ML20210H839

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Effluent & Waste Disposal Semiannual Rept,Jul-Dec 1985
ML20210H839
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 12/31/1985
From: Scott D
COMMONWEALTH EDISON CO.
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
86-84, NUDOCS 8604030193
Download: ML20210H839 (16)
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DRESDEN NUCLEAR POWER STATION EFFLUENT MG WASTE DISPOSAL SEMIANNUAL REPORT Juiv Through December 19 85 GASEOUS EFFLUENTS SL?!MATION OF ALL RELEASES Docket Numbers: 50-10, 50-237, 50-249 UNIT lI.d QUARTER 4th0UARTER A. FISSION AND ACTIVATION CARER

1. Total Release Ci 6.92E+02 3.62E+02 2 Averane Release Rate for Perind uCi/sec 8.71E+01 4.55E+01 3 Percent of Techniemi Snecificmeinn T imi t-  %

B. IODINES

1. Total Iodine-131 C1 1.74E-02 4.35E-03
2. Average Re1 ease Rate for Period uCi/sec 2.19E-03 5.47E-04
3. Percent of Technical Soecification Limit  %

C. PARTICULATES

1. Partictilmeen with half-liv.. SA anv. C1 2.45E-02 1.14E-02

! 2. Average Release Rate for Period uCi/sec 3.08E-03 1.44E-03

3. Percent of Technical Specification Limit  % * *
4. Gross Alpha Radioactivity C1 4.12E-06 1.66E-05 0604030193 851231 I

PDR ADOCK 05000010 l D. TRITIUM R PDR.

l l 1. Total Release C1 7.72E00 1.24E00

2. Average Release Rate for Period uCi/sec 9.71E-01 1.56E-01
3. Percent of Technical Specification Limit  %

l

  • Will be included in the Annual Report on Environmental Radioactivity Data l

l

, uncsurN abcLt.AR POWER STATION UNIT i EFFLUENT AND k'ASTE DISPOSAL SEMIANNUAL REPORT July THROUGH Dacamber 19 85 D-1 Chimney GASEOUS EFFLUENTS GROUND LEVEL RELEASES SEMI-ELEVATED RELEASES XX ELEVATED RELEASES Docket No. 50-10 CONTINUOUS MODE BATCH MODE UCLIDES RELEASED ' UNIT 3rd QUARTER 4th QUARTER 3 1 QUARTER 4A QUARTER

. FISSION GASES Ci Xe-138 Ci *

  • Xc-135m Ci *
  • Kr-87 Ci *
  • Kr-88 Ci *
  • Kr-85m Ci
  • Xe-135 Ci Xe-133 Ci Others: C1 Ci TOTAL Ci NnNr vnvr IODINES I-131 Ci *
  • I-133 Ci *
  • I-135 Ci *
  • TOTAL Ci vnvr vnvr PARTICULATES Sr-89 Ci 1.89E-07
  • Sr-90 Ci 1.41E-07 1.84E-07 Cr-51 Ci Mn-54 Ci 6.04E-08 5.89E-07 Co-58 Ci
  • 2.37E-07 Fe-59 Ci
  • Co-60 Ci 2.30E-05 6.26E-06 Zr-95 Ci
  • Nb-95 Ci Ru-103 Ci
  • Aa-110m Ci Sb-124 Ci I-131 Ci
  • Cs-134 Ci Cs-136 Ci Cs-137 Ci 6.32E-06 2.05E-06 Ba-140 Ci Ce-141 Ci Ce-144 Ci Zn-65 Ci Ba-133 Ci
  • Sb-125 Ci
  • Othirs: Ci C1 C1 C1 Ci TOTAL C1 2.97E-05 9.32E-06 NONE MONF
  • See Table for MDL of Each Nuclide

DRESDEN NUCLEAR POWER STATION TABLE OF MINIMUM DETECTABLE LEVELS FOR GASEOUS EFFLUENTS D-1 Chimnev GASEOUS EFFLUENTS AVERAGE FLOW 50,000 cfm Docket No. 50-10 MDL (uCi/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-06 100 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 Sr-89 1.10E-15 83 Sr-90 1.00E-15 0 Cr-51 1.60E-13 100 Mn-54 3.30E-14 91 Co-58 3.50E-14 99 Fe-59 5.30E-14 100 Co-60 8.70E-14 23 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 Cs-134 1.60E-12 100 Cs-136 5.30E-14 100 Cs-137 3.80E-14 7 Ba-140 6.70E-14 100

'Ce-141 4.70E-14 100 Ce-144 2.00E-13 100 Zn-65 5.90E-14 100 Ba-133 2.60E-14 100 Sb-125 1.80E-14 100 Others:

unE6 DEN NUCLEAR POWER STATION UNIT 2/3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Julv THROUGH December 19 85 2/3 Ch'anev GASEOUS EFFLUENTS ,

_,_ GROUND LEVEL RELEASES SEMI-ELEVATED RELEASES xx ELEVATED RELEASES Docket Nos. 50-237, 50-249 CONTINU0US MODE BATCH MODE JCLIDES RELEASED UNIT 1r.d_ QUARTER Q QUARTER M QUARTER 4 th. QUARTER 3 FISSION GASES Ci Xe-138 Ci 3.13E+02 7.7sv+nt X,-135m Ci 7.04E+01 1.63E+01 Kr-87 Ci 3.51E00 4.32E-01 Kr-88 Ci 6.66E00

  • Kr-85m Ci 4.60E00 * -

Kr-85 Ci 2.12E-02 6.67E-03 Xe-135 Xe-133 Ci Ci 2.52E+02 2.68E+01 4.43E+01 2.85E00 j

Others: C1 Ci TGTAL Ci 6.77E+02 1.41E+02 NONE NONE IODINES I-131 Ci 1.67E-02 3.99E-03 I-133 Ci 8.10E-02 1.25E-02 I-135 Ci 1.33E-01 1.65E-02 TOTAL C1 2.31E-01 3.30E-02 NONE NONE PARTICULATES Sr-89 Ci 2.08E-03 3.14E-03 Sr-90 Ci 1.46E-05 2.07E-05 _

Cr-51 Ci *

  • Mn-54 C1 2.40E-05 5.38E-05 Co-58 Ci
  • 2.89E-06 Fe-59 Ci 8.llE-06 l Co-60 Ci 3.13E-04 3.95E-04 Zr-95 Ci
  • Nb-95 Ci Ru-103 Ci
  • An-110m Ci
  • Sb-124 Ci
  • I-131 C1 2.llE-03 5.74E-04 Cs-134 Ci *
  • Cs-136 Ci *
  • Cs-137 Ci 4.61E-05 3.61E-05 Ba-140 21 1.14E-02 2.93E-03 -

Ce-141 Ci 2.14E-04 4.99E-05 Ce-144 Ci

  • Zn-65 Ci *
  • Ba-133 Ci
  • Sb-125 Ci
  • Othars: Ci C1 C1 Ci _

Ci TOTAL Ci 1.62E-02 7.20E-03 NONE NONE

  • See Table for MDL of Each Nuclide

DRESDEN NUCLEAR POWER STATION TABLE OF MINIMUM DETECTABLE LEVELS FOR GASEQUS EFFLUENTS 2/3 CHIMNEY GASEOUS EFFLUENTS AVERAGE FLOW 3RD QUARTER:263K cfm Docket Nos. 50-237, 50-249 4TH QUARTER:257K cfm MDL (uCi/cc)  % OF TIME < MDL

1. FISSION GASES Xa-138 1.65E-07 53 Xe-135m 6.67E-08 70 Kr-87 5.30E-08 97 Kr-88 8.97E-08 98 Kr-85m 2.73E-08 86 Kr-85 5.73E-06 0 Xe-135 2.72E-08 35 Xe-133 6.65E-08 79 Others:
2. 10 DINES I-131 3.80E-14 0 I-133 4.40E-14 0 I-135 7.90E-14 29
3. PARTICULATES Sr-89 1.10E-15 0 Sr-90 1.00E-15 0 Cr-51 1.60E-13 100 Mn-54 3.30E-14 78 Co-58 3.50E-14 98 5.30E-14 98 Fe-59 8.70E-14 5 Co-60 3.10E-14 100 l Zr-95

-1.90E-14 100 Nb-95 1.90E-14 100 Ru-103 1.90E-14 100 Ag-110m 2.40E-14 100 Sb-124 2.00E-14 27 I-131 1.60E-12 100 Cs-134 5.30E-14 100 Cs-136 3.80E-14 54 Cs-137 10 Ba-140 6.70E-14 4.70E-14 59 Ce-141 100 Ce-144 2.00E-13 5.90E-14 100 Zn-65 100 Ba-133 2.60E-14 1.80E-14 100 Sb-125 Others: La -140 3.00E-14 Detected but not reported.

, use.SDi.N NUCLEAR POWER STATION UNITg EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY THROUGH DECEMBER 19 85 2/3 VENT GASEOUS EFFLUENTS GROUND LEVEL RELEASES XX SEMI-ELEVATED RELEASES ELEVATED RELEASES Docket Nos. 50-237, 50-249 CONTIST0US MODE BATCH MODE UCLIDES RELEASED UNIT InLQUARTER m QUARTER g QUARTER m QUARTER

. FISSION GASES Ci Xe-138 Ci *

  • X -135m C1 *
  • Kr-87 Ci *
  • Kr-88 Ci *
  • Kr-85m Ci
  • Xe-135 Ci 1.39E+01 1.92E+02 Xe-133 Ci 1.09E00 2.68E+01 Others: Ci C!

TOTAL C1 1.SnF+01 2.21E+02 NONE l NOME 10 DINES I-131 Ci 7.02E-04 3.64E-04 I-133 Ci 3.64E-03 1.14F-03 I-135 Ci 5.44E-03 1.02E-03 TOTAL Ci 9.78E-03 2.52E-03 NONE MnMr PARTICULATES Sr-89 Ci 6.46E-05 3.76E-06 Sr-90 Ci 7.75E-Og 2.33E-06 Cr-51 Ci 9.17E-04 1.41r-na Mn-54 Ci 8.49E-04 9.?OF-04 Co-58 Ci 2.10E-04 6.92E-09 Fe-59 Ci 4.38E-04 1.42E-04 Co-60 Ci 4.39E-03 2.79E-03 Zr-95 Ci 1.62E-05

  • Nb-95 Ci 1.95E-06 9.62E-07 Ru-103 Ci 9.62E-06 2.40E-06 An-110m Ci 1.22E-05 Sb-124 Ci 2.75E-05 1.79E-05 I-131 Ci 1.42E-04 7.40E-05 Cs-134 Ci
  • Cs-136 C1 3.78E-06 3.47E-06 Cs-137 Ci 5.75E-05 4.88E-05 Ba-140 Ci 1.03E-03 3.80E-04 Ce-141 Ci 1.14E-05 4.35E-06 Ce-144 Ci 6.29E-06
  • Zn-65 Ci 2.98E-05 4.95E-06 Ba-133 Ci Sb-125 Ci
  • 1.47E-05 Oth7rs: Ci _

Ci C1 C1 Ci TOTAL Ci 8.29E-03 4.22E-01 MANF MnMF

  • See Table for MDL of Each Nuclide

DRESDEN NUCLEAR POWER STATION TABLE OF MINIMUM DETECTABLE LEVELS FOR GASEOUS EFFLUENTS 2/3 VENT GASEOUS EFFLUENTS AVERAGE FLOW D-2: 110K cfm

~

Docket Nos. 50-237, 50-249 (uci/cc)

MJD  % OF TIME < MDL

1. FISSION GASES Ie-138 1.31E-07 100 Xe-135m 6.67E-08 100 Kr-87 8.47E-08 100 Kr 1.46E-07 100 Kr-85m 2.73E-08 96 Kr-85 5.73E-06 100 Xe-135 4.33E-08 42 Xe-133 1.14E-07 85 Others:
2. IODINES I-131 3.80E-14 6 I-133 4.40E-14 9 I-135 7.90E-14 37
3. PARTICULATES~

Sr-89 1.10E-15 0 Sr-90 1.00E-15 -

0 Cr-51 1.60E-13 20 Mn-54 3.30E-14 0 Co-58 3.50E-14 9 Fe-59 5.30E-14 17 Co-60 8.70E-14 0 Zr-95 3.10E-14 97 Nb-95 1.90E-14 94 l

! Ru-103 1.90E-14 83 Ag-110m 1.90E-14 97 l

Sb-124 2.40E-14 66 I-131 2.00E-14 14 Cs-134 1.60E-12 100 Cs-136 5.30E-14 94 l

3.80E-14 3 Cs-137 l Be-140 6.70E-14 6 Ce-141 4.70E-14 74 l Co-144 2.00E-13 71 l Zn-65 5.90E-14 94 l Ba-133 2.60E-14 100 Sb-125 1.80E-14 94 l

Others: La-140 3.00E-14 Detected but not reported.

l L. .

DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY THROUGH DECEMBER 19 85 LIQUID EFFLUENTS SLMiATION OF Ai.L RELEASES Docket Nos: 50-10, 50-237, 50-249 UNIT 3rdQUARTER 4th QUAhTIR A. FISSION AND ACTIVATION PRCSticTR I

1. Total Release (nne dar 1 ~4 -d m . ese.e 21 -6 Ci 1.25E-01 3.70E-05
2. Averace Diluted cane. nn-4,e h-4na uCi/mi 2.60E-10 1.09E-13 3 Fercent of Annifcable T.4-4 e  % * *
3. TRITIUM
1. Total Release Ci 6.74E-01 2.29E-02
2. Averare Diluted Cone. Durine Pe-ind uCi/mi 1.40E-09 6.72E-11
3. Pere (nt of Aeolicable Limfe  % * *
. DISSOLVED AND ENTRAINED CASES
1. Total Release Ci < MDL < MDL
2. Averte Diluted Conc. Durine Period uCi/ml < MDL < MDL
3. Percent of Applicable Limit  % *
  • GROSS ALPHA RADIOACTIVITY 1 Total Release C1 1.93E-04 g,77t_o7 VOLUME OF WASTE RELEASED (orior to dilution) liters 1.39E+06 4.60E+05 VOLUME OF DILUTION WATER USED DURING PSICD i liters 4.80E+11 3.41E+11 k *WILL BE INCLUDED INTHEANNUAL REPORT ON ENVIRGETM/A PX@R@YYd5UMRfoU%MB

DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANN1tAL REPORT JULY THROUGH DECEMBER 19 85 RADWASTE LIQUID EFFLUENTS

1. Number of Batch Releases: 7
2. Total Time Period for Batch Releases: 6,115 min.
3. Maximum Time Period for a Batch Release: 2,295 min.
4. Average Time Period for Batch Releases: 874 min.
5. Minimum Time Period for a Batch Release: 354 min.
6. Average Stream Flow During Periods of Release of Effluent into a Flowing Stream: 6.06E+05 liters / min.

Docket Nos: 50-10, 50-237, 50-249 CONTINUOUS ~ MODE BATCH MODE M14A== Rela ==ad Unit 3rd QUARTER 4th QUARTER 3rd QUARTER 4th QUARTER

-Sr-89 Ci

  • No Sr-90 C1 1.79E-03 DISCHARGE

'Ar-51 Ci

'C -58 Ci 4.13E-05 Fr-59 Ci

  • C -60 C1 2.79E-02 Zn-65 Ci
  • Ru-103 Ci
  • Sb-122 Ci
  • Sb-124 Ci
  • I-133 Ci
  • I I-135 Ci * -

Cr-136 Ci 4.06E-03 C"-137 Ci 8.92E-02

}.g-140 Ci

  • La-140 Ci 6.38E-05 Ca-141 Ci 6.50E-05 Others: Cr-51 C1 1.77E-04 Tc-99m Ci 3.78E-05 Ci Ci j Tc*al F riod Ci NONE NONE 1.25E-01 Xe-133 Ci
  • Xe-135 Ci * \/
  • See Table for MDL of Each Nuclide

DRESDEN NUCLEAR POWER-STATION Docket Nos. 50-10 TABLE OF MINIMUM DETECTABLE LEVELS 50-237,'50-249 FOR LIQUID EFFLUENTS Radumsta LIQUID EFFLUENTS TOTAL GALLONS RELEASED 1.36E+05 MDL (uci/ml)  % of callons < MDL Sr-89 4.00E-08 100 Sr-90 9.00E-C9 0 Ar 3.07E-08 100 Mn-54 6.06E-08 14 Co-58 6.77E-08 78 Fe-59 8.90E-08 100 Co-60 1.35E-07 0 1.10E-07 100 Zn-65 S.39E-08 100 Ru-103 7.01E-08 100 Sb-122 4.06E-08 100 Sb-124 100 I-131 7.42E-08 100 I-133 5.34E-08 100 1-135 9.15E-08 Cs-134 6.32E-08 0 Cs-137 8.90E-08 0 Ba-140 2.09E-07 100 2.30E-08 78 La-140 1.00E-07 78 Ce-141 7.70E-08 100 Xe-133 6.26E-08 100 Xe-135 Cr-51 6.20E-07 78 Tc-99m 5.32E-08 78 Ce-l44 4.05E-07 100 Kr-88 2.23E-07 100 Xe-133m 5.78E-07 100 Xe-138 1.89E-07 100 Kr-87 1.31E-07 100 Mo-99 4.92E-07 100 L

e . l l

DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEV.IANNUAL REPORT JULY THROUGH DECEMBER 19 85 LPCI LIQUID EFFLUENTS

1. Number of Batch Releases: 81
2. Total Time Period for Batch Releases: 100 min.
3. Maximum Time Period for a Batch Release: 1.24 min.
4. Average Time Period for Batch Releases: 1.24 min.
5. Minimus Time Period for a Batch Release: 1.24 min
6. Average Strear Flow During Periods of Release of Effluent into a Flowing Stream: 3.10E&O6 liters / min.

Docket Nos; 50-237, 50-249 CONTINUOUS MODE BATCH MODE b -f %s Released Unit 3rd QUARTER 4th QUARTER 3rd QUARTER 4th QUARTER Sr-89 C1 1.20E-06

  • Se-90 Ci 4.10E-06
  • Ar-41 Ci *
  • Mn-56 Ci 2.58E-05 3.60E-06 Cc-58 Ci =
  • Fr-59 Ci *
  • Cm-60 Ci 1.49E-04 3.08E-05 2n-65 C: *
  • Ru-kq3 Ci *
  • Sb-122 Ci *
  • Sb-124 Ci *
  • I-133 Ci *
  • I-135 Ci *
  • C -134 Ci *
  • C -137 Ci 5.47E-05 2. 60E- 06 Ba-140 Ci *
  • La-140 Ci *
  • Ce-141 Ci *
  • Others: C1 Ci Ci Ci Total F eriod Ci NONE NONE 2.35E-04 3.70E-05 Xe-133 Ci *
  • Xe-135 Ci * *
  • See Table for MDL of Each Nuclide u - . , . _ _ , - . - . _ . . _ _ . . _ . ._-..-_. - ,. - -_.-_

7, -. .

DRESDEN NUCLEAR POWER STATION TABLE OF MINIMUM DETECTABLE LEVELS Docket Nos. 50-237, 50-249 FOR LIQUID EFFL11ENTS LPCI- LIQUID EFFLUENTS- TOTAL GALLONS RELEASED 3.52E+05 MDL (uC1/ml)  % o' Gallons < MDL Sr-89 4.00E-08 81 Sr-90 9.00E-09 62 Ar-41 '3. 07E-08 100 Mn-54 1.90E-07 79 Co-58 1.93E-07 100 Fe-59 2.84E-07 100 Co-60 4.05E-07 15 Zn-65 2.94E-07 100 Su-103 5.39E-08 100 Sb-122 7.01E-08 100 Sb-124 4.06E-08 100 I-131 2.39E-07 100 1-133 5.34E-08 100 I-135 9.15E-08 100 Cs-134 2.01E-07 100 Cs-137 2.47E-07 17 Ba-140 2.09E-07 100 La-140 2.30E-08 100 Ce-141 3.85E-07 100 7.70E-08 100 Xe-133 2.27E-07 100 Xe-135 Ce- 144 1.59E-06 100 Kr-88 7.90E-07 100 Xe-133m 1.99E-06 100 Xe-138 6.38E-07 100 Cr-51 2.03E-06 100 Kr-87 3.86E-07 100 100 j Mo-99 1.53E-06 I

s ..

DRESDEN NUCLEAR POWER STATION EFFLUENT AhT WASTE DISI'OSAL SEMIANNUAL REPORT JULY THROUGH. DECEMBER 19f5 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Dockets 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 ceriod m3 6. us+n,
a. Spent resins , filter siivioma , evaporator bottons, etc. C1 1.76E+03 m3 3.50E+02
b. Dev compressible unste, contaminated equip. , etc. pi_ 9.89E00 M_ 1.bbE+01
c. Irradiated %-its , control rods, etc. Ci 6. ME+04 m3
d. Other (dsscribe) C1
2. Estimate of Major Nuclide Composition (by type of waste)

Z Ci

a. Co-60 52.8  % 9.29E+02 Fe-55 37.0  % 6.SIE+02 3tn-54 4.4  % 7.74E+01 Cs-137 3.1  % 5.46E+01 Other 2.7  % 4.75E+01
b. Co-60 64.0  % 6.33E00 Fe-55 28.8  % 2.85E00 Mn-54 4.3  % 4.25E-01 Cs-137 2.8  % 2.77E-01 Other 0.1 I 9.89E-03
c. Co-60 52.3  % 3.31E+04 Fe-55 41.2  % 2.60E+04 Ni-59 0.I  % 6.32E+01 Ni-63 6.3  % 3.98E+03 Other 0.1  % 6.32Efdl

{ d.  %

3. Solid Waste Disposition NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION 125 MOTOR FREIGHT (EXCLUSIVE USE ONLY) BARNWELL, S.C.

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

B. IRRADIATED FUEL SHIPMENTS (Disposition)

NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION NONE

f -

=

DRESDEN NUCLEAR POWER STATION

~

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY THROUGH DECEMBER 19 85 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: 1
2. Total Activity Released: 7.09E-03 Ci
  • This is the maximum estimated total. For further information, refer to Deviation Variance Report # 12-8-85-101.

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j t.y R.R. #1 5 Morris, llNnois 80460 Telephone 815/942-2920  ;

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January 21, 1986 DJS LTR: # d6-84 [

n ical1T RGullih,n ,

Mr. James G. Keppler 1[2;p k*f_

I -

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[ Regional Adminigtrator -

ig -

l 1 Directorate of Inspection and Enforcement [g5 h. ~

l Region III -

51'-

l f g pis,s_ _ t

U.S. Nuclear kegulatory Cornission 799 Roocevelt Road'
  1. 7 Uh"

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- Glen Ellyn,~1111nois 6b137 l

ST'BJECT: Dresden Station Operating Report NRC Dockets 50-10, 50-237, and 50-249.  ;

Dear Mr. Keppler:

f 1

I i Enclosed is the radioactive effluent report far July through December, .

! ~1985 for Dresden Nuclear Power Station.  !

t i l l One copy of this report is provided for your use and 39 copies i

.! are being submitted.directly to Mr. D. Eisenhut, Deputy Director of the j Office of Nuclear Reactor Regulation. ,

r t

j e

j Sincerely, l 1

! D. . Scott f l Station Manager Dresden Nuclear Power Station

! DJS RB sp i i

Enclosure i i

i cc: R. Berg e i J. C. Golden File /NRC File / Numerical g( i I. l.,ab, t  :

1' }

ff.B E b l- - - _ . - - . _ , _ . _ . - ,-..__,--__..m_ _

r 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 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 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(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(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 Cross 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. Thia sample is sent to a vendor to be analyzed for Sr-89, Sr-90, Fe-55, and Gross Alpha activity.

_

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