Text

Corrected Radioactive Effluent & Waste Disposal Semiannual Rept for Jan-June 1989
	ML20005E159
Person / Time
Site:	Dresden
Issue date:	12/15/1989
From:	; COMMONWEALTH EDISON CO.
To:	;
Shared Package
ML20005E149	List: ML20005E148; ML20005E159;
References
	NUDOCS 9001040004
	Download: ML20005E159 (45)
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DRESDEN' NUCLEAR POWER STATION DOCKET NOS. 50-10, 50-237, 50-249L jy

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i 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 1'

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

These limits provide reasonable:

assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area to 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 g

effluent monitoring equipment is not used, i.e., the burning of contaminated oil in the heating boilers, administrative controls are imposed to limit concentration in'the heating boiler stack to less than 10 CFR Part 20 Appendix B, Table l

II, Column 1 and the contribution to overall dose to less than 0.1 percent of the total station annual release. The a

specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the unrestricted area boundary to less than or equal to 500 mrem / year to the total body or to not less than or equal to 3000 mrem / year to the skin. These l

release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to an infant via the cow-milk-infant 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.

I Dose, Noble Gases This Specification is provided to implement the requirements j

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 Section II.3 of Appendix I.

The statemants provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A l

of Appendix I to assure that the releases of radioactive 1

i material in gaseous effluents will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated. The doce calculations established in the ODCM for 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 ZR03/727 1 of 24 9001040004 890630 PDR ADGOK 05000010 R

PDC J

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

j 1.109. " Calculation of Annual Doses to Man from Routine l

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

- Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1. July 1977. The ODCM equations provide for determining the air doses at the unrestricted boundary based upon the historical average atmospheric conditions.

NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111.

Dose, Radiciodines, Radioactive Material in Particulate Form I

and Radionuclides Other than Noble Gases This specification is provided to implement the requirements of Sections II.0, III.A and IV.A of Appendix I, 10 CFR Part j

50.

The Limiting Conditions for Operation are the guides set i

l '

forth in Section II.C of Appendix I.

The statements provide the required operating flexibility and at the same time L

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 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 ODCM calculational methods

- 4 approved b,y NRC for calculating the doses due to the actual release rates of the subject materials are required to be consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man fro.o Routine i

Releases of Reactor Effluents for the Purpose of Evaluating 4

Compliance with 10 CFR Part 50, Appendix I",

Revision 1, October 1977 and Regulatory Guide 1.111. " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977.

These equations also provide for determining the actual doses based upon the historical average atmospheric conditions.

The release rate specifications for radioiodines, radioactive material in particulate form and radionuclides other than noble gases are l

dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which were examined in 1

i l

ZR03/727 2 of 24 r

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

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the development of these specifications weret

1) individual 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 or concentrations of radioactive materials ensures that the system will be available for use whenever gaseous effluents require treatment prior to release to the environnent. The requirement that the appropriate portions of this system be operablo when specified provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as reasonably achievable". This specification implements the requirements of 10 CFR Part 50.36a, General Design criterion 60 of Appendix A to 10 CFR Part 50, and design objective Section II.D of Appendix I to 10 CFR Part 50.

Explosive Gas Mixture This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the off gas system is minimized in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.

LIOUID EFFLUENTS Concentration 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 specified in 10 CFR Part 20, Appendix B.

Table II, Column 2.

The concentration limit for noble gases, MPC in air (submersion), was converted to an equivalent concentration in water using the International Commission on Radiological Protection (ICRP) Lublication 2.

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.

ZR03/727 3 of 24 1

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DRESDEN NUCLEAR POWER STATION DOCKET NOS. 50-10, 50-237, 50-249 1

Th) Liniting Condition for Operation inplements th] guid s set forth in Section II.A of Appendix 2.

The statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive i

material in liquid effluents will be kept "as low as j

reasonably achievable". The dose calculations in the ODCM i

implement the requirements in Section III.A of Appendix I l

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 f.

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 Ef fluents f rom Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I", April 1977. NUREG-0113 provides methods for done calculstions 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 i

of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as reasonabir 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 Vacuum 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.

1 l

ZR03/727 4 of 24

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

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

2.

The concentration limit for noble gases MPC in air (submersion), was converted to an equivalent concentration in water using the Irternational Conur.ission on Radiological Protection (ICRP) Publication 2.

MAXIMUM PERMISSIBLE CONCENTRATION OF DISSOLVED OR ENTRAINED NOBLE CASES RELEASED FROM THESITEgoggSgIgEDAREAS NUCLIDE MPC(uci/ml)*

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

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

adjusted for infinite cloud submersion in water, and R = 0.0. rem / week, density = 1.0 g/cc abd Pw/Pt = 1.0.

ZR03/727 5 of 24

DRESDEN NUCLEAR POWER STATION DOCKET NOS. 50-10, 50-237, 50-249 AVERAGE ENERGY The average energy of fission and activation gases was calculated for the i

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

i i

in = 2.60E-01 MeV/ dis E = 3.02E-01 MeV/ dis B

ZR03/727 6 of 24

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t DRESDEK NUCLEAR POWER STATION DOCKET NOS. 50-10, 50-237, 50-249 i

MEASUREMENTS AND APPROXIMATIONS A.

Fission and activation gasest The D-1 chimney, D2/3 chimney and D2/3 Reactor Vent are sampled weekly via a grab sample.

The samples are analyzed for specific isotopes present in the release using a Hyper-Pure Germanium (HP Ge) Spectrometry System. Tritium is sampled monthly via a grab sample on the D-1 chimney, D2/3 Chimney, and D2/3 Reactor vent and analyzed using a Liquid Scintillation Counter.

Krypton-85 is estimated in the D2/3 chimney using a recoil or non-recoil calculation using the fission per second plot and the sum of Kr-85m, Kr-87, Kr-88, Xe-133, Xe-135, and Xe 138 activities present in Reactor Off-Gas.

B.

Iodine and Particulate:

Iodine and particulate samples from the D-1 Chimney, D2/3 Chimney and the D2/3 Reactor Vents are collected for a maximum seven day period. These samples are analyzed for specific nuclides present in the release using a HP Ge spectrometry system.

When iodine or particulate samples e.re 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 Gross 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 Ge spectrometry system. A composite of all batches for the month is sent to a vendor to be analyzed for Sr-89, Sr-90, Fe-55, H-3, and Gross Alpha activity. A sample of each Low Pressure Coolant Injection (LPCI) system is analyzed each month for specific isotopes present in the release using a HP Ge spectrometry system..A sample of each LPCI 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 Errorst The methods used for estimating

(

overall errors associated with radioactivity measurements vary with 1-discharge path and form of isotopes.

Factors that contribute to the error include such items as calibration of counting equipment, counting statistics, sampling error, discharge volume, and flow rate monitors.

E.

_ Estimation of Vendor Analyzed Information:

The vendor analyzed data for Sr-89, Sr-90, Fe-55, H-3, and Gross Alpha was previously projected, where applicable, for the months of May and June using April data.

The vendor analyzed liquid radwaste composite sample for May was lost due to personnel error, DVR 12-2/3-89-88 and LER 89-017-0.

The activity levels for April were used to estimate the release for May. The data in this corrected Effluent Report reflects final vendor analyzed information.

ZR03/727 7 ef 24 l

1 DRESDEN NUCLEAR POWER STATION.

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT i

_ January._ Through __ h ae 1982 1

[

GASEOUS EFFLUENTS Docket Numbers: 50-10 l

50-237 SUMMATION OF ALL RELEASES 50-249 EST. TOTAL UNIT lai QUARTER 2nd QUARTER ERROR,%

I I

A.

FISSION AND ACTIVATION CASES 1.

Total Release ci 1.54 E01 7.46 E00 7.31 l

2.

Average Release Rate for Period uCi/sec 1.98 E00 9.49 E-01 3.

Percent of Technical Specification Limit A

A i

B.

10 DINES 1.

Total Iodine-131 Ci 8.86 E-04 1.01 E-03 9.51 l

l 2.

Average Release Rate of I-131 for Period uCi/sec 1.14 E-04 1.28 E-04 3.

Percent of Technical Specification Limit A

A 4.

Total Iodine-131, Iodine-133,and Iodine-135 Ci 1.20 E-02 1.65 t-02 C.

. PARIZCUlAIES

.1.

Particulates with half-lives > 8 days Ci 5.53 E-01 5.16 E-01 8.09 l 2.

Average Release Rate for Period uC1/sec 7.11 E-02 6.56 E-02 3.

Percent of Technical Specification Limit A

A 4.

Gross Alpha Radioactivity Ci MDL MDL e

D2-TRITIUM 1.

Total Release C1 3.12 E00 3.97 E00 7.89 l 2.

Average Release Rate for Period uC1/sec 4.01 E-01 5.05 E-01 3.

Percent of Technical Specification Limit A

A

.A Tha information is contained in the Radiological Impact on Man section of the r: port.

Total airborne release data is provided which includes fission and cctivation gases, iodines, particulates, and tritium.

ZR03/727 8 of 24

DRESDEN NUCLEAR POWER STATION

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EFFLUENT AND WASTE DISPOSAL SEM1 ANNUAL REPORT l

January--__ Thr^ ugh June 19E2 D1 Chimney GASEOUS EFFLUENTS GROUND LEVEL RELEASES Docket Number 50-10 SEMI-ELEVATED RELEASES xx ELEVATED RELEASES i

CONIINUOUS MQDE BATCH MODE I

NUCLIDES RELEASED UNIT is_t QUARTER 2nd QUARTER lal QUARTER 2nd QUARTER FJESION GASES Ci Xe-138

_Ci Xe-135m Ci Kr-87 01 Kr-88 Ci Kr-85m Ci Kr-85 Ci Xe-135

_Ci_

Xe-133 Ci Otherst

__ Ci

_Ci_

TQIAL

_.C i _

None None 10 DINES I-131 C1.

Ci I-133 I-135 Ci TQJAL Ci None None PAR *IlCIL14.TES Sr-89

_Ci,_

Sr-90 Ci Cr-51 Ci Mn-54 C1 9.44 E-Of 2.82 E-06 00-58 01 Fe 59 Ci Co-60

_Ci_

1.64 E-05 1.77 E-06 2r-95

.Ci.

Nb-95 Ci Ru-103 C1 i

Ag-110m 01_

Sb-124 Ci-I-131 Ci Cs-134 C1 Cs-136 C i -_

Cs-137 C1 1.55 E-05 2.25 E-05 Ba-140 Ci Ce-1_41

_C1_

Ce-144 Ci 2n 65 Ji._

Ba-133

_Ci_

Sb-L25

_Ci_

Others:

Ci

_Ci_

_CL 01

_C1_

TOTAL 01 4.13 E-05 2.71 E-05 None Nope

See Table for MDL of Each Nuclide l

ZR03/727

p DRESDEN NUCLEAR POWER STATION i

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REP 0kT-i o

_ January Thr; ugh June 1982 i

i Docket Number 50-10 TABLE OF MINIMUM DETECTABLE LEVELS L

FOR GASEQUS EFFLUENTS D1 Chimney GASEOUS EFFLUENTS AVERAGE FLOW _10 000 efm MDL (uCi/cc)

% OF TIME < MDL 1.

FISSION GASES i

Xe-138 4.16 E-08 100.0 Xe-135m 1.29 E-07 100.0 Kr-87 3.03 E-08 100.0 Kr-88 5.21 E-08 100.0 t

Kr-85m 1.78 E-08 100.0 Kr-85 4.43 E-06 100.0 Xe-135 1.52 E-08 100.0 j

Xe-133 4.32 E-08 100.0

]

Others:

2.

10 DINES

'I-131 5.34 E-14 100.0 1-133 5.57 E.14 100.0 1-135 1.19 E-13 100.0

3. -PARTICULATES Sr-89 3.1 E-11 100.0 Sr-90 6.9 E-12 100.0 Cr-51 4.20 E-13 100.0 Mn-54 5.27 E-14 43.6 Co-58 4.83 E-14 100.0 Fe-59 7.58 E-14 100.0 co-60 1.26 E-13 30.4 Zr-95 9.09 E-14 100.0 Nb-95 4.96 E-14 100.0 Ru-103 4.95 E-14 100.0 Ag-110m 5.12 E-14 100.0 Sb-124 5.86 E-14 100.0 I-131 5.15 E-14 100.0 0s-134 5.73 E-14 100.0 Cs-136 5.49 E-14 100.0 Cs-137 6.21 E-14 42,0 Ba-140 1.91 E-13 100.0 Ce-141 7.64 E-14 100.0 Ce-144 3.27 E-13 100.0 Zu-65 9.03 E-14 100.0 Ba-133 6.93 E-14 100.0 Sb-125 1.39 E-13 100.0 Others:

Gross Alpha 9.4 E-12 100.0 4.

TRITIUM H-3 5.84 E-07 0

ZR03/727 10 of 24

DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

_. January _._ Thr; ugh Junt_._ 1933 D2/3 Chimnev GASEOUS EFFLUENTS GROUND LEVEL RELEASES Docket Numbers: 50-237 SEMI-ELEVATED RELEASES 50-249 xx ELEVATED RELEASES CONTINEDUS_NO.DE BAICH MODE NUCLIDES RELEASED UNIT 1s1 QUARTER 2nd QUARTER 131 QUARTER 2nd QUARTER

...... FISSION CASES

_CL Xe-13fL Ci

____ Xe-135m

_Ci._

1.49 E00 Kr-87 Ci Kr-88 Ci Kt-85m Ci Kt-85 01 2.91 E-03 2.86.E-03 Xe-135

_Ci 1.38 E01 6.42_E00 Xe-133 Ci

_.... Others t Ci_

Cl TDIAL C1 1.53 E01 6 42 E00 None None 10 DINES I-131 C1 7.49 E-04 6.43 E-04 1-133 01 3.78 E-03 3.92 E-03 1-135 Ci 5.87 E-03 5.87 E-03 TOIAL C1 1.04 E-02 1.04 E-02 None None PARTICULATES Sr-89 C1 4.77 E-01 4.61 E-01 Sr-90 01 5.17 E-04 1.32 E-03 Cr -51 Ci Mn-54 Ci 6.52 E-05 6.28 E-05 00-58 Ci Fe-59 C1 Co-60

_.Qi_

1.67 E-04 1.94 E-04 Zr-95 C1 Nb-95 Ci Ru-103 Ci An-110m Ci Sb-124 Ci I-131 Ci 7.64 E-05 6.24 E-05 Cs-134 Ci Cs-136 Ci Cs-137 Ci 3.14 E-05 7.73 E-06 Ba-140 01 6.77 E-04 6.51 E-04 Ce-141 Ci Ce-144 Ci Zn-65 Ci Ba-133

_Ci_

Sb-125 Ci Others:

_Ci Ci

_Ci_

_CL

. C1-TOTAL C1 4.79 E-01 4.63 E-01 None None

See Table for MDL of Each Nuclide ZR03/727 11 of 24

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DRESDEN NUCLEAR POWER STATION i

January Thr ugh June._ 19M Dock;t Numb;rs:

50-237 j

TABLE OF MINIMUM DETECTABLE LEVELS 50-249 f

FOR GASEOUS EFFLUENTS AVERAGE F g2nd atr 289at__qtt_212__ Kcfm D2/3 Chimacy_ GASEOUS EFFLUENTS Kcfm MDL (uci/cc) 1 0F TIME < MD.L 1.

FISSION GASES Xe-138 4.16 E-08 100.0 Xe-135m 1.29 E-07 98.9 Kr-87 3.03 E-08 100.0 Kr-88 5.21 E-08 100.0 Kr-85m 1.78 E-08 100.0

-Kr-85 4.43 E-06 0

Xe-135 1.52 E-08 43.1 Xe-133 4.32 E-08 100.0 Others:

'2.

10 DINES I-131 5.34 E-14 0.552 I-133 5.57 E-14 0

I-135 1.19 E-13 15.5 3.

PARTICULATES Sr-89 3.1 E-11 0

Sr-90 6.9 E-12 50.3 Cr-51 4.20 E-13 100.0 Mn-54 5.27 E-14 7.73 00-58 4.83 E-14 100.0 Fe-59 7.58 E-14 100.0 Co-60 1.26 E-13 8.29 Zr-95 9.09 E-14 100.0 Nb-95 4.96 E-14 100.0 Ru-103 4.95 E-14 100.0 Ag-110m 5.12 E-14 100.0 Sb-124 5.86 E-14 100.0 I-131 5.15 E-14 19.9 Cs-134 5.73 E-14 100.0 Cs-136 5.49 E-14 100.0 Cs-137 6.21 E-14 43.6 Ba-140 1.91 E-13 1.66 Ce-141 7.64 E-14 100.0 Ce-144 3.27 E-13 100.0 Zn-65 9.03 E-14 100.0 Ba-133 6.93 E-14 100.0 Sb-125 1.39 E-13 100.0 Others:

Gross Alpha 9.4 E-12 100.0 4.

TRITIUM H-3 5.84 E-07 0

ZR03/727 12 of 24

DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT i

_lanuary.__ Through June _ 1982 D2/3 Reactor Buildine Vent GASEOUS EFFLUENTS GROUND LEVEL RELEASES Docket Numbers: 50-237 xx SEMI-ELEVATED RELEASES 50-249 ELEVATED RELEASES CDNTlHUDUE_fiODE BATCH MODE NUCLIDES RELEASED UNIT isi QUARTER lad QUARTER 1s1 QUARTER 2nd QUARTER FISSION. GASES __C1 Xe-138 C1 Xe.:135m

_CL Kr-87 Ci_

Kr-8B Ci Kr-85m Ci Kr -85 Ci Xe-135 Ci_

8.64 E-02 1.0!LJ00 Xe-133 CL Otherst Ci_

Ci TQIAL Ci 8.64 E-02 1.04 E00 None None 10D.INES 1-131 Ji 5.18 E-05 2.60 E-04 I-133 C1 1.05 E-04 2.12 E-03 I-135 C1 1.34 E-03 3d8 E-03 TOTAL

_Ci 1.50 E-03 5.96 E-03 Nope None PARTICULATES Sr-89 Ci 6.98 E-Q2 3.88 E-02 Sr-90 01 7.50 E-04 1.39 E-03 Cr_51

_01_

6.h3 E-04 4.42 E-03 Mn-54

_C1 4 87 E-04 1.55 E-03 C0-5.8

_C L 6.54 E-05 7.18 E-04 Fe-59 Ci 6.69 E-05 8.80 E-04 Co _ft0 01 1.80 E-03 5.07 E-03 Zr-93

_Ci_

Nb.25

_Ci_

Ru-103 Ci-An-110m

_C1 6.74 E-06 4.11 E-05 Sb-124 CL I-131

_Ci_

9.39 E-06 4.6tt E-05 Cs -13_4

_C.L Cs-136 Ci Cs-137

_Ci__

1.43 E-05 Ba-140 C1_

__ 2.49.E-05 1.61 E-04 Ch141 Ci Ce-144 Ci Zn-65 C1 1.68 E-05 1.78 E-04 Ba-ll3

_CJ_

Sh-125 Ci Otllers :

_Ci_

JL 1

11 TOTAL

_C1 7.37 E-02 5.33 E-02 None None

See Table for MDL of Each Nuclide ZR03/727 13 of 24

DRESDEN NUCLEAR POWER STATION January Through June 19M Dockst Numb;rst 50-237 TABLE OF MINIMUM DETECTABLE LEVELS 50-240 i

.FOR GASEOUS EFFLUENTS D2:

110 Kcfm AVERAGE FLOW p3, tio

gef, D2/3 Reactor Building Vent GASEOUS EFFLUENTS MDL (uCi/cc) 1 0F TIME < MDL 1.

FISSION GASES X;-138 4.16 E-08 100.0 X;-135m 1.29 E-07 100.0 Kr-87 3.03 E-08 100.0 Kr-88 5.21 E-08 100.0 Kr-85m 1.78 E-08 100.0 Kr-85 4.43 E-06 100.0 X;-135 1.52 E-08 87.3 X;-133 4.32 E-08 100.0 Others:

2.

10 DINES I-131 5.34 E-14 3.31 1-133 5.57 E-14 3.31 I-135 1.19 E-13 60.8 3.

PARTICULATES Sr-89 3.1 E-11 0

Sr-90 6.9 E-12 50.3 Cr-51 4.20 E-13 32.0 Mn-54 5.27 E-14 0

co-58 4.83 E-14 24.9 F;-59 7.58 E-14 26.0 00-60 1.26 E-13 0

Zr-95 9.09 E-14 100.0 Nb-95 4.96 E-14 100.0 Ru-103 4.95 E-14 100.0 Ag-110m 5.12 E-14 61.9 Sb-124 5.86 E-14 61.9 I-131 5.15 E-14 44.8 0s-134 5.73 E-14 100.0 Cs-136 5.49 E-14 100.0 Cs-137 6.21 E-14 53.0 B;-140 1.91 E-13 37.6 02-141 7.64 E-14 100.0 Cs-144 3.27 E-13 100.0 Zn-65 9.03 E-14 47.0 B:-133 6.93 E-14 100.0 Sb-125 1.39 E-13 100.0 Others:

Gross Alpha 9.4 E-12 100.0 4.

TRITIUM H-3 5.84 E-07 0

ZR03/727 14 of 24

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DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

_. January _ Thr; ugh June 19fL9 D2 Isolation Condensn CASEQUS EFFLUENTS xx CROUND LEVEL RELEASES Docket Numbers: 50-237 SEMI-ELEVATED RELEASES ELEVATED RELEASES CONTINUOUS MODE BATCH MODE UCLIDES RELEASED UNIT 131 QUARTER 2nd QUARTER 1si QUARTER 2nd QUARTER FIS.SION_GASEE_ _C1_

Xe-138 Ci Xe-135m Ci Kr-87 Ci i

Er-88 Ci Kr-85m Ci-Kr-85 Ci Xe-135 Ci Xe-133 C1 Others:

Ci Ci TOTAL 01 None None None 10 DINES I-131

_ Ji_

I-133

.. C L I-135 Ci TQIAL

_Ci_

None None None PARI.ICULATES Sr-89 Ci Sr-90 Ci Cr-51 Ci Mn-54 C1 2.32 E-06 Co-58 Ci Fe-59 C1 Co-60 C1 2.86 E-06 2r-95 Ci Nb-95 Ci Ru-103 Ci Ag-110m

_Ci Sb-124

_Ci I-131 Ci Ca:134 li_

Os-136 C1 Cs-137 Ci Ba-140 Ci Cc-141 C1 Ce-12.4 C1 t

Zn-65 Ci Ba-133 Ji_

Sh_-125

_C.i_

Otherst C1 C1 C1 TOIAL Ci None None 5.18 E-06 Non.e

See Table for MDL of Each Nuclide ZR03/727 15 of 24

W; DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

,_Januarv Through June 1982 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES Docket Numbers: 50-10 50-237 i

50-249 4

F EST. TOTAL UNIT 131 QUARTER 2nd QUARTER ERROR,%

AdlSSIOR_AND ACTIVATION PRODUCTS

1. Total Release Ci 3.25 E-01 1.19 E-01 5.58 (not incl. tritium, gases, alpha)

2. Average Diluted Conc. During Period uCi/mL 6.12 E-08 7.93 E-09

3. Percent of Applicable Limit A

A A d B1 TIUM

1. Total Release C1 4.05 E00 4.70 E00 7.75 l

2. Average Diluted Conc. During Period uCi/mL 7.63 E-07 3.13 E-07

3. Percent of Applicable Limit A

A C.

DISS.01VID_AND_ ENTRAINED GASES

1. Total Release C1 1.07 E-04 1.29 E-04 5.58 l

2. Average Diluted Conc. During Period uCi/mL 3.20 E-11 8.60 E-12

3. Percent of Applicable Limit A

A D.

GAOSS._ALMIA_ RAD 10ACILVITY

1. Total Release Ci 4.61 E-03 3.56 E-03 15.1 l

E.

VOLUME OF WASTE RELEASED (prior to dilution) liters 7.95 E06 6.39 E06 5.00 l

l F.

VOLUME OF DILUTION WATER USED DURING PERIOD liters 5.31 E09 1.50 E10 5.00 l

A Tha 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.

ZR03/727 16 of 24

DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

._Janua ry Through June 191L9 Rady_agle LIQUID EFFLUENTS Docket Numbers: 50-10 50-237 1.

Number of Batch Releases: 157 50-249 2.

Total Time Period for Batch Releases: 48,335 min 3.

Maximum Time Period for a Batch Relesse 403 min 4.

Average Time Period for Batch Releases: 308 min 5.

Minimum Time Period for a Batch Release: 190 min

+

6.

Average Stream Flow During Periods of Release of Effluent into a Flowing Stream: 4.16 E05 L/ min CONIINU0VS3 0DE BA7CILMODE

'NUCLIDES RELEASED UNIT 1s1 QUARTER 2nd QUARTER lal QUARTER 2nd QUARTER SI-19

_Di St-9.0

_.01_.

3.70 E-04 6 32 E-05 Ar-41 Ci Mn-54

-Ci 5.91 E-02 3.67 E-02 0o-58

_Ci 1.87 E-03 1.45 E-04 Fe-59

_C1_

6 0h_E-03 1.09 E-03 i

Co-60 C1 1.66 E-01 6.53 E-02 2n-65

_ Ci 5.30 E-05 Ru-103

_Ci Sb-122

. Ci

___Sb-124

.C 1._

7 03 E-02

___3 33_E-05_

I-131 Ci I-133

_21_

1-135 Ci 3.80 E-05 Ceda.4 CL

____2 d1_E-05 Cad 37

._Ci_

1.15 E-02 1.06 E-02 Ba-140 Ci La-140 C1 Ce-141 01 o.thers1_Cr-51_ _Ci._

1.47 E-Q3 1 4.Z_E-04 Fe-55 C1 3.32 E-03 5.52 E-03 Rb-88 Ci 2.62 E-04 Nb-95 C1 1.11 E-05 Tc-99m _Ci_

6 52 I.0ft_.

As._71_ _C1 3.31 1-05 Cs-13]L_ Ci_

9d9 E-06 Hf-181 C1 1.27 E-05 (above) 101Al_EDI_Ecriod___ Ji_

NONE NORE

__3220 E-01 1,19 E-01 Xe-133 Ci 7.87 E-05 3.47 E-05 Xe-1.35

_01 9.10 E_Q5 7 49_I-05 Gr-88 Ci

_,L ]_4 E-05

See Table for MDL of Each Nuclide ZR03/727 17 of 24

m-I DRESDEN NUCLEAR POWER STATION t

_ January ___ Through June 19M a

TABLE OF MINIMUM DETECTABLE LEVELS Docket Numberst FOR LIQUID EFFLUENTS 50-10 50-237 i

50-249 i

1

__Radrasp LIQUID EFFLUENTS TOTAL GALLONS RELEASED _3 40 EQ6 tiDL (uC1/mL) 1 0F GALLONS c MDL I

Sr-89 1.5 E-08 100.0 Sr-90 4.3 E-08 15.3 Ar-41 2.71 E-08 100.0

-8

4. 8 E 08 7.0

[-

F;-59 8.11 E-08 38.6 C -60 1.18 E-07 0

2n-65 9.97 E-08 99.4 Ru-103 6.04 E-08 100.0 Sb-122 7.31 E-08 100.0 Sb-124 4.87 E-08 86.1 1-131 5.62 E-08 100.0 1-133 5.34 E-08 100.0 I-135 9.15 E-08 99.4 09-134 5.51 E-08 99.4 Cs-137 4.04 E-08 1.99 B:-140 2.11 E-07 100.0

.La-140 3.82 E-08 100.0 02-141 9.33 E-08 100.0 X;-133 1.53 E-07 96.9 Xa-135 5.13 E-08 94.5 Cr-51 4.81 E-07 100.0 1

F;-55 5.2 E-07 35.6 Nb-95 Not Determined 99.4 Kr-88 1.71 E-07 99.4 Hf-181 Not Determined 99.4 l

Cs-138 Not Determined 99.4 Tc-99m 4.63 E-08 99.1 l

As-76 Not Determined 98.6 Rb-88 Not Determined 99.4 H-3 4.1 E-06 0

Gross Alpha 1.7 E-08 0

ZR03/727

DRECDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SD41 ANNUAL REPORT

.. January Through June 1982 i.

Containment Cooling Servlet_ Waler LIQUID EFFLUENTS Docket Numbers: 50-237 50-249 1.

Number of Batch Releases: 89 2.

Total Time Period for Batch Releases:

110 min 3.

Maximum Time Period for a Batch Release: 1.24 min 4.

Average Time Period for Batch Releases: 1.24 min 5.

Minimum Time Period for a Batch Release: 1.24 min 6.

Average Stream Flow During Periods of Release of Effluent into a Flowing Stream:

2.38 E06 L/ min CONIINUQUS_tiODE BAIClLMODE NUCLIDES RELEASED UNIT 1s1 QUARTER 2nd QUARTER lit QUARTER 2nd QUARTER Sr-89 Ci Sr-90

_C1_

Ar-41 Ci Mn-54 Ci_

8,20 E-07 2.95 E-05 0o-58 C1 F;-59

__ C L Co-60 01 1.52 E-05 1.29 E-04 2n-65 Ci Ru-103 Ci Sb-122 Ci Sbd2.4

_C1 I-131 C1 I-133 Ci I-135 Ji_

Cs-134

. Ci..

__.l.42_E-07 3.65 E-05__

l Cs-137 C1 9.36 E-06 9.18 E-05 Ba-140

_Ci Ln-160 01 Ce-141

._Ci_

Others: Cr-51 Ci Fe-55 Ci

.CL-Ci (above)

Iolal_Enr Period

_Cl__

None None_

2.58 E-05 2.87 E-ot_._

t

.___.Kc-113

_CL-xe-131 C1

See Table for MDL of Each Nuclide l

l ZR03/727 19 of 24

t DRESDEN NUCLEAR POWER STATION

+

January Through.

J uge.___ 1982 7

TABLE OF MINIMUM DETECTABLE LEVELS Docket Numbersi FOR LIQUID EFFLUENTS 50-237 50-249 r

. Containment _ Cooling Service Water LIQUID EFFLUENTS TOTAL GALLONS RELEASED _3286 E05 MDL (uci/ml.)

1 0F CA1.1ONE < MDL Sr-89 1.5 E-07 100.0

[

f Sr-90.

4.3 E-08 100.0 Ar-41 2.71 E-08 100.0 1

f Mn-54 5.04 E-08 69.7.

00-58 4.98 E-08 100.0 Fe-59 8.11 E 100.0 l

00-60 l'.18 E-07 0

I Zn-65 9.97 E-08 100.0 r

Ru-103 6.04 E-08 100.0 Sb-122 7.31 E-08 100.0 I

Sb-124 4.87 E 100.0 1-131 5.62 E-08 100.0 l

I-133' 5.34 E-08 100.0 I-135 9.15 E-08 100.0 Cs-134-5.51 E-08 87.6 Cs-137 4.04 E-08 29.2 i

Ba-140 2.11 E-07 100.0 La-140 3.82 E-08 100.0 Ce-141 9.33 E-08 100.0

'Xe-133 1.53 E-07 100.0 Xe-135 5.13 E-08 100.0 Cr-51 4.81 E-07 100.0 Fe-55 5.2 E-07 100.0 H 4.1 E-06 56.2 Gross Alpha' 1.7 E-08 0

- ZR03/727 20 of 24

DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

_ January Through June 1982 Docket Numberst 50-10 SOLID WASTE AND IRRADIATED FUEL SilIPMENTS 50-237 50-249 Est Tot.

A2_ SOLID _HASIE SHIPPED OFFSIIE FOR BURIAL OR DlREQSAL (NOT IRRADIATED FUEL)

Error.1

1. Type of Waste Unit 6-month period t

m3 3.08 E02 a.

Spent resins, filter sludges, evaporator bottoms, etc.

1.60 E03 C i_.

13,4 3

m 1.15 E03 b.

Dry compressible waste, contaminated equip., etc.

Ci 2.39 E01 16.6 3

m o

c.

Irradiated components, control rods, etc.

Ci 0

3 m

0 d.

Other (describe)

Ci 0

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

Co-60 67.2 1 1.08 E03 Fe-55 18.9 %

3.02 EQ2_

Mn-54 12.1 %

1.94 EQZ_

Ninfi3 0 805% _1.12 E0L 1

Other 0.995%

1.59 E01_

b.

Co-60 26.6 %

6.36 E00-Fe-55 G l__%

1.51 EQL Mn-54 7.31..% 191_E00_

Ca:137 0.981%

2.34 E-Q1 Qiher 1.329%

3.18 E-01

3. Solid Waste Disposition NMEEB_QE_Si!IMENIS tiQDLDLIIWiSEDRIAIl0E DESIINAIl0N 43 Motor freight (exclusive use only)

Barnwell, SC 12 Motor freight (exclusive use only)

Richland, WA 9

Motor freight (exclusive use only)

SEG, Oak Ridge, TN 6

Motor freight (exclusive use only)

Westinghouse DDR Madison, PA 5

Motor freight (exclusive use only)

CNSI, Channahon, IL B.

IRRADIATED FUEL SilIPMENTS (Disposition)

NWHEILQE SilIPMENIS MODE _0LIRANS10ATAIl0B DESIINA110N None ZR03/727 21 of 24

DRESDEN NUCLEAR POWER STATION l

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL ~ REPORT r

3..

,_Januarv Through June 1931 Docket Numbers:

lt 50-10

~

ABNORMAL RELEASES 50-237 50-249 l

A.

LIQUID

+

1.

Number of Releases: One on 25 March 89. LER 89-1-050249.

i Contaminated demineralized water was used for makeup water to the Isolation condenser to cool the Unit 3 reactor cubsequent to a reactor scram.

j 2.

Total Activity Released: Nuclide

__As11rity (ci)

Mn - 54 1.76 E-03 Co - 58 1.82 E-05 c

5: : 28 1;ttI:81 s

Total 5.47 E-03 i

t B,

GASEOUS 1.

Number of Releases: One on 4 March 89. LER 89-12-050237 Contaminated demineralized water was used for makeup water to the Isolation Condenser to cool the Unit 2 reactor subsequent to a reactor scram.

2.

Total Activity Released: Nuclide

_. Activity (C1.1 U":28 1:llE:82 Total 5.18 E-06 i

c 1

ZR03/727 22 of 24 1

n..

i..',

.;j f.'

i-DRESDEN NUCLEAR POWER STATION DOCKET NOS. 50-10, 50-237, 50-249 RADIOLOGICAL IMPACT ON MAN l

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w IVEV ANNUAL EEfOE1 MAXIhuh DCRES RESULTING F E. 0 M A2r' BORNE RELEAEEh LPERIOD OF RELEASE -- 01/01180 TO 12 / 31/ E i' CALCULATED 1 ;' ' i ? /ij 9 ADULT F,ECEPTOR

-t 1 t' J

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,r TYF E QUARTER QUARTER CUARTER DUAF7Eh A N N u c,L JAN-MAR APR-JUN JUL -5 ET OL1 DEC CAMMA AIR 0.00E400 0.00E400 0.00E400 0.v3E400 0.00E+00 (MRAD)

(-

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BET 6 AIR 0.00EtOO 0.00E+00 0.00E+00 0.00Et00 0.0M 4'M (MRAD)

(

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(

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LIVER LIVEF LIVER GI-LLI LIVER THIS IS A REFORT FOR THE CALENDAR YEAR 17 S i' COMPLIANCE STATUS e

20 EFR 50 6PP. 1 ADULT RECEFlDR 7,

OF r.P P OIRLY

.1 S T QTR OND 01R 3 R 's OT' 4TH OTF YRLY

% DF 0FJ JAN-MAh A F R - J U :'

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i.00 TOT.-_' BODY < MREM) 2.5 0.M 0.

v 0.00 0.

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J.00 0,00 0.00 IS.C 0,00 DRGAN (MREMi

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L: JE:

LIVER 51 - L ! I LIVER R ':00 LIB tASED UFON uDCM CEVISION 11 m c=w E B R u h r, '-

" i s, Lm

awm

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DRESDEN UNIT TUO 1909 ANNUAL f6 PORT MAXIMUM DDEES REEULTING riDM A]RFORNE RF t. E AS E S PERIOD OF RELEASE - 01/01/09 TO 1:31/89 EALCULATED 1?/19/97 INFANT REEEPTOR iLT 2ND

?FD ATH TYPE QUARTER QUARTER O UM:T E R DUnRTER ANNUAL JAN-MAR AFR-JUN JUL -SEP OC1-0EC GAMMA AIR 1.10E-05 1.02E-04 1. 1;S E - 0 6 3.00E-05 1.45E 04 (MRAD)

(t!E

)

(!f E

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(NE

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(NE

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-BETA AIP

'.97E-06 2.47E-04 3.01E-07

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(N

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(NNE )

(N

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(N

)

(NNE )

TOT. 10DY 5.12E-OL 4.26E-OL 7.79E+07

1. 3 0 F -- 0 5 6.11E-05 (MREM)

(NE

)

(NE

)

(NE

)

(N2

)

(NE

)

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(NE

)

(NNE )

(NE

)

(NE

)

(NNE )

ORGAN 1.50E-02 3.19E-02 1 03E-02 3.99F-03 6.00E-02 (MREM)

(NNE )

LUND LUNG THYROID THYROID LUNG THIS IS A REF ORT FOR THE CALENDAR YEAR 1989 COMPLIANCE STATUS - 10 CFR 50 APP. I INFANT RECEPTOR g7 gp 7,

OTRLY IST OTR 2ND GTR 3RD OTR 4TH QTR YRLY

. OF DDJ JAN-MAR APR-JUN JUL-SEF OCl-NOV 01: J APP.1 GAV.MA AIR (MRAD) 5."

0.00 0.00 0.00 0.00 10.0 0.00 LETA AIR (MRAD) 10.0 0.00 0.00

.00 0.00 70,0 0.00 TOT. BODY (hEEM) 2.5

1.00 0.00 0.v; 0. :"!

E.0 0.00 SNIN (MREM) 7.5 0,00 s.00 0.00 0.00 15.0 0.00 ORGAN (MREM) 74 5 0.20

..q7 0.11 0,05 lb.0 o.41 LUNG LUNO THYP01D 1HYRDID LUND

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DRESDEN UNIT TUO

[

1909 ANNUAL REPORT

~ '

MAXIMUM DDCEF RESULTING FROM AIRBORNE RELEASES PERIOD OF RELEACE 01/01/09 TO 12/31/89 CALCULATED 1?/19/09 ADULT RECEPTDR IST 2ND 3RD 41H TYPE QUARTER GUARTER GUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEF OCT-DEC GAMMA AIR 1.18E-0D 1,02E-04 1.83E-Oe 3.00E-05 1.45E-04 (MRAD)

(NE

)

(NE

)

(NE

)

(NE

)

(NE

)

PETA AIR 1.97E-06 2.47E-Oi 3.91E-07 5.17E-06

..0SE 01 (MRAD)

(N

)

(NNE )

(N

)

(N

)

(NNE )

TOT. BODY

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-4.26E-03 7.79E-0?

1.30E-05 6.loE-CD (MREM)

(NE

)

(NE

)

(NE

)

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)

(NE

)

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)

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ORGAN 1.50E-02 1.64E-01 1.13E-02 4.50E-03 1.91E-01 (MREM)

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(HNE )

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LUNG FONE 1 H'r R O I D THYRDID BONE THIS IS A f:E P OR T FOR THE C AL ENDAR YEAR 1999 CohPLIANCE STATUS - 10 CFR 50 AFP. I ADULT RECEPTOR OF APP 1.

QTFLY iST DTR 2ND Q1R 3RD QiR

'TH 07R YRLY 1.

OF DBJ JAN-MAR

(: P R - J U N JUL.-SEP OCT-NOV OBJ APP.I GAMMA AIR (MRAD) 5.0 0.00 0.00 0.0C D.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. 03 15.0 0.00 ORGAN ( M f:E M )

7.5 0.20 2.19 0.15 0.06 15.0 1.27 LUNG FONE THYRDID 1HYROID BONE REEUL75 BAEED UFON ODEM REVISION 11 UPDATE CS20'

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DRESDEN UNil TWO INFANT RELEPTDR 1989 ANNUAL f:EPORT MAXIMUM DDSES (hREM) RESULTIDG f R 0 ti L 10Ulli EFF i.UENT S PERIOD OF RELEASE - 01/01/D9 10 12/31/89 CALCULA1FD 12/19/99 1ST 2ND 2ED 4TH DOSE TYPE QUARTER QUARTER QUARTER DUARTER ANNUAL JAN-MAR AF R-JUN JUL-SEP OCT-DEC TOTAL 1.30E-04 5.65E-05 2.54E-05 2.13E-0D 2 33E-04 BODY INTERNAL 2.09E-04 1.33E-04 4.77F.-05 9.9BE-05 6.13E-04 0F,OAH BONE LIVER LIVER LIVER LIVER THIS IS A REPORT FOR THE CALENDAR YEAR 1989 COMPLIANCE STATUS - 10 CFR 50 AFP. J

.__________ _ ; op npp 1, GTRLY 1CT DTR 2HD OTR 3RD OTR 4TH OTR YRLY

% OF ODJ JAN-MAR APR-JUN JUL-SEP OET-NOV OPJ AFP.I TOTAL FODY (MREM) 1.5 0.01 0.00 0.00 0.00 3.0 0.01 CRIT, ORGAN (MREH) 5.0 0.00 0-.00 0.00 0.00 10.0 0 01 BONE LIVER LIVER LIVER LIVER RESULTS PASED UPON ODCM fil.V I S I O N 11 UPDATE CS204 FfPRUARY 1906 l

l b

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my pw.

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l.

O DRESDEN UNIT TWO INFANT RECEPTDh 1909 sNNUAL REPORT 6

y PROJECTED DOSE AT NEAREST COMMUNITY WATER SYSTEM

PERIOD OF RELEASE - 01/01/89 TO 12/31/S9 CALCULATED 12/19/89 g-6 ST 2ND 3RD 41 H h-DOSE ~ TYPE DUARTER QUARTER GUARTEk OUARTER ANNUAL h.

JAN-MAR APR-JUN JUL-SEP OCT-DEC TOTAL 1.30E-04 L.6LE-05 2.54E~05 2.13E-05 2.33E-04 FDDY INTERNAL 2.09E-04

1. 3 3 E- 0 4 9.7?E-05 9.96E-05 5.13E-04 ORGAN BONE LIVER LIVER LIVtm LIVER.

1HIS IS A REPORT FOR THE CALENDAR-YEAR 1909 r

l L

i COMPLIANCE ETATUS - 40 CFR 141 I

TYPE ANNUAL Lif11!

% OF LIMIT i-TOTAL 4.0 ( tiREM )

0.006 c

BODY INTERNAL 4.0 (MREM) 0.013 DRGAN LIVER f-THIS CALCULATJON-OF DOSE 15 EASED ON TECHNIOUES DEGCRIBED IN THE C0hMONUEALTd EDISDN OFFSITE DOSE CM CUL ATION MANU AL. THEBE TECHN10UES DlFFER FROM THOSE DESCRIBED IN 40 CFR 141.

i RESULTS BASED UPON ODCM REVISION 11 UPDATE CSJ04 FEERUARY 19C6 7

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DRESDEN UNIT TWD ADULT RECEFTOR 1989 ANNUAL REPORT MAXIMUM 00EES (MREM) RESUL TING FROM LIOUID EFFL UFHTC PERIOD OF RELEASE - 01/01/99 10 12/31/BY CALCULATED 12/19/DY 151

' N D 3RD 41H DOSE TYFE OUARTER QUARTER DUARTER CUAkiER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC TOTAL 2.41E-04 1.0$E-04 1.61E-04 1.69E-04 7.54'I-04 140DY INTERNAL 3.37E-04 2.74E-04 2.43E-04

'. 5 6F -0 4 1.11 E- 03 ORGAN LIVER LIVER LIVER LIVER LIVER THIS 15 A REPORT FDR THE CALENDAR YEAR 1989 COMPLIANCE STATUS - 10 CFR 50 AfP. 1

- - - _ _.... UF APP I.

DTRLY IST OTR 2ND OTR 3F:D OT R 11H OTR YRLY

0F ODJ JAN-MAR AfR-JUN JUL-EET DCT-NOV DbJ APP.I TOTAL l'0 D Y (MREM) 1.5 0.07 0.01 0.01 0.01 3.0 0.03 CRXT. ORGAN (MREM) 0.0 0.01 0.01 0.00 0.01 10.0 0.01 LIVER LIVER LIVEh LIVER LIVEP RESULTS D ASED UF'ON ODCM NEVISION 11 UFDATE CS204 i E I' R il A R i' 1986 1

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l DRESDEN UNIT TWO ADULT ftECEPTOR 1989 ANNUAL REPORT PROJECTED DOSE AT NEAREST COMt1 UNITY WATER SYSlEM 4 l

PERIOD OF RELEASE - 01<01/89 TO 12/31/89 CALCULATED 12/19/89 i

l

[

151 2ND 3RD 4TH j<

' DOSE' TYPE

-QUARTER QUARTER QUARIER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCl-DEC J

TOTAL 4.44E-05 2.40E-05 1.36E-05 1.3SE-05 9.55E-OL i

1:0DY l

INTERNAL' 1,31E-04 5.14E-05 3.22E-05 9.47E-05 2.39E-04

~

t ORGAN

[

GI-LLI GI-LLI GI-LLI GI-LL_I GI-LLI p

i THIS IS A REPDPT FOR THE CALENDAR YEAR 1989 l

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l' COMF LI ANCE STATUS - 40 CFR 141 l

1 e

TYPE ANNUAL LIMIT

% OF LIMIT 1

TOTAL 4.0 (MREH) 0.002 L

B O D

IN7ERNAL 4.0 < MREM) 0.006 O R tW A N GI-LLI l

'THIS CALCULATION OF DOSE IS BASED Ot: TECHNIDUES DESCRIPED IN THE l

COMMONWEALTH EDISON OFFSITE DOSE CALCULATION MANUAL, THESE TECHNIGUES DIFFER l

FROM THOSE DESCRIBED IN 40 CFF. 141.

{

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RESULTS BASED UPON-DDCM REVISION 11 j

ttPDATE CS204 j

FEDRUARY 1986 j

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DRESDEN UNIT THREE 1989 ANNUAL REFORT MAXIMUM' DOSES RESUL11NG FROM AIRDORNE RELEASES PERIOD OF RELEASE - 01/01/89 TO 12/31/EV CALCULATED 12/19/89 INFANT RECEPTOR AST 2ND 3RD 4TH TYPE QUARTER QUARTER DUARTER DUAR1ER.

ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC GAMMA AIR 2.20E-04 7.00E-0")

3.02E-05 3.e4E-04 4.65E-04 (MRAD)

(NE

)

(NE (NE

)

(NE (NE

)

BETA AIR-6.13E-05 4.13E-05 6.3?E-06 2.54E-05 1 33E-04 (MRAD)

(NNE )

(N

)

(N

)

(NNE )

~ TOT.. BODY 9.39E-05 2.94E-05 1.27E-05 6.?4E-05 1.99E-04 (MREM)

(NE

)

(NE

)

(NE i

(NE

)

(NE

)

SKIN 2.15E-04 S.46E-05 2.79E-05

1. 2 9F -0 4 4.57E-04 (MREM)

(NE

)

(NE

)

(NE

)

(NE

)

(NE

)

ORGAN 2.07E-02 3.SSE-02 7.57E-02 2.87E-02 1.53E-01 (MREM)

(NNE )

LUNG BONE THYROID THYROID LUND THIS IS A REPORT FOR THE CALENDAR YEAR 1989-COMPLI At'CE ST ATUS - 10 CFR SO APP. I INFANT RECEPTOR

_.. _ _.. _ _. _ _ _. OF APP I.

OTRLY IST QTR 2ND OTR 3RD OTR 4TH GTR YRLY

'. OF DBJ JAN-MAR A P R-- J U N JUL-SEF' OCT-NOV OBJ APF.I 1'

l-

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GAMMA AIR (MRAD) 5.0 0.00 0.00 0.00 0.00 30.0 0 00 BETA AIR (MRAD) 10.0 0.00 0.00 0.00 0.00 20.0 0.00 TOT. 00DY (MREM) 2.5 0,00 0.00 0.0u v.0D 5.0 0.00 SKIN (MREM) 7.5 0.00 0.00 0.00 0.00 15,0 0.00 GRGAN (MREM) 7. "1 0.26 0.52 3.01 0.3F 15.0 1.02 LUPG FONE 1HYROID T 4 'i R D I D LUNO REEULTF BASED UPON 0 0::M REUIBIDN 11 UPDATE CS?O4 FEDRU AF Y 19:

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DRESDEN UNIT THREE 1989 ANNUAL REPORT MAXIHUM DOSES RESULTING FROM AIRBORNE RELEASES PERIOD Dr RELEASE - 01/01/89 TO 12/31/89 CALCULATED 12/19/89 ADULT RECEFTOR iBT 2ND 3RD 4TH TYPE QUARTER QUARTER QUARTER OUARTER ANNUAL JAN-MAR APR-JUN JUL-SEF OCT-DEC GAMMA AIR 2.20E-04 7.00E-05 3 02E-05 1.44E-04 4.6DE-04 (MRAD)

(NE

)

(NE

)

(NE

)

(NE

)

(NE

)

DETA AIR 6.13E-05 4.13E-05 6.37E-06 2. 5 4 E - O ']

1.33E-04 (MRAD)

(NNE )

-(N

)

(N

)

(NNE )

-T OT. BODY 9.39E-05 2.94E-03 1.27E-05 6.24E-05 1.98E-04 (MREM)

(NE

)

(NE

)

(NE

)

(NE

)

(NE

)

SKIN 2.15E-04 8.46E-03 2.78E-05 1.29E-04 4.57E-04 (MREN)

(NE

)

(NE

)

(NE

)

(NF

)

(NE

)

ORGAN 1.60E-02 4.97E-01 8.34E-O' 7.20E-02 6.0SE-01 (MREM)

(NE

)

(NNE )

BONE BONE THYROID THYROID BONE THIS IS A REPORT FOR THE CALENDAR YEAR 1989 C0hFLIANCE STATUS - 10 CFR 50 APF. I ADULT RECEPTOR

___.________. ;, p p g;p p 1.

OTRLY 1ST OTR 2ND OTR 3RD OTR 11H OTR YRLY I'.

OF OBJ JAN-MAR APR-JUN JUL-EEP OCT-NOV OBJ APP.I GAMMA AIR (MRAD) 5.0 0.00 0.00 0.00 0.00 10.0 0.00 BETA' AIR (MRAD) 10.0 0,00 0.00 0.00 0.00 20,0 0.00 TOT.3 FDDY (MREM) 2.5 0.00

'), 0 0 0.00 0.00 5.0 0.00

-SKIN (MREM) 7.5 0.00 0.00 0,00 0.00 15.0 0.00 GRG AN -(MREM) 7.5 0.21 6.63 1.11 0.43 15.0 4.05 BONE BONE TH~YROID THYROID DONE RFSULTB FASED UPON ODCM REVISION 11 UFDM E CS204 FEPRUARY 19Fs

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l>RESDEN UNIT THREE INFANT RECEPTOR

'1989 ANNUAL REPORT

- M AXIMUM DCES (MREM) RESULT 1ND FROM LIQUID EFFLUENTS f

PERIOD OF RELEASE - 01/01/89 TD 12/31/89 CALCULATFD 12/19/89

)ST 2ND 3RD_

4TH

-i DOSE TYPE OUAR1ER DUARTER DUARTER QUARTER ANNUAL l

JAN-MAR APR-JUN JUL-SEP OCT-DEC TOTAL 1.139 04 6.40E-05 2.55E-05 2.14F-OS 2.24E-04 j

' BODY-l lJ

'J NT E R N A L

.1.77E-04 1.49E-04 9.91E-05 1.00E-04

~5.10E-04 ORGAN-BONE LIVER LIVER LIVER LIVER

'THIS IS A REPORT FOR THE CALENDAR YEAR 1989 COMPLIANCE STATUS - 10 CFR-50 APP. I 1

l'

.. - - _ _ _ _.. _, og App I,

GTRLY 1 ST OTR 2ND OTR 3RD OTR 4 'l H OTR YRLY

% OF 1

d GBJ JAN-MAR APR-JUN JUL-SEP GCT-NOV OBJ APP.I

- TOTAL BODY (MREM')

1.5 0.01 0.00 0.00 0.00 3.0 0,01 p

[

SRIT. ORGAN (MREM)'

.S. 0 0.00 0.00 0.00 0.00 10.0 0.02.

g BONE LIVER LIVER LIVER LIVER

-)

t-

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RESULTS PAGED UPON ODCM REVISIDN 11, j

UPDATE CS204 3

[

FEBRUARY 1986

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c' DRESDEN UNIT THREE INFANT RECEPTOP 1989 ANNUAL REPORT PROJECTED DOSE AT NEAREST COMMUNITY WATER SYSTEN t PERIOD OF RELEASE - 01/01/89 TO 12/31/89 CALCULATED 12/19/89 1ST 2ND 3RD 4TH DOSE TYPE

-00ARTER QUARTER DUARTER QUARTER ANNUAL JAN-MAR APR-JUN JUL-SEP OCT-DEC

-T OT AL' 1.13E-04 6,40E-05 2 55E-05 2,14E-05' 2.24E-04 BODY INTERNAL 1.77E-04 1.49E-04 9.91E-05 1,00E-04 5.10E-04

-ORGAN BONE LIVER LIVER LIVER LIVER THIS IS A REPORT FOR THE CALENDAR YEAR 1989 COMPLIANCE STATUS - 40 C f' R 141 TYPE ANNUAL LIMIT

% OF' LIMIT

' TOTAL 4.0 (NREM)-

0,006 BODY INTERNAL 4.0 (MREM) 0.013 ORGAN' LIVER

- THIS CALCULATION OF DOSE IS BASED ON TECHNIQUES DESCRIBED IN THE COMMONUEALTH EDISON OFFSITE DOSE CALCULATION MANUAL. THESE TECHNIOUES DIFFER FROM THOSE DESCRIBED IN 40 CFR 141, RESULTS BASED UPON DDCM REVISION 11 UFDATE CS204 f-EBRUARY 1986 i

T

s 4

g l

l DRESDEN UNIT THREE ADULT RECEPTOR 1989 ANNUAL REPORT tiAXIMUM DOSES ~ (MREM) RESULTING FROM' LIQUID EFFLUENTS PERIOD OF RELEASE - 01/01/89 TO 12/31/S9 CALCULATED 12/19/89 IST 2ND 3RD 4TH DOSE-TYPE QUARTER QUARTER 00ARTER QUARTER ANNUAL JAN-MAR APR-JUN JLil-SEP OCT-DEC iTOTA 2.12E-04 2.05E-04 1.64E-04

'1.71E-04

?.51E-04

' PODY l INTERNAL 2 98E-04 3.05E-04 2.47E-04 2.5SE-04

'1.11 E - 0 3 -

ORGAN LIVER LIVER LIVER LIVER LIVER THIS.IS A REPORT FOR THE CALENDAR YEAR 1999 5

L COMPLIANCE STATUS - 10 CFR 50 APP. I j

1

or Apr.1. -._____--__--

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

% OF OBJ JAN-MAR APR-JUN JUL-5EP GCT-NOV ODJ APP.I-TOTAL BODY (MREM) 1.5 0.01 0.01 0.01 0.01 3.0 0.03

-CRIT. ORGAN (MREH) 540 0.01 0.01 0.00 0.01 10.0 0.03 l

LIVER LIVER LIVER LIVER LIVER Ai RESULTS BASED UPON ODCM PEVISION 11 t

l UPDATE C5204 FEBRUARY 1986 j

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'DRESDEN UNIT THREE ADULT RECEPTOR 1989 ANNUAL REPORl PROJECTED DOBE AT NEAREST 4 CftMMUNITY WM E R SYS1EM 4 PERIOD OF RELEASE - 01/01/89 TO 12/31/89 C A L C ul, AT E D 12/19/89 1ST 2ND 3RD 4TH

' DOSE. TYF'E QUARTER QUARTER QUARTER QUARTER ANNUhL JAN-MAR APR-JUN JUL-SEP GCT-DEC I

L. TOTAL' 3.86E-05 2.71E-05 1.3SE-05 1.35E-03

9. 30E-05 BODY INTERNfiL 1.17E-04 5.SOE-05 3.22E-05 2.47E-05 2.32E-04' ORGAN GI-LLI GI-LLI GI-LLI GI-LLI GI-LLI THIS IS'A REPORT FOR THE CALENDAR YEAR 1989 A-COMPLIANCE STATUS - 40 CFR 141 TYPE ANNUAL LIMIT

% CF LIMIT g.

TOTAL 4.0 (HREM) 0.002 BODY INTERNAL 4.0 (MREM) 0.006 ORGAN GI-LLI

'THIS CALCULATION OF DOSE IS BASED ON TECHNIQUES DESCRIBED IN THL COMMONWEALTH EDISON OFFSITE DOSE CALCULATION MANUAL. THESE TECHNIQUES DIFFER FROM THOSE DESCRIBED IN 10 CFR 141.

RESULTS BASED UPON ODCM REVISION 11 U DATE CS204 FEBRUARY 1986 l

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ll DRESDEN 1989 ANNUAL REPORT BWR TURBINE N-16 "SKYSHINE' DOSES TO NEAREST RESIDENT PROD 3CTION PERIOD - 01/01/89 TO 12/31/89 CALCULATED 12/19/89 NEAREST RESIDENT (UNITS.2 t 3) :

966 n, FISHING ACTIVITY LOCATION 610 ci

'1 S T 2ND 3RD 4TH OUARTER QUARTER QUARTER.

QUARTER ANNUAL JAN-MfR APR-JUN JUL-SEP GCT-DEC POWER.-(Mwe-br')

2.14E+06 2.54E+06 3.07E+06 2.22E+06 9.9BE+06 NEAREST RESIDENT WHOLE BODY DOSES (MREM) :

l FISHING DOSE 3.42E-02 4.05E-02 4.90E-02 3.51E-0?

1.59E-01 l

l.

AT-HOME DOSE 1.47E-02 1.75E-02 2.11E-02 1.52E-02 6.85E-02 l

' TOTAL DOSE 4,89E-02 5.00E-02 7.01E-02 5.06E-02 2.29E-01 l

THIS IS A REPOPT FOR CALENDAR YEAR 1989 RESULTS BASED'UPON ODCM REVISION 11-UPDATE CS204 FEBRUARY 1986 I.

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

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~

March, 1989),

t ZR03/727 24 of 24

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.9) 14

.64

.14 45 43

.64

.18 1.12

.51

.62

.59 l.41 2.23-2.23 1.80 15.42

' U #U 28

.26

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.33

.28

.24

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.19

.24

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.51

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.26

.21

.12 4.32 B $U. 38 i.21

.19

.13

.19

.21

.31 41

.36

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.26

.36

.24

.41 4.15

t 2.16 1.92 2.80 2.11 2.91 2.14 1.50 1.80 2.56 1.68 1.61 1.64 2.28 2.35 1.85 2.91 14.93 i 55 1.02 1.04 1.38 1.26 1.92 2.61 1,41 2.3) 3.39 2.82 1.99 1.50 2.92 2.20 1.52 1.02 30.41 0 M5

.33

.11

.14

.09

.26

.83

.24

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.10

.28

.51

.36

.31 8.33 i ts

.02

.00

.62

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.05

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.19

.33

.36

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.12 1.18 i

p

[.

4 C(Co 00[50(t 51Atlos JanuarvJune 1989 1

~ 300 ft. WINO 58((0 and stND Ole (Cil0N 300 35 ft. Olff tetkil At T(RP(0ATU0( -

NU#8(0 Of 085(OVAfl0a5 4260

.)

i SD(!D DietCTIDs CLA55 57Allti1Y CLA55

.CLA55 m tot. uf tut :

(-

($(

$( $$(

5-55W SW

. SW -

t_

W#v ut udv. TOTAL' (U AU

$U. a 55 R5 (5-TOTAL W

(U

.00 '.00

.00 ".00

.00'

.00

.00 ' 00

.00

.00. 00

. Q

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.00

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.00

.00 9 50 '.00. '.00 ;.00,.00

.00

.00. 00

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-6

~.05

.00

.02

-,12

.09

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.09 05

.02

.12

.05 -.07

.14

.62

.05

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' 3 $$ 02 407

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.16

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.19

.56

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.30

.42

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.61

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.20 6.13 6.13 1 55 '.09

.09

.19

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.12. 12

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.19

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.19

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.00

.02

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.07

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.42

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8 $U

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.14

.19

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.16

.05

.02

.01

.05

.02

.14

.19

.31

.19 1.90 1.90

-t

.92 r.10

.85 1.70 1.17

.63

.61'

.75

.61

.63

.59

.00

.15

.63

.49 1.06 13.24 13.2s 1 55 -.31 41' 47.59

.13 40 42. 52

.59 42

.42 49' 77

.33

.41

.23 7.63 1.63 2 NS

.821.09 '.id

.01

.05

.16

.23

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.45

.33

.12

.19

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~

($

.00

.02

.00

.02

.01

.00

.00'.07

.02

.12

.00

.35

.35 26.80 (U-.00.,.26 00 '.00

.00

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.61

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.00

.40

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.02

.07

.05

.00

.02

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.00

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.00

.02

.00

.16

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.82 3 SU

.05

.09

.l4

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.31

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.60 1.34 1.60 1.11 1.08 15.16 15.16 1 55 :. 20

.61

.40

.21-

.52 1.01

.75 1.06 1.11 1.22 75

.19 1.34

.96

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.68 12.68 12.68 8 #5 '.14

.09 -.14

.00

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.52

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19 $U :.00

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-.26

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.38

.26

.52

.54

.73

.54 40..54

.94

.63 40 1.65 1.65 2 55'.38

.16

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.28 1.11 1.36

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.56 1.00

.00

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.05 1.06 1.06 4 NS

.12 -.05

.01

.00

.62

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.05

.21

.12

.19

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.42

.00

.12 1.00 1.00 C5

.02 ~ 00 -.00

.00

.02

.00

.62

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.00

.02

.14

.l4 17.19

- (U

.00

.00 2 NU

.00

.02

.00

.05

.05 5 50

.02

.00

.05

.02

.09

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.09

.16

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.00

.09

.21

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.12

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.12 3.01 3.03 3 55

.12

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.11

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C(Co 00[50(t STAilot -

- Januc y-June 1989 F-300 ft. #140 5#((0 and Wlu0 010(Cilot 300-35 ft. Olff(R(ufl AL T(NP(RATUR[

$$((0 010(Citos CLA55 STA61tlit CLA55 4[.(t( -('

($(

$( $5[

$ ' SSW

$6 W$t 0

ptV tv et TOTAL (U pu 50 N

SS R$

[5 TOTAL CLA55 3 ht(

);

p

.(3.

.00

.00 00' 00

.00

.00 3 Q

.48

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.00

.00.

.00

.00 e

'.1 50

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. 00 -.00

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-.00

.00

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.00

.00 1

N..00

.07

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00

.00. 00

.00

.05

.00

.45-

.00

.42

.00 00

.23

.2)

. 3 55

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.00 -.00 -.to. 00

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.00..00

.00

.00 '.00

.00

.00 -

- (5

.00

.00 =.00 -.00

.00

.30-00

.00

.00' 40 Th (U-~.00 -.00. 00

.00,.00

.00-

.00

.00 -.00'

.00'

.00

.00 ' 00

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. 00 -.00 '.00 00

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.00 '.00

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'T0! 5.31. 4.95 5.26 5.61-4.74-4.95 4.77 5.99 8.00 7.54 6.95 1.35 8.62 7.89 6.36 5.70 100.00

.96~ 2.49 4.91 46.43 35.45 8.50 1.27100.00

-i l.

5 (U L '.19

.35

.00 -.00

.62

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.19

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- t 1.08 2.35 3.12 3.87 2,72 2.39 1.74 2.75 3.22 2.44 2.54 2.18 3.52 4.01 2.72 2.98 46.43 i $$ -. l.20 1.41-1.13 1.11 1.55 1.90 1.83 2.44 3.70 3.99 2.86 2.02 1.16 2.49 1.85 1.27 35.45 4

IV 0 45 L.33

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.45

. 09

.14

.28

.73

.49 70

.70

.96 1.20

.80

.35

.59

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if (5.

'.02'

.00

.02

.00

.05

.09

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.07 1.27 L

e 1

l i

, O:

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l. =

CECO ORE 50EN NUCLEAR POWER STAil0N

NETEOROLOGICAL DATA 0 ATE

.... WIND SPEED....

. WIND DIRECil0N....WINDSIGhA...

TEMP

...DIFFi...

.....0EWPOINT......

PRECIP

C-00-YY. NN -

35 150 300 35 150 300 35 150 300 35 150 300 35 150 300 10 3-4 89 i

'1.3 12.1 17.0 110 til 128 7

4 3

37.1

.I 1.4

-35.7 35.3-36.0

.00

<3-4-89 2-6.1 10.1. 13.5 120 129 141 26 15 6

38.4

.6 2.2 37.2 17.1 38.3

.00 3-4-09 -3

~ 7.0 11.5 16.6 140 154 165 12 8

1 40.9 1.0 2.0 39.8 40.3 40.1

.00 3-4 09 4 5.5 9.9 15.5 164 177 187 13 8

4 42.4

.2

.9 41.1 41.2 41.0

.00 3-4-89' 5 7.6 12.3' 18.1 150 168 181 10 4.

4 43.0

.4 1.4 41.6 41.7 42.1

.00 3-4-89 6-7.8 11.4 15.5 159 167 113 16 11

'5 44.4

.I

.5 43.2 43.0 42.7

.00 3-4 89 7 6.7 10.1 13.7 177 181 184 29 20 14 -

43.9

.2

.4 42.8 42.7 42.1

.00 3-4-89 8 4.8 8.4 12.6 192 205 209 22 ll 5

42.3

.5 1.0 41.3 41.3 41.2

.00

3-4-89 9 5.2 9.8 14.7 233 229 223 28 19 13 42.4 4

1.2 999.0 41.4 41.4 -

.00 3-4 89 10 7.5 11.7 15.6-268 268 267 9

10 11 42.1

.3

.I 999.0 41.1 40.5

.00 3-4-89 11 6.7 9.4 l1.8 261 263 265 7

6 7

42.5

.5

.4 41.7 40.3 39.8

.00 3-4-89 12.

7.8 l1.0 12.7 255 252 250 8

8 8

42.3

.7

-1.0 41.2 40.0 39.0

.00 3-4-89 13 11.0 14.1 15.8 264 264 263 4

4 4

38.8

.9

-1.9 36.6 35.7 34.3

.00 -

3-4-89 14 10.1 13.6 15.0 280 280 217 9

7 6

36.0

.8

-1.9 32.9 32.1 30.9

.00 3-4 15 13.9 19.3 21.1 289 288 285 6

4 4

33.3

.8

-l.6 29.4 28.3

-27.3

.00 3-4-89 16

'12.9 18.1 20.0 281 286 283 8

6 6

31.6

.8

-1.4 27.7 26.5 25.7

.00 3-4 89 17 12.6 17.7 19.3 289 288 286 6

5 4

30.4

.8

-1.5 26.6 25.3

-24.6

.00 4-89 18 9.3 12.7 14.2 295 294 293 11 10 8

30.2

.8

-1.4 27.3 25.9 25.5

.00 4-89 19 9.0 12.2.13.9 303 302' 299 13 13 13 30.6 9

-1.5 27.0 25.8 25.1

.00 3-4-89 20 12.5 16.6 17.9 339 339-337 6

6 6

28.8

-1.0

-l.6 25.1 24.5 24.1

.00 3-4-89 21 12.1 15.8 - 17.5 331 337 335 5

5 4

27.4

-1.0

-l.6 22.3 21.8 21.1

.00

~.3-4-89 22 13.5 17.9 20.0-340 340 338 4

3 3

26.0

-1.0

-1,6 19.9 19.8 18.6

.00 3-4-89 23 13.0 11.4 18.9 347 348 347 7

7 6

25.0

-1.0

-1,6 19.0 19.1 11.9

.00 3-4 24 11.9 16.4 18.3 360 2

1 7

6 5

24.2

-1.0

-1.6 19.1 19.1 18.1

.00 TOTAL

.00 D

o e,..

, ! 1:

I CEC 0 ORESDEN NUCLEAR PONER STATION m RETEOR0 LOGICAL DATA

~

-0 ATE c.... WIND SPEED....

.WINDDIRECil0N....VIND SIGMA...

TEMP

...DIFF T...

......DEWP0lWT......

PRECIP RM-00-YY HH 35 150 300 35 150 300 35 150 300 35 150 300 35 150 300 10

.3-25-89 I

10.4 15.1 21.5 191-198 191

'A 3

3 51.8

.0

-.2 42.2 41.0 41.3

.00.

3-25-09 2

.9.4 14.6' 20.3 215 213 211 13 10 8

51.2

.0

.I 44.2 43.0 43.I

.00 3-25 3

'10.2 15.9 21.8 230 227 225

'3 2

3 50.1

.2

.5 44.6 43.6 43.5

.00 3-25-09 4 8.7 - 15.0 20.3 234 237 238 3

2 2

48.6

.6 1.2 44.0 43.3 42.9

.00 3-25-89 5

.6.1 12.3 16.8 233. 239 249 -

1 7

9 46.7 1.2 2.4 42.6 42.1 41.3

.00 L3-25-89 -6 9.0 14.1 19.1 283 281' 218 12 8

6 45.8

.3

.2 40.4 39.6 38.1 r0 o

3-25-89 1-8.4-II Y 15.1 279 218 271 8

7 5

43.5

.5

.B 39.0 31.9 37.4

.00 3-25-89 8 1.0 9.3 11.0 288 288 290 8

8 9

44.9

-1.1

-1.5 39.2 38.2 31.2

.00 3-25-89 9-6.6 7.8 8.5 307 307 310 - 23 20 IB 49.4 l.6

-2.3 39.1 38.8, 37.6

.00 3-25-09 to 8.1 10.0 10.2 346 347 345 11 10 9

53.9

-l.1

-2.1 40.5 39.6 38.5

.00

-3 25-89 11 6.4 1.9 8.4 7

7 5

20-15 12 58.5

-l.7

-3.0 42.1 41.3 40.1

.00

3-25 89 12 4.4 5.4 5.8 61 34 53 45 68 28 62.2

.8

-2.4 41.3 40.9 39.6

.00

_3-25 89 13 4.1 4.9 5.1 12 15 18 48 41 33 64.1

-l.1

-2.3 40.6 40.1 38.9

.00 3-25-89 14 6.3 7.3 7.5

-il 74-11 56 48 41 65.4

-l.1

-2.5 40.8 40.0 39.0

.00 3-25-89 15 12.3 15.0 16.1 92 92 89 8

7 5

61.3

-1.4

-2.6 41.6 40.5 39.1

.00-3-25-89 16 8.5 11.1 12.5 69 70 68 to 8

1 58.9

-l.1

-2.2 40.8 39.8 39.0

.00 3-25-89 11_

B.6 12.2 13.8 66 67 65 6

5 3

56.0

.8

-l.7 40.3 39.2 41.5

.00 3-25-89.18 6.9 9.4 11.3 61 10 10 6

4 4

53.3

.6

-l.4 40.0 38.9 38.3

.00 3-25-89'l9

' 5.2 1.2 8.3 69 12 11 8

6 4

49.1

.5

-1.2 39.6 38.4 38.0

.00-3-25-89 20

- 5.6 7.5 -

8.1 15 15 70 to 7

5 45.8

.6

-1.2 38.3 37.2 36.9

.00-3-25-89 21' 6.1 8.0

' 9.1 72 14 10 10 6

4 42.3 1

-1.1 36.5 35.4 34.9

.00

.3-25-89 22 8.9 12.1 14.4 91 93-86 6

4 5

39.7

.6

.1 35.0 33.9 33.4

.00 E

3-25-89 23 5.I 7.0 8.1 93 88 82 Il 1

5 38.7

.5

.8 34.5 33.5 33.1

.00 3-25-89 24 1.1 9.4 11.9 91 93 81 5

6 1

38.3

.6

.8 34.4 33.4 32.9

.00 TOTAL.

.00 m.__ana-w_

____-----_____-________.____.___.____.____..____._____m_

__.. _ _ _. _ _ _ _ _ _ _ _ _. _.

ML20005E159

Text

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