ML19290B889

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Radioactive Effluent Release Rept,Jan-June 1977
ML19290B889
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 06/30/1977
From:
INDIANA MICHIGAN POWER CO.
To:
Shared Package
ML17174B224 List:
References
FOIA-79-488 NUDOCS 7912140349
Download: ML19290B889 (17)
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.f RADIOACTIVE EFFLUENT RELEASE REPORT INDIANA & MICHIGAN POWER COMPANY DONALD C. COOK NUCLEAR PLANT UNIT 1 BRIDGMAN,7tICHIGAN January 1,1977 through June 30, 1977 i

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Docket No. 50-315 1

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License No. DPR-58

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7 INDT RODUCTION This yeport discusses the radioactive discharges from Unit 1 of Donald C. Cook Nuclear Plant during the first six months of calendar year 1977.

The format presented in Section 5.4.lB of " Appendix B Technical Specifications" for the above-mentioned unit, is fcilowed.

On December 23, 1976, a few days prior to this reoorting ceriod, the Unit was shutdown for its first refueling.

The unit was brought back to power on February 23, 1977 and it was niaced in a power ascension program until April 1, 1977.

From April 1,1977 to the end of this reporting period, the Unit was operated to meet the system load requirements.

The liquid and gaseous discharges, during the first and second quarters of this reporting period remained within one percent of their respective Technical Specification limits.

The doses to individuals and the population in general within a 60 mile radius of the plant, remained well within the limits of 10 CFR Part 50.

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II.

Radioactive Releases Details' of the radioactive discharges from the Unit during the first six months of 1977 are presented in Appendix A, in the format of Section 5.4 of Appendix B Environmental Technical Specifications.

As in previous ' reports, the releases were well within the limits of Appendix B Environmental Technical Specifications.

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III.

Radiological Imoact on Man calculated using the measured effluents and meteorological given in Appendix A and Appendix B of this report, respectively Liquid Releases releases at frequent intervals.The liquid releases consist of several batch releases for the purpose of dose calculations.These were treated as continuous factor of 10 was used for all liquid pathways.

A constant dilution doses to individuals from liquid pathways are given below:

The estimated Pathway Organ Dose in Millirem 1.

Drinking Water Whole Body 4.72 x 10-4 GI Tract

5. 71 x 10-4 Thyroid 6.60 x 10-4 Bone 3.07 x 10~4 2.

Fish Consumption Whole Body

1. 56 x 10-2 GI Tract 9,49 x 10-3 Thyroid 1.70 x 10~4 Bone 1.14 x 10-2 3.

Shoreline Activities Whole Body 3.29 x 10-4 Skin 3.86 x 10-4 4.

Swimming Whole Body 9.06 x 10 -6 Skin 1.11 x 10-5 5.

Boating Whole Body 4.53 x 10-6 r

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-6 5.55 x 10 Gaseous Releases

} } } Lh b ceriod. There were 35 batch releases during this reporting using the measured meteorological data at the times of releases. Doses w 3 ~"

Quarterly averages of meteorological data were used in estimating the doses from the continuous releases during each of the two cuarters. The doses received by individuals through the various gaseous patDways are listed below: Pathway Location Organ Dose (mrem) Air Submission Worst Sector Whole Body 2 x 10 -3 Site Boundary -2 Skin 2 x 10 Inhalation a -2 Thyroid 4.9 x 10 Infant-Cow Milk Hearest Cow 3.7 x 10 ~1 Consumption (1.8 mile ENE) Infant Inhalation Nearest residence (.5 mile south) 2.5 x 10 -2 Adult Inhalation Nearest residence (.5 mile south) Thyroid 2.1 x 10 -2 Adult Leafy Veg. -1 Consumption 2.2 x 10 The general population, within a 60 mile radius of the pla 2.31 x 10-gt would receive a total whole body dose of man rem and skin dose of 1.08 x 10-1 man rem as a consequence of the gaseous effluents from the facility during the first two guarters of 1977 .d. r ( i l T573 147 s h d l>q <,1 4

IV. Meteorological Data Appendix.B.contains the cumulative joint-frequency distribution of wind speed and wind direction corresponding to various atmospheric stability classes for both quarters. The meteorological condition during each of the batch gaseous effluent rebases are also furnished in the same appendix. 1578 148

~ V. Conclusions During the first two quarters of the calendar year 1977, Unit 1 generated 2,022,170 MWH Gross of electrical energy.- The operating record for this period indicates that the Unit was operating 68.8% of the time at an average capacity factor of 42%. This relatively low capacity factor resulted from a fuel conservation program to meet system requirements. This report indicates that all radioactive effluents released from this Unit remained within one percent of their technical specification i limits. Further, the radiological consequences to the general populace from these releases were well within the limits of 10 CFR Part 50. Based on this report and similar reports in the l past, it is concluded that the Unit performed without causing any l significant hazard to the health and safety of the public and the environment at large during the first two and a half years of its operation. This further assures that Unit 1, and Unit 2 when in operation, can be operated as designed, with minimal hazard to health and safety of the general public. 1578 149 m 4 } 6 i t

l APPENDIX A Radioactive Release Data A 1578 150 ~

.m First Quarter Second Quarter j l GASES P ( A. Fission and Activation Gases 1. Total released, curies Batch @ 3.8291 2 1.770 X 10-2 1.9714 2.8427 X 10-2 Continuous 11.4337 3.534 93.3615 t 1.3754 2. Average release rate,uC1/sec. Batch 33.982 63.1859 Continuous 1.4704 ,11.8744 3. Percent of Technical Specification Limit 8 .00943 .0575 y .00105 .00680 4. Totals for each isotope released, curies, elevated Batch Xe-133 3.5523 t 6.963 X 10- 3 1.6288 3.901 X 10-3 Xe-135 4.871 X 10-5 2 1.968 X 10-s .1902 1.038 X 10-3 Xe-133 m 1.839 x 10-3 2 5.472 X 10-4 1.879 X 10-2 1.496 X 10- 3 @2749 1.017 X 10-2 5.739 X 10-2 8.146 X 10-3 Kr-85 < 7.474 X 10-11 5.305 X 10-2 6.250 X 10- 3 Kr-85m Kr-87 <2.433 X 10-10 < 1.177 X 10-10 Kr-88 <1 844 X 10-10 2.212 X 10-2t 7.377 X 10- 3 Ar-41 <1.513 X 10-10 1.024 X 10- 3 2.192 X 10-4 s .!i Continuous I h Xe-133 11.4296 3.5333 92.5232 1.1083 Xe-135 1.980 X 10 3 1.22 X 10-4 .3252 7.950 X 10-2 i Xe-133m 2.120 X 10 3 6.480 X 10-4 2.120 X 10- 3 6.480 X 10-4 Kr-85 <6.177 X 10+ 3 3.093 X 10- 3 1.259 X 10- 3 y', Kr-85m <1.259 X 10+1 2.495 X 10-2 1.382 X 10-2 Ar-41 <2,547 X 10+1 .4829 1.719 X 10-1 i B t t 1578 151 o A-1 h 1 J

First Quarter Second Quarter B. Iodines 1. Total I-131 released, curies Batch 2.595 X 10 4 t 8.363 X 10-6 1.309 X 10-4 2.447 X 10-6 Continuous 8.'023 X 10- 3 1.702 X 10-3 9.979 X 10-3 t 5.926 X 10-4 2. Average release rate, uCi/sec. Batch Continuous ~2.304 X 10- 3 4.196 X 10-3 1.032 X 10- 3 1.269 X 10-3 3. Percent of Technical Specifications limit .601 .gg4

4. Total curies of each iodine isotope released Batch I-131 2.595 X 10-4 8.363 X 10-6 1.309 X 10-4 2.447 X 10-6 I-133 <l.962 X 10-13 1.989 X 10-7 t 5.528 X 10-a Continuous I-131 8.023 X 10-3 1.702 X 10-3 9.979 X 10-3 5.926 X 10 4 I-133 1.592 X 10 6 5.924 X 10-7 2.965 X 10-3 6.218 X 10-4 C.

Particulates 1. Total (half life greater than 8 days), curies < 2.633 X 10-6 < 2.662 X 10-6 2. Average release rate, pCi/sec. < 3.386 X 10-7 < 3.386 X 10-7 3. Percent of Technical Specification Limit < 6.095 X 10-s < 6.095 X 10-s 4. Total release of each radionuclide, curies Ba-140 <2.633 X 10-6 < 2.662 X 10-6 5. Gross alpha relecse, curies < 2.31a X 10-7 < 2.340 X 10-7 i 1 k 1578 152 A-2 b

W = r First Quarter Second Quarter l i D. Tritium [ 1.. Total release, c,uries Batch 1.231 X 1013 9.399 X 10-3 9.144 X 10-5 6.981 X 10~6 Continuous 9.461 X 10-2 7.223 X 10- 3 1.023 X 10-2 i7.810 X 10~" 2. Average release rate. uCi/sec. Batch 1.093 X 10-2 2.9308 X 10~3 Continuous 1.217 X 10-2 1.3011 X 10- 3 3. Percent of MPC Limit i G.272 .0498 O 'I (' i fk IL i 9 O i A-3

a i First Quarter Second Quarter LIQUIDS E. Mixed Fission and Activation Products k 1. Total release, curies .68168 2.863 X 10-2 .1802 7.434 X 10- 3 2. Average concentration,pCi/mi 2.1454 X 10-a 1,747 x 10-a 3. Percent of Technical Specification Limit .0808 .2'893 4. Total for each radionuclide released, curies Gross Beta .3859 1.708 X 10-2 .1152 2.739 X 10-3 Co-58 .3240 3.125 X 10-3 6.109 X 10-2 t 9.747 X 10-4 Co-60 .1187 1 2.304 X 10- 3 .4.873 X 10-2 8.426 X 10-4 I-131 2.563 X 10-3 t 4.207 X 10-4 7.172 X 10-3 3.051 X 10-4 I-133 4.183 X 10-s 7.978 X 10-6 7.294 X 10-6 3.377 X 10-6 Cs-137 5.457 X 10-2 2.494 X 10- 3 1.299 X 10-2 i 9,404 X 10-4 Cs-134 5.167 X 10-2 2.240 X 10-3 2.441 X 10-2 2 1,074 X 10-3 Mn-54 2.601 X 10-2 1.588 X 10-3 1.313 X 10-2 6.656 X 10-4 Cs-136 3.271 X 10-4 1.251 X 10-4 6.190 X 10-4 2.743 X 10-4 Nb-95 1.447 X 10-2 1.520 X 10- 3 6.069 X 10-3 6.153 X 10-4 Zr-95 5.293 X 10-3 1.633 X 10- 3 1.065 X 10- 3 2.636 X 10-4 Fe-59 8.919 X 10-3 1.982 X 10-3 2.023 X 10-4 6.776 X 10-5 Na-24 < 2.723 X 10-4 9 2.309 X 10-4 3.605 X 10-5 lj Co-57 9.348 X 10-3 5.984 X 10-4 1.582 X 10-4 5.945 ). 10-s L. Sn-113 8.136 X 10-5 3.9.63 X 10-5 1.070 X 10-4 4.143 X 10-s 'O Cr-51 5.660 X 10-2 9.288 X 10-3 3.458 X 10-3 1.035 X 10- 3 Sb-124 2.459 X 10-3 1.254 X 10-4 < 3.903 X 10-3 2 Zr-97 < 3.903 X 10- 3 3.392 X 10-4 1.283 X 10-4 Ag-110m 6.628 X 10-3 1.149 X 10-3 3.913 X 10-4 1.066 X 10-4 i F. Tritium i E 1. A Total released, curies { 60.2238 .4959 59.3552 .0941 g 1578 154 A-4 C A

.w. h First Quarter L Second Quarter 4 s 1 2. Average concentration, pCi/ml f 1.8954 X 10-6 1.561 X 10- 8 5.7537 X 10-6 9.122 X 10-9 f 3. Percent of MPC Limit .0632 .1918 G. Dissolved and Entrained Gases 1. Total released, curies 2.0765 X 10-2 8.740 X 10-4 9.4295 X 10-4 7.139 X 10-5 2. Average concentration, uCi/ml 6.535 X 10-10 9.1407 X 10-11 3. Percent of Technical Specification Limit O 4 Total for each radionuclide, curies Ar-41 3.270 X 10-4 1.031 X 10-4 3.467 X 10-s 9.643 X 10-6 Xe-133 1.293 X 10-2 2.954 X 10-4 6.745 X 10-4 4.951 X 10-s Xe-133m 1.835 X 10-3 3.256 X 10-4 < l.172 X 10- 3 Xe-135 2.907 X 10-3 5.588 X 10-5 2.192 X 10-4 1.015 X 10-s Kr-85 2.766 X 10-3 9.406 X 10-5 1.458 X 10-5 2.084 X 10-6 H. Alpha Radioactivity, curfes < 3.264 X 10-3 < l.519 X 10- 3 I. Volumes 1. Total volume, prior to dilution, liters 3.8152 X 10+6 1.9535 X 10+6 2. Total Dilution Water, liters 3.1770 X 10+10 1.0314 X 10+10 1573 155 9 s w

V 4, J. Solid Wastes 1.. Evaporator Bottord 256.879 cubic meters 31.307 curies ~ Co-58 Co-60 19 shipments by truck to Sheffield, Illinois 2. Dry Compressibles e 148.116 cubic meters 42.117 curies Co-58, Co-60 11 shipments by truck to Sheffield, Illinois 1 shipment by truck to Morchead, Kentucky e / e 4 ) e t 1578 iS6 I A-6

pav-- NOTES @ Numbers following : are estimated of sampling and analytical error. (i; All figures that are preceded by < are calculated from the minimum de.tectable concentration which can be seen by the instruments used for analysis. ({j Using 2 X 10-7 uC1/cc as the applicable limit. (4) Not including 1.3767 curies of Na-24 released during secondary system testing. (5) Using 3 X 10 3 as the applicable limit d5;' No limit established o O O e \\513 \\bl e K A-7

Y t f. t ni LAKE WATER SAMPLES The following is a listing of the minimum detectable activities from the samples taken from Benton Harbor, St. Joseph, Lake Township, Bridgman, New Buffalo D. C. Cook Plant intakes and the lake north and south of the plant site. Isotope pC1/ml I-I31 < 1.17 X 10-7 Cs-137 < 1.62 X 10-7 Cs-134 < 1.44 X 10-7 Co-60 < 1.S4 X 10-7 Co-58 < 1.11 X 10-7 ~ Cr-51 < 1.11 X 10-7 e Mn-54 < 9.56 X.10- 8 d Zn-65 < 3.41 X 10-7 For Quarterly Ccmposites Sr-89 < 3.80 X 10-6 Sr-90 < 3.40 X 10-8 H3 < 3.30 X 10-8 y )S13 \\SS l 4 ? d 9 1 A-8

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