ML20204F244

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Effluent & Waste Disposal Semiannual Rept,Jul-Dec 1986
ML20204F244
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 12/31/1986
From: Eenigenburg E
COMMONWEALTH EDISON CO.
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
87-078, 87-78, NUDOCS 8703260159
Download: ML20204F244 (16)
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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 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 arialyzed -

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-1 and the 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(L1) 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.S.r-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) spect-rometry 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 a

8703260159 PDR R

861231 ADOCK 05000010 pon jf

4 DRESDEN NUCLEAR POWER STATION UFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY Through DECEMBER 19 86 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES DOCKET NOS. 50-10, 50-237, 50-249 I UNIT 3rd QUARTER 4th QUARTER A. FISSION AND ACTIVATION CASES

1. Total Release Ci 1.10E+02 3.21E+02
2. Averare Release Rate for Perind uCi/see 1.38E+01 4.04E+01
3. Percent of Technical Snecificneinn T.4 mi r  % *
1. Total Iodine-131 -

C1 2.64E-03 7.31E-03

2. Average Release Rate for Period uCi/sec 3.32E 9.20E-04
3. Percent of Technical Soecification Limit  % *
  • C. PARTICULATES
1. Particulates with half-liv.= SA d=ve Ci 1.71E-02 1.34E-02
2. Average Release Rate for Period uCi/sec 2.15E-03 1.69E-03
3. Percent of Technical Specification Limit I * *
4. Gross Alpha Radioactivity Ci 4.43E-06 2.03E-06 D. TRITIUM
1. Total Release Ci 2.53E 00 5.01E 00
2. Average Release Rate for Period uCi/sec 3.18E-01 6.30E-01
3. Percent of Technical Specification Litrit  % * *
  • WILL BE INCLUDED IN THE ANNUAL REPORT ON ENVIRONMENTAL RADIOACTIVITY DATA PAGE 2 0F 15
  • DRESDEN NUCLEAR POWER STATION UNIT 1
  • EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

, , Jay THROUGH DECEMBER 19 86

! D-l CilIMNEY CASEOUS EFFLUENTS GROUND LEVEL RELEASES SEMI-ELEVATED RELEASES XX ELEVATED RELEASES DOCKET NO. 50-10 CONTINUOUS MODE BATCH MODE

'UCLIDES RELEASED UNIT 3rd QUARTER _4thQUARTER 3rd QUARTER 4th QUARTER

. FISSION GASES Ci Xe-138 Ci *

  • Xm-135m Ci *
  • Kr-87 Ci *
  • Kr-88 Ci *
  • Kr-85m Ci *
  • Xe-135 Ci *
  • Xe-133 Ci *
  • Others Ke-133m Ci *
  • Ci TOTAL Ci NONE NONE

. 10 DINES I-131 Ci *

  • I-133 Ci *
  • I-135 Ci
  • TOTAL Ci NONE NONE

. PARTICULATES Sr-89 Ci *

  • Cr-51 Ci *
  • Mn-54 Ci 4.76 E-08 Co-58 *
  • Ci Fe-59 Ci
  • Co-60 Ci 2.43 E-06 1.67 E-05 Zr-95 Ci *
  • Nb-95 Ci *
  • Ru-103 Ci *
  • An-110m Ci
  • Sb-124 Ci
  • Cs-136 Ci
  • Cs-137 C1 3.54 E-06 1.74 E-05 Ba-140 Ci *
  • Ce-141 Ci *
  • Ce-144 Ci Zn-65 Ci *
  • Ba-133 Ci *
  • Sb-125 Ci *
  • Ci Ci C1 Ci TOTAL Ci 5.97 E-06 3.41 E-05 NONE NONE
  • See Table for MDL of Each Nuclide j PAGE 3 of 15

DRESDEN NUCLEAR POWER STATION JULY THROUGH DECEMBER 1986 TABLE OF MINIMUM DETECTABLE LEVELS FOR GASEOUS EFFLUENTS D-1 CHIMNEY GASEOUS EFFLUENTS AVERAGE FLOW 50.000 CFM DOCKET NO. 50-10 MDL (uCi/cc)  % OF TIME < MDL

1. FISSION GASES Ke-138 5.08 E-08 100 Xe-135m 2.14 E-08 100 Kr-87 3.43 E-08 100 Kr-88 6.14 E-08 100 .

Kr-85m 1.86 E-08 100 Kr-85 4.58 E-06 100 Xe-135 1.80 E-08 100 Xe-133 4.42 E-08 100 Others: Xe-133m 1.56 E-07 100

2. IODINES i

I-131 3.12 E-14 100 I-133 3.13 E-14 100 I -135 6.39 E-14 100

3. PARTICULATES Sr-89 1.00 E-15 100 Sr-90 1.00 E-15 100 Cr-51 2.29 E-13 100 Mn-54 2.78 E-14 92 Co-58 2.62 E-14 100 Fe-59 4.33 E-14 100 Co-60 6.39 E-14 27 Zr-95 4.86 E-14 100 Nb-95 2.61 E-14 100 Ru-103 2.71 E-14 100

' Ag-110m 2.74 E-14 100 Sb-124 1.96 E-14 100 I-131 2.88 E-14 100 Cs-134 3.12 E-14 100 Cs-136 3.14 E-14 100 Cs-137 3.37 E-14 18 Ba-140 1.08 E-13 100 Ce-141 3.69 E-14 100 Ce-144 1.52 E-13 100 i

Zn-65 4.44 E-14 100 l 2.60 E-14 100 Ba-133 Sb-125 7.78 E-14 100 .

I 2.16 E-13 100

! Others: Mo-99 La-140 1.25 E-14 100 i

PAGE 4 of 15

  • DRESDEN NUCLEAR POWER STATION UNIT 2/3
  • EFFLUENT AND UASTE DISPOSAL SEMIANNUAL REPORT

, , JULY THROUGH DECEMBER 19 86

'~

2/3 CHIMNEY GASEOUS EFFLUENTS GROUND LEVEL RELEASES SEMI-ELEVATED RELEASES XX ELEVATED RELEASES DOCKET N0s. 50-237, 50-249 CONTINUOUS MODE BATCH MODE JUCLIDES RELEASED UNIT 3rcQUARTER 4thQUARTER 3rd QUARTER 4th QUARTER

. FISSION GASES Ci Xe-138 C1 4.56 E + 01 7.87 E + 01 Xe-135m Ci 1.35 E + 01 1.74 E + 01 Kr-87 Ci 7.69 E 00 1.80 E + 01 Kr-88 Ci 7.43 E 00 2.45 E + 01 Kr-85m Ci 5.88 E 00 9.08 E 00 Kr-85 Ci 4.51 E-03 1.04 E - 02 Xe-135 C1 2.43 E +01 1.43 E + 02 Xe-133 Ci 2.}4 E 00 2.00 E + 01 Others:Xe-133n Ci *

  • Ci TOTAL Ci 1.07 E + 02 3.11 E + 02 NONE NONE

. IODINES I-131 Ci 2.37 E - 03 6.66 E - 03 I-133 Ci 1.56 E - 02 3.10 E - 02 I-135 Ci 2.39 E - 02 5.12 E - 02 TOTAL Ci 4.19 E - 02 8.89 E - 02 NONE NONE

. PARTICULATES Sr-89 Ci 4.03 E - 04 1.10 E - 03 Sr-90 Ci 4.42 E - 06 2.53 E - 05 Cr-51 Ci *

  • Mn-54 Ci 1.01 E - 04 1.44 E - 04 Co-58 Ci *
  • Fe-59 Ci *
  • Co-60 Ci 4.14 E - 04 5.59 E - 04 Zr-95 Ci *
  • Nb-95 Ci *
  • i Ru-103 Ci *
  • An-110m Ci *
  • Sb-124 Ci *
  • I-131 C1 1.82 E - 04 8.19 E - 04 Cs-134 Ci *
  • Cs-136 *
  • Ci Cs-137 C1 3.57 E - 05 1.08 E - 04 i Ba-140 Ci 2.24 E - 03 5.07 E - 03 Ce-141 Ci 8.39 E - 06 8.56 E - 05 Ce-144 Ci *
  • Zn-65 Ci *
  • Ba-133 Ci *
  • Sb-125 *
  • Ci i

Ci C1 Ci TOTAL Ci 3.39 E - 03 7.91 E - 03 l NONE NONE

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

9 DRESDEN NUCLEAR POWER STATION JULY THROUGH DECEMBER 1986 TABLE OF MINIMUM DETECTABLE LEVELS FOR GASEOUS EFFLUENTS 3rd QUARTER: 253 KCFM 2/3 CHIMNEY GASEOUS EFFLUENTS AVERAGE FLOW 4th QUARTER: 280 KCFM DOCKET N0s. 50-237, 50-249 MDL (uCi/cc)  % OF TIME < MDL

1. FISSION CASES l Xe-138 1.72 E-07 83 l Xe-135m 7.55 E-08 90 Kr-87 4.43 E-08 95 Kr-88 8.85 E-08 96 Kr-85m 2.73 E-08 88 Kr-85 7.06 E-06 0 Xe-135 2.72 E-08 40 Xe-133 6.19 E-08 90 Others: Xe-133m 2.30 E-07 100 ,
2. IODINES I-131 3.12 E-14 0 I-133 3.13 E-14 0 1-135 6.39 E-14 21
3. PARTICULATES Sr-89 1.00 E-15 0 Sr-90 1.00 E-15 0 Cr-51 2.29 E-13 100 Mn-54 '2.78 E-14 9 Co-58 2.62 E-14 100 Fe-59 4.33 E-14 100 Co-60 6.39 E-14 0 Zr-95 4.86 E-14 100 Nb-95 2.61 E-14 100 Ru-103 2.71 E-14 100 Ag-110m 2.74 E-14 100 Sb-124 1.96 E-14 100 1-131 2.88 E-14 4 Cs-134 3.12 E-14 100~-

Cs-136 3.14 E-14 100 Cs-137 3.37 E-14 9 Ba-140 1.08 E-13 3 Ce-141 3.69 E-14 57-Ce-144 1.52 E-13 100 Zn-65 4.44 E-14 100 Ba-133 2.60 E-14 100 Sb-125 7.78 E-14 100 l Others: Mo-99 2.16 E-13 100 La-140 1.25 E-14 100 DETECTED, BUT NOT REPORTED PAGE 6 of 15

' DRESDEN NUCLEAR POWER STATION UNIT 2/3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

, , JULY THROUGH DECEMBER 19 86 2/3 VENT GASEOUS EFFLUENTS GROUND LEVEL RELEASES XX SEMI-ELEVATED RELEASES ELEVATED RELEASES

~ DOCKET NOS. 50-237, 50-249 CONTINUOUS MODE RATCH MonE 14UCLIDES RELEASED UNIT 3rd QUARTER 4th QUARTER 3rdQUARTER 4th QUARTER

.. FISSION GASES Ci Xe-138 Ci *

  • Xe-135e ci *
  • Kr-87 Ci *
  • Kr-88 Ci *
  • Kr-85m C1 *
  • Xe-135 Ci 2.88 E 00 9.92 E 00 Xe-133 Ci *
  • Others:Xe-133n t Ci *
  • Ci TOTAL Ci 2.88 E 00 9.92 E 00 NONE NONE ,

'. 10 DINES i I-131 Ci 2.69 E - 04 6.52 E - 04 l I-133 Ci 2.02 E - 03 5.53 E - 03 I-135 Ci Z.53 E - 03 1.12 E - 02 TOTAL Ci 5.12 E - 03 1.74 E - 01 NONE NONE

t. PARTICULATES Sr-89 Ci 3.19 E - 05 2.02 E - 05 Sr-90 Ci 3.10 E - 06 2.33 E - 06 Cr-51 Ci 1.54 E - 03 1.56 E - 04 Mn-54 Ci 1.14 E - 03 4.47 E - 04

-Co-58 Ci 6.51 E - 04 1.50 E - 04 t

Fa-59 Ci 5.22 E - 04 7.63 E - 05 Co-60 Ci 5.89 E - 03 2.87 E - 03 Zr-95 Ci *

  • Nb-95 C1 *
  • Ru-103 Ci *
  • Aa-110m Ci 1.84 E - 04 9.10 E - 06 Sh-124 C1 3.82 E - 05 3.80 E - 06 I-131 Ci 7.51 E - 05 2.00 E - 04 Cs-134 Ci *
  • Cs-136 Ci 2.60 E - 05
  • Cs-137 C1 4.48 E - 05 2.86 E - 05 Ba-140 Ci 6.74 E - 04 2.19 E - 04 Ce-141 Ci 6.02 E - 06 1.47 E - 06 Ce-144 Ci 2.44 E - 05
  • Zn-65 C1 2.27 E - 04 4.52 E - 05 Ba-133 Ci *
  • Sh-125 Ci *
  • Othars:Mo-99 Ci 2.67 E - 03 1.20 E - 03 C1 Ci C1 Ci TOTAL Ci 1.37 E - 02 5.43 E - 03 NONE NONE
  • See Table for MDL of Each Nuclide PAGE 7 of 15

DRESDEN NUCLEAR POWER STATION JULY THROUGH DECEMBER 1986 TABLE OF MINIMUM DETECTABLE LEVELS FOR CASEOUS EFFLUENTS D-2: 110 K CFM 2/3 VENT GASEOUS EFFLUENTS AVERAGE FLOW D-3: 110 K CFM DOCKET Nos. 50-237, 50-249 MDL (uCi/cc)  % OF TIME < MDL

1. FISSION GASES Xe-138 5.08 E-08 100 Xe-135m 2.14 E-08 100 Kr-87 3.43 E-08 100 Kr-88 6.14 E-08 100 Kr-85m 1.86 E-08 100 Kr-85 4.58 E-06 100 Xe-135 1.80 E-08 49 Xe-133 4.42 E-08 100 Others: Xe-133m 1.56 E-07 100
2. 10 DINES I-131 3.12 E-14 4 I-133 3.13 E-14 4 I-135 6.39 E-14 18
3. PARTICULATES Sr-89 1.00 E-15 0 Sr-90 1.00 E-15 0 Cr-51 2.29 E-13 18 Mn-54 2.78 E-14 0 Co-58 2.62 E-14 2 Fe-59 4.33 E-14 9 Co-60 6.39 E-14 o Zr-95 4.86 E-14 100 Nb-95 2.61 E-14 100 Ru-103 2.71 E-14 100 Ag-110m 2.74 E-14 58 Sb-124 1.96 E-14 53 I-131 2.88 E-14 13 Cs-134 3.12 E-14 100--

Cs-136 3.14 E-14 85 Cs-137 3.37 E-14 8 Ba-140 1.08 E-13 0 Ce-141 3.69 E-14 89 -

Ce-144 1.52 E-13 92 Zn-65 4.44 E-14 50 Ba-133 2.60 E-14 100 Sb-125 7.78 E-14 100 2.16 E-13 11 Others: Mo-99 _

La-140 DETECTED, BUT NOT REPORTED PAGE 8 of 15

DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY THROUGH DECEMBER 19 86 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES DOCKET NOS. 50-10, 50-237, 50-249 UNIT 3rdQUARTER 4th QUARIER L FISSION AND ACTIVATION PRODUCTR

1. Total Release (not inct. evief m-gneo=.21nh, Ci 1.05E-01 9.60E-02 2- Averane Diluted Cone. nnring p,v<na uCi/mi 2.83E-10 3.82E-09 ,
3. Percent of Ano14 cable Limir  % * *
3. TRITIUM
1. Total Release Ci 5.64E00 6.05E00
2. Average Diluted Cone. During Period uCi/ml 1.52E-08 2.41E-07
3. Percent of Applicable Limit  % * *

'. DISSOLVED AND ENTRAINED GASES

1. Total Release Ci 1.79E-03 9.52E-03
2. Averge Diluted Conc. Durine Period uCi/ml 4.82E-12 3.79E-10
3. Percent of Applicable Limit  % * *

.....~-

GROSS ALPHA RADIOACTIVITY 1 Total Release C1 2.90E-05 4.64E-05 VOLUME OF WASTE RELEASED (orior to dilution) liters 7.23E+06 8.41E+06 VOLUME OF DILUTION WATER USED DURING PERIm  ;

liters 3.71E+11 2.51E+10

  • WILL BE INCLUDED'IN THE ANNUAL REPORT ON ENVIRONMENTAL RADIOACTIVITY DATA PAGE 9 of 15

DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY THROUGH DECEMBER 19 86 RADWASTE LIQUID EFFLUENTS

1. Number of Batch Releases: 162
2. Total Time Period for Batch Releases: 49165 min
3. Maximum Time Period for a Batch Release: >

555 min-

4. Average Time Period for Batch Releases: 303 min
5. Minimum Time Period for a Batch Release: 7 min
6. Average Stream Flow During Periods of Release of Effluent into a Flowing Stream: 1.89E+05 Liters / Min DOCKET NOS. 50-10, 50-237, 50-249 CONTINUOUS MODE BATCH MODE Isulid.= Relemaad Unit 3rd QUARTER 4th QUARTER 3rd QUARTER 4th QUARTER Sr-89 Ci *
  • Sr-90 Ci 9.93 E - 05 8.77 E - 05 Ar-41 Ci 4.75 E - 05 * -

Mn-54 C1 1.75 E - 02 8.16 E - 03 C -58 Ci 4.30 E - 04 1.87 E - 04 L

Fa-59 Ci 7.19 E - 04

  • Co-60 Ci 6.43 E - 02 7.29 * - 02

'- Zn-65 C1 1.74 E - 04

  • Ru-103 Ci * ,
Sb-122 Ci 3.72 E *

.Sb-124 Ci *

  • I-131 Ci 2.84 E - 04 8.56 E - 05 I-133 C1 1.03 E - 03 *

, - I-135 Ci 1.90 E - 04

  • Cs-134 Ci 1.05 E - 04 1.44 E - 04
Cs-137 Ci 1.22 E - 02 1.38 E - 02 Ba-140 Ci *
  • La-140 C1 2.56 E - 04
  • l Ce-141 Ci . . . . ~ * *
Others
Cr-51 Ci 1.64 E - 03 5.81 E - 05 1

i Mo-99 Ci 2.21 E - 03 *

, Tc-99m Ci 1.16 E - 03

[ Total o Period Ci NONE NONE 1.03 E - 01 9.54 E -02 j Xe-133 Ci 8.21 E - 04 7.19 E - 03

'Xe-135 Ci 9.65 E - 04 2.33 E - 03

  • See Table for MDL of Each Nuclide PAGE 10 of 15

DRESDEN NUCLEAR POWER STATION JULY THROUGH DECEMBER 1986 TABLE OF MINIMUM DETECTABLE LEVELS FOR LIQUID EFFLUENTS DOCKET NOS. 50-10, 50-237, 50-249 RADWASTE LIQUID EFFLUENTS TOTAL GALLONS RELEASED 3.57 E+06 MDL (uCi/ml)  % of Gallons < MDL Fe-55 7.00 E-07 100 Sr-89 4.00 E-09 100 Sr-90 2.00 E-09 0 -

~

Ar-41 3.07 E-08 98 M Mn-54 6.06 E-08 4 l

)

Co-58 6.77 E-08 95 Fe-59 8.90 E-08 94

  • Co-60 1.35 E-07 I Zn-65 1.10 E-07 99 Ru-103 5.39 E-08 100 Sb-122 7.01 E-08 99 Sb-124 4.06 E-08 100 I-131 7.42 E-08 93 I-133 5.34 E-08 99 I-135 9.15 E-08 99 Cs-134 6.32 E-08 90 Cs-137 8.90 E-08 I Ba-140 2.09 E-07 100 La-140 2.30 E-08 97 Ce-141 1.00 E-07 100 Xe-133 7.70 E-08 76 Xe-135 6.26 E-08 71 Xe-138 1.89 E-07 100 ,,

Xe-133m 5.78 E-07 100 Mo-99 4.92 E-07 99 Kr-87 1.31 E-07 100 .

Kr-88 2.23 E-07 100 Cr-51 6.20 E-07 96 Ce-144 4.05 E-07 100 Tc-99m 5.32 E-08 97 PAGE 11 of 15

~

DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY THROUGH DECEMBER 19 86 LPCI LIQUID EFFLUENTS

1. Number of Batch Releases: 130
2. Total Time Period for Batch Releases: 161 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 Durir.g Periods of Release of Effluent into a Flowing Stream: 1.89E+05 liters / min DOCKET NOS. 50-237, 50-249 CONTINUOUS MODE BATCH MODE Nuclides Released Unit 3rd QUARTER 4th QUARTER 3rd QUARTER 4th QUARTER Sr-89 Ci *
  • 1.93 E - 06 Ar-41 Ci *
  • Mn-54 C1 2.79 E - 04 1.32 E - 04 C:-58 Ci 4.30 E - 06 8.64 E - 06 Fa-59 Ci 2.96 E - 06
  • Cc-60 Ci 1.27 E - 03 4.51 E - 04 Zn-65 Ci *
  • Ru-103 Ci *
  • Sb-122 Ci *
  • Sb-124 Ci
  • 2.00 E - 08

.I-131 Ci *

  • I-133 Ci *
  • I-135 Ci *
  • C_-134 Ci *
  • Cc-137 C1 2.88 E - 05 2.40 E - 05 Ba-140 Ci *
  • La-140 Ci *
  • Ce-141 Ci . _~ *
  • Others: Cr-51 Ci 2.10 E - 07
  • t Ci -

C1 above)

Total (For Period Ci NONE NONE 1.59 E - 03 6.18 E - 04 l Xe-133 Ci Xe-135 Ci

  • See Table for MDL of Each Nuclide PAGE 12 of 15

i

. .\,

l U TH E R TABLE OF MINIMUM DETECTABLE LEVELS FOR LIQUID EFFLUENTS DOCKET NOS. 50-237, 50-249 LPCI LIQUID EFFLUENTS TOTAL GALLONS RELEASED 5.64 E+05 MDL (uCi/ml)  % of Callons < MDL Fe-55 7.00 E-07 83 Sr-89 4.00 E-09 100 Sr-90 2.00 E-09 83 Ar-41 3.07 E-08 100 Mn-54 1.90 E-07 21 Co-58 1.93 E-07 91 Fe-59 2.84 E-07 82 -

Co-60 4.05 E-07 0 Zn-65 2.94 E-07 100 Ru-103 5.39 E-08 100 Sb-122 7.01 E-08 100 Sb-124 4.06 E-08 94 I-131 2.39 E-07 100 I-133 5.34 E-08 100 I-135 9.15 E-08 100 Cs-134 2.01 E-07 100 Cs-137 2.47 E-07 28 Ba-140 2.09 E-07 100 La-140 2.30 E-08 100 Ce-141 3.85 E-07 100 Xe-133 7.70 E-08 100 Xe-135 2.27 E-07 100 Xe-138 6.38 E-07 100 Xe-133m 1.99 E-06 100 Mo-99 1.53 E-06 100 j_

Kr-87 3.86 E-07 100 -

Kr-88 7.90 E-07 100 Cr-51 2.03 E-06 94 l Ce-144 1.59 E-06 100 l.

PAGE 13 of 15 l

l

1 DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY THROUGH DECEMBER 19 86 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS DOCKET NOS. 50-10, 50-237, 50-249 A. I SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) l l

1. Type of Waste Unit 6-month period m3 7.94 E + O2
a. Spent resins, filter sidm, evaporator bottcas, etc. Ci 2.23 E + 03 m3 4.24 E + O2
b. Dry conpressible mste, contanin1ted equip. , etc. Ci 7.12 E 00 m3 6.27 E - 01
c. Irradiated 6 , -.ents, control rods, etc. Ci 1.15 E + 04 m3
d. Other (describe) Ci
2. Estimate of Major Nuclide Composition (by type of waste)

% Ci

a. Co-60 52.8  % 1.18E+03 Fe-55 37.0  % 8.25E+02 Mn-54 4.4  % 9.81E+01 Cs-137 3.I  % 6.91E+01 OTHER 2.7  % 6.02E+01
b. Co-60 64.0  % 4.56 E 00 Fe-55 28.8  % 2.05 E 00 Mn-54 4.3  % 3.06E-01 Cs-137 2.8  % 1.99E-01 OTHER 0.1  % 7.12E-03
c. Co-60 52.3  % 6.011.+03 Fe-55 41.2  % 4.74E+03 Ni-59 0.1  % 1.ISE+01 Ni-63 6.3  % 7.25E+02 OTHER 0.1  % 1.15E+01 i
d.  %

l 3. Solid Waste Disposition l NUMBER OF SHIPMENTS MODE OF TRANSPORTATION _ DESTINATION 118 MOTOR FREIGHT (EXCLUSIVE USE ONLY) BARNWELL, S.C.

18 MOTOR FREIGHT (EXCLUSIVE USE ONLY) RICHLAND, WA.

22 MOTOR FREIGHT (EXCLUSIVE USE ONLY) BEATTY, NV.

~

B. IRRADIATED FUEL SHIPMENTS (Disposition)

NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION NONE -- --

I PAGE 14 of 15 i

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DRESDEN NUCLEAR POWER STATION l

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY 1

?

THROUGH DECEMBER 191 '

ABNORMAL RELEASES DOCKET NOS. 50-10, 50-237, 50-249 -

A. LIQUID

1. Number of Releases: 0
2. Total Activity Released: 0 B. GASEOUS
1. Number of Releases: 0
2. Total Activity Released: 0 4

..... ~

PAGE 15 of 15

v -

]

M6 Commonwealth Edison Dr:sden Nuclear P wer St: tion )

-o R.R. # f

  • Morris, Illinois 60450 Telephone 815/942-2920 Februa g First RA %gg S

i DPA (IC EDE LTR: # 87-078 yLLN)5 h k" OL OPMA '01 PA0 Mr. James G. Keppler Regional Administrator FILE g f

' Directorate of Inspection and Enforcement Region III U.S. Nuclear Regulatory Commision 799 Roosevelt Road 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 July through December, 1986 for Dresden Nuclear Power Station.

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

Sincerely.

M.bbh E.D. Eenigenburg p

Station Manager Dresden Nuclear Power Station EDE:RB:jm Enclosure cc: R. Berg J.C. Golden File /NRC

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File / Numerical /'

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