ML20028G787

Corrected Radioactive Effluent Rept for Jul-Dec 1989

ML20028G787
Person / Time
Site:	Dresden
Issue date:	12/31/1989
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20028G786	List: ML20028G785 ML20028G787
References
NUDOCS 9009040146
Download: ML20028G787 (50)

Text

IGhoDEN NUCLEAR POWER STATION DOCKET NOS. 50-10, 50-237, 50-249 REGULATORY LIMITS Gaseous Effluents - Dose-This-Specification is provided'to ensure that the dose at the unrestricted area boundary from gaseous effluents from the units on site will be within the annual dose limits of 10 CFR Pert 20 for unrestricted areas. The annual dose limits are the doses associated with the concentrations of 10 CFR Part

20. Appendix B, Table II.

These limits provide reasonable assurance that

-radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)). Tne specifled 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.-4These 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.

Dose, Noble Gases This Specification is provided to !.mplement the requirements of Sections II.B. III.A and IV.A of Appendi I, 10 CFR Part 50.

The Limiting Conditions For Operation implement the saides set forth in Section II.3 of Appendix I.

The statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is tuilikely to be substantially underestimated. The dose calculations established in the.0DCM 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 1.109, " Calculation of ZEDE/298 1 of 30 9009040146 900801 PDR ADOCK 05000020 PDC R

DRESDEN NUCLEAR POWER-STATION DOCKET NOS. 50-10,,50-237, 50-249 Annual Doses to Man:from Routine Releases of Reactor' Effluents for the-Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating e

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, Radioiodines, Radioactive Materici in Particulate Form and Radionuclides Other than Noble Gases This specification is provided to implement the requirements of Sections g

L 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 1.

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

Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models tod data such that the actua1 exposure of an individual through appror !C ' pathways !s unlikely to be substantially underestimated. The ODCM.a'roiational methods approved by NRC for calculating the doses due to the acttw; +elease rates of the subject materials are required to be consistent with the metho.. ology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of. Evaluating Compliance with 10 CFR Part 50, Appendix I", Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors,"

Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average etmospheric; conditions. The release rate specifications for radioiodines, radioactive material in particulate form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area.- The

~

pathways which were examined in the development of these specifications

!(.

were:

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.

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7 m

l ZEDE/298 2 of 30

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

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

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

LIQUID _ 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 gaees, MPC in air-(submersion), was converted to an equivalent concentration in water using the International Commission on Radiological Protection. (ICRP)'

Publication 2.

(.'

l r

ZEDE/298 3 of 30

DRESDEN NUCLEAR POWER STATION DOCKET NOS. 50-10, 50-237, 50-249-Dose l-This specification is provided to implement the requirements of Sections II.A. III.A and IV.A of Appendix I, 10 CFR Part 50.

__1 di The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix 1.

The statements provido the required operating flexibility and at the same time implement the guides set forth in Section.

IV.A of Appendix I to assure that the releases of radioactive material in The dose liquid effluents will be kept "as lov as reasonably achievable".~

calculations in *he ODCM implement ths requirements in Section III.A of Appendix I that c '.rmance 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 apptcp-late 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 nrterials in liquid effluents will be consistent with the methodology ptovide' in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Rc; tine Releases of Reactor Effluents for the Purpose of Evaluating Com)11ance with 10 CFR Part 50, Appendix I", Revision 1, October 1977 and 3

Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases fur the Purpose of Implementing Appendiv T.", April 1977. NUREG-0113 provides methods for dose calculations with Reg Guide 1.109 and 1.113.

Liquid Waste Treatrent 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.

2EDE/298 4 of 30

DRESDEN NUCLEAR POWER STATION DOCKET NOS. 50-10, 50-237, 50-249 MAXIMUM PERMISSIBLE CONCENT!!ATIONS (MPO)'

The concentration of radioactive materials released in gaseous and liquid effluents from the site to unrestricted areas will be less than the=

r.

concentration levels specified in 10 CFR Part 20, Appendix B~, Columns 1 and 2.

The concentration limit for noble gases.MPC in air (submersion), was.

converted to an equivalent concentration in water using the International Commission on Radiological Protection (ICRP) Publication 2.

MAXIMUM PERMISSIBLE CONCENTRATION OF DISSOLVED OR ENTRAINED NOBLE CASES RELEASED FROM THE SITE TO UNRESTRICTED AREAS IN LIQUID WSTE =

NUCLIDE MPC(pC1/mL)*

Kr-85m 2.0E-04 Kr-85 5.0E-04 Kr-87 4.0E-05 Kr-88 9.0E-05 Ar-41 7.0E-05 Xe-131m 7.0E-04 Xe-133m 5.0E-04 Xe-133 6.0E-04 Xe-135m 2.0E-04 Xe-135 2.0E * -Computed from Equation 20 of ICRP Publication 2 (1959),

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

2EDE/298 5 of 30 s

DRESDEN NUCLEAR POWER SiATION DOCKET NOS. 50-10, 50-337, 50-249 AVERAr4 SNERGY The average energy of fission and activation gases.vas calculated for the gaseous effluents released from the <ite.

The average energy is based on the percentage of each fission gas ac:lide present and its respective average energy per disintegration (E in MeV/ dis) for gamma and beta emissions separately.

Eg=

2.72E-01 MeV/ dis E3=

2.87E-01 MeV/ dis

'ZEDE/294 6 of 30

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

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1 MEASUREMENTS AND APPROXIMATIONS-A.

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

The samples are analyzed for specific isotopes present in the release using a Hyper-Pure Germanium (HP Je) Spectrometry System. Tritium is' sampled monthly rla a grab sample on the D-1 chimney, D2/3 Chimney, q

and D2/3 Reactor Building vent and analyzed using a Liquid

. Scintillation Counte r.

Krypton-85 is estimated in the D2/3 chimney using a recoil o.. nan-recoil calculation using the fission per second plot and the sum ot' 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 sc0ples f rom the.D-1 Chimney, D2/3 Chimney and the D2/3 Reactor Bu'1dino Vents are collected for a maximum seven day period. These sampics are analyzed for specific nuclides present in the release using a-HP Ge spectrometry-system. When iodine or particulate samples are not used for reporting the release rate due to management decision that the sample may not be representative, an average of the preceding sample and the following sample is used to calculate the release. A monthly composite of the particulate samples is sent to a vendor to be analyzed for Sr-89, Sr-90, and Gross Alpha activity.

C.

Liquid Effluents: P.ior to a release, duplicate grab samples are collected from each batch and analyzed for gross activity using a gas flow proportional countor. Radioactive waste batch discharges are also analyzed for specffic isotopes present in the release using a HP Ge spectrometry systc.a.

-A composite of:all batchea for the month is sent to a vendor to be analyzed for Sr-89,- Sr-90, Fe-55,11-3, and Gross Alpha activity. A sample of each Containment Coaling 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 celibration 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 November and December using October data. The data in this corrected Effluent Report reflects final vendor analyzed information.

ZEDE/298 7 of 30 1.

m?"M i

DRESDEN NUCLEAR POWER STATION UNITS 1,3, AND 3 i

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

_hiv Through Dictabn _ 1982 GASEQUS' EFFLUENTS Docket Numbers: 50-10 50-237 SUMMATION OF ALL RELEASES 50-249 3

EST. TOTAL

. TYPE OF RELEASE UNITS A d QUARTER hih QUARTER ERROR,%-

FISSIQH AND ACTIVATI0lLtdE=.S 1.

Total Release Ci 2.25E+00 9.75E+00 7.31

'2.

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

Percent of Technical Specif3. tion Limit A

A

' Ro 10DlHES 1.

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

Average Release Rate of I-131 for Period uCi/sec-1.99E-04 1.15E-04 l

3.

Percent of Technical Specification Limit A

A

~

Total Iodine-131, Iodine-133,and Iodine-135 Ci 2.32E-02 1.54E-02 4

C.'

PARTICULATES' 1.

Particulates with half-lives > 8 days Ci 4.09E-02 4.24E-02 8.09 l

l

.2.

Average Release Rate for Period uCi/sec 5.15E-03

5. 33E -03 3.

Percent of Technical Specification Limit A

.A

4.. Gross Alpha Radioactivity C1 1.27E-05 4.07E-06 Dx_.IRIIIUM 1.

Total Release Ci 3.07E+00

-4.45E+00 7.89 2.

Average Release Rate for Period uCi/sec-3.86E-01 5.60E-01 3.

Percent of Technical Specification Limit A

A j

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

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ZEDE/298 8 of 30

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-DRESDEN NUCLEAR POWER STATION

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' UNITS 1,2, AND 3 EFFLUENT AND WAST 3 DISPOSAL SEMIANNUAL REPORT g,

Julv Through -December '1912 Docket Number.

50-10 y

TABLE OF LOWER LIMITS OF DETECTABILITY 50-237 FOR GASEOUS EFFLUENTS 50-249 LLD (uCi/cc) l'.

FISSION GASES 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 Kr 4.91E-06 Xe-135 1.66E-08.

.Xe-133 4.53E-08 Others:

2.

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

PARTICULATES Sr-89 6.00E-16 Sr-90 6.00E-16 Cr-51 7.21E-13 Mn-54 8.76E-14 Co-58 7.52E-14 Fe-59 1.40E-13 Co-60 1.93E-13 Zr-95 1.38E-13 Nb-95 8.36E-14 Ru-103 8-09E.

Ag-110m 7.42E-14 Sb-124 6.66E-14 I-131 1.25E-13 Cs-134 8.50E-14 Cs -136 1.21E-13 Cs-137 8.77E-14 Ba-140 3.68E-13 Ce-141 1.28E-13 Ce-144 4.85E-13 Zn-65 1.43E-13 Ba-133 9.89E-14 Sb-125 2.22E-13 Others Gross Alpha 4.00E-15 Fe-55 1.20E-14 ZEDE/298 9 of 30

1 DRESDEN NUCLEAR POWER STATION' UNIT 1 EFFLUENT AND WASTE DISPOSAL' SEMIANNUAL REPORT _

Julv Through _Dgs.pinher_.19]L9 D1 Chimnev GASEOUS EFFLUENTS CROUND LEVEL RELEASES-Docket Number 50-10 SEMI-ELEVATED RELEASES xx ELEVATED RELEASES CORIINUOUS MODE BATCH MODE HUCLIDES RELEASED UNIT 314 QUARTER h.th QUARTER-3rd QUARTER sfth QUARTER' E1SS10H GASEE..

Xe-138 Ci Xc-135m Ci y

Kri87

_Ci_

Kr-88 C1 Kr-85m C1 Kr-85.

Ci Je-135 Ci

_,.__Xe-133 Ci TDIAL

_Ci_

None None IODINES

-I-131 C1 I-133 C1 l-135 Ci TOTAL 01 None None PARTICUlATES_ _

SI-89'

_ Ci, 1.76E-05 Sr-2Q C1 8.75E-08 Cr-51 C1 Mn-54 01 3.71E-07 Co-58 01 Fe-59 C1 Co-10

_CL 5.05E-06 5.78E-06 l

2r-95

_C1 Nb-95

-C1 Ru-103 01_

Agd10m CL Sbd24 C1 1-131 Ci Ca-134

_CL Ca-136

_CJ

.Cs-131 C1 2.50E-06 2.0/E-06 Ea:140 C 1. _

e J.e-Lii 01 t

>:_.__Ce-144 C1

,_ _.ln:65

=Qi_

EA-133

_CL Ah-l.25 Ci

_Ec-55 Ci 5.QSE-06

_. IDIAL.

01 3.0ZE,RS 7.SJE-06 None None

• The activity of this nuclide is less than t'ne LLD listed on the appropriate table.

ZEDE/298 10 of 30

DRESDEN NUCLEAR POWER STATION Unit 1 I

EFTLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT-Julv Through _Sasitabar 19B.2 Di Chimnev GASEOUS EFFLUENTS GROUND LEVEL RELEASES Docket Numberst 50-10 SEMI-ELEVATED RELEASES xx ELEVATED RELEASES CONTINUOUS MODE

-NUCLIDES RETEASED UNIT JULY AUGUST SEPTEMBER 3rd QUARTER TOTAL FISS10H_SASES Xe-138 Ci Xedum C1 Kr-87

_Ci__

Kr-BB Ci

- Kt-Em C1 Kr-85 Ci Ke-135 C1 Xe-133 C1 TQIAL C1

_ _.10DlHES I-131

_Ci I-133 C1 I-135 C1

_ _IOTAL C1 RARIICUIATES SI-89 Ui 1.76E-05 1.76E-05 SI-21 Ci 8.75E-08 8.75E-08 Cr-31 C1 Mn-54 Ci 3.71E-07 3.71E-07 Co-18 C1 Fe-59 C1 00-60 01 2.92E-06 1.56E-06 5.71E-07 5.05E-06 2r-95 C1 Nb-95 C1

_Ru-103 Ci As-1Lom Ci Sh-124 C1 I-131 C1 gg-134 Ci

._Jad36.__

Ci Cs-137 Ci 1.24E-Ob 1.09E-06 1.71E-07 2.50E-06 Ra-140

_.gl Ce-141 C1

-Ce-144 C1 2n-61 Ci._..

Da-133 Ci

_Sb-125 C1

_._Je-55 C1 1.02E-06 4.06E-06 5.08E-06 IQIAL

__ Ci 5 ME-01_

2.65E-06 2.25E-05 3 J7E-05 t

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

I ZEDE/298 11 of 30

DRESDEN NUCLEAR POWER STATION UNIT.I.

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT October Through _Desember 1982 D1 Chimnev

_ GASEOUS EFFLUENTS

^

GROUND LEVEL RELEASES Docket Number 50-10 SEMI-ELEVATED RELEASES XX ELEVATED RELEASES CONTINU0llS MODE

- NUCil"'S RELEASED UNIT OCTOBER NOVEMBER DECEMBER 4th QUARTER TOTAL

_ _EISS1(#_ GASES _

Xc-ta8 Ci-

_.._Xe-135m Ci Kr.&7' Ci Kr-BB Ci-

.___KI-85 n C1

___ Kt-85 CL Xe-135 01 Xe-133 CL

___._IDIAL C1 10D1HES I-131 li_

I-133 C1 I-135 C1 10IAL 01 PARIICUIATES Sr-89 Ci Sr-90

_Ci Cr-51 C1 Mn-54 C1 Co-58.

01 Je-59 _

Ci Co-60 CL 1.85E-06 1.92E-07 3.74E-06 5 d8E-06 Zr-95 C1_

Nb-25 Ci Ru-103.

Ci An-110m

_Ci_

Sb-124

_Ci_

1-131'

_gi_

Cs-134 C1 Cs-136 C1 Cs-137 Ci 1.23E-07 1.95E-06 2.07E-06 11c-140

_ni_

_. _.Cc-is1 Ci Cc-144 C1

.___ZIL_fi5 C1 1

' Ba.-123 C1 Sh-125

_cl_

fe-15 C i___

____.IQIAL '

_Ci_

1.85E-06 3.15E-07 3 d2E-06 7,31E-06

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

ZEDE/298 12 of 30

DRESDEN NUCLEAR POWER STATION ~-

UNITS 2 AND 3-

'EFFIUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Juiv Thrtugh December. 1989 l

I D2/3 Chimney GASEOUS EFFLUENTS GROUND LEVEL RELEASES Docket Numbers: 50-237'-

SEMI-ELEVATED RELEASES 50-249-t XX ELEVATED RELEASES CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT 3rd QUARTER Mh QUARTER 3rd QUARTER M b QUARTER

.. FISSION GASES i

Xe-138 Ci Xe-133m C1 1.881100

.Kr-87 Ci Kr-88 C4 Kr-85m L

Kr-85 Ji 2.81E-03 2.30E-03

.__ _Xg-135

_Ci_

2.25E+00 9.75E+00 J e:133 01-IQTAL

_C1 2.25E+00 1.16E+01 None None

(

~.lDDlHLS I-131 C1 1 23E-03 6.66E-04

,._ _1-133 C1 6.15E-03 3 83E-03 I-135 Ci 8.95E-03 5.27E-03 TDIAL C1 1.63E-02 9.77E-03 None None PARTICULATES Sr.-89

.01 2.26E-04 1.83E-04 Sr-90

_Ci 1.53E-06 1,38E _ _.

,_, _Cr-51

_C1_

1.16E-04 Jn-54 C1 1.7QE-05 2.16E-05

.Co-58 C1 Fe-59 01 00-60 Ci 1.47E-04 8.15E-05 2r-95 C1 Nb-95 C1 RurlD3 Ci

_,_,._ Ag-110m 01

_ _ Sh-12A Ci I-131 C1 1.01E-04 3.18E-05

~

Ca-134 C1 Os-136-C1

'l Ca=137-

_El 5.83E-06 1.41E-05 Ba-140 C1 1.04E-03 5.81E-04 Cc-141 C1 Ce-144 C1 2n-65 Ci

-Ba-133 C1 l'

Eh:115 C1 J a-140 C1 2,ShE-03 1.17E-03 Fe-55 C1 2.33E-04 2.23E-04

- _IQIAL 01 3.331-03 2.42E-03 None None

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

p ZEDE/298 13 of 30 e

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DRESDEN NUCLEAR POWER STATION:

UNITS-2 AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Julv Through September 1982 i

f

_ _D2/3 Chimney GASEOUS EFFLUENTS

[

GROUND LEVEL RELEASES Docket Numbers: 50-237 j

SEMI-ELEVATED RELEASES 50-249 XX ELEVATED RELEASES CONTINUOUS MODE

-NUCLIDES RELEASED UNIT JULY AUGUST SEPTEMBER 3rd QUARTER 1

TOTAL FISSION _ GASES _

~

Xe-138 Ci Xe.-115m

_Ci_

r,r-87 C1 Kr _B.8 01

_ _Kr:B5m Ci

_ _._Kr-85 Ci 1.03E-03 9.BQE-04 8.02E-04 2 16E-03 Xe-135 Ci 2.64E-01 1.99E+00 2.25E+00 Xe-133 C1 TOIAL Ci 2.65E-01 9.80E-04 1.99E+00 2.25E+00 IDDINES

,,__l-131

.,_CL 3.44E-04 5.07E-04 3.78E-04 1223E-03 I-133 C1 2.14E-03 1.97E-03 2.04E-03 6.15E-03 1._135 C1 3.56E-03 2 31E-03 3.05E-03 8.95E-03 TDTAL 01 6.04E-03 4.84E-03 5.45E-03 1.63E-02 EARIICUIATES Sr-89 Ci 8.92E-05 1.37E-04 2.26E-04

~Er-90 C1 8.99E-07 6.28E-07 1.53E-06 Cr-51 Ci

___.lin-$.4 Ci 1.7QE-05 1.70E-05 Cn-58 C 1__

Fe-59 Ci QQ-60 C1 6.84E-05 1.97E-05 5.88E-05 1.47E-04 Zr-95 Ci

=

__,.Jb -- 9 5

_C1_

Ru-103 Ci As-110m C1 Sb-124 C1 1-131 C1 1.QQE-05 3.63E-05 5.51E-05 1.01E-04 Ca-134 Ci Os:136 C1

.__.,_Cs - 13 7 C1 7.81E-07 5.05E-06 5.83E-06 Ba-140 Ci 3.63E-04 2 33E-04 3.91E-04 1.04E-03 Ce-141-

_Ci_

Cc-lh4 C1 In-65 Ci Ia-133 Ji_

St,t-125 Ci La.l!tQ C1 4.87E-04 8.63E-04 7.13E-04 2.06E-03

_._En-15 Ci 1.44E-04 3,20E-05 5.70E-05 2.33E-04

_IQIAL C1 1.18E-03 L37E-03 1.28E-03 3.03E-03

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

.ZEDE/298 14 of 30 w

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DRESDEN NUCLEAR POWER STATION UNITS 2 AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT October Through _Dfrember '1982 D2/3 Chimary GASEOUS EFFLUENTS GROUND LEVEL RELEASES Docket Numbers: 50-237 SEMI-ELEVATED RELEASES 50-249 XX ELEVATED RELEASES CDNTINUOUS MODE NUCLIDES RELEASED UNIT OCTOBER NOVEMBER DECEMBER 4th QUARTER TOTAL EISSlDH_. GASES Xe-138-01 _

Xe-135m-

_sL 1.8HE+00 1.88E+00 Kt-87 01

_ _Kr_-88

_ _SL

^

Kt-85m C1 E

Kr-85 C1 1.12E-03 9.85E-04 1.94E-04 2.30E-03 I

Xe-135_

_C1 5.46E+00 4.29E+00 9.75EiD9_

Xe-133 Ci IDIAL Ci 7.34E+00 4.29E+00 1.94E-04 1.161+01 i

IDDlHES

__1-131 C1 3.95E-04 1.94E-04 7.71E-05_

6.66E-04 I-133 Ci 2.60E-03 9.67E-04 2.58E-04 3.83E-03 I-135 Ci 3.97E-03 1.30E-03 5.27E-03 IQTAL

_.01_

6 92E-03 2.46E-03 3.35E-04' 9.77E-03

._ J'ARI1CUlATES=

SI-82

_C1 5.99E-05 6.36E-05 5.94E-05 1.83E-04 Sr-90 Ci 5.35E-07 4.35E-07 4.06E-07' 1.38E-06

_ ___Cr-51

_ci_

1.16E-04 1.16E-04' Mn-54

_Di.

4.33E-06 1.73E-05 2.16E-05 Co-3B Ci

._ __Ee-59 C1 Cn-6D Ci

-2J6E-05 1.68E-05 3.61E-05 8.15E-05 Zr-95 Ji_

Nh-95

_C1

._.__Ru-103 C1 Ar-110m C1

___Sb-124 01 I-131

_Ci 2.88E-05 3.04E-06 3.18E-05 Ca-13h

_C1 Cs-136

_C1.

Cs-137 C1 1.41E-05 1.41E-05 Ba-140

_ __ C 1 2.97E-04 2 13E-04 3.05E-05 5.81E-04 Ce-141 Cl_

_ _J:e-144

_Ci_

l SL-65

_Ci Da-133

_fi

__._Sb-125 Ci_

l

.La-l!tQ

_Ci_

6.26E-04 4 63E-04 8.08E-05 1.17E-03 i

Ee-55 Ci 6.82E-05 8.01E-05 7.48E-05 2.13E-04 TQIAL

._fi 1.10E-03 9 11E-04 4 13E-04 2.42E-03 2

• The activity of thle nuclide is less than the LLD listed on the appropriate table ZEDE/298 15 of 30

DRESDEN NUCLEAR POWER STATION UNITS 2 AND 3-EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Julv Through _ December 1982 D2/3 Reactor Building Vent GASEOUS EFFLUENTS GROUND LEVEL RELEASES

_j Docket Numbers: 50-237 l

XX SEMI-ELEVATED RELEASES 50-249 ELEVATED RELEASES CONTINUOUS MODE BATCH MODE

,m.

nut;Lt.>ES RELEASED UNIT

-31.d QUARTER 4_1h QUARTER 3rd QUARTER Ath QUARTER

. _..... FISSION _DASES m-Xe-118-C1 Xc-135m C1 Er_81--

Ci __

'C1 Kr-J8 Kr-35m 01_

Kr-85

._.C1 1.Q1EQ5 Xe-135

._Ci_

q Xe-133

_C1__

1.002-08 1

TQIAL

_C1 1.05E-05 None-None I

_ _10 DINES 1-131 Ci 3.53E.04 2.49E-Db

__d -133

_C1_.

2.68E-03 2.16E-03 i'

I-135

_ _ _Hi_

3.79E-03 3.19E ' TOTAL C1-6.82E-03

_5 60E-03 l

PARTICULATES None None

__Jr-19 C1 3.64E-05

___3J5E-05 l

Sr-90 C1 2.51E-07 9.24E-07 Cr-51 CL 5.43E-03 5.15E-03

' fin -54 C1 2.16E-03 2.42E-03 Co-53 C1 1.48E 9.17E-04

-j Fe-59 Ci_

1232E-03 1.61E-03 Co-60 Ci 8.33E-03 5.16E-03

'Zr-95 C1

_ Nb-95 Cl

_{

' _ Ru-193 C1 Ag-110m C1 1.20 E04 1.19E-04 Sb-124

_Ci_,

2.57E05 7.88E-05 1-131

_C1_

1.29E-04

3. 98f-J5 Cs-134 C1

,_Ja -116 C1;I _

l

(

Cs-137

_01

_ En-1A0 ti_.

3. RE-04 1.23E-04

_ _Cc_1Al

_.Ci_.

___Qe-144-Ci

_ _Zn-65 C1 2.67E-04 1.56E-04

)

l Ba-113 C1 StL-125

_.Ci_

La-1A0 C1_

3.16E-04 1.23E-04 l

Mo-99

_Ci_

2.16E-03 1,.ft51-93__

F.e-55 C1 1.49E-02 z.24E-02 IRIAL C1 3.70E-02 4.00E-02 l

hone None p

The activity of this nuclide is less that. the LLD linted on the appropriate table.

ZEDE/298' 16 of 30

DRESDEN NUCLEAR POWER STATION UNIT 2 AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Julv Through Septembgr 1912 D2L3_ Reactor Building VenL _ GASEOUS EFFLUENTS GROUND LEVEL RELEASES Docket Numbers: 50-237 XX SEMI-ELEVATED RELEASES 50-249 ELEVATED RELEASES CONTINU0USJ 0DE

-NUCLIDES RELEASED UNIT JULY AUGUST SEPTEMBER 3rd QUARTER TOTAL FlSSION CASES Xe_ LIB C1

_.le-135m Ci

• 87 Ci Kr-88

_ci Y,r-85m Ci Kr-85 Ci 1.05E-05*

1.05E-QL_

Xe-135 Ci Xe-133 Ci 1.00E-08*

1.00E-08 TOTAL C1 1.05E-05 1.05E-05 10 DINES 1-131

_Ci_

1.34E-04 8.39E-05 1.35E-04 3.53E-04 I-133 C1 1.03E-03 5.73E-04 1.0RE-03 2.68E-03 I-135

_Ci_

2.68E-03 2.05E-04 9.01E-04 3x79E-03

....... TOTAL C1 3.84E-03 8.62E-04 2.12E-03 6.82E-03 PARTICUIATES__

Sr-89 C1 182E-06 1.27E-05 1.99E-05 3 6AEQ3__.

Sr-90 C1 2.51E-07 2.51E-07 Cr-51 Ji 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 Co-58 C1 3.03E-04 4.43E-04 7.29E-Q4 1.48E-03 Fe-59

.C1 2.24E-04 3.65E:04 7.84E-04 1.37E-03 Co-6D Ci' 1.86E-03 2.67E-03 3.80E-03 8.33 EQ3 2r-95 C1 Nb-95 01 Ru-103 Ci Ag-110m C1 1.98E-05 3.89E-05 6.10E-05 1.20E-04 Sh-11.4

_.C1._

1.76E-06 2.39E-05 2.57E-05 1-131 C1 1.51E-05 2 d6E-05 8.53E-05 1.29E-04 Cs-134

_Ci_

._._Cs-136' Ci Os-137

_Ci_.

Ea-lA0

_C1 5.81E-05 6.67E-05 1.91E-04 3.16E-04 Cc-lAl-

._Ci_

Co-144 Ci Zn-65

_.01_

1,33E-05 8.04E-05 1.61E04 2.67E-04 Ba-133 Ci

_ J b-125 C1

_ _La-lhD.

Ci

___L81E-05 6.67E-05 1.91E-04 3,16E-04

__. J0-99 C1 2.96 E04 6.03E-04 1.26E-03

__Zd6E-03

__Ec:15_

_.01_ _. 1 37E-03 4.95E-03 7.52E-03 1.49E-D2

_ _ IDIAL

_Ci 6.96E-03 1.18E-02

. __i,.8 2E-0 2 3,lDE-02 The activity of this nuclide is less than the LLD listed on the appropriate table.

See Supplemental Information ZEDE/298 17 of 30 I

DRESDEN NUCLEAR POWER STATION UNITS 3 AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT October __. Through December 1912 D2Ll.leattor Buildinglen.t___ GASEOUS EFFLUENTS r

GROUND LEVEL RELEASES Docket Numbers: 50-237 XX SEMI-ELEVATED RELEASES 50-249 ELEVATED RELEASES CONTINUOUS MJ}E_

NUCLIDES RELEASED UNIT OCTOBER NOVEMBER D'QbfjER 4th QUARTER TOTAL EISELON_GASIS Xe-138 Ci Xe-135m Ci Kr-87 C1 KC Ci Kr-85m C1 Kr-85 Ci Xe-135

_Qi Xc-133 Ci TOTAL C1

-10 DINES I-131

._Ci_

1.34E-04 8.17E-05 3.351-05 2.49E-04

'I-133 C1 1.17E-03 6.77E-04 3.14E-94 2.16E-03 1-135

_C1 1.74E-03 8.98E-04 5.50E-0; 3.19E-03 TOTAL Ci

__3204E-03 1.66E-03 8.98E-04 5.60E-03 PARIICULAIES _

Sr-89 C1 1.84E-05 6.35E-06 1.07E-05 3 55E-05 Er-90 01 7.95E-07 1.29E-07 9.24E-07 Cr-51 C1 1.56E-03 9.60E-04 L. 6 3-03 5.15E-03 tip-54 Ji_

6.13E-04 3.50E-04 1.46E-03 2.42 EQ3.__

00.58 C1 3.62E-04 2.28E-04 3.27E-04 9.17E-04 Fe-59 01 3.90E-04 2.35E-04 9.81E-04 1.61E-Q3__

C9 -60 C1 1.93E-03 1.16E-03 2.07E-03 5.16E-03 Zr-95 C1 i

Nb-95 C1 Ru-103 Ci 0

Ag_llDm C1 4.ji!2E-05 3.07E-05 3.86E-05 1.19E-04 Sb-124 Ji_

1.49E-05 4.31E-06 5.96E-05 7.88E-05 I-131 C1 3.98E-05 3.98E-05

_ J a-134

_Ci_

Cs-136

_Ci

~Ga:137

_01_

_...._f a-ll 0 C1

$_.99E-05 4.08E-05 1.2hE-05 1.23E-04 t

Cc-lhl ci

_..__Ce-144 Ji t

Zn-h5

_C1_

3.80E-05 Lt13E-05 im07E-04 1.5bE-04 Ila-133_

_CL

_____S b -125.

_Ci_

___la-140

_C1 6.99E-05 4.08E-05 1 26E-05 1.23E-04 1

a.,_Mo:29 31_

8.99 E04 SJAE-04 1.94E-04 1.65E-03 Ec-55

_CL 6.99E-03 2.65E-03 l 2HE-Q7 L24E-02 t

TDIAL C1 1.30E-02 6.27E-03 2.07E-02 4.00E-02 The activity of this nuclide is less than the LLD listed on the appropriate table.

2EDE/298 18 of 30 l

DRESDEN NUCLEAR POWER STATION UNITS 1, 2, AND 3 EFFLUENT AND WASTE DISPOSAL SD11 ANNUAL REPORT July-

.Through Deca =her 1982 LIQUID EFFLUENTS

+

SUMMATION OF ALL RELEASES Docket Numbers 10-50-237 50-249 EST. TOTAL UNIT ltd QUARTER 41h QUARTER ERROR,%

L61__f1SSION AND_ACHVATION PRODUCTS

1. Total Release Ci 8.98E-02

.1.23E-01 5.58 (not incl. tritium, gases, alpha)

2. Average Diluted Conc. During Period uCi/mL 1.43E-09 1.01E-08 1

3. Percent of Applicable Limit A

A L__lR111UM

.1. Total Release Ci 5.44E+00 4.11E+00 7.75

2. Average Diluted Conc. During Period uCi/mL 8.66E-08 3.37E-07 3.-Porcent of Applicable Limit A

A C J SSDLVID AND ENTRAINED _QASES

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

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

3. Percent of Applicable Limit A

A-D1__9RDSS_ ALP 11A RADIOACTIVITY

1. Total Release Ci-2.51E-03 LLD 15.1 E.

VOLUME OF WASTE RELEASED (prior to dilution) liters l5.87E+06 5.79E+06 5.00 F.

VOLUME OF DILUTION WATER USED DURING PERIOD liters 6.28E+10 1.22E+10 5.00 A Ths'information is contained in the Radiological Impact on Man section Lof this report. Total liquid release data is provided which includes fission and activation products, tritium, and dissolved and entrained gases.

ZEDE/298-19 of 30

DRESDEN NUCLEAR POWER STATION' UNITS 1, 2. AND 3 July Through Deca =her 1982 i

TABLE OF LOWER LIMITS OF DETECTABILITY Docket Numbers: 50-10 FOR LIQUID EFFLUENTS 50-237 i

50-249~

LLD (pC1/mL)

Sr-89 5.00 E-09 Sr-90 5.00 E-09 Ar-41 2.94 E-08 Mn-54 6.56 E-08 i

Co-58 5.62 E-08 Fe-59 8.04 E Co-60 9.73 E-08 Zn-65 8.07 E-08 Ru-103 5.77 E-08 Sb-122 6.63 E-08 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-C/

La-140 2.67-E-08 Ce-141 8.87 E-J8 Xe-133 1.33 E- 07 Xe-135 5.06 E 08 Cr-51 4.72 E 07 Fe 5.2 E -07 7

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 Cs-136 Not Determined

[

2EDE/298 20 of 30

DRESDEN NUCLEAR POWER STATION i

UNITS 1, 2, AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Julv Through December 1912 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.

Avarage 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 CONTINHOUS MODE BATCH MODE NUCL1 DES RELEASED UNIT 3rf QUARTER 4_th QUARTER 3rd QUARTER l

4_th QUARTER Sr-89

. 01_

. _ Sr-90 C1 1.01E-04

,__1 d1E-04

_.__.Ar 11 01 1

Mq-54 C1 1.43E-02 1.58E-02

_0o-58 Ci 3.48E-05 2.85E-04 Fe-59 C1 9.82E-05 Co Ci 4.87E-02 7.07E-Q2

___Zn-65 Ci Ru-103 C1 Sb-122 Ci

'Sb-124 C1

__I-131 C1

_ I-133 Ci I-135 Ji_

Cs-134 Ci Cs-137 Ci 9.47E-03 2.36E Ba-140 31

_El 0 C1 3.72E-06 t

Ce-141 Ci Cu-64 C1 3 d51-06 Rb-88 Ci 1.05E-04 Os-138 C1 4.75E-06 Fe-55 C1 1.67E-02 L21E-02 AL-.

Ci Ci SL._

(above)

Iolal_. Eor Perind__ _C1__

NONE NONE 8.95E.02 1 J3E-0.1 3n-133 C1 1.66E-05

._.le-135 Ci 5.98E-05 L30 E-05

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

ZEDE/298 21 of 30

DRESDEN NUCLEAR POWER STATION UNITS 1, 2, AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Julv Through Septembar_ 1982

_ J adwa te LIQUID EFFLUENTS Docket Numbers: 50-10 50-237 50-249 BATCH MODE NUCLIDES RELEASED UNIT July August September 3rd QUARTER TOTAL Sr-89 Ci Sr-20 C1 1.52E-05 3 73E-05 4.81E-05 1.01E-04 2

Ar-41 Ci Mn-54 C1 6. 8 7.E-03 4.63E-03 2.75E-03 1.43E-02 C0-58 Ci 3.48E-05

_ 32_48E-05 Fe-59 01 9.82E-05 9ajlE-05 go-60 C1 1.76E-02 1.69E-02 1.42E-02 4.87E-02 Za-65 Ci Ru-103 Ci Sb-122 Ci Sb-124 Ci I-131 Ci I-133 Ci I-135 C1 Cs-131 C1 Cs-137 C1 4.02E-03 3.14E-03 2.31E-03 9.47E-03 Ba-140 Ci La-140 Ci 3.72E-06 3.72E-06 Ge-141 Ci

_Cn-64 C1 3.25E-06 3J5E-06' Rb-88 C1 1.05E-Q4 1.05E-04 Cs-138

_ _ _ _ C1 4.75E-06 4.75E-06 Fs-55 C1 1.39E-02 2.14E-03 6.74E-04 1.67E-02 01 Ci C1 (above)

Iot.aLFor Period C1 4 d61-02 2.69E-02 2J0E-02 8 25E-02 _

Xe-133

_C1 1.66E-05 I d6E-05 Xe-135 Ci 7.36E-06

? 25E-05 2.99E-05 5.98E-05 1

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

ZEDE/298 22 of 30

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

.Ortober Through D1cembar_ 19&2 Radwaste LIQUID EFFLUENTS Docket Numbers: 50-10 r0-237 50-249 BAIClLliODE NUCLIDES RELEASED UNIT OCTOBER NOVEMBER DECEMBER 4th QUARTER TOIA L _

Sr-89 Ci Sx-90 C1 2.75E-05 4 22E-05 4.09E-05 L11E-04 Ar-41 Ci Mn-54 C1 1.53E-03 7 1QE-03 6.62E-03 1.58E-02 Qo-58 Ci 2.85E-04

__ 2 35E-04 Fe-59 C1 Co-60 Ji_

7.82E-03 2d9E-02 3.30E-02 7.S]E-02 7J1-65 Cl Ru-LO3 Ci Sb-122_

C1 Sh-124 Ci l-L31

_Ci_.

I-133 Ci

.135 C1 z

Cs-134 C1 Cm-137 C1 2.62E-03 7,48E-03 1.35E-02 2.36E-02 Ba-140 C1

. _ La-140 Ji_.

Ce-141

_fi

.En-55

_fi 3.03E-04 6.77E-03 4.99E-03 L2 G-Q2__

C1 (above)

IoFLEar_f.erio.d_ _C i_..

1.26E-02 5.18E-02 5.82E-02 L13E_0L___

Xe-133 C1 Xe-135 Ci 5.62E-06 7.3hE-06 1.30E-05 The activity of this nuclide is less than the LLD listed on the appropriate table.

ZEDE/298 23 of 30

DRESDEN NUCLEAR POWER STATION UNITS 2 AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORI Julv Through December. 19B2 CCSW LIQUID EFFLUENTS Docket Numbers: 50-237 50-249 1.

Number of Batch Releaseo 8.50E+01 2.

Total Time Period for Batch Releases: 1.05E+02 min 3.

Maximum Time Period for a Batch Release: 1.24E+00 min 4.

Average Time Period for Batch Releases: 1.24E+00 min 5.

Minimum Time Period for a Batch Release: 1.24E+00 min 6.

Average Stream Flow During Periods of Release of Effluent into a Flowing Stream: 1.67E+06 L/ min CONTINUOUS MODE BAIClLfiODE NUCLIDES RELEASED UNIT 3rd QUARTER

!Lth QUARTER 3rd QUARTER lth QUARTER t

~

Sr-89 Ci Sr-90 01 Ar-41 Ci Mn-54 Ci 3.26E-05 1.78E-05 Co-58 Ci Ee-59 C1 3.44E-05 3.17E-05 C.o.-60 Ci Zn-65 01 Ru-103 C1 Sb _-122 Ci Sb-124 Ci I-131 Ci I-133 Ci I-135 Ci Cs-134 Ci 4.94E-05.

1.42E-Q5 Cs-137 Ji_

1.15E-04 4.37E-05 Ba-140 Ci 5.60E-07 La-140 C1 5.60E-07 Ce-141 Ci fr-51 C1 Fe-55 C1 2.06E-05 1.34E-05 Ca-L31

_Ci 4 12E-07 C1 Ci Ci

_C1._

C1 l

(above)

I_nial_ Eor __Egriod C1 NONE NONE 2.52E-04 1.22E-04 Xe-133

_Ci Ke-135 Ci

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

ZEDE/298 24 of 30

DRESDEN NUCLEAR POWER STATION UNITS 8 AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUA1 EPORT

__luly Through _S.eptember 193.9 CCSW LIQUID EFFLUENTS Docket Numbers 50-237 50-249 BATCILMQDE NUCLIDES RELEASED UNIT JULY AUGUST SEPTEMBER

?rd QUARTER TOTAL __-_

Sr-89 C1 Sr-90 Ci Ar-41 Ci Pin-54 Ci 2.08E-05 7.15E-06 4.61E-06 3.26E-05 0o-58 C1 Fe-59 Ci Co-60 Ji_

1.74E-05 9J 7E-06 7 3 H -04 3.AM-05_.

Ztt-b5 Ci Ru-LO3 C1 Sb-122 0i Sb-124

__ Ci J-131 C1 I-133

_Ci

.1-135 C1 Os-134 Ci 3.35E-05 9.61E-06 6.25E-06 4.94E-05 Ca-137 C1 5.87E-05 3.22E-05 2.40E-05 1.15E-04 Da-140 01 La-140 C1 Cc-J41 Ci Cr-51 Ci fe-55 C1 2.06E-05 2.06E-u5

_Ci C1 (above) 2.52E-04 10181 For Period C1 1.51E-04 SJ6E-05 4 22E-05 _

Xe-133 01 Xe-135 C1

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

ZEDE/298 25 of 30

DRESDEN NUCLEAR POWER STATION UNITS 2 AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT October _ Through December. 1982 CCSW LIQUID EFFLUENTS-Docket Numbers 50-237 50-249 BAICll MODE NUCLIDES RELEASED UNIT OCTOBER NOVEMBER DECEMBER 4th QUARTER TOTAL St-89 Ci Sr-90 Ji Ar-41 Ci Mn_kh Ji._

1.6&E-05 7.85E-07 3.93E-07 IJ8E-05 Co-58 Ci Fe-59 Ci Co-60 C1 1.86E-05 1.05E-05 2.64E-06 3.17E-05 Zn-65 C1

_Ru-103 C1 Sh-112 Ji Sb-124 Ci I-131

_.01 I-133 C1 1-135 Ci Cs-134 C1 1.34E-05 7.54E-07 1.42E-Q5__

Cs-137 01 2.94E-05 9.09E-06 5.18E-06 4.37E-05_.

Bo-140 C1 5.60E-07 5.60E-07 La-140 Ci 5.60E-07 5.60E-07

.Cc-141 Ci Cr-51 C1 Fe-55 Ci 1.34E-05 1.34E-01_

Cs-136 Ci_

4.12E-07 4d2E-07 Ci (above)

Intal._for Period

_ _Ci_

7.91E-05 3.38E-05 9.38E-06 1.22E-04 Xm-133 Ci Xe-135 Ci The activity of this nuclide is less than the LLD listed on the appropriate table.

ZEDE/298 26 of 30

DRESDEN NUCLEAR POWER STATION-UNITS 1, 2. AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT-luly Through Dec_ ember __191U!

Docket Numbers:50-10 50-237 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 50-249 Est-Tot.

Ac_SDLID WASTE _S}i1PPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)

Err m &'

1. Type of Waste Unit 6-month period tr.3 5.62E+01 a.

Spent resins, filter sludges, evaporator bottoms, etc.

01 9.00E+02 l

3 m

7.10E+02 b.

Dry compressible waste, contaminated equip., etc.

Ci 9.92E+00 3

m 1.42E+01 4

c.

Irradiated components, control rods, etc.

j Ci 3.97E+00 j

d.

Other (describe)

Ci 0

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

Ci E

Co-60 54.1 %

4.87E+02 Fe-55 21.2 %

1.91E+02 Mn-54 5.64 %

5.08E+0L Cs-137 10.9 %

9. 81 E+0.L Ni-63 6.46 %

5 81E+01 b.

Co-60 25.3 %

2.51E+00 Fe-55 59.9 %

5.MEiD0_

Mn-54 1.14 %

1.13E-01 Cs-137 11.8 %

1.17E+00 Other i

n.

Co-60 2.0.2

% _8.02E-01 l

Fe-55 68.0 %

2.70E+00 l

Mn-54 1.72 %

6.83E-02 Cs-137 9.38 %

3 12E-01 Other L

3. Solid Waste Disposition l

NiltiDER_OF SHIPMENTS tiQHE OF TRANSPORTATION DESIINATl0N 23 Motor fre4.ght (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 5

Motor freight (exclusive use only)

Westinghouse DDR Madison, PA l

B.

IRRADIATED FUEL SHIPMENTS (Disposition)

NUMDEILDE_S111EliENIS MODE _.QE_TRANSE0RIATION DESTINATION l

None l

ZEDE/298 27 of 30

DRESDEN NUCLEAR POWER STATION UNITS-1,:2, AND 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Julv Through Dictmher

.19 BR Docket Numbers: 50-10 50-237 50-249 ABNORMAL RELEASES A.

LIQUID 1.

Number of Releases:

0 2.

Total Activity Released:

0

(

B.

GASEOUS 1.

Number of Releases:

0 2.

Total Activity Released:

0 l

l TOTAL 0

SUPPLEMENTAL INFORMATION I

.At 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 l'

Vsntilation System Effluent was being collected.

Because the normal sample vessel was

' unavailable, another container was used. The beaker selected to obtain-the sample had been previously used for a crose check program and thus contained approximately 1.0E-05 curies of Kr 85 and 1.0E-08 curies of Xe 133. The contents of the contaminated beaker resulted O.

I a high radiation alarm in the main control room. The alarm *:as 1Lnediately reset.

~No Technical Specification limits were exceeded during this event.

T1.e safety significance of-this incident is minimal because the Reactor Building Ventilation radiation monitors I

ware operable =and automatic isolation would have occurred if necessary. Labeling of the sample vessels was changed to clearly state that they are to be u.ed for sampling purposes or for calibration standards and cross checks.

1 ZEDE/298 28 of 30

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COMPLIANCE STATUS -~10 CFR 50 APP.

I-INFANT. RECEPTOR

.--------- %-0F APP I'.

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% OF LIMIT.

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T.IVF6 N, j 4 4 q% -?s y# ir M 3 1 -~ 5 "EM iTHISHIS ALREPORT-FORLTHEJCALENDARLYEAR 1989c 5 M, 'yko^ h'. .IN SO, j m I h s a: d V;y M a.twwg%il .e:' ?T-t - rf .,2 W i

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' COMPLIANCE STATUS - 40'CFRS1'41) ~

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.1 ANNUAL LIMIT!._ '%:0FJLIMITs

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Ya f b r. =--t r. w-9 %$MP ', ' e - 8 N ADULTURE'CEPTOR'b 'N -W P %;; y n p yW L M u. ~ m ,,l / e. 4 + n ^ c- ~. = ~ ~~ ~ ~ j"., a ,,U, nG'; pj ' ~ 19891ANNUAQ REPORTl s s eMQGv 9y j MAXIMUN," DOSES M MREN W RESULTINGTFROM1 LIQUID EFFLUENTSR' L ' N, m c k MM JPERIODiOF#RELEASEj-E01/. 01789)T0?l2/31/89; LCALCULATEDf00/02f90;>>- 1 0 i , en y 2 gas r m ~ ~-J n [ ~ ^ -[' rl 's n. '.3 $M s L 13RD n ' 'M4,J4Ttth.,! M (ANNUAE a >l [ 4 ?1STl.. ,,U2NDi (n;. f i.... m MdMDOSEiTYPET DUARTER; /GUARTERe: 100ARTERJ 00ARTER] V ] sJUL-SEP;l iOCMDECF 's w: 7f W M M- +L%:. 4 = LJAN-MAR? J APR-JUN i m, w -3 u# s, i. - ? he d-n y' x y. g-15 y .s... 2. = m-1 ( a s. .<m. 4.-a v - lWn2 y , M TOTAL? 12.12E-04 i. 2.05E-04: ' :1:.76E-04D A4i69E-04? J1.06E f "gs,m a F J' D D-.,'/i. ,0,. ? 115 6 EL O'3,:: .n % # l;v ld N k BODYs-t mm a. p4 _ v N ! "2.56E-04.. 74 05E',0 4 ; > 5 1 INTERNAL,? L2.98E-04% J3~.05E-04' N .,x l%,4 fe' M, R $0ROA ~ ~ n + . LIVER) TIVER ~ LIVER ~ ?LIVERL R..IVERa - P W: ~ M+ q~

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I' l ZEDE/298 L' 30 of 30 i

W ++ w. ~ h ':[. Ctto 00t300 STaf!N Js170soseberIN9-35 ft. 015 $ND and O!E OllItfl# 150 35 ft. OlffBBf!AL ftIMHfRE HER Of 008tHAf!05 s 4414 END . 0!IItflN CLall Stu!L!?! C1458 Clatl ; I - ' III R Ist ! Et St Mt 8 IN - H III I ON N NV 10fiL IV N H I $$ 5 5 'TMAL E0.05 .00.00 .00.00 .00 .00 .00.00 .00 .02 .02.05 .M .07 .11 .41 .41 .W .00 .02.02 .00 .00 .00.02.00 .00.00 .00 .05 .07.00.02.02 .23 .23 9 80.45 .02 .00 .00.02 .02.00.05.05 .07 .05 .02 .00 .00 .02.07 .43 .43

• I

.25 -.23.32 .25 .27 .41.27.11 -.14.20.20 .09 .25 ill.16.16 3.42 3.42 3$$.50 .75.45 .61 .45 .M .M .45.32 .45.23.29.25.20.27.39 6.H 6.34

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.29 .39.14.29.50 .45.57 .23 .40 27 .M .25 .27 .10.10 .H 5.19 5.19 - E.25 .16 .16 .09.16.14.07 .07 .11 .07 .25 .14 .07.16.27.27 2.45 2.45 10.44 - 50 .57 '.M .20 .07.16.25.25 .20.29 .20.29 .16 .40 .40 .41 .79 5.17 5.17 i ' IO .07 .23 .14 .09 .11 .09.39.25 .11 .14.09.07 .14 .07 .M .07 2.22 2.22 4H.07 .11 .20 .14 .07 .10.16.32 .14 .09 .10.14.14 .07 .09.02 2.15 2.15 3' I .77 .72 2.63 1.31 .72 1.16.42 .39.63.59 .57 .45 .70 .41 .25.61 12.73 12.73 7 88.63 .61 1.02.59 1.20 1,43 1.H.1.59 1.31 1.20 .77.29 1.38 1.H .79.97 15.00 15.00 5.14 .07 .02 .00 .43 1.11 .H .75.61 .54 .45 .16.14.59.44 .20 6.H 6.M E .00 .00 .00 .00.16 .77 .M .02.02.07.41 .09 .00.05.10 .05 2.00 2.00 M.50 to .09 .29.10 .05.05 .09.09 .41 .43.39 .23 .50 .H .91 .H .63 6.00 6.00 W. 07 .00 .07 .05 .07 .02.11 .11 .27 .02 .14 .14 .14.14 .00 .05 1.43 ' 1,43 4 80 .00 .02 .00 .02.05 .02.05.05.14 .38.27.20.20.09.02.11 1.43 1.43

• I

.06 .62 .H .07 .27 .27.!! .H .N .H .63 .M .77. 00.93.91 9.90 9.90 1 88 .H .14 .14 .02.02 .14.16.41 1.00.79 .H .H .57.52.29.32 5.96 5.96 25 .00 .00.00 .00.00 .05.00.05 .07.02.02.05 .00.00.00.00 .25 .25 5 .00 .00 .00 .00 .00 .00.00 .00 .00 .00 .00 .00 .00 .00 .00.00 .00 .00 1 IO .05 .01 .00 .00 .00.00.00 .07 .32 .20.11.14 .07.05 .39.11 1.56 1,56 I 1 10 .02 .00 .00 .00.00 .00 .00.00.07 .20.16 .02 .05.05.02.02 .61 .61 1 3 80 .00 .02 .00 .00 .00 .00 .00 .00.09.05.11 .02 .07.07 .02.05 .50 .50 l' I .25 .02.00 .00 .00 .02.02 .27.61 .M .32 .14 .M .32.95 .H 4.03 4.83 l 1 $$.05 .00.00 .00.00 .02 ' 02.02.32 .M .23 .07 .20.00.07.02 1.M 1.M 0 5 '.00 .00.00 .00 .00 .00.00 .00 .00 .00 .00 .00 .00.00.00 .00 .00 .N 5 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00.00 .00 .00 .00.00 .00 .00 .00 0.H II .00 -.00.00 .00 .00 .00 .00 .00.02.05.02 .00 .00 .07.05 .00 .20 .20 1 R .00 .00.00 .00 .00 .00 .00.00 .02 .00.02 .00 .00.05.05 .00 .14 .14 9 IU.00 .00 .00 .00.00 .00.00 .00.02.05.05 .00 .00.02.02.00 .16 .16 1 I .02 .00 .00 .00 .00 .00.00 .00 .14.14.02 .02 .00 .00 .07 .02 .52 .52 288 .00..00 .00 .00 .00 .00 .00 .00 .02.00.02.05 .00 .00 .00.00 .09 .09 p L 45 .00 .00.00 .00.00 .00.00.00.00.00.00 .00 .00 .00.00.00 .00 .H E .00 .00.00 .00 .00 .00.00 .00 .00 .00 .00 .00 .00 .00.00.00 .M .00 1.11 D .00 .00.00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 2W .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00. 00 .00 .00 .00 5H .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 I .00 .00 .00 .00 .00 .00.00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 i 3 85 .00 .00 .00 .00 .00 .00.00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 1 38 .00 .00 .00 .00 .00 .00 .00 .00 .00.00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00

e-CICo DitS00 $74f100 Julf Decesher 1989 35 ft. III0 SPEED and VII0 D!Ittfl0B 150 35 ft. DIFTIBIsfl4L ftIPERATRE SPED D!tttflog class stal!LQ CLASS CLASS I et E ~ III E E$t 51 SSI 5 $5v St USv V VIV IV III 70 fat EU IU $8 5 55 E-ES TOTAL , 30 .00 .00 .00 .00 .00 .Ct .00 .00 .00 .00 .00.00 .00 .00 .00.00 .00 .00 330 .00 .00 .00.00.00.00.00.00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 258 .00 .00 .00 .00.00 .00.00.00.00 .00 00.00 .00.00 .00.00 .00 .00 -i I. 00.00 .00 .00.00 .00 .00 .00 .00 .00 .00 .00 .00 .00.00 .00 .00 .i 3IS.00 .00 .00 .00 .00 .00 .00.00 .00.00 .00.00 .00 .00 .00 .00 .00 .00 8E .00 .00. 00.00.00 .00.00.00 .O .00 .00.00 .00 .00 .00 .00 .00 .00 E8 .00 .00 .00 .00.00 .00 .00.00 .N .00 .00 .00 .00 R.00.00 .00 .00 .00 IV .H .00. 00.00 .00 .00.00 .00 .00 .00 .00.00 .00 .00 .00.00 .00 .00 3 10 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00.00 .00 .00 .00.00 .00 .00 9 SV .00.00 .00 .00 .00 .00.00 .00 .C0 .00 .00 .00 .00 .00 .00.00 .00 .00

• I,.00

.00 .00 '.00 .00 .00.00.00 .40..00 .00 .00 .00 .00 .00.00 .00 .00 l 4 55.00 .00 .00 ; 00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 6 IS .00 .00 .00 .00.00 .00 .00.00.00 .00 .00.00 .00 .00 .00 .00 .00 .00 l IS .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00.00 .00 .00 j .00. l ) EU .00 .00 .00 .00.00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 G IU .00 .00 .00 .00.00 .00 .00.00 .00 '.00 .00 .00 .00 .00 .00 .00 .00 .00 i f50 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 I .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00

4 53

.00 .00 .00 .00 .00 .00.00 .00 .00 .00 .00.00 .00 .00 .00 .00 .00 .00 65 .00 .00 .00.00 .00 .00.00 .00 .00 .00 .00 .00 .00.00.00 .00 .00 23 .00 .00 .00 .00.00 .00.00.00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 [ EU .00 .00 .00 .00 M.00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 l IU .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00.00 .00 .00 .00.00 .00 .00 j C 30 .00 .00 .00 .00.00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00.00 .00 .00 AI .00. 00 .00 .00.00 .00.00 .00 .00 .00 .00 .00 .00 .00 .00.00 .00 .00 L$$ .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00.00 .00 .00 .00.00 .00 .00 I ES .00. 00 .00 .00.00 .00 .00 .00 .00 .00 .00 .00 .00.00 .00.00 .00 .00 I IS .00 .00 .00 .00.00 .00 .00 .00 .00 .00 .00 .00 .co.00 .00.00 .00 .00 .00 707 5.37 5.10 6.43 3.69 4.71 7.05 5.23 6.44 4.64 7.45 7.0% 4.30 7.70 6.71 7.00 7.00100.0013.34 4.62 4.67 31.40 't.6611.78 4.53100.00 l 1 $D.75 '.72 .39 ,11.20 .34 .34 .68 1.06 .64 .64 .82 1,43 1.59 1,74 1.65 13.34 0 IU.16.25 .27 .14.18 .11 .52.36 .48 .41 .41 .32 .39 .29.18.16. 4.62 8 30.11.14 .20 .20 .14 .23 .20 .41 .43 .43 .66 .39 .41 .25 .18.25 4.67 I 2.15 1.79 3.60 1,63 1.27 1.04 1.22 1.45 2.45 1.99 1.74 1.06 2.61 1.84 2.36 2.34 31.40 f $5 1.52 1.54 1.65 1.22 1.68 1.97 1.59 2.47 2.97 2.41 1.90 1.04 2.40 1,77 1,43 1.70 29.66 t 0 IS .43 .45 .16 .29 .93 1.61 1.22 1.02 1.16 .64 .84 .45 .41 .77 .66 .54 11.78 ) fR$.25 .16 .16 .09 .32 .93.14.09 .14 .14 .46 .23 .07 .20 .45.32 4.53 i O

1 e i CICe 8tISDEI STA!!0E July Noeaber 1H9 300 ft. IIB $ PED and flR D!tICT100 300% ft. DIFFIEDf1E 7tIPEt479tf '1 IEEER OF 085I894f1085 (M2 SPEID DIIRCf!0I CL&85 574BILITI class CIA $$ I MI Rt DC' t' - ist St S5t 8 SSI $5 ISV I UR H IIV 70fE D BU 80 I SS E R$ TOTAL D .00 .00 .D6 .00.00.00.00 .W .00 .00.00 .00 .00 ~.00~.00 .00 .00 .00 ( .R .G0.00 .00 '.00.00.00 .00.00.00.00 .00 .00 .00 .00 .00.00 .00 .00 9 80.00 .02 .00 '.00.02 .00.00 .00.00 .00 .00 .00.00.00 .02 .02 .09 .09 I .07 .02 .02 .16.09 .18.34.11 -.00.07 .H .14 .16.16 .07 .07 1.60 1.60 ) 355.05.05 .05 .05.09.02.00 .02 .09 .07.05 .02 .02.02 .09 .02 .71 .71 IS .00 .00 .02 .00.09 .02 .00 .02.05 .05.02 .02 .05.02 .02.02 .41 .41 IS .00 .00 .00. 00 '.02 .00.00 .00 .00 .00.02 .00 .00 .00 .02.00 .07 .07 2.t9 R.05 .00 .00 .00.00 .00 .00 .00.00 .00 .00 .00 -.00 .00 .00 .02 .07 1 .07 R.14 .07.02. 00.00.02.02 .00.00 .00 .00 .02.00 .00 .02 .07 .44 444 4 80.28 .16 .07 .09 ~.00 .14.14 .00.02 .11 .07 .07 .11.!! .09 .21 1.67 1.67 -I .09 .32. 53 .73 .H .69 1.03 .H .69 .50 .30 .53 .48 .37 .23.26 7.75 7.75 7 SS.14 .16 .25 .39 23.32 .H .30.16 .44 25.15.14 .09 .14 .H 3.60 3.60 t L IS.05 .07 .23. 14 .14 .07 .09 .14.11 .16 .16 .H .11 .00 .18 .07 1.90 1.90 l-ES .00 .02 .02 .07 .00 .00 .07 .07.00 .02.02.05.02.00 .02.00 .39 .39 15.42 R.09 .00 .00 .00 .00 .00 '.00 .00 .00 .00 .00 .00 .00 .00 .02 .18 .30 30 10.11 .11 .09 .05.00.00.00 .00.00 .00 .00 .00 .00.09 .14 .14 .76 .70 0 SU .H .23 .30 .25 .16 .09 .14.02.11 .09.05.05 .21 .21 .32 .H 2.41 2.41 l 3.41 .99 1.33 1.74.55 .60 1.01 .60 .H .76 1.22 .H .73.60 .50 .46 13.07 13.07 t 1 $$ .41 .44 .H .62.55 .71 .96 .H .53 .64 .46 .H .46.32 .37 .09 8.87 8.87 L 2 IS.11 .23 .07 .14 .44 .09.00 .69 .37 .14.21 .37.16.16 .37 .14 4.56 4.54 L ES.00 .05 .02 .07.09 .02.09 .11.14.05.05.11.07.02.00.02 .92 .92 30.90 D.11 .09 .00.00.00 .00 .00 .00.00 .00 .00 .07 .00.02 .05.14 .48 44 1W.05.11 .02 .00 .00 .00 .00 .02.00.00 .05 .09 .05.09 .16.14 -.74 .78 3 80 02 .05 .09 .02 .00 .02 .00 .14.14 .09.07 .09.25.25.21 .11 1.60 1.60 3 1.01 .66 1.01 .25.18.21 .07 .73.92 1.17.05.69.92.85 .00.69 11.00 11.00 ' 1 38 .60 .21 .44 .23.37.53.57 1.10 1.54 1.40.00 .44 .57 1.10 1.15 .H 11.76 11.76 8E.18 .11 .14 .02.09.14.32 .H .50.55.57 .73 .32.25 .44 .32 5.43 5.43 ts .07. 07.05 .00 '.00.02.11 .16.00.14 .02 .21 .02.00 .05 .00 .H .H 32.00 ':0 .02 .05 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00.00 .07 07 1W.02 .00 .00 .00.00 .00 .00.02.00 .02 .00 .02.00.00.09.11 .30 .30 9 50,.05 .07 .00 .00.00 .00 .00.00 .07 .07 .07 .02 .00.02 .00.02 .39 .39 I .87 .78 .21 .00 .00 .00 .02 .18.57 .H .48 .H .76 .66 1.26 .78 7.57 7.57 2 55.26.21 .07 .00.02 .16 .07 .14.53 .96 .55.21 .H .39 .18 .32 4.42 4.42 4 IS .07 '.00 .00 .00.00.00.11 .00 .44 .28.02 .09 .05 .00 .02.05 1.17 1.17 IS .07 .00.00 .00.00 .00 .02 .00 .00 .07 .00 .H .02.00 .00 .02 .30 .30 14.21 D .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00.00 .00 .00 .00 00 210 .00 .00 .00 .00.00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00.00 .00 .00 5 50 .00 .05 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .05 .05 I .23 .07 .00 .00 .00 .00 .00 .02.44 .34.16 .02 .23.16 .30 .25 2.27 2.27 385 .00 .02 .00 .00 .00 .00 00 .02.23.21 i30 .07 .28.09 .02 .00 1.24 1.24 1 IS.02 .00 .00 .00 .00 .00 .00 .00 .00 .02 .00.02 .00 .00 .00 .00 .07 .07 IS .00 .00 .00 .00 .00 .00 .00 .00 .00 .02 .00 .00 .00.00 .00 .00 .02 .02 3.65

.l j

1 Ctto 085D5 STATIOR.

hly Decembet IN9 300 ft. W12 SMD and f ID D!f!Cfl08 = M0 35 ft. 0;mIIIf!AL TMPDAfft! SPED - titICTICI CL&$$ STAl!LITT CLASS 'i CLAES I HE :! = Bt ISI St $$! 5-58V 89. V55 I UM N WW TOTAL EV IU St I SS IS U TOTAL ' 1 N .00 .00 .00 .00 .00 .00.00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 3W .00 .00.00 .00 .00 .00.00.00 .00 .00 .00 .00 .00 .00 .00.00 .00 .00 2SU .00 .00 .00 00 .00 .00 .00 .00 .00 .00.00 .00 .00 .00. 00.00 .00 .00 I.05 100 .M .00.00 .00 .00 .00 .05.05 .00 -.00.00. 11 .07 .05 .37 .37 3 SS .02 .00.00 .00 -.00 ~.50 .00 .00 -.00 .00.00 .09 .00. 00.02.00 .14 .14 8E .00 .00.00 .00 .00 .00. 00 .00 .00 .00.00 .00 .00 .00 .00.00 .00 - .00 ES .00 .00 _.00 .00.00 .00 .00.00 .00 .00.00 .00 .00.00 .00.00 .00 .00 .50 '. H .00 .00 .00 .00 .00 .00 .00 .00 '.00 .00'.00 .00 .00 .00 .00 .00 .P .00 3W .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00.00 .00 .00 ( 9 $U .00 .00 .00 .00 .00 .00 .00.00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 I .02 .00 .00.00. 00 .00 .00 .00 .00.00 .00 .00 .00 .00 .00 .02 .02-4 55 .00 .M .00 .00 .00 .00.00 .00 .00 .00.00 .00.00 .00 .00 .00 .00 .00 6E .00 .UU .00 '. 00 .00 .00 .00 .00 .00 .00 00 .00 .00 .00 .00.00 .00 .00 l 5 .00 .00 .0J .00 .00 .00.00 .00 .00 .00 .00 .00 .00 .00 .00.00 .00 .00 .02. N .00. 00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00.00 .00 .00 .00 .00 -- 4 W. 00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00.00 .00 .00 i f $U .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00.00.00 .00 .00 .00 .00 I .00 .00.00 .00 .00. 00.00 .00 .00 .00 .00 .00 .00 .00 .00.00 .00 .00 4SS .00 .00 .00 .00 .00. 00.00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 6E .00 '.00 .00 .00.00 .00 .00 .00 .00 .00.00.00 .00 .00 .00.00 .00 .00 5 .00 .00.00 .00 00 .00 .00 .00 .00 .00 .00 .00 .00.00 .00.00 .00 .00 '.00 ' H '.00 .00 '.00 -.00 .00 .M .00 .00 .00-.00 .00 .00 .00.00 .00 .00 .00.00 .W .00 .00 .00 .00 '. 00 '.00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 C 50 .M .00 .00 .00.00 .00. 00 .00 ~.40 .00.00 .00 .00 .00 .00.00 .00 .00 AI .00 .P .00 .00 .00 .00 .00 .00 .00 .00.00 .00 .00.00 .00.00 .00 .00 L58 .00 .00.00 .00 .00- .00 ' 00 .00 .00.00 .00 .00 .00 -.00 .00.00 .00 .00 l IE .00 .00.00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00.00 .00 .00 5 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 '.00 .00 .00 .00.00 .00 .00 .00 l. L l l 70f 5.09 5.52 5.69 5.02 3.50 4.06 6.14 7.04 0.76 9.19 6.90 6.30 6.53 6.19 7.50 5.49100.00.92 2.29 6.21 43.65 30.74 13.55 2.64 100.00 8N.20.14.00 .00 .00 .00.00 .00 -.00 .00 .00 .07 .00.02.07.34 .92 OW .37 .30.14.05 .00.02.02.05 .00 .02.05.14 .05.10.41.50 2.29 8N .44 .57.46 .37 .10 .25.24.21 .34 .37 .25.23 .57.60.64 .46 6.21 I 2.75 2.44 3.09 2.09 1.17 1.67 2.27 2.29 3.65 3.53 3.09 2.41 3.20 2.91 3.23 2.57 43.65. 1 SS 1.49 1.12 1,44 1.20 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 0E .44 .41 .46 .30 .05 .32 1.33 1.54 1.51 1.24 .99 1.33 .69 .44 1.06.60 13.55 . T IS.14 .14.09 .14 .11.05 .30 .34 .14 .32 .11 .46 .14 .02 .09 .05 2.64

l I \\ CECO INE8EN MLIAR P0lER STATION j IETEWOL001 CAL MTA i OATE ... W!@ 8 PEED.... .WI@ D!lECTION. ...W!@ $!0MA... TEF ...DIFFT... ...... DEWPOINT...... PIECIP W-DF/:'

• 35 150 300 35 150 300 35 150 300 35 150 300 35 150 300 10 t12-09 1 6.5 13.1 17.8 M2 M4 M7 0

7 5 60.0 .2 .5 55.5 M.3 M.5 .00 t-12-99 2 4.0 8.2 !!.6 M5 354 357 12 6 4 58.7 .3 .7 M.4 53.2 53.5 . )0 >12-09 3 4.3 9.0 13.5 337 350 357 9 6 3 57.1 .0 53.4 52.2 52.1 .00 9-12-99 4 3.7 8.1 12.4 333-350 358 7 5 3 55.4 .4 .5 53.0 51.7 51.8 .00 t-12-09 5 4.7 9.8 13.9 M7 354 359 6 4 3 M. ! .3 50.8 49.7 49.5 .00 t-12-09 6 5.4 !!.! 14.9 352 N0 4 8 5 3 53.5 .3 8 47.6 4.3 45.6 .00 t12-09 7 5.3 10.3 13.3 353 1 4 8 4 3 53.6 .6 -1.3 4.4 44.9 44.7 .00 P12-09 8 5.3 9.6 !!.6 356 2 7 10 5 5 M.4 .9 -1.8 4.3 44.5 44.3 .00 bl2-99 9 7.1 13.2 14.4 1 5 7 5 4 56.1 -1.2 -2.1 43.5 41.6 41.2 .00 t-12-99 10 5.7 10.7 !!.7 20 19 18 13 9 6 58.4 -1.3 -2.4 41.0 39.1 30.8 .00 F12-99 11 5.4 8.8 9.3 21 21 20 15 0 9 60.8 1.1 -2.2 40.1 30.0 37.8 .00 t-12-99 12 5.7 8.5 9.4 10 9 20 16 15 64.3 -1.7 -2.9 30.9 E.7 %.2 .00 912-99 13 6.0 0.4 9.0 17 23 24 38 21 20 65.3 -1.3 -2.7 37.9 35.9 35.2 .00 t-12-49 14 4.9 7.4 8.2 21 21 20 21 13 12 65.4 .9 -2.0 37.3 35.0 M.7 .00 9-12-99 15 4.4 7.9 8.8 9 13 19 10 65.2 .7 -1.5 39.9 N.8 36.3 .00 t-12-99 16 2.6 5.8 7.4 M9 1 7 9 7 5 64.1 .2 .7 43.0 30.4 M.3 .00 t12-99 17 3.6 8.1 10.7 M9 356 360 6 2 2 63.4 .1 .3 44.7 41.4 37.9 .00 912-09 18 2.9 6.4 8.4 33 42 43 26 29 28 62.1 .2 .2 4.3 43.4 42.0 .00 >12 49 19 3.9 6.9 8.6 48 56 59 15 10 8 60.9 .0 .6 45.0 43.6 42.2 .00 9 12-99 20 2.9 5.3 7.5 57 65 4 9 5 4 60.3 .1 .5 43.8 41.5 40.2 .00 l 9 12-09 21 2.7 6.8 9.3 26 35 41 13 14 9 59.3 .4 .2 4.3 43.2 41.2 .00 t-12-99 22 3.7 8.3 11.2 350 399 5 14 13 58.5 .3 48.9 4.6 45.6 .00 9-12-09 23 4.6 10.5 13.9 13 17 20 12 7 6 57.5 .3 .8 49.4 47.8 47.8 .00 t t 12-09 24 5.1 !!.2 14.4 9 14 20 9 4 3 56.0 .6 50.8 48.7 48.7 .00 ( TOTAL .00 l l L w _.m_.,_____._,v- "F ' ' '}}