ML20244D118

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Corrected Radioactive Effluent Rept for Jul-Dec 1988 for Dresden Nuclear Power Station
ML20244D118
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 12/31/1988
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20244D112 List:
References
NUDOCS 8904210157
Download: ML20244D118 (15)


Text

_-- -_-_-__- - _ _- -

DRESDEN NUCLEAR POWER STATION DOCKET NOS. 50-10, 50-237, 50-249 MEASUREMENTS ALU 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 samplo..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 greb 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 L

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 i

L 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 15 0727a 8904210157 890328 PDR ADOCK 05000010 R

PDC I

DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Julv Through Deca =her_ 1918 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES Docket Numbers: 50-10 50-237 50-249 UNIT 3.rd QUARTER.41h QUARTER A.

FISSION AND ACTIVATION GASES 1.

Total Release Ci 1.81 E01 1.66 E01 2.

Average Release Rate for Period Luci/sec 2.20 E00 2.09 E00 3.

Percent of Technical Specification Limit

' A' E.

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

~

Percent of Technical Specification Limit 3.

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 a

D.

TRITIUM 1.

Total Release Ci 8.40 E00 4.76 E00 2.

Average Release Rate for Period uC1/see 1.06 E00 5.99 E-01 3.

Percent of Technical Specification Limit Q Will be included in the Annual keport on Environmental Radioactivity Data Page 2 of 15

-0727a I

l' DRESDT:N NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Julv Through December 1988 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 Ath QUARTER 3rd QUARTER Ath QUARTER FIESION GASES C1 Xe-138 Ci Xe-135m Ci Kr-87 Ci Kr-88 Ci Kr-85m Ci Kr-85 Ci Xe-135 C1' Xe-133 C1 Others:

C1 Ci TOTAL Ci None None 10 DINES I-131 Ci I-133 Ci I-135 C1 TOTAL' Ci None None PARTICULATE Sr-89 Ci Sr-90 C1 1.20 E-07 Cr-51 Ci Mn-54 Ci 2.29 E-07 Co-58 Ci Fe-59 Ci Co-60 C1 1.17 E-06 3.01 E-06

__ Zr-95 Ci Nb-95 Ci Ru-103 Ci Ar-110m Ci Sb-124 Ci I-131 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 Zn-65 Ci Ba-133 Ci Sh-125

_.Ci Others:

C1 Ci Ci Ci Ci TOTAL Ci 8.94 E-06 8.61 E-06 None None

  • See Table for MDL of Each Nuclide Page 3 of 15 i

-DRESDEN NUCLEAR' POWER STATION:

-EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT juiv __ Through Dec==her_ 19BB Docket Number 50-10

TABLE OF MINIMUM DETECTABLE LEVELS-FOR GASEOUS EFFLUENTS D1 Ch4=nev GASEOUS EFFLUENTS

. AVERAGE FLOW 50.000 cfm' MDL (uCi/cc) 1 0F 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 4.43 E-06 100.0 Xe-135 1.52 E 100.0 Xe-133.

4.32 E-08 100.0 Others:

2.

IODINES 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. 8 E-11 100.0-Sr-90 9.7 E-12 83.2 Cr-51 4.20 E-13 100.0 Mn 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 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 '40 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 0727a

DRESDEN NUCLEAR POWER STATION I

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Julv Through _DecemhnI_1983 D2/3 Chimney GASEOUS EFFLUENTS GROUND LEVEL RELEASES Docket Numbers: 50-237 SEMI-ELEVATED RELEASES 50-249 xx ELEVATED RELEASES CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT ltd QUARTER 4th QUARTER 3rd QUARTER 4th QUARTER FISSION GASES Ci Xe-138 C1 2.54 E00 Xe-135m

_C1._. d 56 E00 Kr-87 Ci Kr-88 Ji Kr-85m Cl Kt-85

__ Ci 2 16_E-03 2,_68 E-03 Xe-135 Ci 1.40 E01 1.64 E01 Xe-133 Ci l

Others:

Ci ci TQTAL C1 1J1 E01 1.64 E01 None None 10 DINES I-131 Ci 1.54 E-03 5.52 E-04 I-133 C1 1.06 E-0.2 3,42 E-03 I-135

_Ci 1.56 E-02 4.04 E-03 TOTAL Ci 2.77 E-02 8.01_E-S3 None None PARTICULATE Sr-89 Ci 7.03 E-05 4.82 E-05 Sr-90 C1 3.37 E-07 3.26 E-07 Cr-51 Ci Mn-54 C1 1.90 E-04 3.22 E-05 Co-58 Ci Fe-59 Ci Co-60 Ci 5.96 E-04 1.57 E-04 Zr-91 Ci Nb-95 Ci c

Ru-103 Ci Ag-110m Ci Sb-124 Ci I-131 C1 1.46 E-04 8.05 E-05 Cs-134 C1 Cs-136 Ci Cs-137 Ci 2A 5 E-05 2.28 E-04 Ba-140 Ci 8.99 E-04 5.45 E-04 Ce-141 Ci Ce-144 C1 Zn-65

_Ci Ba-133 Ji_

Sb-125

_Ci Othen:

C1 Ci Ci C1 Ci TOTAL Ci 1.93 E-03 1.09 E-03 None None

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

DRESDEN NUCLEAR, POWER STATION Julv Through Dec==her 1988' Dockot Numbarst 50-237 TABLE OF MINIMUM DETECTABLE LEVELS 50-249

^

-FOR GASEOUS. EFFLUENTS' 3rd atr-289.

Kefm D2/3 Chimnev GASEOUS' EFFLUENTS LAVERAGE FLOW 4th'a[tr313 Kcfm MQL (uCi/cc) 1 OF TIME < MDL

.1.

FISSION GASES' Xe-138 4.16 E-08 98.9 Xe-135m 1.29 E-07 98.4 i

Kr-87 3.03 E-08 100.0 Kr-88 5.21 E-08 100.0 Kr-85m 1.78 E-08' 100.0 Kr-85 4.43 E-06 0

Xe-135 1.52 E-08 47.8 l

Xe-133-4.32 E-08 100.0 l

Others:

1 I

2.

10 DINES I-131 5.34 E-14 0

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 49.5 Cr-51 4.20 E-13 100.0 L

1 Mn-54 5.27 E-14 42.9 0o-58 4.83 E-14 100.0 Fe-59 7.58 E-14 100.0 Co-60 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

>i Sb-124 5.86 E-14 100.0 I-131 5.15 E-14 4.9 1

Cs-134 5.73 E-14 100.0 Cs-136 5.49 E-14 100.0 Cs-137 6.21 E-14 21.7 i

Ba-140 1.91 E-13 7.6 l

Ce-141 7.64 E-14 100.0 Ce-144 3.27 E-13 100.0 Zn-65 9.03 E-14 100.0 j

Ba-133 6.93 E-14 100.0 Sb-125 1.39 E-13 100.0 Others:

Page 6 of 15 1

0727a J

DRESDEN NUCLEAR P0 STATION EFFLUENT AND MASTE DISPOSAL SEMIANNUAL REPORT Julv Through December 19Bfl

\\

l-D2/3 Vent GASEOUS EFFLUENTS GROUND LEVEL RELEASES Docket Numbers: 50-237 l

xx SEMI-ELEVATED RELEASES 50-249 ELEVATED RELEASES CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT 3rd QUARTER hih QUARTER 3rd QUARTER hih QUARTER FISSION GASES Ji Xe-138 Ci Xe-135m Ci Kr-87 J i__

Kr-88 Ci Kr-85m Ci Kr-85 Ci Xe-135 Ci 2.06 E-01 Xe-133 Ci Others:

01 Ci TOTAL C1 2.06 E-01 None None 10 DINES I-131 Ci 9.66 E-05 4.36 E-05 I-133 Ci 6.01 E-04 1.36 E-04 I-135 Ci 4.22 E-04 1J1_E-Q5 TOTAL 01 1.12 E-03 2.00 E-04 None None PARTICULATE Sr-89 C1 8.89 E-07 Sr-90 Ci Cr-51 C1 1.09 E-04 7.28 E-05 Mn-54 Ci 3.29 E-04 2.15 E-04 Co-58 C1 1.63 E-05 5.53'E-05 Fe-59 Ci 2.25 E-05 1.27 E-05

)

Co-60 Ci 1.36 E-03 1.58 E-03 2r-95 Ci Nb-95 C1 Ru-103 Ci Ag-110m C1 Sb-124 Ci 1.19 E-06 I-131 C1 1.16 E-05 3.73 E-06 i

C3-134 Ci Cs-136 Ci Cs-137

_Ci 1.35 E-05 1.82 E-05 Ba-140 Ci 2.15 E-05 3.74 E-06 Ce-141 Ci Ce-144 Ci Zn-65 Ji_

5.33 E-06 Ba-133

_Ci Sb-125 Ci Others:

Ci l

Ci Cl TOTAL C1 1.89 E-03 1J6 E-03 Nong None __

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

DRESDEN NUCLEAR POWER STATION.

hJ

Juiv'

'Through Dec==her 1988 Docket Numbarst-J 50-237 J

TABLE OF MINIMUM DETECTABLE LEVELS 50-240

'~

FOR GASEOUS EFFLUENTS D2:

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

110 Kcfm

'MDL (cCi/cc)

% OF TIME < MDL 1.

FISSION GASES-Xe-138-4.16 E-08 100.0 l

.Xe-135m 1.29 E-07

'100.0' L

.Kr-87 3.03 E-08 100.0 Kr-88 5.21 E-08 100.0 Kr-85m 1.78 E-08 100.0 m

Kr 4.43 E-06 100.0 Xe-135 1.52 E-08 96.2 Xe-133 4.32 E-08 100.0 Others:

2.

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 2.8 E 66.3 Sr-90

'9.7 E-12 100.0 Cr-51 4.20 E-13 32.6 Mn-54 5.27 E-14.

O Co-58 4.83 E-14 53.8 Fe-59 7.58 E-14 78.8 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-14 100.0-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 Ba-140 1.91 E-13 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

').

DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT July Through Dec==her 1988 LIQUID' EFFLUENTS

.]

SUMMATION OF ALL RELEASES Docket Numbers: 50-10 50-237 50-249-1, UNIT-3rd QUARTER ith QUARTER -

A.

FISSION AND ACTIVATION PRODUCTS

1. Total Release (not. incl. tritium, gases, alpha)

Ci 1.41 E-02.4.22 E-02

2. Average Diluted. Conc. During Period uCi/mL 7.05 E-08 4.51 E-07
3. Percent of Applicable Limit B.

TRITIUM

1. Total Release Ci 5.02 E-01 5.25 E00 1
2. Average Diluted Conc. During Period uCi/mL 2.51 E-06 5.60 E-05
3. Percent of Applicable Limit C.

DISSOLVED 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.

GROSS ALPHA' RADIOACTIVITY

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 o Will be included in the Annual Report on Environmental Radioactivity Data Page 9 of 15 0727a

DRESDEN NUCLEAR POWER STATION =

S EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Julv Through December 1933 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 l

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: 2f,2. 72 L/ min CONIINUQUS MODE BATCH MODE....

NUCLIDES RELEASED UNIT 3rd QUARTER Alb QUARTER 3rd QUARTER Alh QUARTER Sr-89 Ci Sr-90 C1 Ar-41 Ci 2.65 E-05 Mn-54 C1 1.24 E-03 3.42 E-04 00-58 C1 1.02 E-05 3.52 E-04 Fe-59 C1 7.03 E-04 Co-60 01 1.09 E-02 2.53 E-02 Zn-65 Ci i

Ru-103 C1 Sb-122 C1 Sb-124 Ci 1.60 E-07 I-131-Ci

.l I-133 Ci l

I-135 C1 Cs-134 Ci Cs-137 C1 1.84 E-03 5.48 E-03 Ba-140 01 La-140 C1 1.11 E-06 j

Ce-141 Ci Others: Cr-51 Ci 5.71 E-04 Zr-95 Ci 5.70 E-08 Nb-95 Ci 6.00 E-0B__

l Fe-55 Ci 9.44 E-03 (above)

Total For Period Ci None None 1.40 E-02 4J,2 E Xe-133 C1 1.03'E-04 Xe-135 Ci 9.49 E-06 3.02 E-04

  • See Table for MDL of Each Nuclide 1

i Page 10 of 15

)

0727a l

J

DRESDEN NUCLEAR POWER STATION

'Julv Through December 1988 TABLE OF MINIMUM DETECTABLE 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 26.7 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 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 99.3 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 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 Xe-135 5.13 E-08 93.8 Cr-51 4.81 E-07 95.8 Fe-55 4.8 E-07 0

Zr-95 Not Determined 99.3 Nb-95 Not Determined 99.3 I,

Page 11 of 15 0727a

DRESDEN NUCLEAR POWER STATION

's -

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

~

Julv Through December 1988 LPCI LIQUID EFFLUENTS-Docket Numbers: 50-237 50-249 l

l 1.

Number of Batch Releases:. 95 2.

Total Time Period for Batch Releases: 117.80 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: 13,248.5 L/ min CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT 3rd QUARTER hih QUARTER 3rd QUARTER Ath QUARTER Sr-89

_Ci_

Sr-90 Ci Ar-41 Ci Mn-54 C1 8.52 E-06 3.40 E-07 00-58 Ci Fe-59 Ci Co-60 C1 6.79 E-05 1.32 E-05 Zn-65 Ci Ru-103 Ci Sb-122 C1 Sb-124 Ci I-131 Ci I-133 Ci I-135 Ci Cs-134 Ci Cs-137

_C1 L30 E-05 2,10 E-05 Ba-140 Ci La-140 Ci Ce-141

_CL f'

Otheral_CI-51_

Ci Fe-55 Ci Ci C1 (above)

Iolal For Period __. Ci None None 1.09 E-04 3.A5_E-05 _

Xe-133

_CL Xe_135 Ci

  • See Table for MDL of Each Nuclide l

Page 12 of 15 l

0727a

DRESDEN NUCLEAR POWER STATION Julv Through Deca =her 1988 TABLE OF MINIMUM DETECTABLE LEVELS Docket Numbers:

FOR LIQUID EFFLUENTS 50-237 50-249 LPCI LIQUID EFFLUENTS TOIAL GALLONS RELEASED 412.300 MDL (uCi/mL)

% OF GALLONS < MDL Sr-89 6.0 E-08 100.0 Sr-90 3.1 E-08 100.0-Ar-41 2.71 E-08 100.0 l

Mn-54 5.04 E-08 33.7 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 I-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 I

Page 13 of 15 0727a

DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT s

Julv Through December 1983 Docket Numbers:

50-13 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 50-237 50-249 A,_E011D_}]ASIE__ElilPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRAD::6TED_IEEL)

1. Type of Waste Unit 6-month period 2

m

.1 02 Spent resins, filter sludges, evaporator bottoms, etc.

a.

Ci 6.12 E02 n

1.04 E03 b.

Dry compressible waste, contaminated equip., etc.

Ci 1.97 E02 m

2.36 E00 c.

Irradiated componente, control rods, etc.

Ci 2.00 E-01 m'

0 d.

Other (describe)

Ci 0

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

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_EQ1_

h,__

Co-60 24.4 %

4.81 301 Fe-55 71.3 %

1.40 E02 Mn-54 2.8 5.52 E00 Cs-137 1.4 %

2.76 E00 Other 0.2 %

3.94 E-01 1

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 NUtiaER OF SHIPMENTE tiODE OF TRANSEDRTATION DESTINATION 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)

NUMBER OF SHIPMENIS MODE OF TRANSPORTATION DESTINATION None Page 14 of 15 0727a

_ _ _ _ _ _ _ _ _ _ _ _ _ _ ~

DRESDEN NUCLEAR POWED 0TATION-o.

s

. EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

~Julv Through December '1938 Docket' Numbers:

'g.

50-10 ABNORMAL RELEASES 50-237 50-249 L

i

'A.

-LIQUID 1.

Number of Releases:

None 2.

Tota 1' Activity Released:

'None B.

GASE0US

.I 1.

Number of Releases:

None 2.

Total Activity Released:

None 15 of 15 0727a i

l