ML20235U304

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Corrected Effluent & Waste Disposal Semiannual Rept for Jan-June 1988
ML20235U304
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 06/30/1988
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20235U308 List:
References
NUDOCS 8903090138
Download: ML20235U304 (15)
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Text

f r .

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

_.. 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(L1) spectrometry system. Tritium is collected via a continuous sample on the D-2/3 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 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.

1 Page 1 of M hO R

1981a

DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT.

_lanuary__ Through June 19ES GASE0US EFFLUENTS SITdMATION OF ALL RELEASES Docket Numbers: 50-10 50-237 50-249 UNIT isi QUARTER 2nd QUARTER.

~A. FISSION AND ACTIVATION GASES

1. Total Release Ci 8.33 E01- 5.00 E91-
2. Average Release Rate for Period uCi/ cec 1.06 E01- 6.36 E00
3. Percent of Technical Specification Limit  % * '*

B. IODINES

1. Total Iodine-131 Ci 1.40 E-01 9.16 E-03
2. Average Release Rate for Period uCi/sec 1.78 E-02 1.17 E-03
3. Percent of Technical Specific:rtion Limit  % *
  • l j

C. PARTICUIATES

1. Particulate with half-lives > 8 days Ci 1.23 E-02 3.01 E-02
2. Average Release Rate for Period uCi/sec 1.56 E-03 3.83E-U
3. Percent of Technical Specification Limit  % * *
4. Gross Alpha Radioactivity Ci 2.20 E-10 <MDL D. TRITIUM
1. Total Release Ci 9.82 E00 3.04 E00
2. Average Release Rate for Period uCi/see 1.25 E00 3.87 E-01
3. Percent of Technical Specification Limit  % * *
  • Will be included in the Annual Report on Environmental Radioactivity Data Page 2 of 15 1981a

DRESDEN NUCLEAR POWER STATION

. . EFFLUENT AND WASTE DISPOSAL ~ SEMIANNUAL REPORT January Through- June 1918

(

4 D1 Chimnev GASE0US EFFJ.UENTS GROUND LEVEL RELEASES Docket Number 50-10 SEMI-ELEVATED RELEASES xx ELEVATED RELEASES CONIIWQUS MODE BATCH MODE NUCLIDES RELEASED UNIT lit QUARTER 2nd QUARTER lat QUARTER 2nd QUARTER FISSION GASES C1 Xe-138 C1 *

  • Xe-135m C1 -
  • f.

Kr Ci *

  • Kr-88 _Ci_ *
  • Kr-85m C1
  • _

_ Kr-85' C1 *

  • Xe-135 Ci
  • _

Xe-133 C1- *

  • Others:Xe-133m C1 *
  • Ci TOTAL Ci *
  • None None 10 DINES I-131 Cl- *
  • I-133 Ci *
  • I-135 C1 *
  • TOTAL C1 *
  • None None PARTICULATE Sr-89 C1 *
  • Cr-51 C1 *
  • fin-54 Ci_ * *~

Co-58 C1 *

  • Ci *
  • Fe-59 Co-60 Ci 6.68 E-06 3.07 E-06 Zr-95 Ci *
  • C1 *
  • Nb-95 Ru-103 01 *
  • Ag-110m Ci *
  • Sb-124 C1 *
  • Cs-134 Ci
  • 3.29 E-07 ___

Cs-136 Ci * * .

Cs-137 C1 3.90 E-06 2.81 E-05 Ci *

  • Ba-140-

-Ce-Ili Ci * *  !

t Ce-144 Ci *

  • Zn-65 Ci *
  • Ba-133 Ci * * .

Ci *

  • Eb-125 Others: Mo-99 Ci *
  • La-140 Ci *
  • C1 t C1 Ci TQIAL Ci 1.06 E-05 3.15 E-05 None None
  • See Table for MDL of Each Nuclide Page 3 of 15 1981a

DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January Through June 1988 Docket Number 50-10 TABLE OF MINIMUM DETECTABLE LEVELS FOR GASEOUS EFFLUENTS D1 Chimney GASEOUS EFFLUENTS AVERAGE FLOW 50.000 cfm MHL (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-08 100.0 Xe-133 4.32 E-08 100.0 Others:
2. 10 DINES I-131 5.34 E-14 100.0 I-133 5.57 E-14 100.0 I-135 1.19 E-13 100.0
3. PARTICULATE Sr-89 2.5 E-14 100.0 Sr-90 1.5 E-14 100.0 Cr-51 4.20 E-13 100.0 Mn-54 5.27 E-14 100.0 Co-58 4.83 E-14 100.0 Fe-59 7.58 E-14 100.0 Co-60 1.26 E-13 18.7 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 1-131 5.15 E-14 100.0 Cs-134 5.73 E-14 92.6 Cs-136 5.49 E-14 100.0 Cs-137 6.21 E-14 7.7 Ba-140 1.91 E-13 100.0 Ce-141 7.64 E-14 100.0 Ce-144 3.27 E-13 100.0 Zn-65 9.03 E-14 100.0 Ba-133 6.93 E-14 100.0 Sb-125 1.39 E-13 100.0 Others:

Page 4 of 15 1981a

DRESDEN NUCLEAR POWER STATION

'. EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January Through June 1988 D2/3 Chimnev GASEOUS EFFLUENTS GROU'ID LEVEL RELEASES Docket Numbers: 50-237 SEMI-ELEVATED RELEASES 50-249 j xx ELEVATED RELEASES CONTINU0US MODE BATCH MODE NUCLIDES RELEASED UNIT ist QUARTER 2nd QUARTER lat QUARTER 2nd QUARTER

___f1SSION GASES Ci Xe-138 C1 2.09 E01

  • Xe-135m Ci 5.80 E00
  • Kr-87 Ci
  • 8.59 E-06 Kr-88 C1
  • 1.64 E00 Kr-85m Ci
  • 8.64 E-01 Kr-85 Ci 6.60 E-03 1.59 E-03 Ke-135 Ci_ 3.87 E01 1.38 E01 Xe-133 Ci 1.11 E01 4.23 E00 Others: Ci Ci TOTAL Ci 7.65 E01 2.05 E01 None None IODINES I-131 Ci 3.25 E-03 4.99 E-04 I-133 Ci 1.16 E-02 2.93 E-03 I-135 Ci 2.31 E-02 5.47 E-03 TOTAL _Ci_ 3.80 E-02 8.90 E-03 None None ARTICULATES Sr-89 C1 1.22 E-07 2.25 E-05

_Sr-90 Ci 6.82 E-10 3.14 E-07 Cr-51 Ci *

  • Ma-54 C1 2.62 E-05 2.21 E-05 Co-58 Ci *
  • Fe-59 Ci *
  • Co-60 Ci 4.51 E-04 1.13 E-04 Zr-95 C1 *
  • Nb-95 Ci *
  • Ru-103 Ci *
  • Ag-110m Ci *
  • Sb-124 Ci *
  • I-131 Ci 8.04 E-04 2.81 E-02 Cs-134 Ci *
  • Cs-136 Ci *
  • Cs-137 Ci 7.95 E-05 5.48 E-05 Ba-140 Ci 2.89 E-03 3.13 E-04 Ce-141 C1 3.09 E-06 4.20 E-05 Ce-144 C1 *
  • Zn-65 Ci *
  • Ba-133 Ci *
  • Sb-125 Ci *
  • Dibers: Mo-99 C1 La-140 Ci *
  • _Ci_

Ci

_Ci TOTAL Ci 4.25 E-03 2.87 E-02 None None

  • See Table for MDL of Each Nuclide Page 5 of 15

7 .,

7. ,

DRESDEN NUCLEAR POWER STATION

,7

  • -G' l
  • Dockst Numbsrst y ,

g 4: :50-237z L50-249:

~

TABLE OF MINIMUM DETECTABLE LEVELSi FOR GASEOUS EFFLUENTS AVERAGE FLOW _.11t_qtt_.2&3__ Kcfm-

-D2/3 Chimney GASEOUS EFFLUENTS 2nd qtr 305 Kcfm 1MDL (uCi/ce) 1'0F TIME < MDL

1. FISSION GASES' Xe 1381 4.16 E-08 92.3 Xe-135m 1.29 E-07 96.7 Kr-87 3.03 E-08 99.5-Kr-88 5.21 E-08 99.5'
Kr-85m 1.78 E-08 99.5 Kr-85 4.43 E-06 0.0 Xe-135- 1.52 E-08 50.0.

Xe-133 4.32 E-08 95.1

_Others:

2. . IODINES, i

I-131 5.34 E-14 0.0

'I-133 5.57 E-14 38.5 I-135 1.19 E-13 33.5 3;. PARTICULATE.

Sr-89 2.5 E-14 0.0

.Sr-90. 1.5 E-14 .33.5

.Cr-51 4.20 E-13 100.0.

Mn-54 5.27'E-14 35.2.

Co-58 4.83 E-14 100.0 Fe 7.58 E-14 100.0 Co-60 1.26 E-13 3.9 2r-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 17.6 Cs-134 5.73 E-14 100.0 Cs-136 5.49 E-14 100.0 Cs-137 6.21 E-14 52.7 Ba-140 1.91 E-13 9.3 Ce-141 7.64 E-14 94.0 Ce-144 3.27 E-13 100.0 Zn-65 9.03 E-14 100.0 Ba-133 6.93 E-14 100.0 Sb-125 1.39 E-13 100.0 <

Others:

Page 6 of 15 i 1981a

DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 4

_ January Through June 19BB D2/3 Vent GASE0US EFFLUENTS GROUND LEVEL RELEASES Docket Numbers: 50-237 xx SEMI-ELEVATED RELEASES 50-249 ELEVATED RELEASES CONTINUOUS MODE BATCH MODE UCLIDES RELEASED UNIT lal QUARTER 2nd QUARTER lat QUARTER 2nd QUARTER EISSION GASES Ci Xe-138 Ci *

  • Xe-135m Ci *
  • Kr-87 Ci *
  • Kr-88 C1 Kr-85m Ci *
  • Xe:135 Ci 6.75 E00 2.24 E01 Xe-133 Ci
  • 7.14 E00 Rih.ers: Ci *
  • Ci IQIAL C1 6.75 E00 2.95 E01 None None 10 DINES I:1.31 Ci 7.39 E-02 6.67 E-05 I-133 Ci 9.66 E-03 1.91 E-04 I-135 Ci 1.87 E-02 1.33 E-06 IQIAL C1 1.02 E-01 2.59 E-04 None None ARTICULATES Sr-89 Ci 1.40 E-08 2.56 E-06 Sr-90 Ci 1.29 E-10 1.15 E-06 Cr-51 C1 7.17 E-04 7.20 E-06 Mn-54 C1 2.69 E-04 2.07 E-04 Cn-58 Ci 2.81 E-04 2.65 E-05 Fe-59 C1 5.29 E-05 3.72 E-05 Co-60 C1 2.27 E-03 1.06 E-03 Er-95 Ci 7.80 E-05
  • Nb-95 Ci *
  • Ru-103 _ci
  • An-110m C1 1.57 E-05 1.19 E-06 Eb-124 C1 1.30 E-06
  • I-131 Ci 3.47 E-05 2.35 E-06

.Ca-134 _Ci_

Gs-136 Ci 5.58 E-06

  • qa 137 Ci 7.36 E-06 2.45 E-05 Ba 140 Ci 4.68 E-04
  • Ci *
  • Ce:141 Ce-144 Ci
  • 3.14 E-06 Zn 65 C1 1.40 E-04 4.76 E-06 Ra-133 _f1_
  • Ci *
  • Eb-125 Qthers: C1 Me:99 Ci 3.66 E-03
  • Ci IOTAL C1 8.00 E-03 1.38 E-03 None None
  • See Table for MDL of Each Nuclide Page 7 of 15

DRESDEN NUCLEAR POWER STATION, ,

' January

[ , .

Through June 1988 Dockat Numbaro:- )

L' 50-237 j TABLE OF MINIMUM DETECTABLE LEVELS- 50-240 FOR GASEOUS EFFLUENTS

[. '

l -D2: 11 0 Kcfm.

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 L

Xe-135m 1.29 E-07 100 Kr 3.03 E-08 100 Kr-88' 5.21 E-08 100 Kr-85m 1.78 E-08 100 Kr-85 4.43 E-06 100 Xe-135 1.52 E-08 50.5 Xe-133 4.32 E-08 96.2 Others:

2. . IODINES I-131 5.34 E-14 3.9 I-133 5.57 E-14 17.5 I-135 1.19 E-14 40.4
3. PARTICULATE Sr-89 2.5 E-14 16.9 Sr-90 1.5 E-14 50.8.

Cr-51' 4.20 E-13 33.9 Mn-54 5.27 E-14 0.0 Co-58 4.83 E-14 7.1 Fe-59 7.58 E-14 9.3 Co-60 1.26 E-13 0.0 Zr-95 9.09 E-14 96.2 Nb-95 4.96 E-14 100.0 Ru-103 4.95 E-14 100.0 Ag-110m 5.12 E-14 61.7 Sb-124' 5.86 E-14 95.6 I-131 5.15 E-14 34.6 Cs-134 5.73 E-14 100.0 Cs-136 5.49 E-14 88.5 Cs-137 6.21 E-14 34.4 Ba-140 1.91 E-13 50.0 Ce-141 7.64 E-14 100.0 Ce-144' 3.27 E-13 96.2 Zn-65 9.03 E-14 54.1 Ba-133 6.93 E-14 100.0 Sb-125 1.39 E-13 100.0 Others: Mo-99 3.95 E-13 50.8 Page 8 of 15 1981a l

DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Januarv~ Through June 1988 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES Docket Numbers: 50-10 50-237 50-249 UNIT 111 QUARTER 2nd QUARTER-A. FISSION AND ACTIVATION PRODUCTS

1. Total Release (not incl. tritium, gases, alpha) Ci '7.78 E-03 5.23 E-02
2. Average Diluted-Conc. During Period uCi/mL -6.54 E-08 6.70 E-07

.3., Percent of Applicable Limit  % *

1. Total Release C1 2.62 E00 8.81 E00
2. Average Diluted Conc. During Period uCi/mL. 2.20 E-05 1.13 E-04
3. Percent of Applicable Limit  % * -*

C. DISS01VED A D ENTRAINED GASES'

1. Total Release ci 3.02 E-04 2.05 E-04
2. Average Diluted Conc. During Period uCi/mL 2.54 E-09 2.62 E-09
3. Percent of Applicable Limit  %' *
  • D. CROSS ALPHA RADIOACTIVITY
1. Total Release Ci <MDL <MDL

. E. VOLUME OF WASTE RELEASED (prior to dilution) liters 3.42 E06 1.38 E07 F. VOLUME OF DILUTION WATER USED DURING PERIOD liters 1.16 E08 6.43 E07

  • Will be included in the Annual Report on Environmental Radioactivity Data Page 9 of 15 1981a

4 ' DRESDEN NUCLEAR POWER STATION F EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Januarv Through June 1918 1

L .a Radwaste LIQUID EFFLUENTS Docket Numbers: 50-10 50-237

1. Number of Batch Releases: 183 50-249
2. Total Time Period for Batch Releases:.58,633 min.
3. Maximum Time Period for a Batch Release: 447 min
4. Average Time. Period for Batch Releases: 320 min
5. Minimum Time Period for a Batch Release: 11 min
6. . Average Stream Flow During Periods of Release of Effluent into a Flowing Stream: 8.57 E04 L/ min.

CONIIEU.0UE_ MODE BATCH MODE NUCLIDES RELEASED UNIT in QUARTER 2nd QUARTER in QUARTER 2nd QUARTER Sr-89 Ci *

  • 1.71 E-04 Ar-41 C1 *
  • Mn-54 Ci 3.00 E-04 5.13 E-03 Co-53 _01 Fe-59 Ci
  • 7.20 E-05 Co-60 C1 4.72 E-03 3.79 E-02 Zn-65 Ci *
  • Ru-103 Ci *
  • Sb-122 Ci *
  • Sb-124 Ci_ *
  • I-133 C1 *
  • I-135 Ci *
  • Cs-134 Ci *
  • Cs-137 Ci 2.56 E-03 5.99 E-03 Ba-140 Ci *
  • La-140 ,_Ci *
  • Ce-141 Ci *
  • 2.51 E-03 Cr-51 1. 0 9 E-Ol i _

Ci_

Cs-138 C1 3.38 E-04 C1 (above)

Io_tal For Period Ci None None 7.71 E-03 5.21 E-02 Xe-133 C1 1.79 E-04 1.36 E-04 Xe-135 Ci 1.23 E-04 6.89 E-05

  • See Table for MDL cf Each Nuclide Page 10 of 15 i

1981a L_________

m DRESDEN NUCLEAR POWER SIATION:

_ January Through' June 1988' 1

TABLE OF MINIMUM DETECIABLE LEVELS Docket Numbers:

FOR LIQUID EFFLUENTS 10 50-237 50-249

'Radwaste LIQUID EFFLUENTS TOTAL GALLONS RELEASED 4.145.460 MDL (uC1/mL)  % OF GALLONS < MDL Sr-89' 8.3 E-08 100.0 Sr-90 2.4 E-08 75.7 Ar-41 2.71 E-08 100.0 Mn-54 5.04 E-08 18.9 Co-58 4.98 E-08 100.0 Fe-59 8.11 E-08 99.0 Co-60 1.18 E-07 0.0 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 99.5 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 2.2 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 91.5 Xe-135 5.13 E-08 89.1 Cr-51 4.81 E-07 99.3 Fe-55 3.1 E-07 83.0 Page 11 of 15 1981a

. DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Januarv Through June 19B3 LPCI LIQUID EFFLUENTS Docket Numbers: 50-237 50-249

1. Number of Batch Releases: 97
2. Total Time Period for Batch Releases: 120.3 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: 1.32 E04 L/ min CONIJHUQUEJQDE BAIC1LMQDE NUCLIDES RELEASED UNIT lai QUARTER 2nd QUARTER 131 QUARTER 2nd QUARTER Sr-89 C1 2.10 E-06
  • Ar-41 . ._Ci_

Ma-54 _Ci 9.81 E-07 1.50 E-05 Co-58 Ci *

  • Fe-59 Ci *
  • Co-60 Ci 6.10 E-05 1.48 E-04 Zn-65 Ci *
  • Ru-1D3 Ci *
  • Sb-122 C1 *
  • Sb-124 _Hi_

I-131 Ci *

  • I-133 C1 *
  • I-135 Ci *
  • Cs-114 Ci *
  • Cs-137 Ci 9.77 E-06 2.13 E-05 Ba-140 Ci *
  • Ci *
  • La-160 Ce-141 Ci *
  • Others: Cr-51_ _Qi Fe-55 C1 *
  • 11-Ci (above)

Iolal_For Perioi _ _Ci None None 7.42 E-05 . . .

1. ELE-0.4__

Xe-133 Ci *

  • Ci *
  • Xe-135
  • See Table for MDL of Each Nuclide Page 12 of 15 1981a

DRESDEN NUCLEAR POWER SIATION January Through- June 19RB TABLE OF MINIMUM DETECTABLE LEVELS Docket Numbers:

l FOR LIQUID EFFLUENTS 50-237 50-249, LPCI LIQUID EFFLUENTS TOTAL GALLONS RELEASED 4.21 EOS MDL-(uCi/mL)- 1 0F GALLONS < MDL Sr-89' 7.9 E-08 95.9 Sr-90 2.7 E-08 95.9 Ar-41 2.71 E-08 100.0 Mn-54 5.04 E-08 63.9 Co 4.98 E-08 100.0 Fe-59 8.11 E-08 100.0 Co-60 1.18 E-07 14.4 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 -+.

1-131 -5.62 E-08 100.0 I-133 5.34 E-08 100.0 I-135 9.15 E-08 100.0 Cs-134 5.51 E-08 100.0 Cs-137 4.04 E-08 40.2 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 Page 13 of 15 1981a

DRESDEN NUCLEAR POWER STATICN EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January Through June 19BB Docket Numbers:

50-10 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 50-237 50-249 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISf0 SAL (NOT IRRAD::ATED FUEL)

1. Type of Waste Unit 6-month period m 06.4
a. Spent resins, filter sludges, evaporator bottoms, etc.

Ci 7.18 E02 m .6

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

Ci 1.09 E01

c. Irradiated components, control rods, etc. -

Ci 1.86 E00

d. Other (describs)

Ci

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

% ci

a. Co-60 74.5 % 5.35 E02 Fe-55 12.4 % 8.90 E01 Mn-54 9.8 % 7.04 E01 Cs-137 0. 7 % 5.03 E00 Other 2.6  % 1.87 E01
b. Co-60 24.4 % 2.66 E0Q_

Fe-55 71.3 % 7.77 EOD_

Mn-54 2.8 % 3 93_E-Q1 Cs-137 1.4 % 1.53 E-QL Other 0.2 % 2.18 E-02

c. Co-60 29.41 % 5.47 E-01 Fe-55 67.95 % _L2ftEQQ_

Mn-54 2.64 % 4.91 E-02

d.  %
3. Solid Waste Disposition NUMBER OF SHIPMENIS MODE OF TI%NSEQRIATION DESIINAIIDN 1 Motor freight (exclusive use only) Chem-Nuclear, IL 42 Motor freight (exclusive use only) Barnwell, SC ]

Motor freight (exclusive use only) 16 SEG, TN 1 Motor freight (exclusive use only) Quadrex, TN j 2 Motor freight (exclusive use only) Westinghouse-DRR, PA B. IRRADIATED FUEL SHIPMENTS (Disposition)

UUMBER OF SHIPMENIS MODE OF TRANSPORTATION DESTINILIl0B 1 Motor freight (exclusive use only) Barnwell, SC Page 14 of 15 1981a

F ]

-]

a: , ; ...

> i i

DRESDEN NUCLEAR POWER STATION ~!

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

[j '._ January .Through June 1918 Docket Numbers:

50-10 ABNORMAL RELEASES 50-237 50-249 A. LIQUID

1. Number of Releases: Nons
2. Total Activity Released: None

'B. GASEOUS

1. Number of Releases: None
2. Total ~ Activity Released: None 15 of 15 I

1981a E1_______________ _ _ _ . _ _ _ _ _ . _ . _ _

_j

t *

  • Commonwealth Edison Dresden Nucicer Power Station R R #1 Morris, litanois 60450 Telephone 815/942-2920 February 13, 1989 EDE LTR: #89-139 U.S.' Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Subject:

Dresden Nuclear Power Station Units 1, 2, and 3 Corrected Operating Report NRC Dockets 50-10. 50-237. 50-249 To Whom it May Concern:

Enclosed is the corrected radioactive effluent report for January through June 1988 for Dresden Nuclear Power Station as outlined in the November 1986 Federal Regirter. The final data for Sr89 Sr90, Fe55, Tritium and gross alpha have been included in the report.

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

Sincerely Yours, b .M E. D. Eenige urg Station Manager Dresden Nuclear Power Station EDE:JW:ade Enclosure cc: J. Wallace J. C. Golden File /NRC File / Numerical 4 f Y ~~ f

~

1981a

?' .

DRESDEN NUCLEAR F0WER STATION DOCKET NOS. 50-10, 50 .237, 50-249 MEASUREMENTS AND AFFROXIMATIONS 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 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 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 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.

Page 1 of 15 i l 1981a

_ YD

[-

DRESDEN NUCLEAR POWER STAT 1014 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT -

_JanuarJ_._ Through E June._ _ ~ 198.8 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES Docket Numbers: 50-10 50-237 50-249 UNIT lit QUARTER 2nd QUARTER 1

A. FISS10N AND ACTIVATION GASES _

< 1. Total Release- Ci 8.33 E01 5.00 E01

'2. Average Release Rate _for Period uCi/see 1.06 E01 6.36 E00

3. Percent of. Technical Specification Limit  % *
  • i B. 10 DINES
1. Total Iodine-131 Ci 1.40 E-01 9.16 E-03
2. Average Release Rate for Period uCi/sec 1.78 E-02 1.17 E-03
3. Percent of Technical Specification Limit  % * -*

C. PARTICUIATES

1. Particulate with half-lives > 8 days 'Ci 1.23 E-02 3.01 E-02
2. Average Release Rate for Period uCi/sec 1.56 E-03 3.83 E-03
3. -Percent of Technical Specification Limit  % * *
4. Gross Alpha Radioactivity Ci 2.20 E-10 <MDL-L__IRIIlUM
1. Total Release Ci 9.82 E00 3.04 E00
2. Average Release Rate for Period uCi/see 1.25 E00 3.87 E-01
3. Percent of Technical Specification Limit  % * *
  • Will be included in the Annual Report on Environmental Radioactivity Data l 1

l Page 2 of 15 ]

1981a

DRESDEN NUCLEAR POWER STATION-

. EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

_Jang ry Through June 1983 D1 Chimnev GASEOUS EFFLUENTS GROUND LEVEL RELEASES Docket Number 50-10 SEMI-ELEVATED RELEASES xx ELEVATED RELEASES CONIIEUDUS MODE BAICR 210SE NUCLIDES RELEASED UNIT 111 QUARTER 2nd QUARTER 131 QUARTER 2nd QUARTER FISSION CASES Ci Xe-138 Ci *

  • Xe-135m Ci *
  • Kr-87 Ci * *

.l Kr-88 JL *

  • Kr-85to ci *
  • Xe-135 Ci *
  • Xe-133 C1 *
  • Others:Xe-133m C1 *
  • _Di TOTAL Ci *
  • None None IDDINES I-131 Ci *
  • I-133 C1 *
  • I-135 Ci *
  • TOTAL Ci *
  • None None PARTICULATE Sr-89 Ci *
  • Cr-51 Ci *
  • MD-54 Ci *
  • Co-58 C1 *
  • Fe-59 Ci *
  • Co-60 C1 6.68 E-06 3.07 E-06 Zr-95 Ci *
  • Nb-95 _Ci _

Ru-103 Ci *

  • Ag-110m Ci *
  • Sb-124 C1 _

I-131 Ci *

  • Cs-134 Ci
  • 3.29 E-07 Cs-136 C1 *
  • Cs-137 C1 3.90 E-06 2.81 E-05 Ba-140 Ci *
  • Ce-141 _Ci Ce-144 Ci *
  • Zn-65 Ci *
  • Ba-133 Ci *
  • Sb-125 Ci *
  • Ci *
  • La_141 C1 Ci Ci _

TOTAL C1 1.06 E-05 3.15 E-05 None None

  • See Table for MDL of Each Nuclide Page 3 of 15 1981a

. DRESDEN NUCLEAR POWER STATION

..' EFFLUENT AND WASTU DISPOSAL SEMIANNUAL REPORT-January Through June- 19ES Docket Number 50-10 TABLE OF MINIMUM DETECIABLE LEVELS FOR CASE 0US EFFLUENTS.

D1 Chimnev _ GASEOUS EFFLUENTS AVERAGE FLOW 50.000 cfm NHL (uC1/cc)  % OF TIME'< MDL

1. FISSION GASES Xe-138 4.16 E-08 100.0 Xe-135m 1.29 L-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 Others:
2. 10 DINES I-131 5.34 E-14 100.0 I-133 5.57 E-14 100.0 I-135 1.19 E-13 100.0
3. . PARTICULATE Sr-89 2.5 E-14 100.0 Sr-90~ 1.5 E-14 100.0 Cr-51 4.20 E-13 100.0 Mn-54 5.27 E-14 100.0 Co-58 4.83 E-14 100.0 Fe-59 7.58 E-14 100.0

, Co-60 1.26 E-13 18.7 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 1-131 5.15 E-14 100.0 Cs-134 5.73 E-14 92.6 Cs-136 5.49 E-14 100.0 Cs-137 6.21 E-14 7.7 Ba-140 1.91 E-13 100.0 Ce-141 7.64 E-14 100.0 Ce-144 3.27 E-13 100.0 Zn-65 9.03 E-14 100.0 Ba-133 6.93 E-14 100.0 Sb-125 1.39 E-13 100.0 Others:

Page 4 of 15 1981a

I

~

DRESDEN-NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMTANNUAL REPORT Janeary.__ Through June 19EB D2/3 Chimney GASEOUS EFFLUENTS l

GROUND LEVEL EELEASES Docket Numbers: 50-237 )

SEMI-ELEVATED RELEASES 50-249 l I

xx ELEVATED RELEASES CQNTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT 111 QUARTER 2nd QUARTER 111 QUARTER 2nd QUARTER flSSION GASES Ci Xe-138 C1 2.09 E01

  • q Xe-135m Ci 5.80 E00
  • Kr-87 Ci
  • 8.59 E-06 Kr-88 Ci
  • 1.64 E00 Kr-85m Ci
  • 8.64 E-01 Kr-85 Ci 6.60 E-03 1.59 E-03 Xe:135 C1 3.87 E01 lo38 E01 Xe-133 C1 1.11 E01 4.23 E00 Others: C1 Ci TQIAL _fi_ 7.65 E01 2.05 E01 None None 10 DINES I-131 Ci 3.25 E-03 4.99 E-04 I-133 Ci 1.16 E-02 2.93 E-03 I-135 Ci ___2.31 E-02 5.47 E-03 T.QIAL Ci 3.80 E-02 8.90 E-03 None None PARTICULATE Sr-89 C1 1.22 E-07 2.25 E-05 Sr-90 Ci 6.82 E-10 3.14 E-07 _

Cr-51 C1 *

  • Mn-54 C1 2.62 E-05 2.21 E-05 Co-58 Ci *
  • Fe-59 Ci *
  • Co-60 Ci 4.51 E-04 1.13 E-04 Zr-95 C1 *
  • Nb-95 Ci *
  • Ru-103 Ci *
  • Ag-110m Ci *
  • Sb-124 Ci *
  • I-131 Ci 8.04 E-04 2.81 E-02 Cs-134 Ci *
  • Cs-136 Ci *
  • Cs-137 Ci 7.95 E-05 5.48 E-05 Ba-140 C1 2.89 E-03 3.13 E-04 Cc-141 Ci 3.09 E-06 4.20 E-05

_ _ _fe-144 Ci *

  • Zn-65_ Ci *
  • Ba-133 *
  • _fi Sb-125 Ci *
  • La-140 Ci *
  • Ci.

C1 Ci TOTAL C1 4.25 E-03 2.87 E-02 None None

  • See Table for MDL of Each Nuclide Page 5 of 15

______m._.

1

. DRESDEN NUCLEAR POWER STATION Dockat Numbars: )

50-237 TABLE OF MINIMUM DETECTABLE LEVELS 50-249 FOR GASEOUS EFFLUENTS i

_1.s.t_qtt_283__ Kcfm D2/3 Citimney GASEOUS EFFLUENTS AVERAGE FLOW 2nd qtr 305 'Kcfm

.MDL (uCi/cc)  % OF TIME: ( MDL

1. FISSION GASES Xe-138 '4.16 E 92.3.

Xe-135m 1.29 E-07 96.7

-Kr-87 3.03 E-08 99.5 Kr 5.21 E 99.5 Kr-85m 1.78 E-08 99.5 Kr 4.43 E 0.0 Xe-135~ 1.52 E-08 50.0 Xe-133 4.32 E-08 95.1 Others:

~2.- 10 DINES I-131 5.34 E-14 0.0 I-133 5.57 E-14 38.5 I-135 1.19 E-13 33.5

3. PARTICULATE Sr-89 2.5 E-16 0.0 Sr-90 1.5 E-14 33.5 Cr-51 4.20 E-13 100.0 Mn-54 5.27 E-14. 35.2 Co-58 4.83 E-14 100.0-Fe-59 7.58 E-14 100.0 Co-60. 1.26 E-13 3.9

.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 17.6 Cs-134 5.73 E-14 100.0 Cs-136 5.49 E-14 100.0 Cs-137 6.21 E-14 52.7 Ba-140 1.91 E-13 9.3 Ce-141 7.64 E-14 94.0 Ce-144 3.27 E-13 100.0 Zn-65 9.03 E-14 100.0 Ba-133 6.93 E-14 100.0 Sb-125 1.39 E-13 100.0 Others:

Page 6 of 15 l

1981a

, DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE' DISPOSAL SEMIANNUAL REPORT

. January Through June 1983 D2/3 Vent GASEOUS EFFLUENTS GROUND LEVEL RELEASES Docket Numbers: 50-237 xx SEMI-ELEVATED RELEASES 50-249 ELEVATED RELEASES CONTINUOUS MQDE BATCH MODE NUCLIDES RELEASED UNIT lal QUARTER 2nd QUARTER ini QUARTER 2nd QUARTER EIESION GASES Ci Xe-138 Ci *

  • Xe-135m Ci *
  • Kr-87 C1 *
  • Kr-88 Ci *
  • Kr-85m Ci *
  • Ke-135 _Ci_ 6.75 E00 1 24 E01 Xe-133 C1
  • 7.14 E00 Rthers: Ci *
  • C1 TQIAL Ci 6.75 E00 2.95 E01 None None J0 DINES I:131 Ci 7.39 E-02 6.67 E-05 I-133 Ci 9.66 E-03 1.91 E-04 I-135 Ci 1.87-E-02 1.33 E-06 10lbL C1 1.02 E-01 2.59 E-04 None None ARTICULATES Sr-89 C1 1.40 E-08 2.56 E-06 Sr-90 Ci 1.29 E-10 1.15 E-06 Cr-51 Ci 7.17 E-04 7.20 E-06 Mn-54 Ci 2.69 E-04 2.07 E-04 Co-58 Ci 2.81 E-04 2.65 E-05 Fe-59 Ci 5.29 E-05 3.72 E-05 Co-60 C1 2.27 E-03 1.06 E-03 Zr-95 Ci 7.80 E-05
  • Nb-95 Ci *
  • Ru-103 Ci *
  • Ar-110m Ci 1.57 E-05 1.19 E-06 Sb-124 Ci 1.30 E-06
  • I-131 C1 3.47 E-05 2.35 E-06 Carl 14 _.Ci_ *
  • Cs-136 Ci 5.58 E-Oo
  • C.E.-13 7 Ci 7.36 E-06 2.45 E-05 Ra 140 C1 4.68 E-04
  • Ce-141 C1 * * ,

Ce-144 C1

  • 3.14 E-06 2n-65 C1 1.40 E-04 4.76 E-06 _ _.(( __

Ba-133 Ci *

  • Sb-125 Ci *
  • Others: Ci  !

Mo 99 Ci 3.66 E-03

  • Ci TOTAL C1 8.00 E-03 1.38 E-03 None None
  • See Table for MDL of Each Nuclide Page 7 of 15

- - - - _ - - - - _-. -- J

DRESDEN NUCLEAR POWER STATION January Through June ___'1988 Dockat Numbers:

L. 237 l'

TABLE OF MINIMUM DETECTABLE LEVELS 50-240 l FOR GASEOUS EFFLUENTS 1

I' D2: 110 Kcfm

_D2/3 Vent GASEOUS EFFLUENTS AVERAGE FLOW D3: 110 Kefm l-l MRL (uCi/cc)  % OF TIME < MDL

1. FISSION GASES LXe-138 4.16 E-08 100 Xe-135m 1.29 E 100 Kr-87 3.03 E-08 100 Kr-88 5.21'E-08 100 Kr-85m 1.78 E-08 -100 Kr-85 4.43 E-06 ~100 L Xe-135 1.52 E-08 50.5 Xe-133 4.32 E-08 96.2 Others:
2. IODINES I-131 5.34 E-14 3.9 l

I-133 5.57 E-14 17.5 I-135 1.19 E-14 40.4

3. PARTICULATE Sr-89 2.5 E-14 16.9 Sr-90 1.5 E-14. 50.8 Cr-51 4.20 E-13 33.9 Mn-54 5.27 E-14 0.0 Co-58 4.83 E-14 7.1 Fe-59 7.58 E-14 9.3

'Co-60 1.26 E-13 0.0 Zr-95 9.09 E-14 96.2 Nb-95 4.96 E-14 100.0 Ru-103 4.95 E-14 100.0-Ag-110m 5.12 E-14 61.7 Sb-124 5.86 E-14 95.6 I-131 5.15 E-14 34.6 Cs-134 5.73 E-14 100.0 l Cs-136 5.49 E-14 88.5 Cs-137 6.21 E-14 34.4 Ba-140 1.91 E-13 50.0 Ce-141 7.64 E-14 100.0 Ce-144 3.27 E-13 96.2 Zn-65 9.03 E-14 54.1 Ba-133 6.93 E-14 100.0 Sb-125 1.39 E-13 100.0 Others: Mo-99 3.95 E-13 50.8 Page 8 of 15 1981a

DRESDEN NUCLEAR POWER' STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January Through June 1983 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES Docket Numbers: 50-10 50-237^

50-249 UNIT- 15_t QUARTER 2nd QUARTER A. FlSS10N AND ACTIVATION ERQDEIS

1. Total Release (not incl. tritium, gases, alpha) Ci 7.78 E-03 5.23 E-02
2. Average Diluted Conc. During Period uCi/mL 6.54 E-08 6.70 E-07
3. Percent of. Applicable Limit  % *
  • B. TRITI.UM
1. Total Release Ci 2.62 E00 8.81 E00
2. Average Diluted Conc. During Period uCi/mL 2.20 E-05 1.13 E-04
3. Percent of Applicable Limit  % *
  • L__plSS01VED AND ENTRAINED CASES
1. Total Release Ci 3.02 E-04 2.05 E-04
2. Average Diluted Conc. During Period uCi/mL 2.54 E-09 2.62 E-09
3. Percent of Applicable Limit  % *
  • D. GROSS ALPHA RADIOACTIVITY
1. Total Release Ci <MDL <MDL-E. VOLUME OF WASTE RELEASED (prior to dilution) liters 3.42 E06 1.38 E07 F. VOLUME OF DILUTION '-7.TER USED DURING PERIOD liters 1.16 EOS 6.43 E07
  • Will be included in the Annual Report on Environmental Radioactivity Data Page 9 of 15 1981a

- - - - - - - -____-__._____.._______.._m.___

i4 O^ *

'DRESDEN NUCLEAR POWER STATION EFFLUENT.AND WASTE DISPOSAL SEMIANNUAL REPORT January' Through June 1933 Radwaste LIQUID EFFLUENTS Docket Numbers:~50-10

.50-237

1. Number of Batch Releases: 183 50-249
2. Total-Time Period for Batch Releases: 58,633 min-

'3. Maximum Time' Period for a Batch Release: 447 min

4. Average Time Period for. Batch Releases: 320 min
5. Minimum Time Period for a Batch Release: 11 min
6. Average Stream Flow.During-Periods of _.

Release of Effluent into a Flowing Stream: 8.57 E04-L/ min CONIIN!JDDS_MQpE BATCilft0DX NUCLIDES RELEASED UNIT in QUARTER 2nd QUARTER 131 QUARTER 2nd QUARTER' Sr-89 .Ci *

  • 1.71'E-04 Ar-41 Ci *
  • Mn-54 C1 3.00 E-04' 5.13 E-03 Co-53 ..Ci_ *
  • Fe-59 C1
  • Ru-103 Ci *
  • Sb-122' 31 *
  • Sb-124 CL_ *
  • _

I-133 Ci *

  • I-135 . _01_ _

Cs-134 C1 *

  • Cs-137 C1 2.56 E-03 5.99 E-03 Ba-140- Cl *
  • La-14D Ci '* -*

Ce_-141 Ci *

  • 2.51 E-03

._gr-51 C1_. 1.09 E-04

  • Cs-138 C1 3.38 E-04 C1 (above)

Iotal For Period' Ci None None 7.71 E-03 5.21 E-02 Xe-133 C1 1.79 E-04 1.36 E-04 Xe-135 Ci 1.23 E-04 6.89 E-05

  • See Table for MDL of Each Nuclide Page 10 of 15 1981a

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

i y, DRESDEN NUCLEAR POWER STATION

c. c >

January Through' June 1918

' TABLE OF MINIMUM DETECTABLE LEVELS Docket Numbers: '

FOR LIQUID EFFLUENTS 10.

50-237 50-249 Radwaste LIQUID EFFLUENTS TOTAL GALLONS RELEASED 4.145.460 MDL (uCi/mL)  % OF GALLONS < MDL' T

'Sr-89 8.3 E-08 100.0 Sr-90 2.4- E-08 75.7 Ar-41 2.71 E-08 100.0

.Mn-54 5.04 E-08 18.9 Co-58 4.98 E-08 100.0 Fe-59 8.11 E-08 99.0 Co-60 1.18 E-07 0.0 Zn-65 9.97 E 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 99.5 I-133- 5.34 E-08 100.0 I-135 9.15 E-08 100.0 Cs-134- 5.51 E-08 100.0 4

-Cs-137 4.04 E-08 2.2 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 91.5 Xe-135 5.13 E-08 89.1 Cr-51 4.81 E-07 99.3 Fe-55 3.1 E-07 83.0 Page 11 of 15

,n 1981a .

~

DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

_lanuary. Through June 19&B LPCI LIQUID EFFLUENTS Docket Numbers: 50-237 i 50-249

1. Number of Batch Releases: 97
2. Total Time Period for Batch Releases: 120.3 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: 1.32 E04 L/ min CONTIN _UQUS_M0EE BATCH MODE NUCLIDES RELEASED UNIT ini QUARTER 2nd QUARTER 131 QUARTER 2nd QUARTER Sr-89 Ci 2.10 E-06
  • Ar-41 _fi_

Mo _54 _Ci 9.81 E-07 1.50 E-05 Ci *

  • Co-58 Ci *
  • Fe-59 Co-60 Ci 6.10 E-05 1.48 E-04 Zn-65 A
  • Ru-103 Ci Ci *
  • Sb-122 Ci *
  • I-133 Ci Ci *
  • I-135 Cs-134 C1 *
  • Cs-137 Ci 9.77 E-06 2.13 E-05 Ci *
  • Ba-140 Ci *
  • La-1tDi Ci *
  • Ce-141 Others: Cr-51 Ci Fe-55 Ci
  • _Ci C1 (above)

IotaLfor Period __ Ci None None 7.42 E-05 1.84 E-04 Ci *

  • Xe-133 Xe-135 Ci
  • See Table for MDL of Each Nuclide Page 12 of 15 1981a

DRESDEN NUCLEAR POWER STAIION January Through June 1988 TABLE OF MINIMUM DETECTABLE LEVELS Docket Numbers:

FOR LIQUID EFFLUENTS 50-237 50-249 LPCI LIQUID EFFLUENTS TOTAL GALLONS RELEASED 4.21 E05 MDL (uCi/mL)  % OF GALLONS < MDL Sr-89 7.9 E-08 95.9 Sr-90 2.7 E-08 95.9 Ar-41 2.71 E-08 100.0 Mn-54 5.04 E-08 63.9 Co-58 4.98 E-08 100.0 Fe-59 8.11 E-08 100.0 Co-60 1.18 E-07 14.4 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 I-135 9.15 E-08 100.0 Cs-134 5.51 E-08 100.0 Cs-137 4.04 E-08 40.2 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 Page 13 of 15 1981a

, DRESDEN NUCLEAR POWER STATION EFFLUENT AND. WASTE DISPOSAL SEMYANNUAL REPORT

_h nuary__ Through June 1983 Docket Numbers:

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

50-249 A. SOLID WASTE SHIPPED'0FFSITE FOR BURIAL OR DISPOSAL (NOT IRRADJAIED_ EUEL)

1. Type of. Waste Unit 6-month period m 06.4
a. Spent resins, filter sludges, evaporator bottoms, etc.

Ci 7.18 E02

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

Ci 1.09 E01 Irradiated components, control rods, etc.

m 2.3 c.

Ci 1.66 E00

d. Other (describe)

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

% C1

a. 'Co-60 74.5 % 5.35 E02 Fe-55 12.4 % 8.90 E01 Mn-54 9.8  % 7.04 E01 Cs-137 0.7  % 5.03 E00 Other 2.6  % 1.87 E01
b. Co-60 24.4 .% 2.66 E00 Fe-55 71.3 % 7.77 E00 Mn-54 2.8  % 3.05 E-01 Cs-137 1.4  % 1.53 E-01 Other 0.2  % 2.18 E-02
c. Co-60 29.41 % 5.47 E-01 F_e.-5 5 67.95 1 _ l l ft 1 0 0._

Mn-54 2.64 % 4.91 E-02

_1

d.  %
3. Solid Waste Disposition NUMBER CF SHIPMENTS MODE OF TRANSPORTATION DESTINATION l 1 Motor freight (exclusive use only) Chem-Nuclear, IL 42 Motor freight (exclusive use only) Barnwell, SC 16 Motor freight (exclusive use only) SEG, TN l 1 Motor freight (exclusive use only) Quadrex, TN 2 Motor freight (exclusive use only) Westinghouse-DRR, PA B. IRRADIATED FUEL SHIPMENTS (Disposition)

NUMBER OF SHIPMENTS MDDE OF TRANSPORTATION DESTINATION 1 Motor freight (exclusive use only) Barnwell, SC Page 14 of 15 1981a

f '

DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

_ January Through June- 19&B Docket Numbers:

50-10 ABNORMAL RELEASES 50-237 50-249 A. LIQUID

1. Number of Releases: None
2. Total Activity Released: None B. GASEOUS
1. Number of Releases: None
2. Total Activity Released: None I

15 of 15 l 1981a )

l

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