ML20151G693

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Corrected Effluent & Waste Disposal Semiannual Rept,Jul-Dec 1987
ML20151G693
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 12/31/1987
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20151G696 List:
References
NUDOCS 8804200110
Download: ML20151G693 (16)
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Text

_ _ _ _ _ _ _ . -__.

DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT July Through _,pecember __1911,,

GASEQUS EFFLUENTS SUMMATION OF ALL RELEASES Docket Numbers: 50-10 50-237 50-249 4

UNIT 3rd QUARTER 4th QUARTER ,

i A. FISSION AND ACTIVATION CASES

1. Total Release Ci 3.33 E00 4.90 E00
2. Average Release Rate for Period uCL/sec 4.19 E-01 6.17 E-01
3. Percent of Technical Specification Limit  % * *

'B. 10 DINES

1. Total Iodine-131 Ci 2.30 E-02 6.74 E-02  !
2. Average Release Rate for Period uCi/see 2.89 E-03 8.48 E-03 [
  • I
3. Percent of Technical Specification Limit  %

C. PARTICULATES

1. Particulates with half-lives > 8 days Ci 9.02 E-03 1.63 E-02
2. Average Release Rate for Period uCi/sec 1.13 E-03 2,06 E-03
3. Percent of Technical Specification Limit
4. Gross Alpha Radioactivity Ci 9.93 E-06 3.31 E-06 ,

D. TRITIUM

1. Total Release Ci 5.38 E00 6.60 E00 i t

\'

2. Average Release Rate for Period uCi/sec 6.77 E-01 8.30 E-01  !
3. Percent of Technical Specification Limit e Will be included in the Annual Report on Environmental Radioactivity Data ,

t Page 2 of 16 j 0727c kN I '

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, 8804200110 Spee d PDR ADOCK 050M 010 R DCD i

    • ** EFFLUENT AND idASTE DISPOSAL SEMIANNUAL REPORT

.- July Through December 199J, DI Chimney GASEOUS EFFLUENTS GROUND LEVEL RELEASES Docket Number 50-10 SEMI-ELEVATED RELEASES xx ELEVATED RELEASES CONTINUOUS HODE BATCH NODE NUCLIDES RELEASED UNIT 1rg QUARTER 4th QUARTER 3rd QUARTER 4th QUARTER FISSION CASES Ci Ke-138 Ci *

  • Xe-135m Ci *
  • Kr-87 Ci *
  • Kr-88 Ci *
  • Kr-85m Ci *
  • Xe-135 Ci *
  • Xe-133 Ci ,

Others Xe-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 C1 1.21 E-06
  • Sr-90 Ci 1.26 E-07 1.10 E-07 Cr-51 Ci *
  • Co-58 Ci *
  • Fe-59 Ci * * .

e i Co-60 Ci 3.85 E-06 4.96 E-06 Zr-95 Ci *

  • Ub-95 Ci *
  • Ru-103 Ci *
  • An-110m Ci *
  • Sb-124 Ci *
  • Cs-134 Ci
  • 2.74 E-07 Cs-136 Ci *
  • j Cs-137 Cl 2.28 E-06 2.82 E-05 Ba-140 Ci *
  • Ce-141 Cl *
  • Co-144 Ci *
  • Zn-65 Ci *
  • Ba-133 Ci * * ,

Ci *

  • Sb-125

__ Otherst Mo-99 Ci *

  • La-140 Ci *
  • Ci Ci Ci n TOTAL Ci 9,15 E-06 3.35 E-05 None None 7
  • See Table for MDL of Each Nuclide I Page 3 of 16 01270 - _ _ . _ _ - _ _ _ _ _ _

~

DRESDEN~ NUCLEAR POWER STTTION

, . EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Julv Through December 1917 Dockst Number 50-10 TABLE OF MINIMUM DETECTABLE LEVELS F0k GASEOUS EFFLUENTS D1 Chimney GASEOUS EFFLUENTS AVERAGE FLOW 50.000 cfm hDL (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 Xe-135 1.69 E-08 100 Xe-133 4.18 E-08 100 Others: Xe-133m 1.49 E-07 100
2. 10 DINES 1-131 3.26 E-14 100 1-133 2.89 E-14 100 1-135 5.73 E-14 100
3. PARTICULATES Sr-89 2 E-15 66.9
Sr-90 1 E-15 50.0 Cr-51 2.21 E-13 100 Mn-54 2.54 E-14 94.6 Co-58 2.53 E-14 100 Fe-59 3.89 E-14 100 Co-60 6.21 E-14 27.2 Zr-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 I-131 2.76 E-14 100 Cs-134 3.02 E-14 97.8 Cs-136 2.95 E-14 100 Cs-137 3.05 E-14 15.8 Ba-140 1.02 E-13 100 Ce-141 3.59 E-14 100 Ce-144 1.50 E-13 100 Zn-65 4.39 E-14 100 Ca-133 3.56 E-14 100 Sb-125 7.57 E-14 100 Others
Mo-99 2.03 E-13 100 La-140 9.36 E-15 100 Page 4 of 16 07270

~ ~ -

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  • * *- RFFLUENT AND WASTE DISPOSAL SENIANNUAL~ REPORT July Through December.1911

'D2/3 Chimney GASEOUS EFFLUENTS GROUND LEVEL RELEASES Docket Numbers: 50-237 SENI-ELEVATED RELEASES 50-249 xx ELEVATED RELEASES CONTINUOUS NODE BATCH NODE NUCLIDES RELEASED UNIT M QUARTER 4_th QUARTER. M QUARTER 4_td1 QUARTER FISSION GASES Ci to-138 Ci 1.38 E-02 1.30 E-02 Ko-135m Ci 4.50 E-03 7.42 E-02 Kr-87 Ci 1.12 E-03

  • Er-88 C1 2.33 E-03
  • Kr-85m Cl 1.03 E-03
  • Re-135 Ci 3.30 E-02 6.61 E-02 Xe-133 Ci 4.32 E-03 9.50 E-04 Others Xe-133m Ci *
  • Ci TOTAL Ci 6.48 E-02 1.54 E-01 None Mone 10 DINES I-131 Ci 9.87 E-04 2.60 E-03 __

I-133 Ci 6.17 E-03 1.58 E-02 I-135 Ci 7.05 E-03 2.45 E-02 TOTAL Ci 1.42 E-02 4.29 E-02 None None PARTICULATES Sr-89 Cl 3.66 E-05 5.08 E-07 Sr-90 Ci 1.54 E-06 5.06 E-09 Cr-51 Ci *

  • Mn-54 Ci 3.52 E-05 1.24 E-05 Co-58 Ci *
  • Fe-59 Ci *
  • Co-60 Ci 4.71 E-04 1.64 E-04

. Zr-95 Ci *

  • Nb-95 Ci *
  • j Ru-103 Ci *
  • An-110m Ci *
  • i Sb-124 Ci * *
I-131 Ci 8.24 E-05 8.06 E-04 Cs-134 Ci * *

! Cs-136 Ci *

  • i Cs-137 Ci 1.83 E-06 3.72 E-05 Ba-140 C1 1.04 E-03 2.52 E-03 Co-141 Cl 9.93 E-05 7.13 F-04 l Co-144 Cl *
  • Zn-65 Ci * *

! Ba-133 Cl *

  • j Sb-125 Ci *
  • l Others: No-99 Cl *
  • i La-140 Ci *
  • l Ci

, ci

! Ci TOTAL Ci 1,77 E-03 4.25 E-03 Wone None

  • See Table for MDL of Each Nuclide l

Pate 5 of 16 01210

07273 .

~

. DRESDEN NUCLEAR POW 3R STATION July Through December 193Jl -Dockot Numbera; 50-237 TABLE OF MININUM DETECTABLE LEVELS 50-249 FOR CASE 00S EFFLUENTS 3rd atr 285.0 Kefa D2/3 Chimner GASEOUS EFFLUENTS AVERAGE FLOW 4th otr 276.9 Ecfm HEL (uC1/cc)  % OF TIME < MDL

1. FISSION GASES Ko-138 4.63 E-08 85.9 Xo-135m 1.98 E-08 90.2 Kr-87 3.31 E-08 93.4 Kr-88 5.50 E-08 97.8 Kr-85m 1.67 E-08 97.8 Kr-85 4.08 E-06 0 Ko-135 1.69 E-08 17.9 X3-133 4.18 E-08 94.0 Others: Xe-133m 1.49 E-07 100 l 2. 10 DINES 1-131 3.26 E-14 0.5 1-133 2.89 E-14 0.5 I-135 5.73 E-14 13.0
3. PARTICULATES l

Sr-89 2 E-15 0 3r-90 1 E-15 0 Cr-51 2.21 E-13 100 Mn-54 2.54 E-13 48.4 l

Co-58 2.53 E-14 100 Fe-59 3.89 E-14 100 Co-60 6.21 E-14 14.7 Zr-95 4.49 E-14 100 Mb-95 2.48 E-14 100 Ru-103 2.59 E-14 100 As-110m 2.72 E-14 100 Sb-124 1.85 E-14 100 1-131 2.76 E-14 6.0 Cs-134 3.02 E-14 100 Cs-136 2.95 E-14 100 Cs-137 3.05 E-14 27.2 Ca-140 1.02 E-14 21.7 Ce-141 3.59 E-14 89.7 Co-144 1.50 E-13 100 Zn-65 4.39 E-14 100 Ba-133 3.56 E-14 100 Sb-125 7.57 E-14 100 Others: Mo-99 2.03 E-13 100 La-140 9.36 E-13 Detected but not reported Page 6 of 16 07270

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. DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SENIANNUAL REPORT July Through December _1987 ,

D2/3 Vent CASEOUS EFFLUENTS

~

GROUND LEVEL RELEASES i Docket Numbers: 50-237 ,

xx SEMI-ELEVATED RELEASES 50-249 l ELEVATED RELEASES

(

CONTINUOUS NODE BATCH NODE NUCLIDES RELEASED UNIT lgd QUARTER 4th QUARTER 3rd QUARTER 4th QUARTER FISSION CA.?ES Ci Xe-138 Ci *

  • Ee-135m Ci *
  • Er-87 Ci *
  • Er-88 Ci *
  • Er-85m Ci *
  • s

~

Er-85 Ci *

  • Xe-135 Ci 3.27 E00. 4.75 E00 Xe-133 Cl * * .

Others Xe-133m Ci *

  • Ci ,

TOTAL Ci 3.27 E00 4.75 E00 None None  !

10 DINES I-131 Cl 3.59 E-04 1.05 E-03 1-133 Ci 2.70 E-03 7.94 E-03 I-135 Ci 5.69 E-03 1,55 E-02 <

IQTAL Ci 8.75 E-03 2.45 E-02 None None [

PARTICULATES .

~

Sr-89 Ci 5.08 E-06 5.49 E-05 3 Sr-90 Ci 1.07 E-06 2.17 E-06 Cr-51 Ci 2.42 E-04 7.85.E-04 Mn-54 Ci 4.54 E-04 4,53 E-04 Co-58 Ci 2.05 E-04 3.61 E-04 Fe-59 Ci 7.74 E-06 8.63 E-05 Co-60 Ci 3.63 E-03 4.19 E-03 2r-95 Ci

  • 1.48 E-06 . .

i Nb-95 Ci *

  • Ru-103 Ci * *

, ____An-110m Cl

  • 5.63 E-06 Sb-124 Cl
  • 2.86 E-06 [

1-131 Ci 1.69 E-03 8.69 E-04 i

! Cs 1,34 Ci *

  • l Cs-136 Cl 4.36 E-07 4.77 E-06 Cs-137 Ci 5.04 E-05 2.69 E-05 l Ba-140 Ci 1.07 E-04 4.94 E-04 Ce-141 Ci *
  • i co-144 Ci * *  ;

Zn-65 .Ci 8.50 E-05 1.85 E-04 Ba-133 Ci_

  • 1.39 E-04 g i Sb-125 Ci *
  • Others: Mo-99 Ci 7.47 E-04 4.25 E-03 i j La-140 Ci
  • i TOTAL Ci 7.24 E-03 r 1.19 E-02 None Note i
  • See Tr4ble for MDL of Each Nuclide l Iodine and Particulate foic November 3, 1987 - November 17, 1987 estimated from data from ,

previous and following weeks. I r2nncL LcA E ,____ . _ _ _ _ _ _ _ _ _ __ _ _ _ . _ _ _

g - - -- - - - ~,.

m . .

. DRESDEN NUCLEAR POW 8R STATION i July Throu8h ,,Pacamber 193]. Dock:t Numbers: j 20-237 TABLE OF MININUM DETECTABLE LEVELS 50-?40 FOR CASE 0VS EFFLUENTS  :

1 D2: 110 Kcfm

_D2/3 Vent CASEOUS EFFLUENTS AVERAGE FLOW D3: 110 Kcfm i

HQL (uCi/cc)  % OF TIME < MDL

1. FISSION GASES  ;

Xe-138 '

4.63 E-08 100 i

< Xe-135m 1.19 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 Xe-135' 1.69 E-08 44.0 +

Xe-133 4.18 E-08 100 Others: Xe-133m 1.49 E-07 100

2. 10 DINES  :

?

I-131 3.26 E-14 16.3 r

I-133 2.89 E-14 18.5 1-135 5.73 F.-14 32.1
3. PARTICULATES S r-89' 2 E-15 0 ,

Se-90 1 E-15 0 cc-51 2.21 E-13 0 '

, Mn-54 2.54 E-14 0 Co-58 2.53 E-14 48.9 Fe-59 3.89 E-14 70.1 Co-60 6.21 E-14 0 Zr-95 4.49 E-14 96.2 Mb.95 2.48 E-14 100 ku-103 2.49 E-14 100 As-110m 2.72 E-14 91.9 Sb-124 1.85 E-14 89.1 1-131 2.76 E-14 15.2 Cs-134 3.02 E-14 100 Cc-136 2.95 E-14 55.4 Cs-137 0.05 E-14 8.7 Ba-140 1.02 E-13 15.2 Co-141 3.59 E-14 100 Co-144 1.50 E- 13 100 Zn-65 4.39 E-14 27.1 Ba-133 3.56 E-14 96.2 Sb-125 7.57 E-14 100 Others: Mo-99 2.03 E-13 26.1 La-140 9.36 E-15 Detected but not reported Page 8 of 16 0127a

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DRESDEW NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT July Through December 198],

LIQUID EFFLUENTS SUMMATION OF ALL RELEASES Docket Numbers: 50-10 50-237 50-249 UNIT 2r4 QUARTER 4th QUARTER A. FISSION AND ACTIVATION CASES

1. Total Releaso (not incl. tritium gases, alpha) Ci 5.08 E-02 4.65 E-02
2. Average Diluted Conc. During Period uCi/n1 2.07 E-07 1.17 E-07
3. Percent of Applicable Limit  % *
1. Total Release Ci 3.61 E00 5.63 E00
2. Average Diluted Conc. During Period uCi/mL 1.47 E-05 1.42 E-05
3. Percent of Applicable Limit  % *
  • C. D_I?;E_QJ.VED Q AND ENTRAINED GASES
1. Total Release Ci 3.53 E-05 1.11 E-05
2. Average Diluted Conc. During Period uCi/mL 1.44 E-10 2.80 E-11

~

3. Percent of Applicable Limit D.__ GROSS ALPHA RADIOACTIVITY
1. Total Release Ci l l2.45E-05l3.95E-04l E. VOLUME OF WASTE RELEASED (prior to dilution) liters l l1.70E06l1.78E06 l F. VOLUME OF DILUTION WATER USED DURING PERIOD liters 2.45E08l3.97E08l

'A Will be included in the Annual Report on Environmental Radioactivity Data Page 9 of 16 07270

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. 4 '. , 9 DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL R5 PORT July Through December 191], .

R,pdweste LIQUID EFFLUENTS Docket Numbers: 50-10 50-237 -

1. Number of Batch Releases: 134 50-249
2. Total Time Period for Batch Releases: 34,195 ein
3. Maximti. Time Period for a Batch Release: 298 min
4. Average Time Period for Batch Releases: 255 min '
5. Minimum Time Period for a Batch Release; 198 min l

, 6. Average Stream Flow During Periods of Release of Effluent into a Flowing Stream: 1.58 E06 L/ min CONTINUOUS M0QR BATCH MODE NUCLIDES RELEASED UNIT 3rd QUARTER 4th QUARTER 3rd QUARTER I 4th QUARTER ,

Sr-89 _

Ci 4.69 E-07

  • Sr-90 Ci 5.27 E-05 6.17 E-05 Ar-41 Ci *
  • Mn-54 Ci 5.15 E-03 4.03 E-03 Co-58 Ci 4.30 E-11
  • Fe-59 Ci 8.10 E-13 * ,

Ci i co-60 1.93 E-02 3.44 E-02 Zn-65 Ci *

  • h-103 Ci *
  • Sb-122 __ C i Sb-124 Ci *

I-133 Ci *

  • I-135 Ci * * .

Cs-134 Ci *

  • Cs-137 Ci 5.55 E-03 5.87 E-03 Ba-140 Ci *
  • La-140 Ci *
  • Ce-141 Ci ,,

Others: Cr-51 Ci *

  • Fe-55 Ci 4.07 E-03 6.42 E-04 Er-88 Ci 1.5 E-13
  • Ci (above)

Total For Period Ci _ None None 3.00 E-02 4.50 E-02 [

Xe-133 C1 1.03 E-05 1.11 E-05 Xe-135 Ci 2.50 E-05 i

  • See Table for P.DL of Each Nuclide i

B Page 10 of 16 0727o ,

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+ .. . ,.  ;

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. . 'DRESDEN NUCLEAR POWER STATION [

  • - Julv Throup,h December 1917

+te TABLE OF .1:WIMUM DETECTABLE LEVELS Docket Numbers:

, FOR LIQUID EFFLUENTS 50-10  ;

y 4 50-237 <

50-249_ >

c Radweste LIQUID EFFLUENTS TOTAL CALLONS RELEASED 2.830.920 [

l BRh (uCi/rL)  % OF GALLONS'< MDL ha #,.

t Sr-89 2 E-08 83.2 Sr-90 7 E-09 33.7 A"-41 -

3.07 E-08 0.7 Mn-54 6.16 E-08 97.8 Co-58 6.51 E-08 97.8 l

Fe-59 9.00 E-08 0 [

~

CJ-60 1.70 E-07 100 Zn-65 s 1 17 E-07 100 i Ru-103 5.39 E-08 100 f 1 Sb-122 7.01 E-08 100 .!

t i

Sb-124 4.06 E-08 100 I-131 6.42 E-08 100 ,

1-133 5.34 E-08 100 1-135 9.15 E-08 100 Cs-134 7.12 E-08 100 f Cs-137 2.75 E-07 0 Ba-140 2.09 E-07 100 La-140 2.30 E-08 100 Co-141 9.02 E-08 100 Ko-133 1.83 E-07 97.8 f Xe-135 6.09 E-C8 95.5 Cr-51 5.77 E-07 100  ;

Fe-55 5 E-08 50.0 l r

Er-88 Not Available 95.0 [

i i

Page 11 of 16 0727c

DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT July Through December 19p]

LPCI LIQUID EFFLUENTS Docket .@ .M cc. 50-237 50-249

1. Number of Batch Releases: 102
2. Total Time Period for Batch Releases: 126.48 min
3. Maximum Time Period for a Batch Release: 1.24 min
4. Average Time Period for Batch Releases: 1.24 min S. Minimum Time Period for a Batch Releaso: 1.24 min
6. Average Stream Flow During Periods of Release of Effluent into a Flowing Stream: 2.81 E06 L/ min CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT 3rd QUARTER 4th QUARTER 3rd QUARTER 4th QUARTER Sr-89 Ci *
  • 1.94 E-04 Ar-41 Ci *
  • Mn-54 Cl 3.93 E-06 9.00 E-07 Co-58 Ci *
  • Fe-59 Ci *
  • Sb-122 Ci *
  • Sb-124 Ci *
  • I-133 Ci *
  • I-135 Ci *
  • Cs-134 Ci *
  • Cs-137 Cl 1.66 E-05 1.43 E-05 Ba-140 Ci *
  • La-140 Ci *
  • Ce-141 Ci *
  • Others: Cc-51 Ci , _ _ ,

Fe-55 Ci 2.07 E-07 3.70 E-06 Ci *

  • Ci * *

(above)

T_otel For Period Ci None None 2.08 E-02 2.32 E-04 l Xe-133 Ci Ci *

  • Xe-135 l

t

  • See Table for MDL of Each Nuclide i

i l

l Page 12 of 16 07278 l

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. DRESDEN NUCLEAR POWER STATION

July Through December 1987 TABLE OF MINIMUM DETECTABLE LEVELS Docket Numbers:

FOR LIQUID EFFLUENTS 50-237 50-249 LPCI LIQUID-EFFLUENTS TOTAL GALLON 1 RELEASED 442.680 MDL (uC1/mL)  % OF GALLONS < MDL Sr-39 2 E-08 100 Sr-90 7 E-08 83.2 Ar-41 3.07 E-08 100

.Mn-54 6.16 E-08 32.6 Co-58 6.51 E-08 100 Fe-59 9.00 E-08 100 Co-60 1.70 E-07 0 Zn-65 1.17 E-07 100 Ru-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 1-133 5.34 E-08 100 I-135 9.15 E-08 100 Cs-134. 7.12 E-08 100 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 l

Xe-133 1.83 E-07 100 l

Xe-135 6.09 E-08 100 Cr-51 5.77 E-07 100 Fe-55 5 E-08 33.7 I

l l

l Page 13 of 16 0727a 1

. DRESDEN NUCLEAR POWER STATION EFFLUENT AND 'iASTE DISPOSAL SEMIANNUAL REPORT July Through December 1987 Docket Numbers:

50-10 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 50-237 50-249 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)

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

Ci 2.46 E02 Dry compressible waste, contaminated equip., etc.

b.

Ci 2.79 E01

c. Irradiated components, control rods, etc.

Ci 0 m* O

d. Other (describe)

Ci 0

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

% Ci

a. Co-60 84.4 % 2.08 E02 Fe-55 0  % 0 Mn-54 12.9 % 3.17 E01 Cs-137 0.7  % 1.72 E00 Other 2.0 % 4.92 E00
b. Co-60 88.9 % 2.48 E01 Fe-55 0  % 0 Mn-54 7.8 % 2.18 E00 Cs-137 3.3 % 9.20 E-01 Other 0  % 0
c.  %
d.  %
3. Solid Waste Disposition NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION 54 Motor freight (exclusive use only) Barnwell, SC 19 Motor freight (exclusive use only) Richland, WA 20 Motor freight (exclusive use only) Beatty, NV B. IRRADIATED FUEL SHIPMENTS (Disposition)

NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION 1 Motor Freight / Transatlantic Goteborg, Sweden Shipping Page 14 of 16

, 0727a 5 g.-e --w -- >y.w - ->wi - ww- -- -

w g,-y +-ei------ ------y -w--- - ----a w: *, - y-

In cecordance with Specifications 6.6.C.1 and 6.9.C of the Technical Sp:cifications, Dresden' Station has changed from using the station liquid r;dwaste processing equipment to using CNSI's equipment as the normal means fcr dewatering and colidifying liquid radwaste as described in CNSI's Topical R:pretl which was approved.by the NRC on April 11, 1983. Dresden Station has rivided its Process Control Program to reflect the fact that vendor carvices have become the primary means of processing liquid rad waste rather thin the permanently installed Station system (Stock System). This change was On-Site Reviewed in accordance with Station procedures. Use of CNSI's NRC cppesved process control program and equipment will continue to assure that w cto processing at Dresden Station is performed in accordance with applicable critsela and requirements. This change was implemented as a more cost cffective manner of processing waste as well as reducing radiation exposure to ctition personnel. Additionally, the revised PCP requires that the topical r:ptet for the vendor services must be submitted to the NRC and the colidification/ stabilization media must be approved by the licensed burial sites prior to use at Dresden. The PCP (Revision 1, February,1988) is cttached.

l.9NSI-2 4313-01354-01P-h, "Mobile Gament Solidificatien System".

15 of 16 0727e

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. DRESDEN NUCLEAR POWER STATION

'E'FFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT July Through December 1911 Docket Numbers:

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

1. Number of Releases: 2 __
2. Total Activity Released: 3.48 E-04 Ci Co60 D3 Isolation Condenser blown.on August 7, 1987. See DVR #12-3-87-48,

-49 and -50 for further information.

D3 Isolation Condenser blown on September 28, 1987. See DVR

  1. 12-3-87-68, for furthe" information. Curie content estimated from isotopic and August 7, 1987 release volume.

B '. GASEOUS

1. Number of Releases: 0
2. Total Activity Released: 0 __

16 of 16 1 0727e

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