ML19256F419

Excerpts of Radwaste & Environ Monitoring,Jul-Dec 1973.

ML19256F419
Person / Time
Site:	Quad Cities
Issue date:	02/28/1974
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML19256F405	List: ML19256F412 ML19256F416 ML19256F418 ML19256F419 ML19256F421 ML19256F423 ML19256F425 ML19256F431 ML19256F434 ML19256F441 ML19256F446 ML19256F450 ML19256F472 ML19256F475
References
FOIA-79-491 NUDOCS 7912190117
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QUAD CITIES NUCLEAR POWER STATION RADIOACTIVE WASTE AND ENVIRONMENTAL MONITORING JULY THROUGH DECEMBER 1973 5xce8 PTS .

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SUMMARY

Gaseous and liquid effluents for the period remained at a fraction of the Technical Specification limits. Calculations of environmental concen-trations based on effluent, Mississippi River Flow, and meteorological 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 concentration values listed in Appendix B. Table II of 10CFR20. Gamma radiation exposure from noble gases released to the atmosphere represented the critical pathway for the period with a maximum individual dose estimated to be 6 mrem for the six-month period, and 9 mrem for the year 1973, 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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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 atmosphere dur-ing the period July 1 through December 31, 1973, are listed in Table 1.1-1.

A six-month total of 5.7 x 105 curies of noble gases was released during the period with a maximum release rate during any one-hour period of 0.065 Ci/sec. Release rates during any one month of the period did not exceed 10.2% of the Technical Specification limit. Gamma dose rates off-site were calculated based on measured release rates, isotopic composition of the noble gases, and meteorological data for the period. Isodose contours are shown in Figure 1.1-1 for the last six months of the year and in Figu~re

, 1.1-2 for the entire year. Average concentration contours for noble gases are shown in Figure 1.1-3 for the six-month reporting period and in Figure l.1-4 for the year. Based on measured effluents and meteorological data for

the reporting period, the maximum off-site external radiation exposures oc-curred north of the plant and over the Mississippi River immediately west of j the plant. Had a person been present continuously at either of these loca-l tions, his dose would have been 12 mrem. When occupancy and shielding are considered, the dose to an individual is not likely to exceed 6 mrem. For the year, the maximum off-site external radiation exposure occurred over the Mississippi River west of the plant. A person who had been at this location

for the entire year would have received a dose of 20 mrem. The maximum ex-i posure over a land area occurred just north of the site. The dose to an in-l dividual at that location would be 18 mres without correcting for occupancy or shielding. Consideration of occupancy and shielding is likely to reduce the dose to a value not greater than 9 mrem for the year.

A total of 4.2 curies of I-131 and 3.7 curies of I-133 were released during the six-month period. The highest monthly radioiodine release rate was 89%

of the Technical Specification limit prior to revision of the Specifications.

The calculated six-month and yearly average concentration contours for I-131 in air are shown in Figure 1.1-5 and Figure 1.1-6. The maximum off-site six-month average is estimated to be 8 x 10-2 pCi/m3 . The highest yearly average concentration of iodine is estimated to be 0.1 pCi/m3 just west of the site and over the Mississippi River. Thehighestyearlyaverageover land occurred north of the site and was estimated to be 0.08 pCi/m .

Six-month totals of 0.091 curies of beta-gamma emitters and 7.1 x 10-7 curies J of alpha emitters were released as airborne particulate matter. The highest monthly release of beta-gamma particulate activity did not exceed 56% of the Technical Specification limit. Concentration contours for radioactive air-

, borne particulates are shown in Figure 1.1-7 for the reporting period and in L Figure 1.1-8 for the entire year. The maximum off-site average level for the h last six months is estimated to be 2 x 10-2 pCi/m3 . The maximum off-site

{ average level for the entire year is also estimated to be 2 x 10-2 pCi/m 3. I 4

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2 1.2 LIQUIDS RELEASED TO MISSISSIPPI RIVER A total of 1.5 x 107 liters of radioactive liquid wastes contain-ing 10.1 curies (excluding tritium) were discharged from the station. These wastes were released at an average concentration of 1.1 x 10-8 pCi/ml which is 11% of the Technical Specification release limit for unidentified radio-activity. During the same period, 3.8 curias of tritium and 2.3 x 10~"

curies of alpha radioactivity were released. Mouthly 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 7.6 x 10-8 uCi/ml. This particular release occurred on October 5, 1973, when the A Floor Drain Tank, batch number 1591, was being discharged. The dura-tion of this maximum release was 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> and 35 minutes.

Based on measured effluents and long-term average Mississippi R$1er flow, the maximum off-site doses to seven " critical" organs of a person consuming water drawn from the nearest public water intake at Davenport, Iowa, were calcula-ted 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 0.016 pC1/1 for the year. The maximum dose to a body organ was .131 mrem to the thyroid which is .009% of the NCRP limit of 1500 mrem. Almost all of this dose was from I-131. The total body dose was .054 mrem, .011% of the

. 500 mrem limit.

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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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7 TABLE 1.2-1 REPORT OF RADIOACTIVE EFFLUENTS Docket No. 50-254 and 50-265 FACILITY: QUAD CITIES YEAR: 1973 Six Month 1.2 Liquid Effluents Units July Aug. Sept. Oct. Nov. Dec. Total

1. Cross Radioactivity a) Total Release Curles 2.6 1.5 0.8 1.4 1.9 1.7 10.1 b) Average Concentration Released pCi/ml 1.7 E -08 9.8 E -09 6.0 E -09 8.8 E -09 1.2 E -08 1.1 E -08 1.1 E -08 c) Maximum Concentration Released pci/mi 6.5 E -08 6.5 E -08 6.6 E -08 7.6 E -08 7.0 E -08 6.3 E -08 t; d)  % of Tech. Spec. Limit  % 17.0 9.8 6.1 8.8 12.0 10.5

2. Tritium a) Total Release Curies 1.2 1.5 1.4 1.8 19 3.8 b) Average Concentration Released pC1/ml 7.5 E -09 9.8 E -09 1.0 E -08 1.1 E -08 1.8 E -08 2.3 E -08 c) % of Tech. Spec. Limit  % 2.5 E -04 3.3 E -04 3.5 E -04 3.7 E -04 6.0 E -04 7.6 E -04

-3. Dissolved Noble Gases -

Ch IN) a) Total Release Curies ND ND ND ND

'3' ND ND b) Average Concentration

__, Released pCi/mi HD ND ND ND ND ND sg) c) % of Tech. Spec. Limit  %

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4. Gross Alpha Radioactivity a) Total Release Curies 8.3 E -05 2.1 E -05 4.9 E -06 3.0 E -05 5.7 E -05 3.3 E -05 2.3 E -04 b) Average Concentration Released pC1/ml 5.4 E -13 1.3 E -13 3.6 E -14 1.8 E -13 3.5 E -13 2.0 E -13 ND = Not Detect'ble l ' ' b

M.5dmarr#wArmnnen.<4 TABLE 1.2-1 (Cont'd)

REPORT OF RADIDACTIVE EFFLUENTS Docket No. 50-254 and 50-265 YEAR: 1973 FACILITY: QUAD CITIES Six Month ,

Aug. Sept. Oct. Nov. Dec. Total Units July 1.2 1.1guld Effluents

5. Volume of Liquid Waste to Discharge Canal Litera 1.7 E +06 2.2 E +06 2.2 E +06 2.5 E +06 2.7 E +06 3.3 E +06 1.5 E +07 1.5 E +11 1.4 E +11 1.6 E +11 1.6 E +11 1.7 E +11 9.3 E +11

6. Volume of Dilution Water Liters 1.5 E +11

7. Isotopes Released: Curies 0.1 2.7 E -02 1.9 E -02 9.4 E -03 1.6 E -02 2.1 E -02 3.1 E -02 Cs-134 8.4 E -03 Cs-136 3.3 E -03 1.9 E -03 1.4 E -03 1.8 E -03 ND ND 7.3 E -02 5.5 E -02 2.7 E -02 4.4 E -02 5.1 E -02 8.3 E -02 0.3 Cs-137 2.8 E -01 8.9 E -02 2.1 1-131 1.3 4.0 E -02 3.2 E -01 1.4 E -01 ND ND ND 0.2 I-133 1.7 E -01 ND ND 5.3 E -02 3.8 E -02 5.2 E -03 4.5 E -03 8.9 E -03 1.5 E -02 0.1

- Co- 58 2.2 E -02 2.6 E -02 4.3 E -02 0.2 Co- 60 6.0 E -02 4.5 E -02 1.9 E -02 8.0 E -02 1.7 E -02 1.7 E -02 1.6 E -02 3.9 E -02 3.3 E -01 0.5 Cr- 51 7.8 E -03 1.2 E -02 0.1 Mn- 54 1.0 E -02 9.8 E -03 2.8 E -03 3.8 E -03 5.1 E -03 4.7 E -03 2.7 E -03 ND 2.0 E -03 4.9 E -03 0.02 Za- 65 2.3 E -03 2.2 E -02 1.8 E -02 4.9 E -02 Sr- 89 2.8 E -04 1.7 E -03 4.7 E -03 C7s 8.6 E -05 4.0 E -04 6.8 E -04 6.5 E -06 2.9 E -04 4.1 E -04 1.9 E -03 Sr- 90 ND N ND ND ND ND ND Ba-140 ND 5.1 E -03 5.1 E -03

La-140 ND ND ND ND 1.1 E -01 ND ND ND ND ND 0.1

__. Na- 24 ND ND ND 0.1 Tc- 99m 1.1 E -01 ND ND g

2.0 E -02 5.6 E -03 3.3 E -02 1.0 E -03 ND ND 0.1 Cys ZrNb- 95 ND ND 1.5 E -04 Fe- 59 1.5 E -04 ND ND ND ND = Not Detectable

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2.0 SOLID RADIOACTIVE WASTE g

- The total amount of solid waste packaged for disposal was 1.27 x 10

cubic feet during the last six-month period. The total amount of radio-activity involved was calculated to be just under 238 curies. Solid radio-active wastes were shipped to either Nuclear Engineering Company, Sheffield, Illinois or Chemical Nuclear Services, Bellevue, Washington. Date, volume and radioactivity of each shipment are shown in Table 2.0-1.

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TABLE 2.0-1 SOLID RADI0 ACTIVE WASTE QUAD CITIES 1973 Volume Volume Volume 3

Date (ft ) Curies Date (it 3) Curies Date 3 (ft ) Curies 7-02 117.6 2.04 9-04 117.6 .40 12-03 117.6 .73 7-03 176.4 7.80 9-05 117.6 .43 12-05 117.6 1.11 7-05 176.4 9.13 9-06 117.6 .89 12-06 117.6 .66 7-06 117.6 10.28 9-10 117.6 1.32 12-10 117.6 3.10 7-07 176.4 8.19 9-11 117.6 1.45 12-11 117.6 .83 7-09 176.4 4.25 9-12 448.35 1.27 12-12 117.6 1.44 7-10 176.4 13.88 9-13 117.6 .96 12-14 117.6 1.70 7-11 117.6 3.68 9-14 117.6 2.55 12-17 117.6 1.29 7-13 117.6 11.39 9-17 117.6 1.08 12-18 117.6 2.25 7-14 117.6 1.00 9-18 117.6 1.87 12-20 58.8 1.22 7-16 117.6 6.76 9-19 117.6 1.73 12-21 117.6 1.11 7-17 117.6 9.68 9-20 117.6 1.05 12-26 117.6 .34 7-18 117.6 11.40 12-27 499.8 .51 7-19 117.6 13.65 10-01 117.6 .55 12-28 176.4 1.07 7-20 117.6 .96 10-02 117.6 .68 12-31 58.8 .27 7-21 117.6 5.83 10-03 117.6 .43 7-23 279.3 .37 10-04 117.6 .41 7-24 58.8 1.12 10-05 117.6 2.77 7-25 117.6 .87 10-09 117.6 1.26 7-26 117.6 1.80 10-11 382.2 .11 7-27 117.6 1.98 10-22 58.8 .62 7-28 117.6 3.13 *10-23 44.1 1.03 7-31 117.6 .85 *10-24 44.1 1.43

• 10-25 44.1 .67 8-01 117.6 .85 *10-26 44.1 .37 8-02 345.4 .06 10-29 117.6 .93 8-07 58.8 .70 8-08 58.8 .08 11-01 117.6 1.91 6-Month 8-09 58.8 .45 11-02 117.6 3.09 Total 12693.35 237.35 8-10 58.8 2.38 11-05 117.6 1.72 8-13 330.7 .36 11-06 117.6 4.01 8-14 58.8 5.68 11-07 117.6 3.74 8-15 58.8 .59 11-08 117.6 2.14 8-16 58.8 .03 11-09 117.6 4.09 8-17 58.8 1.47 11-13 117.6 5.46 8-20 58.8 .92 11-14 117.6 1.24 8-21 58.8 1.95 11-15 117.6 .38 B-22 58.8 1.56 11-16 117.6 .57 8-23 58.8 3.76 11-19 117.6 1.12 8-24 58.8 1.86 11-20 58.8 .89 B-27 117.6 1.34 11-21 176.4 1.89 8-28 117.6 .36 11-26 176.4 1.44 8-29 117.6 1.03 11-27 117.6 1.16 8-30 117.6 .11 11-29 117.6 1.47 B-31 117.6 .83 11-30 117.6 .73 ,

• Waste shipped to Chemical Nuclear Services, Bellevue, Washington. All other waste shipped to Iuclear Engineering Co., Ine , Sheffield, Illinois.

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