ML20212H335

From kanterella
Jump to navigation Jump to search
Effluent & Waste Disposal Semiannual Rept,Gaseous Effluents - Summation of All Releases,Jul-Dec 1986
ML20212H335
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 12/31/1986
From: Eenigenburg E
COMMONWEALTH EDISON CO.
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
87-078, 87-78, NUDOCS 8703060075
Download: ML20212H335 (16)
v • d • e


Text

, }" ' . ,  ! /.

2

.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 arialyzed ,

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.

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(Li) spectrometry system. A composite of all batches for the month is sent to a vendor to be analyzed for.S.r-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) spect-rometry system. This sample is sent to a vendor to be analyzed l for Sr-89, Sr-90, Fe-55, and Gross' Alpha activity.

l

. .~.

jFeT8ci!W$h -

R PAGE 1 of 15

DRESDEN NUCLEAR POWER STATION OFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY Through DECEMBER 19 86 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES DOCKET NOS. 50-10, 50-237, 50-249 UNIT 3rd QUARTER 4th OUARTER A, FISSION AND ACTIVATION CASES

1. Total Release Cf 1.10E+02 3.21E+02
2. Average Release Rate for Perind uCi/see 1.38E+01 4.04E+01 3- Percent of Technical Specificneinn Limir  % *
  • B- 10 DINES 1 Total Iodine-131 Ci 2.64E-03 7.31E-03
2. Average Release Rate for Period uCi/sec 3.32E-04 9.20E-04

[

l 3. Percent of Technical Specification Limit  % * *

C. PARTICULATES
1. Particulates with half-livan SA dava Ci 1.71E-02 1.34E-02
2. Average Release Rate for Period uCi/see 2.15E-03 1.69E-03
3. Percent of Technical Specification Limit  % * *
4. Gross Alpha Radioactivity Ci 4.43E-06 2.03E-06 D. TRITIUM
1. Total Release Ci 2.53E 00 5.01E 00
2. Average Release Rate for Period uCi/sec 3.18E-01 6.30E-01
3. Percent of Technical Specification Limit  % * *
  • WILL BE INCLUDED IN THE ANNUAL REPORT ON ENVIRONMENTAL RADI0 ACTIVITY DATA PAGE 2 0F 15

DRESDEN NUCLEAR POWER STATION UNIT I EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

. . Juty THROUGH DECEMBER 19 86 D-1 CHIMNEY GASEOUS EFFLUENTS GROUND LEVEL RELEASES SEMI-ELEVATED RELEASES XX ELEVATED RELEASES DOCKET NO. 50-10 CONTINUOUS MODE BATCH MODE kUCLIDESRELEASED UNIT 3rd QUARTER _4thQUARTER 3rdQUARTER 4th QUARTER

(.- FISSION GASES Ci Xe-138 Ci *

  • Xe-135m Ci *
  • Kr-87 Ci *
  • l Kr-88 Ci *
  • Kr-85m Ci *
  • Xe-135 Ci Xe1133 Ci
  • OthersKe-133m Ci *
  • I Ci l TOTAL Ci NONE NONE
f. 10 DINES

! I-131 Ci

  • l I-133 Ci
  • I-135 Ci
  • l TOTAL Ci NONE NONE L. PARTICULATES

! Sr-89 Ci *

  • l Cr-51 Ci l Mn-54 Ci
  • 4.76 E-08 Co-58 Ci
  • Fe-59 Ci
  • l Co-60 Ci 2.43 E-06 1.67 E-05 I

Zr-95 Ci *

  • Nb-95 Ci *
  • Ru-103 Ci Art-110m Ci * *

> Sb-124 Ci I-131 Ci Cs-134 Ci Cs-136 Ci Cs-137 C1 3.54 E-06 1.74 E-05 Ba-140 Ci

  • Ce-141 Ci Ce-144 Ci *
  • Zn-65 Ci Ba-133 Ci *
  • Sb-125 Ci Othnrs : Mo-99 Ci C1 Ci Ci Ci TOTAL Ci 5.97 E-06 3.41 E-05 NONE NONE
  • See Table for MDL of Each Nuclide PAGE 3 of 15

1 DRESDEN NUCLEAR POWER STATION-JULY THROUGH DECEMBER 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 5.08 E-08 100 Xe-135m 2.14 E-08 100

'Kr-87 3.43 E-08 100 Kr-88 6.14 E-08 100 .

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

2 . IODINES I-131 3.12 E-14 1d0 I-133 3.13 E-14 100 I-135 6.39 E-14 100

3. PARTICULATES Sr-89 1.00 E-15 100 Sr-90 1.00 E-15 100 Cr-51 2.29 E-13 100 2.78 E-14 92

.Mn-54 100 Co 2.62 E-14 4.33 E-14 100

-Fe-59 Co-60 6.39 E-14 27 Zr-95 4.86 E-14 100 Nb-95 2.61 E-14 100

! Ru-103 2.71 E-14 100 2.74 E-14 100 Ag-110m 1.96 E-14 100 Sb-124 2.88 E-14 100 1-131

' 3.12 E-14 100-

Cs-134 3.14 E-14 100

, Cs-136 18 Cs-137 3.37 E-14 1.08 E-13 100 Ba-140 100 Ce-141 3.69 E-14 1.52 E-13 100 Ce-144 Zn-65 4.44 E-14 100 Ba-133 2.60 E-14 100 7.78 E-14 100 Sb-125 100 2.16 E-13 Others: Mo-99 1.25 E-14 100 La-140 PAGE 4 of 15

DRESDEN NUCLEAR POWER STATION UNIT 2/3

' EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY TiiROUGH DECEMBER 19 86 2/3 CHIMNEY GASEOUS EFFLUENTS GROUND LEVEL RELEASES SEMI-ELEVATED RELEASES XX ELEVATED RELEASES DOCKET N0s. 50-237, 50-249 CONTINUOUS MODE BATCH MODE (UCLIDES RELEASED UNIT 3rcQUARTER 4thQUARTER 3rd QUARTER 4th QUARTER

, FISSION CASES Ci Xc-138 Ci 4.56 E + 01 7.87 E + 01 Xe-135m Ci 1.35 E + 01 1.74 E + 01 Kr-87 Ci 7.69 E 00 1.80 E + 01 Kr-88 Ci 7.43 E 00 2.45 E + 01 Kr-85m Ci 5.88 E 00 9.08 E 00 Kr-85 Ci 4.51 E-03 1.04 E - 02 Xe-135 Ci 2.43 E +01 1.43 E + 02 Xe-133 Ci 2.}4 E 00 2.00 E + 01 Others:Xe-133n Ci l Ci TOTAL Ci 1.07 E + 02 3.11 E + 02 NONE NONE

. 10 DINES I-131 Ci 2.37 E - 03 6.66 E - 03 I-133 Ci 1.56 E - 02 3.10 E - 02 I-135 C1 2.39 E - 02 5.12 E - 02 1 TOTAL Ci 4.19 E - 02 8.89 E - 02 NONE NONE

. PARTICULATES Sr-89 Ci 4.03 E - 04 1.10 E - 03 Sr-90 C1 4.42 E - 06 2.53 E - 05 Cr-51 Ci *

  • I Mn-54 Ci 1.01 E - 04 1.44 E - 04 I Co-58 Ci *
  • l Fe-59 Ci *
  • l Co-60 Ci 4.14 E - 04 5.59 E - 04 I Zr-95 Ci *
  • Nb-95 Ci *
  • Ru-103 Ci *
  • An-110m Ci Sb-124 Ci I-131 Ci 1.82 E - 04 8.19 E - 04 Cs-134 Ci Cs-136 Ci *
  • Cs-137 Ci 3.57 E - 05 1.08 E - 04 Ba-140 C1 2.24 E - 03 5.07 E - 03 Ce-141 Ci 8.39 E - 06 8.56 E - 05 l Ce-144 Ci *
  • i Zn-65 Ci *
  • Ba-133 Ci *
  • Sb-125 Ci l Othnrs: Mo-99 Ci I Ci l Ci l Ci Ci l TOTAL Ci 3.39 E - 03 7.91 E - 03 NONE NONE
  • See Table for MDL of Each Nuclide PAGE 5 of 15

=; ~

7 ,,

-(:

DRESDEN NUCLEAR POWER STATION JULY THROUGH DECEMBER 1986 TABLE OF MINIMUM DETECTABLE LEVELS FOR GASEOUS EFFLUENTS 3rd QUARTER: 253 KCFM

.n 2/3 CHIMNEY CASEOUS EFFLUENTS AVERAGE FLOW 4th QUARTER: 280 KCFM

-DOCKET Nos. 50-237, 50-249 MDL (uCi/cc)  % OF TIME < MDL

.1.- FISSION GASES Xa-138 1.72 E-07 83 Xe-135m 7.55 E-08 90 Kr-87 4.43 E-08 95 Kr-88 8.85 E-08 96 Kr-85m 2.73 E-08 88 Kr-85 7.06 E-06 0 Xe-135 2.72 E-08 40 Xe-133 6.19 E-08 90 Others: Xe-133m 2.30 E-07 100 ,

2.- 10 DINES I-131 3.12 E-14 0 I-133 3.13 E-14 0 1-135 6.39 E-14 21

3. PARTICULATES Sr-89 1.00 E-15 0 Sr-90 1.00 E-15 0

-Cr-51 2.29 E-13 100 Mn-54 2.78 E-14 9 Co-58 2.62 E-14 100 Fe-59 4.33 E-14 100 Co-60 6.39 E-14 0 2r.93 4.86 E-14 100 Nb-95 2.61 E-14 100 Ru-103 2.71 E-14 100 Ag-110m 2.74 E-14 100 Sb-124 1.96 E-14 100 1-131 2.88 E-14 4 3.12 E-14 100^~

Cs-134 Cs-136 3.14 E-14 100 Cs-137 3.37 E-14 9 Ba-140 1.08 E-13 3 Ce-141 3.69 E-14 57-Ce-144 1.52 E-13 - 100 2n-65 4.44 E-14 100 Ba-133 2.60 E-14 100 Sb-125 7.78 E-14 100 2.16 E-13 100

.0thers: Mo-99 1.25 E-14 100 DETECTED, BUT NOT REPORTED La-140 PAGE 6 of 15

- - - - v-f i ^'. '* ' ' ,' ~w ' _ .DRESDEN NUCLEAR POWER STATION I' UNIT 2/31

' , . EFFLUENT AND WASTE. DISPOSAL SENIANNUAL REPORT

~ , . . .; -

JULY--

THROUGN DECEMBER
19 = 86 -

? '

'2/3 VENT 2 GASEOUS. EFFLUENTS-GROUND LEVEL RELEASES.

'XX ' SEMI-ELEVATED RELEASES ELEVATED RELEASES

. DOCKET NOS. 50-237, 50-249

^ CONTINUOUS MODE-

  • RATCH MonE-1UCLIDES RELEASED UNIT .-3rd QUARTER 4th QUARTER -3rdQUARTER 4th QUARTER;

% FISSION GASES Ci-In-138 C1- * *-

-Xe-135m Ci Kr-87 Ci

  • Er-88-- Ci

'Kr-85m Ci Kr-85 Ci * -*

In-135 'C1 2.88 E 00 9.92 E 00 Za-133 Ci *-

  • Others:Xe-133s i Ci *
  • Ci TOTAL Ci- .2.88 E 00 9.92 E-00 NONE NONE ,
t. -10 DINES -

-I-131 Ci- 2.69.E - 04- 6.52 E - 04 ,

I-133- C1 2.02.E - 03 5.53 E -I-135 Ci- Z 33 E - 03 1.12 E - 02 TOTAL Ci 5.12 E - 03 1.-74 E - 01 NONE NONE lJ PARTICULATES Sr-89 Ci 3.19 E - 05 2.02 E - 05'

'Sr-90 Ci '3.10 E - 06 2.33 E - 06 Cr-51 Ci 1.54 E - 03 1.56 E - 04 Mn-54 C1 1.14 E - 03 4.47 E - 04 Co-58 C1- 6.51 E - 04 1.50 E - 04 Fa-59 Ci 5.22 E - 04 7.63 E - 05 '

Co-60 Ci- 5.89 E 2.87 E - 03

~2r-95 Ci

  • Nb-95 Ci *
  • i Ru-103 Ci
  • i- An-110m C1 1.84 E - 04 9.10 E - 06 Sh-124 -C1 3.82 E - 05 3.80 E - 06 I-131 Ci 7.51 E - 05 2.00 E - 04 l' Cs-134 Ci *
  • _ Cs-136 Ci 2.60 E - 05

!' Ca-137 Ci 4.48 E - 05 2.86 E - 05 Ba-140 Ci 6.74 E -'04 2.19 E - 04 Ca-141 C1 6.02 E - 06 1.47 E - 06 Ca-144 C1 2.44 E - 05

  • t 2n-65 C1 2.27 E - 04 4.52 E - 05 Ba-133 Ci Sh-125 Ci *
  • Othirs:Mo-99 Ci 2.67 E - 03 1.20 E - 03 C1 Ci Ci i

Ci TOTAL C1 1.37 E - 02 5.43 E - 03 NONE NONE i-j.

  • See Table for MDL of Each Nuclide I PAGE 7 of 15 i..,,.-...-,,-,----..,..-
(

~A . . .

~u DRESDEN NUCLEAR POWER STATION

-JULY THROUGH DECEMBER 1986 TABLE OF MINIMUM DETECTABLE LEVELS '

.FOR CASEOUS EFFLUENTS D-2: 110 K CFM 2/3 VENT GASEOUS EFFLUENTS - AVERAGE FLOW D-3: 110 K CFM

DOCKET Nos. 50-237, 50-249 MDL (uCi/cc)  % OF TIME < MDL

1. FISSION CASES Xe-138 5.08 E-08 100 Xe-135m 2.14 E-08 100
Kr-87 3.43 E-08 100 Kr :6.14 E-08 100

-Kr-85m 1.86 E-08 100 Kr-85 4~58 E-06

. 100 Xe-135 1.80 E-08 49

-Xe-133 4.42 E-08 100 Others: Xe-133m 1.56 E-07 100 ,

2 IODINES I-131- 3.12 E-14 4 I-133 3.13 E-14 4 I-135 6.39 E-14 18

3. PARTICULATES.

Sr-89 1.00 E-15 0 Sr-90 1.00 E-15 0 Cr-51 2.29 E-13 18

Mn-54 2.78 E-14 0 Co-58 2.62 E-14 2 Fe.39 4.33 E-14 9 Co-60 6.39 E-14 0 Zr-95 4.86 E-14 100 Nb-95 2.61 E-14 - 100

!- Ru-103 2.71 E-14 100 Ag-110m 2.74 E-14 58 Sb-124 1.96 E-14 53 I-131 2.88 E-14 13 Cs-134 3.12 E-14 100 ~

-Cs-136 3.14 E-14 85 Cs-137 3.37 E-14 8 Ba-140 1.08 E-13 0 Ce-141 3.69 E-14 89 -

Ce-144 1.52 E-13 92 4.44 E-14 50 2n-65 2.60 E-14 100 Ba-133 7.78 E-14 100 Sb-125 Others: Mo-99 Ej4 La-140 DETECTED, BUT NOT REPORTED PAGE 8 of 15

. , - . , g

. 's s r .- * *

.  :-DRESDEN NUCLEAR POWER STATION-

~

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY THROUGH DECEMBER 19 86 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES

  • DOCKET NOS.. 50-10, 50-237, 50-249-

+%

UNIT 3rdQUARTER 4th QUARTER

'N FISSION AND ACTIVATION PRODUCTR i

l- Total Release-(nor indl. erfeim gnene.n1nwn Ci 1.05E-01 9.60E-02

2. Averane Diluted cone. nnving b r4na uCi/m1' 2.83E 3.82E-09 ,
3- Percent of Annifcable Limfr  % * ~*

7 34--TRITIUM

~

'1. Total Release Ci 5.64E00 6.05E00-

i. '2- Average Diluted Cone. During Period uCi/mi 1.52E-08 2.41E-07
3. ' Percent of Apolicable Limit  % * *

.' DISSOLVED'AND ENTRAINED GASES 1 Total Release Ci 1.79E-03 9.52E-03 2 .. 'Averne~ Diluted Conc. Durina Period uCi/mi 4.82E-12 3.79E-10

3. Percent of Applicable Limit  % * *

~

l .- GROSS ALPHA RADIOACTIVITY

j. ' l. Total Release C1 2.90E-05 4.64E-05 l- .

. - VOLUME OF WASTE RELEASED (orior to dilution) liters 7.23E+06 8.41E+06 VOLUME OF DILUTION WATER USED DURING PERIG) a liters 3.71E+11 2.51E+10 C WILI~BE' INCLUDED' IN'THE~ ANNUAL REPORT ON ENVIRONMENTAL RADIOACTIVITY DATA -

!. PAGE 9 of.15

p ,

, .cy . -

., q

't

-jQg , . . ,.

. s

/ ' O. .; .: .

, y- .

, a..

r.3 .

~ . . -,

DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SD1IANNUAL REPORT

~ ~

, c JULY THROUGH DECEMBER 19 86'

' RADWASTE ~- ' LIQUID EFFLUENTS

. 1. Number of Batch Releases: 162

-2. Total Time Period for Batch' Release's': 49165 min'

+

3. Maximum Time Period for a Batch Release:- '

555 min 4 '. Average: Time Period for Batch Releases:

1' 303 min

5. . Minimum Time Period for a Batch Release: ! 7 min 6.- Average' Stream; Flow During feriods of Release of Effluent:into a Flowing'Sr;tesa: 1.89EH)5 ' Liters / Min' -

DOCKET NOS. 50-10, 50-237, 50-249.

" CONTINUOUS MODE B'ATCH MODE

. my.1 u 3 1maand Unit 3rd QUARTER -- 4th'- QUARTER 3rd QUARTER 4th QUARTER i

Sr Ci * * '

^

Sr-9 ' -Ci' 9.93 E - 05 8.77 E - 05 x

-Ar-41 C1 4.75 E - 05 *- '

Mn-54 Ci _1.i5 E - 02 8.16 E - 03 Co-58 Ci 4.30 E - 04 1.87 E - 04 Fr.-59 Ci 7.19 E - 04

  • Co Ci 6.43 E - 02 7.29 * - 02 Er-65 Ci l'.74 E - 04 -*

Ru-103 Ci *

  • Sb-122 Ci 3.72 E - 04  ;
-Sb-124 Ci
  • i
  • I-131 Ci 2.84 E - 04 8.56 E - 05 iI-133- -

Ci- 1.03 E - 03 <

  • I-135 C1 1.90 E - 04
  • 2C -134 Ci 1.05 E - 04 1.44 E - 04 Cc-137 C1 1.22 E - 02 1.38 E - 02 '

Ba-140 Ci * * -

Ci 2.56 E - 04 *

-La-140

)'

Ca-141 Ci . .#-

Others: Cr-51 Ci 1.64 E - 03 5.81 E - 05 Mo Ci 2.21 E - 03

  • Tc-99m Ci 1.16 E - 03 *

.Fe-55 Ci * - '*

lbtal Nriod Ci NONE NONE J.03 E - 01 9.5 E -02

'Xe-133' Ci 8.21 E - 04 7.19 E - 03 Xe-135- Ci f 9.65 E - 04 2.33 E - 03

  • See Table for MDL of Each Nuclide PAGE 10 of 15

g .

g .-

, q.. ,

.562 _ _' ,,; i '$ '

.- u ,~m; , .

3. ; .
n

~ ,: " (*

j ( --

('r -n '

ct 9 ' ,.)M.! 4 '

DRESDEN NUCLEAR POWER STATION sc P7 '

JULY THROUGH DECEMBER 1986

" +/; uE 3 TABLE OF MINIMUM DETECTABLE LEVELS

, -g F0,R' LIQUID EFFLUENTS N, (( ;

DOCKET NOS, 50-10, 50-237, 50-249

'~

RADWASTE LIQUID EFFLUENTS TOTAL GALLONS RELEASED 3.57 E+06 MDL' (uCi/ml)  % of Callons < MDL

'~ "

-y Fe-55 7.00 E-07 100

+L Sr-89 y 4.00 E-09 100

- Sr-90' " 2.00 E-09:

0 ,

s j Ar-41 T 3.07'Ei8 98 Ma-54 6.06 E-08 4

' ' ,- ' Cds58 6.77 E-08 95 7; ,

'Ja-59 8.90 E-08 94 -

y/ . Co-60 1.35 IE-07 1

n Zn-65 1.10 E-07 99:,

Ru-103 5.39 E-08' 100 Sb-122 7.01 E-08 99 4 '. Sb--124 4.06 E-08 100 o I-131 .7.42 E-08 93

99 I-133 5.'34 E-08 I-135 .9.15 4-08 99

, Cs-134 6.32 E-08 90 1

Cs-137 8. s90 E-08 100 Ba-140 ,  ? C9 E107 La-140 ' 2.30 E-08 97

, Ce-141 1.00 E-07 100 Xe-133' -7.10 E-il8 76

~..'

Xe-135 6.26 E-08 71

?~ Xe-138 1.89 E-07 1,00 Xe-133m- 5.78 E-07 100 Mo-99 4.92 E-07 99 Kr-87 1.31 E-07 100 -

. Kr-88 2.23 E-07 100 J

l Cr-51 6.20 E-07 96

' Ce-144 4.05 E-07 100 I

Tc-99m 5.32 E-08 97 PAGE l'1 of 15

p 3, -. -=

3' i;$i* ..;..  :;.

sc ,

^54 ,.

x

.)

p, j DRESDEN NUCLEAR POWER STATION

qlg '

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT.

%b ~ [ JULY- THROUGH DECEMBERi 19 86 a di'

  1. . 9

.' LPCI LIQUID EFFLUENTS ~

.:h.

k,; a -

W.. 1. Number'of Batch Releases:- 130 -'

.2. Total Time Period'for Batch Releases: -161 min.-

& 13. Maximum Time Period for'a Batch Release: 1.24 min.

4.- Average Time' Period 2for Batch Releases:- 1.24. min.

~

, 5. Minimum Time Period for a Batch Release:- .1.24 min.

O- -

6..~ Average Stream Flow During Periods of Release

'F of Effluent into a Flowing Stream: 1 1.89E+05 liters / min.

DOCKET NOS. 50-237,-50-249 CONTINUOUS MODE BATCH M_0DE Ak1 h Relmaamd Unit 3rd QUARTER 4th QUARTER 3rd QUARTER 4th_ QUARTER'

'St -89' ~

'Ci \*- -*1 s 'Sr-90 Ci-

  • 1.93 E Ar-41 Ci -* .*

.' 54 C1 2.79 E - 04

{ Mad 1.32 E - 04 i

'fCo-58 Ci 4.30'E - 06 8. 64 E -- 06 >

'. : Fa-59

. 'Ci- 2.96 E - 06 *-

Co-60 -- C1 1.27 E - 03 4.51 E - 04

,Zn-65 Ci * '*

I

..Ru-103 Ci ,

Sb-122- Ci * *

- Sb-124 - ~Ci 2.00 E - 08
  • F :I-133 Ci' <

-I-135- Ci * *;

O C9-134 Ci i *

  • CS-137: C14 5

.88 E - 05 2.40 E - 05

. . > - + ..

Ba-140 Ci *
  • iLa-140 ' Ci *
  • lCe-141- Ci .. .~ * *
0the rs
- ' Cr-51 Ci- 2.10 E - 07
  • Ci * '

Ci

' 1.59 E - 03 6.18 E - 04

Totalh riod Ci~ NONE NONE

-Xe-133 Ci Xe-135' Ci

  • See Table for MDL of Each Nuclide PAGE 12 of 15

6 -..

w '

s ..

~_

U H E R -

TABLE 0F MINIMUM DETECTABLE LEVELS FOR LIQUID EFFLUENTS DOCKET HOS. 50-237, 50-249 LPCI LIQUID EFFLUENTS- TOTAL GALLONS RELEASED 5.64 E+05.

MDL (uCi/ml) - % of Gallons <)GH; JFe-55 7.00 E-07 83 Sr-89 4.00 E-09. 100 Sr-90 2.00 E-09 83 Ar-41 3.07 E-08 100 Mn-54 1.90 E-07 21 Co-58 1.93 E-07 91 Fe-59 2.84 E-07 82 -

Co-60 4.05 E-07 0 Zn-65 2.94 E-07 109 Ru-103 5.39 E-08 100-Sb-122 7.01 E-08 100 Sb-124 4.06 E-08 94 I-131 2.39 E-07 100

, I-133 5.34 E-08 100 I-135' 9.15 E-08 100 Cs-134 2.01 E-07 100 Cs-137 2.47 E-07 28 ,

Ba-140 2.09 E-07 100 La-140 2.30 E-08 100 Ce-141 3.85 E-07 100 Xe-133 7.70 E-08 100 2.27 E-07 100 Xe-135 6.38 E-07 100 Xe-138 , _ ,,

1.99 E-06 100

.Xe-133m 1.53 E-06 100 Mo-99 Kr-87 3.86 E-07 100 -

Kr-88 7.90 E-07 100 l

Cr-51 2.03 E-0.6 94 Ce-144 1.59 E-06 100 PAGE 13 of 15

e, -

J -

DRESDEN NUCLEAR POWER STATION-EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY THROUGH DECEMBER 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 m8 7.94 E + O2
a. Spent ' resins, filter sludges, evaporator bottans, etc. Ci 2.23 E + 03 l m3 4.24 E + O2
b. Dry ccupressible waste, contaminated equip. , etc. Ci 7.12 E 00 m3 6.27 E - 01
c. Irradiated cmponents, control rods, etc. Ci 1.15 E + 04 m3
d. Other (describe) Ci

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

% Ci

a. Co-60 52.8  % 1.18E+03 Fe-55 37.0  % 8.25E+02 Mn-54 4.4  % 9.81E+01 Cs-137 3.I  % 6.91E+01 OTHER 2.7  % 6.02E+01
b. Co-60 64.0  % 4.56 E 00 Fe-55 28.8  % 2.05 E 00 Mn-54 4.3  % 3.06E-01 Cs-137 2.8  % 1.99E-01 OTHER 0.1  % 7.12E-03
c. Co-60 52.3  % 6.01E+03 Fe-55 41.2 2 4.74E+03 Ni-59 0.1  % 1.15E+01 Ni-63 6.3  % 7.25E+02 OTHER 0.1  % 1.15E+01
d.  %
3. Solid Waste Disposition NUMBER OF SHIPMENTS MODE OF TRANSPORTATION _ DESTINATION 118 MOTOR FREIGHT (EXCLUSIVE USE ONLY) BARNWELL, S.C.

18- MOTOR FREIGHT (EXCLUSIVE USE ONLY) RICHLAND, WA.

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

B, IRRADIATED FUEL SHIPMENTS (Disposition)

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

PAGE 14 of 15

, 4

-DRESDEN NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY THROUGH DECEMBER' 19_Bh_

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: 0 l 2. Total Activity Released: o i

l I

l PAGE 15 of 15 t

pad

~

t -

-. Commonwealth Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 February 3, 1987 EDE LTR: # 87-078 PRICRITY ROUTIliG Tir s t' Sec nd Mr. James G. Keppler f )

Regional Administrator 's ~_-44~_

Directorate of Inspection and Enforcement ,

F * -

Region III U.S. Nuclear Regulatory Commision

+lk k- ,-

b

~

799 Roosevelt Road u,M IIL_

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 July through December, 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. R.H. Vollmer, Deputy Director of the Office of Nuclear Reactor Regulation.

Sincerely, M. *p E.D. Eenigenburg Station Manager Dresden Nuclear Power Station EDE:RB:jm Enclosure cc: R. Berg J.C. Golden File /NRC File / Numerical

/

6h I qi FEB 2 3 1387 L

Retrieved from "https://kanterella.com/w/index.php?title=ML20212H335&oldid=3099541"