ML20134P534

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Effluent & Waste Disposal Semiannual Rept,Jan-June 1985
ML20134P534
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 06/30/1985
From: Scott D
COMMONWEALTH EDISON CO.
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
85-823, NUDOCS 8509060355
Download: ML20134P534 (16)
v • d • e


Text

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

A. Fission and activation gases: The D-1 chimney and D-2/3 chimney are sampled daily (beginning in April 1985) via a grab sample.

The D-2 and D-3 Reactor Vents are sampled weekly via grab sample.

The samples are analyzed for specific isotopas present in the release using a Ge(Li) spectrometry system. ' Tritium is collected via a monthly grab sample (beginning in April 1985) and analyzed using a Liquid Scintillation counter.

B. Iodine and Particulate: Iodine and particulate samples from the D-1 Chimney, the D-2/3 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. 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) spec-trometry system. This sample is sent to a vendor to be analyzed for Sr-89, Sr-90, Fe-55, and Gross Alpha activity.

8509060355 850630 O DR ADOCK O h&

1

, DRESDEN NUCLEAR POWER STATION )

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY Through JUNE 19 85 l GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES Docket Nos. 50-10, 50-237, 50-249 UNIT Ine QUARTER 2nd QUARTER L FISSION AND ACTIVATION GASER

1. Total Release ci 7.97E+02 1.09E+03
2. Average Release Rate for Perind uCi/sec 1.03E+02 1.39E+02
3. Percent of Technical Specificneinn T.1 fe  % * *
l. IODINES
1. Total Iodine-131 Ci 1.68E-02 2.34E-02
2. Average Release Rate for Period uCi/sec 2.16E-03 2.98E-03 i 3. Percent of Technical Soecification Limit  % * *

. PARTICULATES

1. Particulates with half-lived 3R Any, Ci 2.59E-02 3.24E-02
2. Average Release Rate for Period uCi/see 3.33E-03 4.12E-03
3. Percent of Technical Specification Limit  % * *
4. Gross Alpha Radioactivity C1 1.95E-04 4.73E-06 TRITIUM
1. T2tal Release C1 2.84E+01 1.11E+01 1

I 2. Average Release Rate for Period uCi/sec 3.66E00 1.41E00

3. Parcent of Technical Specification Limit  % * *
  • Will be included in the Annual Report on Environmental Radioactivity Data 1

URESDEN NUCLEAR P03ME sgATION UNIT 1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY THROUGH JUNE 19 _8,5 _

D-1 Chimnev GASEOUS EFFLUENTS GROUND LEVEL RELEASES SEMI-ELEVATED RELEASES XX ELEVATED RELEASES Docket No. 50-10 CONTINUOUS MODE BATCH MODE bCLIDESRELEASED' UNIT IstQUARTER 2ndQUARTER lseQUARTER 2nd QUARTER (

L FISSION GASES Ci l Xe-138 Ci *

  • l Xc-135m Ci *
  • l I Kr-87 Ci *
  • I Kr-88 Ci *
  • I Kr-85m Ci *
  • Xe-135 Ci *
  • l Xe-133 Ci *
  • Others: Ci Ci TOTAL Ci NONE NONE 10 DINES I-131 Ci *
  • I-133 Ci *
  • I-135 Ci *
  • TOTAL Ci h0NE NONE PARTICULATES Sr-89 C1 1.86E-06 2.00E-06 Sr-90 Ci *
  • Cr-51 Ci *
  • l Co-58 Ci *
  • Fe-59 Ci *
  • Co-60 Ci 1.09E-05 2.39E-05 Zr-95 Ci *
  • Nb-95 Ci *
  • Ru-103 Ci *
  • Ar-110m Ci *
  • Sb-124 Ci *
  • Cs-134 Ci
  • 2.17E-07 l Cs-136 Ci *
  • I Cs-137 Ci 6.64E-06 7.61E-06 i Ba-140 Ci *
  • I Ce-141 Ci *
  • I Ce-144 Ci *
  • l Zn-65 Ci *
  • I Ba-133 Ci *
  • I Sb-125 Ci *
  • I Othera: C1 Ci '

I Ci l Ci l Ci l TOTAL C1 1.96E-05 3.37E-05 NONE NONE

  • See Table for MDL of Each Nuclide

~

9 DRESDEN NUCLEAR POWER STATION TABLE OF MINIMUM DETECTABLE LEVELS FOR GASEOUS EFFLUENTS D-1 Chimney GASEOUS EFFLUENTS AVERAGE FLOW 50,000 cfm Docket No., 50-10 MDL (uC1/cc)  % OF TIME < MDL

1. FISSION GASES Xe-138 5.43E-08 100 Xe-135m 2.37E-08 100 Kr-87 3.88E-08 100 Kr-88 6.47E-08 100 Kr-85m 1.86E-08 100 Kr-85 5.73E-08 100 Xe-135 1.89E-08 100 Xe-133 5.18E-08 100 Others:
2. 10 DINES I-131 3.80E-14 100 I-133 4.40E-14 100 I-135 7.90E-14 100
3. PARTICULATES 2W .%

Sr-90 1.00E-15 100 Cr-51 1.60E-13 100 Mn-54 3.30E-14 96 Co-58 3.50E-14 100 Fa-59 5.30E 100 Cc-60 8.70E-14 0 Zr-95 3.10E-14 100 Nb-95 1.90E-14 100 Ru-103 1.90E-14 100 Ag-110m 1.90E-14 100 Sb-124 2.40E-14 100 I-131 2.00E-14 100 Cc-134 1.60E-12 96 C:-136 5.30E-14 100 t

Cc-137 3.80E-14 0 l_

Ba-140 6.70E-14 100 C -141 4.70E-14 100 l C -144 2.00E-13 100 Zn-65 5.90E-14 100 Ba-133 2.60E-14 100 Sb-125 1.80E-14 100 Others: La-140 3.00E-14 100

UtiMLLxAnsW5LQEM 1ROLO @tTATION UNIT M3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY THROUGH JUNE 19 85 2/3 Chimney GASEOUS EFFLUENTS GROUND LEVEL RELEASES SEMI-ELEVATED RELEASES xx ELEVATED RELEASES Docket Nos. 50-237, 50-249 CONTINUOUS MODE BATCH MODE JCLIDES RELEASED UNIT latQUARTER M QUARTER ineQUARTER 2ndQUARTER FISSION GASES Ci Xe-138 Ci 2.69E+02 4.18E+02 Xe-135m Ci 5.15E+01 4.99E+01 Kr-87 Ci

  • 6.14F+01 Kr-88 Ci
  • A_7AF+01 Kr-85m Ci
  • 1.14E+01 Kr-85 Ci 2.70E-02 3_s6E-02 Xe-135 Ci 4.60E+02 3.78E+02 Xe-133 Ci
  • 2.63E+01 Others: Ci Ci TOTAL Ci 7.81E+02 1.06E+03 NONE NONE IODINES I-131 - Ci 1.53E-02 2.21E-02 I-133 Ci 9.42E-02 1.05E-01 I-135 Ci 1.64E-01 1.24E-01 TOTAL Ci 2.74E-01 2.51E-01 NONE NONE PARTICULATES Sr-89 Ci 3.30E-03 4.92E-03 Sr-90 Ci 9.13E-05 7.05E-06 Cr-51 Ci *
  • Mn-54 Ci 9.93E-05 1.28E-04 Co-58 Ci
  • 2.72E-05 Fe-59 Ci
  • 3.37E-05 Co-60 Ci 4.95E-04 1.17E-03 Zr-95 Ci *
  • Nb-95 Ci *
  • Ru-103 Ci *
  • An-110m
  • Ci 8.26E-06 Sb-124 Ci 1.95E-06
  • I-131 C1 2.77F-01 2.81E-03 Cs-134 Ci *
  • Cs-136 Ci *
  • Cs-137 Ci 8.21E-05 4.81E-05 Ba-140 Ci 1.05E-02 1.44E-02 Ce-141 Ci 2.61E-04 2.55E-04 j Ce-144 Ci *
  • l Zn-65 Ci *
  • j Ba-133 Ci *
  • l Sh-125 Ci *
  • j Oth1rn Ci j Ci l C1 Ci Ci  !

TOTAL Ci 1.75E-02 2.38E-02 NONE NONE l

  • See Table for MDL of Each Nuclide t .

~

DRESDEN NUCLEAR POWER STATION TABLE OF MINIMUM DETECTABLE LEVELS FOR GASEOUS EFFLUENTS 2/3 Chimney GASEOUS EFFLUENTS AVERAGE FLOW 1st Qtr.-287,000 Kcfm Docket Nos. 50-237, 50-249 2nd Qtr.-281,000 Kcfm MDL (uCi/cc)  % OF TIME < MDL

1. FISSION GASES Xa-138 1.65E-07 0 Xe-135m 6.67E-08 0 Kr-87 5.30E-08 90 Kr-88 3.97E-08 88 Kr-85m 2.73E-08 91 Kr-85 5.73E-08 0 Xe-135 2.72E-08 0 Xe-133 6.65E-08 92 Others:
2. IODINES I-131 3.80E-14 0 I-133 4.40E-14 0 I-135 7.90E-14 0
3. PARTICULATES Sr-90 1.00E-15 0 Cr-51 1.60E-13 100 Mn-54 3.30E-14 0 Co-58 3.50E-14 92 Fe-59 5.30E-14 96 Co-60 8.70E-14 0 Zr-95 3.10E-14 100 Nb-95 1.90E-14 100 Ru-103 1.90E-14 100 Ag-110m 1.90E-14 96 Sb-124 2.40E-14 96 I-131 2.00E-14 o C:-134 1.60E-12 100 CC-136 5.30E-14 100 Cc-137 3.80E-14 o Ba-140 6.70E-14 o Ce-141 4.70E-14 0 Cc-144 2.00E-13 100 Zn-65 5.90E-14 100 Ba-133 2.60E-14 100 Sb-125 1.80E-14 100 Others: La-140 3.00E-14 100,

t0Mt)L8J NUCLEAR POWER STATION UNIT 2/3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT -

JANUARY THROUGH JUNE ' 19 85 2/3 VENT GASEOUS EFFLUENTS GROUND LEVEL RELEASES XX SEMI-ELEVATED RELEASES ELEVATED RELEASES Docket Nos. 50-237, 50-249 CONTINUOUS MODE BATCH MODE JCLIDES RELEASED ' UNIT IstQUARTER 2na QUARTER tyrQUARTER haQUARTER I FISSION GASES I Xe-138 Ci *

  • Xc-135m Ci * '

Kr-87 Ci

  • l.03E00 Kr-88 Ci
  • 9.68E-01 Kr-85m Ci
  • Xe-135 Ci 1.57E+01 9.57E00 Xe-133 Ci 6.65E-01 1.07E01 Others: C1 Ci TOTAL Ci 1.64E+01 2.50E+01 NONE NONE IODIhTS I-131 Ci 1.46E-03 1.33E-03 I-133 Ci 9.71E-03 1.10E-02 I-135 Ci 1.61E-02 2.05E-02 TOTAL C1 2.73E-02 3.28E-02 NONE NONE PARTICULATES Sr-89 C1 2.53E-04 6.15E-04 Sr-90 C1 3.48E-06 6.37E-05 Cr-51 Ci 3.75E-04 4.47E-04 Mn-54 Ci 4.17E-04 5.94E-04 Co-58 Ci 1.82E-04 1.44E-04 Fe-59 Ci 1.44E-04 3.15E-04 Co-60 Ci 4.24E-03 3.94E-03 Zr-95 Ci *
  • Nb-95 Ci 4.60E-06
  • Ru-103 Ci 1.26E-05 8.06E-06 Ae-110m Ci *
  • Sb-124 Ci 9.50E-06 1.39E-05 I-131 Ci 3.96E-04 3.28E-04 Cs-134 Ci 3.01E-06 4.80E-07 Cs-136 C1 2.71E-05 7.64E-06 Cs-137 Ci 5.67E-05 7.23E-05 Ba-140 Ci 2.15E-03 1.96E-03 Ce-141 Ci 5.65E-05 5.25E-05 Ce-144 Ci *
  • Zn-65 Ci 3.87E-05 2.48E-05 Ba-133 Ci *
  • Sb-125 Ci *
  • Oth7rn: Ci C1 C1 Ci Ci I TOTAL Ci 8.37E-03 8.59E-03 NONE NONE
  • See Table for MDL of Each Nuclide

~

S DRESDEN NUCLEAR POWER STATION TABLE OF MINIMUM DETECTABLE LEVELS FOR GASEOUS EFFLUENTS 2/3 VENT GASEOUS EFFLUENTS AVERAGE FLOW 220,000 cfm MDL (uCi/cc)  % OF TIME < MDL Docket Nos. 50-237, 50-249

1. FISSION GASES Xa-138 1.31E-07 100 Xe-135m 6.67E-08 100 Kr-87 8.47E-08 88 Kr-88 1.46E-07 95 Kr-85m 2.73E-08 86 Kr-85 5.73E-08 100 Xe-135 4.33E-08 0 Xe-133 1.14E-07 0 Others:

r 2. IODINES I-131 3.80E-14 0 I-133 4.40E-14 0 I-135 7.90E-14 0 i3. PARTICULATES Sr-90 1.00E-15 0 Cr-51 1.60E-13 0 Mn-54 3.30E-14 0 Co-58 3.50E-14 0 Fs-59 5.30E-14 0 Co-60 8.70E-14 0 Zr-95 3.10E-14 100 Nb-95 1.90E-14 96 Ru-103 1.90E-14 0 Ag-110m 1.90E-14 100 Sb-124 2.40E-14 0 I-131 2.00E-14 0

, C;-134 1.60E-12 0 C:-136 5.30E-14 0 C -137 3.80E-14 0 Ba-140 6.70E-14 0 ,

Ce-141 4.70E-14 0 C -144 2.00E-13 100 Zn-65 5.90E-14 0 l- B -133 2.60E-14 100 Sb-125 1.80E-14 100 l:

Others: La-140 3.00E-14 I

i

DRESDEN NUCLEAR POWER STATION LFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY THROUGH JUNE 19 85 RADWASTE LIQUID EFFLUENTS

1. Number of Batch Releases: 107
2. Total Time Period for Batch Releases: 120,193 min
3. Maximum Time Period for a Batch Release: 6,051 min.
4. Average Time Period for Batch Releases: 1,123 min.
5. Minimum Time Period for a Batch Release: 5 min.
6. Average Stream Flow During Periods of Release of Effluent into a Flowing Stream: 4.04E05 Liters / min.

Docket Nos. 50-10, 50-237, 50-249 CONTINUOUS MODE BATCH MODE En1 h Relamand Unit 1st QUARTER 2nd QUARTER .t st QUARTER 2nd QUARTER Sr-89 Ci

  • 1.86E-03 1.85E-03 Sr-90 Ci 4.21E-03 7.00E-03 Ar-41 Ci
  • 2.32E-04 Mn-54 Ci 3.44E-03 7.31E-03 Co-58 Ci '

1.03E-04 2.73E-03 Fa-59 Ci 1.20E-04 5.53E-03 Co-60 Ci 3.78E-02 4.42E-01 Zn-65 Ci *

  • Ru-103 Ci
  • 1.04E-04 Sb-122 Ci
  • 1.18E-02 Sb-124 Ci
  • 2.04E-04 I-131 Ci 8.32E-04 1.65E-03 I-133 Ci
  • 4.0E-08 I-135 Ci
  • 2.3E-08 Cc-134 Ci 3.39E-03 8.51E-02 Cc-137 Ci 6.36E-02 1.19E00 Ba-140 C1 1.06E-05 1.68E-03 La-140 Ci 6.36E-04 3.59E-03 Ce-141 C1 4.60E-05 2.80E-03 Others; Cr-51 Ci 5.98E-04 2.29E-04 An-110m Ci
  • 1.05E-05 Ci Ci Total [ b Ci .NONE NONE 1.17E-01 1.79E00 Za-133 Ci
  • Za-135 Ci
  • 1.19E-04
  • See Table for MDL of Each Nuclide

DRESDEN NUCLEAR POWER STATION

\

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT '

JANUARY THROUGH JUNE 19 85 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES Docket Nos. 50-10, 50-237, 50-249 UNIT 1stQUARTER 2nd QUARTER L. FISSION AND ACTIVATION PRODUCTS 1- Total Release (not incl. evie4 ,pe,..ni g Ci 1.17E-01 1.79E00

2. Averace Diluend cnnc. nuvfng P vfna uCi/mi 3.93E-10 3.44E-09
3. Percent of Annifenhie Timfe  % * *
l. TRITIUM
1. Total Release Ci 3.14E00 3.61E00
2. Average Diluted Cone. Durine Period uCi/mi 1.21E-07 5.84E-08
3. Percent of Apolicable Limit  % *
  • DISSOLVED AND ENTRAINED GASES
1. Total Release Ci <MDL < MDL
2. Averse Diluted Conc. Durine Period uCi/mi < MDL < MDL
3. Percent of Applicable Limit  % * *

. GROSS ALPHA RADIOACTIVITY 1 Total Release Ci 6.74E-04 1.14E-03

, VOLUME OF WASTE RELEASED (orior to dilution) liters 3.93E+06 5.43E+06 i

VOLUME OF DILUTION VATER USED DURING PERI @ (RADWAKE) liters 2.58E+10 6.15E+10 l

J I

VO?.r" OF DTtHTIo'T tJATFn tw rrimr: pm7m (t 'rt ' 9 liters ' 2.49E+11 4.47E+11

)

( *Will be Included in the Annual Report on Envrrheni Radigartivity Data j

., . ~ _ . _. _. . . _

t e

. t 1

DRESDEN NUCLEAR POWER STATION Docket Nos. 50-10, TABLE OF MINIMUM DETECTABLE LEVELS 50-237, 50-249 FOR LIQUID EFFLUENTS RADWASTE LIQUID EFFLUENTS TOTAL GALLONS RELEASED 2.04E+06 MDL (uCi/ml)  % of Gallons <MDL Sr-89 4.00E-08 0 l

Sr-90 9.00E-09 0 Ar-41 3.07E-08 94 Mn-54 6.60E-08 0 Co-58 8.00E-08 0 Fe-59 1.10E-07 0 Co-60 1.70E-07 0 Zn-65 1.30E-07 , 100 Ru-103 5.39E-08 90 Sb-122 7.01E-08 86 Sb-124 4.06E-08 89 I-131 8.70E-08 0 I-133 5.34E-08 96 I-135 9.15E-08 95 Cs-134 7.20E-08 0 Cs-137 8.90E-08 0 Ea-140 2.09E-07 0 La-140 2.30E-08 0 Ce-141 1.10E-07 0 Xe-133 7.70E-08 100 i

Xe-135 7.90E-08 94 i,

f

- - - - = . - - . . . ~ , .

, _ _ - - . - - - - - , . . _ - - - - . <. -r.v__ . - - -, _ . , _ , --._

, DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY THROUGH JUNE 19 85 LPCI LIQUID EFFLUENTS

1. Number of Batch Releases: 100
2. Total Time Period for Batch Releases: 124 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: 2.67E06 liters / min.

Docket Nos. 50-237,C NT OUS MODE BATCH MODE Nuclides Released Unit 1st QUARTER 2nd QUARTER ist QUARTER 2nd QUARTER Sr-89

  • Ci 1.45E-05 2.63E-06 Sr-90 Ci *'
  • Ar-41 Ci *
  • Mn-54 Ci 2.29E-05 2.68E-05 C -58 Ci *
  • Fa-59 Ci *
  • Cc-60 Ci 1.15E-04 1.21E-04 _.

Zn-65 C1 *

  • Ru-103 Ci *
  • Sb-122 Ci *
  • Sb-124 Ci *
  • I-133 Ci *
  • I-135 Ci *
  • C :-134 C1 1.64E-06
  • Co.-137 Ci 1.32E-05 2.59E-05 Ba-140 Ci
  • La-140 Ci
  • Ce-141 Ci
  • Others: C1 C1 C1 C1 (above)

Total For Period Ci NONE NONE 1.68E-04 1.77E-04 Xe-133 Ci *

  • Ie-135 Ci * *
  • See Table for MDL of Each Nuclide

DRESDEN NUCLEAR POWER STATION TABLE OF MINIMUM DETECTABLE LEVELS FOR LIQUID EFFLUENTS Docket Nos. 50-237, 50-249 LPCI LIQUID EFFLUENTS TOTAL GALLONS RELEASED 4.34E+05 MDL (uC1/ml)  % of Gallons < MDL Sr-89 4.00E-08 0 Sr-90 9.00E-09 100 Ar-41 3.07E-08 100 Mn-54 6.60E-08 0 Co-58 8.00E-08 100 Fe-59 1.10E-07 100 Co-60 1.70E-07 0 Zn-65 1.30E-07 100 Ru-103 5.39E-08 100

^

Sb-122 7.01E-08 100 Sb-124 4.06E-08 100 I-131 8.70E-08 100 I-133 5.34E-08 100 I-135 9.15E-08 100 Cs-134 7.20E-08 92 Cs-137 8.90E-08 0 Ba-140 2.09E-07 100 La-140 2.30E-08 100 Ce-141 1.10E-07 100 Xe-133 7.70E-08 100 Xe-135 7.90E-08 100

r DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY THROUGH JUNE 19 85 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Docket Nos. 50-10, 50-237, 50-249 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)

1. Type of Waste Unit 6-month period m3 6.88E+02
a. Spent resins, filter s14a==, evaporator bottcmis, etc. Ci 1.30E+03 m3 5.65E+02
b. Dry compressible t.aste, contaminated equip. , etc. Ci 2.18E+01 m3
c. Irradiated ,--sts , control rods , etc. Ci m3
d. Other (deceribe) Ci
2. Estimate of Major Nuclide Composition (by type of waste)

% Ci

a. Co-60 52.8  % 6.86E+02 Fe-55 37.0  % 4.R1E+02 Mn-54 4.4  % 5.72E+01 Ce-137 3.I  % 4.01E+01 Other 2.7  % 3.51E+01
b. Co-60 64.0  % 1.40E+01 Fe-55 28.8  % 6.28E00 Mn-54 4.3  % 9.37E-01 Ce-137 2.8  % 6.10E-01 Other 0.1  % 2.18E-02
c. 2
d.  %
3. Solid Waste Disposition NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION 145 Motor Freight (Exclusive Use Only) Barnwell, S.C 46 Motor Freight (Exclusive Use Only) Richland, WA.
3. IRRADIATED FUEL SHIPMENTS (Disposition)

NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION NONE

r .-

]

DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY THROUGH JUNE 19 85 ABNORMAL RELEASES Docket Nos. 50-10, 50-237, 50-249 A. LIQUID

1. Number of Releases: 2
2. Total Activity Released: 6.38E-02 Ci*

B. GASEOUS

1. Number of Releases: 1
2. Total Activity Released: 3.40E-05 Ci**

9

  • This is the maximum estimated total. For further information, refer to Deviation Variance Reports #12-3-85-33 and 12-3-85-34.
    • This is the maximum estimated total. For further informationf refer to Deviation Variance Report #12-3-85-5.

J

r ,

e -

Commonwealth Edison

  • / '

Dresden Nuclear Power Sttlon g R.R. 01 N <

Morris, ll!inois 60450

'-s__-' Telephone 8'5/942-2920 l

August 15, 1985 DJS LTR: # 85-823 raIc11TY Rc"T!'1  !

Qte _

l no, '.L l Mr. James G. Keppler ~Q iTJ_

Regional Administrator i_._IJ-Directorate of Inspection and Enforcement 7  !> -

Region III U.S. Nuclear Regulatory Commission

[J[g) p

'] ~7"[ ~_

799 Roosevelt Road IILE Glen Ellyn, Illinois 60137

SUBJECT:

Dresden Station Operating Report, NRC Dockets 50-10, 50-237, and 50-249.

Dear Mr. Keppler:

Enclosed is the radioactive effluent report for January through June, 1985 for Dresden Nuclear Power Station.

One copy of this report is provided for your use and 39 copies are being submitted directly to Mr. D. Eisenhut, Deputy Director of the Office of Nuclear Reactor Regulation.

Sincerely.

(y*^

D.J. Scott Station Manager Dresden Nuclear Power Station DJS:RB:sp Euclosure s cc: R. Berg fI J.C. Golden AUG 301985 File /NRC File / Numerical 2

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