ML17346A934

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Radioactive Effluent Release Data,Jul-Dec 1983.
ML17346A934
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 12/31/1983
From:
FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17346A933 List:
References
NUDOCS 8504090459
Download: ML17346A934 (33)
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Text

RADIOACTIVEEFFLUENT RELEASE DATA 3ULY 19S3 THROUGH DECEMBER 1983 SUBMITTED BY NUCLEAR CHEMISTRY DEPARTMENT TURKEY POINT PLANT FLORIDA POWER Bc LIGHT COMPANY 8g030i 850g01045~yq 05000260 PDR AQOCV pDR

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~~ II SEMIANNUALREPORT OF RADIOACTIVEEFFLUENT RELEASE PTP UNITS 3 8c 0 7 83 12 83 I'ntroduction All liquid and airborne discharges to the environment during this reporting period were analyzed in accordance with Technical Specification requirements. The minimum frequency of analysis as required by Safety Guide 21 was met or exceeded.

Aliquots of representative pre-release samples were either isotopically analyzed for gamma emitting isotopes on a multichannel analyzer, or evaporated and analyzed for gross beta-gamma activity in a 2< gas flow proportional counter. The efficiency of the gas flow proportional counter is adjusted so that the activity determined by gross beta-gamma analysis approximates the isotopic activities determined by gamma spectrum analysis and selected beta determinations, exclusive of tritium and dissolved gases.

The above procedure was followed for all releases from the waste disposal system and for secondary system'batch releases. Frequent periodic sampling and analysis were used to conservatively estimate the quantity of radioactivity released via the steam generator blowdown system.

The following comments will aid in the interpretation. and evaluation of the liquid release data presented in Table I, pages 1 through 7.

1. The reported values in Table I, page 1, include in their computation the quantity of radioactivity released from both the waste disposal system and the secondary . system. The secondary . system releases occurred when contaminated water was blown down from the steam generators during primary to secondary leakage conditions, or when the generators were drained for repair or refueling. Activity that entered the plant storm drain system was also included in the secondary system activity released and in the total activity released.

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07/83 - 12/83 i ~

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The reported values in Table I, pages 2 and 3 are the total quantities of radioactivity for individual nuclides released from the waste disposal system and the secondary system together. The values in Table I, pages 0 and 5 are for the waste disposal system only and page 6 is for the secondary system only.

3. During primary to secondary leakage, release of several short-lived nuclides from the secondary system occurs. These short-lived nuclides are not generally detected in batch released from the waste disposal system due to the long holdup time of processed water. Only those isotopes that were detected in the secondary system releases were reported. All non-detectable isotopes are listed as (-).

V/eekly and monthly composite samples for the waste disposal system were prepared to give proportional weight to each liquid release made during the designated period of accumulation. The composites were analyzed for gamma.

emmitting isotopes on a multichannel analyzer attached to a high resolution Ge(Li) detector, and for Sr-89 and Sr-90, using a chemical separation and subsequent beta determination with a 2m gas flow proportional counter.

Tritium was determined by use of liquid scintillation techniques and gross alpha radioactivity was detertnined by use of a 2m gas flow proportional counter. All concentrations for radioactivity determined from analysis of a composite were multiplied by the total represented volume of the liquid waste released to determine the total quantity of each isotope and of gross alpha activity released during the compositing period.

5. At least one representative batch of liquid effluent from the waste disposal system was analyzed monthly for dissolved fission and.activation gases by use of gamma spectrum analysis. The resulting isotope .concentrations were multiplied by the total volume released for the month in order to estimate the C

07/83 - l2/83 total dissolved gases released. If more than orts batch of effluent was analyzed, the concentrations were weighted in an appropriate manner. The results are totaled on a monthly basis in Table I, page 7. Dissolved gases, if any, from secondary system releases were determined from the samples of the individual releases. Isotopic concentrations were multiplied by the volume released to determine the quantity of radiogas nuclides released.

6. Representative samples of secondary system batch releases were analyzed individually for gamma emitting 'sotopes. Analysis of a representative composite for tritium was made for releases which occurred due to primary to secondary leakage.
7. The applicable limit for release of radioactive material in liquid waste is five curies per quarter excluding tritium and dissolved gases.

Airborne Releases Airborne releases to the atmosphere occurred from: release of gas decay tanks, the instrument bleedline, containment purges, and the secondary system during conditions of primary to secondary leakage. The techniques employed in determining the radioactivity in airborne releases are:

a) Gamma spectrum analysis for fission and activation gases, b) Removal of particulate material by filtration and subsequent gamma-spectrum analysis, Sr-89-90 determination, gross alpha analysis, and gross beta-gamma analysis, c) Absorption of halogen radionuclides on a charcoal filter and subsequent 1

gamma-spectrum analysis, and d) Condensation of water vapor in a gas sample followed by analysis for tritium using liquid scintillation techniques.

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07/83 - 12/83 All sporadic gas t'eleases from the plant which were not Ietounted for by the above methods were conservatively estimated as curies of Xe-133 equivalent by use of the plant vent process monitor recorder chart and the current calibration curve for the monitor.

The maximum rated capacity for the hogging jets and the maximum measured flow rate for the condenser air ejectors, and an estimate of the rate of exhaust from the atmoshperic dumps were used to conservatively estimate the airborne releases from the secondary system whenever applicable.

The following comments will aid in the interpretation and evaluation of the airborne release data presented in Table IL

1. Calculation of total radioactivity of noble gases, I-131, and particulates is based upon detectable radionuclides only.
2. The applicable limit for release of total radioactive materials in gaseous waste is 0.012 Ci/sec when averaged over the calendar quarter. The percent of the applicable limit for total gaseous release was computed as follows:

% L'aste off Limit =

Total curies released in gaseous durin uarter x 100

(.012 Ci/sec) (Seconds in quarter)

3. The applicable limit for the release of I-131 and particulate radionuclides with half-lives greater than eight days in airborne waste is:

E Qi (.10,000 m~, where Qi = release rate of it" nuclide, Ci/sec MPC; . sec and MPC; = maximum permissible concentration of the ith nuclide, Ci/m The release rate, Ql, was determined by dividing the total activity released in Ci, for the ith nuclide (ty,) 8d), during the calendar quarter by the seconds in the quarter.

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07/83 - 12/83

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MPC; values were obtained from 10CFR20, Appendix 8, Table II, Column l.

The MPC chosen was the most conservative value of either the soluble or insoluble MPC for each isotope.

The percent

% of Limit =

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of applicable limit was determined M Ci x 10096 as follows:

10,000 m3 / sec O'he maximum gaseous release rate for each month is listed in Table 11, page 1, under Section A, Line 3. The applicable limit for maximum allowable release rate is 6.7 6+00 p C%iec, average over one hour.

5. All values reported in Table II, pages 2 and 3, include the particulate, gaseous, and halogen activity released from the containments during purging, auxiliary building (leakage from pumps, valves, etc), the gas waste disposal system and the secondary system when applicable. If a minimum detectable activity value was not calculated for an isotope, it will be listed as ( ).

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NUCLEAR CHEMISTRY PROCEDURE NC-3 APPENDIX II PREPARAI'ION OF THE MONTIILY "PIIELI>:INAI<Y REPORT ON INDIOACTIVE RELEASES" AND THE

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PAGE 1 YEAR 1983 "RADIOACTIVE EFFLUENT RELEASES" PORTION OF THE SEMIANNUAL OPERATING REPORT

~ TABLE I Report of Radioac~tve E flueots: Liquid A. Gross Radioactivit 8-. 8 Jul Au Se tember October November December.

1.06 E+01 1.07 E+01 8.95 E+00 6.10 E+01 7.79 EW1 2.54 E+01

1. Total Release mCi Ci/ml 3.25 E-10: 2.01 E-10 1.85 E-10 1.20 E-09 1.63 E-09 6.55 E-lp
2. Av Concentration Durin Releases Concentration for Month Ci/ml 3.'20 E-ll 4.37 E-ll 3.27 E-11 3.10 E-10 5.09 E-10 1.32 E-lp
3. Av

/ml 270E10 169E09 530E10 150EP8 270E08 I 940EO

4. Hax Concentration. Released
5. Percent of Technical Specification 6.05 E-pl 3.29 E&0 Limit for Total Activit Released Tritium
1. Total Release Ci 6.90 E+01 1.36 E+02 6.08 E+01 4.06 E+Ol 4.90 E+Ol 3.98 E+0:
2. Av Concentration Durin Releases Ci/ml 2.10 E-06'.55 E-06 1.30 E-06 8.10 E-07 1.30 E-06 1.03 E-Ol Concentration for Month .

Ci/ml Z.07 E-07 5.55 E-07 2.20 E-07 2.10 E-07 3.20 E-07 2.07 E-O

3. Av C. Disso ve No e Gas 2.00 EWO 1.69 E+02 1.56 E+02 7.07 E+02 2.33 E+Ol 8.38 E+0
1. Total Release mCi Ci/ml 6.10 E-ll 3.17 E-09 3.20 E-'09 1.40 E-08 4.86 E-10 2.16 E-0
2. Av Concentration Durin Releases 6.00 E-12 6.90 E-10 5.70 E-10 3.60 E-09 1.52 E-lp ~

4.36 E-1

3. Av Concentration for Month D.'ross Al ha Radioactivity
1. Total Release mCi'1.28 E-02 <i.99 E-02) (<2.40 E-02) (<4.17 E-02) (<1.80 E-02) i(<9 E-0
2. AV COnCentratiOn Durin ReleaSeS Ci/ml (<3.90 E-13 (<3.73 E-13) (<5.00 E-13 (<8.30 E-13 (<3.77 E-13) 7<2.39 E-1
3. Av Concentrati on for Month ijCi/ml (<3.84 E-14 (<8.12 E-14) (<8.80 E-14 (<2.10 E-13 (<1.17 E-13) (<4.84 E-1 E. Volumes
1. Vol of Li uid Waste to Dischar e Liters 3.85 E+07 3.80 E+07 '.49 E+07'.16 E+07 1.17 E+07 1.72 E+C Liters 3.28 E+10 5.33 E+10 4.83 E+10 5.03 E+10. 4.77 E+10 3.88 E+1
2. Vol of Dilution Water Durin Rel.

3.33 E+ll 2.45 E+ll 2.74 E+ll 1.95 E+ll 1.53 E+ll 1.92 E+1

3. Vol of Dilution Water for Month. Liters NOTE: Numbers in parentheses represent maximum sensitivity. in pCi/ml.

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NUCLEAR CHEMISTRY PROCEDURE NC-3 APPENDIX II

PREPARATION OF THE MONTHLY "PRELIMINARY RfPORT ON RADIOACTIVE RELEASfS" AND THE - PAgE 2 YEAR .1983 "RADIOACTIVE EFFLUfNT RfLEASES" PORTION OF THE SEMIANNUAL OPERATING REPORT TABLE I Report of Radioactive'uents: Liquid - Total Isoto e Unst Au ust Se tember October ovem er Dece er Ag-llpm mCi (<4.3 E-08) 3.93 E-02 (< 2. 7 E-08) 5.58 E-01 5.69 E-01 4.34 E-01 Ba-140 mCi '(< l. 4 E-p7) (<2.5 E-07) (<2.4 E-07) (<6.7 E-07) (< 7.2 .E-07) (<7. 7 E-07)

Br-82 mCi 3.46 E-01 (<5.2 E-07) (<2.0 E-06) (<9.0 E-06) (<2. 8 E-06) (<2.P E-06)

Co-58 mCi 7.76 E-02 2.83 EWO 2.38 E-01 2.15 E+Ol 2:51 E+Ol 1.05 E+Ol Co-60 9.24 E-01 2.37 EWO 1.77 E+00 1.43 E+Ol 9.87 E+00 5.04 E+Op i Cr-51 mCi (<2.0 E-07) .3.51 E-pl (<2.5 E-07) 2.95 1.29 EW1 E+Op 4.44 EWO Cs-134 1.20 E-01 3.98 E-01 2.25 E-pl 3.67 E+00 4.22 E+00 7.34 E-01 Cs-136 . mCi (<5.7 E-08) (<8.4 E-08) (<9.3 E-08) 3.72 E-02 3.14 E-01 (<1.8 E-07)

Cs-137 mCi 2.14 E-01 6.87 E-01 7.82 E-01 6.67 E+00 6.77 E+00 1.81 EMO F-18 2.11 E-pl 2.13 E-01'<

5.94 E-02 1.36 E-01 9.86 E-02 Fe-59 mCi (<6.9 E-08) l. 1 E-07) ( <6. 3 E-08) (<2.9 E-07) 3.23 E-01 8.72 E-02 I-131 mCi 5.15 E&0 1.70 E+00 4.56 E+00 8.51 E+00 1.04 E+Ol 3 19 -01 I-132 mCi 2.59 E-01 I-133 mCi 3.61 E+00 4.78 E-01 1.26 E+00 6.0'4 E-01 <1 6 E-La-140 mCi ( <2.2 E-08) (<4.3 E-08) (<4.1 E-08) 9'.29 E-02 2.67 E-01 <5.4 E-08 Mn-54 mCi ( <3.4 E-08) 3.91 E-02 (<2.4 E-08 1.53 E-02 3.48 E-01 1 76E-Mo-99/Tc-99m (<1.4 E-07) 1.98 E-01 <2.2 E-06 6.18 E-01 Nb-95 ( <3.5 E-08) ((4.9 E-08) 2.22 E-01 7.54 E-01 5.70 E-01 NOTE: Numbers in parentheses represent maximum sensitivity in pCi/m1 ~

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NUCLEAR CHfNISTRY PROCEDURE NC-3 APPENDIX II PREPARATION OF THf HONTHLY "PRELININARY REPORT ON RADIOACTIVE RELEASfS" AND THE PAGE 3 YEAR 1983. "RADIOACTIVE EFFLUENT RELEASES" PORTION OF THE SEMIANNUAL OPERATING REPORT TABLf I Repovt of Radioactive RER ueots: Liquid - Total Isoto e Un> t u y August Septe er cto er ove er December Ru-103 mCi (< 2.9 E-08) (<5.1 E-08) (<3.2 E-08) 3.32 E-01 3.38 E-01 1.39 E-01 Sb-124 - mCi (<4.7 E-08) (<5.9 E-08) (<4 7 E-08) 8.38 E-02 5.61 E-01 3.39 E-01 Sb-125 (<8.0 E-08) ( 1- 3 E-07) (<8. 1 E-08) 1.01 E-01 3.27 E-01 2.58 E-01 Sr-89 mCi (<7.6 E-09) 1.35 E+00 1.90 E-02 2.53 E-01 3;64 E-01 1.45 E-0 Sr-90 mCi (<5.12 E-09) (<1.02 E-08) 3.20 E-02 (<4.61 E-08) (<4.8 E-09) (<4.99 E-08)

Zr-95 - mCi (<6.0 E-08) (< 7. 8 E-08) ( <4. 5 E-08) 8.67 E-02 4.59 E-01 2.79 E-01 Total mCi 1.06 E+01 1.07 E+01 8.95 E+00 6.10 E+Ol 7.79 E+01 2.54 E+Ol NOTE: Numbers in parentheses represent maximum sensitivity in uCi/ml.

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NUCLEAR CHEMISTRY PROCEDURE NC-3 APPENDIX I I PREPARATION OF THE MONTHLY "PRELIMINARY REPORT ON RADIOACTIVE RELEASES" AND THE PAGE.Z .

YEAR 1983 -"RADIOACTIVE EFFLUENT RELEASES" PORTION OF THE SEMIANNUAL OPERATING REPORT TABLE I Report of Radioactive Effluents: Liquid - waste Disposal system Isoto e Un> t Au ust Se tember October November December Ag-110m mCi <4.3 E-08 3.93 E-02 <2.7 E-08 .4.34 E-01 Ba-140 . mCi (< 1.4 E-07) (< 2.5 E-07) (< 2.4 E-07) (< 6. 7 E-07) ( <7. 2 E-07 <7.7 E-07 Co-58 mCi "7.76 E-02 1.36 E+00 2.28 E-01 2.13 E+Ol 2.45 E+Ol 9. 1 +00 Co-60 mCi 7.18 E-01 2.31 EWO 5.84 E-01 1.43 EW1 9.40 E&0 4.99 E+00 Cr-51 (< 2.0 E-07) 3.51 E-01 (< 2.5 E-07) 2.95 EWO 1.29 E+01 4.44 E+00 Cs-134 1.20 E-01 3.98 E-01 1.52 E-01 3.67 E+00 4.22 E+00 7 34 E-O Cs-136 mCi (< 5. 7 E-08) (< 8. 4 E-08) (<9. 3 E-08 3.72 E-02 3.14 E-01 Cs-137 mCi 2.09 E-01 6.50 E-01 2.67 E-01 6.41 EWO 6.77 E+00 4 E Pe-59 mCi (< 6.9 E-08) (< 1. 1 E-07) (< 6. 3 E-08) (< 2.9 E-07) 3.23 E-ol 8.72 E-02 I-131 mCi 4.57 E-02'.60 E-01 1.74 EWO 5.07 EWO 1.03 EWl 3.11 E-01 La-140 mCi (< 2. 2 E-08) (< 4. 3 E-08) (< 4. 1 E-'08 9.29 E-02 2.67 E-01 Mn-54 mCi <3.4 E-08 <5.2 E-08 <2.4 E-08 153 E- 2 Mo-99/Tc-99m mCi (< 1. 4 E-07) 1.98 E-01 (<2.2 E-06) 6.18 E-01 4.05 EWO < 1.8 E-06 Nb-95 ,

mCi (<3.5 E-08) (< 4.9 E-08) <3.00 E-08) 2.22 E-01 7.54 E-01 Ru-103 mCi (< 2.9 E-08 <5.1 E-08 " <3.2 E-08 3 32 E-O sb-124 mCi (<4.7 E-08) (<5.9 E-08 (< 4. 7 E-08 8.38 E-02 5.61 E-01 3.39 E-01 Sb-125 ,

mCi (< 8.0 E-08) -

(< 1. 3 E-07 (<8. 1 E-08 1.01 E-01 3.27 E-01 Sr-89 mCi (<6.65 E-09 '.35 E+00 1.90 E-02 2 3 1.45 E-01 NOTE: Numbers in parentheses represent. maximum sensitivity in pCi/ml.

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NUCLEAR CHEMISTRY PROCEDURE NC-3

.PPENDIX II PREPARATION OF. TIlE MONTHLY "PRELIMINARY REPORT ON RADIOACTIVE RELEASES" AND THE PAGE 5

EAR 1983 "RADIOACTIVE EFFLUENT RELEASES" PORTION OF THE SEMIANNUAL OPERATING REPORT TABLE I Report of Radioactive Effluents: Liquid - Waste Disposal System Isoto e Un t Ju y Au ust Se tember D Sr-90 (<4.79 E-09) (<4.20 E-09) 3.20 E-02 (<4.61 E-08 <4.8 E-09 Zr-95 (<6.0 E-08) (<7.8 E-08) (<4.5 E-08) 8.67 E-02 4.59 E-01 2.79 E-01 Total mC3. 1.17 E+00 7.31 E+00 3.02 E+00 '.60 E+01 7.68 E+01 2.43 E&l NOTE; Numbers in 'parentheses represent maximum sensitivity in pCi/ml.

NUCLEAR CHEHISTRY PROCEDURE NC-3 APPENDIX II PREPARATION OF THE MONTHLY "PRELIMINARY REPORT ON RADIOACTIVE RELEASES" AND THE EAR 1983 "RADIOACTIVE EFFLUENT RELEASES" PORTION OF THE SEHIANNUAL OPERATING REPORT PAGE 6 TABLE I

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'eport of Radioactive Effluents: Liquid - Secondary system Isoto e Un> t. Jul Au ust Se tember October November Decem er Br-82 mCi 3.46 E-01 Co-58 mCi 1.47 E+00 9.89 E-03 1.88 E-01 5.72 E-01 5.47 E-ol j

Co-60 mCi 2.06 E-01 5.83 E-02 1.19 EWO 7.54 E-03 4.73 E-01 4.56 E-02 Cs-134 mCi 7.34 E-02 Cs-137 mCi. 5.18 3.74 E-02 5.15 E-01 2.56 E-01 3.71 E-01 E-03'.11 i

F-18 mCi E-Ol 2.13 E-01 5.94 E-02 1.36 E-01 9.66 E-02 I-131 mCi 5.10 EWO 1.04 EWO 2.82 E+00 3.44 E+00 1.46 E-01 8.35 E-03 I-132 mCi 2.59 E-01 I-133 mCi. 3.61 E+00 4.78 E-01 1.26 E+00 6.04 E-01 Mn-54 mCi 3..91 E-02 Total mCi'.48 E+00 3.34 E+00 5.93 'E+00 4.89 E+00 1.19 E+00 1.07 E+00 NOTE: Numbers in parentheses represent maximum sensitivity in ~Ci/ml.

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NUCLEAR. CHEMISTRY PROCEDURE NC-3 ~ '

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)PPENDIX II PREPAINTION OF TIIE MONTIILY "PRELININARY REI'ORT ON RADIOACTIVE RELEASES" AND TIIE "PAGE 7

<EAR 1983 "RADIOACTIVE EFFLUENT RELEASES" PORTION OF TIIE SEHIANNUAL OPERATING REPORT

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TABLE I Report of Radioactive Effluents: Liquid - Dissolved Gas Tota Jul Au usr September October November December Kr-85 mCi (<4.58 E-06) ((1.56 E-05) ..(<1.13 E-05) (<4.32 E-05) (<1.28 E-05) (<5.09 E-05)

Xe-131m mCi 9.52 E-Ol (<2.23 E-'06) 4.48 EWO 1.18 E+Ol (<1.98 E-06) (<4'.ll E-06)

Xe-133 3.52 E-01 1.62 E+02 1.50 EW2 6.88 E+02 2.23 E+01 8.01 E+Ol 2.86 E+00 9.42 E-01 7.47 E+00 (<4.18 E-07) 2'. 89 Xe-133m 4.33 E-01 XB-135 mCi 2.64 E-01 3.65 E+00 2.07 E-01 ((1.49 E-07) 1.01 EWO 7.93 E-01 Haste Dis osa S stem Kr -85 mCi ((4.58 E-06) (<1.56 E-05) (<1.13 E-05) (<4.32 E-05) (<1.28 E-05) (<5.09 E-05)

Xe-131m mCi 9.52 E-Ol ((2.23 E-06) 4.48 E&0 1.18 EWl (<1.98 E-06) (<4.11 E-06) 3.52 E-ol 1.62 E+02 1.50 E+02 6.88 E+02 2.23 E+Ol 8.01 E+Ol Xe-133 mCi 4.33 E-01 2.86 E+00 9.42 E-01 7.47 E+00 (<4.18 E-07) -2.89 E+00 Xe-133m mCi Xe-135 mCi 2.64 E-01 3.65 E+00 2.07 E-01 (<1.49 E-07) 1.01 E+00 7.93 E-ol Secon ar S stem Kr-85 mCi Xe-131m Xe-133 mCi Xe-133m mCi Xe-135 mCi s

NOTE Numbers in parentheses represent maximum sensitivity in pCi/ml.

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NUCLEAR CIIEMISTRY PROCEDURE NC-3 APPENDIX III PREPARATION OF TIIE MONTHLY "PRELIMINARY REPORT ON RADIOACTIVE RELEASES" AND THE PAGE' YEAR 1983 "RADIOACTIVE EFFLUENT RELEASLS" PORTION OF THE SEMIANNUAL OPERATING REPORT TABLE I I Report of Radioactiive t 1oents: Airborne

. Fsssson an ctsvat>on. Gases Se tember October November December

1. Total Release 2.45 E+03 3.59 E+03 1.74 EW3 1.98 E+03 1.07 EW3 2.50 EW3
2. Av Release Rate for period Ci/sec 8.12 E+02 1.48 E+03 7.19 E+02 6.56 E+02 4.42 EW2 )1.03 E+03
  • 3. Max Release Rate for Period Ci/sec 3.98 E+04 3.63 E+04 9.69 E+03 1.39 E+04 2.99 EW4 i4.52 E+03
  • maximum air orne re ease rate average over one our or eac mont . Tec n ca Spec> ]cat ons 1m>t s 6./ EK4 pC sec averaged over one hour.

B. Io ne - 131

1. Total Iodine -.131 Ci 7.26 E-03 3.65 E-02 1.93 E-03 4.91 E-02 1.11 E-02 5.66 E-04
2. Av Release Rate for period Ci/sec 2.40 E-03 1.51 E-02 7.98 E-04 1.63 E-02 4.59 E-03 2.34 E-04 C. Particulates
1. Particulates with t 1/ >8 days 8.98 E-05 6.84 E-04 2.48 E-05 6.17 E-04 2.09 E-04 2.69 E-04
2. Av Release Rate for Period Ci/sec 2.83 E-04 1.02 E-05 2.04 E-04 8.64 E-05 1.11 E-04
3. Gross Al ha Radioactivit Ci 3.19 E-OS 5.02 E-OS 2.25 E-08 4.37 E-07 1.24 E-07 1.17 E-07 D. Tr tium

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1. Total Release Ci 7.77 E-02 1.24 E-01 2.37 E-02 7.66 E-02 3.54 E-02 3.63 E-02 i
2. Av Release .Rate for Period Ci/sec 2.57 E 5.12 E-02 9.79 E-03 2.54 E-02 1.46 E-02 1.50 E-02 E. Percent o A >ca e sm>t
1. Fission and Activation Gases 8.25 E+00 5. 88'+00
2. I-131 and Part tl/2>8d 5.82 E-01 7.76 E-Ol NOTE: Num ers n parent eses represent max>mum sens t v ty n pC> m .

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NUCLEAR CHEMISTR

Y. PROCEDURE

NC-3 ~ ~

APPENDIX III PREPARATION OF THE MONTHLY "PRELIMINARY REPORT ON RADIOACTIVE RELEASES" AND THE YEAR 1983 "RADIOACTIVE EFFLUENT RELEASES" PORTION OF THE SEMIANNUAL OPERATING REPORT PAGE .2 TABLE II Airborne Releases - Particulates Isoto e -Un> t July Au ust Se tember October November December Sa-140 Ci" (<1. 4 E-13) 3.33 E-05 (<8.6 E-14) 2.38 E-05 (<7.3 E-14) (<8.9 E-14)

Co-58 Ci (<3. 2 E-14) 1.64 E-04 1.62 E-06 7.83 E-05 6.48 E-05 4.6b E-05 1

Co-60 Ci 1.10 E-05 6.68 E-05 8.61 E-06 2.22 E-05 3.12 E-05 3.27 E-05 Cr-51 (<2.1 E-13) 1.77 E-05 (<1.1 E-13) (<4.4 E-13) 7,70 E-06 3.52 E-Cs-134 Ci 1.01 E-05 6.55 E-05 3.94 E-06 9.69 E-05 1.86 E-05 3.93 E-05 Cs-136 Ci 5.91 E-06 2.88 E-05 (<5.0 E-14) 3.05 E-05 4.50 E-06 (<2. 6 E-14)

Cs-137 Ci 2.13 E.-05 1.15 E-04 6.24 E-06 1.43 E-04 3.67 E-05 9.29 E-05 Ci 4.09 E-05 1.74 E-04 3.82 E-06 1.93 E-04 4.03 E-05 1'.37 E-06 I-131 La-140 Ci (<4. 1 1.69 E-05 (<4.1 E-14) 1.59 E-05 (<5.2 E-14), (<3.3 E-14)

E-14)'.45 Mn-54 Ci E-07 1.51 E-06 (<2.3 E-14) (<6.6 E-14) (<4.0 E-14) 1 34 E-06 Nb-95 Ci (<2.4 E-14) (<6.6 E-14) (<2.2 E-14) (<5.3 E-14) 1.40 E-06 1.12 E-05

(<3.1 E-14) (<7.0 E-14) (<2.0 E-14) 1.85 E-06 1.67 E-06 (<2.0 E-Ru-103 Ci 2.45 E-07 2.45 E-07 5.98 E-07 1.15 E-05 1.94 E-06 2.4 E-06 Sr-89 Sr-90 Ci 6.44 E-08 6.44 E-08 (<6.0 E-16) (<5.17 E-16) (<5.71 E-16) , (<6.2 E-16)

Zr C j (<4. 9 E-14) (<1.1 E-13) .(<3.5 E-14) (<8.9 E-14) (<7.1 E-14) 5.28 E-06 Total .Ci 8.98 E-05 '6. 84 E-04 2.48 E-05 6.17 E-04 2.09 E-04 2.69 E-04 NOTE: Numbers in parentheses represent maximum sensitivity in yCi/ml.

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NUCLEAR CHEMISTRY PROCEDURE NC-3 APPENDIX III PREPARATION OF TIIE MONTHLY "PRELIMINARY REPORT ON RADIOACTIVE RELEASES" AND TIIE PAGE '3 YEAR 1983 "RADIOACTIVE EFFLUENT RELEASES" PORTION Of THE SEMIANNUAL OPERATING REPORT TABLE I I Airborne iiee eases - Gaseous Fission and Actsvatton Gases t July August September October November Isoto e Un>

7.38 EWO 2.34 E-01 2.63 E-Ol 5.64 E&0 3.78 E-01 1;90 E-01 Ar-41 Ci Kr-85 . 6.08 E+00 3.45 E&0 3.09 E+00 1.31 E+01 3.94 E+00 . 6;58 E+00 Kr-85m Ci 1.32 E+00 1.14 E+00 2.99 E-01 2.59 E-01 E+03'ecember 3.85 E-ol 3.38 E- 2 Kr-87 Ci 2.00 E-02 3.97 E-02 1.45 E-02 2.93 E-03 6.46 E-02 9.10 E- 5 Ci 1.81 E+00 1.77 E+00 2.40 E-ol 2.39 E-ol 3.07 E-01 7.51 E-03 K0-88 ~

5.27 E+00 3.79 E+00 3.31 E+00 9.67 E+00 2.44 E+00 1.45 E+00 Xe-131m. Ci C

2.39 E+03 3.55 E+03 1.72 E+03 1.94 E+03 1.05 2.49 EW3 Xe-133 Ci Xe-133m Ci 1.71 E+01 1.01 E+Ol 4. 02'+00 8.27 E+00 4.43 E+00 1.00 E+00 Xe-135 .Ci 2.42 E+Ol 2.12 E+Ol 5.41 E+00 '.40 E+00 7.37 E+00 .8.77 E-01 Xe-135m Ci (<3.7 E-04) 2.71 E-02 (<8.8 E-05) (<2.03 E-04) (<1.71 E-06) (<2.67 E-04)

Xe-138 Ci (<1.2 E-03) (<2. 2 E-03) (<1. 8 E-04) (<6.89 E-04) (<6.19 E-06) (<6.63 E 4)

Total Ci 2.45 E+03 3.59 E+03 1.74 E+03 1.98 E+03 1.07 E+03 2. 50,K+03 Halo ens Gaseous Isoto e Un) t July August September October November December I-131 7.22 E-03 3.63 E-02 1.93 E-03 4.89 E-02 1.11 E-02 5.65 E-04 I-133 Ci 2.03 E-02 8.13 E-03 7.36 E-04 6.91 E-03 1.20 E-03 1.01 E-04 I-135 .Ci 3.40 Z-03 (< 3. 3 E-13) (< 2. 4 E-13) (< 2. 1 E-13) '<2. 5 E-13) (< 6. 8 E-13)

Br-82 Ci 5.90 E-04 7.06 'E-05 1.53 E-05 (<2.4 E-13) 2.09 E-04 3.02 E-05 Total 3.15 E-02 4.45 E-02 2.68 E-03 5a58 E-02 1.25 E"02 6.96 E-04 ote: um ers n paren eses represen max>mum sens >v y sn p > m .

t C

Plant Turkey Point Radioactive Waste Repor~

July 1, 1983 Thru December 31, 1983 DATE OF SHIPMENT CVRZES CUBIC FEET DISPOSITION (Shipped to:)

07-11-83 .891 170 Barnwell, S.C.

07-14-83 ~ 1418 170 Barnwell, S.C.

07-18-83 ~ 52071 170 Barnwell, S.C.

07-20-83 059643 1050 Hanford, WA.

08-12-83 82 '37 84 Barnwell, S.C.

08-24-83 .06223 1050 Barnwell, S.C.

08-29-83 73 '37. 84 Barnwell, S.C.

09-13-83 .59995 1050 Hanford, WA.

09-14-83 10.218 84 Barnwell, S.C.

09-19-83 1.0166 170 Barnwell, S.C.

09-22-83 4 '281 170 Barnwell, S.C.

09-29-83 79.050 84 Barnwell, S.C.

10-04-83 ~ 832473 1050 Hanford, WA.

10-14-83 ~ 115483 1050 Hanford, WA.

10-18-83 67.425 84 Barnwell, S.C.

10-25-83 ~ 1311295 1050 Hanford, WA.

11-01-83 037605 1050 Hanford, WA.

11-04-83 121483 1050 Hanf ord, WA.

11-07-83 1. 171 170 Barnwell, S.C.

11-21-83 028892 840 Barnwell, S.C.

11-10-83 2.421 170 Barnwell, S.C.

11-17-83 ~ 131406 1050 Hanford, WA.

11-18-83 ~ 132345 1050 Hanford, WA.

11-28-83 .112847 1050 Hanford, WA.

11-29-83 .160855 1050 Hanford, WA.

12-09-83 86.025 84 Barnwell, S.C.

12-12-83 1.024 170 Barnwell, S.C.

12-13-83 .11251 1050 Hanford, WA.

12-15-83 1.252 170 Barnwell, S.C.

12-19-83 2.314 170 Barnwell, S.C.

30 Shipments 416.71106 Curies 16694 Cubic Feet On-Site as of Jan. 1, 1984: .212.36000 Curies 3564 Cubic Feet

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