ML20234D760

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Effluent & Waste Disposal Semiannual Rept for Jan-June 1987
ML20234D760
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 06/30/1987
From: Eenigenburg E
COMMONWEALTH EDISON CO.
To:
References
87-495, NUDOCS 8709220184
Download: ML20234D760 (16)
v • d • e


Text

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DRESDEN NUCLEAR POWER STATION DOCKET NOS. 50-10, 50-237, 50-249 l

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. The Tritum is collected via a continuous sample on the D2/3 chimney and via a grab sanple 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 an.! 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 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'speci-fic isotopes present in the release 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.

8709220184 870630 PDR ADOCK 05000010 R PDR PAGE 1 0F 15 h i 1

_ _ _ _ _ _ - _ - _ - - _ - _ - _-- 1

9 .

DRESDEN NUCLEAR POWER STATION .

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY Through JUNE 19 87 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES DOCKET N0s. 50-10, 50-237, 50-249 UNIT ist QUARTER 2nd QUARTER A. FISSION AND ACTIVATION CASES .

1. Total Release C1 1.12 E+02 1.57 E+02
2. Averane Release Rate for Perina uC1/see 1.44 E+01 2.00 E+01
3. Percent of Technical Snecifienrinn Timie  % *
  • B. 10 DINES
1. Total Iodine-131 Ci 4.61 E-03 3.41 E-03
2. Average Release,3 ate for Period uCi/sec 5.93 E-04 4.34 E-04
3. Perl.mi,et Technical Specification Limit  % *
  • c C. PARTICULATE ,,
1. Parti ulates with half-livan % anya Ci 8.87 E-03 1.23 E-02
2. Average Release Rate for Period uCi/sec 1.14 E-03 1.56 E-03 >
3. Percent of Technical Specification Limit  % * * '.
4. Gross Alpha Radioactivity C1 1.20 E-05 5.79 E-06 D. TRITIUM
1. Total Release C1 2.18 E00 4.62 E 00
2. -

Average Release Rate for Period uCi/sec 2.80 E-01 5.88 E-01

3. Percent of Technical Specification Limit  % * *
  • WILL BE INCLUDED IN THE ANNUAL REPORT ON ENVIRONMENTAL RADIOACTIVITY DATA PAGE 2 0F 15 m__.__ . . _ _ . _ _ - _ _ _ - . - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ - _ _ _ _ _ _ _ _ - - _ - _ _ _ - _ _ _ _ _ - _ . _ _ _ . . _ ._ _ _ _ _ _ _ _ _ ._ ._.--.___..________.______..______________m__.__._-

L EFFLUEET AND WASTE DISPOS U5EMkA UU L REPORT JANUARY THROUGH JUNE 1987 D-1 CHIMNEY GASEOUS EFFLUENTS i

GROUND LEVEL RELEASES SEMI-ELEVATED RELEASES XX ELEVATED RELEASES DOCKET NO. 50-10 JOUS MODE v nr

'UCLIDES RELEASED UNIT 1stQUARTER 2nd QUARTER 1stQUARTER 2nd QUARTER

. FISSION GASES Ci Xe-138 Ci *

  • Xe-135m Ci .

Kr-87 C1 Kr-88 Ci *

  • Kr-85m Ci Kr-85 C1 Xe-ISE C1 Xe-133 Ci Others: Xel33m Ci CL TOTAL A NONE NONE

. 10 DINES I-131 Ci

___.1- ll3____________C_i__

I-IS$ Ci ,

TOTAL Ci NONE _ NONE u PARTICULATE

-89 Ci * *

~

or-90 Ci *

  • Cr-51 *
  • Ci 6.89 E - Of

~

Mn-54 C1 2.43 E-07 Co-58 Ci *

  • Fe-59 Qi _______,_____

Co-60 Ci 7 69 F - 07 3,87 E-06 Zr-95 Ci *

  • Nb-95 C1 Ru-103 Ci *
  • An-110m Ci Sb-124 C1 I-131 *
  • Ci I Cs-134 Ci * *

~

Cs-136 Ci *

  • Cs-137 C1 2.58 E - 06 3.26 E-06 Ba-140 C1 Ce-141 C1 Ce-144 CJ Zn-65 Ci Ba-133 C1 Sb-125 *
  • __ Ci .

_.__O_thersigq g,g____,C, i _ *

  • Ci Ci . , _ ,

- C1

~ TOTAL C1 4.04 E - 06 7.37 E-06 NONE NONE

  • See Table for MDL of Each Nuclide PAGE 3 0F 15 u_____________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

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DRESDEN NUCLEAR POWER STATION JANUAnY THROUGH JUNE 1987 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 cl. FISSION GASES Xe-138 4.63 E-08 100 Xe-135m 1.98 E-08 100 Kr-87 3.31 E-08 100. .

Kr-88 5.50 E-08 100 Kr-85m 1,67 E-08 100 Kr-85 4.08 E-06 100 1 Xe-135 1.69 E-08 100 l Xe-133 4.18 E-08 100 1.49 E-07 100 Others :Xe-133m

2. 10 DINES 0

I-131 3.26 E-14 0

I-133 2.89 E-14 100 I-135 5.73 E-14 3.. PARTICULATE Sr-89 1.00 E-15 100 Sr-90 1.00 E-15 100

'Cr-51 2.21 E-13 100 Mn-54 2.54 E-14 86 i Co-58 2.53 E-14 100 Fe-59 3.89 E-14 100 -]

Co-60 6.21 E-14 47 j Zr-95 4.49 E-14 100 1 2.48 E-14 100 Nb-95 2.59 E-14 100 l q

Ru-103 2.72 E-14 100 i I

  • 1.85 E-14 100 l I-131 2.76 E-14 100 Cs-134 3.02 E-14 100 Cs-136 2.95 E-14 g ]

Cs-137 3.05 E-14 100 l Ba-140 1.02 E-13 '

100 Ce-141 3.59 E-14 100 Cc-144 1.50 E-13 i 100 Zn-65 4.39 E-14 100 Ba-133 3.56 E-14 100 -

l Sb-125 7.57 E-14 2.0", E-13 100 Others: Mo-99 100 -

La-140 9.36 E-15 .

PAGE 4 0F 15

____________D

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY THROUGH JUNE 1987 D-2/3 CHIMNEY GASEOUS EFFLUENTS **

GROUND LEVEL RELEASES SEMI-ELEVATED RELEASES XX ELEVATED RELEASES DOCKET NOS. 50-237, 50-249 CONTINUOUS MODE BATCH MODE

'UCLIDES RELEASED UNIT -

1st QUARTER 2ndQUARTER- 1st QUARTER 2ndQUARTER

. FISSION GASES Ci Xe-138 C1 3.81 E + 01 4.10 E + 01 X,-135m C1 3.03 E 00 1.27 F + 01 Xr-87 C1 4.32 E - 01 1.81 E 00 Kr-88 C1 2.42 E 00 6.83 E 00 Kr-85m Ci 3.03 E 00 6.82 E 00 Kr-85 Ci 7.40 E - 03 8.95 E - 03 Xe-135 Ci 5.68 E + 01 7.05 E + 01 Xe-133 C1 2.94 E 00 1.15 E + 01 Others :Xe-133m Ci *

  • Ci TOTAL C1 1.07 E + O2 1.51 E + O2 NONE NONE

. I0 DINES I-131 C1 4.07 E - 03 2.22 E - 03 I-133 Ci 1.90 E - 02 1.16 E - 02 I-135 C1 2.87 E - 02 1.86 E - 02 TOTAL Ci 5.18 E - 02 3.24 E - 02 NONE NONE m PARTICULATE _

-89 C1 4.38 E - 04 4.59 E - 04

.ar-90 _

Ci 7.68 E - 06 1.12 E - 05 Cr-51 Ci *

  • Mn-54 C1 4.89 E - 05 4.36 E - 05 Co-58 Ci *
  • Fe-59 Ci *
  • Co-60 Ci 1.70 E - 04 1.33 E - 04 Zr-95 Ci *
  • Nb-95 Ci
  • Ru-103 Ci *
  • Ac-110m Ci *
  • Sb-124 Ci *
  • I-131 Ci 9.58 E - 04 9.62 E - 05 Cs-134 Ci *
  • Cs-136 Ci *
  • 4 Cs-137 C1 6.15 E - 05 2.66 E - 05 Ba-140 C1 4.41 E - 03 1.96 E - 03 Ce-141 C1 9.37 E - 05
  • Ce-144 Ci *
  • Zn-65 Ci Ba-133 Ci *
  • Sb-125 Ci Others : Mo-99 Ci 1.53 E - 05
  • C1 Ci C1 s C1 TOTAL C1 6.20 E - 03 2.73 E - 03 NONE NONE
  • See Tabic for MDL of Each Nuclide
    • The particulate sample f11ter from the week of 02 June 87 was found damaged and, therefore, not representative. Particulate release for that week has been calculated as the average of the previous and following week's sample.

Page 5 of 15 _ _ _ _

DRESDEN NUCLEAR POWER STATION JANUARY THROUGH JUNE 1987 TABLE OF MINIMUM DETECTABLE LEVELS FOR GASEOUS EFFLUENTS 1st QUARTER: 277 KCFM i D-2/3 CHIMNEY GASEOUS EFFLUENTS AVERAGE FLOW 2ND QUARTER:- 284 KCFM DOCKET NOS. 50-237, 50-249 MDL (uCi/cc)  % OF TIME < MDL

'1. . FISSION GASES Xe-138 1.55 E-07 81 Xe-135m 6.43 E-08 94 Kr-87 4.85 E-08 97 Kr-88 7.97 E-08 93 Kr-85m 2.27 E-08 89 Kr-85 5.91 E-06 0 Xe-135 2.31 E-08 13 Xe-133 5.80 E-08 91 Others: Xe-133m 2.04 E-07 100

2. 10 DINES 1'

1-131 3.26 E-14 0-I-133 2.89 E-14 12 I-135 5.73 E-14 19

, 3. PARTICULATE Sr-89 1.00 E-15 0 Sr-90 1.00 E-15 0 Cr-51 2.21 E-13 100 Mn-54 2.54 E-14 27 Co-58 2.53 E-14 100 Fe-59 3.89 E-14 100 Co-60 6.21 E-14 3 2r-95 4.49 E-14 100 Nb-95 2.48 E-14 100 Ru-103 2.59 E-14 100 Ag-110m 2.72 E-14 100 Sb-124 1.85 E-14 100 2,76 E-14 22 i .I-131 l Cs-134 3.02 E-14 100 Cs-136 2.95 E-14 100 Cs-137 3.05 E-14 3 l ,

Ba-140 1.02 E-13 11 i 3.59 E-14 70 )

Ce-141 Ce-144 1.50 E-13 100 Zn-65 4.39 E-14 100 y Ba-133 3.56 E-14 100 j 7.57 E-14 100 -

Sb-125 l

l Others: M -99 2.03 E-13 88 La-140 9.35 E-15 Detected, but not repofted PAGE 6 0F 15 w___-_____

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY THROUGH JUNE 19 87 D-2/3 VENT GASEOUS EFFLUENTS GROUND LEVEL RELEASES XX SEMI-ELEVATED RELEASES ELEVATED RELEASES DOCKET NOS. 50-237, 50-249 CONTINUOUS MODE BATCH MODE

'UCLIDES RELEASED UNIT 1stQUARTER 2nd QUARTER 1stQUARTER 2ndQUARTER

. FI_SSION GASES Ci Xe-138 Ci *

  • Xs-135m Ci *
  • Kr-87 Ci
  • Kr-88 C1 Kr-85m C1 Kr-85 Ci
  • Xe-135 Ci 4.87 E00 6.08 E 00 Xe-133 Ci
  • O thers :Xe-133m Ci *
  • C1 TOTAL Ci 4.87 E00 6.08 E 00 NONE NONE

, IODINES I-131 C1 5.44 E-04 1.19 E - 03 I-133 C1 3.50 E-03 8.33 E - 03 I-135 C1 6.20 E-03 1.57 E - 02 TOTAL Ci 1.02 E-02 2.52 E - 02 NONE NONE PARTICULATE

-89 Ci 1.89 E - 06 1.52 E - 05 or-90 Ci 1.79 E - 06

  • Cr-51 Ci 2.84 E-05 4.32 E - 04 Mn-54 Ci 2.25 E-04 4.05 E - 04 Co-58 C1 4.11 E-05 3.89 E - 04 Fe-59 Ci 1.66 E-05 1.38 E - 05 Co-60 Ci 1.70 E-03 4.67 E - 03 Zr-95 Ci
  • Ru-103 Ci *
  • Ac-Il0m Ci 4.44 E - 06 Sb-124 C1 1.25 E-06 6.02 E - 07 I-131 Ci 7.94 E-05 4.16 E - 04 Cs-134 Ci *
  • Ci
  • Cs-136 4.43 E - 06 Cs-137 Ci 3.29 E-05 6.32 E - 05 Ba-140 C1 8.97 E-05 4.52 E - 04 C,-141 Ci *
  • Cc-144 Ci *
  • Zn-65 C1 6.27 E-06 1.12 E - 04 Ba-133 Ci *
  • Sb-125 Ci *
  • Others:Mo-99 Ci 4.46 E-04 2.61 E - 03 Ci C1

> Ci J Ct ~

TOTAL Ci 2.67 E - 03 9.60 E - 03 NONE NONE

  • See Table for MDL of Each Nuclide PAGE 7 0F 15

l LRESDEN NUCLEAR POWER STATION JANUARY THROUGH JUNE 1987 TABLE OF MINIMUM DETECTABLE LEVELS FOR GASEOUS EFFLUENTS D-2: 110 KCFM D-2/3 VENT CASE 0US EFFLUENTS AVERAGE FLOW D-3: 110 KCFM DOCKET NOS. 50-237, 50-249 MDL (uCi/cc)  % OF TIME < MDL

1. FISSION GASES Xe-138 4.63 E-08 100 Xe-135m 1.98 E-08 100 Kr-87 3.31 E-08 100 Kr-88 5.50 E-08 100 Kr-85m 1.67 E-08 100 Kr-85 4.08 E-06 100 I Xe-135 1.69 E-08 23 Xe-133 4.18 E-08 100 Others: Xe-133m 1.49 E-07 100
2. 10 DINES I-131 3.26 E-14 0 I-133 2.89 E-14 8 I-135 5.73 E-14 12
3. PARTICULATE Sr-89 1.00 E-15 17 Sr-90 1.00 E-15 50 Cr-51 2.21 E-13 39 Mn-54 2.54 E-14 0 Co-58 2.53 E-14 11 Fe-59 3.89 E-14 73 4 Co-60 6.21 E-14 0 Zr-95 4.49 E-14 96 Nb-95 2.48 E-14 100 Ru-103 2.59 E-14 100 Ag-110m 2.72 E-14 92 Sb-124 1.85 E-14 92 I-131 2.76 E-14 12 3.02 E-14 100 Cs-134 2.95 E-14 93 Cs-136 3.05 E-14 3 Cs-137 1.02 E-13 8 Ba-140 3.59 E-14 100 Ce-141 1.50 E-13 100 Cc-144 4.39 E-14 45 Zn-65 100 Ba-133 3.56 E-14 _

7.57 E-14 100 Sb-125 16 Others* M -99 2.03 E-13 '

La -140 9.36 E-15 Detected, but not reported PAGE 8 0F 15

DRESDEN NUCLEAR POWER STATION 1

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT  !

1 JANUARY THROUGH JUNE 19 87 LIQUID EFFLUENTS

' SUMMATION OF ALL RELEASES DOCKET NOS. 50-10, 50-237, 50-249 1

UNIT 1st QUARTER 2ndQUARTER >

A. FISSION AND ACTIVATION PRODUCTR

1. Total Release (not incl. er4rinm gnen.c.n1nh, Ci 9.75 E --02 1.83 E - 01
2. Averace Diluted Conc. nnving parina uCi/ml 3.98 E - 09 2.58 E - 09 i
3. Percent of Ano11 cable Timir  % *
  • 1
3. TRITIUM i
1. Total Release Ci 5.26 E 00 7.78 E 00
2. Average Diluted Conc. Durine Perind uC1/ml 2.15 E - 07 1.10 E - 07
3. Percent of Applicable Limit  % *
  • I 1

DISSOLVED AND ENTRAINED GASES

1. Total Release Ci 5.25 E-03 2.97 E - 03
2. Averge Diluted Conc. Durine Period uCi/ml 2.14 E-10 4.19 E - 11 I
3. Percent of Applicable Limit  % *
  • GROSS ALPHA RADIOACTIVITY 1 Total Release Ci 5.53 E-05 4.61 E - 05 l . VOLUME OF WASTE RELEASED (prior to dilution) liters 1.15 E+07 9.06 E + 06

~

j l 1 VOLUME OF DILUTION WATER USED DURING PERIOD i liters 2.45 E+10 7. 08 E + 10

  • WI'LL BE INCLUDED IN THE ANNUAL REPORT ON ENVIRONMENTAL RADIOACTIVITY DATA i l PAGE 9 0F 15 .

_ ---- - ]

,$ f d '

DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT -

JANUARY' THROUGH_, JUNE 1987-RADWASTE _ LIQUID EFFLUENTS

1. Number'of Batch Releases: 210
2. ' Total Time Period for Batch Releases: 62846 MIN.
3. Maximum Time Period for a Batch Release: 488 MIN.
4. Average Time Period for Batch Releases: 299 " MIN.
5. Minimum Time Period for a Batch Release: 8 MIN.
6. Average Stream Flow During Periods of Release of Effluent into a Flowing Stream: 3.66 E+05 LITERS / MIN.

DOCKET NOS. 50-10, 50-237, 50-249 CONTINUOUS MODE BATCH MODE Nuclides Released Unit lat QUARTER 2nd QUARTl'R lst QUARTER 2nd QUARTER i

Sr-89 C1 1.22 E - 04 1.70 E - 03 l Sr-90 C1 1.09 E - 04

  • i Ar-41 Ci _ , , _
  • 3.80 E - 03 Mn-54 Ci 9.82 E-03 2.84 E - 02 Co-58 C1
  • 6. 41 E - 04 Fe-59' C1 2.88 E-04 4.91 El .03 Co-60 Ci 5.~0 5 E-02 9.32 E - 02 Zn-65 Ci
  • 3.24 E - 04 Ru-103 Ci * *

'Sb-122 Ci *

  • Sb-124 C1 ( *
  • I-133 Ci *
  • I-135 Ci *
  • Cs-134 C1 1.80 E-05 2.24 E - 05 Cs-137 C1 1.68 E-02 1.23 E - 02 Ba-140 Ci * '*

La-140 Ci *

  • Ce-141 Ci *
  • Others: Cr-51 C1

C 1._.i.

Tc-99m Ci ,

.Fe-55 C1 1.51 E - 02 3.72 E - 02 (above)

Totai For Period C1 NONE NONE 9.73 E - 02 1.83 E - 01 Xe-153- Ci 2.67 E-03 l1.87E-03 Xe-135 ,4

_.C1, 2.58 E-03 1.10 E - 03

  • See Table for MDL of Each Nuclide PAGE 10 0F 15 _ _ _ _ __ - _ .

n p

j: '

.\f

( '

DRESDEN NUCLEAR POWER STATION JANUARY THROUGH JUNE 1987

't:

TABLE OF MINIMUM DETECTABLE LEVELS I[. :e FOR LIQUID EFFLUENTS

, DOCKET NOS. .50-10, 50-237, 50-249 RADWASTE LIQUID EFFLUENTS TOTAL GALLONS RELEASED 4.77 E+06 MDL (uC1/ml)

% of Gallons < MDL Sr-89 4.00 E-09 33 Sr-90 2.00 E-09 50

,. Ar-41 3.07 E-08 99 l

Mn-54 6.16 E-08 o Co-58 6.51 E-08 99 Fe-59 9.00 E-08 88 Co-60 1.70 E-07 0  ;

I 1

Zn-65 1.17 E-07 99

( Ru-103 5.39 E-08 100 Sb-122 7.01 E-08 100

' 4.06 E-08 100 Sb-124 6.42 E-08 100 I-131 5.34 E-08 100 1-133 l 1

9.15 E-08 100 I-1D5 Cs-134 7.12 E-08 98 Cs-137 2.75 E-07 0 Ba-140 2.09 E-07 100 La-140 2.30 E-08 100 Ce-141 9.02 E-08 100 Xe-133 1.83 E-07 73 Xe-135 6.09 E-08 73 Xe-138 1.69 E-07 100 Xe-133m 5.23 E-07 100 Mo-99 4.93 E-07 100 Kr-87 1.07 E-07 100 Kr-88 1.98 E-07 100 Cr-51 52 77 E-07 99 Ce-144 3.68 E-07 100 i-

> Tc-99m 4.85 E-08 100 l

/' 16 Fe-55 7.00 E-07 Ba-133 8.98 E-08 PAGE 11 0F 15 100

t. -

f

  • 1

(

DRESDEN NUCLEAR POWER STATION '

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

  • 1 . .

JANUARY THROUGH JUNE 19,,8_7 LPCI LIQUID EFFLUENTS

1. Number of 3ar.ch Releases: 150 >
2. Total Time Period for Batch Releasce: 186. KIN. T-
3. Maximum Time Period for a Batch teJ U ce: ,1.24 MIN.'
4. Average Tim 2 Period for Batch Releas'os: 1.24 MIN.
5. Minimum Time Period for a Batch neloese: 1.24 MIN. A
6. Average Stream Flow During Periods ob Release' .

of Efflue'nt into a Flowing Stream:3.66 E+05 LITERS / MIN.

~

DOCKET NOS. 50-237, 50-249 CONTINUOUS MODE o

BATCH MODE l Nuclides Released Unit 1st QUARTER 2nd QUARTER A g QUARTER 2nd QUARTER __

i l Sr-89 Ci

  • I --

Sr-90 Cl '

  • i
  • J Ar-41 Ci * * -

Mn 54 C1 -

1.3d F-05 1.83 E-05 j'

Co-58 Ci '

' 4

  • Y -

E d

Fe-59 Ci S * *' J

'Co-60 Ci _1,, l.36 E-04 7.01 E-05

~I Zn-65 Ci /  ! * '

  • /

Ru-103 Ci _

  • I
  • Sb-122 Ci , i *r Sb-124 Ci '/* * "

I-131 Ci *

  • r I-133 Ci _

I-135 Ci * * '

Cs-134 Ci * . T' -

Cs-137 .

Ci 9. 63 E-06 1.36 E-05  ?

Ba-140 Ci * *'

_ g_ ,i

' 4.ft- 14 0 Ci

  • _j
  • j,-8 ,

y J

Ce-141 Ci *

  • i, F-Others: Cr-51 Ci __

j' ~~ &

Ci / .d .

(above) '

a Total For Period Ci NONE .f0NE 1.59 E-04 1.02 E-04 -

ar Xe-133 Ci . .

  • l ',*i Xe-135 C1

,,,_g L * .p l

  • _,
  • See Table for MDL of Eacti ~Nuclide '

L____- - --_- -_--------_ _---__-------- -----_ ----- micat 2 2 u- n-- --- -_---- -------- m -- --

u . . .

, , q

- )

3 .

_ :-) g E

I

- /

' DRE5 DEN NUCLEAR POWER STATION JANUARY TisROUGfl JUNE 1987 s

TABLE OF MINIMUM DETECTABLE LEVELS (

9 '

FOR LIQUID EFFLUENTS b0 DOCKET NOS. 50-237, 50-249

.Y ' . s LPC1 -LIQUID EFFLUENTS TOTAL GALLONS RELEASED 6.51 E+05 J j; 'ADL (uC1/el) % of Gallons < MDL g .

I l

3 Sr-89 .4.00 E-09.' 100 l Nl>

Sr-90 2.00 E-09 ,

100 Ar-41 3.07 E-08 100 Mn~Q4 6.16 E-08 25

'+

Co 6.51 E 100 Fe-59 9.00 E-08 100

. ,[

" 1.70 E-07 0 i Co-60' Zn-65 1.17 E-07 100 E'u-103 5.39 E-08 100 Sb-122 7.01 E-08 100 Sb-124 4.06 E-08 100 I-131 6.42 E-08, ,, ,

100 5.34 E-08 100 I-133 100

. I-P3 5 9.15 E-08 100 4 Ca -134 7.12 E-08 i

j Cs-l't? 2.'/5 E-07 22 i 100 Ba-140 2.09 F.-07 100 La-140 - 2.30 E-08 100

@-141 9.02 E-08 100 Xe-133 l.03 E-07 100 Xe-135 6.09 E-08 100 75-138 1.69 E-07 100 I Xe-I33m

  • 5.23 E-07 100 Mo-99 4.93 x.07 100 Kr-87 1.07 E-07 4

100

'Kr 88 1.93 g.0f 100 Cr-51 5.77 E-07 100 cc-144 3.68 E-07 100 Tc-99m 4,55 E-08

  • 'J Fe-55 7.00 F-01 100 he.-133 8.98 E-08 100 PAGE 13'0F 15 I - _ _

DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY THROUGH JUNE 19 87 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS DOCKET NOS. 150-10, 50-237, 50-249 A '. - SOLID WASTE SHIPPED OFFSITE'FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) 1.- Type of Waste Unit 6-month period m8 4.22 E+02'

a. ' Spent resins, filter sludges, evaporator bottoms, etc. Ci 5.33 E+02 m3 5.14 E+02
b. Dry compressible waste , contaminated equip. , etc. C1 1.89 E+01 m3 0
c. Irradiated conponents, control rods, etc. Ci 0 m3 0
d. Other (describe) Ci 0

~2. .

Estimate of Major Nuclide Composition (by type of waste)

% Ci

a. Co-60 52.8  % 2.81 E+02 Fe-55 37.0 % 1.97 E+02 Mn-54 4.4 % 2. 35 E+01 Cs-137 3.1 - % 1.65 E+01 OTHER 2.7 % 1.44 E+0L
b. Co-60 64.0 % 1.21 E+0>l Fe-55 28.8 % 5.44 E00 Mn-54 4.3  % 8.13 E-01 Cs-137 2.8  % 5.29 E-Ol' OTHER 0.1  %' 1.89 E-02
c. Co-60 52.3  %

Fe-55 41.2  %

Ni-59 0.1  %

Ni-63 6.3  %

OTHER 0.1  %

d.  % ,_
3. . Solid Waste Disposition NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION 69 MOTOR FREIGHT (EXCLUSIVE USE ONLY) BARNWELL, S.C.

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

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

B. IRRADIATED FUEL SHIPMENTS (Disposition)

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

PAGE 14 0F 15

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4 DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

.. JANUARY THROUGH JUNE 19 87 ABNORMAL RELEASES l l

DOCKET NOS. 50-10, 50-237, 50-249  ;

A LIQUID 1

1. Number'of Releases: 0
2. Total Activity Released: 0 r

B. GASEOUS

1. Number of Releases: 0
2. Total Activity Released: 0 PAGE 15 0F 15 '

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,, ._ -)'; , >~~~' y. Commonwealth Edison r

~, . )$ Dresden Nu;leir Power Stiti;n

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J' ! R.R. 01 ~

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\L~'/ ' Morris, Illinois815/942 Telephone 60450 2920 July 31, 1987 PhlaRITY ROUT 1pG_

EDE LTR: #87-495: -

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-Mr. A. Bert Davis Acting. Regional Administrator M -

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!' Directorate'of Inspection and Enforcement Region III

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'U.S. Nuclear Regulatory. Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 1

SUBJECT:

Dresden Station Ope' rating Report, NRC Dockets 50-10, 50-237, 50-249

.i

Dear'Mr. Davis:

Enclosed is the radioactive effluent report for January through June, 1987 for Dresden Nuclear Power Station.

One copy of each report is provided for your use and eight copies are being distributed per the rules and regulations outlined in the November

'86 Federal' Register.

Sincerely yours, 7

E.D. Eeni nb rg.

Station M n er Dresden Nuclear Power Station EDE:RE:bjs Enclosure j cc: R. Berg J.C. Golden File /NRC File / Numerical i

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