ML17338B055

Semiannual Rept of Radioactive Effluent Releases Rept, Jan-June 1979

ML17338B055
Person / Time
Site:	Turkey Point
Issue date:	06/30/1979
From:	FLORIDA POWER & LIGHT CO.
To:
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ML17338B054	List: ML17338B053 ML17338B055 ML17338B056 ML17338B057
References
NUDOCS 7909110565
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ATTACEBfENT I SE>IIANiiJAL REPORT OF RADIOACTIVE EFFLUENT RELEASES PTP UNITS .3 & 4. 1/79 6/79 Introduction 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 has been met or exceeded.

Li uid Releases, Aliquots of representative pre-release samples were either isotopically anal-P 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 adjusted so that the activity determined by gross beta-gamma analysis approximates the isotopic activities detexmined 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 5:

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, or during lancing of the generators.

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t l

1/79 6/79 2.'he reported values in Table I, page 2 are the total quantities of radioactivity for individual nuclides released from the waste disposal system and the second-ary system together. The values in Table I, page 3 are .for the waste disposal system only and .page 4 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 releases from the waste disposal system due to the long hold-up time of processed water. Only those isotopes that were detected in the second-ary system releases were reported. All non-detectable isotopes are listed as

( ) ~

4. Weekly and monthly composite samples for the waste disposal system were pre-pared to give proportional weight to each liquid release made during the des-ignated period of accumulation. The composites were analyzed for gamma emit-ting 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 deter-mined 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 h

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 concentxations were multi-plied by the total volume released for the month in order to estimate the. total dissolved gases released. If more than one 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 5. Dissolved gases, if any, from

fj I

l l

i

.I I

1/79 6/7 9

'econdary system releases were determined from the'amples 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 indi-vidually 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. The applicable limit for release of radioactive material in liquid waste is five curies per quarter excluding tritium and di.ssolved gases.

8. The following notes have be'eri added to help explain some of the results in Table I:

pn pages 2 and 4, an entry entitled "Unidentified" is made in the isotope listing. This activity is the result of an analysis of blow-down water yielding a low gross beta-gamma activity value and being multiplied by a large volume of water. The low activity of the blow-down water often makes isotopic analysis of the water unreasonable and therefore a gross beta-gamma counter efficiency is chosen so that the total activity determined by gross beta-gamma analysis will approxi-mate the total activity which would be determined using an isotopic analysis.

On page 3, in the June column,, the 1-132 activity value has been super-scripted with a lower case "a" to call attention to it. ~ormally, because of its short half-life, I-132 is not present in the waste disposal system'eleases. However, in June, the I-132 was present as a decay product of Te-132.

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

r 1/79 6/79 I

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-spec-trum analysis, Sr-89-90 determination, gross alpha analysis, and gross beta-gamma analysis.

c) Absorption of halogen radionuclides on a'harcoal filter and subsequent gamma-spectrum analysis, and d) Condensation of water vapor in a gas sample followed by analysis for tritium using liquid scintillation techniques.

All sporadic gas releases from the plant which were not accounted for by the above methods were conservatively estimated by curies of Xe-133 equivalent by use of the plant vent process monitor recorder chart.

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.

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:

Total curies released in gaseous of Limit = 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:.

1/79 6/79 E 'ec',

MPC 3 ( 10,000 m 3

where Q.. i release rate of th nuclide, Ci/sec and MPC = maximum permissible concentration of the ith nuclide, Ci/m'3 The release rate, Qi, ~

was determined by dividing the total activity 'released in Ci, for the ith nuclide,(tj >'d), during the calendar quarter by the seconds in the quarter.

MPCi values .were obtained from 10CFR20, Appendix B, Table II, Column 1. The MPC chosen was the most conservative value of either the soluble or insoluble h

MPC for each isotope.

The percent of applicable limit was determined as follows:

% of Limit ~

E MPC.

x 100%

3 I

10,000 m /sec C

4. The maximum gaseous release rate for each month is listed in Table II, page 1, under Section A, Line 3. The applicable limit for maximum allowable release rate is 6.7 E+04 pCi/sec.

5. All values reported in Table II, pages 2 and 3, include the particulate, gaseous,.

and/or halogen activity released from'he 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 ( ) .

1979 Table I Report of Radioactive Effluents: Liquid Page 1 Liquid Releases JANUARY FEBRUARY MARCtl 'APRIL JUNE A. Gross Radioactivity (8-Y)

1. Total Release (mCi) 3 91 E+01 1.24 E+01 2.86 E+Ol 2.54 F+Ol 2.76 E+01 2.26 E+Ol 3.7 E-10 2.0 E-10 2.2 E-10 2.8 E-10 1.2 E-10

2. Avg Concentration During Releases(pCi/ml)

3. Av Concentration for Month (pCi/ml) 7.0 E-ll 1.2 E-10 1.8 E-10 1.7 E-10 1.0 E-10 1.4 E-08 3.6 E-09 3.3 E-09 9.8 E-'09 3. 3 E-09 4. 3* E-09

4. Max Concentration Released (pCi/ml)

5. Percent of Technical Specification

'.5 1.6 E+00 E+00 Limit for Total Activity Released (/)

B. Tritium

l. Total Release (ci) 1.76 E+01 5.06 E+01 7.96 E+Ol 4.44 E+01 1.81 E+01 8.68 E+01

2. Avg Concentration During Releases(pCi/ml) 9.9 E-08 1.5 E-06 5.7 E-07 3.8 E-07 1.9 E-07 4.6 E-07

3. Avg Concentration for Month (pCi/ml) 9.9 E-08 2.9 '-07 3. 4 E-07. 3. 2 E-07 1.1 E-07 4.0 E-07 C. Dissolved Noble Gas

1. Total Release (mCi) '2.37 E+01 .4.14 E+01 (<5.1 E-06) 1.12 E+02 1.11 F+00 4.82 E+00

2. Avg Concentration During Releases(pCi/ml) ].3 P 10 l. 2 E-09 (<3. 6 E-17) 9. 7 E-10 l. 1 E-ll 2.6 E-ll

3. Avg Concentration for Month (pCi/ml) 1.3 E-10 2.3 E-10 (<2 . 2 E-17) 8.0 E-10 6. 8 E-12 2.2 E-11 D. Gross Alpha Rad'ioactivity

1. Total Release (mCi) <7.7 E-09 3. 1 P.-02 <9.6 E-09 (<9.6 E>>09) (<7.7 E-09 (<1.2 E-08)

2. Avg Concentration During Releases(pCi/ml) <4.3 P,-20 9.2 E-13 (<6'.9 E-20 (<8.3 E-20) (<7.9 E-20 (<6.4 E-20)

3. A'vg Concentration for Month . (pCi/ml) <4.3 E-20) 1.8 E-13 (<4.1 E-20 (<6. 9 E-20) (<4.7 E-20 (<5.5 E-20)

E. Volumes

1. Vol of Liquid Haste to Discharge (Liters) 1.43 E+07 2.15 E+06 1.08'E+07 .

1,37 E+07. 1.04 E+07 1.76 E+07

2. Vol of Dilution Mater During Rel (Liters) 1.78 E+ll 3.37 E+10 1.40 E+ll 1.16 E+ll 9.73 E+10 1.88 E+ll

3. Vol of Dilution Mater for Month (Liters) 1.78 E+ll p.77 E+11 2:33 E+ll 1.40 E+11 1.63 E+ll 2.19 E+11 NOTE: Numbers in parentheses represent maximum sensitivity in pCi/ml.

Q 0

1979 able I . Re ort of Radioactive Effluents: Li uid - Total Pa e 2 Isotope Unit JANUARY .FEBRUARY MARCH APRIL JUNE Ag-110m mCi 2.87 E-01 7 54 E-Ol 4.57 E-OI: 1.28 E-Ol 3.51 E-02 (<3. 8 E-O.S)

Ba-140 mCi (< 1. 5 E-07) (<8.4 E-08) (<B. 6 E-08) (<9.1 E-08), (<9.0 E-08 <7.7 E-08 Co-58= mCi 1.15 E+Ol. 2.61 E+00 3.82 E+00 9.08 E+00 3.35 E+00 3.56 E+00 Co-60 mCi 1.46 E+01 3.83 E+00 7,53 E+00 6.97 E+00 4.10 E+00 9.89 E+00 Cr-51 mCi (<2.8 E-07) 2.65 E-Ol (<2.1 E-07) 1.09 E+00 (<2. 3 E-07) (<1.6 E-07)

Cs-'134 mCi 3.87 E+00 3.81 E-01 1.09 E+00 1.64 E+00 4.40 E+00 1.82 E+00 Cs-136 mCi (<3.0 E-08) {<2. 4 E-08) (<2.1 E-08) (<1.8 E-08) (<2.1 E-08) (<2. 2 E-08)

Cs-137 mCi 5.98 E+00 1.12 H+00 2.37 E+00 3.01 E+00 7.01'+00 2.98 E+00 Fe-59 mCi (<6.5 E-08) (<4.7 E-08) '<4. 9 E-08) 1.7 ~ E-01 (<4. 2 E-OS) (<4.8 F.-08)

I-131 mCi 5.7'-01 1.32 E-Ol 4.58 E-01 1.97 E-01 6:0 H-01 (<1.8 E-08)

I-132 mCi 5. 8 F.-ol

'I-133 mCi {<3. 8 E-08) (<2. 3 E-08) 1.5 E-01 2.38 E-01 1.59 E+00 1.67 E-01 La-140 mCi 6.7 H-02 (< l. 0 E-08) (<1.3 H-08) 1.57 E-01 (<1.6 H-08+ <1.1 E-08 Mn-54 mCi 3: 8 E-01 (<2. 5 E-08) '. 92 E-02 (<2.4 E-08) 5;3 E-02 (<3. 0 H-08)

Mo-99/Tc-99m mCi (<2. 2 E-07) (<1. 3 E-07) (<l. 4 E-07) 1.19 E-01 (<1. 4 E-07) (<1.4 E-07)

Sb-124 8.03 E-01 1.01 H+00 3.70 E+00 1.17 E+00 . 3.72 F+00 1.11 E+00 Sb-125 8. 8 E-Ol 1.20 H+00 3.79 E+00 1.36 L+00 2.69 H+00 1.59 E+00 Sr-89 mCi (<2.8 E-09) 9.0 E-02 5.13 F+00 7.78 E-02 4.64 E-02 3.44 H-Ol Sr-90 'mCi (<2.8 H-09) 3. 6 E-02 (<3.4 H-09) 1.18 E-02 (<3.3 H-09) (<3.0 E-09).

Te-132 mCi 2.13 E-01 (<1.8 E-08) (<1.9 E-08) (<1.8 E-08) (<2.2 E-OS) 5.82 H-Ol Unidentified mCi 1.01 E+00 Total mCi 3.91 E+Ol 1.24 E+01 2.86 E+01 2,54 E+01 2.76 E+Ol 2.26 E+Ol NATE: Numbers in parentheses represent maximum sensitivity in pCi/ml.

1979 Table I ort of Radioactive Efflnents: Liquid. Waste Isotope Unit 'ANUARY Re

' FEBRUARY hKRCH 'PRIL Dis osal S HAY stem P, e JUNE Ag-110m mCi 2.87 E-Ol'.54 E-Ol 4 57 E-OI.'<8.6 1.28 E-Ol 3.51 E-02 (<3.8 E-.08)

Ba-140 mCi (<1.5 E-07) (<8.4 E-08) E-08) (<9.1 E-08) (<9.0 E-08) (<7'.7 E-08)

Co-58 mCi 8.3 E+00 2.4 E+00 3.52 E+00 5.76 E+00 2.29 E+00 2.29 E+00 Co-60 mCi 3.57 E+00 2. 4 E+00 3.81 E+00. 2.98 E+00 2.65 E+00 4.87 E+00 Cr-51 mCi (<2.8 E-07) 2.65 E-01 (<2. 1 E-07) 1.09 8+00 (<2.3 E-07) (<1. 6 E-07)

Cs-134 mCi 1.52 E+00 3.81 E-Ol 6.47 E-01 3.68 E-01 3.88 E-01 1.04 E+00 Cs-136 mCi (<3.0 E-08) (<2.4 E-08) (<2.1 E-08) (<1.8 E-08) (<2.1 E-08) (<2.2 E-08)

Cs-137 mCi 2.2 E+00 7.74 E-Ol 1.32 E+00 8.18 E-01 6.33 E-01 1.51 E+00 Fe-59 mCi (<6.5 E-08) (<4.7 E-08) (<4.9 E-08) 1.70 E-01 (<4.2- E-08} (<4.8 E-08}

I-131 mCi 4.35 E-01 1.32 E-Ol 1.68 E-01 1.97 E-01 (<2:4 E-08) (<1.8 E-08)

I-132 mCi 5.8 E-Ola T.a-140 mCi 6.7 E-02 (<1.0 E-08) (<1.3 E-08) 1.57 E-ol {<1.6 E-08) {<l.1 E-08)

Hn-54 mCi 1.12 E-01 (<2. 5 E-08) 7.82 E-02 (<2.4 E-08) 5.3 E-02 (<3.0 E-08)

Ho-99/Tc-99m mCi ~

(:<2; 2 E-07) (<1. 3 E-07) (<1.4 E-07) 1.19 E-01 (<1%4 E-07) (<1.4 H-07)

Sb-124 mCi 8.03 E-01 1.01 E+00 3.70 E+00 1.17 E+00 3.72 E+00 1.11 E+00 Sb-125 mCi 8.21 E-Ol 1.20 E+00 3. 79 'E+00 1.36 6+00 2.69 E+00 1.59 E+00 Sr-89 mCi (<2.8 E-09) 9;0 E-02 5,13 E+00 3.67 E-02 4.1 E-02 3.44 E-Ol Sr-90 mCi (<2.8 E-09) 3. 6 E-02 (<3.4 E-09) 1.18 E-02 (<3.0 E-09) (<3. 0 E-09)  !

Te-132 'mCi 2.13 E-01 (<1.8 E-08) ~ (<1.9 E-08) (<1.8 E-08) (<2.2 E-08) 5.82 E-01 ~

Total mCi 1.83 E+Ol 9.44 E+00 2.26 E+Ol 1.44 E+01 1.25 E+Ol 1.39 E+01 NATE: Numbers in parentheses represent maximum sensitivity-in pCi/ml.

1979 Table I . Re ort of Radioactive Effluents: Li uid Secondar S stem Pae4 Isotope Unit JANUARY .FEBRUARY MARCH APRIL HAY JUNE Co-58 mCi 3.18 E+00 2.1 E-01 2.99 E-01: 3.32 E+00 1.06 E+00 1:27 E+00  !

Co-60 mCi' 1.10 E+Ol 1.43 E+00 3.72 E+00 3.99 E+00 1.45 E+00 '5.02 E+00 Cs-134 mCi 2.35 E+00. 4.38 E-01 1.27 E+00 4.01 E+00 7.79 E-01 Cs-137 mCi 3.78 E+00 3.43 E-Ol 1. 05 'E+00 2.20 E+00 6.38 E+00 1.47 E+00 i I-131 mCi 1. 3 E-01 2. 9 E-.01 6.0 E-01 I

. I-133 mCi 1. 5 E-01 2.38 E-Ol 1.59 E+00 1.67 E-01 Mn-54 mCi -2. 7 E-Dl Sb-125 mCi - 6.0 E-02 Sr-89 mCi (<2. 8 .'E-09 4.11 E-02 5.4 E-03 S1-90 mCi (<2.8'. E-09) (<3.5 E-09) (<3:3 E-09)

Unidentified mCi 1.01 E+00-Total . mCi 2.08 E+01 2.99 E+00 5.95 E+00 1.11 E+01 1.51 E+01 8.71 E+00 NDTH: Numbers in parentheses represent'aximum sensitivity in pCi/ml,

0 1979 Table 1 Report of Radioactive. Effluents: Liquid - Dissolved Gas Page 5 Total JANUARY .FEBRUARY HARCII APRIL JUNL'r-85 mCi 1.41 E+01 1.96 E+Ol (<5.1 E-06$ (<4.2 E-06) (<6.0 E-06) ~

(<5.3 E-06)

Xe-131m -mCi (<9.2 E-07) (<1.3 E-06) (<5.5 E-07) 1.83 E+01 (<9.7 E-07) (<8.7 E-07)

Xe-133 mCi 9.6 E+00. 1.63 E+Ol (q3. 5 E-08) -

9. 31 E+01 6.6 E-01 4.82 E+00 Xe-133m mCi (<2.1 E-07) (<3.0 E-07) (<1. 3 E-07) (<1. 5 E-D7) <1.7 E-07 <1.7 E-07 Xe-13S mCi (<2.5 E-08) 5.54 E+00 (<1.4 '-08) 5.08 E-01 4.46 E-01 (<1.8 E-08)

Total 2.37 E+01 4.14"E+Ol (<5.1 E-'06) 1.12 E+02 1.11 E+00'.82 E+00 klaste Disposal System Kr-85 mCi 1.41 E+01 1.96 E+Dl (<5.1 E-06) (<4.2 E-06) (<6.0 E-06 <5. 3 '-06 Xe-131m mCi (<9.2 E-07) (<1.3 E-06) (<5.5 E-07) 1.83 E+01 (<9. 7 E-07) (<8. 7 E-07)

Xe-133 mCi 9. 6 E+00 1.63 E+Ol <3.5 E-08 9.31 E+01 Xe-133m mCi (<2. 1 E-07) (<3. 0 E-OI) (<1,3 E-07) (<1.5 E-07) (<1. 7 E-07) (<1. 7 E-07)

Xe-135 mCi (<2:5 E-08) 5.54 E+00 (<1.'4 E-08) 5.08 E-'01 4;46 E-01 (<1.8 E-08)

Secondax S stem Kr-85 Xe-131m mCi Xe-133 mCi Xe-133m mCi Xe-135 iinvp N>>mba rs 4n narentbeses represent maximum r

sensitivity in UCi/ml..

- 1979 Table II Report of Radioactive Effluents: Airborne Page 1 JANUARY FEBRUARY NARC H APRIL JUNE A. Fission and Activation Gases

1. Total Release (Ci) 1,19 E+03 1.29 E+03 - 1.87 E+03 2.28 E+03 1.74 E+03 8.35 E+02

2. Avg Rel Rate for Period. (pCi/sec) 4.4 E+02 5.4 E+02. 6. 9 E+02 8.8 E+02 - 6.4 E+02 3. 2 E+02

" 3. Haz Rel Rate for Period (pCi/sec) 2.8 E+03 1. 1 E+04 6.9 E+03 2. 3 E+04 3.0 E+03 6.8 E+02

>'Maximum airborne release rate averaged over one hour for each month. Technical Specification limit is 6.7 E+04 pCi/sec avera ed over one hour. 'I B. Iodine - 131

1. Total Iodine - 131 (Ci) 6.2 E-03 7. 5 E-04 3.5 E-03 1.8 E-03 3.3-. E-03 1.7 E-03

2. Avg Rel Rate for Period (pCi/sec) 2.3 E-03 3.1 E-04 1.3 E-03 6. 9 E-04 1.2 E-03 6.5 E-04 C. Particulates

1. Particulates with tl/2>8d (Ci) 1.13 E-02 4.72 F.-03 2.56 E-04 1.84 E-02 1.99 E-03 4.36 E-04

2. Avg Rel Rate for Period (pCi/sec) 4.2 E-03 2.0 E-03 9.5 E-05 7.1 E-03 7. 4 E-04 1. 7 E-04

3. Gross Alpha Radioactivity (Ci) 8.6 E-08 5.3 E '.5 E-09 9.5 E-08 1.5 E-08 7.3 E-09 D. Tritium

1. Total Release (ci) 1.. 7 E-02 1.5 E-02 6. 4 E-02 2.6 E-02 9.3 E-02 3.7 E-02

2. Avg Rel Rate for Period (pCi/sec) 6. 3 E-03 6.3 E-03 2.4 E-02 1.0 E-02 3.4 E-02 1. 4 E-02 E. Percent of Applicable Limit UARTER I UARTER II

1. Fission and Activation Gases (%) 4.7 E+00 5.1 E+00

2. I-131 and Part (tl/2>8d) (%) 1. 7 E-01 1. 1 E-Ol NOTE: Numbers in parentheses represent maximum sensitivity in pCi/cc.

1979 Page 2 Isotope Unit JANUARY FEBRUARY MARCH , APRIL JUNE Ba-140 Ci (<1.7 E-12) (<l. 1 H-12) (<1.1 H-13) (<2.3 E-12) ,3.6 E-05 (<1.3 E-13)

Ce-141 8. 9. E-05 1.7 H-05 (<2.1 E-14) (<3.6 E-13) (<6. 4 E-14) (<2.2 E-14)

Ce-144 Ci 7.3 H-05 <8.3 F.-13 <9.3 E-14 <1 6 .-12 <9. 9 E-14 Co-57 2. 0 E-05 7.4 E-06 (<1. 2 E-14) 2.7 E-05 7.3 E-07 <l. 3 F.-14 Co-58 Ci 4.2 E-03 2.0 E-03 8.0 E-05 1.3 E-02 1.1 E-03 2.5 E-04 Co-60 Ci 5. 5 E-03 2. 2 E-03 9.9 H 2.2 E-03 3.7 E-04 E-04 Cr-51 -

Ci 5.4 E-04 2.4 E-04 (<2.4 E'13) 2.3 E-03 1.2 H-04 (<2. 7 H-13)

Cs-134 4.3 ~ E-05 (<4.2 H-13) 2:. 4 E-05 3.5 E-05 8.3 E-05 1.8 E-,05 Cs-136 Ci (<5.5 '-13) (<3. 6 E-13) (<3-4 E-14) (<3. 9 E-13) (<8.7 E-14) (<2. 6 E-14)

Cs-137 Ci 8.3 E-05 3. 1 '--E-:06 .- 3.7 E-05 4.8 '-05 1.2 E-04 2.8 E-05 Fe-59 (<1. 4 E-12) (<8. 6 E-13) (<5. 7 E-14):1. 5 E-04 1.7 E-05 (<6. 2 E-14)

I-131 1.3 E-05 (<2.4 E-13) 7.2 H-06 6.1 E-06 1.2 E 05 2.7 E-06 La-140 Ci (<3.2 E-13) (<1.6 E-13) (<3.9 E-14) (<1.5 E-13) 4.6 F;05 4,4 E-06 Hn-54 Ci 1.7 E-04 5.7 H-05, (<4.7 H-14) 2.9 E-04 4, 1 E-05 1.2 05 Nb-95 Ci ~ ~ 5. 1 E-05 1.1 E-04 (<3.3 E-24) 1.5 E-04 1. 4 H-.05 (<3. 7' E-14)

.Ru-103 3.3 E-04 6). 0 H-05 (<2. 6 E-14) (<5, 7 E-13) (<9.0 H-14) (<3.1 E-14)

Ci - 1. 5 H-05 2. 2 F.-05 (<3.5 E-14) 1.2 E-04 (<1.1 H-13) (<4. 5 H-14)

Sb-124 ~

Sb-125 Ci 1,5. E-05 (<7. 3 E-13) (<7, 2 E-14) (<1, 3 E-l 2) (<2. 3 E-13) (<8. 2 E-14)

Sr-89 Sr-90 'i Ci

~

2.9

--3.9 E-06 E-07 6.4 1 1 H-06 E-06 E-13) 6.3 2.8

(<6.9 E-06 E-06 H-14)

2. 4 5.3 E-06 H-06 E-12) 2.

3.

(<1.9 7

7 E-05 E-07 E-13) 1.0 1.2

(<5,9 E-05 H-06 E-14)

Zn-65. 1.5 H-04 <9,9 ( 1.0 Zr-95 Ci 2.8 E-05 <6.9 E-13) (<4.5 E-14) 8.0 E-05 (<1,6 E-13) (<5.0 E-14)

Total Ci 1.13 E-02 4.72 E-03 2.56 E-04 1,84 H-02 1.99 E-03 4.36 E-04 NATE: Numbers $ n narentheses represent maximum sensxtivity 'in 1)Ci/c Ca

0 1979 Table II Airborne Releases - Gaseous Page 3 Fission and Activation Gases Isotope Unit 'ANUARY FEBRUARY MARCH: APRIL JUNE

'i Ar-41 1.32 E+Ol 1.93 E-01 6.17 E+00 4.41 8+00 1.73 E+00 8.12 E+00 Kr-85 Ci 1. 3 E-01 (<3. 1 E-05) 1.26 E-Ol 5.83 E-02 (<6.5 E-05) 1.37 E-01 Kr-85m 9.3 E-03 5.1 E-03 4.4 E-01 5.52 E-01 1.1 E-Ol 1 7 E-02 Kr-87 Ci (<1.2 E-06) (<1.9 E-07) 9.0 E-03 1.72 E-Ol (<4.0 E-07) (<6.8- E-06)

Kr-88 Ci (<2 9 E-06) (<2 0 E-07) 2.0 E-01 5.52 E-Ol (<4.9 E-07) 5.7 E-03 Xe-13ln Ci 3. 1 E-02

(<3. 2 E-06) 1.05 E-Ol 1.91 E-02 (<8. 7 E-06) 4.93 E-02 Xe-133 1.18 E+03 1.29 E+03 1.85 E+03 2.26 E+03 1.74 E+03 8.25 E+02 Xe-133m Ci 1.02 E-01 5.3 E-02 1.49 E+00 2.26 E+00 (<2.0 E-06) 2.55 E-ol XG-135 Ci 9.34 E-01 1.93 F;01 7. 7 E+00 9.48 E+00 2.3 .E+00 1.78 E+00 Xe-135m (<5.4 E-06) (<1.3 E-07) (<1.1 E-06) (<7.6 E-07) (<3.1 E-07) (<2. 9 E-06)

Xe-138 (<1.8 E-05) (<2.0 E-07) (<5. 7 E-06) (<1. 4 E-06) (<5. 5 E-07) (<1.7 E-05)

Total Ci 1.19 E+03 'l. 29 E+03 1.87 E+03 ',28 E+03 '.74= E+03 8.35 E+02 Halo ens (Gaseous)

Isotope Unit JANUARY FEBRUARY MARCH APRIL JUNE I-131 6.2 E-03 7.5 E-04 3.5 E-03 1. 8 L'-03 3. 3 L'-03 1. F-I-133 Ci 2.6 E-03 4.5 E-04 9. 4 E-04 4. 2 E-.04 l. 5 E-03 l. 1 E-03 I-135 (<2.6 E-13) (<1.2 E-13) 1.0 E-13) (<3.6 E-13) (<1.4 E-13) (<8.8'-14)

Br-82 3.0 E-04 6.9 E-05 Total 8.8 E-03 1.20 E-03 '.7 E-03 2.3 E-03 4.8 E-O3 2. 8 E-03 xnvt: ~ N>>mhr rs in narentheses renresent maximum sensitivity in uCi/cc.