ML19256F450
ML19256F450 | |
Person / Time | |
---|---|
Site: | Quad Cities |
Issue date: | 12/31/1977 |
From: | COMMONWEALTH EDISON CO. |
To: | |
Shared Package | |
ML19256F405 | List: |
References | |
FOIA-79-491 NUDOCS 7912190159 | |
Download: ML19256F450 (24) | |
Text
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QUAD CITIES STATION RADIOACTIVE WASTE AND ENVIRONMENTAL MONITORING 1977 ANNUAL REPORT 2
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MARCH 1978 1625 2'97 .
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SUMMARY
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- : i Gaseous and liquid effluents for the period remained at a fraction of
?! the Technical Specification limits. Calculations of environmental T{ - !
concentrations based on effluent, Mississippi River flow, and meteor-ological data for the period indicate that consumption by the public l of radionuclides attributable to the plant will not exceed the quantity
! of those radionuclides that result from continuous exposure to the con- l J. centration values listed in Apprendix B, Table II, of 10CFR20. Gamma j radiation exposure from noble gases released to the atmosphere repre-
.g
-3 sented the critical pathway for the period with a maximum individual dose estimated to be 0.02 mrem for the six-month period, and 0.07 mrem for the year, when a shielding and occupancy factor of two is assumed.
- ' Environmental monitoring results confirm that dose via other pathways
?' was not significant.
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. I. ' i-I 1.0 EFFLUENTS i I.
1.1 GASEOUS EFFLUENTS TO THE ATMOSPHERE
{
Measured concentrations and isotopic composition of noble gases, '
radiciodine, and particulate radioactivity released to the atmosphere during the period July to December 1977, are listed in Table 1.1-1. A six-month , (
total of 9.09E+03 curies of noble gases was released during the period at an average release rate of 5.72 E+02 uCi/sec. Average release rates during either quarter of the period did not exceed 6.4% of the Technical Specifi- 1.
cation limit.
P' A total of 0.44 curies of' beta-gamma emitters and 1.78E-05 curies of alpha emitters were released as airborne particulate matter.
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in- g i 1.2 LIQUIDS RELEASED TO MISSISSIPPI RIVER (
. 4 A total of 5.68E+06 liters of radioactive liquid wastes contain- [
n ing 0.30 curies (excluding tritium) were discharged from the station during I
- 1. the final six months of the year. These wastes were released at an average l s concentration of 7.24E-10 uCi/ml which is0.7% of the Technical Specification -(
. releases limit for unidentified radioactivity. During the same period, 11.6 l curies of tritium and 1.68E-04 curies of alpha radioactivity were released. j Quarterly release estimates and principal radionuclides in liquid effluents }
are given in Table 1.2-1.
The maximum concentration of radioactivity, above background, in the Quad i Cities Unit 1/2 discharge canal during the period was computed to be 6.24E-08 [
uCi/ml. ;
2.0 SOLID RADIOACTIVE WASTE The total amount of solid waste packaged for disposal was 21709 ;
cubic feet during the six-month period. The total amount of radioactivity 3 involved was calculated to be 1402.16 curies. Solid radioactive wastes l were shipped to either Nuclear Engineering Company, Sheffield, Illinois, j or Morehead, Kentucky, or Chemical Nuclear Services, Bellevue, Washington.
Date, volume and radioactivity of each shipment are shown in Table 2.0-1. ,
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. 1.0 EFFLUENTS
% 1.1 GASEOUS EFFLUENTS TO THE ATMOSPHERE M
, Measured concentrations and isotopic composition of noble gases, radioiodine, and particulate radioactivity released to the atmosphere during the period July to December 1977, are listed in Table 1.1-1. A six-month
- total of 9.09E+03 curies of noble gases was released during the period at an average release rate of 5.72 E+02 pCi/sec. Average release rates during
- either quarter of the period did not exceed 6.4% of the Technical Specifi-cation limit.
A total of 0.44 curies of beta-gamma emitters and 1.78E-05 curies of alpha emitters were released as airborne particulate matter.
, 1.2 LIQUIDS RELEASED TO MISSISSIPPI RIVER
. . ~
- A total of 5.68E+06 liters of radioactive liquid wastes contain-
- ing 0.30 curies (excluding tritium) were discharged from the station during the final six months of the year. These vastes were released at an average concentration of 7.24E-10 uCi/ml which is0.7% of the Technical Specification releases limit for unidentified radioactivity. During the same period, 11.5
~
curies of tritium and 1.68E-04 curies of alpha radioactivity were released.
Quarterly release estimates and principal radionuclides in liquid effluents are given in Table 1.2-1.
The maximum concentration of radioactivity, above background, in the Quad Cities Unit 1/2 discharge canal during the period was computed to be 6.24E-08 uCi/ml.
1 ..
B.ji 2.0 SOLID RADIOACTIVE WASTE kN The total amount of solid waste packaged for disposal was 21709
.tg
- cubic feet during the six-month period. The total amount of radioactivity
.A involved was calculated to be 1402.16 curies. Solid radioactive wastes were shipped to either Nuclear Engineering Company, Sheffield, Illinois, k' .
or Morehead, Kentucky, or Chemical Nuclear Services, Bellevue, Washington.
7 Date, volume and radioactivity of each shipment are shown in Table 2.0-1.
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TABLE 1.1-1 fu k.
-i EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT 1977 .
l GASEQUS EFFLUENTS-SUMMATION OF ALL RELEASES
'i; 4
r Muarter Quarter Est. Tota Unit 3rd 4th Error,g A. Fission & Activation Gases
~: _
CI I.54E+03 7.55E+03
- 1. Total release _
uCi/see 1.94E+02 9.50E+02
- 2. Avera,qe release rate for_ period
- 3. a. Percent of Tech. Spec. limit 1.16E-02 6.28E-02 Chimnev
- b. Percent of Tech. Spec. Ilmit 6.34E+00 Stack % ,fLDL h B. lodines C1 2.41E-01 2.45E-01 1 Total iodine-131 _
uCi/sec 3;03E-02 3.08E-02
, 2,, Aver, age release rate for period _
j 3. a. Percent of Tech. Spec. limi t statior
% 1.95E+00 1.98E+00 F l um
(.5; '
C. Particulates
[f[ _ _
C1 2 38E-01 2.05E-01 1 Parti culate_s with half-lives > 8 days uC1/sec 2.9AE-02 2.58E-02
- 2. Averace release rate for_oeriod 1
is:' 3.59E-06 I.42E-05 3 Gross alpha radioactivity t.
- IEf, s -
f-?r, ; D. T ri t i tr.1 1
M1.7.
& 1 Tot a l . r.,e l e a se C1 5.01E+00 9 99E + 00 d..._ ,,
Aversee release rate for neriod uti/sec 6.30E-01 1.24E + 00 -[
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TABLE 1.1-1 Cont'd a 1977 EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT I GASEOUS EFFLUENTS-ELEVATED RELEASE Continuous Mode Batch Mode Quarter Quarter 0.uarter Quarter Nuclides Released Unit 3rd 4th I. Particulates .
Sr-Bo C1 2.h6E-02 Cl 6.3cE-oc
_Sr c0 _
C1 4.67E-04 5.,3 8 E-_04_ _
Cs-134_
Cl 1.35E-03 1.54E-03 C s -137_ _ _
Cl 7.51E-03 1.74E-02 Ba-Iho , ,
1.03E-02 2.40E-02 ,
_La-140 _ __Ci i Cr51 C; (LDL _(tot
(
Mn54 C1 2.53E-05 4.40E-05 l
=
CoS3 C1 (LDL (LDL i t Co63 Cl 1. 05_E -03 _1.71E-03 II3I Cl 1.31E-02 1.15E-02 Ag l i O.? C1 (LDL (LDL i 2.84E-04 2.78E-04 Ce141 C_1
.g Cl 1.LSE-05 ( LDL k Nb95 - _ _ _
.t c
- ) _
Cl Ci __ _
Cl Unidentified Ci 1.58E-01 m
k g g s 1625 402
.. a. . - -- - - - - - - __ .~ _ , 2
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QUAD CITIES NUCLEAR POWER STATION TABLE 1.1-1 Cont'd ,
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1977 (N GASEOUS EFFLUENTS-ELEVATED RELEASE Batch Mode Continuous Mode
$^
[ Nuclides Released Unit 3rd 4th Fission gases
.i 1. .
Kr-85 CI --
(LDL ( LDL 3
I K r-85m ___ __ -
Ci 7.78E+01
-- . 5.81E+02 a 2.44E+01 Ci 4.80E+00
'( r .87 _ _ _
t.,
K r-88 Ci 1.62E+01 1.76E+02 1
C1 1.10E+03 4,50E+03
? Xe.131 Ci 3.40E+02 2.21E+03
$ X c-1J3 _
C1 (LDL (LDL
! X e-135m Ci (LDL JLDL Xc-118 _ _
3 CI --
r.M b
2EA d, Ci (LDL (LDL U ni den (i f i ed ~
1.54E+03 7,49g+03 WE Total for Period C1 C';
.u v 1 2. todines j ,
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1.99E-01 1.93E-01 t
j I-131 C1 Ci 8.95E-01 6.97E-01
} ! l-133 __
Ci 1.58E+00 4.52E-01 1-133 _
,q* ! ..
C1 2.67E+00 1.34E+00. . _ _
- - -Total for Period
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TABLE 1.2-1
' EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT 1977 a
LlqulD EFFLUENTS-SUMMATION OF ALL RELEASES Quarter Quarter Est. Tota ~
Unit 3rd 4 th Error, %
1
] A'. Fission and Activation Products
]
,1 1. Total release (not including Cl 1.85E-01 1.17E-01 y _ t r_i t i isn . cases ._ a loha)
. c 2 Average diluted concentratica durjn_q_ period uCi /ml 4.48E-10 1.04E-09
,I 3. Percent of applicable limit % 4.48E-01 1.04E+00 l+ . Maximum diluted concentration i durino oeriod uti /ml 6.24E-08 5.86E-08
'g 4 .i
- B. Triti um 1 Total release Ci 4.63 7.01E+00 ~
2 Average direted concentration 5 durino period uCi /ml 1.12E-08 6.25E-08
- 3. Perc_nt e of a2plicable limit % 3.74E-04 2.08E-03
] -
i C. Dissolved and Entrained Gases
.1 Ci (LDL (LDL
) 1. Total r e l e a,s e_,
e 2 Average diluted concentration d u r i n_q,y e r i o d _ uCi/n1 (LDL < tot
.b m ,y
__3 .
Percent of acolicable 11;ni t % ( LDL_ _ _(L D!. _
s:
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D. Gross Alpha Radioactivity x
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y y '
- 1. Total release C1 4.54E-05 1.23E-04 --
1.10E-13 1.09E-12 jd _2 . Averace concen_tr_ation released uC i /n1 _ _
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7$[ E. Volume of waste released (prior Liters 2.29E+06 3.39E+06 57 2 ,
t o di lut ion)- . - - - -- .
w..m.
el F. Volume of dilution water used
.; t.. . der i ,e e e r_i o d t i t cc, c.i3E+ii i.i2E+ii .
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[jf 7 1625 504 1 's.* j b
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.. QUAD CITIES NUCLEAR POWER STATION g,
,t[ TABLE 1.2-1 Cont'd
.' EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT 1977 Liqui 0 EFFLUENTS
[E Continuous Mode Batch Mode 7 Quarter Quarter Quarter Quarter,
- j Unit 3rd s
Sr-89 Ci 1.16E-03 CI 1.54E-04
, _S_r-90 C s ,jjk Ci 6.19E-02 3.09E-02 C; 9.05E-02 5.15E-02 1s_)31 __
Ci (LDL (LDL g 1-131
[ Co-58_ Ci 4.17E-04 1.52E-03 Co-60 Ci __
2.24E-02 3.80E-02 Ci (LDL (LDL Mo Zn-61 C1 2.28E-04 (LDL Mn-54_ C1 1.45E-03 1.49E-03 i
Cr Ci __
(LDL (LDL (LDL
[ Zr o,5 Ci ( LDL j Hb C1 (LDL (LDL
.j Mo co Ci ,
(LDL (LDL
" .i&g .
_A_o110- Ci 1.77E-04 (LDL l,y - - .
,I' B a- 1_40 CI _
( LDL (LDL h (LDL (LDL 3 Cs136 Ci s
La-140 C1 1.07E-03 1.24E-03 Ci Unidentified Ci 6.00E-03
.tk - - - - - - -
x$,3.v
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1 Total for Period (_above)_ Cl 1.79E-01 7
yu: ,
.% (LDL fC W W.
Xe-133 C1 <LDL (LOL
.k g4 Xe-135 C1 (LDL Y sh --. -
3 1625 505
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Co. For burial at Nuclear UNITS 1/2 .
Engineering Co., Inc. QUAD-CITIES STATION .
CN - Chemical Nuclear Co. For TABLE 2.0-1 Cont'd Durial at Nuclear Engineering Co., Inc.
DISPOSITION OF HATERIAL I
VOLUME (ft 3) VOLUME (ft 3) MlLLI CURICS CURICS l PER MONTH PER SHIPMENT PER HONTH DATE CO. TRANS. BURIEL SITE PER SillPHENT l I 7-20 CN SilE FF I El 0 j 45 _
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l SilEFFIELD 45 1817 f7-29 CH __
2481.9 2380 114.76 i 7 -29 itN
" 102.9
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" 102.9 534
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i CN ' Chemical Nuclear Co. For TABLE 2.0-1 Cont'd f Burial at Nuclear Engineering Co., Inc.
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? I f DISPOSITION OF MATERIAL , ;
e VOLUME (ft 3) VOLUME (ft 3) MILLI CURICS CURICS h PER SHIPMENT PER #10 NTH DATE CO. TRANS. DURIEL SITE PER StilPMENT PER MONTH l
i !
88.2 5118.05 4359.4 132.6 f 8-31 Hti Sheffield _
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. . - ,:":', l' g 1978 Annual Report 1. -
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1.0 Effluents (Page 3) 91 ' ~~ -' r : CHANGE 1.2 Liquids Released to the Mississipoi from to monthly average concentration 4.73E-09 2.78E-09
% limit 4.8% 2.8%
Table 1.1-1 (Page 14)
Section 3 - Particulates 1st Quarter from to Cs 137 1.19E-02 1.19E-03 Section 3 - Particulates 2nd Quarter from to Sr 89 Blank 1.87E-02 Sr 90 Blank 4.98E-05 Unidentified Blank 6.04E-02 Section 3 - Particulates 4th Quarter from to Sr 89 Blank 3.00E-02 Sr 90 Blank 1.11E-04 Unidentified Blank <LLD
~O Table 1.1-1 (Page 16)
Section 3 - Particulates 2nd Quarter from to Unidentified <LLD 5.20E-03 Section 3 - Particulates 4th Quarter from to Sr 89 Blank 1.93E-03 Sr 90 Blank 2.13E-04 Unidentified Blank 3.00E-02 1978 Annual Report Table 1.2-1 (Page 18) CHA.
Section A - Fission and Activation Products from to Average diluted Concentration - 3rd QTR 2.49E-09 1.26E-09 I Percent of Applicable Li=it - 3rd QTR 2.49E+00 1.26E+00 -
Average diluted Concentration - 4th OTR 9 2.90. O Percent of Applicable Limi ,
DUPLICATE DOCUMENT !
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N o. of pages:
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bl l' b Q f .D( ' y
- Quad-Cities Errata bIY h,Y I Semi-Annual Report - Second Quarter 1979 C 3 9 C Cl ( S O 3 b [
O Table 1A Change From To B. Iodines 2nd Quarter 1979
- 3. Percent of Tech Spec limit Blank 2.45 C. Particulates
- 1. Particulates with half live
> 8 days Blank 2.76E-01
- 2. Average release rate for period Blank 3.51E-02
- 3. Gross Alpha radioactivity Add C1 in unit column D. Tritium
- 1. Total release Blank 7. 90E+01
- 2. Average release rate for period Blank 1.00E+01 Table 1B
- 3. Particulates Sr 89 Blank 4.97E-02 Sr 90 Blank 3.00E-04 Table 1C g 3. Particulates Sr 89 Blank 1.79E-03 Sr 90 Blank 3.13E-04 Table 2A B. Tritium
- 1. Total release Blank 2.71E+00
- 2. Average diluted concentration Blank 1.07E-08
- 3. Percent of applf. cable limit Blank 3.57E-04 Table 2B Liquid Effluents Sr 89 Blank 1.63E-04 Sr 90 Blank 1.34E-04 Unidentified Blank 6.54E-02 Total for period (above)
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