ML20209D698

From kanterella
Jump to navigation Jump to search
Effluent & Waste Disposal Semiannual Rept,Jan-June 1986
ML20209D698
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 06/30/1986
From: Scott D
COMMONWEALTH EDISON CO.
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
86-527, NUDOCS 8609090409
Download: ML20209D698 (16)
v • d • e


Text

, ,

DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January Through June 19 86 m GASEOUS EFFLUENTS /

SUMMATION OF ALL RELEASES Docket Nos. 50-10, 50-237,30-249 UNIT lst QUARTER 2nd QUARTER A, FISSION AND ACTIVATION CASES

1. Total Release Ct 3.59E00 3.50E00 2, Average Release Rate for Perind uCi/sec 4.62E-01 4.45E-01 3- Percent of Technical Soecifientinn Tinir  %
1. Total Iodine-131 Ci 9.61E-03 8.15E-03
2. Average Release Rate for Period uCi/sec 1.24E-03 1.04E-03
3. Percent of Technical Specification Limit  %

C. PARTICULATES

1. Particulaten with knif-livon 3R dnye Ci 7.82E-03 5.08E-03
2. Average Release Rate for Period uC1/sec 1.01E-03 6.46E-04
3. Percent of Technical Specification Limit  % * *
4. Gross Alpha Radioactivity Ci 5.40E-06 2.53E-06 D. TRITIUM
1. Total Release Ci 7.16E-01 1.03E00
2. Average Release Rate for Period uCi/sec 9.21E-02 1.31E-01
3. Percent of Technical Specification Limit  % * *
  • Will be included in the Annual Report on Environmental Radioactivity Data 8609090409 860630 }EY7 f PDR ADOCK 05000010 R PDR [I (
  • DRESDEN NUCLEAR POWER STATION UNIT I EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January THROUGH June 1986 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 lst QUARTER 2ndQUARTER lstQUARTER 2nd QUARTER

. FISSION GASES Ci Xe-138 Ci *

  • Xe-135m Ci *
  • Kr-87 Ci *
  • Kr-88 C1 *
  • Kr-85m Ci *
  • Xe-135 *
  • Ci Xe-133 Ci * * -

Others : Xe-133n Ci *

  • Ci TOTAL Ci NONE NONE

. 10 DINES I-l31 Ci

  • 5.14E-06 I-133 Ci *
  • I-135 Ci *
  • TOTAL Ci 5.14E-06 NONE NONE

. PARTICULATES Sr-89 Ci *

  • l Cr-51 Ci *
  • Mn-54 Ci 2.46E-07 3.58E-07 Co-58 Ci *
  • Fe-59 Ci *
  • Co-60 C1 1.4RF-05 4.03E-06 l Zr-95 Ci *
  • Nb-95 Ci *
  • Ru-103 Ci
  • 1.50E-06 An-110m Ci *
  • Sb-124 Ci
  • 3.71E-07 Cs-134 Ci
  • Cs-136 Ci
  • l Cs-137 C1 4.67E-06 7.41E-06 Ba-140 Ci
  • Ce-141 Ci *
  • Ce-144 Ci *
  • Zn-65 Ci *
  • Ba-133 Ci *
  • Sb-125 Ci *
  • l C1 C1 Ci l Ci l TOTAL C1 2.47E-05 1.37E-05 NONE NONE
  • See Table for MDL of Each Nuclide J

DRESDEN NUCLEAR POWER STATION January through June, 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 Xe-138 5.08E-08 100 Xe-135m 2.14E-08 100 Kr-87 3.43E-08 100 Kr-88 -

6.14E-08 100 Kr-85m 1.86E-08 100 Kr-85 4.58E-06 100 Xe-135 1.80E-08 100 Xe-133 4.42E-08 100 Others: Xe-133m 1.56E-07 100

2. I0 DINES I-131 3.12E-14 85 I-133 3,13E-14 100 I-135 6.39E-14 100
3. PARTICULATES Sr-89 1.00E-15 100 Sr-90 1.00E-15 100 Cr-51 2.29E-13 100' Mn-54 2.78E-14 99 Co-58 2.62E-14 100 Fe-59 4.33E-14 100 Co-60 6.39E-14 50 Zr-95 4.86E-14 100 Nb-95 2.61E-14 100 Ru-103 2.71E-14 89 Ag-110m 2.74E-14 100 Sb-124 1.96E-14 100 1-131 2.88E-14 99 Cs-134 3.12E-14 100 Cs-136 3.14E-14 100 Cs-137 3.37E-14 10 Ba-140 1.08E-13 100 Ce-141 3.69E-14 100 Ce-144 1.52E-13 100 2n-65 4.44E-14 100

. Ba-133 2.60E-14 100 Sb-125 7.78E-14 100 Others:

Mo-99 2.16E-13 100 La-140 1.25E-14 100

DRESDEN NUCLEAR POWER STATION UNIT 2/3

.' EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January THROUGH June 1986 2/3 Chimney GASEOUS EFFLUENTS GROUND LEVEL RELEASES SEMI-ELEVATED RELEASES XX ELEVATED RELEASES Docket Nos. 50-237, 50-249 CONTINUOUS MODE BATCH MODE IUCLIDES RELEASED UNIT Ist QUARTER 2nd QUARTER istQUARTER 2nd QUARTER

, FISSION GASES Ci Xe-138 Ci

  • X*-135m Ci 8.64E-01 Kr-87 Ci
  • 5.18E-01 Kr-88 Ci
  • 7.78E-01 Kr-85m Ci
  • 1.73E-01 Kr-85 Ci 1.32E-03 1.54E-03 Xe-135 Ci 8.64E-01 4.32E-01 Xe-133 Ci 6.91E-01 Others :Xe-133m Ci Ci TOTAL Ci 2.42E00 1.90E00 NONE NOME

. 10 DINES I-131 Ci 5.57E-04 5.03E-04 I-13) Ci 2.69E-03 2.41E-03 I-135 C1 2.37E-03 2.57E-03 TOTAL Ci 5.62E-03 5.48E-03 NONE NONE

. PARTICULATES Sr-89 Ci 1.83E-04 1.42E-04 Sr-90 Ci 2.34E-06 3.30E-06 Cr-51 Ci

  • Mn-54 Ci 1.09E-05 6.41E-05 Co-58 Ci
  • 1.02E-06 Fe-59 Ci
  • 6.97E-06 Co-60 Ci 1.67E-04 2.06E-04 Zr-95 Ci
  • Nb-95 Ci Ru-103 Ci 2.21E-05 8.97E-06 l An-110m Ci Sb-124 Ci
  • I-131 C1 3.92E-05 3.45E-05 Cs-134 Ci 1.92E-06 Cs-136 Ci *
  • Cs-137 Ci 1.68E-05 3.68E-05 Ba-140 Ci 5.66E-04 4.30E-04 Ce-141 Ci Ce-144 Ci Zn-65 Ci
  • Ba-133 Ci *
  • Sb-125 Ci *
  • C1 Ci C1 Ci TOTAL Ci 1.01E-03 9.34E-04 NONE NONE
  • See Table for MDL of Each Nuclide

DRESDEN NUCLEAR POWER STATION January through June, 1986 TABLE OF MINIMUM DETECTABLE LEVELS 1st Quarter: 265 kcfm FOR CASEOUS EFFLUENTS 2nd Quarter: 257 kefm 2/3 Chimney GASEOUS EFFLUENTS AVERAGE FLOW Docket Nos. 50-237, 50-249 MDL (uCi/cc)  % OF TIME < MDL

1. FISSION GASES Xe-138 1.72E-07 100 Xe-135m 7.55E-08 99 Kr-87 4.43E-08 99 Kr-88 8.85E-08 99 Kr-85m 2.73E-08 99 Kr-85 7.06E-06 0 Xe-135 2.72E-08 98 Xe-133 6.19E-08 99 Others: Xe-133m 2.30E-07 100
2. 10 DINES I-131 3.12E-14 4 I-133 3.13E-14 21 I-135 6.39E-14 46
3. PARTICULATES Sr-89 1.00E-15 0 Sr-90 1.00E-15 0 Cr-51 2.29E-13 100 Mn-54 2.78E-14 51 Co-58 2.62E-14 96

. Fe-59 4.33E-14 97 Co-60 6.39E-14 6 Zr-95 4.86E-14 100 2.61E-14 100 Nb-95 Ru-103 2.71E-14 87 2.74E-14 100 Ag-110m 1.96E-14 100 Sb-124 2.88E 39 I-131 3.12E-14 97 Cs-134 3.14E-14 100 Cs-136 3.37E-14 29 Cs-137 20 Ba-140 1.08E-13 3.69E-14 100 Ce-141 100 Ce-144 1.52E-13 100 Zn-65 4.44E-14 100 Ba-133 2.60E-14 100 Sb-125 7.78E-14 Others: Mo-99 2.16E-13 100 La-140 1.2SE-14 Detected, but not reported.

1

, , , .r.. --.---.,--,-w y . . , - . - -

~ . . - - - -r.-.-e, .. , - - -- ,

DRESDEN NUCLEAR POWER STATION UNIT 2/3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT J<nu~ry THROUGH Jun, 19 86 2/3 Vent GASEOUS EFFLUENTS GROUND LEVEL RELEASES xx SEMI-ELEVATED RELEASES ELEVATED RELEASES Docket Nos. 50-237, 50-249 CONTINUOUS MODE BATCH MODE iUCLIDES RELEASED UNIT lA QUARTER 2ndQUARTER 1st QUARTER 2nd QUARTER FISSION GASES Ci Xe-138 Ci *

  • Xe-135m Ci *
  • Kr-87 *
  • Ci Kr-88 Ci
  • Xe-135 C1 1.17E00 5.70E-01 Xe-133 Ci
  • 1.03E00 Others :Xe-133m Ci *
  • Ci TOTAL Ci 1.17E00 1.60E00 NONE NONE

. IODINES I-131 Ci 1.26E-04 1.27E-04 I-133 Ci 1.30E-03 9.66E-04 I-135 Ci 2.56E-03 1.57E-03 TOTAL Ci 3.99E-03 2.66L-03 NONE NONE

. PARTICULATES Sr-89 C1 4.31E-05 2.03E-05 Sr-90 Ci 7.22E-06 6.08E-06 Cr-51 Ci 1. 8 5 E- 04 4.40E-04 Mn-54 C1 4. 99 E- 04 5.95E-04 i Co-58 Ci 1. 96E- 04 1.98E-04 Fe-59 C1 3.73E-05 1.34E-04 Co-60 C1 4.68E-03 2.30E-03 Zr-95 C1 6.29E-06 Nb-95 Ci Ru-103 Ci

  • 6.27E-07 An-110n Ci 1.65E-05 1.38E-05 Sb-124 C1 2.15E-07 5.64E-06 I-131 C1 4.32C-05 1. 35 E-0 5 Cs-134 Ci
  • Cs-136 Ci Cs-137 Ci 1.88E-04 5.16E-05 Ba-140 C1 2.I1E-04 1.09E-04 Cc-141 Ci 9.70E-07
  • Ce-144 Ci Zn-65 Ci 1.05E-04 6.54E-05 Ba-133 Ci *
  • I Sb-125 Ci 8.51E-06
  • l Oth ;rs : Mo-99 Ci 5.61E-04 3.67E-04 l Ci l Ci l C1 Ci l TOTAL Ci 6.79E-03 4.13E-03 NONE NONE l
  • See Table for MDL of Each Nuclide l l

,_ - _ _ - - .. . _ _ . ~ _ _ _ _ - -

i ..

l' l

i DRESDEN NUCLEAR POWER STATION January through June, 1986 TABLE OF MINIMUM DETECTABLE LEVELS FOR GASEOUS EFFLUENTS D2: 110K cfm i 2/3 Vent GASEOUS EFFLUENTS AVERAGE FLOW D3: 110K cfm Docket Nos. 50-237, 50-249 MDL (uCi/cc)  % OF TIME < MDL l 1. FISSION GASES l

l Xe-138 5.08E-08 100 Xe-135m 2.14E-08 100 l Kr-87 3.43E-08 100 l Kr-88 6.14E-08 100 Kr-85m 1.86E-08 100 l Kr-85 4.58E-06 100 .

! Xe-135 1.80E-08 89 l Xe-133 4.42E-08 97 Others: Xe-133m 1.56E-07 100 l

2. 10 DINES 3.12E-14 4 I-131 3.13E-14 18 I-133 6.39E-14 35 I-135
3. PARTICULATES Sr-89 1.00E-15 0 Sr-90 1.00E-15 0 Cr-51 2.29E-13 46 Mn-54 2.78E-14 0 Co-58 2.62E-14 0 l

! Fe-59 4.33E-14 45 Co-60 6.39E-14 0 l 96 Zr-95 4.86E-14 Nb-95 2.61E-14 100 Ru-103 2.71E-14 97 Ag-110m 2.74Ei14 66 Sb-124 1.96E-14 87 I-131 2.88E-14 50 3.12E-14 100 Cs-134 3.14E-14 100 Cs-136 3.37E-14 0 Cs-137 1.08E-13 15 l

Ba-140 3.69E-14 96 Ce-141 1.52E-13 100 Ce-144 24 Zn-65 4.44E-14 100 Ba-133 2.60E-14 96 Sb-125 7.78E-14 Others: Mo-99 2.16E-13 45 La-140 1.25E-14 Detected, but not reported.

l >

DRESDEN NUCLEAR POWER SIATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

, January THROUGH June 19 86 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES Docket Nos. 50-10, 50-237, 50-249 UNIT is(QUARTER 2ndQUARTER

4. FISSION AND ACTIVATION PRODUCTR I.

Total Relea=e (nnt inct_ ev4efin,.gneoc niph. Ci 1.27E-02 1.19E-04

2. Aversee Diluted Cnne. Diiving PavinA uCl/ml 5.18E-10 1.49E-12
3. Percent of Anolienhie Limie  % * *
3. TRITIUM
1. Total Release Ci 1.02E00 2.52E-03
2. Average Diluted Conc. Durine Period uCi/ml 4.16E-08 3.15E-11
3. Percent of Apolicable Limit * *
2. DISSOLVED AND ENTRAINED GASES
1. Total Release Ci 4.06E-05 < MDL
2. Averge Diluted Conc. Durine Period uCi/mi 1.66E-12 < MDL
3. Percent of Applicable Limit  % * *

'. GROSS ALPHA RADIOACTIVITY 1 Total Release Ci 5.73E-06 < MDL VOLUME OF WASTE RELEASED (orior to dilution) liters 1.58E+06 1.00E+06 VOLUME OF DILUTION WATER IMm DtRINF. PERIOD i liters 2.45E+10 7.99E+10

~

  • Will be included in the Annunt Report on Environmental Radioactivity Data

DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January THROUGH June 19 86 Radwaste LIQUID EFFLUENTS

1. Number of Batch Releases: 13
2. Total Time Period for Batch Releases: 3,279 min.
3. Maximum Time Period for a Batch Release: 388 min.
4. Average Time Period for Batch Releases: 252 min.
5. Minimum Time Period for a Batch Release: 10 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 Nuclides Released Unit ist QUARTER 2nd QUARTER lst QUARTER 2nd QUARTER Sr-89 Ci

  • NO Sr-90 Ci 1.87E-05 DISCHARGE Ar-41 Ci
  • Mn-56 Ci 2.52E-03 Co-58 Ci 1.01E-04 -

Fa-59 Ci 1.82E-04 Cc-60 Ci 8.03E-03 Zn-65 Ci

  • Ru-103 Ci
  • Sb-122 Ci
  • Sb-124 Ci
  • I-133 Ci
  • I-135 Ci
  • C -134 Ci 5.69E-05 Cs-137 C1 1.54E-03 Ba-140 Ci
  • La-140 Ci
  • Ce-141 Ci
  • Others: C1 Ci C1 Ci tatuxe)

Total For Period Ci NONE NONE 1.24E-02 Xe-133 Ci 2.69E-05 Xe-135 Ci 1.37E-05 v

  • See Table for MDL of Each Nuclide

DRESDEN NUCLEAR POWER STATION January through June, 1986 TABLE OF MINIMUM DETECTABLE LEVELS FOR LIQUID EFFLUENTS Docket Nos. 50-10, 50-237, 50-249 Radwaste LIQUID EFFLUENTS TOTAL GALLONS RELEASED 2.36E+05 MDL (uCi/ml)  % of Gallons < MDL Sr-89 4.00E-09 100 Sr-90 2.00E-09 0 Ar-41 3.07E-08 100 Mn-54 6.06E-08 0 Co-58 6.77E-08 57 Fe-59 8.90E-08 42 Co-60 1.35E-07 0 Zn-65 1.10E-07 100 Ru-103 5.39E-08 100 Sb-122 7.01E-08 100 Sb-124 4.06E-08 100 I-131 7.42E-08 100 I-133 5.34E-08 100 I-135 9.15E 08 100 Cs-134 6.32E-08 67 Cs-137 8.90E-08 9 Ba-140 2.09E-07 100 La-140 2.30E-08 100 Ce-141 1.00E-07 100 Xe-133 7.70E-08 94 Xe-135 6.26E-08 94 Xe-138 1.89E-07 100 Xe-133m 5.78E-07 100 Mo-99 4.92E-07 100 Kr-87 1.31E-07 100 Kr-88 2.23E-07 100 Cr-51 6.20E-07 100 Ce-144 4.0SE-07 100 Tc-99m 5.32E-08 100

DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January THROUGH June 1986 LPCI LIQUID EFFLUENTS

1. Number of Batch Releases: 103
2. Total Time Period for Batch Releases: 128 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: 4.01E+05 Liters / min Docket Nos. 50-237, 50-249 CONTINUOUS MODE BATCH MODE Nuclides Released Unit 1st ' QUARTER 2nd QUARTER lst QUARTER 2nd QUARTER Sr-89 Ci *
  • Ar-41 Ci *
  • Mn-54 C1 2.18E-05 1.20E-05 Co-58 Ci 2.76E-05
  • F'-59 Ci 3.30E-07
  • C:-60 Ci 2.89E-04 7.98E-05 Zn-65
  • Ci
  • Ru-103
  • Ci
  • Sb-122
  • Ci
  • Sb-124
  • Ci
  • I-133 Ci
  • I-135 Ci
  • Cc-134 Ci *
  • Cn-137 C1 1.00E-05 2.72E-05 Ba-140 Ci *
  • La-140 Ci
  • Ce-141 Ci *

,Qthers: Ci Ci Ci Ci Total Period Ci NONE NONE 3.49E-04 1.19E-04 Xe-133 Ci

  • Xe-135 Ci *
  • See Table fot' MDL of Each Nuclide

. .~~~

DRESDEN NUCLEAR POWER STATION January through June, 1986 TABLE OF MINIMUM DETECTABLE LEVELS FOR LIQUID EFFLUENTS Docket Nos. 50-237, 50-249

f. PCT LIQUID EFFLUENTS TOTAL GALLONS RELEASED 4.47E+05 MDL (uCi/ml)  % of Gallons < MDL Sr-89 4.00E-09 100 Sr-90 2.00E-09 93 Ar-41 3.07E-08 100 Mn-54 1.90E-07 80 Co-58 1.93E-07 90 Fe-59 2.84E-07 96 Co-60 4.05E-07 32 Zn-65 2.94E-07 100 Ru-103 5.39E-08 100 Sb-122 7.01E-08 100 Sb-124 4.06E-08 100 100 1-131 2.39E-07 100 I-133 5.34E-08 100 I-135 9.15E-08 100 Cs-134 2.01E-07 Cs-137 2.47E-07 27 Ba-140 2.09E-07 100 La-140 2.30E-08 100 Ce-141 3.85E-07 100 Xe-133 7.70E-08 100 Xe-135 2.27E-07 100 Xe-138 6.38E-07 100 Xe-133m 1.99E-06 100 Ho-99 1.53E-06 100 Kr-87 3.86E-07 100 Kr-88 7.90E-07 100 Cr-51 2.03E-06 100 cc-144 1.59E-06 100

DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January THROUGH June 19 86 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Docket 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 6.18E+02
a. Spent resins, filter sludges, evaporator bottoms, etc. Ci 4.57E+03 m3 2.95E+02
b. Dry conpressible aste, contaninated equip. , etc. Ci 1.06E+01 ma 7.68E+00
c. Irradiated a-c-+ts, control rods, etc. Ci 1.91E+04 m3
d. Other (describe) Ci
2. Estimate of Major Nuclide Composition (by type of waste)

% Ci

a. Co-60 52.8  % 2.41E+03 Fe-55 37.0  % 1.69E+03 Mn-54 4.4  % 2.01E+02 Cs-137 3.1  % 1.42E+02 Other 2.7  % 1.23E+02
b. Co-60 64.0  % 6.78E00 Fe-55 28.8  % 3.05E00 Mn-54 4.3 g 4.56E-01 Cs-137 2.8 g 2.97E-Ol Other 0.1 g 1.06E-OZ
c. Co-60 52.3 g 9.99E+03 Fe-55 41.2 g /.6/E+03 Ni-39 U.1 g 1.91E+U1 Ni-63 6.3  % 1.20E+03 Other 0.1  % 1.91E+01
d.  %
3. Solid Waste Disposition NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION 132 Motor Freight (Exclusive Use Only) Barnwell, S.C.

15 Motor Freight (Exclusive Use Only) Richland, WA.

B. IRRADIATED FUEL SHIPMENTS (Disposition)

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

- - ~

~

(

+

DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January THROUGH June 19 86 ABNORMAL RELEASES Docket Nos. 50-10, 50-237, 50-249 A. LIQUID

1. Number of Releases: 1
2. Total Activity Released: 2.03E-04Ci B. GASEOUS
1. Number of Releases: 0
2. Total Activity Released: 0

.z' 3,ns

.J' Commonwealth Edison $2* **1 Dresden Nuclear Power St: tion Ib Nh R.R. #1 IV ~1:l4_

Morris, filinois 60450 d f ^! __ _

Telephone 815/942-2920

( _

FILE M 7 July 28, 1986 DJS LTR: # 86-527 Mr. James G. Keppler Regional Administrator Directorate of Inspection and Enforcement Region III U.S. Nuclear Regulatory Commission 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 January through June, 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. D. Eisenhut, Deputy Director of the Office of Nuclear Reactor Regulation.

Sincerely, f

'~ jIf J. Scott Station Manager Dresden Nuclear Power Station DJS:RB:jm Enclosure /

< 6 cc: R. Berg J.C. Golden /l File /NRC File / Numerical SEP 219%

+

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

Retrieved from "https://kanterella.com/w/index.php?title=ML20209D698&oldid=3080709"