ML20150B328

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Effluent & Waste Disposal Semiannual Rept,Jul-Dec 1987
ML20150B328
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 12/31/1987
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20150B332 List:
References
NUDOCS 8803160321
Download: ML20150B328 (16)
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DRESDEN NUCLEAR POWER STATION DOCKET NOS. 50-10, 50-237, 50-249 MEASUREMENTS AND APPROXIHATIONS 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. 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 tho 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 systam. 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(L1) 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 system. This sample is sent tc a vendor to be analyzed for Sr-89, Sr-90 Fe-55, and Gross Alpha activity.

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l Page 1 of 16 810 2I O 8803160321 r:201 PDR ADOCK 05000010 I R DCD i j

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, DRESDSN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT July Through December 1981 CASEOUS EFFLUENTS SUMMATION OF ALL RELEASES Docket Numbers: 50-10 50-237 50-249 UNIT 3rd QUARTER 4th QUARTER ,

A. FISSION AND ACTIVATION GASES

1. Total Release Ci 3.33 E00 4.90 E00
2. Average Release Rate for Period uCi/sec 4.19 E-01 6.17 E-01
3. Percent of Technical Specification Limit  % *
  • B. TODINES
1. Total Iodine-131 C1 2.30 E-02 6.74 E-02
2. Average Release Rate for Period uCi/see 2.89 E-03 C.48 E-03
3. Percent of Technical Specification Limit  % *
  • C. PARTICULATES
1. Particulates with half-lives > 8 dais 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 4.95 E-06 D. TRITIUM
1. Total Release ci 5.38 E00 6.60 E00
2. Average Release Rate for Period uCi/sec 6.77 E-01 8.30 E-01
3. Percent of Technical Specification Limit  % *
  • Will be included in the Annual Report on Environmental Radioactivity Data Page 2 of 15

DRESbEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

, July Through December 19 8_!_

D1 Chimney GASEOUS EFFLUENTS GROUND LEVEL RELEASES Docket Number 50-10 SEMI-ELEVATED RELEASES xx ELEVATED RELEASES CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT 3_rd QUARTER 4th QUARTER 3rd QUARTER 4th QUARTER FISSION CASES Ci Xe-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 *
  • I-133 Ci *
  • I-135 Ci *
  • TOTAL Ci *
  • None None PARTICULATES Sr-89 C1 1.21 E-06
  • Cr-51 Ci *
  • Co-58 Ci *
  • Fe-59 Ci *
  • Nb-95 Ci *
  • Ru-103 Ci *
  • An-110m Ci *
  • Sb-124 Ci *
  • Cs-134 Ci
  • 2.74 E-07 Cs-136 Ci *
  • I Cs-137 Ci 2.28 E-06 2.82 E-05 1

1 Ba-140 Ci *

  • Co-141 Ci *
  • Co-144 Ci *
  • Ba-133 Ci *
  • l Sb-125 Ci *
  • La-140 Ci *
  • Ci C1 Ci TOTAL Cl 9.15 E-06 3.34 E-05 None None
  • See Table for MDL of Each Nuclide Page 3 of 16

DRESDEN N CLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

  • . ', July Through December 1987 Docket Number 50-10 TABLE OF MINIMUM DETECTABLE LEVELS FOR GASEOUS EFFLUENTS D1 Chimney GASEOUS EFFLUENTS AVERAGE FLOW 50.000 efm MDL (uC1/cc)  % OF TIME < MDL
1. FISSION CASES Xe-138 4.63 E-08 100 Xe-135m 1.98 E-08 100 Kr 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 I-131 3.26 E-14 100 I-133 2.89 E-lo 100 I-135 5.73 E-14 100
3. PARTICULATES Sr-89 2 E-15 100 Sr-90 1 E-15 100 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 As-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 Co-141 3.59 E-14 100 Co-144 1.50 E-13 100 2n-65 4.39 E-14 100 Ba-133 3.!6 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 1

Page 4 of 16 l l

DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT July Through Decemb9r 1987 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 3rd QUARTER 4th QUARTER 3rd QUARTER 4th QUARTER FISSION CASES Ci Xe-138 Ci 1.38 E-02 1.30 E-02 Xe-135m Ci 4.50 E-03 7.42 E-02 Kr-87 Ci 1.12 E-03

  • Kr-88 Ci 2.33 E-03
  • Kr-85m C1 1.03 E-03
  • Xe-135 Ci 3.30 E-02 6.61 E-02 Xe-133 Ci 4.32 E-03 9.50 E-04 Others:Xe-133m Cl *
  • Ci TOTAL Ci 6.48 E-02 1.54 E-01 None None IODINES 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 C1 1.42 E-02 4.29 E-02 None None PARTICULATES Sr-89 Ci 3.66 E-05 1.55 E-04 Sr-90 Ci 1.54 E-06 2.36 E-06 Cr-51 Ci *
  • Mn-54 Ci 3.52 E-05 1.24 E-05 Co-58 Ci *
  • Fe-59 Ci *
  • Nb-95 Ci *
  • Ru-103 Ci *
  • AK-110m Ci *
  • Sb-124 Ci *
  • I-131 Ci 8.24 E-05 8.06 E-04 Cs-134 Ci *
  • Cs-136 Ci *
  • Cs-137 Ci 1.83 E-06 3.72 E-05 Ba-140 Ci 1.04 E-03 2.52 E-03 Ce-141 CL 9.93 E-05 7.13 E-04 Co-144 Ci *
  • Ba-133 Ci *
  • Sb-125 Ci *
  • La-140 Ci *
  • Ci ci ci TOTAL Ci 1,77 E-03 4.41 E-03 None None
  • See Table for MDL of Each Nuclide PaBe 5 of 16

DRESDEN NUCLEAR POWER STATI0tl July Through _Docember 1987 Docket tiumbers:

50-237 TABLE OF MINIMUM DETECTABLE LEVELS 50-249 FOR GASEOUS EFFLUENTS 3rd otr 285.0 Kcfm

_ D2/3 Chimney GASEOUS EFFLUENTS AVERAGE FLOW 4th ete 276.9 Kcfm MDL (uCi/cc)  % OF TIME < MDL

1. FISSION GASES Xe-138 4.63 E-08 85.9 Xe-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-OS 97.8 Kr-85 4.08 E-06 0 Xe-135 1.69 E-08 17.9 Xe-133 4.18 E-08 94.0 Others: Xe-133m 1.49 E-07 100
2. IODINES I-131 3.26 E-14 0.5 I-133 2.89 E-14 0.5 I-135 5.73 E-14 13
3. PARTICULATES Sr-89 2 E-15 0 Sr-90 1 E-15 0 Cr-51 2.21 E-13 100 Mn-54 2.54 E-13 48.4 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 Kb-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 I-131 2.76 E-14 6.0 l Cs-134 3.02 E-14 100 I Cs-136 2.95 E-14 100 i Cs-137 3.05 E-14 27.2 l Ba-140 1.02 E-14 21.7  ;

Co-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 l Page 6 of 16

DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT July Through Decembsr 1987 D2/3 Vent GASEOUS EFFLUENTS GROUND LEVEL RELEASES Docket Numbers: 50-237 xx SEMI-ELEVATED RELEASES 50-249 ELEVATED RELEASES CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT 3rd QUARTER 4th QUARTER 3rd QUARTER 4th QUARTER FISSION CASES Ci Xe-138 Ci *

  • Xe-135m Ci *
  • Kr-87 Ci *
  • Kr-88 Ci *
  • Kr-85m Ci *
  • Xe-135 Ci 3.27 E00 4.75 E00 Xe-133 Ci *
  • Others:Xe-133m Ci *
  • Ci TOTAL Ci 3.27 E00 4.75 E00 None None IODINES I-131 Ci 3.59 E-04 1.05 E-03 ,

I-133 Ci 2.70 E-03 7.94 E-03 I-135 Ci 5.69 E-03 1.55 E-02 TOTAL Ci 8.75 E-03 2.45 E-02 None None PARTICULATES Sr-89 Ci 5.08 E-06 2.81 E-05 Sr-90 Ci 1.87 E-06 1.65 E-06 cc-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 Zr-95 Ci

  • 1.48 E-06 Nb-95 Ci *
  • Ru-103 Ci *
  • An-110m Ci
  • 5.63 E-06 l Sb-124 Ci
  • 2.86 E-06 l I-131 Ci 1.69 E-03 8.69 E-04 l Cs-134 Ci *
  • j Cs-136 Ci 4.36 E-07 4.77 E-06 I Cs-137 Ci 5.04 E-05 2.69 E-05 Ba-140 Ci 1.07 E-04 4.94 E-04 Co-141 Ci *
  • Co-144 Ci *
  • Zn-65 Ci 8.50 E-05 1.85 E-04 Ba-133 Ci
  • 1.39 E-04 Sb-125 Ci *
  • Others: Mo-99 Ci 7.47 E-04 4.25 E-03 La-140 Ci *
  • Ci TOTAL Ci 7.24 E-03 1.19 E-02 1 None None
  • See Table for MDL of Each Nuclide Iodine and Particulate for November 3, 1987 - November 17, 1987 estimated from data from previous and following weeks.

Page 7 of 16

vae.aut.a avut.cAn evaca o tat wu July Through December 1987 Docket Numbers:

50-237 TABLE OF MINIMUM DETECTABLE LEVELS 50-240

. FOR GASEOUS EFFLUENTS D2: 110 Kefm

_D2/3 Vent GASEOUS EFFLUENTS AVERAGE FLOW D3: 110 Kcfm MDL (uCi/cc)  % OF TIME < MDL

1. FISSION GASES Xe-138 4.63 E-08 100 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 I-133 2.89 E-14 18.5 I-135 5.73 E-14 32.1
3. PARTICULATES Sr-89 2 E-15 0 Sr-90 1 E-15 16.3 Cr-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 -

Nb-95 2.48 E-14 100 Ru-103 2.59 E-14 100 As-110m 2.72 E-14 91.9 <

Sb-124 1.85 E-14 89.1 I-131 2.76 E-14 15.2 Cs-134 3.02 E-14 100 Cs-136 2.95 E-14 55.4 Cs-137 3.05 E-14 8.7 Ba-140 1.02 E-13 15.2 Co-141 3.59 E-14 100  !

Ce-144 1.50 E-13 100 2n-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 i

' - - - - ~ - ~

DRESDEN NUCLEAR POWER STATION 1

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT July Through December 1981 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES Docket Numbers: 50-10' 50-237 50-249 UNIT 3rd QUARTER 4th QUARTER A. FISSION AND ACTIVATION GASES

1. Total Release (not incl. tritium, gases, alpha) Ci 5.08 E-02 4.65 E-02
2. Average Diluted Conc. During Period uCi/mL 2.07 E-07 1.17 E-07
3. Percent of Applicable Limit  % *
1. Total Release ci 3.61 K00 6.19 E00
2. Average Diluted Conc. During Period uCi/mL 1.47 E-05 1.56 E-05
3. Percent of Applicable Limit  % *
  • C. DISSOLVED AND ENTRAINED CASES
1. Total Release ci 3.53 E-05 1.11 E-05
2. Average Diluted Conc. During Period uC1/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-04)

E. VOLUME OF WASTE RELEASED (prior to dilution) liters l l1.70E06 l1.78E06 l F. VOLUME OF DILUTION WATER USED DURING PERIOD liters l l2.45E08l3.97E08l Will be included in the Annual Report on Environmental Radioactivity Data Page 9 of 16

l DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPOP.T July Through December 1987 Radwaste 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 min '
3. Maximum Time Period for a Batch Release: 298 min l 4. Average Time Period for Batch Releases: 255 min
5. Minimum Time Period for a Batch Release: 198 min
6. Average Stream Flow During Periods of Release of Effluent into a Flowing Stream: 1.58 E06 L/ min CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT 3rd QUARTER 4th QUARTER 3rd QUARTER 4th QUARTER Sr-89 Ci 4.69 E-07
  • Sr-90 Ci 5.27 E-05 1.08 E-04 Ar-41 Ci *
  • Mn-54 Ci 5.15 E-03 4.03 E-03 Co-58 Ci 3.30 E-11
  • Fe-59 Ci 8.10 E-13

Ru-103 Ci *

  • Sb-122 Ci *
  • 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 *
  • Co-141 Cl *
  • Others: Cr-51 Ci * * ,

Fe-55 Ci 4.07 E-03 2.01 E-03 Kr-88 Cl 1.5 E-13

  • CL (above)

Total For Period Ci None None 3.00 E-02 4.64 E-02 Xe-133 Cl 1.03 E-05 1.11 E-05 Xe-135 Ci 2.50 E-05

  • See Table for KDL of Each Nuclide Page 10 of 16 i

DRESDEN NUCLEAR POWER STATION July Through D*cemb*r 1982 TABLE OF MINIMUM DETECTABLE LEVELS Docket Numbers:

FOR LIQUID EFFLUENTS 50-10 50-237 50-249 Radwaste LIQUID EFFLUENTS TOTAL GALLONS RELEASED 2.830.920 MDL (uci/mL)  % OF GALLONS < MDL Sr-89 2 E-08 83.2 Sr-90 7 E-09 50.0 Ar-41 3.07 E-08 0.7 Mn-54 6.16 E-08 97.8 co-58 6.51 E-08 97.8 Fe-59 9.00 E-08 0 Co-60 1.70 E-07 100 2n-65 1.17 E-07 100 Ru-103 S.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 I-133 S.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 Co-141 9.02 E-08 100 ,

Ie-133 1.83 E-07 97.8 Xe-135 6.09 E-08 95.5 l Cr-51 S.77 E-07 100 Fe-SS S E-08 50 Kr-88 Not Available 95 l l

l l

Page 11 of 16 1

DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT July Through December 19aJ7, LPCI LIQUID EFFLUENTS Docket Numbers: 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
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: 2.81 E06 L/ min CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT 3rd QUARTER 4th QUARTER 3rd QUARTER 4th QUARTER Sr-89 Ci *
  • Ar-41 Ci *
  • Mn-54 Ci 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 CL *
  • Cs-134 Ci *
  • Cs-137 C1 1.66 E-05 1.43 E-05 Ba-140 Ci *
  • La-140 Ci *
  • Co-141 Ci *
  • Others: Cr-51 Ci *
  • Fe-55 C1 2.07 E-07 1.09 E-05 Ci *
  • Ci * *

(above)

Total For Period Ci None None 2.08 E-02 4.50 E-05 Xe-133 Ci *

  • Xe-135 Ci * *
  • See Table for MDL of Each Nuclide Page 12 of 16

DRESDEN N CLEAR POWER STATION

. . . July Through D*cembse 1981 TABLE OF MINIMUM DETECTABLE LEVELS Docket Numbers:

FOR LIQUID EFFLUENTS 50-237 50-249 LPCI LIQUID EFFLUENTS TOTAL GALLONS RELEASED 442.680 .

MDL (uCi/mL)  % OF GALLONS < MDL Sr-89 2 E-08 100 Sr-90 7 E-08 100 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 2n-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 I-133 5.34 E-08 100

{

I-135 9.15 E-08 100 Cs-134 7.12 E-06 100 i Cs-137 2.75 E-07 0 i Ba-140 2.09 E-07 100 ,

La-140 2.30 E-08 100 Co-141 9.02 E-08 100 Xe-133 1.83 E-07 100 Xe-135 6.09 E-08 100 cc-51 5.77 E-07 100 Fe-55 5 E-08 66.8 1

I l

t 1

Page 13 of 16  ;

1

DRES6EN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT July Through December 1981 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 FUET.)

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

C1 2.46 E02

b. Dry comprecsible waste, contaminated equip., etc.

C1 2.79 E01

c. Irradiated components, control rods, etc.

Ci 0 .

d. Other (describe)

CL 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 SMIPMENTS (Disposition)

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

i

In accordance with Specifications 6.6.C.1 and 6.9.C of the Technical Specifications, Dresden Station has changed from using the station liquid I radwaste processing equipment to using CNSI's equipment as the normal means for dowatering and s011difyin5 liquid radwaste as described in CNSI's Topical Reportl which was approved by the NRC on April 11, 1983. Dresden Station has c'e' vised its Process Control Program to reflect the fact that vendor services have become the primary means of processing liquid rad waste rather than the permanently installed Station system (Stock System). This change was On-Site Reviewed in accordance with Station procedures. Use of CNSI's NRC approved process control program and equipment will continue to assure that waste processing at Dresden Station is performed in accordance with applicable criteria and requirements. This change was implemented as a more cost effective manner of processing waste as well as reducing radiation exposure to station personnel. Additionally, the revised PCP requires that the topical report for the vendor services must be submitted to the NRC and the solidification / stabilization media must be approved by the licenced burial sites prior to use at Dresden. The PCP (Revision 1, February,1988) is attached.

I CNSI-2 4313-01354-OlP-A, "Mobile Cement Solidification Systam".

15 of 16

DRE3 DEN NUGLEAR POWER STATION

. . . EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT July Through December 1981 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 C1 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 further 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

_ . _ . _ ~__

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