ML19256F418

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Excerpts of Radwaste & Environ Monitoring,Jan-June 1973.
ML19256F418
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 06/30/1973
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML19256F405 List:
References
FOIA-79-491 NUDOCS 7912190115
Download: ML19256F418 (11)
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'O QUAD CITIES NUCLEAR POWER STATION SECTION II: RADIOACTIVE WASTE AND ENVIRONMENTAL MONITORING JANUARY THROUGH JUNE 1973 5 X C E R P T.S 1625 178

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SUMMARY

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Gaseous and liquid effluents for the period remained at a fraction of the Technical Specification limits. Calculations of environmental concentrations based on effluent, Mississippi River Flow, and meteoro-logical data for the period indicate that consumption by the public of radioactive materials attributable to the plant is unlikely to exceed 1% of those that could result from continuous exposure to the concentra-tion values listed in Appendix B, Table II of 10CFR20. Gamma radiation exposure from noble gases released to the atomosphere represented the critical pathway for the period with a maximum individual dose estimated to be two mrem for the six-month period, 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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3 1.0 EFFLUENTS 1.1 CASEOUS EFFLUENTS TO THE ATMOSPHERE Measured concentrations and isotopic composition of noble gases, radioiodine, and particulate radioactivity released to the atmos-phere during the period January 1 through June 30, 1973, are listed in Table 1.1-1.

A six-month total of 3.3x105 curies of noble gases was released during the period with a maximum release rate during any one-hour period

{ of 0.2 Ci/sec. Release rates during any one month of the period did not I

exceed 7.5% of the Technical Specification limit. Cam =a dose rates off-site were calculated based on reasured release rates, isotopic composition of the noble gases, and meteorological data for the period. Isodose contours are shown in Figure 1.1-1. Average concentration contours for noble gases are shown in Figure 1.1-2. Based on measured effluents and meteore.sgical data for the period, the maximum off-site external radiation exposure occurred over the Mississippi River immediately west of the plant.

Had a person been present continuously at this location, his. dose would have been 5 mrem. The maximum off-site external gamma dose over land areas, without correcting for occupancy or shielding, was 4 mrem at the north and northwest site boundaries. When occupancy and shielding are considered, the dose to an individual is not likely to exceed 2 mrem.

l A total of 1.29 curies of I-131 and 0.72 curies of I-133 were released during the six-month period. The highest monthly radioiodine release rate 37% of the Technical Specification limit. The highest single j day release occurred on June 7, 1973, via the reactor building ventilation f stack following a seal failure on a Unit 2 cleanup system re-circulation 4, .

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4 1.1 GASEOUS EFFLUENTS TO THE KfMOSPHERE (Cont'd) g pump. The average concentration in the Unit 2 reactor building vent for June 7 was 4.58x10-ll pCi/ce. The calculated six-month average .

concentration contours for I-131 in air are shown in Figure 1.1-3.

The maximum off-site six-month average is estimated to be 1x10-2 pCi/m3 .

Six-month totals of 0.028 curies of beta-gamma emitters and 9.9x10-7 curies of alpha emitters were released as airborne particulate

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matter. The highest monthly release of beta-gamma particulate activity did not exceed 8% of the Technical Specification limit. Concentration contours for radioactive airborne particulates are shown in Figure 1.1-4.

The maximum off-site six-month average level is estimated to be 3x10-3pci/m ,3 O

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TABLE 1.1-1 REPORT OF RADI0 ACTIVE EFFLUENTS DOCKET NOS: 50-254 and 50-265 YEAR: 1973 FACILITY: QUAD CITIES Feb ruary March April May June 6 Mo. Total 1.1 Caseous Effluents Units January

1. Gross Radioactivity Releases 5.0 E+4 5.9 E+4 5.4 E+4 4.0 E+4 4.4 E+4 8.4 E+4 3.3 E+5 a) Total Release Curies b) Maximum Release Rate mci /sec 85 100 208 55 66 54 c) Isotopes Released Curies Xe-138 1.6 E+4 1.4 E+4 1.6 E+4 1.3 E+4 1.9 E+4 3.2 E+4 1.1 E+5 Kr-87 7.1 E+3 7.9 E+3 7.3 E+3 6.3 E+3 7.6 E+3 1.5 E+4 5.1 E+4 Kr-88 5.5 E+3 6.0 E+3 6.0 E+3 4.0 E+3 4.0 E+3 8.1 E+3 3.4 E+4 Kr-85m 2.6 E+3 6.1 E+3 3.7 E+3 2.2 E+3 2.0 E+3 4.3 E+3 2.1 E+4 Xe-135 8.1 E+3 7.7 E+3 8.0 E+3 6.5 E+3 6.3 E+3 1.3 E+4 5.0 E+4 Xe-133 1.1 E+4 1.9 E+4 1.3 E+4 7.8 E+3 5.0 E+3 1.2 E+4 6/8 E+4 d) % of Chimney Limit  % 3.9 5.3 3.5 3.1 4.0 7.5 e) % of Vent Stack Limit  % ND ND ND 0.6 0.4 ND
2. Iodine Releases a) Isotopes Released Curies .

1-131 7.2 E-2 4.0 E-2 1.3 E-1 1.4 E-1 3.2 E-1 5.9 E-1 1.29 1-133 5.5 E-2 3.7 E-2 4.3 E-4 4.0 E-3 1.3 E-2 6.1 E-1 0.72 I-135 ND ND 8.3 E-4 1.8 E-3 8.0 E-3 5.1 E-1 0.52 C7s b) % of Chimney Limit  % 0.4 0.2 1.0 1.3 2.8 4.9 c) % of Vent Stack Limit 1.8 1.3 3.1 14.6 37.3 13.0

()  %

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ND = Not detectable.

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TABLE 1.1-1 (Cont'd)

REPORT OF RADI0 ACTIVE EFFLUENTS DOCKET NOS: 50-254 and 50-265 YEAR: 1973

, FACILITY: QUAD CITIES April May June 6 Mo. Total Units January Feb rua ry_ March 1.1 Gaseous Effluents

3. Particulate Releases 4.3 E-3 3.3 E-3 4.8 E-3 9.5 E-3 2.8 E-2 Curies 3.5 E-3 2.5 E-3 2.2 E-8 9.9 E-7 a) Gross Beta-Gamma Curies 1.2 E-7 1.0 E-7 6.4 E-7 1.6 E-8 9.5 E-8 b) Gross Alpha c) Isotopes Released Curles 1.6 E-4 2.9 E-4 6.8 E-4 1.1 E-4 2.7 E-5 6.5 E-6 6.0 E-5 Sr-89 2.0 F-6 4.3 E-6 1.2 E-6 2.5 E-5 1.2 E-5 4.4 E-6 1.0 E-6 2.7 E-3 Sr-90 4.2 E-4 5.2 E-4 1.7 E-4 1.3 E-4 2.4 E-4 Cr-51 1.2 E-3 1.6 E-3 3.4 E-3 1.7 E-4 1.5 E-4 4.4 E-4 2.4 E-4 7.5 E-4 1-131 2.2 E-5 2.4 E-5 ND ND 6.0 E-5 ND 1.4 E-5 2.4 E-5 1.4 E-t Ca -134 ND 9.0 E-6 4.8 E-5 3.5 E-5 2.0 E-5 Ca-137 2.1 E-4 1.0 E-4 7.4 E-5 5.3 E-4 1.3 E-3 2.7 E-4 1.1 E-4 3.8 E-4 C0-58 4.4 E-5 9.5 E-5 5.3 E-5 5.2 E-5 5.8 E-5 Co-60 7.6 E-5 ND ND 2.9 E-5 ND 2.9 E-5 ND ND Fe-59 ND 4.7 E-5 ND ND 4.7 E-5 ND ND Ba-140 ND ND 4.1 E-5 5.8 E-5 9.8 E-5 2.0 E-4 ND La-140 0.16 0.03 0.02 0.04 0.07 d) % of Chimney Lir't  % 0.19 8.0 3.7 2.6 5.6 1.3 3.7 e) % of Vent Stack Limit 4;., Sum of Iodines &

Particulates C7s N 0.6 0.4 1.1 1.3 2.8 5.0 ty, a) % of Chimney Limit  %

8.8 17 41 21 5.5 4.0 b) % of Vent Stack Limit  %

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ND = Not detectable.

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11 j 1.2 LIQUIDS RELEASED TO MISSISSIPPI RIVER 7

A total of 1.8 x 10 liters of radioactive liquid wastes containing 11.3 curies (excluding tritium) were discharged from the station. These-wastes were released at an average concentration of 1.4 x 10-8 pCi/ml which is 14% of the Technical Specification release limit for unidentified radio-activity. During the same period,11.9 curies of tritium, 0.034 curies of dissolved noble gases, and 6 x 10~ curies of ;.lpha radioactivity were released.

Monthly 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

8. 7 x 10-8 uCi/ml. This particular release occurred on May 26-27, 1973, when the A Floor Drain Tank, batch number 1356, was being discharged. The duration of this maximum release was 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> and 37 minutes.

Based on measured effluents and long-term average Mississippi River flow, the maximum off-site doses to seven " critical" organs of a person con-

. suming water drawn from the nearest public water intake at Davenport, Iowa, were calculated using ICRP (Ref.1.2-1) assumptions; these data are summarized in TABLE 1.2-2. The average concentration (excluding tritium) in drinking water was 0.061 pC1/1 for this semi-annual period. The maximum dose to a body organ was 0.057 mrem to the thyroid which is 0.004% of the NCRP limit of 1500 mrem. Almost all of this dose was from I-131. The total body dose was 0.043 mrem, 0.009% of the 500 mrem limit. Most of this whole body dose was from Na-24.

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Ref. 1.2-1: International Commission on Radiation Protection, Radiation Protection, ICRP, Publication 2, Pergamon Press,1959. .

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TABLE 1.2-1 REPORT OF RADIDACTIVE EFFLUENTS DOCKET NOS: 50-254 and 50-265 YEAR: 1973 FACILITY: QUAD CITIES Units January Feb rua ry March April May June 6 Mo. Total 1.2 Liquid Effluents

1. Cross Radioactivity 11.3 Curies 1.21 1.70 0.70 2.15 4.69 0.85 a) Total Release b) Average Concentration 5.4 E-09 1.4 E-08 Released pCi/mi 1.0 E-08 1.4 E-08 4.3 E-09 2.2 E-08 3.8 E-08 c) Maximum Concentration 6.4 E-08 Released pC1/mi 7.0 E-08 8.4 E-08 5.0 E-08 7.0 E-08 8.7 E-08 d) % of Tech. Spec.

% 10 14 4 22 38 5 Limit

2. Tritium 1.40 1.19 11.9 2.17 2.51 2.22 2.40 a) Total Release Curies b) Average Concentration 7.6 E-09 Released pCi/ml 1.9 E-08 2.1 E-08 1.4 E-08 2.4 E-08 1.1 E-08 c) % of Tech. Spec.

% 6.2 E-04 7.1 E-04 4.5 E-04 8.0 E-04 3.7 E-04 2.5 E-04 Limit

3. Dissolved Noble Gases 3.4 E-02 a) Total Release Curies 9.4 E-04 2.6 E-04 3.3 E-02 ND ND ND b) Average Concentration Released pCi/ml 8.1 E-12 2.2 E-12 2.0 E-10 ND ND ND

--- c) % of Tech. Spec.

C7N Limit  % 2.0 E-05 5.5 E-06 5.1 E-04 N

'J' 4. Gross Alpha Radioactivity Curies 2.3 E-06 2.2 E-06 5.8 E-05 4.8 E-05 4.6 E-04 3.4 E-05 6.0 E-04

__, a) Total Release b) Average Concentration C3D Released pCi/ml 1.9 E-14 1.8 E-14 3.5 E-13 4.8 E-13 3.7 E-12 2.2 E-13 ty,

5. Volume of Liquid Waste .

to Discharge Canal Liters 4.0 E+06 3.5 E+06 3.6 E+06 2.5 E+06 2.0 E+06 1.9 E+06 1.8 E+07 g

ND = Not delectable w 1

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9 0 TAB LE 1. 2-1 (Con t ' d) REPORT OF RADIOACTIVE EFFLUENTS DOCKET NOS: 50-254 and 50-265 YEAR: 1973 FACILITY: QUAD CITIES January February Eorch April May June 6 Mo. Total 1.2 Liquid Effluents  !! nits

6. Volume of Dilution 1.6 E+11 1.0 E+11 1.2 E+11 1.6 E+11 7.8 E+11 Water Liters 1.2 E+11 1.2 E+11
7. Isotopes Released Curies 0.11 6.0 E-04 1.5 E-03 4.9 E-03 9.4 E-02 7.7 E-03 Co-134 0.002 Ba-La-140 2.1 E-03 2.2 E-01 4.2 E-01 1.1 E-01 4.6 E-01 3.6 E-01 7.9 E-02 1.7 I-131 1.9 E-01 3.1 E-02 0.23 Cs-137 1.6 E-03 2.8 E-03 5.5 E-04 2.3 E-03 9.8 E-02 9.3 E-02 5.0 E-02 1.3 E-01 4.3 E-01 7.2 E-02 0.87 Co-58 3.3 E-01 7.4 E-02 0.63 Co-60 4.0 E-02 4.1 E-02 1.9 E-02 1.3 E-01 3.3 E-01 4.9 E-01 2.0 E-01 1.02 1.7 E-01 2.38 Cr-51 1.7 E-01 0.27 3.6 E-03 4.0 E-03 1.0 E-02 1.5 E-02 1.2 E-01 5.2 E-03 Mn-54 4.7 E-02 8.7 E-03 0.065 5.6 E-04 4.9 E-04 9.5 E-04 6.8 E-03 Zn-65 5.0 E-03 6.9 E-04 0.015 Sr-89 2.7 E-03 2.8 E-04 1.9 E-03 4.9 E-03 4.4 E-05 1.6 E-04 1.1 E-04 1.2 E-04 6.4 E-05 6.0 E-04 Sr-90 1.0 E-04 1.0 E-02 2.2 E-02 7.0 E-03 9.8 E-04 - -

2.2 E-04 ,

0.04 Cu-64 2.4 E-02 9.0 E-04 0.03 1-132 1.3 E-03 2.3 E-03 1.3 E-03 2.9 E-05 4.1 E-02 3.4 E-02 4.8 E-02 5.9 E-02 1.9 E-02 2.5 E-02 0.23 I-133 0.015 Mn-56 7.5 E-03 -

3.0 E-03 4.2 E-03 - -

4.8 E-02 1.8 E-01 8.0 E-02 6.9 E-02 -

3.5 E-03 0.38 Na-24 3.3 E-02 0.37 5.2 E-02 3.5 E-02 8.2 E-03 1.6 E-01 1.0 E-02

-* W-187 1.3 E-05 0.14 1.0 E-02 7.8 E-02 7.5 E-03 3.4 E-02 1.1 E-02 C7% Tc-99m 0.003 Ps) Mo-99 3.2 E-03 LJ7 8.8 E-05 8.8 E-05 As-76 0.094 Np-239 9.4 E-02 1.8 E-04 1.9 E-03 4.2 E-03 9.8 E-03 0.016 ZrNb-95 0.002 C33 Fe-59 2.4 E-03 C7s 8.2 E-05 8.2 E-05 Ce-141. 2.1 E-04 Ce-144 2.1 E-04 3.0 E 3.0 E-04 Sb-124 C

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15 2.0 SOLID RADIOACTIVE WASTE The total amount of solil waste packaged for disposal was 2.29x10" cubic feet during the six-month period. The total amount of radioactivity in-volved was estimated to be 56 curies. All solid radioactive wastes were shipped to Nuclear Engineering Company, Sheffield, Illinois. Date, volume and radioactivity of each shipment are shown in Table 2.0-1.

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16 TABLE 2.0-1 ,

SOLID RADIOACTIVE WASTE

  • QUAD CITIES 1973 Volume Volume Date (ft 3) Curies _ Date (ft 3) Curies 1-04 551 0.43 5-01 478 1-85 1-09 551 0.92 5-03 478 0.28 1-10 551 0.49 5-10 110 0.73 1-12 309 0.42 5-14 478 2.76 1-16 441 0.65 5-15 441 2.06 1-18 Af? 0.65 5-22 478 l'.56 1-22 551 0.53 5-24 801 1.93 1-25 441 0.37 5-31 213 0.99 1-26 441 0.75 1-29 559 0.85 6-04 367 1.07 6-07 147 1.24 2-01 441 0.51 . 6-12 220 1.84 2-05 441 0.70 6-14 147 0.36 2-08 441 0.28 6-18 960 0.01 2-13 441 0.47 6-22 118 1.81 2-15 441 0.51 6-23 118 0.30 2-20 551 0.74 6-25 118 1.73 2-22 441 0.58 6-26 118 1.87 2-23 441 0.68 6-27 118 0.24 6-28 588 2.85 6-29 59 0.06 3-01 463 0.66 6-30 176 1.68

. 3-06 441 0.52 3-08 441 0.58 3-14 441 0.64 3-16 441 0.47 3-20 441 0.30 3-22 441 0.51 3-27 441 0.25 3-29 485 1.74 4-03 478 0.61 6-Month 22,900 56 4-05 441 2.35 Total 4-10 463 0.29 4-12 478 2.64 4-17 470 2.28 4-19 441 2.28 4-24 441 1.11 4-26 463 1.13 1625 188 0 .

  • All waste shipped to Nuclear Engineering Company, Inc. , Sheffield, Illinois

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