ML20235M747

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Effluent & Waste Disposal Semiannual Rept Jul-Dec 1988
ML20235M747
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 12/31/1988
From: Eenigenburg E
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
0727A, 727A, 89-111, NUDOCS 8902280406
Download: ML20235M747 (16)
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'DRESDEN NUCLEAR POWER STATION DdCKET NOS.- 50-10,50-237;50-249 MEASUREMENTS AND APPROXIMATIONS A. ' Fission and activation gases: The D-1 chimney and D2/3 chimney are sampled daily via a grab sample. .The D-2 and D-3 Reactor Vents are sampled! weekly via a grab sample. The samples are' analyzed for specific isotopes present in the release using a Ge(Li) spectrometry system. Tritium is collected via a continuous. sample on the D-2/3 i

- chimney and via a grab sample on the D2/3 Reactor Vent and analyzed using a Liquid Scintillation Counter.. Kr-85 is estimated in the D2/3

. chimney using a recoil or non-recoil calculation using fission /sec.

plot and the sum of Xe-138, Kr-87, Kr-88, Kr-85m, Xe-133:and Xe-135 activities.

B. Iodine and Particulate: Iodine and particulate samples from the D-1 and D2/3 Chimney and the D-2 and D-3 Reactor Vents are collected for a seven' day period. These samples are analyzed for. specific nuclides present in the release using a Ge(Li) spectrometry system. When particulate samples are not used for reporting the release rate due L

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 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. Rad-waste' batch discharges are also analyzed for specific isotopes present in the release.using a Ge(Li) spectrometry _ system. A' composite of all batches for the month is sent to a vendor to be analyzed for Sr-89, Sr-90, Fe-55, and Gross Alpha. One of the LPCI samples for each month is analyzed for specific isotopes present in the releases using a Ge(Li) spectrometry system. This sample is sent to a vendor to be analyzed for Sr-89, Sr-90, Fe-55, and Gross Alpha activity.

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Page 1 of 15 j l

1 0727a i

8902280406 881231  ; {[

PDR ADOCK 05000010 R PDC -

/

. .DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT-Julv Through Deca =her 19&B GASEOUS EFFLUENTS

. SUMMATION OF ALL RELEASES Docket Numbers: 50-10 50-237

.50-249 UNIT 3rd QUARTER ith QUARTER

'A. FISSION AND ACTIVATION GASES

'1. Total Release. Ci 1.81 E01 1.66 E01 1

2. Average Release Rate for Period -uCi/sec 2.28 E00 2.09 E00 3.. Percent of Technical Specification Limit  % * *

.B. 10 DINES 1.. Total. Iodine-131 Ci 2.88 E-02 8.21 E-03

2. Average Release Rate-for Period uCi/sec 3.63 E-03 1.03 E-03

-3. . Percent of Technical Specification. Limit  % *

  • C. PARTICULATE
1. Particulate with half-lives > 8 days 01 3.83 E-03 3.06 E-03

' 2. - Average Release Rate for Period uCi/sec 4.82 E-04 3.85 E-04

3.  : Percent of Technical-Specification Limit  % * *
4. Gross' Alpha-Radioactivity Ci MDL MDL D. TRITIUM
1. Total Release Ci 8.38 E06 4.69 E06
2. . Average Release Rate for Period uCi/see 1.05 E06 5.90 E05
3. . Percent of Technical Specification Limit  % * *
  • Will be included in the Annual Report on Environmental Radioactivity Data k

Page 2 of 15 0727a f

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1

DRESDEN NUCLE 4R POWER STATION'

. .. EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT July Through December 1983 D1 Chimnev GASEOUS EFFLUENTS GROUND LEVEL RELEASES- <

Docket Number 50-10 SEMI-ELEVATED. RELEASES xx ELEVATED RELEASES CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT 3rd QUARTER hih QUARTER 3rd QUARTER h.th QUARTER FISSION GASES Ci Xe-138 C1 *

  • Xe-135m Ci *
  • Kr-87 _.01 *'
  • Kr-88 Ci *
  • Kr-85m C1 *
  • l Xe-135 C1 *
  • Xe-133 C1 *
  • Others: Ci Ci TOTAL C1 None None

-IODINES I-131 C1 *

  • I-133 - 01' *
  • e I-135 C1. '*
  • TOI&L C1 None None PARTICULATE Sr-89 Ci * *  !

'Sr-90 _Ji 1.20 E-07

  • l Cr-51 Ci *
  • 2.29 E-07 Co-58 Ci *
  • Fe-59 Ci *
  • Co-60 C1 1.17 E-06 3.01 E-06 Zr-95 C4 *
  • Nb-95 Ci *
  • Ru-103 C1 *
  • An-110m Ci *
  • Sb-124 C1 *
  • Cs-134 Ci *
  • Cs-136 Ci *
  • Cs-137 Ci 7.65 E-06 5.37 E-06 Ba-140 Ci *
  • Ce-141 Ci *
  • Ce-144 Ci *
  • Ba-133 Ci *
  • Sb-125 C1 *
  • Others: C1 J Ci

_C1 Ci l Ci j TOTAL Ci 8.94 E-06 8.61 E-06 None None )

  • See Table for MDL of Each Nuclide Page 3 of 15 w - a

.y .- . - _ _ _ _ _ _ _ _ _ - - - - - - - - _ - - - - - - - - - _ - - - - - . - - - - - - - _ - - - - - - - - - -

DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Julv- 'Through December 1983 Docket Number 50-10 TABLE OF MINIMUM DETECTABLE LEVPLS FOR GASEOUS EFFLUENTS D1' Chimney GASEOUS EFFLUENTS AVERAGE FLOW-50.000 efm El (uCi/cc)  % OF TIME < tid 1 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-08 100.0

.Xe-133 4.32 E-08 100.0- -l Others:

.2. 10 DINES

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

3. PARTICULATE l

Sr-89 2.8 E-11 100.0 Sr-90' 9.7 E-12 83.2 Cr-51 4.20 E-13 100.0

.Mn-54 5.27 E-14 96.7

'Co-58' '4.83 E-14 100.0 Fe-59 7.58 E-14 100.0 Co-60 1.26 E-13 46.2

.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 i Sb-124 5.86 E-14 100.0 I-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 26.6

.Ba-140 1.91 E-13 100.0 Ce-141 7.64 E-14 100.0 Ce-144 3.27 E-13 100.0 i Zn-65 9.03 E-14 100.0 Ba-133 6.93 E-14 100.0 Sb-125 1.39 E-13 100.0 1 Others: 1 Page 4 of 15 0727a w_ _ _ _ _ .-

DRESDEN NUCLEAR POWER STATION

... EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

, July __ Through _DenemheI_. 1988 D2/3 Chimnev GASE0US EFFLUENTS l I

GROUND LEVEL RELEASES l Docket Numbers: 50-237 SEMI-ELEVATED RELEASES 50-249 xx ELEVATED RELEASES CONTINUOUS MODE BAIC1LEQDE NUCLIDES RELEASED UNIT 3rd QUARTER Mh QUARTER 3rd QUARTER h_th QUARTER FISSION GASES Ci Xe-138 _Ci 2.54 E00

  • Xe-135m C1 1.56 E00
  • Kr-87 Ci *
  • Kr-88 _CL *
  • Kr-85m Ci *
  • Kr-85 C1 2.16 E-03 2.68 E-03 Xe-135 C1 1.40 E01 1.64 E01 l

Xe-133 Ci *

  • Others: Ci  ;

C1 l TOTAL Ci 1.81 E01 1.64 E01 None None  !

10 DINES -

I-131 Ci 1.54 E-03 5.52 E-04 )

I-133 _Ci 1.06 E-02 3.42 E-Q3 I-135 _Ci_ 1.56 E-02 4.04 E-03 TOTAL Ci 2.77 E-02 8.01 E-03 None None PARTICULATE Sr-89 Ci 7.03 E-05 4.30 E-05 Sr-90 C1 3.37 E-07

  • Cr-51 Ci *
  • Mn-54 C1 1.90 E-04 3.22 E-05 1 Co-58 Ci *
  • Fe-59 _gi__ *
  • Co-60 Ci 5.96 E-04 1.57 E-04 Zr-95 Ci *
  • Nb-95 Ci *
  • Ru-103 Ci *
  • An-110m C1 *
  • Sb-124 Ci *
  • I-131 -C1 1.46 E-04 8.05 E-05 Cs-134 Ci *
  • Cs-136 Ci *
  • Cs-137 _Di 2.45 E-05 2.28 E-04 i Ba-140 _Ci 8.99 E-04 5.45 E-04 J Ce-141 Ci *
  • Cp-144 Ci_ *
  • Zn-65 Ci *
  • _

Ba-133 _Ci_

Sb-125 *

  • Ji 01hers: ci C1 Ci C1 Ci TOTAL C1 1.,33 E-03 1.09 E-03 None None
  • See Table for MDL of Each Nuclide Page 5 of 15  ;

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.DRESDEN NUCLEAR POWER. STATION

[; .. 'Julv- Through _ Deca =her 1988 , Docket Numbarst F -

50-237.

TABLE OF MINIMUM DETECTABLE' LEVELS. 50-249 FOR GASEOUS EFFLUENTS-i 3r'd atr 289. Kcfm l>

D2/3 Chimnev GASEOUS EFFLUENTS AVERAGE FLOW 4tha[tr313 Kcfm .,

l1 MDL-(uCi/cc).  % OF TIME < MDL- i

1. FISSION GASES Xe-138 4.16 E-08 98.9 .j)

Xe-135m- 1.29 E-07 98.4 1 Kr-87 3.03 E-08 100.0 Kr-88 5.21 E -100.0 Kr-85m- 1.78 E-08 100.0 Kr-85' 4.43 E-06 0

, Xe-135 1.52 E-08 47.8 Xe-133. 4.32 E-08 100.0 Others:

2. , IODINES I-131 5.34 E-14 0 1 I-133 5.57 E-14 3.8.

I-135 ~1.19 E-13 26.1 "3. PARTICULATE Sr-89 2.8 E-11 0 Sr-90 9.7 E-12 66.3 ,

Cr-51 4.20 E-13 100.0 i Mn-54 5.27 E-14 42.9 Co-58 4.83 E-14 100.0 Fe-59 7.58 E-14 100.0 Co 1.26 E-13 2.7

Zr-95 9.09 E-14 100.0 Nb-95 4.96 E-14 100.0 Ru-103 4.95 E-14 100.0 Ag-110m 5.12 E-14 100.0 Sb-124 5.86 E-14 100.0 I-131 5.15 E-14 4.9 Cs-134 5.'73 E-14 100.0 /'

,Cs-136 5.49 E-14 100.0 Cs-137 6.21 E-14 21.7 Ba-140- 1.91 E-13 7.6 Ce-141 7.64 E-14 100.0 )

Ce-144 3.27 E-13 100.0 l Zn-65 9.03 E-14 100.0 l Ba-133 6.93 E-14 100.0 Sb-125 1.39 E-13 100.0 Others:

i Page 6 of 15 0727a

DRESDEN NUCLEAR-POWER' STATION

d. ' EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

, . . . Julv Through Decamber 1983 4 ,a,> .

D2/3 Vent GASEOUS EFFLUENTS p;

L ' GROUND LEVEL RELEASES .

, Docket Numbers: 50-237 xx SEMI-ELEVATED RELEASES 50-249 ELEVATED RELEASES qQMIJNMOUS MODE BATCH MODE

-NUCLIDES RELEASED UNIT hd QUARTER 4.th QUARTER hd QUARTER !ith QUARTER FISSION GASES Ci Xe-138 Ci *

  • Xe-135m C1 *
  • Kr-87 C1 *
  • Kr-88 _.01 * *

'Kr-85m Ci *

  • Xe-115 Ci
  • 2.06 E-01 Xe-133 Ci *
  • Others: Ci C1 IQIAL Ci' 2.06 E-01 None Noite IQDINES I-131 Ci__ 9.66 E-05 4.36 E-05 I-133 _ C1 6.01 E-04 1.36 E-04

'I-135 Ci- 4.22 E-04 1.61 E-05 TOTAL Ci l'.12 E-03 2.00 E-04 None- ,

None PARTICUIATES Sr-89 Ci 8.89 E-07 *

'Sr-90 C1 *

  • Cr-51 C1 1.09 E-04 7 2B_E-05 Mn-54 Ci 3.29 E-Oh 2.15 E-04 Co-58 C1 1.63 E-05 5.53_E-05 Fe-59 C1 2.25 E-05 1.27 E-05 Co-60 C1 1.36 E-03 1.58 E-03 Zr-95 Ci *
  • Nb-95 Ci *
  • Ru-103 Ci *
  • Ag-110m Ci *
  • Sb-124 C1 1.19 E-06
  • I-ill- C1 1.16 E-05 3.73 E-06 Cs-134 C1 * * . _ _ _

Cs-136 C1 *

  • Cs-137 _ni_ 1.35 E-05 1.82_E-05 Ba-140 01 2.15 E-05 3.74 E-OfL Ce-141 _Ci_

Ce-144 Ci *

  • Zn-65 .C1 5.33 E-06
  • Ba-133 Ci *
  • Sb-125 _Ci_

Q1hers: Ci C1 Ri_ _

TOTAL C1 1.89 E-03 1.96 E-03 None None

  • See Table for MDL of Each Nuclide Page 7 of 15 0727a

" si ,

DRESDEN NUCLEAR POWER STATION,

j
i. '- . o,1.g , ,,

Julv ' .Through Dec==her' 19&B Docket Numb:;rst Y

50-237 1 ' TABLE OF MINIMUM DETECIABLE LEVELS- 50-240 j.

< J' FOR GASEOUS EFFLUENTS' by D2:' 110' Kcfm

,. D2/3 Vent- GASEOUS EFFLUENTS  : AVERAGE FLOW D3: '110 Kcfm

,: MDL(uC1/cci 1,OF TIME < MDL; a

'1..

FISSION' GASES' I

Xe-138 4.16 E , 100.0 lXe-135m 1.29 E-07 100.0 Kr-87 3.03 E-08 100.0-Kr-88E 5.21 E-08 L100.0 a Kr-85m 1.78 E-08 100.0

?' Kr-85 '

4.43 E-06 100.0-

Xe-135: 1.52 E-08 96.2

'Xe-133 4.32 E-08 -100.0 Others:

y l2. 10 DINES:

I-131' 5.34'E-14 3.8 I-133_ 5.57 E-14 14.7

'I-135 1.19 E-13 78.3

3. PARTICULATE Sr-89 2.8 E-11 66.3~

Sr-90 9.7 E-12 100.0 Cr-51 4.20 E-13 32.6

'Mn-541 5.27'E-14 0 Co-58 4.83 E 53.8 Fe-59 7.58 E-14 78.8 Co-60 1.26 E-13 0 Zr 9.09 E-14 1100.0 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 96.2 I-131 5.15 E-14 59.2 Cs-134 5.73 E-14 100.0 Cs-136 5.49 E-14 100.0 Cs-137 6.21 E-14. 30.4 g Ba-140 1.91 E 58.2

+

Ce-141' 7.64 E-14 100.0 Ce-144 3.27 E-13 100.0 Zn-65 9.03 E-14 96.2 Ba-133- 6.93 E-14 100.0 Sb-125; 1.39 E-13 100.0 Others:

Page 8 of 15 0727a 3 ,

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______-__________A

[ ,

. 'DRESDEN NUCLEAR POWER STATION p . .

f: EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Julv Through -December 198B' n LIQUID EFFLUENTS

- SUMMATION OF ALL RELEASES Docket Numbers: 50 50-2371 50-249 UNIT 3rd QUARTER !Lth QUARTER A. FISSION AND ACTIVATION PRODUCTS

1. Total Release (not incl. tritium, gases, alpha) Ci 1.41 E-02 1.85 E-01
2. Average Diluted Conc. During Period uCi/mL 7.05 E-08 1.97 E-06

?. Iercent of Applicable Limit  % * *

,B. TRITIUM

1. Total Release C1 1.55 E-06 1.05 E01
2. Average Diluted Conc. During Period uCi/mL 7.55 E-12 1.12 E-04 3..Perce*t of Applicable Limit  %  :*-
  • C. DISS0J3ED AND ENTRAINED GASES
1. Total Release Ci 9.49 E-06 4.05 E-04
2. Average Diluted Conc. During Period uCi/mL 4.75 E-11 4.32 E-09
3. Percent of Applicable Limit  % *
  • D. GRQSS_bLPHA RADI0 ACTIVITY
1. Total Release Ci MDL MDL E. VOLUME OF WASTE RELEASED (prior to dilution) liters 1.90 E06 1.11 E07 F. VOLUME OF DILUTION WATER USED DURING PERIOD liters 1.98 E08 8.26 E07
  • Will be included in the Annual Report on Environmental Radioactivity Data Page 9 of 15 0727a i

DRESDEN FUCLEAR POWER STATION J

EFFLUENT AND WAUTE DISPOSAL SEMIANNUAL REPORT Julv Throuf' December 1988 Radwaste LIQUID EFFLUENTS Docket Numbers: 50-10 50-237

1. Number of Batch Releases: 136 50-249
2. Total Time Period for Batch Releases: 43,471 min
3. Maximum Time Period for a Batch Release: 419 min
4. Average Time Period for Batch Releases: 320 min
5. Minimum Time Period for a Batch Release: 3 min
6. Average Stream Flow During Periods of Release of Effluent into a Flowing Stream: 262.72 L/ min CONTINUQPS MODE BATCil MODE NUCLIDES RELEASED UNIT hd QUARTER _4th QUARTER Ad QUARTER 4_th QUARTER Ci *
  • Ar-41 _D1
  • 2.65 E-05 Mn-54 Ci 1.24 E-03 5.25 E-03 C0-58 C1 1.02 E-05 3.52 E-04 Fe-59 Ci
  • 7.03 E-04 Co-60 C1 1.09 E-02 2.53 E-02,_

Zn-65 Ci *

  • Ru-103 *
  • C1_

Sb-122 Ci * *

  • 1.60 E-QZ__

Sb_124 Ji_ *

  • I-135 01 *
  • _

Cs-134 Ci *

  • Cs-137 Ci 1.84 E-03 5.48 E-03 Ba-140 Ci *
  • La-140 Ci
  • 1.11 E-06 Ce-141 Ci *
  • _

Others: Cr-51 Ci

  • 5.71 E-04 Zr-95 Ci
  • 5.70 E-08 Nb-95 Ci
  • 1.47 E-01 (above)

Intal far Period _Ci_ None None 1.40 E-02 1.85 E-Q1__

Xe-133 _C1 I d3_E-0_4__

Xc-135 Ci 9.49 E-06 3.02 E-04

  • See Table for MDL of Each Nuclide Page 10 of 15 0727a

DRESDEN NUCLEAR POWER STATION s;~

, --July Through. Deca =her 1988 IABLE OF MINIMUM DETECIABLE LEVELS Docket Numbers:

FOR LIQUID EFFLUENTS 50-10 50-237-50-249 Radwaste -LIQUID' EFFLUENTS TOTAL GALLONS RELEASED 3.017.130

~

MDL (uCi/mL)  % OF GALLONS < MDL Sr-89 6.0 E-08 83.2 Sr-90 3.1 E-08 83.2 Ar-41 2.71 E-08' 98.3

-Mn-54 5.04-E-08 20.3 Co-58 4.98 E-08 93.5 Fe-59 8.11 E-08 89.7 00-60 1.18 E-07 0 Zn-65 9.97 E-08 100.0 Ru-103 6.04 E-08 100.0 Sb-122 ~ .7.31 E-08 100.0 Sb-124 4.87 E-08 99.3 I-131 5.62 E-08 100.0 I-133 5.34 E-08 100.0 1-135 9.15 E-08 100.0 Cs-134 15.51 E-08 100.0 Cs-137 4.04 E-08 1.7

.Ba-140 2.11 E-07 100.0.

La-140 3.82 E-08 99.3 Ce-141 9.33 E-08 100.0 Xe-133 1.53 E-07 96.9 g Xe-135 5.13 E-08 93.8 Cr-51 4.81 E-07 95.8 Fe-55 4.8 E-07 42.9' Zr-95 Not Determined 99.3 Nb-95' Not Determined 99.3 l

O Page 11 of 15 j 0727a 1 l

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-; .'l. . DRESDEN NUCLEAR POWER STATION

~

EFFLUENT AND WASTE DISPOSAL SEMIt.NNUAL REFORT-

'Julv Through December 19M ,

n LPCI LIQUID EFFLUENTS Docket Numbers: '50-237 50-249-l'.. Number of Batch Releases: '95 .

,.7

2. . Total Time Period:for Batch Releases: 117.80 min L ,

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

b 6.- Average Stream Flow During Periods of

. Release of Effluent into a Flowing Stream: 13,248.5 L/ min I _

CONTINUOUS MQDE- BATCH MODE

NUCLIDES RELEASED UNIT 3rd QUARTER M b QUARTER 3rd QUARTER M h QUARTER.~;

Sr-89 'C1 *

Ci *

  • At-41 Mn-54 Ci 8.52 E-06 1.85 E-08' co-58 Ci _ _ _

Fe-59 Ci *

  • Co-60 Ci- 6.'79 E-05 6.01 E-06 Zn-65 C1' * *

/ Ru-103 Ci *

  • t Sb-122' Cl- *
  • Sb-124- C1 *
  • I-133- C1- *
  • I-135 Ci *
  • Cs-134 'C1 * *

'Cs-137 C1 3.30 E-05 1.63 E-05

%- Ba-140 Ci *

  • Ci *
  • La-140' Ce-141 Ci *
  • L Others: Cr-51 Ci_

Fe-55 Ci *- *-

-Ci *

  • Ci * *

(above) 1 Total For Period Ci None None 1.09 E-04 2.24 E < Xe-133 Ci *

  • Xe-135 C1 * *
  • See Table for MDL of Each Nuclide Page 12 of 15

'0727a

==_--_=___.-_-__-_____--__-_ _ _ _ - _ _ _ _ - - - - - - _ _ _ - _ - _

DRESDEN NUCLEAR POWER STATION l

'. 1 e Julv Through Dec==her 1988 f TABLE OF MINIMUM DETECTABLE LEVELS Docket Num'bers' FOR LIQUID EFFLUENTS- 50-237 {

50-249 i i

LPCI- LIQUID EFFLUENTS TOTAL GALLONS RELEASED 412.300 tFjj (uci/mL)  % OF GALLONS < MDL Sr-89 6.0 E-08 100.0 4

Sr-90 3.1 E-08 100.0 Ar-41 2.71 E 100.0 Mn-54 5.04 E-08 78.1 Co-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 Sb-122 7.31 E-08 100.0 Sb-124- 4.87 E-08 100.0 I-131 5.62 E-08 100.0-

'I-133 5.34 E-08 100.0 1-135 9.15 E-08 100.0 Cs-134 5.51 E-08 100.0 Cs-137 4.04 E-08 0 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 4.8 E-07 100.0 l

l Page 13 of 15 l l

0727a L.. ..

.DRESDEN NUCLEAR POWER. STATION

, , . EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Julv Through December -1988 Docket Numbers:

50-10 1 SOLID WASTE AND' IRRADIATED FUEL SHIPMENTS 50-237  !

50-249 I A. SOLID WASTE SHIPPED OFFSITE FOR- BURIAL OR DISPOSAL (NOT IRRAD::ATED FUIL)

1. Type of Waste- Unit 6-month period
a. ' Spent. resins, filter sludges, evaporator bottoms, etc.
  • Ci 6.12 E02 m2 1.04 E03
b. Dry compressibic waste, contaminated equip., etc.

Ci 1.97 E02 m3 . 6 E00 -l

c. Irradiated components, control rods, etc.

C1 2.00 E-01

d. Other (describe)

Ci 0 l

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

% ci

a. Co-60 74.5 % 4.56 E02 Fe-55 12.4 % 7.59 E01_

Mn-54 9.8 % 6.00 E01 Cs-137 0.7 % 4.28 E00 Other 2.6  % 1.59 E01

b. Co-60 24.4  % 4.81 E01 Fe-55 71.3  % 1.40 E02 Mn-54 2.8 1 5.52 E0D_

Cs-137 1.4  % 2.76 E00 Other 0.2 % 3.94 E-01

c. Co-60 29.41 %' 5.88 E-02 Fe-55 67.95 % 1.36 E-01 Mn-54 2.64 % 5.28 E-03
d.  %
3. Solid Waste Disposition NUtiBER OF SilIPMENTS MODE OF TRANSPORTATION DESIINAIl0N 4

2 Motor freight (exclusive use only) Westinghouse DDR 57 Motor freight (exclusive use only) Barnwell, SC 4 Motor freight (exclusive use only) Richland, WA 9 Motor freight (exclusive use only) SEG 1 Motor freight (exclusive use only) Alaron 3 Motor freight (exclusive use only) CNSI B. IRRADIATED FUEL SHIPMENTS (Disposition) l NUMBER OF SHIIMENIS MODE OF TRANSPORTATION DESTINAIIDN None Page 14 of 15

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y,- ,

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Julv Through Deca =her -1988 Docket Numbers:  :

50-10 -i ABNORMAL RELEASES 50-237- j 50-249- 1 A.,' LIQUID = i 1.: Number'of Releases: None _

1

.2. To'tal Activity Released: None B. CASE 0US-

'l. Number of Releases: None

2. - Total Activity' Released: None 15 of 15 l

l 1

l

'0727a m m. _ _ _ _ _

A Commonwealth Edison

  • 1 Q Dresden Nuclear Power Station v R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 February 6, 1989 EDE IlfR: #89-111 U.S. Nuclear Regulatory Commission Doctment Control Deck Washington, DC 20555

Subject:

Dresden Nuclear Power Station Operating Report NRC Dockrts 50-10. 50-237. 50-249 To Whom It May Concern:

Enclosed is the radioactive effluent report for July through December 1988 for Dresden Nuclear Power Station.

A copy of this report will be furnished to be NRC Resident Inspector.

Sincerely Yours,

.h l E. D. Eenigenburg z ln/V)

/

Station Manager g

  • Dresden Nuclear Power Station EDE:JW:rg Enclosure cc: J. Wallace J.C. Golden File /NRC File / Numerical 0727a y,

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