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 J
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SUMMARY
4 i s
i Gaseous and liquid effluents for the period remained at a fraction of
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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 sented the critical pathway for the period with a maximum individual
- 3 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 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.
l
{
.tv in-g 1.2 LIQUIDS RELEASED TO MISSISSIPPI RIVER
(
i 4
A total of 5.68E+06 liters of radioactive liquid wastes contain-
[
ing 0.30 curies (excluding tritium) were discharged from the station during I
n 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
l involved was calculated to be 1402.16 curies.
Solid radioactive wastes 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
.tg The total amount of solid waste packaged for disposal was 21709 cubic feet during the six-month period. The total amount of radioactivity
.A involved was calculated to be 1402.16 curies.
Solid radioactive wastes k'
were shipped to either Nuclear Engineering Company, Sheffield, Illinois, 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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Q,UAD CITIES NUCLEAR POWER STATION M
TABLE 1.1-1 NM~
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EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT 1977 l
-i GASEQUS EFFLUENTS-SUMMATION OF ALL RELEASES
'i; r
Muarter Quarter Est. Tota 4
Unit 3rd 4th Error,g A.
Fission & Activation Gases
~:
CI I.54E+03 7.55E+03 1.
Total release 2.
Avera,qe release rate for_ period uCi/see 1.94E+02 9.50E+02 3.
a.
Percent of Tech. Spec. limit 1.16E-02 6.28E-02 Chimnev b.
Percent of Tech. Spec. Ilmit
,fLDL 6.34E+00 Stack 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 _
3.
a.
Percent of Tech. Spec. limi t statior j
1.95E+00 1.98E+00 F
l um
(.5; '
[f[
C.
Particulates C1 2 38E-01 2.05E-01 1
Parti culate_s with half-lives > 8 days 2.
Averace release rate for_oeriod uC1/sec 2.9AE-02 2.58E-02 1
is:'
3.59E-06 I.42E-05 t.
3 Gross alpha radioactivity
- IEf, sf-?r, D.
T ri t i tr.1 1
M1.7.
C1 5.01E+00 9 99E + 00 d..._,,
1 Tot a l. r.,e l e a se uti/sec 6.30E-01 1.24E + 00
-[
[7 J.,
Aversee release rate for neriod
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h TABLE 1.1-1 Cont'd
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1977 a
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
_Sr c0 6.3cE-oc Cs-134_
5.,3 8 E-_04_
C1 4.67E-04 Cl 1.35E-03 1.54E-03 C s -137_ _ _
Cl 7.51E-03 1.74E-02 Ba-Iho
_La-140
_ __Ci 1.03E-02 2.40E-02 i
Cr51 C;
(LDL
_(tot
(
l Mn54 C1 2.53E-05 4.40E-05 t
=
CoS3 C1 (LDL (LDL i
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
Ce141 C_1 2.84E-04 2.78E-04
.g k
Nb95 Cl 1.LSE-05
( LDL
.t c
)
Cl Ci Cl Unidentified Ci 1.58E-01 k
m 1625 402 g
g s
.. a.
- __.~ _, 2
3 QUAD CITIES NUCLEAR POWER STATION w
TABLE 1.1-1 Cont'd EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1977
(
GASEOUS EFFLUENTS-ELEVATED RELEASE N
Continuous Mode Batch Mode
$^
[
Nuclides Released Unit 3rd 4th
.i 1.
Fission gases Kr-85 CI (LDL
( LDL 3
I K r-85m ___
. 5.81E+02 Ci 7.78E+01 Ci 4.80E+00 2.44E+01 a
'(
r.87 t.,
K r-88 Ci 1.62E+01 1.76E+02 1
?
Xe.131 C1 1.10E+03 4,50E+03 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 Ci (LDL (LDL
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d, U ni den (i f i ed WE Total for Period C1 1.54E+03 7,49g+03 C';
.u 1
2.
todines v
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j I-131 C1 1.99E-01 1.93E-01 t
Ci 8.95E-01 6.97E-01
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l-133 Ci 1.58E+00 4.52E-01
,q* !..
1-133
/d.,
- - -Total for Period C1 2.67E+00 1.34E+00 j
y-1625 503 b
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y QUAD CITIES NUCLEAR POWER STATION n,
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 y
t r_i t i isn. cases._ a loha)
Cl 1.85E-01 1.17E-01 c
2 Average diluted concentratica uCi /ml 4.48E-10 1.04E-09 durjn_q_ period
,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
.i 4
B.
Triti um 1
Total release Ci 4.63 7.01E+00
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2 Average direted concentration 5
durino period uCi /ml 1.12E-08 6.25E-08 Perc_nt of a2plicable limit 3.74E-04 2.08E-03
]
3.
e i
C.
Dissolved and Entrained Gases
.1
)
1.
Total r e l e a,s e_,
Ci (LDL (LDL e
2 Average diluted concentration
.b,y d u r i n_q,y e r i o d _
uCi/n1 (LDL
< tot m
__3.
Percent of acolicable 11;ni t
( LDL_ _
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s:
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D.
Gross Alpha Radioactivity
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x y
y 1.
Total release C1 4.54E-05 1.23E-04 jd
_2.
Averace concen_tr_ation released uC i /n1 1.10E-13 1.09E-12
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Volume of waste released (prior Liters 2.29E+06 3.39E+06 57 2 t o di lut ion)-
w.
.m.
F.
Volume of dilution water used l
e der i,e e e r_i o d t i t cc, c.i3E+ii i.i2E+ii
.; t...
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1625 504
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QUAD CITIES NUCLEAR POWER STATION w
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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
_S_r-90 CI 1.54E-04 C s,jjk Ci 6.19E-02 3.09E-02 1s_)31 C;
9.05E-02 5.15E-02 1-131 Ci (LDL (LDL g
[
Co-58_
Ci 4.17E-04 1.52E-03 Co-60 Ci 2.24E-02 3.80E-02 Mo Ci (LDL (LDL Zn-61 C1 2.28E-04 (LDL Mn-54_
C1 1.45E-03 1.49E-03 Ci (LDL (LDL i
Cr __
[
Zr o,5 Ci
( LDL (LDL j
Hb C1 (LDL (LDL
.j Mo co Ci (LDL (LDL
".i&g.
_A_o110-Ci 1.77E-04 (LDL l,y
( LDL (LDL
,I' B a-1_40 CI h
3 Cs136 Ci (LDL (LDL 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:
.%fC Xe-133 C1 (LDL
<LDL W W.
.k Xe-135 C1 (LOL (LDL g4 Y
3 1625 505 sh
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5 9
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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
l VOLUME (ft 3)
VOLUME (ft 3)
MlLLI CURICS CURICS l
DATE CO. TRANS.
BURIEL SITE PER SillPHENT PER MONTH PER SHIPMENT PER HONTH I
45 1021.5 l
1 l
7-21 CN SiiEFFIELD 45 2037.4 l
7-21 HN SilEFF I ELD 88.2 3157.3 l
l 7-22 liN 102.9 3924.5 7-22 lin I
88.2 4141.6 45 1519.7 7-22 CN l
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CN - Chemical Nuclear Co.
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Burial at Nuclear Engineering a
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DISPOSITION OF MATERIAL VOLUME (ft 3)
VOLUME (ft 3)
MILLI CURICS CURICS f
PER SHIPMENT PER MONTH PER SHIPMENT PER MONTH i
3,l DATE CO. TRANS.
DURIEL SITE I
l 1817 f7-29 CH SilEFFIELD 45 7
itN 102.9 2481.9 2380 114.76 i
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SUMMARY
1 Co.
l'or burial at t!uclear UtilTS 1/2 Engineering Co., Inc.
QUAD-CITIES STATION i
CN ' Chemical Nuclear Co.
For TABLE 2.0-1 Cont'd f
Burial at Nuclear Engineering Co.,
Inc.
)
?
I f
DISPOSITION OF MATERIAL e
h VOLUME (ft 3)
VOLUME (ft 3)
MILLI CURICS CURICS DATE CO. TRANS.
DURIEL SITE PER StilPMENT PER MONTH PER SHIPMENT PER #10 NTH l
i f
8-31 Hti Sheffield 88.2 5118.05 4359.4 132.6 9
104.4 4258 9-1 HN
)
45 3419 9-1 CN i
]
9-2 HN l
105 10712 h
1 9-6 liti 102.9 6897.1 1
l 9-6 CN 45 2201 l
9-7 CN 45 1
6346 I
104.4 6301.9 i
9-7 HN 11844.
9-7 ItN 105 l
i j
9-8 Ct1 45 l
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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
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Section 3 - Particulates 2nd Quarter from to Unidentified
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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 O
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N o. of pages:
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.,O bl l' b Q f.D( ' y Quad-Cities Errata bIY h,Y I
C Semi-Annual Report - Second Quarter 1979 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 3.
Particulates g
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)
DUPLICATE DOCUMENT Entire document previously r - -- -
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