ML17340A818

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Radioactive Effluent Release Data,Jul-Dec 1980.
ML17340A818
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 02/21/1981
From:
FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17340A817 List:
References
NUDOCS 8103110714
Download: ML17340A818 (15)
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Text

RADIOACTIVE EFFLUENT RELEASE DATA DJLY 198/ THROUGH DECEMBER 1980 vSUBMXTTED BY NUCLEAR CHEMISTRY DEPARRIENT TURKEY POINT PLANT FLORIDA POWER 8 LIGHT COMPANY FEBRUARY 12, 1981

SEMIANNUAL REPORT OP RAD TIVE EFFLUENT RELEASES, PTP U 3 6 4, 7/80 - 12/80 Introduction All liquid and airborne discharges to .the environment during this reporting period were analyzed in accordance with Technical Specification xequirements. The minimum frequency of analysis as required by Safety Guide 21 was met or exceeded.

Li id Releases Aliquots- of representative pre-release samples were either isotopically anal-yzed for gamma emitting isotopes on a multichannel analyzer, or evaporated" and anal-yzed for gross beta-gamma activity in a 2m gas flow proportional counter. The effici-ency of the gas flow proportional counter is a'djusted 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 fxom the waste disposal system and for secondary system batch releases. Prequ'ent periodic sampling and analysis were used to conservatively estimate the quantity of radioactivity xeleased 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 6:

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.

2. The reported values in Table I, pages 2 and 3 are the total quantities of radio-achivity for individual nuclides released from the waste disposal system and the secondary system togethex. The values in Table I, page 4 are for the waste dis-posal system only and page 5 is for the secondaxy 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 releases 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 ( ).

4. Weekly and monthly composite samples for the waste disposal system were prepared to give proportional weight to each liquid release made during the designated period ofaccumulation. The composites were analyzed for gamma emitting 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 determina-tion with, a 2m gas,flow .proportional counter. Txitium was determined by use of liquid scintillation techniques and gross alpha radioactivity was determined 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 sys-tern was analyzed monthly for dissolved fission and activation gases by use of gamma spectrum analysis. The resulting isotope concentxations were multiplied by the total volume released for the month in order to estimate the total dis-solved gases released. Xf more than one batch of effluent was analyzed, the con-centrations were weighted in an appropriate manner. The results axe totaled on a monthly basis in Table E, page 6. Dissolved gases, if any, fxom 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 wexe analyzed individ-ually for gamma emitting isotopes. Analysis of a representative composite for tritium, gross alpha and selected beta emitters was made for releases which occurred due to primary to secondary leakage.

7/80 12/80 7.. The applicable limit for release of radioactive material in liquid waste is five curies per quarter excluding tritium and dissolved gases.

Airborne Releases.

Airbozne zeleases to the atmosphere occurred from: release of gas decay tanks, the instrument bleedline, containment purges, and the secondary system during con-ditions 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 gamma-spectrum analysis, and d) Condensation of water vapor in a gas sample followed by analysis for tri-tium using liquid scintillation techniques.

All sporadic gas releases from the plant which were not accounted 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 atmospheric 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 II.

1. Calculation of total radioactivity of noble gases, I-131, and particulates is =

based upon detectable radionuclides only.

'. The applicable limit for release of total radioactive materials in 7/80 12/80 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:

Total curies released in gaseous waste durin arter 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:

'ec'

"< 10,000 m'

, where Q. ~

i i release rate of .th nuclide, Ci/sec MPC and MCPi ~ maximum permissible concentration of the ith nuclide, Ci/m3 The, release, rate, Q, <<was determined ."by<<dividing the total activity released i

in Ci, for the th nuclide (t~ > 8d), during the calendar quarter by the seconds in the quarter.

MPC. values were obtained from 10CFR20, Appendix B, Table ZZ, Column 1. The MPC chosen was the most conservative value of either the soluble or insoluble MPC for each isotope.

The percent of applicable limit was determined as. follows:

% of Limit =

E MPC.

i x 100%

3 10,000 m /sec

4. The maximum gaseous release rate for each month is listed in Table ZZ, page 1, under Section A, Line 3. The applicable limit for maximum allowable release rate is 6.7 E+04 gCi/sec, averaged over one hour.
5. All values reported in Table ZI, 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 during conditions of primary to secondary system leakage.

If a minimum detectable activity value was not calculated for, an isotope, it will be listed as ( )

1980 Table I Rcport of Radioactive Effluents'. Liquid Page 1 7,iquid Releases JULY AUGUST 'EPTEHBER OCTOBER NOVEMBER DECEMBER A. Gross Radioactivity ((7-y)

l. Total Release (mci) 1.67 E+01 . 3.37 E+01 9..09 E+00 236 +1 +02 1.90 E+01
2. Avg Concentration During Releases(uCi/ml) 6.1 E-ll 9.8 E-ll 4.2 E-ll l. 6 E-10 2. 0 E-09 1 3 E-10
3. Av Concentration for Month (uCi/ml) 6-1 '-Il 9-8 E-ll . 3.4
  • E<<ll l. 2 E-10 1.8 E-09 1.1 E-10

~i. llax Concentration Released - (uCi/ml) 5.5 E-10 3.4 E-10 4.6 E-10 3.1 E-09 1.5 E-.08 3.0 E"09

5. Percent of Technical Specification 1.2 E+00. 9.6 E+00 Limit for Total Activity Released (/)

B. Tritium

1. Total Release (Ci) 08 E+Ol 1.63 E+02 1.03 E+02 1.02 E+Ol
2. Avg Concentration During Releases(pGi/ml) 7 0 E-08 1.A E-07 1. 1 E-06 4.7 E-07 7.2 E-08
3. Avg Concentration for Month (ljCi/ml) .-07 7.0 E-08 142 E-07 8. 5 E-07 4.3 E-07 5.9 . E-08 C. Dissolved Noble Gas
1. Total Release . (mCi) 9.23 E+00 5.94 E+00 6;80 E+00 4.68 E+Ol 6.37 E+Ol 3.65 E+Ol
2. Avg Concentration During Releases(pCi/ml) 3.4 E-ll 1.7 E-ll 3. 1 E-11 3. 1 E-10 2.9 E-10 2.6. E-10
3. Avg Concentration for Month (pCi/ml) 3.4 E-ll 1.7 E-ll 2.6 E-11 2.4 E-lo 2.7 E-10 '.l E-10 D. Gross Alpha Radioactivity
1. Total Release (mCi) < .0 -09 <7 9 ~ E-09 <1. 0 E-08 '<1.0 E-08 <l. 2 E-08 <6. 5 E-09
2. hvg Concentration During Releases(pCi/ml) <3 3 E 20 <2 3 E 20 {<4. 6 E-20) (<6.7 E-20) (<5. 5 E-20) (<4. 6 E'-20)
3. A'vg Concentration for Month (pCi/ml) <3 3 E-20 <2.3 E-20) <3.8 E-20) (<52 E-20) (<5.0 E-20) (<3. 8 E-20) ~

E. Volumes

l. Vol of Liquid Haste to Discharge (Liters) 3.85 E+07 1.69 E+07 1.11 E+07 8.29 E+06 1.90 E+07 1.83 E+07 2.. Vol of Dilution Hater During Rcl (Liters) 2.74 E+ll 3.43 E+ll 2.18 E+ll 1.49 E+ll 2.19 1.41 E+ll E+ll'.38
3. Vol of Dilution Hater for Month (Liters) 2.74 E+ll 3.43 E+ll 2.65 E+ll 1.93 E+ll E+ll 1.72 E+ll I

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

1980 Table I Re'rt oZ Radioactive Eff1uents'. Li uid - Total Pa e 2 Isotope Unit JULY ~

AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Ba-140 mCi (<5.8 E-08) ~

(<6.7 E-08) (< 5. 9 E-08.} (<1.4 E-07) 4.29 E+00 ~

2.41 E-Ql Co-58 mCi 8.96 E-02 1.35 E-01 3.77 E-02 5.18 E+00 1.06 E+Ol 4.06 E+00 Co-60 mCi 9.78 E+00 2.10 8+00 1.46 E+00 9.25 E+00 9.62 E+00 4.59 E+00 Cr-51 mCi (<1. 3 E-07) (<1.5 E-07) (<1.1 E-07) 2.14 E+00 1.33 E+00 9.13 E-01 Cs-134 mCi 6.94 E-01 8.63 E-02 3.68 E-.02. 4.15 E-01 3.41 E+00 4.37 E-01 Cs-136 mCi (<1. 6 E-08) (<1. 7 E-08) (<1.8 (< 3. 6 E-08) 5.65 E-Ol (<1.8 E-08)

E-08)'.07 Cs-137 mCi 1.32 E+00 1.57 E-Ol E-02 1.08 E+00 4.97 E+00 6.89 E-ol Cs-138 mCi 4.00 E+Ol F-18 mCi 9.1 E-01 5.47 E+00 1.00 E+00 5.38 E-01 5.48 E+Ol I-131 mCi. 5.5'-01 5.14 E-Ol 6.86 E-01 1.23 E-Ol 3.61 E+Ol 6.42 E+00 I-132 mCi 5.6 E-01 6.66 E+00 7,45 E-01 5.08 E-01 4.29 E+Ol

.I-133 mCi 2.68 E+00 9.17 E+00 3.65 E+00 9.88 E-01 8.05 E+Ol I-134 mCi 1.81 E+00 2.34 E-01 6.07 E+01 I-135 mCi 7.30 E+00 1.34 E+00 1.17 E+00 .6.A6 E+Ol La-140 mCi (<6. 9 E-09) (<9. 1 E-09) (<9.1 E-09) (< l. 8 E-08) 8.$ 8 E-Ol (<9.1 E-09)

Mn-54 mCi 9.0 E-03 (<2.1 E-08). (<2.0 E-08) 3.41 E-ol 8.04 E-Ol 2.60 E-01

~ Mo-.99 mCi (<1.1 E-07) (<1.2 E"07) (<1.2 E-07) ~

(<2.4 E-07) 5.98 E-01 2.1 E-02 Na-24 mCi 3.3 E-02 2.68 E"01 1.03 E+Ol Nb-95 mCi (<1.6 E-08) (<1.8 E-08) (<1.6 E-08) 5.30 E-01 1.86 E-03: 6.5 E-02 Ru-103 mCi (<1.5 E-08) (<l. 7 E-08) (<1.5 E-08) 5.20 E-01 9.85 E-02 (<2.1 E-08)

DENOTE:

Sb-124 <<l. 4 E-08) (<2. 3 E-08) (<1.6 E"08) 7.99 E-02 (<2.7 E-08) (<2.5 E-08)

Sb-125 mCi (<4.9 E-08) (<5.6 E-08) (<4.9 E-08) 1.43 E-Ol (<6.4 E-08) (<5.8 E-08)

Sr-89 mCi 3.02 E-02 4. 0 E-02 2.6 E-02 7.45 E~02 9.00 E+00 1.31 E+00 Sr-90 mCi 1.29 E-02 1.6 E-02 2.7 E-02 7.66 E-02 1.65 E-01 3.28 E-02 Numbers in parentlieses represent maximum sensitivity in pCi/ml.

I

~ ~

1980 able Re ort of Radioactive Hffluents: Li uid <<Total Page 3 Isotope Unit JULY .AUGUST SEPTEMBER " OCTOBER NOVEMBER DECEMBER Zr-95 mCi (<2.8 E-08) (<3.2 E-08) (<2. 9 E-08) ~ 1.82 E"01 ~ 1.08 E-ol . (<4'.2 E-08)

Total mCi 1.67 E+Ol 3.37 E+01 9.09 E+00 2.36 8+01 4.37 E+02 l.;90 E+Ol NAVE. N>>mhnrs 4n narentbrses renresent maximum sensitivitv in uCi/ml.

1980 Table I Re ort oZ Radioactive Hffluents: Li uid - 'Haste'is osal S stem Pa e 4 Isotope Unit JULY ,AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Ba-140 mCi (<5.8 E-08) (<6. 7 E-OS) (<5. 9 E-08) ~ (<1.4 '-07) (<9-6 E-08) . (<7.6 E-08}

Co-58 mCi 8.96 E-02 ~ 1.35 E-Ol 3.77 E-02 4.88 E+00 4..51 E+00 3.28 E+00 Co-60 mCi 4.80 E-01 3.80 E-.01 3.95 E-01 8.03 E+00 5.15 E+00 2.28 E+00 Cr-51 mCi (<1. 3 E-07) (<l. 5 E-07) (<1.1 E-07) 2.14 E+00 1.33 E+00 9.13 E-01 Cs-134 mCi 6.37 E-02 8.63 E-02 3.68 E-.02 4.15 E-Ol 5-96 E-Ol 2-74 E-Ol Cs-136 , mCi. (<l. 6 E-08) (<1. 7 E-08) (<1.8 E-08) (<3.6 E-08) (<2. 1 E-08) (<1.8 E-,OS)

Cs-137 mCi 1.45 E-01 1.57 E-01 8.07 E-02 9.56 E-Ol 1.22 E+00. 4 45 E 0 I-131 mCi (<1.4 E-OS) (<1.8 . E-08) (<1. 4 E-OS) (<3. 0 E-OS) 1.48 E+00 1:47 E-01 La-140 mCi (<6. 9 E-09) (<9.1 E-09) (<9. 1 E-09) (<1. 8 ~ E-08) (< l. 4 E-OS) (<9. 1 E-09)

Mn-54 mCi . (<1.8 '-08) (<2. 1 E-OS) (<2.0 E-08) 3.41 E-Ol 2.64 E-Ol 1.49 E"01 I

Mo-99 mCi (<1=. 1 E-07) <1. 2 E-07) (<1.2 E-07). (<2.4 E-07) (<1.4 E-07 Nb-95 mCi (<l. 6 E-08) (<1.8 E-08) (<1.6 E-OS) 5.30 E-01 1.86 E-Ol 6.50 E-02 Ru-103 mCi (<1.5 E-OS) <1.7 E-08) (<1.5. E-08) 5.20 E-01 9.85 E-02 (<2.1 E-08)

Sb-124 mCi (<1.4 E-08) <2.3 E-08) (<1.6 E-08) 7.99 E-,02 (<2'7 ~ E-08) (<2. 5- E-08)

'b-125 mCi (<4.9 E-08) <5.6 E-08) (<4.9 E-08) 1.43 E-Ol <6.4 E-Sr-89 mCi .3. 2 E-03 1.4 E-03 (<3.0 E-OO) 7.45 E-02 1.95 E-01 5.58 E-03

~ Sr-90 mCi 2. 9 E-03 1.4 E-03 1.7 E-02 7.66 E-02 (<3.5 E-09) 8.96 E-03 Zr-95 mCi (<2.8 E-OS) <3.2 E-08) (<2.9 E-OS) 1.82 E-Ol 1.08 E-Ol <4.2 E-OS)

Total mCi 7.84 E-Ol 7.61 E-01 5;67 E-01 1.84 E+Ol 1.51 E+Ol 7.57 E+00 NOTE: Numbers in parentheses represent maximum sensitivity in pCi/ml.

1980 Table I Re ort of Radioacti ve Pffluents: . Li uid . Secondar S stem Pa e 5 Isotope Unit JULY AUGUST SEPTEMBER OCTOBER NOUEMBER DECEMBER Ba-140 mCi 4.29 E+00 ~ 2 '1 E-ol.

Co-58 mCi 3.04 E-01 6.10 E+00 7.78 E-01 Co-60 mCi 9' E+00 1.72 E+00 1.06 E+00 1.22 E+OQ 4.47 E+00 2 '1 E+00 Cs-134 mCi 6.3 E-01 2 '1 E+00 1.63 E-Ol Cs-136 mCi 5.65 E-01 Cs-137 mCi 1.17 E+00 1.25 E-Ol 3. 5 +

Cs-138 mCi 4.00 E+Ol-F-18 mCi 9. 1 E-01 F 47 E+00 1~0 E+00 5.38 E-01 5 '8 E+Ol I-131 mCi 5. 5 E-01 5 '4 E-Ol 6 '6 E-01 1 ~ 23 E-Ol 3.46 E+Ol 6.27 E+00 I-132 5. 6 ~ E-ol 6 '6 E+00 7 '5 E-ol 5.08 E-ol 4-29 E+Ol I-133 mCi 2 '8 E+00 9.17 E+00 3 '5 E+00 F 88 E-Ol 8 '5 E+Ol T.-134 mCi F 81 E+00 2,34 E>>01 6.07 E+Ol I-135 7 '0 E+00 1 ~ 34 E+00 1.17 E+00 6.46 E+Ol La-140 mCi 8;58 E-Ol Mn-54 mCi 9.0 E-03 5.40 E-Ol 1.11 E-Ol Mo-99 mCi 5.98 E-ol 2.1 E-02M Na-24 mCi 3.3 E"02 2 '8 E-01 1.03 E+Ol Sr-89 2.7 E-02 3~9 E-02 2' E-02 Sr-90 mC '. 1.0 E-.02 1~5 E-02 1~0 E-02 1.65 E-01 2.38 - 2 Total mCi 1.59 E+Ol 3.30 E+Ol 8.52 E+00 5.21 E+00 4.21 E+02 1 ~ 15 E+01 NOTE: Numbers 4n nArc nt liococ yonrocont mouimssm ~ neo 4 t.4 e4 < ~~ < ~ .~l I 1

1980 Table 1 Report. of Radioactive Effluents:.,Licjuid Dissolved Gas Page 6 SEPTEHBER OCTOBER NOVR1BER DECEHBER Total JULY AUGUST Kr-85 mCi 6.74 E+00 4.91 E+00 4.89 E+00,i 3.52 E+Ol (<6. 7 E-06) ~ 2.20 E+Ol Xe-131m mCi (<1.3 E-06) (<1.3 E-06) (<1.2 E-06) ( <1. 6 E-06) 1.50 E+Ol '<1.4 E-06)

Xe-133 mCi 2.49 E+00-. 1.03 E+00 1.91 E+00 1.16 E+Ol 3.82 E+Ol 1.45 E+Ol Xe-133m mCi (<2.6 E-07) (<2.7 E-07) (<2.5 '-07) (<3.4 E-07) (<1.7 E-07) (<2.9 E-07)

(<2.9 E-08) (<2.9 E-08) (<2.8 E-08) (<3.9 E-08) 1.05 E+Ol (<3.2 E-08)

Xe-135 mCi Waste'isposal System Kr-85 mCi 6.74 E+00 4.91 E+00 4;89 E+00 3.52 g+Ol (<6. I E-06) 2.20 E+Ol mCi (<1. 3 E-06) (<1. 3 E-06) ( <1. 2 E-06) (<1.6: E-06) ( <9. 2 E-07) (<l. 4 E-06)

Xe-131m Xe-133 mCi 2.49 E+00 1.03 E+00 1.91 E+00 1.16 E+Ol 1.92 E+Ol 1.45 E+Ol mCi ( <2. 6 E-07) ( <2. 7 E-07) (<2.5 E-07) (<3.4 E"07) (<1.7 E-07) (<2.9 E 07)

Xe-133m Xe-135 mCi (<2.'9 E-08) (<2.9 E-08) (<2.8 E-08) (<3.9 E-08) 3.3.8 E-Ol (<3.2 E-08)

~

Secondary System Kr-85 mCi Xe-131m mCi 1.50 E+Ol Xe-133 mCi 1.90 E+Ol Xe-133m mCi 1.02 E+Ol Xe-135 mCi

1980 Table XI, Report of Radioactive Effluents! Airborne Page 1 JULY AUGUST , SEP'/EMBER ~ OCTOBER NOVEMBER DECEMBER

h. Pission and Activation Gases
1. To tal Release 8.43 E Ol 8.34 E+Ol 2.72 E+02 1.08 E+02 1.77 E+03 4.87 E+02
2. Avg Rel Rate for Period (pci./sec) 3.5 F+pl 2.8 E+Ol l. 1 E+02, 4.5 E+01 5.9 E+02 2.0 E+02
  • 3. Hax Rel Rate for Period (pci/sec) 1..0 E+03 1.8 E+03 1.0 E+03 3.0 E+03 2.5 E+04 9.0 E+02

~Haximum airborne release rate averaged over one hour for each month. Technical Specification limit is 6.7 E+Ot> jci/se averaged over one hour.

B. Iodine 131

l. Total Iodine 131 (ci) 6..2 E" 05 9.9 E-05 6.7 .E-05. 1. 1 E-'04 4.1 E-02 1.7 E-03
2. Avg Rel Rate for Period (yci/sec) 2. 6 E-05 3.3 E-05 2.8 E-05 4.6 E-05 1.4 E-02 7.1 E-04 C. Particulates
1. Particulates with tl/2>8d (Ci) 9.06 E-05 7.76 E-05 3.87 E-OS 5.10 .E-04 8.66 E-03 -1.42 E-04
2. Avg Rel Rate for Period (uCi/scc) 3.8 E-05 2.6 E-05 1.6 E-05~ 2.1 E-04 2. 9 E" 03 5.9 E-OS
3. Cross Alpha Radioactivity (Ci) 9 4 E p9 7.5 E-09 . 4.6 E-09 2.8 E-08 5. 5 E-08 F 9 E-08 D. Tritium
1. Total Release (ci) 8,26 E-02 1.32 E-01 9.21 E-,02 6.74 E"02 1.46 E"01 1.20 E"02
2. Avp Rel Rate for Period (uci/sec) 3.4 E-02 4.4 E-02 3-8 E-02 2.8 E-02 4.9 E-02 5.0'-03 H. Percent of Applicable Limit Quarter III Quarter IV
l. Pission and Activation Gases '%) 4.7 E-01 2.5 E+00 2, '-131 and Part '(tl/2>8d) (/) 3.9 E-03 5.6 E-01 NOTE: Numbers in parentheses represent maximum sensitivity in pci/cc.

1980 Page 2 isotope Unit. JULY, AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Ba-140 Ci (<5. 6 E-14) (<6.8 E-14) (<5.7 E-14) (<1; 6 E-13) 1. 0 'E-05 (<1. 0 E-'13)

Ce-141 Ci (<l. 9 . E-14) (<1.7 E-14) (<1.8 E-14) 1.8 E-06 (<2. 7 E-14) (<l. 5 E-.14)

Co-57 Ci (<9.0 E-15) (<1.0 E-14) (<1.3 E-14) 9.4. E-07 '<1.6 E-14) (<9.6 E-15)

Co-58 Ci (<3.1 E-14) 2. 9 E-06 (<2.2 E-14) 1.8 E-04 6.4 E-03 1.7 E"05 Co-60 Ci 5.5 E-05 6.'1 E-05 3.1 E-05 3.0 E-04 2.0 E-03 1.0 E-04 Cs-134 Ci (<3.0 E-14) 1.2- E-06 (<2.4 E-14) (<6.0 E-14) 8.7 E-05 4.6 E-06 Cs-136 Ci (<1.8 E-14) (<2.6 E-14) (<1.7 E-14) (<4.4 E-14) 2. 1 E-05 (<3. 7 E-14)

Cs-137 Ci 2. 9 E-06 5.6 E-06 '<3.0 E-14) , 1.3 E-05 9.1 E-05'.7 1.3. E-05.

I-131 Ci (<1.4 E-14) (<1.5 E-14) (<1.4'-14) (<3.1 E-14) E-05 9. 7 E-07 I

La-140 Ci (<1.1 E-$ 4) (<1.0 E-14) (<9. 2 E-15) 1.3 E-06 9.0 E-06 (<2.3 E-14)

Mn-54 Ci (<2.5 E-14) (<3.9 E-14) (<2.0 E-14) 8.0 E-06 4.8'-06 3.1 E-06 Sr-89 Ci 3.2 E-05 5.2 E-06 6.9 E-06 5.2 E-06 5.2 E 06 5.2 E-06 Sr-90 Ci 7. 4 E-07 1.7 E-06 8.1- E-07 (<5.3 E-16 <4.2 E-16 <5.3 E-16 Total Ci 9.06 E-05 7.76 E-05 3.87 E-05 5.1G E-04 8.66 E-03 1-42 E-04 Un'<'I'. ~ lT~ tmhnvn vas I hewer vervain sv t. i 4~wdl4

~ ~ ~ 4 ~ Banal

198Q Table II Airborne Releases Gaseous Page 3 Fission and Activation Gases JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Isotope Ar-41 Ci 6.87 E-Ol

'i 1.60 E+Ol 8.36 E+00 4.80 E-01 2.91 E+00 .31 E-01 Kr-85 Ci (<4.3 E-05) 9.05 E"02 ( 4.9 E-05) 1.52 E-Ol 8.50 E-Ol '8.55 E-Ol Kr-85m (<4.9 E-07) 6.3 E-03 (<1.6 E-07) '.2 E-04 1.01 E+00 9.35 E-03 Kr-87 Ci (<8. 7 E-07) (<9. 7 E-07) (<3.3 E-07) (<9.5 E-07) Q.93 E-01 (<1.8 E-06)

Kr-88 (<l. 1 E-06) (<1. 8 Z-06) (<3.8 E-07) 3.3 - E-05 9.08 E-01 2.5 E-05 Xe-131m Ci (<2.2 . E"05) (<8.2 E-05) (<7.6 E-06) 5.98 E-02 1.44 E-01 7.46 E-Ol Xe-133 Ci 8.29 E+Ol 6.54 E+Ol 2.63 E+02 "

1.07 E+02 1.75 E+03 4.85 E+02 Xe-133m Ci <4.6 E-06 2.60 E-01 1.93 E-01 2.3 -01 6 +00 '

7 XG-135 Ci 4.53 E-01 1.20 5.55 E-Ol 2.76 E-Ol 6.04 E+00 2.05 E-Ol E+00'.68 Xe-135m Ci 1.33 E-ol E-01 2.8 E-02 .(<1. 5 I

E-06) 6.98 E+00 7.24 E-02 Xe-138 (<1. 3 E-06) (<1. 6 E-06) (<4.4 E-07) (<7. 7 E-06) 3.37 E+00 (<1.7 E-06)

To tal 8.43 E+Ol 8.34 E+Ol 2.72 E+02 1.08 E+02 '.77 @+03 4.87 E+02 Halopens (Gaseous)

, JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Isotope Unit I-131 6.2 'E-05 9.9 E-05 6.7 E-05 1.1 E-04 4.1 E-02 1.7 E-03 I-133 Ci 1. 6 E-04 8;0 E-04 4.3 E-04 7.3 E-05 7.7 E-03 <3.4 E-14 I-135 Ci (<1.1 E-13) 3.6 E-04 .6.0 E-05 5.0 E-05 3.7 E-03 (<5.6 E-14)

Br-82 Ci (<7.-9 E-14) 2.8 E"05 2.2 E-05 (<4.1 .E-14) 1.0 E-04 '<4.0 -E-14)

Total Ci 2.2 E-04 1.29 E-03 5.8 E-04 2.3 E-04 5. 3 E-02 1.7 E-03 NOTE:. Numbers in parenth eses represent maximum sensit ivity'in Cileel

RADIOACTIVE WASTE REPORT July -l., 1980, through December 31, 1980 Date of Shi ment Curies Cu. ft.

7/08/80 0. 644 170 Buried in Barnwell, SC 7/10/80 3. 219 170 7/14/80 0. 388 1,100 7/16/80 0.010 "525 7/21/80 0.011 525 7/23/80'/04/80 0.007 525 2.736 . 170 I~

8/11/80 1.931 170 8/25/80 0.966 '70 8/27/80 0.317 1,100 9/03/80 0.012 525 9/08/80 0.241 170 9/10/80 0.009 525 9/15/80 1.127 170 9/17/80 0.003 525 9/23/80 0.010 412.5 9/29/80 14. 245 150 10/06/80 1. 980 150 10/08/80 0. 179 525 10/14/80 0.143 525

, 10/21/80 0.009 525 10/27/80 1. 080 150 11/04/80 1. 288 170 11/06/80 0.805 170 ll/12/80 0. 004 525 11/18/80 0. 008 525 11/24/80 0. 546 1,100 12/01/80 4. 678 170 12/04/80 4. 253 170 12/08/80 0.002 525

'12/23/80 12.876 170 31 Shipments 53.727 12,502.5 On site as of January 1, 1980 16.500 3,700

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