAL FISS.10N CASES xe-138 Ci xe-133m

_ci Kr-87

_Ci Kr.-88 Ci Kr-85m Ci KI-85 01 Xe-135 Ci Xe-133 C1 TOTAL Ci 10 DINES I-131

_Ci_

I-133 Ji_

I-135 C1 TOTAL Ci PARTICULATES St-89 C1 1 1.(ig-05 1.76E-05 Sr-90

_Ci_

8.75E-08 8.75E-Dj__

Cr-51 C1 Mn-54 Ci 3.71E-07 3.71E-07 Co-58 C1 Fe-59 01 Co-40 C1 2.12E-06 1.56E-06 5.71E-07 5.05E-Q6_.

2r-95 C1 Nb-95 C1_

Ru-101

_Ci_

Ag-LLQm Ci Sb-124 Ci I-131

_01_

C3-134 Ci Cg-136 Ci Cs-137 C1 1.24E-06 1.09E-06 1.7]E-07 2.50E-06 Ba-140 C1

(

Ce-141 C1 W

Ce-144 Ci 2n-65 Ci Ba-133 C1 Sh-125 Ci Fe-55 C1 1.02E-96 4.06E-06 5J BE-06 TOTAL Ji 5.15E-06 2.63I-06 2 15E-05 1 011-05

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

ZEDE/108 15 of 32

DRESDEN NUCLEAR POWER STATION UNIT 1 a

EFTLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

_Qclobar_._ Through DarnahtI_ 1982 Di Chiinney GASEOUS EFFLUENTS CROUND LEVEL RELEASES Docket Number 50-10 SEMI-ELEVATED RELEASES XX ELEVATED RELEASES CONTINUQUS.JQDE NUCLIDES RELEASED UNIT OCTOBER NOVEMBER DECEMBER 4th QUARTER TOTAL FlSS10tL.0ASES Xe-138 Ci Xt-135m Ci Kr-87 Ci Kr-88 Ci Kr-S5m 01 Kt-B5 Ci Xe-135 Ci Xe-133 Ci TOTAL Ci 10 DINES I_131 Qi I-133 Ci I-135 Ci TOTAL C1 PARTICUMTES sr-89 Ci Sr-90 Ci Cr-51 Ci Mn-54 Ci Cn-5_8 Ci Fe-59 Ci Co-60 C1 1 15E-06 1.92E-07 3.74E-J6 5.78E-06 2r-95 Ci_

Nb-35

_CL Ru-103

_01 Ag-110m Ci Sh_124 Ci I-131 Ci C a.-l.3_4 C1 Cg-136 Ci Cs-137 C1 1 23E-07 1.95E-06 2.07E-06 Ba-140 C1 g

Ce-11.tl

_.CL Ce:144

_Ci_

2p-65 Ci Ba-133 Ci Sb-125 CL Fe-55 Ci_

TDIAL C1 1J5E-06 3.15E-07 5.69E-06 7.85E-06

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

ZEDE/108 16 of 32

v DRESDEN NUCLEAR POWER STATION UNITS 2 AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Julv Through _Daceahar 1989 D2/3 Chimney GASEOUS EFFLUENTS GROUND LEVEL RELEASES Docket Numberst 50-237 SEMI-ELEVATED RELEASES 50-249 XX ELEVATED RELEASES CORIINUOUS3 0DE BAICE_ MODE NUCLIDES RELEASED UNIT 3rd QUARTER sj;h QUARTER 3rd QUARTER Alh QUARTER FISSION GASES Xe-138

_CL Xt-135m Ci-1.BBE_+00 Kr-87 Ci i'

Kr-88

_C1 Kr-85m Ci Kr-85 Ci_ - _21815:03 2,30E-03 Ke-135 C1 2.25E+00 9.75E+00 Xe-133 Ci TQTAL C1 2.25E+00 1.16E+01

None, None 10 DINES

_L_131 Ci_

L13E-03 6 16E-04 I-133 Ci 6.15E-03 3.83E-03 2

1-135 Ci 8.95E-03 5.27E-03 TOTAL C1 1.63E-02 9.77E-03 None None FARTICULAIES__

Sr-89 C1 2.26E-04 1.80E-04 Sr-90 C1

1. 53 E-06 1.61E-06 Cr-51 Ci 1.16E-04 Mn-54

_.C1._

1 10E-05 2.16E-05 Co-5B

_C L.-

Fe-59

_01 Co-60 C1 1.47E-04 8.15E-05 Zr-95 01 Nb-95 Ci_

Ru-103 C1 Ap-110m Ci Sh:124 C1 I-131 C1 1.01E-04 3 1BE-05 Cs-134 Ci Cs-136 C1 Cs-137 01 5.83E-06 1.41E-05 Ba-140 Ci 1.04E-03 5.81E-04 Ce-141 Ci_

l Cc-lh4

__ C1 Zn-63 Ci Bg-133 Ci Sh:125 C1 La-L40 01 106E-03 1.17E-03 Fe-55 C1_....... 2.33E-04 liDjE-04 i

TOTAL Ci 3.83E-03 2.40E-03 NONE NONE

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

ZEDE/108 17 of 32

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DRESDEN NUCLEAR POWER STATION l

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. UNITS 2 AND 3 EFFLUENT AND WASTE DISPOSAL SEM1 ANNUAL REPORT Julv Through _.S.epta=her 1982 D2/3 Chimney GASEOUS EFFLUENTS i

GROUND LEVEL RELEASES

~

Docket Ntunbers: 50-237 SEMI-ELEVATED RELEASES 50-249 XX ELEVATED RELEASES CONTINUOUS MODE NUCLIDES RELEASED UNIT JULY AUGUST SEPTEMBER 3rd QUARTER TOTAL FISSION GASES Xe-138 C1 Xe-135m Ci Kr-87 Ci

... Kr-88 Ci Er-85m Ci Kt-85 Ci 1.03E-03 9.80E-04 8.02E-04 2 81E-03 Xe-135 C1 2.64E-01 1.99E+00 2.25E+00 Xe-133

_Ci_

TOTAL 01 2.65E-01 9.80E-04 1.99E+00 2.25E+00 10 DINES I-131 Ci 3.44E-04 5.07E-04 3.78E-04 1.23E-03 1-133 C1 2.14E-03 1.97E-03 2.04E-03 6.15E-03 1_135 Ci 3.J6E-03 2d6E-03 3.03E-03 8.95E-03 TOTAL C1 6.04E-03 4.84E-03 5.45E-03 1.63E-02 PARIICMIATES Sr-89 Ci 8.92E-05 1.37E-04 2.26E-04 Sr-90 C1 8.99E-07 6.28E-07 1 13E-06 Cr-51 Ci Mn-54 C1 1.70E-05 1.70E-05 00-58 Ci Fe-59 Ci Co-60 Ci 6.84E-05' 1.97E-05 5.88E-05 1.47E-04 Zr-95 Ci i

l Nb-95 C1 t-Ru-103 Ci Ag-110m Ci Sb-124 Ci I-131 C1 1.00E-05 3.63E-05 5.51E-05 1.01E-04 Cs-134 Ci C3-116 Ci Ca-137 Ci 7,jlE-07 5.05E-06 5._8.3 E-06 Ba-lh0 Ci 3.63E-04 2.83E-04 3.91E-04 1.04E-03 g

Ce-141 C1 Ce-144 Ci Zn-65 C1 Ea-133 Ci Sh125 Ci La-140 Ci 4.87E-04 8.63E-04 7.13E-04 2.06E-03 Fe-55 Ci 1.44E-04 3dQE-05 5.70E-05 2d3E-04 TOTAL C1 1.18E-03 1.37E-03 1.28E-03 3.83E-03 l

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

ZEDE/108 i

l 18 of 32

DRESDEN NUCLEAR POWER STATION s

UNITS 2 AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT October Through _DetsshtI_. 1989

_D1/3.Chimaev GASEOUS EFFLUENTS GROUND LEVEL RELEASSS I

Docket Numbers: 50-237 i

SEMI-ELEVATED RELEASES 50-249 XX ELEVATED RELEASES i

CONIINURUS_M0DE l

NUCLIDES RELEASED UNIT OCTOBER NOVEMBER DECEMBER 4th QUARTER TOTAL FISSION GASES _

Xe-138

_Ci Xe-135m C1 1.BBE+00 1 88E+00.

Kr-87 Ci Kr-88 C1 Kr-85m Ci Kr-85 C1 1.12E-03 9 85E:0.4 1.94E-04 2.30E-03.

Xc-135 Ci 5.46E+00 4,.29E4 00 -

9.751+.00_

Xe-133 C1 TOTAL 01 7.34E+00 4.29E+00 1.94E-04 1.16E+01 10DIEES I-131 C1 3.95E-04 1.94E-04 7.71E-05 6.fiE-04 I-133.

_Ci_

2.60E-03 9.11E-04 2 53E-04 3,83E-03__

1 I-135 C1 3.97E-03 1.30E-03 5.27E-Q3__

TOTAL Ci 6.97E-03 2.46E-03 3.35E-04 9.77E-03 PARI 1CUIATES_._

Sr-89

_Ci_,

5.99f-05 5.99E-05 5.99E-05 1 10E-04..

Er:90 Ci st35E-07 5,35E-07 5.35E-07 1 61E-06__

Cr-51 C1 1.16E-04 1.16E-04 Mn-56 Ci 4.33E:06 1 1,'iE-O s 2 16E-05 4

0o-58 01 Fe-59

_CL CD-60

_CL 2.86E-05 1 68E-05 3.61E-05 8.15E-05 1

2r-95 Ci Nb-95 Ci

.___Ru-103 C1 Ag-110m Ci_

Sb-124 Ci I-131 01 22BBE-Q5 3 0AE:06 3 18I-01_

Cs-134 Ci Ca-136

_CL Ca-137 Ci id1E-05 1.41E-01__

Ba-140 C1 2 32E-04 2.53E-04 3.05E-05 5.81E-04...

Ce-141 C1 Cc-1A4

_Ci Zn-65 Ci_

Ba-133 Cl i

Sb-125 Ci

_ _l,a_1AO C1 6.26E-04 4.68E-04 8.08E-05 1 12E-03__,

Fe-55 JL 6 82E-01 6.82E-05 6 BRE:05 2tQ5E.04__

2 TOTAL C1 1.10E-03 8J5E-04 4.12E-04 2.40E-03

(

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

appropriate table ZEDE/108 19 of 32

DRESDEN NUCLEAR POWER STATION UNITS 2 AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

.fuly__ Through _Decamher_1989 D2/3 Reactor Building Vent GASEOUS EFFLUENTS GROUND LEVEL RELEASES Docket Numbers: 50-237 1

XX SEMI-ELEVATED RELEASES 50-249 ELEVATED RELEASES CONIINUOVS_ MODE BAIClLfl0DE NUCLIDES RELEASED UNIT ltd QUARTER

.41h QUARTER 3rd QUARTER hih QUARTER FISSION GASES Xe-138 Ci Je135m

_Ci_

Kr-87 01 Kr-88 Ci Kr-85m Ci It-85

._Ci_

1.052-05 xe-115 Ci Xe-133_

Ci LODE-08 TQIAL Cl.

1.05E-05 None None 10 DINES I-131

_Ci 3.53L-04 2d9E-04 I-133 C1 2.68E-03 2.16E-03 I-135 Ci_

3 ]SE-03 3.19E-03 TOTAL

_C1 6.82E-03 5.60E-03 PARIICHIAIES None None Sr-89 C1 3.fAE-05 5.52E-05 Sr-90

_Ci_

2dlE-07 L32E-06 Cr-51 Ci 5.43E-03 5.15E-03 Mn-54 C1 2.16E-03 2.42E-03 Co-58 01 1.4BE-03 9 17E-04 Fe59 C1 1.37E-03 1.klE-03 Co-60 Ci 8 33E-03 5.16E-03 Zr-95 Cl Nb-95 Ci Ru-103 Ci Ag-llDm

_Ci 1 2QE-04 1 d2E-04 L

Sb-124 C1 2.57E-05 7.88E-Oi 1-131 Ci 1.29E-04 3.98E-05 Ca-134 C1 l-Ca-136

_Ci_

Cs-137 C 1__,

Ba-14D

_CL 3 14E-04 1.23E-04 Ce-141 Ci Ce-144 C1 Zn-65

_Ci_

2 d2E-DA 1.56E-04 B.a-133

_Ci_

Sb-125

_.Ci La-140 Ci 3.16E-04 1.23E-04 Ma-RP

_Ci_

2 d6E-Q3_.__

id51_D3 Fe-55 C1 1 42E-02 L1DE-0?

TOIAL

_Ci 3.70E-02 3.86E-02 None None The activity of this nuellde is less than the LLD listed on the appropriate table.

ZEDE/108 20 of 32 I

I DRESDEN NUCLEAR POWER STATION UNIT 2 AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT or Julv Through _Sepinsher 1983 I -

D1L3 Atattor Building _ Vent __ GASEOUS EFFLUENTS GROUND LEVEL RELEASES Docket Numbers: 50-237 4

0 XX SEMI-ELEVATED RELEASES 50-249 ELEVATED RELEASES CONTINUOUS _ MODE NUCLIDES RELEASED UNIT JULY AUGUST SEPTEMBER 3rd QUARTER TOTAL FISSJDN_ CASES Xe-138

_C1

-Xe-135m

_CL Kr-87 C1 Kr-88 Ci Kr-85m Ci Kr-B5

_CL 1.05E-05*

1 & E-05 i

Xe-135 Ci Xe-133 Ci 1.00E-OS*

1.00E-08 TOIAL C1 1.05E-05 1.05E-05 IDDINES 1.3fE-04 6 31E-05 l 35E-04 3.53E-04 I-131 Ci t

t I-133

_.Ci_

1,D.3E-03 5.73E-04 1.08E-03 2.68E-03 1-135 C1 2.6)E-03 2.05E-04 9 01E-04 3.79E-03 TOTAL 01 3.84E-03 8.62E-04 2.12E-03 6.82E-03 PARTIC111AIES St-89 C1 3.81E-06 1.27E-05 1.t99E-05 3.64E-05 SI-90 Ci 2 5]E-07 2.51E-07 Cr-51 C1 1.31E-03 1.92E-03 2.20E-03 5.43E-03 Mn-54 Ci 4.17E-04 5.95E-04 1.15E-03 2.16E-03 00-18 01 3.03E-04 4.43E-04 7,29E-04 1.4BE_03.__

1.2fE-04 3d 5E-0A 7.84E-04 1.37E-03___

Fe-59 C1 t

Co-60 C1 1.B6E-03 2.67E-03 3.80E-03 8.33E-03 2r-95 Ci I

Nb-95 Ci Ru 103 CL Ag-l10m Ci 1.98E-05 3 89E-05 6.10E-05 1.20E-04 Sb-124 C1 1.76E-06 2.39E-05 2.57E-05 1-131 C1 1.51E-05 2.86E-05 8.53E-05 1.29E-04 Cs.._134

_Ci_

Cs:136

_01 l

Cs-137 Ci B -lh0 Ci 5.81E-05 6,67E-05 1.91E:04 3.16E-04 R

Ce-141 C1

\\-

Cc-ll.th

__ C1

/

... 20-65

_Ci_

2,.5SE-05 8.04E-05 1.61E-Q.4

_2.67E-04 l

Ba-133 Ci Sb-125 Ci_

La-140 Ci 5.BlE-05 6.67E-05 1.91E-04 3.16E-04 l.

flo_12.

_Ci_ ___2.i16E-04

._,_ LD3E-04 L116E-03

_ 2d6E-03 En:55 C1 2.37E-03 4.95E-03 7.59E-03 1.49E-02 IQIAL C1 6.96E-03 1dSE-02 1.82E-02 3.70E-02 The activity of this nuclide is less than the LLD listed on the appropriate table.

See Supplemental Information ZEDE/108 21 of 32

DRESDEN NUCLEAR POWER STATION UNITS 2 AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT October Through -Deca =her 1919 I

D2/3 Rear, lor Buildine Vent GASEOUS EFFLUENTS GROUND LEVEL RELEASES Docket Numbers: 50-237 XX SEMI-ELEVATED RELEASES 50-249 ELEVATED RELEASES CONTINU.QUE_fl0DE NUCLIDES RELEASED UNIT OCTOBER NOVEMBER DECEMBER 4th QUARTER TOTAL FJSSION-. GASES Xe 138

_Ci Xe-135m Ci Kr-87 Ci Kr-88

.QL rr-Rim

_Ci s

Kr-85

_,CL xe-135 Ci xe-133 Ci TOTAL

_CL 10 DINES I-131 C1 1.34E-04 8d2E-05 3.35E-05 2.49E-04 I-133 Ci 1.17E-03 6.77E-04 3.14E-04 2.16E-03 I-135 C1 1.74E-03 8.98E-04 5.50E-04 3.19E-03

_ -_I0IAL C1 3.04E-03 1.ffE-03 8,18E-04 5d.QE-Q3_.

FARIlCUIATES__

Sr-89 C1 1.84E-05 1.84E-05 1.84E-05 5.52E-05 Br-90 Ci 7.95E-07 7.95E-07 7.95E-07 2.39E-06 Cr-51 C1 1.56E-03 9.60E-04 2.63E-03 5.15E-03 l-Mn-$h CL 6.13E-Qh 3 50E-04 1.46E-03 2 d2E.-M_

0o-58 C1 3.62E-04 2.28E-04 3.27E-04 9.17E-04 Fe-59 Ci 3.90E-04 2.35E-04 9.81E-04 1.61E-03 _

Co-60 01 1.93E-03 1.16E-03 2.07E-03 5.16E-03 zr _95 Ci Nb-25 C1 Ru-103 Ci Ag-110m Ci 4.92E-05 3.07E-05 3.86E-05 1.19E-04 Sb-124 C1 1.49E-05 4.31E-06 5.96E-05 7.88E-05.

1_131

_.C L 3 dBE-05 3 93E 05_

Cn-134

_CL Cg-126 Ci Cs-137 C1 Ba-lhD

_.CL 6.99E-05 4a Q8E-05 L26E-05 1,13E-04 Ce-lh1 Ci Ce-144 Ci In-65 Ci 3.80E-05 1.13E-05 1.07E-04 1.56E-04 Ba-133 Ci Sb-12)

_QL l

La-1A0 CL 6.99E-05 4.08E-05 1.26E-05

___h21E-04 fio-99 Ci 8,99E-04

.5.,$_4 E-04 1.94E-04

1. kiE-03_.__

Fe-55 Ci 6.99E-03 6.99E-03 6.99E-03 2.10E-02 TOTAL C1 1 30E-02 LQhE-02 1.49E-Q2 3.86E-Q2_ _

1

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

ZEDE/108 22 of 32

x=

1 DRESDEN NUCLEAR POWER STATION c

E UNITS 1, 2. AND 3 4

F EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

,Julv Through Dec==her 1982 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES Docket Numbers: 50-10 50-237

$0-249 EST. TOTAL UNIT 3rd QUARTER Ath QUARTER ERROR,%

A, FISSION AND ACTIVATION PRODUCTS r

1. Total Release Ci 8.98E-02 1.11E-01 5.58 (not incl. tritium, gases, alpha)

2. Average Diluted Conc. During Period uCi/mL 1.43E-09 9,10E-09

3. Percent of Applicable Limit 1

A A

P L.__TR1I1UM

1. Total Release Ci 5.44E+00 2.99E+00 7.75

2. Average Diluted Conc. During Period uC1/mL 8.66E-08 2.45E-07

3. Percent of Applicable Limit A

C.

DISSOLyi,D AND ENTRAINED CASES

1. Total Release Ci 7.64E-05 1.30E-05 5.58

2. Average Diluted Cone. During Period uCi/mL 1.22E-12 1.07E-12

3. Percent of Applicable Limit A

A D.

GROSS ALPHA RADIfRCTIVITY r

1. Total Release Ci 2.51E-03 LLD

-15.1 E.

VOLUME OF WASTE RELEASED (prior to dilution) liters 5.87E+06 5.79E+06 5.00 F.

VOLUME OF DILUTION WATER USED DURING PERIOD liters 6.28E+10 1.22E+10 5.00 h 1k The information is contained in the Radiological Impact on Man section of this report. Total liquid release data is provided which includes fission and activation products, tritium, and dissolved and entrained g:sas.

ZEDE/108 23 of 32 w

1 DRESDEN NUCLEAR POWER STATION UNITS 1, 2, AND 3 o

July Through Dec==her 1912 TABLE OF LOWER LIMITS OF DETECTABILITY Docket Numbers: 50-10 FOR LIQUID EFFLUENTS 50-237 50-249 1

LLD (uci/mL)

Sr-89 5.00 E-09 l

Sr-90 5.00 E-09 Ar-41 2.94 E-08 Mn-54 6.56 E-08 Co-58 5.62 E-08 Fe-59 8.04 E-08 Co-60 9.73 E-08 Zn-65 8.07 E-08 Ru-103 5.77 E-08 Sb-122 6.63 E-08 i

Sb-124 4.53 E-08 I-131 5.75 E-08 Cs-134 5.51 E-08 Cs-137 6.05 E-08 Ba-140 2.12 E-07 La-140 2.67 E-08 Ce-141 8.87 E-08 Xe-133 1.33 E-07 Xe-135 5.06 E-08 Cr-51 4.72 E-07 Fe-55 5.2 E-07 Kr-88 1.71 E-07 Cs-138 Not Determined Tc-99m 4.63 E-08 Rb-88 Not Determined H-3 8.00 E-07 Cu-64 Not Determined Gross Alpha 5.00 E-08 ZEDE/108 24 of 32

=-

DRESDEN NUCLEAR POWER STATION UNITS 1, 2, AND 3 4

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1

J Julv Through December _,_.19M Radwaste LIQUID EFFLUENTS Docket Numbers: 50-10 50-237 1.

Number of Batch Releases: 1.49E+02 50-249 2.

Total Time Period for Batch Releases: 4.48E+04 min 3.

Maximum Time Period for a Batch Release 5.68E+02 min

+

4.-

Average Time Period for Batch Releases: 3.01E+02 min 5.

Minimum Time Period for a Batch Release: 2.00E+00 min 6.

Average Stream Flow During Periods of Release of Effluent into a Flowing Stream: 1.67 E+06 L/ min CQNTINUOUS liODE BATCH MODE NUCLIDES RELEASED UNIT ltd QUARTER Mh QUARTER 3rd QUARTER hh QUARTER St-89 01 St-20_

Ci

-= Lt01E-04

__.8d5E-05 l

Ar-41 Ci_.

Ma-54 C1 1.43E-02 1.5BE-02 00-58 Ci 3.48E-05 2.85E-04 Fe-59 Ci 9 82E-05 Co-60 C1 4x8ZE-Q2 7.07E-02 2n-65 Ci_

Ru-103 C1 Sb-122 Ci Sb-124

- 01 I-131

_,, Ci_

I-133 Ci I-135 Ci Cs-134 Ci C.ar137 Ci 9.47E-03 2.36E-02 l

BA.140 Ci_

La-140 C1 3.72E-06 Cc-141 Ci Cu-64 C1 3.25E-06 j_

Rh:8g Ji_

2 D5E-04 l

Cs-118 Ci__

4.75E-06 l

Fe-55_.

01 1.67E-02 9.09E-04 C1 Ci_

_Ci_

Ci__

(above) l Io.tp1 For firiod Cl NONE NONE 8.95E-02 1.11E-01 Xe-133 01 1.66E-05 Xe-135 Ci 5.98E-05

1. 30 E--S$__,

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

ZEDE/108 25 of 32 l

DRESDEN NUCLEAR POWER STATION UNITS 1, 2 AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

.. July Through September 198.9

,_Radwaale LIQUID EFFLUENTS Docket Numbers 50-10 50-237 50-249 I

BATCH MODE NUCLIDES RELEASED UNIT July August September 3rd QUARTER TOTAL Sr-89

_C1_

S _$t0

- Ci 1.52E-05 3.75E-05 4.81E-05 1.01E-04 t

Ar-41 C1 Mn-54

- 01 6.8?E-03 4.63E-03 2.75E-03 1.43E-02 Co-58

_Ci

___3dBE-05 3d6E-05___

Fe-59 C1 9.82E-05 9.82E-Q5 C0-40__

_.01 1.71E-02 1 19E-02 1 d2E-02 4.87E-02 2n-65 Ci Ru-103 Ci

,___Sb.122 C1

_ fib _114

._C i_

1-131 Ci I-133 Ci I-135

_Ci Cs-134 C1-Ca-137

_C1_

4 02E-03 3.14E-03

,__li31E-03 9.47E-03 Be140 Ci

.__1,a - M 0

_Ci_

3 72E-06 3.72E-Q6 Ce-141 Ci Cu-64 C1 3.25E-06 3 25E-Qb Rb-88 C1 1.05E-04 1.05E-04 Cs-138 Ci_

4 15E-06 4.75E-06 Fe._15 Ci L3]E-02 2.14 E-03,.,_

6. 74 E-04_

1.67E-02 C1 CL_

Ci (above)

Iotal For Period Ci bl6E-02

. 2.69E-02 LQ0E-02 8.95E.02 Xe-133 Ci 1.66E-QS 1.66E-05 Xe-135 Ci 7.,JfE_.06 2.25E-05 2.99E-05 5.93E-05

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

I r

ZEDE/108 26 of 32

p- -

LRESDEN NUCLEAR POWER STATION UNITS 1, 2. AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT t

DC.taher Through Der.cahgI__. 1912 Radwaste LIQUID EFFLUENTS Docket Numbers: 50-10 50-237 50-249 BATCH MODE NUCLIDES RELEASED UNIT OCTOBER NOVEMBER DECEMBER 4th QUARTER TOTAL Sr-89 Ci Sr-20 C1 2.75E-05 2.75E-05 2.75E-05 8.25E-05 Ar-Al Ci Mn-54 Ci I d3E-03 7.60E-03 6.62E-03

1. 5BI-02.-._

Cg.58 Ci_

2.85E-04 2.85E-04,,

Fe-59 Ci Co-60 Cl-7.82E-03 2.99E-02 3.30E-02__

7.07E-02 Zn-h L Ci_

Ru-103

._C1.

Sh-122 Ci_

Sb-12.4 C1 I-131 C1 I-133

_.C1 I-135 Ci Cs-134 Ci Cs-137 Ci 2.62E-03 7.48E-03 1.35E-02 2.361-02 En-l_4..Q.

Ci

_...... La-lh0 C1._

Ce-141 C1 Fe-55 Ci 3.03E-04 3.03E-04 3.03E-04 9.09E-04 C1 (above)

Iolal_EDI_ft.riod Ci 1.26E-02 4.53E-02 5.35E-02 1.11E-01 Xe-133 Ci-xe-135 C1 5.fi2E-06 7 d6E-OfL 1.30E-05

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

l l

I ZEDE/108 27 of 32

{

DRESDEN NUCLEAR POWER STATION UNITS 2 AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT July Through Dee==her 1919

_._CCSW_

LIQUID EFFLUENTS Docket Numbers: 50-237 50-249 1.

Number of Batch Releases: 6.70E+01 2.

Total Time Period for Batch Releases: 8.31E+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 Releas" of Effluent into a Flowing Stream: 1.67E+06 L/ min CONTINUQU.S.J)QDE RATCil MODE NUCLIDES RELEASED UNIT 3rd QUARTER Alb QUARTER 3rd QUARTER Aih QUARTER

~

Er-89 Ci Sr-90 Ci Ar-41 Ci Mn-54 Ci_

3.26E-05 1.66X-05 Co-58

- Ci En-59 JL 3.44E-05 2.3DE-05 Co-60 C1 2n-65 Ci_

Ru 103

_.Ci -

Sh-122 Ci Sb-124 Ci I-131 Ci I-133 Ci i-135 Ci CA-134 Ci 4.94E-Q5 1.34E-Q1.,_

CA-137 Ci 1.15E-04 3.32F-05 Ba-140-01

___.5JQ E-0 7 La-140 01 5.60E-07 l

Cc-lhi CL l

Cr-51 Ci Fe-55 Ci 2.QhE-05 Ci

__CL C1 C1 C1 Ci I

(above)

Inlal For Period C1 NONE NONE 2.52E-04.

8.73E-05 Xer.133

_CL Xe-135 C1

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

l l

ZEDE/108 l

28 of 32 l

DRESDEN NUCLEAR POWER STATION UNITS 2 AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Julv Through September 19M

,__CCSW LIQUID EFFLUENTS Docket Numbers: 50-237 50-249 BATCH MODE NUCLIDES RELEASED UNIT JULY AUGUST SEPTEMBER 3rd QUARTER TOTAL Sr:89 Ci_

Er-90 C1._

Ar-41 Ci Mn-54 Ci 2.0BE-05 7.15E-06 4.61E 3.26E-05 Co-58 Ci Fe.19 Ci Co-60 C1 1.74E-05 9.67E-06 7.34E-06 3.44E-05 Zn-15

_C1_

Ru-103 Ci Sb-122 Ci Sbd14 Ci I-131 C1-I-133 Ci 1-135 C1 CR-134 Ci

.3.133E-05 9.61E-06

6. lie-06 4.90.E-05 i

2 ADE-05 1.15E-04 Car 137

_C1_..... 5.E7E-05 3 22E-05 i

Ba-1A0 Ci-La-140 01 Cedal Ci Cr-51 Ci Fe-15 C1 2.Q6E-05 2 D6E-05 i

C1 Ci (above)

Total _forferiod Ji_

lillE-DA 5.81E-05 b 22E-05 2.il2E -0L Xe-133 C1 Xe-135 C1 Ci The activity of this nuclide is less than the LLD on the appropriate table.

I ZEDE/108 29 of 32

DRESDEN NUCLEAR POWER STATION UNITS 2 AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1

_Qcioher_ Through DtCambfr. 1982 CCSW LIQUID EFFLUENTS Docket Numbers: 50-237 50-249 BAICH RQDE NUCLIDES RELEASED UNIT OCTOBER NOVEMBER DECEMBER 4th QUARTER TOTAL SI-89 Ci Sr-90 Ci Ar-41 Ci Mn-54 C1 1.66E-05 3.64E-08 1.66E-05 Co-3]L

_CL Fe-59 Ci Co-60 C1 1.86E-05 4.k1E-06 2.30E-Ou Zn-65 Ci Ru-1.03 Ci Sh-122 CL Sb-11h C1 I-131 Ci I-133 CJ _

J-135 Ji Cs-134

_CL 1.3hE-05 1.34E-05 cm-137 C1 2.94E-05 3.ZBE-06 3 31E-03_

Ba-140 01 5.60E-07 5.60E-07 La-14Q

_Ci 5.60E-07 5.60E-07 Ce-141 Ci Cr-51

_CL Fe-55 Ci Ci C1 (above)

IQial_for_Egriod Ci_

7.91E-Q$

8114E-06 8.73E-05 Xe-133 Ci Xc-133 Ci

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

I ZEDE/108 30 of 32

DRESDEN NUCLEAR POWER STATION UNITS 1, 2, AND 3

- o EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Julv Through Deca =her 1983 Docket Numbers 50-10 50-237 SOLID WASTE AND IRRADIATED TUEL SHIPMENTS 50-249 Est Tot.

L SOLID WASTE SHIPPED OFFSITE FOR BURIAL _0R DISIOSAL_INOT IRRADIATED FUEL)

Erron1 4

1. Type of Waste Unit 6-month period m3 5.62E+01 l

a.

Spent resins, filter sludges, evaporator bottoms, etc.

i Ci 9.00E+02 3

m 7.10E+02 b.

Dry compressible waste, contaminated equip., etc.

C1 9.92E+00 16d 3

m 1.42E+01 c.

Irradiated components, control rods, etc.

Ci 3.97E+00 3

m 0

d.

Other (describe)

Ci 0

j

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

co-60 54.1 1 _4J2EtDL Fe-55 21 2 1

1. 91E+QL Mn-54 5.64 1._LDBE10L Cs_137 10.9 1

_ 9. 81 E+0L N1-63

6. 46.J 5.81E+01 l

b.

Co-60 25.3 1 2.51E+00 l

Fe-55 59.9 1 5.94EiQD_

Mn-54 1.14 1 1.13E-OL Cs-ll7 ILB_1 _L 1ZEt00_

Other c.

Co-60 20.2 1 8.02E-01 Fe-55 6LQ__1 2.70E+00 Mn_51 bl23 JLdDE-OL Cs-137 9.38 1 3.72E-01 Other

3. Solid Waste Disposition L

NltiBER OF SHIPMENTS MODE OF TRANSIDRTATION DEETINATION 23 Motor freight (exclusive use only)

Barnwell, SC 4

Motor freight (exclusive use only)

SEG, Oak Ridge, TN l

5 Motor freight (exclusive use only)

CNSI, Channahon, IL l

5 Motor freight (exclusive use only)

Westinghouse DDR l

Madison, PA l

Be IRRADIATED FUEL SHIPMENTS (Disposition)

NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESIINATIDH None ZEDE/108 31 of 32 1

DRESDEN NUCLEAR POWER STATION UNITS 1, 2. AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Julv Through Dec==her 19 82 Docket Numbers: 50-10 50-237 50-249 3

ABNORMAL RELEASES A.

LIQUID r

=1.

Number of Releases 0

2.

Total Activity Released:

0 B.

CASE 00S I

1.

Number of Releases:

0 j

2.

Total Activity Released:

0 i

TOTAL 0

t SUPPLEMENTAL INFORMATION t

AL'1316 hours0.0152 days <br />0.366 hours <br />0.00218 weeks <br />5.00738e-4 months <br /> on September-12, 1989 a routine sample of the Unit 2/3 Reactor Building

[

V:ntilation System Effluent was being collected. Because the normal sample vessel was

~

unnvailable, another container was used. The beaker selected to obtain the sample had been pr;viously used for a cross check program and thus contained approximately 1.0 E-5 curies

'of Kr 85 and 1E-B curies of Xe 133. The contents of the contaminated beaker resulted in a high radiation alarm in the main control room. The alarm was immediately reset.

l ND Technical Specification limits were exceeded during this event. The safety significance cf this incident is minimal because the Reactor Building Ventilation radiation monitors ware operable and automatic isolation would have occurred if necessary.

Labeling of the i

-cample vessels was changed to clearly state that they are to be used for sampling purposes or for calibration standards and cross checks.

k ZEDE/108 32 of 32

,m.,

DRESDEN NUCLEAR POWER STATION DOCKET NOS. 50-10. 50-237. 50-249 D,..

)

RADIOLOGICAL IMPACT ON MAN 1

i e

i l

t

w-DRFFDEN UNIT ONE 1999 ANNUAL RFPORT M A/:IMUM DOSEF REEUITING FROM AIRLORNF RFl.EASEE PERIOD OF RELEASE - 01/01/S7 TO 12/31/E9 CALCULATED 02/06/90 INFANT RFCEPTOR IST OND 3RD

$TH TYFE QUARTER CUARTER QUARTER DUARTFR ANNUAL JAN-MAR AFR-JUN JUL-SEF GCT-bEC GAMMA AIR 0.00E+00 0.00E+00 0.00F400 0.00E+00 0.00F400 (MRAD)

(

)

(

)

(

)

(

)

(

)

LETA AIR 0.00Et00 0.00E400 0.00E+00 0.00E400 0.00EiOO (MRAD)

(

)

(

)

(

)

(

)

(

)

TOT. FDDY 0.00E400 0.00E400 0.00EiOO 0.00EiOO 0.00EiOO (MREM)

(

)

(

)

(

)

(

)

(

)

SKIN

0. 00 Ei OO 0.00EiOO 0.00E400 0.00E400 0.00EiOO (MREM)

(

)

(

)

(

)

(

)

(

)

ORGAN 3.93E-05 2.5BE-05 1.04E-05 3.17F-05 S 73F-05 (MREM)

(SE

)

(SE

)

(SE

)

(SE

)

(EE

)

LIVFR 1.IVER LIVER

!. 3 VFR LIVFR THIS IS A REPORT FOR THE CALFNDAR YEAR 1989 COMPL I ANCE STATUS - 30 CFR 50 APP. I INFANT RECEPTOR

, pp App y, Q T R t.Y iST OTR 2ND OTR 3RD OTR 4TH GTR YRLY

% Of l

OBJ JAN-MAR APR-JUN Jul -RFP OCT-NOV OBJ APP.I GAMMA AIR (MRAD) 5.0 0.00 0.00 0.00 0.00 10.0 0.00 BETA AIR (HRAD) 10.0 0.00 0.00 0.00 0.00 20 0 0.00 l1 TOT. BODY (MREM) 2.D 0.00 0.00 0.00

0. 0(

5.0 0.00 EN2N (MREM) 7.5 0.00 0.00 0.00 0.00 15.0 0.00 l

O RG All ( 11R E M )

7.5 0.00 0.00 0.00 0.00 15.0 0.00 LIVFR l.IVER LIVER LIVER LIVER l

RESULTS BASED UP0H ODCM RFYISION 11 UPDATE CS204 FEBRUARY 1986 i~~

x.

3!

1 DRESDEN UNIT ONE k;

1989 ANNUAL REPORT MAXIMUM DOSEE RESULTING FROM AIRDCRNE RELEASES PERIOD OF RELEASE - 01/01/89 TD 22/31/89 C ALCUt. A TED 02/26/90 f

ADULT RECEPTOR iST 2ND 3RD 4TH TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL 1

I JAN-MAR AVR-JUN JUL-SEP OCT-DEC GAMMA AIR 0.00E400 0.00E400 0.00E+00 0.00E+00 0.00E+00 (MRAD)

(

)

(

)

(

)

(

)

(

)

DETA AIR 0.00E+00 0.00E+00 0.00E.400 0.00E400 0.00E400 (MRAD)

(

)

(

)

(

)

(

)

(

)

TOT. LODY 0.00E400 0.00E400 0.00Ef00' O.00E400 0.00Ef00

}

(MREM)

(

)

(

)

(

)

(

)

(

)

SNIN 0.00Ef00 0.00E400 0.00E+00 0.00E400 0.00E400 (MREM)

(

)

(

)

(

)

(

)

(

)

ORGAN 1.60E-05 3,23E-05 2.25E-05 1.52E-05 1.01E-04 (MREM)

(SE (SE

)

(EE 3

(SE

)

(SE

)

LIVER LIVER BONE GI-LLt LIVER THIS IS A RFPORT FOR THE cal.FNDAR ' YEAR 3989 1

COMFLIANCE STATUS - 10 CFR 50 AFP. I Abul.T RECEPTOR i

% OF APP I.

QTRLY JST QTR DND OTR 3RD OTR 4TH QTR YRLY

% OF ODJ JAN-MAR APR-JUN JUL-SEP OCT-NOV OBJ APP.I GAMMA AIR (MRAD) 5.0 0.00 0.00 0.00 0.00 10.0 0.00 DETA AIR (MRAD) 10.0 0.00 0.00 0.00 0.00 20.0 0.00 TOT. 10DY (MREM) 2.5 0.00 0.00 0.00 0.00 5.0 N 00 SNIN (MREM) 7.5 0.00 0.00 0.00 0.00 15.0 0.00 DROAN (MREM) 7.5 0.00 3.00 0.00 0.00

.15.0 0.00 LIVER LIVER BONE GI-ILI LIVER RESULTE EASED UPON ODCM REVISION 11 UPDATF CS204 FEDRUARY 1986

ow -

w DRESDEN UNIT T k'O 19E9 ANNUAL REPORT MAXIMUM DOSES RESULTING FRDM AIkFORNE RELEAFFS PERIOD OF RELEAEE - 01/01/89 TD 2/31/89 CALCUl.ATED 02/26/90 INFANT RECEPTOR 10T 2ND 3RD 4TH TYPE QUARTER DUARTER QUAR 1ER GUAR 1ER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC CAMMA AIR 1.jSF-05 3.02E-04 3.85E-06 3 00E-05 1.15E-04 (MRAD)

(NE

)

(NE

)

(NE

)

(NE

)

(NE

)

DETA AIR 1.97E-06 2.47E-04 3.91E-07 5.17F-06 2.55F-04 (MRAD)

(N

)

(NNE )

(N

)

(N

)-

(NNE )

10T. EODY 5.32E-06 4.26E-05 7.79E-07 1.30E-05 6.loF-05 (MREM)

(NE

)

(NE

)

(NE

)

(NE

)

(NE

)

EKIN 1.05E-05 2.65E-04 1.70F-06 2.6EF-05 3.03E-04 (MREM)

(NE

)

(NNE )

( flE

)

(NF

)

(NNE :

ORGAN 1.50E-02 3.19E-02 1.03E-02 2.43E-02 8.32E-02 (MREM)

(NNE )

LUNG LUNG THYROID LUNG tUNG THIS IS A REPORT FOR THE cal.ENDAR YEAR 1989

[

COMPLIANCE STATUS - 10 CFR 50 APP. I INFANT RECEPT 0R

.% OF APP I.

QTRLY iST OTR 2ND OTR 3RD OTR 4TH QTR YRLY

2. OF OBJ JAN-MAR APR-JUN JUL-SEP DCl-NOV OBJ APP.I GAMMA AIR (MRAD)

S.0 0.00 0.00 0.00 0,00 10 0 0.00 PETA AIR (MRAD) 10.0 0.00 0.00 0.00 0.00 20.0 0.00 l

TOT. BODY (MREM) 2.5 0.00 0.00 0.00 0.00 5.0 0.00 SKIN (MREM) 7.5 0.00 0.30 0.00 0.00 15.0 0.00 ORGAN (MREM) 7.5 0.20 0.43 0.14 3.32 15.0 0.54 LUrJG LUNG 1HYROID

1. U N G LUNG g.'

RESULTS BASED UPON ODCM REVISION 11 UPDATE CS204 FEbWUARf 3986 L

=,'

i%Lc_

. ~ =.

+

wawm;m v~

N M.

d.

.DRESDEN UNIT TWO 1989 ANNUAL RFPORT MAXIMUM-DOSES RESULTING FROM AIRBORNE RELEASES PERIOD OF RELEASE 01/03/89 TO 12/31/B9' CALCULATFD 02/26/90 ADULT RECEPTOR o

IST 2ND

'3RD 4TH TYPE.

QUARTER QUARTER 00ARTER QUANTER ANNUAL

'JAN-MAR APR-JUN JUL-SFP OCT-DEC LGAMMA' AIR-1~.18E-05

-1 02E-Oi 1.85E-06 3,00E-05' 1.45E-04 (MRAD)

(NE

.)

(NE

)

(NE

)

(NE

)

(NE

)

BETA AIR 1.97E 2.47E-04 3.91E-07 5.17E-04 2.55E-04

-(MRAD)

(N.

)

(NNE )

(N.

)

(N

)

(NNE )

TOT. BODY.

,5.12E-04 4.26E-05 7.79E-07 1.30E-05 6.14F -(MREM)

(NE

)

(NE

')

(NE

)

(NE

)

(NE

)

SKIN 1.05E-05 2.65E-Oi

.1.70E-06 2+68E-05 3.03E-04

-(MREM)

(NE.

)

(NNE )

(NE

)

(NF

)

(NNE )

' ORGAN 1.50E-02 1.64E-01 1 14E-02 2.50E-02 2.11E-01

(MREM)

(NNE >-

(NNE )

(NNE >

(NNE )

LUNG BONE GI-LLI LUNG.

BONE THIS.IS A REPORT FOR THE CALENDAR YEAR 3989 COMPLIANCE STATUS - 10 CFR 50 ' APP. I ADUI.T RECEPT 0R

% OF APP I.

OTRLY iST OTR 2ND OTR 3RD OTR 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 0.00 BETA AIR (MRAD) 10.0 0.00 0.00 0.00 0.00 20.0 0.00

[.

-T'"

40DY : -( MREd )

2.5 0.00 0.00 0.00 0.00 5.0 0.00 SK

(MREM)

.7.5 0.00 0.00

.0.00 0400 15.0 0.00

. ORGAN (MREM)

7. 5' O.20 2.19 0.15 0.32

.t5.0 1.40

-LUNG BONE GI-LLI LUNG BONE 1

RESULTS BASED UPON ODCM REVISION 11 UPDATE CS204 FEBRUARY 1986

www

.i l':

DREEDEN UNIT THREE t

.1989 ANNUAL REPORT 1'

MAXIMUM DO5ES RESULTING FROM AIRBORNE RELEASES PERIOD OFLRELEASE - 01/01/89 TO 12/31/89 CALCULATED 02/24/90 INFANT RECEPTOR j

1 1ST 2ND

'3RD 4TH 3

TYPE OUARTER DUARTER QUARTER' OUARTFR ANNUAL JAN-MAR APR-JUN JUL-SEP GCT-DEC

]

GAMMA' AIR' 2.20E-04 7.00E-05 3.02E-05 1.44F-04 1.65E-04

-(MRAD)

(NE

)

(NE

)

(NE

)

(NE

)

(NE

)

DETA AIR 6.13E-05 4.33E 6.37E-06 2.54E-05 1.33E-04

.(MRAD)

(NNE )

(N

)

(N

-)

(NNE )

TOT 4 BODY 9.39E-05

2. 9 4E- 05 1.27E-05 6.24E-05 1.98E-04 J

(MREM)

(NE

)-

(NE

)

(NE

)

(NE

)

(NE

)

h

$NIN 2.15E-04 8.46E-05 2.75E-05 1.29E-04 4.57E-04 (MREM)

(NE

)

(NE

)

(NE

)

(NE

)-

(NE

)

ORGAN 2.07E-02 3.8SE-02 7.57E-02 2.98E-02 J.55E-01 i

l'

(MREM)

(NNE >

(NNE )

L t

I LUNG FONE THYROID THYRDID LUNG I

L THIS IS A REPORT FOR THE CALENDAR YEAR 1989

)

[

j.

}i:

?

l

[

.I

(

COMPLIANCE STATUS - 10 CFR 50 AFP, I

[

INFANT RECEPTOR I

(

% OF APP 1.

f

[

QTRLY iST QTR 2ND QTR 3RD OTR 4TH QTR

'YRLY

%'0F l

0BJ JAN-MAR APR-JUN JUL-SEP OCT-NOV DBJ APP +I-i OAMMA 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

().00 20.0 0.00 TOT. BCDY-(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 0.28 0.52 1.01 0,40 15.0 1.03

s LUNG FONE THYRDID THYROID 1.UNG h.

l RESULTS BASED UPON I

CDCM REVISION 11 l

UPDATE CS204 i

FEBRUARY 1986 i

f I

I h'

I b--m b

I DRESDEN UNIT THREE 1989 ANNU AL REPORT MAXIMUM DOSES RESULTING FROM AIRBORNE RELEASES PERIOD OF.RELEASF - 01/01/89 TO 12/31/89 CALCULATED 02/26/90 ADULT RECEPTOR 1ST 2ND 3RD 4TH

. TYPE QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC GAMMA AIR 2.20E-04 7.00E-05 3.02E-05.

1.44E-04 4 65E-04' (MRAD)

(NE

)

(NE

)

(NE

]

(NE.

)

(NE

)

DETA AIR 6.13E-05 4.-13E-05 4.37E-06 2.54E 1.33E '(MRAD)

(NNE )

(N

)

(N

)

-(NNE )

TOT. BODY 9.39E-05 2.94E 1.27E-05 6.24E-05 1.9BE-04 (MREM)

(NE

)

(NE

)

(NE

)

(NE

)

(NE

-)

SKIN 2.15E-04 8.44E-05 2.78E-05 1.29E-04 4.57E-04 (MREM)-

(NE

)

(NE i

(NE. )

(NE

)

(NE

)'

ORGAN.

1.60E-02 4.97E-01 8.35E-02 3.32E-02 6.11E-01'

., MREM)

(NE

)

(NNE )

(

BONE BONE GI-LLI THYROID BONE THIS IS A RFPORT FOR THE CALENDAR YEAR 1989 COMPLIANCE STATUS - 10 CFR 50 APP. I ADUIT RECEPTOR

..___..______ x op App I, UTRLY 1ST OTR 2*iD OTR 3RD OTR 4TH QTR YRLY

% OF OBJ JAN-MAR APR-JUN JUL-SEP OCT-NOV GUJ APP.I DAMMA 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 0.21 6.63 1.12 0.44 15.0 4.07 BONE BONE GI-l.LI THYROID BONE RESULTS BASED UPON ODCM REVISION 11 UPDATE CS204 FEBRUARY 1985

mggwww.

~.;

'l i

]

S c...

e. -

1 DREBDEN TINIT'TWO INFANT-RECEPTOR:

1989 ANNUAL REPORT MAXIMUM: DOSES (MREM) RESULTING FROM LIQUID EFFLUENTS 1

PERIOD OF RELEASF - 01/01/89 TO 12/31/89 CALCULATED 02/26/90

.1ST 2ND 3 Rli 4TH DOSE' TYPE QUARTER GUARTER.

QUARTER QUARTER.

ANNUAL JAN-MAR APR-JUN JUL-SEP GCT-DEC

{

TOTAL 1.30E-04

-5.65E-05 5.7RE-05 3.64E-05 2.80E-04 DODY INTERNAL 2.09E-04 1.33E-04 1.25E-04 1.90E-04 6.30E-04 10RGAN-DONE.

LIVER LIVER LIVER LIVER l.

THIS IS o' REPORT.FOR THE CALENDAR YEAR 1989 COMPLIANCE STATUS - 10 CFR 50 APP. I 4

1

% OF APP I.

QTRLY IST OTR 2ND OTR 3RD OTR 4TH QTR

~YRLY

% OF-OBJ JAN-MAR APR-JUN

-JUL-SEP OCT-NOV OBJ.

APP.I

. TOTA'L BODY (MREM) 1.5 0.01 f,00 0.00-0.00 3.0 0.03-1 CRIT. ORGAN (MREM) 5.0 0'.00 0.00 0.00 0.00 10.0 ~

O'.01 BONE LIVER LIVER LIVER LIVER l

.f RESULTS BASED UPON _j ODCM REVISION 11 1

UPDATE CS204 l

FEBRUARY 1986 j

.i l-l 4

i h

i f

i i

)

~6 h u I

i: &

49

.e DRESDEN UNIT TWO

-INFANT RECEPTOR 1989 ANNUAL REPORT-PROJECTED DOSE AT NEAREST COMMUNITY WATER SYSTEM *

. PERIOD OF RELEASE - 01/01/89 TO 12/31/89 CALCul,ATED 02/24/90 p

1ST 2ND 3RD 4TH

]

DOSETTYPE

. QUARTER QUARTER QUARTER QUARTER-ANNUAL

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

1.30E-04 5.65E-05 5.78E-05 3.64E-05 2.80E-04 DODY-

INTERNAL

.2.09E-04 1.33E-04 3.25E-04 1.90E-04

~6.30E-04 ORGAN-o H

BONE LIVER-LIVER LIVER' LIVER THIS IS A REPORT FOR THE CALENDAR YEAR 1989 COMPLJANCE STATUS - 40 CFR 141 TYPE ANNUAL LIMI.

% OF LIMIT TOTAL-40 (MREM) 0.007 BODY

-INTERNAL 4.0 (MREM) 0.016 ORGAN l

LIVER-THIS CALCULATION OF DOSE IS BASED ON TECHNIQUES DESCRIBED IN~THE COMMONWEALTH EDISDN OFFSITE DOSE CALCULATION MANUAL. THESE TECHNIQUES DIFFER FROM THOSE DESCRIBED IN 40 CFR 141.

RESULTS BASED UPON

[

ODCS REVISION 11 UPDATE CS204 FEBRUARY 1986' L

g c

I

(

'b f*

DRESDEN UNIT Tdo j

. ADULT _ RECEPTOR b

1989 ANNUAL REPORT l;

MAXIMUM DOSES (MREM) RESULTING FROM LIQUID EFFl.UENTS'

[

PERIOD OF RELEASE - 01/01/89 TO 12/31/89 CALCULATED 02/26/90 IST 2ND 3RD 4TH DOSE TYPE-

-GUARTER QUARTER QUARTER OUARTER

~ ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC LTOTAL' 2.41E-04 1.SiE-04 1.73E-04 3.26E-04 9.23E-04 BODY

[

INTERNAL 3.37E-04 2.74E-04 2.52E-04 4i94E 1.36E-03' L

' ORGAN O

LIVER LIVER LIVER LIVER l.IVER L

THIS IS A REPORT FOR THE CALENDAR YEAR _1989 L.

COMPLIANCE STATUS - 10 CFR 50 APP. I

% OF APP I.

~~

0TRLY JST OTR 2ND OTR 3RD OTR 4TH OTR--

YRLY

% OF-

[-

7 OBJ JAN-MAR APR-JUN JUL-SEP GCT-NOV OBJ A F:P. I:

TOTAL BODY-(MREM) 1.5 0.02 0.01 0.01 0.02 3.0 0.03 L

CRIT. ORGAN (MRF.M) 5.0 0.01 0.01 0.01 0.01 10.0 0+01 LIVER LIVER LIVER 1.IVER LIVER RESULTS BASED UPON ODCM REVISION 11 UPDATE.CS204

f',

FEBRUARY.1?R6 L

V 6

..j :-

9

.DRESDEN UNIT TWO ADULT RECEPTOR 1989 ANNUAL REPORT PROJECTED DOSE AT NEAREST COMMUNITY WATER SYSTEM 4 PERIOD OF RELEASE - 02/01/89.TO 12/31/89 CALCULATED 02/26/90 1ST 2ND 3RD 4TH K00SEJ-TYPE QUARTER QUARTER QUARTER GUARTER

. ANNUAL JAN-MAR APR-JUN

. JUL-SEP OCT-DEC

-. TOTAL-4.44E-05 2.40E-05 2.49E-05 2.31E-05 1.1SE. BODY.

' INTERNAL 1.31E-04

'5.14E-05 4.12E-05 3.97E-05 2.63E-04 ORGAN GI-LLI DI-LLI GI-LLI GI-LLI GI-LLI THIS IS A REPORT FOR'THE CALENDAR YEAR 1989 COMPLIANCE STATUS - 40 CFR 141 TYPE ANNUAL LIMIT

% OF LIMIT TOTAL' 4.0 (MREM) 0.003

. BODY INTERNAL-4.0 (MREM) 0.007 ORGAN.

GI-LLI

'*.. 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 PASED UPON ODCM REVISION 11 UPDATE CS204 FEBRUARY 1986 I

i-

---.---------m.

.---mm.mm-

i

q. ;

DREEDEN UNIT THREE

-INFAHT RECEPT 0R 1989 ANNUAL REPORT-MAXIMUM DOSES (MRFM) REstlLTING FROM lit 1UID. EFFLUENTS FERIOD 0F RELEASE - 01/01/89 TO 12/31/89 ColCulATED 02/26/90 1ST 2ND 3RD 4TH DOSE. TYPE-QUARTER QUARTFR QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC x

TOTAL 1.'13E-04 6.40E-05 5.79E-05 4.93E-05 2.85E-04 DODY-INTERNAL 1.77E-04 1.49E-04 1.26E-04 2.6PE-04

~7.05E-04 ORGAN DONF LIVER LIVER LIVER LIVER THIS-IS A-REPOR' FOR THE CALENDAR YEAR 1989 COMPLIANCE STATUS - 10 CF R 50 APP.

I-

.op App I, GTRLY JST OTR 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 0.01 0.00 0.00 0,00 3.0 0.01 CRIT. ORGAN (MREM) 5.0 0.00 0'.00 0.00 0.01 10.0 0.01 DONE LIVER LIVER LIVER 1.IVER RESULTS BASED (JP0H ODCM REVISION 11 UPDATE CS204 FEBRUARY 1986 i

r:g

,y n 3{

l:

s-3

s..-

M l

t DRESDEN' UNIT THREE

'{'

INFANT RECEPTOR 1989-ANNUAL REPORT-

)

i PROJECTED-DOSE AT NEAREST COMMUNITY WATER SYSTEM

4 l-PERIOD 0F RELEASE - 01/01/89 TO 12/31/89 CALCULATED 02/26/90

.l 1ST 2ND 3RD 4TH DOSE T.YPE-QUARTER GUARTER QUARTER DUARTER ANNUAL.

~

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

TOTAL 1.13E-04 6.40E-05 5,79E-05 4.93E-05 2.SSE-04

. D O D Y.

INTERNAL 1.77E-04 1.49E-04' j.26E-04' 2.68E-04 7 05F-04 ORGAN g$

BONE.

LIVER LIVER LIVER LIVER

'k i

f

)

THIS IS A REPORT FOR THE CALENDAR YEAR 1989 6

i l

COMPLIANCE ETATUS - 40 CFR J41 I

TYPE ANNUAL LIMIT

% OF LIMIT TOTAL 4.0 (MREM) 0.007 g

BODY

{

INTERNAL 4.0 (MREM) 0.018 l

ORGAN LIVER 1

. *. 'THIS CALCULATION OF DOSE IS BASED ON TECHNIQUES DESCRIBED-IN THE I

COMMONUEALTH EDISON OFFSITE DOSE CALCULATION MANUAL. THESE TECHNIQUES DIFFER I

FROM THOSE DESCRIBED IN 40 CFR 141.

-l RESULTS BASED UPON.

ODCM REVISION 11 i

UPDATE'CS204 j

FEBRUARY 1986 l

1 r

l I

i

?

]

mw 4

1

]u

!*N* '

ls DRESDEN UNIT THREE ADitLT RECEPT 0RJ 1989~ ANNUAL REPORT

]

MAXJMUM DOSES -(MREM) REFULTING FROM LIQUID. EFFLUENTS.-

-]

PERIOD OF RELEASE - 01/01/89 TO 12/31'/89 CALCULATED 02/26/90 1ST 2ND 3RD 4TH

' DOSE TYPE QUARTER QUARTER GUARTER QUARTER

. ANNUAL l

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

3

. TOTAL 2.12E-04 2 03E-04 1.76E 4.62E-04L

-1.05E-03 BODY INTERNAL 2.9BE-04 3.05E-04 2.56E-04 7.00E-04 1.56E-03 s

0RGAN-f LIVER-L.IVER t.IVER LIVER LIVER l

1 THIS IS A REPORT FOR THE CALENDAR YEAR 1989 l

1 COMPLIANCE STATUS -.10 CFR 50 APP. I

____________ g og App I,

OTRLY iST OTR 2ND OTR 3RD OTR 4TH GTR YRLY

!L OF OBJ JAN-MAR APR-JUN JJt.-SEP GCT-NOV OBJ APP.IL t

TOTAL BODY (MREM) 1.5 0.01 0.01 0.01 0.03 3.0.

0.04 I

4 i

CRIT. ORGAN (MREM) 5.0 0.01 0.01 0.01 0.01 10.0~

0.02~

l Y

b s:

LIVER LIVER LIV.?R LIVER

-LIVER

)

L f

[:-

E-B RESULTS BASED UP0H.

ODCM REVISION 11 UPDATE CS204

[

FEBRUARY 1996 l

j 1

1 Ik l

?

i g.

i 1

I i

)

Juu~a--

A

ggg., m -

.a

)

?

1

}

o.

[

c

,j t

DRESDEN UNIT THREE ADULT RECEPTOR 1

1989 ANNUAL REPORT

_l PROJECTED DOSE AT NEAREST COMMUNITY l>! A1 ER 9YSTEM t 4

PERIOD OF RELEASE - 01/01/89 TO 12/31/89 CALCULATED 02/26/90 IST 2ND 3RD 4TH

-l L DOSE' TYPE -

QUARTER QUARTER QUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP DCT-DEC 7

?

TOTAL 3.86E-05 2.71E-05

. 2,51E-05 3.51E-05 1.26E-04 f,

-BODY _'

i

' INTERNAL 1.17E-04

.5480E-05 4.12E-05 5.25E-05 2.69E-04 ORGAN.-

GI-LLI GI-LLI OI-LLI-GI-LLI GI-LLI-l THIS IS A REPORT FOR THE CALENDAR YEAR 1989-l k

j COMPLIANCE STATUS - 40 CFR 141

gl TYPE ANNUAL LIMIT

% OF LIMIT TOTAL 4.0 (MREM) 0.003 L

BODY' L

INTERNAL 4.0 (MREM) 0.007 l

ORGAN ~

GI-LLI l

THIS CALCULATION OF DOSE IS BASED ON TECHNIQUES DESCRIDED IN THE COMMONWEALTH EDISON OFFSITE DOSE CALCULATION MANUAL. THESE TFCHNIQUFS DIFFER l

h

FROM.THOSE DESCRIBED IN'40 CFR 141.

f s

v

[i j

f I'

'RESULTS BASED UFON ODCM REVISION 11 UPDATE CS204 FEBRUARY 1906 j

a h

a l

il

-m

__.m

pg m

.s 7}

4

.i DRESDEN I

)

1989 ANNUAL REPORT BWR TURBINE N-16 *SNYSHINE' DOSES TO NEAREST RESIDENT PRODUCTION PERIOD -' 01/01/89 TO 12/31/89 CALCULATED. 02/26/90 j

3 NEAREST RESIDENT (UN.tTS 2 t 3'>

966 m FISHING ACTIVITY LOCATION

.610 m.

. j i

QU ER QUAF ER QU R ER

. QU RTER.

ANNUAL

.JAN-MAR APR-JUN JUL-SEP OCT-DEC l POWER (Mwn-br>

'2.14Ef06 2.54E+04-3.07E+06 2,55E406' 1.03E+07 l

~. NEAREST RESIDENT WHOLE BODY DOSES (MREM) :

i i

' FISHING DOSE 3.42E-02 4.05E-02 4.90E-02 4.06E-02 1.6.4E-01

,l

'l AT-HOME DOSE 1.47E-02 1.75E-02 2.11F-02 1.75E-02 7.08E-02

]

.h

'l

. TOTAL DOSE 4.89E-02 5.80E-02 7.01E-O?

5.81E-02

-2.35E-01

~THIS IS A REPORT FOR CALENDAR YEAR 1989 d

l CESULTS BASED UPON

,0DCM REVISION 11 UPDATE CS204 g

FEBRUARY 19S6-

's i

1

(:

)

q a

1 1

l

)

L 1

l t

i')

l l

i I

i Er b: -

La--a -

l

ea

?,...

!s t

L, : ;l.L.. 4..'

DRESDEN NUCLEAR POWER STATION / DOCKET NOS. 50-10,'50-237, 50-249.

J i

r METEOROLOGICAL DATA h

I

(

?

l t

k-e

,'4 1

d f

l

.i l

l L-1, l

1, I

l l

I e

___.________.______.__.__._.-m-__.

p p

a q.

h

=d.

i p

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35 ft. V!RD SPED and f!sD DIttCfl08 150-35 ft. DIFFDIst!AL fluPD879tt HND 0F 04SttVAfl005 *4414 SPED -

DittCT100 CLASS 8748!LITY CLASS r

. !. IS! $1 SSE $ SSW SV f5V V-

.VuN N Iuv TOTAL IV H SU

'N

$$ HS > ES. TOTAL CIASS I ' NI II Ett EU.05 ~.00

.00

.00 :.00

.00

.02

.05.09

.07

.11

.41

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.00 :.02

.02

.00

.02

.00

.00. 00

.00

.05

.07

'.00

.02.02

.23

.23 9 $U

.05

.02

.00

.00.02

.02.00 -.05

.05

.07

.05

.02

.00

.02

.07

.43

.43 E.

I

.25

.23

.32

.25 ' 27

.41. 27

.11.14.20

.20

.09

.25.11

.16.16 3.42 3.42 3 SS

.50

.75 ~.45 -.61

.45

.36

.45.32

.45

.23

.29.25.20

.27

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US-.29

.39

.14

.29

.50.45.57

.23

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.27

.36. 25

.27

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.25

.16

.09

.16

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.07

.11

.07

.25

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.07

.16.27

.27 2.45 2.45..

18.46 s

EU.57

.36

.20. 07

.16

.25.25

.20.29.20

.29 -.16

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.41

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.07

.23

'.18

.09

.11

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.39

.25.11

.18

.09

.07 '.14.07

.09

.07 2.22 2.22 4 SU

.07

.11

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.18

.07

.18.16

.32

.14'

.09

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.14

.14 07

.09.02 2.15 2.15 p

-5

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.72 1.16 ' 82.39.63.59

.57

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.70

.41

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.59 1.20 1.43 ' t 04 1.59 1.31 1.20

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.29 1.38 1.04

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- RS

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.02 '.00

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.66 -.75

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.16

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.00

.00. 00

'.16 77

.07

.02

.07

.61

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.00

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.18

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D.09

.29

.18

.05

.09

.41

.43

.39

.23

.50

.84

.91

.84

.63 6.00 6.00 NU

.07

.00

.07

.05.07

.02.11

.11

.27.02

.14

.18

.14.14

.00

.05 1.43 1.43 8 SU

.00'

.02 00

.02.05

.02

.05

.05.14.18

.27 -.20.20.09

.02.11 1.43 1.43 I

5

.86

.42

.66

.07

.27

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.64

.88

.68

.63

.36

.77 1.00.93.91 9.90 9.90 1SS.34

.14

.18

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.66

.34

.57

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.29.32 5.96 5.96 2 R$

.00-

.00

~.00

. 00

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.00

.05.07

.02

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.00

.00.00

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- ES

.00

.00.30

.00

.00 24.97 D -.05

.07

.00

.07

.32.20

.11

.14

.07

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.39.11 1.56 1.56 1 10 '.02

'.00

.00

.07

.20.16

.02.05.05

.02.02

.61

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1 3 SU

.00 ;.02

.00

.09

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.11..02

.07

.02.05

.50

.50 1 >

I

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.00 00.02

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.61

.34

.32

.14

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4.83 1 SS

.05

.00

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.07

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.00

.07

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- 8 IS

.00

.00. 00.00

.00.00

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.00

.00.00

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.00..00

.00 8.48 1

D

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.07

.05.00

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.00 '.00

.00

.02

.00

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.00

.14

.14 9 SU.00

.00

'.00

.00

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.05

.00

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.16

.16.

I

.02

.00

.18

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.52

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2 $$ ' 00

.00

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.00

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.00

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.00

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p y!0

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, gp,

[

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Ceco DRI23 $71!!05 My December 1989 h

'35 ft. VID SPCD and VIC C1810fl0N

~ 150 35 ft. D1TTUDf!AL TEUEtATU81 SPtp m DIBICTIOR CIES' StillLITY CLASS L

CLASS I'

BNI II : INE I ESI $1 $$1 6 SSV ' SV VSV V,

VW H MV TOTAL IU BU SU 5 SS R$ ES 70!!L IV

.00

.00.00. ~.00

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.00 '.00

.00

.00'.00

.00 00

.00.00 -.00

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.00. 00

.00.00

.00.00.00. 00.00 '.00

.00.00

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.00 2 SU

.00

.00.00.00.00

.00

.00 '.00

.00.00

.00

.00 4 I ' 00

.00

.00 '.00 -.00

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.00.00

.00

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.00

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.00

.00 /.00

.00

.00.00 '.00

.00

.00 - -.00

.00'.00

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.00. 00.00

.00

.00.00

.00

.00 00

.00.00

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, ES '. 00

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.00

.00 00

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t EU

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L 4 $$. 00

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.00

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707 5.37 5.10 6.43 3.69 4.71 7.05 5.23 6.48 6.68 7.45 7.09 4.30 7.70 6.71 7.00 7.00 100.00 13.34 4.62 4.67 31.40 29.66 11.78 4.53 100.00 t

8 10

.75

.72

.39

.11

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.68 1.06

.84

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.25

.27

.14 38.11

.52.36

.48

.41

.32

.39.29.18

.16 4.62 8 $1 '.11

.18

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.23.20

.41

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.66

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.41

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+

- 0 55

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.25. 16

.16

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p o

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'I Met! 0F OBSt4Vifl0N o 4362 SPED 01PiCT100 CLASS

$7A81!,1t! CLASS

. CLASS I-pt It ERE. t: Ist G $51 S SSI $8 VSV V ' #pt ' It Wu TOTAL EU MU SU R NS: 15. 7078L EU

.00

.00 ~.00. 00,.00.00

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.00.00. 02 00.00.00. 00

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I

.07

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.00

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.18

.16

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.07 140 1.60 3 56.05 05 '.05.05:.09

.02.00.02

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.02.02 '.09.02

.71

.71 E:.00

.00

.02

.00. 09.02

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.05.02

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.41

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. 0

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, EU.05 -.00

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4 $U.28

.16

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.07 '.07. 11.11

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I

.09

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.53

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.48.37

,23.28 7.75 7.75

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. 7 SS '.14 :.16

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.23.32

.34.30

.16

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.16

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.07

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.18

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.11

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.11

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t$

.00 -.02

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.09..05.00

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8 80 '.09. 23

.30.25.16

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2.41 I

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.60 1.01

.60

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.76 1.22

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.73.60

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11 SS

.41

.48

.64

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.55.71

.99.53

.64.46

.64

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.00

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.05.09

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.00.18 14

.09

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.25.25 '.21.11 1.60 1.60 y

I 1.01

.66 1.01

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.69

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.85 '.80

.69 11.00 11.00 1 SS '.60.. 21

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' TIS.18

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.73 32.25.48.32 5.43 5.43

!$.07

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9 $U ' 05

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.87

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.28

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4 US

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14.21

{

11

. EU

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v 2H

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3 SS

.00

.02

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.07

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.00 -.00

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, yv

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CICo DtISDD $!ATION -

hir+ December 1989 E

300 ft. IIRD SPID and t!BD D1ttCT!05 -

300 35 ft. D117tttNTIAL TDPt!ATUt!_.

(7

- SPED D!!!CT!05 CLASS STA81L171 CLASS CLASS I'

Ist ut - IRE I ISE $1 SSI 5 SSV St VSV I et ut upt TOTAL EV 80. SU -

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15 70!AL

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.00 -.00

.00.05

.05-

.00

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T0f 5.89 5.52 5.65 5.02 3.58 4.06 6.14 7.04 8.76 9.19 6.90 6.30 6.53 6.19 7.50 5.69100.00

.92 2.29 6.21 43.65 30.74 13.55 2.64 100.00

]

- S IO.28.14

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.07

.00

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.41

.50 2.29

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.57 60

.64

.46 -6.21 4

I 2.75 2.84 3.09 2.89 1.17 1.67 2.27 2.29 3.65 3.53 3.09 2.41 3.28 2.91 3.23 2.57 43.65 r

f SS 1.49 1.12 1.44 1.28 1.26 1.74 1.95 2.57 3.12 3.71 2.41 1,67 1.81 2.02 1.97 1.17 30.74 0 R$ 44

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.99 1.33

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.14

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J

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p.

k CECO DRESDEN E LEAR POWER STATION IETEOROLOGICAL DATA

DATE

....WINDSPEED....

. WIND DIRECTION.... WIND $10MA...

TE9

...DIFF T...

...... DEWPOINT......

PRECIP lfi-DD-YY }N 35 150 -300 35 150 300 35. 150 300 35 150 300 35 150 300 10 9-12-89 1

6.5 13.1 17.8 342 346 347 0

7 5

60.0

.2

.5 55.5 54.3 54.5

.00

'9-12-89 2

4.0' 8.2 11.6.

345 354 357 12 6

4' 58.7

-.3

.7 54.4 53.2 53.5

.00 9-12-89 3 4.3 9.0 13.5 337 350 357 9

-6 3

57.1

.0

.1 53.4 52.2 52.1

.00 g

9-12-89 4

3. 7. ' 8.1 12.4 333' 350 358 7

5 3

55.4

.4

.5 53.0 51.7 51.8

.00 9-12-99 5.

4.7 9.8 13.9 347 354 359 6

4 3

54.1

.1

.3 50.0 49.7 49.5

.00 12-89 6

5. 4

'!!.1-14.9 352 360 4

8 5

3 53.5

.3

.8 47.6 46.3 45.6

.00 9-12-89 7

~ 5. 3 10.3 13.3 353 1

4 8'

4 3

53.6

.6

-1.3 46.4 44.9 44.7

.00 9-12 8 5.3

9. 6 11.6 356 2

7-10 5

5 54.4

.9

-1.8 46.3 ' 44.5 44.3

.00 9-12-89 7.1-13.2 14.4 1

5 7

11 5

4 56.1

-1.2

-2.1 43.5 41.6 ' 41.2 -

.00 9-12-09 10 5.9 10.7 -11.7 20 19 18 13 9

6 58.4

-1.3

-2.4 41.0 39.1 38.8 -

. 00

'9-12-89 11 5.4

8. 8 - 9.3 21-21 20 15 8

9 60.8

-1.1

-2.2-40.1 38.0 37.8 :

.00 s

9-12-89 12 5.7 8.5 9.4 11 10 9

20 16 15 64.3

-1.7

-2.9 38.9 36.7 36.2

. 00 9-12-89013 6.0 0.4 9.0 17 23 24 28 21 20 65.3

-1.3,

-2.7 37.9 35.9 35.2

.00 12-89'14-4.9 7.4 8.2 21.

21 20 21 13 12 65.4

.9

-2.0 37.3-35.0 34.7

.00 9-12-89l 15 4.4 7.9 8.8 9

11 13 19 11 10 65.2

.7

-1.5 39.9. 36.8 36.3 00-9-12-89 16

2. 6' 5.8

7. 4 - - 349

-1 7

9 7

5 64.1

.2-

.7-43.0 30.4 36.3

.00 -

9-12-89 17 3.6 8.1

.10.7 349 356 360 6

2 2

63.4

.1

.3 44.7 ' 41.4

-37.9

.00 12-89,18 2.9 6.4

' 8. 4 33 42 43 26 29 28 62.1'

.2

.2 44.3 43.4 42.0

.00 9-12-89 19 3.9 6.9 8.6 48 56 59 15 10 0

60.9

.0

.6 45.8 43.6 42.2

.00 l

.9-12-89 20

- 2.9 - 5. 3 - 7.5 57 65 66 9

5 4-60.3

.1

.5 43.8 41.5.

40.2-

.00 l

9-12-89'21 2.7- - 6.0 9.3

' 26 35 41 13 14-9 59.3

.4

.2 46.3 43.2-41.2

.00 9-12-89,22 3.7 8.3 11.2 350 359 5

14 11 13 58.5

.3 48.9 46.6 45.6

.00 9-12-89 23-

4. 6 10.5 13.9 13 17 ' 20 12 7

6 57.5

.3

.8 49.4 47.8 47.8

.00-9-12-89 24 5.1 11.2 14.4 9

14 20 9

4 3

56.0

.1

.6 50.8 48.7 48.7

.00 y

TOTAL

.00 2

ML20011F342

Text

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