ML20246F428

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Radiological Effluent Rept for Jan-June 1989
ML20246F428
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 06/30/1989
From: Eenigenburg E
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
89-634, NUDOCS 8908300329
Download: ML20246F428 (46)
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Morris, Illinois 60450 ,  !

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August.,24', 1989f r

y EDE LTR: #89-634 .l 1

U.S.' Nuclear Regulatory Commission

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Document Control Desk'.

Washington,'DC 20555

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Subject:

Dresden Nuclear' Power Station {

L0perating Report..

NRC Dockets,50-10.'50-237. 50-249

.-To Whom I't May' Concern:

,3 .

Enclosed.is'the radioactive effluent report for January.througli June 1989' l lfor..Dresden Nuclear Power Station.' j A: copy of this report will be furnished to the NRC. Resident Inspector. ,

'i

' Sincerely Yours, l

\!: .

E. D. Ee g bur .

Station ger ~l Dresden Nuclear Power. Station

EDE:SK:jt  ;

I

, Enclosure ]

l cc: 'S. Kova11 I J.C. Golden File /NRC File / Numerical ,

0727a

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8908300329 890630

, PDR ADOCK 05000010 l R PDC i 2__:________ _ _ _ - _ - _ - _ _ _ _ - --  !

a s DRESDEN NUCLEAR POWER SIATION DOCKET NOS. 50-10, 50-237, 50-249

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REGULATORY LIMITS Gaseous Effluents - Dose This Specification is provided to ensure that the dose at the unrestricted area boundary from gaseous effluents from the units on site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. The annual dose limits are the doses 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 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 II, Column 1 and the contribution to overall dose to less than 0.1 percent of the total station annual release. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the unrestricted area boundary to less than or equal to 500 mrem / year to the total body or to not less than or equal to 3000 mrem / year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to an 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.

4 Dose, Noble Gases This Specification is provided to implement the requirements of Sections II.B. III.A and IV.A of Appendix I, 10 CFR Part

50. The Limiting Conditions For Operation implement the guides set forth in 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 requireme.1ts 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 dose 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 0727a 1 of 22

78 DRESDEN NUCLEAR POWER STATION DOCKET NOS. 50-10,-'50-237. 50-249 1 ;g,. .

l ,.~

1.109 " Calculation of Annual Doses to Man from Routine'-

H- Releases of Reactor Effluents for the Purpose of Evaluating

, Compliance with 10'CFR Part 50, Appendix'I," Revision'1, L ' 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.

L Dose, Radioiodines, Radioactive Material in Particulate For's

? and Radionuclides Other than Noble Cases This specification is provided to' implement the requirements H of Sections II.C. III.A and IV.A of Appendix I, 10 CFR Part i 50. .The Limiting Conditions for. Operation are the guides' set I forth in Section II.C 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 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 1 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 E substantially underestimated. The ODCM calculational methods L approved by NRC for calculating the doses duefto 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 from Routine Releases of Reactor Effluents for ths 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 atmospheric conditions. The release rate specification, for radiciodines, radioactive material in particulate form and radionuclides other than noble gases are dependent on the existing radionuclides pathways to man, in the unrestricted area. The pathways which were examined in 0727a 2 of 22

T.

4

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

~

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.

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

amounts or concentrations of radioactive materials ensures l that the system will be available for use whenever gaseous effluents require treatment prior to releese 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 Derign 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 ensere 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) Publication 2.

Dose This specification is provided to implement the requirements of Sections II.A, 111.A and IV.A of Appendix I, 10 CFR Part 50.

0727a 3 of 22

___-________a

i :DRESDEN NUCLEAR-POWER STATION DOCKET NOS. 50-10. 50-237, 50-249-3 j 'Tha Limiting Condition for.Op3 ration impicm:nts ths guidss set forth in Section111.A of: Appendix I. LThe statements

'l' provide the required oper'ating flexibility and at the same time implement'the guides set forth in Section IV.A of

' Appendix 1 to assure that the releases of radioactive material in liquid effluents will be kept "as low at reasonably achievable". The dose' calculations in the ODCM implement the requirements in Section III.A of Appendix I-that conformance with the guides of Appendix I be shown by calculational procedures based on models=and data such that'

' the actual exposure of an individual,through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the'0DCM 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.l.109,f' Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR'Part 50, Appendix I", Revision 1, October 1977 and Regulatory Guide.

-1.113 " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of.

Implementing Appendix I", April 1977. NUREG-0113 provides methods for' dose calculations with Reg Guide 1.109 and 1.113.

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

Mechanical 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 4 steamline radioactivity monitors which initiate isolation.

1' 0727a 4 of 22

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

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MAXIMUM PERMISSIBLE CONCENTRATIONS- (h!PC) +

'The concentration of radioactive materials released in gaseous'and liquid

< effluents from'the site to unrestricted areas will belless.than the 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 Infiernational Commission on Radiological Protection -(ICRP) Publication 2.

4 MAXIMUM PERMISSIBLE CONCENTRATION OF DISS07.VED OR ENTRAINED NOBLE GASES RELEASED FROM THE SITE TO UNRESTRICTED AREAS IN L10JJ1D WASTE NUCLIDE MPC(uC1/ mil *~

'Kr-85m' 2 X 10-'O' Kr-85 5 X 10-4 3

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 10-4 Xe 133 6 X 10-4 Xe-135m 2 X 10-4 Xe-135 2 X 10-4

  • 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.

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0727a 5 of 22

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

e.

AVERAGE ENERGY Tite average energy of. fission and activation gases was calculated for the o gaseous effluents released froin the site. The average energy is based on the percentage of each fission gas nuclide present and its respective

' average. energy per disintegrate. ion (E in MeV/ dis) for gamma and beta a emissions separately..

Eg= 2.60E-01 MeV/ dis

. E3 = 3.02E-01 MeV/ dis 0727a 6 of 22

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L 7 'DRESDEN NUCLEAR POWER SIATION DOCKET NOS. 50-10, 50-237, 50-249 .

MEASUREMENTS AND APPROXIMATIONS

-A. Fission and activation gases: The D-1 chimney, D2/3 chimney and D2/3 J- o 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 Ca) 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 ac'tivities 2

present in Reactor Off-Gas.

B. Iodine and Particulate: Iodine and particu sts samples frem 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 are not used for reporting the release rate due to management decision that the: sample may not be representative, an average of the preceding l 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 batch's for the month is sent to a. vendor to be analyzed for Sr-89, Sr-90, Pe- 55, H-3, and Cross 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 Errors: The methods used for estimating overall errors associated with radioactivity measurements vary with discharge path and form of isotopes. Factors that contribute to the error include such items as calibration of counting equipment, counting statistics, sampling error, discharge volume, and flow rate monitors.

E. Estimation of Vendor Analyzed Information: The vendor analyzed data for Sr-89, Sr-90, Fe-55, H-3, and Gross Alpha have been projected, where applicable, for the months of May and June using April data. A corrected Effluent Report will be submitted when the data becomes available.

0727a 7 of 22

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. .; < DRESDENNUCpEARPOWERSTATION ,

^

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT q

{ ' _.ilanuary Through: June . 1982

< GASEOUS' EFFLUENTS . Docket Numbers: 50-10

.50-237.

SUMMATION OF ALL RELEASES '50-249-E EST. TOTAL UNIT . - ht QUARTER 2nd QUARTER ERROR,% ~ ,

T

A FISS. ION AND ACTIVATION GASES ,

1. Total Kelease Ci 1.54 E01- 7.46 E00 .7.31ll1
2. =Averege Release Rate for Period. .uCi/sec 1.98 E00 9.49 E-01

~

3. Percent;of Technical-Specification Limit  % m A.

. ) .' 10 DINES 1.- Total Iodine-131, Ci 8.86 E-04 1.01 E-03 9.51 l_

2. Average. Release Rate of'I-131 for Period uCi/sec. 1.14'E-04 1.28 E-04
3. Percent lof Technical Specification Limit-  % A A

=4. Total 1 Iodine-131, Iodine-133.and Iodine-135 Ci 1.20 E-02 1.65 E-02 C. ' PARTICULATE

1. Particulate with half-lives > 8 days Ci. 4.20 E-03 1.41 E-02 -8.09 l1

-2. Average Release kate for Period uCi/sec 5.40 E-04 1.79 E-03

3. - Percent of Technical Specification Limit  % A A
4. Cross Alpha Radioactivity Ci' MDL MDL
p. . TRI.IIUM
1. Total Release Ci 3.12 E00 3.97 E00 -7.89 l'
2. Average Release Rate for Period uCi/sec 4.01 E-01 5.05 E-01
3. Percent of Technical Specification Limit  % A A

~A The information is contained in the. Radiological Impact on Man-section of the report. Tota 1' airborne release data is provided which includes fission and activation gases, iodines, particulate, and tritium.

0727a 8 of 22

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. DREEDEN NUCLEAR POWER STATION

, EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

_J.anuary . Through . Tune 1982 D1 Chimney GASEOUS EFFLUENTS GROUND LEVEL RELEASES l Docket Number 50-10 SEMI-ELEVATED RELEASES xx ELEVATED RELEASES CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT 1A1 QUARTER 2nd QUARTER 1s1 QUARTER 2,nd QUARTER l FISSIDB_9ASES .Ci

_ Xe-138 Ci *
  • l Xe-1.35sn ci *
  • Kr-87 Ci *
  • Ir-8B Ci *
  • Kr-85m Ci *
  • Xe-135 Ci *
  • Xe-133 Ci *
  • 01hers: C1 Ci l IQIAL Ci None None 1

10DIBES 1-131 Ci *

  • I-133 Ci *
  • I-135 ._Ci *
  • TOIAL Ci None None

___l'ARIlC.UJAIES Sr-89 Ci * *

.Sr-90 Ci *

  • _ _Cr-51 Ci *
  • _ _ . Ma-54 _Ci_ 9.44 E-06 2.82 E-06 Cu-5B _C1 l

Fe-59 Ci *

  • Co-60 01 1.64 E-05 1.77 E-06 Ir-25 Ci *
  • Nh-25 Ci *
  • Ru-103 _Ci

_,. Ag 110m C1 *

  • __Shd2tt Ci *
  • l-131 Ci *
  • Cs-134 Ci *
  • _qi_ *
  • _ . Car 136 Ca.-1137 Ci 1.55 E-05 2.25 E-05

.Da-140 Ci *

  • Ce-141 C1 *
  • Ce-144 C1 *
  • _ Ju .fik Ci

_ Da-133 Ci *

  • Ci *
  • Sb-1.25 Others: C1 Ci

_____ _ Ci_.

_ _ _ _Ci__

ji TOIAL Ci 4.13 E-05 2.71 E-05 None None

  • See Table for MDL of Each Nuclide 0727a 9 of 22 l

h b. , ,: . -

DRESDEN NUCLEAR POWER STATION 9? ['i " ' -e , . EFFLUENT.AND WASTE DISPOSAL SEMIANNUAL REPORT pl6 , ,

' January Through June '1912. ,

., .. ,. ., ~

l ci.', + 7? ,

! , Docket: Number

, 50-10 l - f. ' TABLE OF MINIMUM DETECTABLE LEVELS E FOR GASEOUS EFFLUENTS u , ,

D1 Chimnev_1_ GASEOUS: EFFLUENTS-- > AVERAGE FLOW 50.000'cfm- ,

MDLi(uCi/cc)  % OF TIME h MDL 1

. -FISSION GASES,

1.:

L .

Xe-138 '4.16 E -100.0

.Xe-135m, 1.29 E-07 100.0 Kr-87~ 3.03 E-08i 4100.0-Kr-88' 5.21'E-08 100.0 Kr-85m~ 1.78 E-08 ~100.0-Kr-85' .4.43'E-06 '100.0; 9 Xe-135~ "1.52 E-08 100.01 Xe-133' 4.32'E-08 100.0i 0thers: 1 21 10 DINES I-131 '5.34'E-14' 100.0- '

'I-133- 5.57 E-14 100.0

l. ,c I-135- 1.19 E-13 100.0 13 . PARTICULATE-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' 00-58 4.83 E-14 100.0 Fe-59 7.58 E-14 100.0 0o-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 1-131 5.15 E-14 100.0 Cs-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 W 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 r,7 0 0727a 10 of 22

DRESDEN NUCLEAR POWER STATION

. EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

_.Jonunry . . Through June 19&R 3

~

__.D2/_3. Chimnev GASEOUS EFFLUENTS GROUND LEVEL RELEASES Docket Numbers: 50-237 SEMI-ELEVATED RELEASES 50-249 xx ELEVATED RELEASES CONTINUOUS MQDE BATCH MODE NUCLIDES RELEASED UNIT 1R QUARTER 2nd QUARTER id QUARTER 2nd QUARTER FISSION GASZf__ Ci Xe-138 Ci *

  • Xe-135m Ci 1.49 E00
  • Kr-87 Ci *
  • lir-88 Ci *
  • Kr-85m _C1 *
  • lir-85 C1 2.91 E-03 2.86 E-03 _.

Xe-135 C1 1.38 E01 6.42 E00

_ _Xe-133 Ci *

  • Dahera; C1 Ci TOTAL Ci 1.53 E01 6.42 E00 Ncqe None 10 DINES J-131 __Ci 7.49 E-04 6.43 E-04 I _133 Ci 3.78 E-03 3,92 E-03 L-135 Ci 5.87 E-03 5.87 E-03 TOTAL Ci 1.04 E-02 1.04 E-02 None None

..--_l'bRTIC11L6TES SI-89 C1 4.77 E-08 4.26 E-08 Sr-20 01 1.07 E-10

  • Cr-51 Ci *
  • Mn-54 Ci 6.52 E-05 6.28 E-05 Co-58 Ci *
  • Fe-59 Ci_ *
  • Cs-50 Ci 1.67 E-04 1.94 E-04 .__

Zr-95 Ci *

  • Nb-95 Ci *
  • En-103 Ci *
  • Ag_llQm Ci *
  • Ci *
  • Eb-124

! __ _l-131 Ci 7.64 E-05 6. 24._E-05 l Cs-134 Ci *

  • Cs .136 Ci *
  • Cs-137 Ci 3.14 E-05 7.73 E-06 l ]}a-140 Ji 6.77 E-04 6.51 E-04 l Ce-141 Ci *
  • l Ce-144 Ci *
  • 29-65 _L'i_ *
  • Ba-133 0.1 *
  • l _ J -125 Ci * *

.D5 herr 1 C1

_nL Ci Ci Ci TQIAJ., Ci 1.02 E-03 9.78 E-04 None None

  • See Table for MDL of Each Nuclide 0727a 11 of 22

-c _

t: DRESDEN, NUCLEAR POWER STATION yf ,

s. '

January Through) June 1981 ' DockSt Numbers: '

s . .50-237' TABLE OF MINIMUM DETECTABLE LEVELS 50-249

-FOR. GASEOUS EFFLUENTS,'

ist atr 252 Kcfm -

D2/3'Chimnew GASEOUS EFFLUENTS. AVERAGF FL0tf y g agr go9 _ Kcfm

@L (uCi/cc)  % OF TIME < MDL

1. FISSION CASES:

Xe-138 4.16 E-08 100.0

..v Xe-135m 1.29 E-07 98.9 Kr 3.03 E-08_ 100.0' Kr 5.21 E-08 100.0

~

Kr-85m 1.78 E 100.0-Kr-85' 4.43 E 0 Xe-135 1.52 E-08 43.1

Xe-133 4.32 E-08 .100.0

- "Others:

i

2. 10 DINES o

I-131 5.34 E-14 0.552 I-133 5.57 E-14 0 I-135 1.19 E-13 15.5

3. PIRTICULATES Sr-89 3.1 E-11 0 Sr-90 6.9 E-12 67.4 Cr-51 4.20 E-13 100.0 Mn-54' 5.27 E-14 7.73
02-58 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 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 1.39 E-13 100.0 Sb-17.5 Others:

Gross Alpha 9.4 E-12 100.0

4. TRITIUM H-3 5.84 E-07 0 0727a 12 of 22

. , _  ; DRESDEN NUCLEAR POWER STATION

. EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January Through June 193_2 D2/3 Vent GASE0US EFFLUENTS

__ GROUND LEVEL RELEASES Docket Numbers: 50-237 xx SEMI-ELEVATED RELEASES 50-249 ELEVATED RELEASES-C0]iIJJiUOUS MODE BATCH MODE NUCLIDES. RELEASED UNIT isi QUARTER. 2nd QUARTER 131 QUARTER 2nd-QUARTER FISSIDE.JASES C1

-Xe-138 Ci- *-

  • Xe_-135Hi ci '*
  • Kr-87 Ci *
  • Kr-88 Ci- *
  • __

Kr-85m~ Ci *

-Xe-135' Ci 8.64 E-02 1.04 E00 Xe-133 Ci *

  • OtligIs : _.Ci Ci TOTAL Ci 8.64 E-02 1.04 E00 None None'-

10 DINES J-131- Ci 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 3.58 E-03 TOTAL C1 1.50 E-03 5.96 E-03 None None PARIlEULATES SI-32__ C1 6.98 E-09 3.43 E-09

'Sr 01 7.14 E-11

  • Cr-51 Ci 6.43 E-04 4.42 E-03

_ 31-54 Ci 4.87 E-04 1.55 E-03

'Co-58 Ci 6.54 E-05 7.18 E-04 Fe-50 Ci 6.69 E-05 8.80 E-04 Co-60 C1 1 80 E-03 5.07 E-03 Zr-95 Ci * *

'Nb-95 Ci *

  • Ru -103 Ci *
  • Ag-110m Ci 6.74 E-06 4.11 E-05 Sb-124 C1 *
  • I-131 Ci 9.39 E-06 4.64 E-05 Cs_-134 Ci *
  • Cs--136 Ci, *
  • Ba-140 Ci 2.49.E-05 1.61 E-04 Ce-141 fi_ __

Ce-144 Ci *

  • Zn-65 Ci 1.68 E-05 1.78 E-04 Da-133 Ci *
  • Sb-125 C1 *
  • Qtiters.: _C1 Ci C1 TO.TAL C1 3.13 E-03 1.31 E-02 None [ None
  • See Table for MDL of Each Nuclide 0727a 13 of 22

p, ,

DRESDEN NUCLEAR' POWER SIATION L ,

January Through June 1982 Docket Numbers:

l 50-237 TABLE OF MINIMUM DETECIABLE LEVELS 50-240 FOR GASEOUS EFFLUENTS D2: 110 Kcfm L D2/3 Vent GASEOUS EFFLUENTS AVERAGE FLOW D3: 110 Kcfm MDL (uCi/cc)  % OF TIME < MDL

1. FISSION GASES 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 Kr-85m 1.78 E-08 100.0 Kr-85 4.43 E-06 100.0 Xe-135 1.52 E-08 87.3 Ae-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 1-135 1.19 E-13 60.8
3. PARTICULATE Sr-89 3.1 E-11 0 Sr-90 6.9 E-12 67.4 Cr-51 4.20 E-13 32.0 Mn-54 5.27 E-14 0 Co-58 4.83 E-14 24.9 Fe-59 7.58 E-14 26.0 Co-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 1 Sb-124 5.86 E-14 61.9 I-131 5.15 E-14 44.8 Cs-134 5.73 E-14 100.0 Cs-136 5.49 E-14 100.0 Cs-137 6.21 E-14 53.0 Ba-140 1.91 E-13 37.6 Cc-141 7.64 E-14 100.0 Ce-144 3.27 E-13 100.0 i In-65 9.03 E-14 47.0 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 J l

H-3 5.84 E-07 0 i j

0727a 14 of 22

, DRESDEN NUCLEAR POWER STATION

. EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

, . _. January Through June 1982 D2 Iso Condensor CASE 0US EFFLUENTS xx GROUND LEVEL RELEASES Docket Numbers: 50-237 SEMI-ELEVATED RELEASES ELEVATED RELEASES CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT lai QUARTER 2nd QUAhTER Jat QUARTER 2nd QUARTER flSSION Gb! IFS Ci Ci

  • ___Xe-138 Xe-135m Ci
  • Kr-87
  • _.C1 Ci
  • Kr-J8 Kr-85m Ci
  • Ci
  • ____Kr-85 _

Ci

  • Xe-135 Xe-133 Ci
  • Others: 01 Ci TOTAL Ci None Nor e None 10 DINES I-131 Ci
  • I-133 Ci
  • I-135 Ci
  • ___TQIAL Ci None None None PARTICULATE Er-89 Ci
  • ___ C c . 'il

.____lki-5 4 Ci 2.32 E-06 Ci

  • Co-58 En-59 _Ci 09:00 _Ci 2.86 r-06 Z.r-95 Ci
  • Nb-95 Ci .

Ru-103 Ci

  • Ag _11Qrg__ C1
  • Ci
  • Sb-124 _

Ci

  • Id 31 Ci
  • Cs-134 Cs-136 Ci
  • Ce-131 _C1 Ba-140 C1
  • Ce-141 Ci
  • l l fR-144 _.Ci Ci

___ _.11a-131 _Q1 Ci

  • Sh..125 Q1heral Ci C1 Ci

____JQIAL Ji None None 5.18 E-06 Nome

  • See Table for MDL of Each Nuclide 0727a 15 of 22

r

. o .

l 3 , DRESDEN NUCLEAR POWER SIATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January Through June 1982 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES Docket Numbers: 50-10 50-237 50-249 EST. TOTAL UNIT 131 QUARTER 2nd QUARTER ERROR,%

L _ EISElpN AND ACTIVATION PRODUCTS

1. Total Release Ci 3.25 E-01 1.22 E-01 5.58 l' (not incl. tritium, gases, alpha)
2. Average Diluted Conc. During Period uCi/mL 6.16 E-08 8.19 E-09
3. Percent of Applicable '!-4 t  % A A EdRIInti
1. Total Release Ci 4.05 E00 3.75 E00 7.75 l
2. Average Diluted Conc. During Period uCi/mL 7.67 E-07 2.52 E-07
3. Percent of Applicable Limit  % A A C. DISS0lVED AND ENTRAINED GASES 1, Total Release C1 1.07 E-04 1.29 E-04 5.58 l
2. Average Diluted Cone. During Period uCi/mL 3.22 E-11 8.66 E-12
3. Percent of Applicable Limit  % A A h _GRQSS ALPHA RADIOACTIVITY
1. Total Release C1 4.60 E-03 3.67 E-03 15.1 l E. VOLUME OF WASTE RELEASED (prior to dilution) liters 7.82 E06 6.11 E06 5.00 l F. VOLUME OF DILUTION WATER USED DURING PERIOD liters 5.28 E09 1.49 E10 5.00 l A The information is contained in the Radiological Impact on Man section of this report. Total liquid release data is provided which includes fission and activation products, tritium, and dissolved and entrained gases.

0727a 16 of 22

)

1

. DRESDEN NUCLEAR POWER STATION

. EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January Through June 1989 Radwaste 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 Release: 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 CONTINUQRS EQDE BATCH MODE NUCLIDES RELEASED UNIT ist QUARTER 2nd QUARTER lat QUARTER 2nd QUARTER Sr-89 C1 *
  • Sr-90 C1 3.70 E-04 9.03 E-05 Ar-41 'Ci *
  • Mn-54 Ci 5.91 E-02 3.67 E-02~

C9 -5B _Ci 1.87 E-03 1.45 E-04 fe-59 _Ci 6.04 E-03 1.09 E-03

-Co-60 Ci 1.66 E 6.53 E-02 2n-65 C1 5.30 E-05

  • _ Ru-1D3 Ci *
  • Sb__122 Ci * *

,,_,_Sh-124 Ci 7.03 E-02 3.93 E-05 I-131 Ci *

  • I-133 Ci * *

.____l-135 Ci

  • 3 30_E-D5__

_ Ca-134 Ci

  • 2.61 E-05

_._ _Cm-137 Ci 1.15 E-02 1.06 E-02 Ba-140 Ci *

  • La-140 C1

.___Ce-141 Ci *

  • Others: Cr-51 C1 1.47 E-03 1.47 E-04 Fe-55 C1 3.32 E-03 7.89 E-03 Rb-88 Ci
  • 2.62 E-04 Nb-95 Ci 1.11 E-05
  • Tc-99m C1
  • 6.57 E-06 As-76 Ci
  • 3.31 E-05 Cs-138 _01 9.49 E-06
  • 1[1-181 Ci 1.27 E-05 *

(above)

Talal_for_fatiod. Ci NONE NONE 3.20 E-01 1.22 E-01 Xs-133 Ci 7.87 E-05 3.47 E-05 Xe-135 Ci 9.10 E-05 7.69 E-05 Kr-BJ Ci

  • 1.74 E-05
  • See Table for MDL of Each Nuclide 0727a 17 of 22

y,_ . DRESDEN NUCLEAR POWER STATION l 3.,

January Through June 1932 TABLE OF MINIMUM DETECTABLE LEVELS Docket Numbers:

FOR LIQUID EFFLUENTS 50-10 50-237 L

50-249 1

Radwagle LIQUID EFFLUENTS TOTAL GALLONS RELEASED 3.402.080 MD1 (uCi/mL) 1 0F GALLONS < MDL Sr-89 1.5 E-08 100.0 Sr-90 4.3 E-08 0 Ar-41 2.71 E-08 100.0 Mn-54' 5.04 E-08 0 Co-58 4.98 E-08 72.0 Fe-59 8.11 E-08 38.6 Co-60 1.18 E-07 0 Zn-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 1-135 9.15 E-08 99.4 Cs-134 5.51 E-08 99.4 Cs-137 4.04 E-08 1.99 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 96.9 Xe-135 5.13 E-08 94.5 Cr-51 4.81 E-07 100.0 Fe-55 5.2 E-07 91.9 Nb-95 Not Determined 99.4 Kr-88 1.71 E-07 99.4 Ilf-181  :.ot Determined 99.4 Cs-138 Not Determined 99.4 Tc-99m 4.63 E-08 99.1 As-76 Not Determined 98.6 Rb-88 Not Determine <1 99.4 11 - 3 4.1 E-06 0 Gross Alpha 1.7 E-08 0 0727a 18 of 22

,. _4 '

. DRESDEN NUCLEAR POWER F"4 TION'

, iEFFLUENT AND WASTE DISL'CLAL SEMIANNUAL REPORT ~

Januarv- Through June 1982 LPCI LIQUID EFFLUENTS E0: ket Numbers: 50-237

, 50-249

1. - Number of Batch Releases: 64 2.~ Total Time Period for Batch Releases: 80 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: 2.33 E06 L/ min CONTINUOUS MODE BATL9 MODE

'NUCLIDES RELEASED UNIT 131 QUARTER 2nd QUARTER 1s1 QUARTER' 2ad QUARTER Sr-89 Ci *

Ar-41 C1 *- -*

Mn-54 Ci 8.76 E-07 2.07 E-05 Co-58 Ci *- *-

Fe-59' J i_ *

  • C.g-60 Ci 7.94 E-06 2.88 E-05 Zn-65 Ci *
  • Ru-103 Ci~ * '*

___Sb-122 Ci Sb-124' Ci * -*

I-131 Ci * *

'I-133_- Ci 1-135 Ci- * *'

Cs-134 Ci 9.72 E-08 2.44 E-05

___ Cs-137 01 6.06 E-06 6.48 E-05 Ba-140 *

  • J La-140 Ci *
  • Ce-141 Ci *
  • Others: Cr-51 Ci *
  • CI' Ci (above)

Ig_tal For Period Ci None None 1.50 E-05 1.39 E -Xe-133 Ci *

  • Ci *
  • Xe-135
  • See Table for MDL of Each Nuclide 0727a' 19 of 22

. DRESDEN NUCLEAR POWER STATION

. _ January Through. June 1982 TABLE OF MINIMUM DETECTABLE LEVELS Docket Numbers:

FOR LIQUID EFFLUENTS 50-237 50-249 LPCI LIQUID EFFLUENTS. TOTAL GALLONS RELEASED 277.760 MDL (uCi/mL) '% OF GALLONS < MDL Sr-89 1.5 E-07 100.0 Sr-90 4.3 E-08 100.0 Ar-41 2.71 E-08 100.0 Mn-54 5.04 E-08 12.5 00-58 4.98 E-08 100.0 Fe-59 8.11 E-08 100.0 Co-60 1.18 E-07 0 Zn-65 9.97 E-08 100.0 Ru-103 6.04 E-08 100.0 Sh-122 7.31 E-08 100.0 Sb-124 4.87 E-08 -100.0 1-131 5.62 E-08 100.0 1-133 5.34 E-08 100.0 I-135 9.15 E-08 100.0 Cs-134 5.51 E-08 34.4 Cs-137 4.04'E-08 3.13 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-3 4.1 E-06 37.5 Gross Alpha 1.7 E-08 0 0727a 20 of 22

[/

1 m

DRESDEN NUCLEAR POWER STATION n EFFLUENT AND WASTE DISPOSAL SEMIANNUhL REPORT

[

L4

' January Through! June 1982

. Docket Numbers:

50-10 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 50-237 50-249

.Est Tot.

ALSQ1JRJASIE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED' FUEL) Error.%

~1. Type of Waste Unit 6-month period m3 3.08'E02

a. Spent resins, filter sludges, evaporator bottoms, etc.

Ci '1.60 E03 12.4 m3 1.15 E03

b. Dry compressible waste, contaminated equip., etc.

c1 2.39.E01 16.6 m3 0

c. Irradiated components, control rods, etc. -

C3 0 m3 0

.d. Other (describe)

Ci 0

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

% ci

g. Co-60 67.2 % 1.08 E03 Fe-55 18.9 % 3.02 E02 Mn-54 12.1 % 1.94 E02 Ni-63 0.805% 1.29 E01 Other 0.995% 1.59 E01 h, 00-60 26.6 % 6.36 E00-Fe-55 63.1 % 1.51 E01 Mn-54 7.99 % 1.91 E00 Cs-137 0.981% 2.34 E-01 Other 1.329% ~3.18 E-01 l3. Solid Waste Disposition N1!!iDER OF SHIPMENTS MODE Of TRANSPORTATION DESTINATIO?]

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 j

.B. IRRADIATED FUEL SHIPMENTS (Disposition)

HRiBER_Qf SHIPMENTS tiQDE OF TRANSPORTATION DESTINATION None 0727a 21 of 22 l

_ _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ - _ - - _ _ _ _ _ _ _ _ - _ - - - _ - _ _ _ _ _ _- ._ U

,1 . ,

DRESDEN NUCLEAR POWER STATION

.. c w .

., . EFFLUENT AND WASTE DISPOSAL SEM1 ANNUAL REPORT January Through June 19fLt Docket Numbers:

50 ABNORMAL RELEASES 50-237 s 50-249 A. LIQUID

1. Number-of Releases: One on 25 March 89. DVR 12-3-89-19.

LER 89-1-050249 2, Total Activity Released: Hucijde Activity (Ci)

Mn - 54 1.76 E-03 Co - 58 1.82 E-05 2 : 28 1:211:83 Total 5.47 E-03 B. GASEOUS

1. Number of' Releases: One on 4 March 89. DVR 12-2-89-52.

LER 89-12-050237~

2 Total Activity Released: Huclide Activity (01)

Mn - 54 2.32 E-06 Co - 60 2.86 E-06 Total 5.18 E-06 i

i i

l

-0727a 22 of 22 1

(

I

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

-O _g', =

' RADIOLOGICAL IMPACT ON MAN l

L________

I .h lhl ^

.p,.

DRECDCN' UNIT ONC-

' ' #' I

.1707 ANNUAL RCPORT' MAXIMUM DDOCO-RCCULTIND~TRDM AIRDORNC'RCLEAOCS

PCRIOD OF-RCLCACC 01/01/07 TD-12/31/07 CALOULATCD 00/16/07 INIANT RCCCPTCR-ICT OND 3RD 4 Til '

'-T YPC - 00ARTER OUARTER QUARTCR- D'UARTCR' ANNUAL'.

JAN-MAR APR-JUN JUL-0CP 00T-DEC I :OAMMA AIf! 0.00C100' O.00C100 0.00C100 0.00C100- 0.00C100:

-( MR AD ) - ( ) ( -). ( ) (^ ) ( .)

-DCTA. AIR 0.00Cl00 0.00Cl00 0.00C100 0.00C100 0.'00C100' (tiRAD) -( -) (- ) ( )- (' ) (- .).

TOT ." DDDY =

0.00Cl00 0.00Cl-00 -0.00C100. 0.00C100 0.00Cl00.

(MRCM)' ( ) '( ) ( ) (~ ~-) (- )

-OKIN.. 0.00C100 0.00C100 0.00C100 0.00C100 '.0.'00Cl00 L .- (MRCM)' ( ) ( ) -( >- (- ) (,  :) ,

' ORGAN. 3. 73C r05 2.50C-05 0.00C100 0.00C100- 4.51C-05 (MRCM)- (CC ') (CC ) ( -) ( ) (CC .)

LIVCR LIVCR LIVER T!!IC IOTA. REPORT FOR Tl!C CALCNDAR YEAR 1707 COMPLIANCC OTATUC - 10 CTR 50 ' APP. I INEANT RCOCPTOR

- - % OF' APP I. - - - - - - - - - - - - - -

GTRL) 1CT QTR 2ND QTR 3RD GTR 4TH OTR YRLY  % OF; CDJ .JAN-MAR APR-JUN- JUL SCP GCT-NOV ODJ- APP.I.

'CAMMA AIR (MRAD)- 5.0 0.00 0.00 0.00 0.00 10.0 0.00 DCTA AIR :(MRAD) 10.0 0.00 0.00 0.00 0.00- 20.0' O.00 TOT. DDDY (MREM)- 2.5 0.00. 0 00 0.00- 0.00 5.0 0.00-b [0 KIN fliRCM) 745 0.00 0.00 0.00 0.00. 15.0 0.00 10 ROAN (MRCM)- 7.5 0.00 0.00- 0.00' O.00 15.0- 0.00 LIVER LIVER LIVER RCCULTC DACED UPON-CDCM REVISION 11 UPDAlt CC204 ICDRUARY 1706 L=_=___-_ __ - _ _ _ _ _ . . __ ._- _

\

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DRCCDEN UNIT Cric

'1907: ANNUAL' REPORT MAXIMUM D00CO RCOULTINO FROM AIRDDRNC RELEACEO. ,

PERIOD Cr RELCAOC - 01/01/07.TO-12/31/07- CALCULATED 00/16/07

-ADULT RECEPT 0R 10T. OND. 3RD 4Tl! .

TYPC .

QUARTER .CUARTCR CUARTER GUARTER ~ ANNUAL.

- .JAN-MAR- APRLJUN'- JUL-OCP CCT-DEC JCAMMA' AIR? 0.00E!00 0.00C100- 0.00E100 0.00El00 0.00E400 (MRAD) .

( ) -.(- ). (_ ) ,.

.(- .). ( ).

DCTA AIR 0.00C100 0.00Cf00 0.00E400 'O.00E100- 0.00E400

-(MRAD) ( -) ( ) ( -) ( ) ( .).

TOT.;D0DYL -0.00E100 0.00C100 0.00Cl00- 0.00CiOO. .0.00CiOO (MRCM) ( F (- ) -( ~) ( ) -(- )

OKIN- 0.00E100 0.00C100 0.00Cf00 0 00C100 0.00CiOO-(MRCM) ( .) ( 1- ( ) ( ) .( >

CROAN. 3.60C405 3.03C'05 ~0.00C100 0.00EiC0 '6.03E-05 (MRCM) (OC l' (OC ) ( ) ( ) (GC' )

LIVCR 'LIVCR LIVER

~

T!!IO IO A REPORT' FOR Tl!C CALENDAR YCAR 1707 COMPLIANCE OTATUC - 10.0FR 50 APP. I ADULT RECCPTCR

_ _ . _ _ . _ ._. % O F A P P I . . - - - - - - - - -- -

CTRLY IST GTR OND OTR 3RD QTR 4Til GTR YRLY.  % OF

ODJ JAN-MAR APR-JUN JUL-OCP GCT-NOV ODJ APP..I

-0AMMA AIR (MRAD) 5.0 0.00 0.00 0.00 0.00 ' 10 .' O 0.00 zDETA' AIR (MRAD) 10.0. 0.00 0.00 0.00 0.00 20.0 0.00

TOT. 00DY-(MRCM) 0.5 0.00 0.00 0.00 0.00 5.0 0 00 f0 KIN (MRCM) 7.5 0.00 0.00 0.00 0.00 15.0 0.00

'CRCAN (MREM) 7.5 0.00 0.00 0.00 0.00 15.0- 0.00 LIVER LIVER LIVER 1

RCO'JLTO DACCD UPON l, ODCM REVISION 11 l UPDATC 00004 l

FEDRUARY 1906 l

1 O ,1.'___________m_. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ . . _ _ _ _ _

gg- .-

q ,

. 7-9< :e j 4 u f

$4 p%, M. - ,

DRCODEN UNIT TUD u

1, c - -

I '- .4707 ANNUAL REPORT-l MAXIMUM DDSCO REOULTING rROM AIRDORNE RELC.)SCO p , 'PCRIOD Or.RCLCASE -

- 01/01/07'TO 12/31/07 0ALCULATED 00/16/07 l= 'INTANT RCCCPTDR h

l

'10T 2ND 3RD - 4 Til TYPC IGUARTER QUARTER GUARTER -QUARTER' ANNUAL-L ~ JAN-MAR APR"JUN JUL-CCP .CCT-DCC b 0AMMA AIR ' <1.10C-05 1.02C-04 0.00El00 0.00C!00- 1.14E )'

(MRAD) ' ( MC- -) (NC )L ( ) ( (NE -) r DCTA..' AIR :1.77C-06 2.47C-04 0.00Cl00 0.00E100 2.49C-04 (MRAD) (N . -L .(NNC') (- ) ( ) (NNE );

!= ' TOT. DODY' 5.12C"06 4.26C-05 0.00C1-00 0.00E000 -4.77E-05

'(MRCM) (NE ) (NC- ) ( ') -( 1 (NC. -)

OKIN 1.05C-05 2 65C-04 0.00E!00~ 0.00El00. 2.75C-04 1

!(MRCM) (NC' ) (NHC.') .

( ) (- ,)' (NNE-)

. ORGAN 14 E - 02 2.67C-00 0.00C100. 0.00E100 4.10E-02

'(MRCM) (NNC.-) (NNC ) ( ) ( )  :(NNC' )

LUNO 'L UN0 ' LUNO T!!IO.IO A REPORT'r0R'Tlic CALENDAR YEAR 1707 COMPLIANCC STATUC 10 CFR 50 APP. I-INFANT RCOCPTOR

- , ., )( OF APP I'.

QTRLY 10T GTR 2ND GTR 3RD GTR 4TH GTR .YRLY  :( OF CDJ JAN-MAR -APR-JUN JUL-CCP 00T-NOV DDJ APP.I OAMMA' AIR-(MRAD) 5.0 0.00 0.00 0.00 0.00 10.0 0.00 DCTA AIR (MRAD) 10.0 0.00 0.00 0.00 0.00 20.0 'O.00 TOT.-DODY'(MREM) 2.5 0.00 0.00 0.00 0.00 5.0 0.00 CMIN (MREM)- 7.5 0.00 0.00 0.00 0.00 15.0 0.00

' ORGAN (MRCM) 75 0.17- 0.34 0.00 0.00 15.0 0;27-LUNO LUNC LUNO RCOULTO DACCD UPON' ODCM REVIOION 11 UPDATE 00204 FCDRUARY 1906 w-_=____________- _______ ____

yp- +3

.a  :..'. .

'DRCCDEN UNIT'TUO.

1907 ANNUAL REPORT

' MAXIMUM DOCCC'RCOULTINC'Fr.OM AIRDORNC RELEACCC PCRIOD OF.RCLCACC - 01/01/07 TC 12/31/07 CALCULATED 03/16/07 ADULT .RCCEPTOR 10T 2ND CRD 4Til -

17YPCL QUARTER QUARTER DUARTERJ GUARTER ANNUAL-JAN-MAR APR-JUN JULeSEP 'OCT-DEC oCAHMA: AIR 1.10E205 1.02C-04 0. 00 E-100 0.00E100 -1.14E-04

(HRAD) ( NC '  ;- (NC ). ( )- (. ) .(NC >

DCTA AIR 1.77E 2.47C-04 .0.00Ef00- 'O.00C100 2.4?E-04

' (MPAD)-

. -(N ) (NNE F ( ) ( ). l(NNC 0 TOT, DODY- 5.10E-06 4.26C-05 0.00El00' 'O.00El00 4.77E-05 -

'(MRCM)H (NC. >' (NC -). ( ) ( )' (NE )

CMIN . 1.05E-05 2.65E904 0.00Ef00- 0.00E400 2.75E-04

(MRCM) (NC .) -(NHC ) -(- ) ( -)' (NNC )'

ORCAN .1. 4 6 C" 0 2 - 2.90E-02 0.00E400 0.00EiOO 4.32E (MRCM) -(NNE > (NNC ) ( ) ( ')- (NNC >

'LUNO. lCI-LLI LUNG

. T!!IC IS' A REPORT -FOR T!!C CALENDAR YEAR 1907

' COMPLIANCE CTATUC - 10 CFR 50 APP. I ADULT RCCCPTOR

- . . . _ _ . . .._ g er gpp y, _ _ _ _ - . - _ _

GTRLY 1CT GTR 2ND OTR -3RD OTR 4Til QTR YRLY  % OF OBJ JAN-MAR APR-JUN JUL-SEP OCT-NOV DBJ APP.I-L DAMMA AIR (MRAD.5 5.0 0.00 0.00 0.00 0.00 10.0' O.00 DCTA' AIR (MRAD) 10.0 0.00 0.00 0.00 0.00 20.0 0.00 TOT. DODY-(MREM) 2.5 0.00 0.00 0.00 0.00 5.0 0.00 CKIN-(MRCM) 7.5 0.00 0.00 0.00 0.00- 15.0 0.00 CRCAN (MRCM) 7.5 0.17 0.37 0.00 0.00 15.0 0.29

LUNC GI LLI LUNG 1

i l :' RESULTC DACED UPON ODCM REVISION 11- -

l UPDATE CO204 FCDRUARY 1986 L

u I

1

___-.-_.____________________m____-- - - _ _ _ _ _ _ _ _ _ . _ _ - - - _ - _

7

, . . ' 1 ,.

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DRESDEN UNIT TilREE I

1909 ANNUAL.REPOR..

MAXIMUH"D00EO REOULTING FROM'AIRDORNE RELEACEO  !

fPERIOD OF RELEACE - 01/01/09 TO 12/21/09 CALCULATED OD/16/89 INFAllT RECEPTOR

. ICT 2ND 3RD- 4TH! l

' TYPE QUARTER QUARTER DUARTER' 00ARTER ANNUAL. '!

-JAN-MAR- APR-JUN- JUL-0EP OCT-DEC.

,, gj

.. . 1 CAMMA AIR 2.20Ca04 7.00E-05 0.00C100 0.00Ef00 2.90E-04

.(MRAD) (flE ~ ) (NE ) (. ). -(- ); (NE ') ]

DETAfAIR- 6.13C-05 4.13E-05 0.00E100 0.00E100- 1 03C-04. l

( MR AD ) - (NNE )- (NNE ) ( ) ( )- (NNE')-

? T O T ..- D 0 D Y 9.39E 05 2.94E-05 0.00E!00 0.00E-100 1.23E-0.4;  ;

'( tiREM )' (NE ') . - (!!E -) ( ) ( ' ): (NE -) l CKIN ' 2.15E r0 4, 0.46E-05.. 0.00Cf00' O.00El-00 3.00E-04 H dMREM) (NE .) -( NE .) -(. )' (' )- (NE )

-OROAN 14.00Er03 0 56C-02 0.00E100 -0.00E100 '2.97C  ;

(MREM).- .(NNE )~ (NNE ) ( ) ( ). (NNE )- 'l 1

LUNC TilYROID T ilYR O I D --

.Ti!IO.IO A REPORT FOR Tile CALENDAR YEAR 1909 i

COMPLIANCE CTATUS 10-CFR 50 APP. I INFANT RECEPTOR -l y

% Of APP I. - - - - - - - - - -.- .

j GTRLY 107 OTR 2ND QTR 3RD QTR 4Tli GTR YRLY  % OF-CDJ JAN-MAR APR-JUN -JUL-SEP O C T -N D ',' ODJ. APP.I~

CAMMA' AIR-(MRAD) 5.0 0.00 0.00 0.00 0.00 10.0 0.00 DETA A!n (MRAD) 10.0 0.00 0.00 0.00 0.00 20.0 0.00 i

' TOT. DODY-(MREM). 2.5 0.00 0.00 0.00 0.00 5.0 'O.00 l OKIN (MREM) 7.5 0.00 0.00 0.00 0.00 15.0 0.00

.0 ROAN:(MREM) 7.5 0.06 0.34 0.00 0.00 15.0 0.20 LUNO T!!YRDID TilYROID RESULTS DACED UPON 1 CDCM RC','ICION 11-E UPDATE CS204 FEDRUARY 1906 l

l l l

4 l'

lL 1

e -.= _ _ _ - _ _ _ - - - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ _ _ _ - _ _ _ _ _ _ - _ - _ - _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _

w ,

7 ,

. ey; ;

DRECDEN UNIT Tl! REC 1709 ANNUAL" REPORT

' , LiiAXItfuti D00E0 REOULTINO- FR0ri AIRDORNE RCLEACEO

PERIOD.Or RELCASE ":01/01/07:TO 12/31/07 . CALCULATED 0D/16/09

' ADULT RCCCPTOR

'10T OND '3RD 4TH

TYPC) -QUARTER QUARTER QUARTER GUARTER ANNUAli JAN-MAR APR-JUN. JUL-SEP OCT-DEC 10AMMA AIR. 2.00E-04 7. 0 0 C-- 0 5 0. 00 E-i O O 0.00E400' 2.90E-04

. ( MR AD ){ (NC; F (NE- ')-. -( -). -( ) (NC- ).

'DCTA AIR 6.13E 2 05 4.13E-05 .0.00E400 0.00E400. 1.03E-04) '

(MRAD) (NNC ) (NNE') ( ). ( ) (HNC >s LTOT. DODY 9.3?C-05 2.94E-05 0.00EiC0 0.00E400 '1.23C ~(MREM). "(NC ) (NC ) ( .). (. )' (NC ').

CMIN 2 .15 E -- O i - 0.46E-05 0.00EiOO 0.00E400 3.00E-04

-(MREM).. (NE ') (NC ') ( ) ( ) (NC )

OROAN 4.17C-03 2.94E-02 0.00CiOO 0.00CiOO 3.35C-02

(MREM) (NNC )'.

(NNE J' (- ). ( -) (NNE->

LUND TNYROID . THYROID T!!!O .IO A REPORT FOR Tl!C CALENDAR YEAR 1907-ll E

L L COMPLIANCE OTATUO - 10 CFR 50 APP. I

-ADULT RECEPT 0R

% OF. APP I. - - - - -----

L DTRLY 10T OTR OND OTR 3RD Q1R 4T!! OTR YRLY  % Or l-, CDJ. JAN-MAR APR-JUN JUL-SEP GCT-NOV OBJ APP.I i .

E <0AMMA AIR (MRAD) 5.0 0.00 0.00 0.00 0.00 10.0 0.00 DCTA AIR-(tiRAD) 10.0 0.00 0.00 0.00 0.00 20.0 0.00 L TOT.~DCDY (MRCM) 2.5 0.00. 0.00 0.00 0.00 5.0 0.00

[!  : OMIN - (tiREM) 7.5 0.00 0.00 0.00 0.00 15.0 0.00 OROAN.(MREM) 7.5 0.06 0.37 0.00 0.00 15.0 'O.22 l

L

[ LUNO TNYROID TilYROID p

l1 RCOULTO DA0ED UPON I ODCM REVISION 11 l' UPDATE CO204 L TEDRUARY 1986 L

I 1'

Q __ ___ - ___ __- _ _ _ _ _ .

o; 4 y

(7;;,

i- DRECDEN UNIT TUD L INFANT RCCCPTOR-l:

K, a :1707 ANNUAL RCPOR1 MAX! MUM 000CC.(MREM) RCCULTINC rROM LIQUID CfrLUCNTS

PCRIOD OF RELCACC - 01/01/07 TC 12/31/07 CALCDLATED OC/16/09 1 C T- OND 3RD 4 Tit.

. DOCCcTYP'C QUARTER- DUARTER 00ARTER QUARTER ANNUAL JAN-MAR APR- JUN JUL-CCP- OCT-DEC TOTAL 1.30C-04 4.02C-05 0.00C100- -0.00Cf00 1.70E-04 DODY-INTCRNAL- 2.07C 04 1.17C-04 0.00C100 0.00C-100 3.01C-Q4 ORCAN:

DONE LIVER LIVER TilIO IC;A REPORT FOR THE CALENDAR YEAR 1707 COMPLIANCE STATUC -'10 Crn-50' APP..I

- , . . , ,.- % OF APP I. ~ ~ - - - ---

GTRLY 1CT OTR 2ND OTR- 3RD QTR .4Til GTR YRLY  % our DDJ JAN MAR- APR-JUN JUL-CCP OCT-NOV ODJ APP.I'

- TOTAL DODY (MRCM): 1.5 0 . '01' 0.00 0.00 0.00 3.0 0.01.

CRIT. CRCAN(MRCM). 5. 0 ' O.00 0.00 0.00 0.00 10.0' O.00 DONC LIVER LIVCri RCSULTS DACED UPON DDCM REVISION 11 UPDATE CS204 FCDRUARY 1906

)

l

- _ _ _ - - - _ - _ - _ _ _ -- 1

t c

i-

., O;4 DRECDEN UNIT TUD' l:

1 s INFANT RECEPTOR 1:

l 1707 ANNUAL REPORT PROJECTED DOCE:AT.NCARECT COMMUNITY UATER SYOTEM

  • frCRIOD-OF RELEACE '01/01/07'TO 12/31/07- CALCULATED 08/16/07

.10 T OND 3RDc ~ 4 Tl!

DOCC'TYPC OUARTER OUARTER QUARTCR QUARTER' 1 ANNUAL

'JAN-MAR APR-JUN JUL- SEP 00THDEO l

TOTALE 1.30E 04 4.00C-05 0.00E400 0.00C400 1.70E-04 DODY'

-INTERNAL' O.07E-04 1417E-04 0.00Cl00 0.00E100 3.01Ea04

- ORGAN DONE LIVER LIVER T!!!O IO A RCPORT~FOR T!!C CALENDAR YCAR 1707 COMPLIANCE STATUC 40 CFR 141

~TYPC ANNUAL LIMIT

  • OF LIMIT

' TOTAL 4.0 (MREM) 0 004 DODY INTERNAL 4.0 (MREM) 0.000 CROAM LIVER

  • Ti1IO CALCULATION OF DOCE IS DA0ED ON TE0ltNIQUES DECCRIDED IN Tl!E COMMONUCALTl! EDICON OFFSITE DOCE CALCULATION MANUAL. T!!ESE TEC}lNIOUES DIFFER FROM Tl! DOC DCOCRIDED IN 40 CFR 141.

REOULTS ItACED UPON ODOM REVIOION 11 UPDATE CS204 FEDRUARY 1906

m. u + . .,

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J

.1707 ANNUAL REPORT

MAXIMUti D00E0 f(MREtO RCOULTIND FROM LIQUID' EFFLUENTS b lPCRIOD OF RCLEACE 01/01/07 TO-12/31/07' CALCULATCD 00/16/07 I
  • "T- 2ND , c3RD .4Til

[ DOCE TYPC. QUARTER JAN-MAR CUARTER APR-JUN QUARTER JUL-CEP GUARTER OCT-DEC-ANNUAL' O

0.00CiOO

. ' TOTAL' O . 41 E- 0 ". 1.70E204 0.00E400 .4 .10C-- 0 4 .-

1: DODY'

l. INTERNAL 3.37E 04 2.67E-0* 0.00C100. 0.00C100 6iO6E-04' l? LIVER LlVER LIVER' r . .

D ' T!!IO. IO A 'EPORT TOR Tl!C CALCMDAR- YEAR 1907 COMPLIANCE 0TATUC '10 CFR 50 APP. I

... ...... g op Apr I, --.. ...- ----

QTRLY 10T DTR 2t!D GTR 3RD GTR 4Til GTR YRLY  %.0F CDJ JAN MAR AP R-- J UN JUL-~SCP OCT-NOV ODJ APP.I

' TOTAL:DODY.(MREM) 1.5 0.00 0.01 'O.00 0.00 3.0 0.01 ORIT. .ORG Af1(MDCli) 5.0 0.01 0.01 'O.00 0.'00 10.0 0.01 LIVER LIVER LIVER RESULTS DAGED UPON ODCM REVISION-12=

UPDATE CO204 TEBRUARY 3706

.__._____m___~

____m_m_____________.__ _ . _ _ _ _

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c.n ',-

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DRESDEN' UNIT' TUO ADULT'RECEPTDR 1707-ANNUAL RCPORT'

-PROJECTED D00E AT NEARCOT COMMUNIT) 4ATER SYSTEM *

  1. PERIOD OF RELEASE - 01/01/07 TO' 12/21/07 CALCULATCD 00/16/09

-10T -CND .3RD 4 Til M

'DOSC.TYPC- GUARTER -00ARTCR OUARTER 00ARTER ANNUAL ~

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

- -TOTAL 4.44E 05- ;1.03C 05 0.00E100 0.00E100- 6.20E-05

,DDDY INTERNAL 1.31C-04 ,4.64E-05; 0.00Elc0 0.00C100 1. 70 E-~ 0 4

0CCAN CI-LLI- LOI--LLI DI-LLI THIO IO A REPORT FOR T!!E CALENDAR YEAR 1907 COMPLIANCE STATU0 - 40 CFR'141

, TYPC ANNUAL LIMIT 10 0F LIMIT TOTAL 4.0 (MREM) 0.002

'D0DY INTERNAL. 4.0 (MREM) .0.004 GROAN 01-LLI

, -*. TilIO CALCULATION OF D00C 10 DACED.ON TCCifMIGUEO DECORIDED IN Ti!C L COMMONUCALTl! CDIODN OFFCITE DOCE CALCULATION MANUAL. TilLCE TECllNIGUES DITTER -

PROM TH00E DCOCRIDCD .!N 40 CFR 141.

I:

/ -RCCULTC DAOCD UPON ODCM REVISION 11 UPDATE CS204 FCDRUARY 1986 11 L

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p - DREODENLUNITTTlfREE INFM!T CCCEPTCP

'1707LANNUAL REPORT MAXIMUM DOCES (MREM)RESULTING FROM LIGUID EFTLUENTG PERIOD OF RELEACE' . 01/01/07 TO~12/31/07' CALCULATED 08/16/07 1CT- 2ND 3RD 4 Tif ,

DOCE TYPE- QUARTER QUARTER :00ARTER 0UARTER ANNUAL JAN-MAR APR-JUN JUL-CEP _

OCT-DEC

TOTAL' 1.~ 13 E -- 0 4 . 41E-05 0.00E400 0'. 0 0 E -10 0 1. 57E- 04-.

D0DY.

INTERNAL 1.77i' 04 1.32C-04 0.00EiC0 0.00Cl00 0.'73E-04 ORGAN-DONE LIVER LIVER Tl!!C IC A. REPORT FOR Tl!E CALENDAR YEAR 1707 COMPLI ANCE STATUC -- 10 CFR 50 APP. I

.. ......-.. % OF APP I. ---"-- - - - -

QTRLY 1CT OTR' '2ND OTR 3RD OTR 4Til GTR ,YRLY  %' 0F DDJ JAN-MAR 'APR JUN JUL-0EP OCT-NOV ODJ APP.I

' TOTAL DODY (MREM) 1.5 0. 0'1 .0.00 0.00 0.00 3.0 0.01

CRIT. CROAN(MREM) 5.0 - 0.00 0.00 0.00 0.00 10.0 'O.00 DONE LIVER LIVER RECULTG DACED UPON ODCM REVISION-11 UPDATE CO204 TEDRUARY 1706 1

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  • PCRIOD OF RELCACE 01/0I/07 T0 12/31/09 CALCULATED 03/16/87 n .,

~

1CT- '2ND' 3RD. 4 Til .

' DOSE TYPC QUARTER._ OUARTER- CUARTCR c0UARTER ANNUAL-JANrMAR ' A P R -'J U N JUL-SEP DCTrDEC TOTAL 1'.13C-04 4.41E-05 -0.00E400 0.00E100 1 5?C- 04'

,DDDY. ,

iINTERNAL. 1.77E  :.32C-04 0.00E100 0.00EiOO 2.93E-04

oncAN DONC LIVER ' LIVER Tl!!C
IS.'A REPORT FOR Tite CALENDAR YCAR 190?-

COMPLI ANCE' CTATUS - 40 CFR 141

  • TYPC ANNUAL' LIMIT  % OF. LIMIT

. TOTAL 4.0 (MREM)' O.004-

"3 pony-4 4.0 (MREM) 0.007 INTERNAL CRCMI LIVER

  • - -T!!IC CALCULATION OF- DOCE IC DACED ON TECl!NIGUCC DESCRIDCD IN THE

': COMMON' J EALT11 EDICON OFTSITE DOCE CALCULATION M/iNUAL. TilECC TCCilNIGUEC DIFFER TROM TH00E OCCCRIDED IN 40 CFR 141.

RCSULTS 1: ACED UPON ODCM REVISION 11 UPDATC CO204 FCDRUARY 1986

... /

i j

DRECDEN UNIT Tl!REE ADULT RECEPTOR 1?O7 ANNUAL REPORT MAXIMUM DOCES ' MREM) RESULTING FROM LIOUID EFTLUEt4TC PERIOD OF RELEACE 01/01/07 TO-12/31/07 CALCULATED 08/26/09 1CT OND 3RD 4 T!!

DOCE TYPE 00ARTER OUARTER 00ARTER OUARTER ANNUAL JAN-MAR APR-JUN JUL-CEP DCT-DEC TOIAL 2.12E-04 1.70E 04 0.00E100 0.00EiC0 4.07E-04 DODY INTERNAL 2.70E- 04 2.77L-01 0.00Ef00 0.00E100 5.77E-04 OT:CAN LIVER LIVER LIVER TilIC IS A REPORT FOR TIlC CALENDAR YEAR 17C7 COMPLI AtlCE CTATUC 10 CFR 50 APP. I

- % OF APP I. - - - -- ---

OTRLY 1CT OTR 2ND OTR 3RD OTR 4T!! OTR YRLY  % OF CDJ JAN-MAR APR~JUN JUL-SEP OCT -NOV ODJ APP.I TOTAL DODY (MREM) 1.5 0.01 0.01 0.00 0.00 3.0 0.01 CRIT. CRCAN(MREM) 5.0 0.01 0.01 0.00 0.00 10.0 0.0.1 LIVER LIVER LIVER REOULTS DACED UI'ON ODCM REVISION 11 UPDAT'E CO204 FEDRUARY 1906

_m ___-._ _ _ _ _ . _ _ _ _ _____-_____________________.__.__m. _ _ _ _ _ _ . _ _ _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _____x_ _ _ _ _ - _ _ _ _ _

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. .DRCCDCN UNIT T!! REC L ADULT RECEPTOR-L<

l l' .1707 ANNUAL REPORT L PROJCCTED DOCL AT.NCARCCT COMMUNITY UATCR SYSTEM *.

l PCRIOD OF RCLCACE - 01/01/07 TO 12/31/07 CALCULATED 00/16/07 1CT 2ND 3RD 4Til DOCE TYPC OUARTER 00ARTER OUARTER GUARTER ANNUAL J A N - h.'4 R APR-JUN JUL-CEP OCT -DEC TOTAL 3.06E-05' O.02C 05 0.00C400 0.00E400 5.00C DODY .

j INTCPNAL 1.17C-Oa 5. 20E 0.00Cl00 0.00EiOO 1.67C-04 ORCAN CI-LLI CI-LLI DI-LLI Ti!IC IS A REPORT FOR TifC CALENDAR YEAR 1707 COMPLI ANCE CT ATUC - 40 CFR 14:

TYrc ANNUAL LIMIT  % Of LIMIT TOTAL 4.0 (MREM) 0.001 D0DY INTERNAL 4.0 (MDCM). 0.004 ORGAN CI-LLI

  • TlfIC CALCULATION OF DOCE IC DACED ON TEClfNIOUEC 1- 50RIDED IN TilC COMMONUEALT!! CDICON DTFCITE DOCE Ct.LCULATION MANUAL. T}iCCC TECHNIGUEC DIFFCR FROM Tif0CC DCCCRIDED IN 40 CFR 141.

RESULTC DACCD UPON ODCM REVISION 11 UPDATE CO204 FCDRUAliY 1986

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..' DRESDEN NUCLEAR POWER STATION DOCKET NOS. 50-10, 50-237, 50-249 METEOR 0 LOGICAL' DATA:

(Includes hourly data for Abnormal' Release dates on the 4th and 25th of

. March, 1989)-

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CECO DRE5Dtb STAiton January-Jue 1999 35 ft. WIND $P((0 and WIND DIRECil0N 150-35 f t. L,.7E9ENTI AL TEMPERATURE

. Il C A5 W NN[ WE [NE i (5E 5 5 55W SW WSW W WNW TW NNW TOT AL' IU NU N 55 R5 (5 TDTAL 4

1 (U .00 . 00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00

- 3 #U 40 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00

. .! Sit ' .00 .00 . 00 .00 .00 .00 .00 .00 00 .00 .00 .00 .00 .00 .00 .00 .00 .00

-t . 00 .00 .00 . 00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 l

'3 55 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 00 .00 .00 6 #5 .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 .M .00 .00 .00 .00 .00 .00 .00

.00 EU .00 .00 .00 .00 .00 .00 .00 .00 .50 .00 .00 .00 .00 .00 .00 .00 .00 .00

~ 3 EU .00 .00 .00 .00 .00 .00 .00 .00 . 00 .00 .00 .00 .00 .00 .00 .00 .00 .00 9 SU .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .60 .00 .00 .00 .00 .00

- N .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 4 55 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 6 KS .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 EU .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 G MU .00 . 00 .00 .00 .00 .00 .t:0 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 7 50 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 N 00 ,. 00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 4 55 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 6 55 .00 .00 .00 .00 . 00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 'A C5 . 00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00

.00 EU .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ."0 MU .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 C SU .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 AN .00 .00 .00 .00 .00 .00 .00 .06 .00 .00 .00 00 . 00 .00 .00 .00 .00 .00 t 55 .0n .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00

. E M5 .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

.00 101 5.11 J.34 5.34 J.89 6.12 6.48 a.32 6.22 B.95 1.10 6.3B 5.55 1.66 8.14 6.53 6.81 100.0015.d2 d.32 d.15 34.93 30.41 8.33 1.18 l00.00 l 5 (V .91 14 .E4 .14 45 43 .6d .18 1.12 .51 .62 .59 f.47 2.23 2.23 1.80 15.42 l U MU .28 .26 .11 .33 .28 .24 .21 .13 .2d .28 .]? .51 .33 .26 .21 .12 4,32

' 8 $U ' .30 .21 .19 .33 .19 .21 .21 .31 81 .36 .2d .31 .26 .36 .24 81 d.15

-4 2.16 1.92 2.80 2.11 2.91 2. id 1.50 1.80 2.56 1,66 1,61 1.6A 2.28 2.35 1.05 2.91 34.93 i 55 1.0? 1.04 1.38 1.26 1.92 2.61 1.41 2.33 3.39 2.82 1.99 1.50 2.92 2.28 1.52 1.02 30.41 0 K5 .33 .!? .14 .09 .28 .83 .2d .66 .91 1.04 1.23 .18 .28 .51 .38 .31 8.33 1 IS .02 .00 -.02 .02 .42 .02 .05 .14 .19 .33 .36 .11 .12 .09 .09 .12 1.18 1

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h 3; 1-g y (iy' ls ' CECO 00ESDEN ST&710# ) . ' January-June,1989

[. 300 fti NIND SPEED and NIND O!0EC110N 300G5 ft. BlFT[0ENilAL 7EMPE0ATWE NUN 8E0 f4 085E0 Vail 0NS 4260 y

h ' , SPEED - . .

.. . . - Dl0EC710N CLASS S'A81LITV CLASS .

' i

- CLA55 m W NNE NE J ENE E . ESE . *E . 55E 5: SSir < 5N ' NSW N- NNN NN ' NNN . TOTAL ' EU l ND : : 5U .N 55 . N5 ES : 7OTAL >

~

i EUi i.00i :.00 .00 .00 2. .00 ;.00- .00 .00 ' .00 .00 .00 .00 .00 I .00 .00 00 . 00 .00

  • NU . '.80 ' . 00 c .00 - .00 . .00- .00 .00 ' 00 .00 ~ .00 .00 E .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 :

-? N: .05 .00 -.02 .!! .09 -.05 .99 : .05 ' .02 .12 .05 .07 .14 .02 .45 .05- ' .99 .99

- 3 55 . 02 .07J .05 : .05 1.07 .05 .00 14 .99 .16 .09 ;19 .01 .07 .00 . 05. 1.17 1.17

' #5 o .02 .00 .00 . 00 ' .02 00 .02 .00 .00 .02 .00- .02 .02 .00 . 99 .00 .23 '- .23 ' , 1 E5' ' .00'. 00 .00 '.00 !- :.10 / g60 .00 L .00 .00 00 .00 .00 .00 .00 00 .00 .00 .00 2.39

^ EU '.021 .45' de .'90R ' 00' N) . 00

. .00 .00 .00 .00 .00 .00 .00 .00 .02 .09 . 99 NU .07 ~ .00 ' .00 " .05 . 00. .00 .00 '.00 . . 00 ' 00 .00 .00 .00

. . 00 .00 .29 .21 .21 4 50 : '.0 7 .09 .09 .05 .00 ' 1.07 .02 .00 ' .00 .00 .00 ' .02 . 02 ,07 .12 .05 .68 .68

, --N .14 . ..!! . .19 j ' 56 '.33 49 .38 i .42 .54 .38 45 .61 .38 40 .28 .28 6.13 , 6.13 7 55 .09 .09 .19 .31 .12 . 12 .21 .35 .45 : .33 35 .45 .19 .23 .19 .23 3.90 3.90

- NS .00 .02 .09 - .02' .07 .00 - .00 = 07 ,.12 . 09 - .14 .14 .12 .12 .05 .05. 1.10 1.10

- E5 : .00 ' .00. . 00 '.02 .02 .00 .00 .00 .00. .07 .01 ' .02 .02 .05 . 00 :.00 28 .28 12.39 7

. EU ,16 ' .00 ; .00 ; .00 .62 .00 .00 , .00 .00 .00 100 .00 .02 .06 .05 . 16 42 42 .

' NU .16 a . 05 ; ',05.. 00 _. 05 00 .02' .00 .00 .00 ' .00 .02 .05 .99- . 21 .3I 1.01 1.01 8 $U ' .09 .id .14 L .19 .12 .02 .16 .05 .02 .07 .05 . 02 .14 .19 . 31 .19 1.90 1.90

,,. a .92 ' '.70 .85 1.78 - ,17 .63 ,61. ' ,75 ' .87 ' .63 .59 .80 .75 .63 . d9 1.06 13.24 13.24-1 55 .31 41 47 .59 .13 .40 .42 .52 '.59 42 .42 49 .77o . 33 .47 .23 7.63 7.63 2 K5 ~.02 .09 .14 .07 . 05' 05 .16 '.23 09 . 09 .14 .d5 .33 . 12 . 19 .09 2.32 2'.32~

l ES .00 ' . '.00 : .62 .00 . 00 ' '.00 .02 .07 .00 - .00 .07 .02 .02 .12 . 00 -.00 .35 .35 ~

26.88 EU. 400 .26 .00 ' .00 .00' .00 1 00 .00 - .00 .00 .00 .02 .00 ,.0 7 .45 .00 .40 .H I a0 ' .02 T .07 .05 .00 .02 .00 .07 .00 .02 ~.00 .02 .00 .00 .16 . 28 .09 .82 .62-

' 3 50 ' .05 ' .09 ' .09 '.16 .02 .99 1 .09 .14 .09 .05 .07 .00 . 07 .21 . 14 .07 1.86 - 't.46

-N l.43 .61 1.27 -1.29 - .66 .85 .31 .80 .80 .47 .75 . 80 1.34 1.60 1.13 1.08 15.i6 15.16 1 35 .28 .61. 40 ' .!! -.52 ' l.01 .75 _ l.06 1.13 1.22 75 .89 1.3d .96 .87 .68 12.68 - 12.68 8 KS .16 : 409 .18 ".00 .00 .21 .52 .14 .28 .38 .49 .54 '.28 '.09 .26 .!? 1.11 ' 3.71

. ES; .00 .00 .00 ' .00 .00 .00 .00 .02 .02 .05 . 12 .07 .09 .05 . 02 ~ .05 . .49 .49 34.72 EU~ .00 . 05 . 00 ; . 00 ".00 .00 .00 ' .00 .00 .00 . 00 .00 .00 .00 . 00 .00 .05 . 05 l EU .00 .05 .09 .00 .00 .09 .00 .00 .09 .00 .02 .02 .00 .02 . 00 .00 40 40

- 9 SU ' .00 ' .02 .05 .00 .07 .09 .09

.05 .02 .00 .02 .07 .07 '.00 . 02 .02 .61 .61 l .- N 45 .d9 . 26 .!! 47 .38 .26 .54 .73 .54 40 .54 .94 . 63 . 40 7.65 7.65 2 55 .38 .16 .02 .02 .12 .33 ,42 ~ .28 1.17 1.36 .62 .56 1.08 .80 . 20 .05 7.86 7.86 4 85 ,.12 .05 .07 .00 J0 .62 .02 .05 .21 .12 .19 .05 .05 .02 . 00 .12 1.08 1.08 IS . 02 - .00 .On . 00 .00 .00 .02 .00 .00 .02 .02 A2 .00 .00 .00 .02 .14 .14 17.19-ED .00- .00 .05 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00

' 2 CU .00 00 - .00 '.00 .00 .00 .00 .00 .00 .02 .02 .00 .00 .00 . 00 .00 .05 .05

. 5 $U . 02 .02 .00 . 00 .00 ,00 ,.00 00 .05 .62 .09 .02 .02 .00 . 90 .00 .26 .26

'- N . 09 .16 49 .00 .00 .00' .09 .21 40 . I2 .10 .26 .38 .40 . 14 .12 3.03 3.03 3 55 .12 .00 .00 .00 .00 .00- .02 .09 .35 49 42 .21 .16 .t9 . 05 . 02 2 04 2.04 I ES .00 .05 '.00 .00 . 00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ..00 .00 .05 .05 ES .00 ' .00 . 00 .00 .00 .00 .00 . 00 .00' .00 .00 .00 .00 .00 .00 .00 .00 .00 5.42

. . - . _ . _ _ - _ m - _..__a ______________m, _ . _ _ . _ - - _ - _ _ _ _ _ _ . - _ _ _ __.__:__--____.__.__

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l CEto DRESDEk iT& TION January-June 1989-  ;

300 ft. klWD SP((D and WIND DIRECT!DN 300-35 ft. OlFFERENTI AL itRPERATURE j i

SPIED ' DIRECTION CLASS $7ABillTV CLA55 Ll CLALS k NWI NE ENE E ESE if 5$E 5 $5W $b WSW . W WNW NW Eku TOTAL EU MU 50 t 55 ES E5 TOTAL {

i i

EU .00 ' .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 . 00 .00 .00 .00 i 3 MU .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 t 2 SU . 00 .00 .00 .00 - .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ~ .00 .00 .00 .00 j

- N .00 .07 .05 .00 .00 .00 .00 .00 .05 .00 .00 .05 .00 .02 .00 soo .23 .23 i 3 55 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .02 .id .00 .00 .00 .16 .16

- 6 CS .00 .00 .00 .00 , .00 .00 .00 .90 .00 .00 .00 .00 .00 .00 .00 .0( .00 .00 i E5 L .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .0f .00 . 00 -  !

40 l

1 4

EU .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .to .00 .00 .00 .00 .00 .00 3 MU .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 9 50 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 . 00 .00 .00 00 l

-N .00 .00 .00 .00 .00 .00 .00 .00 .00 . 00 .00 .00 .00 .00 .00 .00 .00 .00 d 55 .00 .00 .00 .00 . 00 .00 .00 60 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 6 C5 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 E5 -.00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 l

.00 t EU .00 .00 .00 .00 .00 .f4 .50 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 ,

6 MU .00 .00 .00 - .00 .00 . .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 l 7 $U .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 W .00 M .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 4 55 .00 .00 .00 .00 .00 .00- .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 90 6 M5 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .09 .00 .00 .00 .00 .00 .00 .00 E5 .00 .00 ' .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00

.00 j

[U .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 MU .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 C SU .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 AN .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00

'l t 55 .00 ,00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00 .00

  1. C5 .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 . 11 0 .00 .00 .00 .00 .00

,00 TOT 5.31 4.95 5.28 5.61 4.7d 4.95 d.77 5.99 B.00 7.54 6.95 7.35 B.62 7.89 6.36 5.70 100.00 .96 2.49 4.91 46.43 35.45 8.50 1.27 100.00

$ EU .19 .35 .00 .00 .02 .00 .00 .00 .00 .00 .00 .02 .02 .07 .09 .19 .96 0 NU .26 .16 .19 .05 .07 .09 .09 .00 .12 .02 .07 .05 .05 .28 .49 .49 2.49 8 $U .23 .38 .38 40 .21 .28 .33 .21 .16 .23 .23 .id .33 47 .59 .33 d.91

-N 3.08 2.35 ' 3.12 3.87 2.72 2.39 1.14 2.75 1.22 2.de 2.54 2.98 3.52 d.01 2.72 2.98 46.43 T 55 1.20 1.41 1.13 1.11 1.55 1.90 1.83 2.44 3.78 3.99 2.06 2.62 3.76 2.49 1.85 1.27 35.45 0 RS .33 .31 45 .09 .14 .28 .73 .49 .70 .70 .96 1.20 .00 .35 .59 .38 B.50 Y [5 .02 .00 .02 .02 .02 .00 .05 .t9 .02 .14 .28 .14 .14 .21 .62 .01 1.27 j 1

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3n; jCECODRE5DENNUCLEARPOWERSTATION  !

,' HETEOROLO6] CAL DATA r

DATE- .... WIND SPEED.... .WINDDIRECil0N. ..'.WINDSIGNA... TEMP: ...Diff T... ...... DEWPOINT...... PRECIP C -DD-YY HH 35 150 300 35 150 300 35 150 300. 35 150 300 '35 150 300 10 i

3-4-89 1. 7.3' 12.1 17.0 110 117 128- 7 4 ~37.1 .1 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 37.1 38.3 .00 ll 3-4-89 3 7. 0 . 11.5 16.6 140 154 165 12 = 8 7 40.9 1.0 2.0 39.8 40.3 40.7 .00 3- 4 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 .173 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 11 5. 42.3 .5 1.0 41.3 41.3 41.2 . 00 l 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 l- 3- 4-89 10 . 7.5 '11.7 15.6 268 268 267 9 10 11 42.7 .3 .l. 999.0 - 41.1 40.5 .00.

3- 4-89 11 6.7 9.4 . 16.8 261 263 265 7 6 7 42.5 .5 .4 41.7 40.3 39.8 .00 3- 4-89 12 7.8 11.0 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 <t64 263~ 4 4 4 38.8 .9 -1.9 36.6 35.7 34.3 .00

. 3- 4-89 14 10.1 13.6 15.0 280 280 277 9 7 6 36.0 .8 -1.9 32.9 32.1 ' 30.9 .00 -!

3- 4-89 15 13.9 19.3 21.1 289 288 .285 6 4 4 33.3 .8 .-1.6 29.4 28.3 27.3 .00 .,

3- 4-89 16 .12.9 18.1 20.0 287' 286 283 8 6 6 31.6 .8 -1.4 27.7- 26.5- 25.7 .00 -l 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  ;

3- 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  ;

3- 4-09 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 -1.6 25.1 24.5 24.1 '. 00 3- 4-89 21. 12.1 15.8. 17.5 337 337 335 5 5 4 27.4 -1.0 -1.6 22.3 21.8- 21.1 . 00 3- 4-09 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 17.4 '18.9 347 348 347 7 7 6 25.0 -1.0 -1.6 19.0 19.1 17.9 .00  !

3-.4-89 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 1

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. CECO DRESDEN NUCLEAR PONER STATION METEOROLOGICAL 0ATA

~D A T E' ....I'IND SPEED.. .. . WIND DIRECTION.' ... WIND EIGMA...' TEMP ...Diff T... ..... 0EW POINT...... PRECIP

. C -DD-YY HH 35 150- 300 35 150 300 ' 35 150 300 35 150 300 35 15e '300' 10

3-25-89 l 10.4' '15.7 -21.5 197 198 197 4 3 3 5!.B .0 .2 - 42.2 41.0 41.3 . 00-3-25-89 2- 9.4 - 14.6 20.3 ' 215 213 211- 13 . 10 8 51.2 .0 .I 44.2 43.0 '43.1 .00

> 3-25-89. 3- '10.2 15.9 21.8 230 227 225 3 2 3~ 50.1 .2 .5 44.6 . 43.6 43.5 .00 3-25-89 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 5 6.1 12.3 16.8 233 239 249 7 '7. _9' 46.7  : 1.2 - 2.4 42.6 '42.1 41.3 .00 3-25-89 6 9.0 14.7 19.1 283 281 278 12 8 6 45.8 .3 .2 40.4 39.6 : 38.7 ' .00 3-25-89 1 8.4 12.2 15.1: 279 278 277 8 7 5 43.5 .5 . .8 39.0 37.9 37.4' .00 3-25 8 7.0 . 9.3 11.0 288 268 290 8 8 9 44.9 -1.1 -1.5 39.2 38.2 37.2 .00 3-25-89 9 6.6 - 7.8 8.5 307 307 310 23 20 18 49.4 -l.6 -2.3 39.7 .38.8 , 37.6 .00 3-25-89 to 8.1 10.0 10.2 346 347 345 11 10 9 53.9 -1.7 - -2.7 40.5 39.6- 38.5 .00 25-89 11 6.4 7.9' 8.4 7 7 5 20 15 .12 58.5 -1; i. -3.0 42.1 41;3 40.1- .00-3-25-89'l2 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 72 75 78 48 41 33 64.7 -l.1 -2.3 40.6 40.1 38.9 .00

~3-25-89 14' 6.3 7.3 1.5 71 74 77- 56 48 47' 65.4 -1.1 -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 39.7. .00 3-25-89 16 8.5 11.1 12.5- 69 10 68 10 8 7 58.9 -1.1: -2.2 40.8 39.8 39.0 .0t 3-25-89 17 8.6 12.2 13.8 66 67 65 6 5 3 56.0 .8 -1.7 40.3 39.2 41.5 . 00 ;

3-25-89 18 6.9 9.4 11.3' 67 10' 70 6 4 4 53.3 .6 -1.4 40.0' 30.9 38.3 .00

'3-25-89 '19 5.2 7.2 8.3 69 72 11 8 6 4 19.7 .5 -1.2 39.6 38.4 38.0 .00:

3-25-89 20 5.6 7.5 8.1 75 75 70 10 - 7 5 45.8 .6 -1.2 38.3 37.2 '36.9 .00 3-25-89 21 6.1 - 8.0 9.7 12 74 . 70 10 6 4. 42.3 .7 -1.1 36.5 35.4 34.9 .00 3-25-89 22 8.9 12.1 14.4 97 93 86 6 4 5 39.7 .6 .7 35.0 33.9 33.4 .00 3-25-89 23 5.1 7.0 8.7 93 88 82 ll 7 5 38.7- .5 .8 34.5 33.5 33.1 .00

.3-25-89 24 7.1 9.4 l1.9 97 93 87 5 6 7 38.3 .6 .8- 34.4 33.4 32.9 .00 TOTAL- .00 l

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