ML17340A818

Radioactive Effluent Release Data,Jul-Dec 1980

ML17340A818
Person / Time
Site:	Turkey Point
Issue date:	02/21/1981
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17340A817	List: ML17340A815 ML17340A818 ML17340A819
References
NUDOCS 8103110714
Download: ML17340A818 (15)

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.

7/80 - 12/80 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 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:

m'

< 10,000

, where Q.

MPC " 'ec' i

and MCPi

~ release rate of i nuclide, Ci/sec

.th

~ maximum permissible concentration of the i nuclide, Ci/m th..

3 The, release, rate, Q, <<was determined."by<<dividing the total activity released th in Ci, for the i 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 x 100%

MPC.i 10,000 m /sec 3

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

2. Avg Concentration During Releases(uCi/ml) 6.1 E-ll 9.8 E-ll 4.2 E-ll

3. Av Concentration for Month (uCi/ml) 6-1 '-Il 9-8 E-ll

. 3.4

• E<<ll

~i. llax Concentration Released (uCi/ml) 5.5 E-10 3.4 E-10 4.6 E-10 236

+1

l. 6 E-10

l. 2 E-10 3.1 E-09

+02

2. 0 E-09 1.8 E-09 1.5 E-.08 1.90 E+01 1 3 E-10 1.1 E-10 3.0 E"09

5. Percent of Technical Specification Limit for Total Activity Released

(/)

1.2 E+00.

9.6 E+00 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)

3. Avg Concentration for Month (ljCi/ml)

.-07 7 0 E-08 1.A E-07 7.0 E-08 142 E-07

1. 1 E-06

8. 5 E-07 4.7 E-07 7.2 E-08 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. Avg Concentration for Month (pCi/ml) 3.4 E-ll 3.4 E-ll 1.7 E-ll 1.7 E-ll

3. 1 E-11

3. 1 E-10 2.6 E-11 2.4 E-lo 2.9 E-10 2.6.

E-10 2.7 E-10 '.l E-10 D. Gross Alpha Radioactivity

1. Total Release (mCi)

<.0

-09

<7 9

~ E-09

2. hvg Concentration During Releases(pCi/ml)

<3 3 E 20

<2 3

E 20

<1. 0 E-08

'<1.0 E-08

{<4.6 E-20)

(<6.7 E-20)

<l. 2 E-08

(<5. 5 E-20)

<6. 5 E-09

(<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 2.. Vol of Dilution Hater During Rcl (Liters) 2.74 E+ll 3.43 E+ll 2.18 E+ll 1.49 E+ll

3. Vol of Dilution Hater for Month (Liters) 2.74 E+ll 3.43 E+ll 2.65 E+ll 1.93 E+ll I

NOTE:

Numbers in parentheses represent maximum sensitivity in pCi/ml.

1.90 E+07 2.19 E+ll'.38 E+ll 1.83 E+07 1.41 E+ll 1.72 E+ll

1980 Table I Re'rt oZ Radioactive Eff1uents'.

Li uid - Total Pa e

2 Isotope Unit JULY

~

AUGUST SEPTEMBER

• OCTOBER NOVEMBER DECEMBER Ba-140 Co-58 Co-60 Cr-51 Cs-134 Cs-136 Cs-137 Cs-138 mCi mCi mCi mCi mCi mCi mCi mCi 8.96 E-02 9.78 E+00 1.35 E-01 2.10 8+00

(<1. 3 E-07)

(<1.5 E-07) 6.94 E-01 8.63 E-02

(<1. 6 E-08)

(<1. 7 E-08) 1.32 E+00 1.57 E-Ol

(<5.8 E-08)

~

(<6.7 E-08)

(< 5. 9 E-08.}

3.77 E-02 1.46 E+00

(<1.1 E-07) 3.68 E-.02.

(<1.8 E-08)'.07 E-02

(<1.4 E-07) 5.18 E+00 9.25 E+00 2.14 E+00 4.15 E-01

(<3. 6 E-08) 1.08 E+00 4.29 E+00

~

1.06 E+Ol 9.62 E+00 1.33 E+00 3.41 E+00 5.65 E-Ol 4.97 E+00 4.00 E+Ol 2.41 E-Ql 4.06 E+00 4.59 E+00 9.13 E-01 4.37 E-01

(<1.8 E-08) 6.89 E-ol F-18 I-131 I-132

.I-133 I-134 I-135 mCi mCi.

mCi mCi mCi mCi 9.1 E-01 5.5'-01 5.6 E-01 2.68 E+00 5.47 E+00 5.14 E-Ol 6.66 E+00 9.17 E+00 1.81 E+00 7.30 E+00 1.00 E+00 6.86 E-01 7,45 E-01 3.65 E+00 1.34 E+00 5.38 E-01 1.23 E-Ol 5.08 E-01 9.88 E-01 2.34 E-01 1.17 E+00 5.48 E+Ol 3.61 E+Ol 4.29 E+Ol 8.05 E+Ol 6.07 E+01

.6.A6 E+Ol 6.42 E+00 La-140 Mn-54

~

Mo-.99 Na-24 Nb-95 mCi mCi mCi mCi mCi 9.0 E-03

(<1.1 E-07) 3.3 E-02

(<2.1 E-08).

(<1.2 E"07) 2.68 E"01

(<1.6 E-08)

(<1.8 E-08)

(<6. 9 E-09)

(<9. 1 E-09)

(<9.1 E-09)

(<2.0 E-08)

(<1.2 E-07)

(<1.6 E-08)

(<l.8 E-08) 3.41 E-ol

~ (<2.4 E-07) 5.30 E-01 8.$ 8 E-Ol 8.04 E-Ol 5.98 E-01 1.03 E+Ol 1.86 E-03:

(<9.1 E-09) 2.60 E-01 2.1 E-02 6.5 E-02 Ru-103 Sb-124 Sb-125 mCi mCi

(<1.5 E-08)

(<l. 7 E-08)

<<l. 4 E-08)

(<2. 3 E-08)

(<4.9 E-08)

(<5.6 E-08)

(<1.5 E-08)

(<1.6 E"08)

(<4.9 E-08) 5.20 E-01 7.99 E-02 1.43 E-Ol 9.85 E-02

(<2.1 E-08)

(<2.7 E-08)

(<2.5 E-08)

(<6.4 E-08)

(<5.8 E-08)

Sr-89 Sr-90 mCi mCi 3.02 E-02 1.29 E-02

4. 0 E-02 1.6 E-02 2.6 E-02 2.7 E-02 7.45 E~02 7.66 E-02 9.00 E+00 1.65 E-01 1.31 E+00 3.28 E-02 DENOTE:

Numbers in parentlieses represent maximum sensitivity in pCi/ml.

1980 able I Re ort of Radioactive Hffluents:

Li uid <<Total Page 3

~

~

Isotope Zr-95 Unit mCi JULY

(<2.8 E-08)

.AUGUST

(<3.2 E-08)

(<2. 9 E-08)

~

1.82 E"01 SEPTEMBER OCTOBER NOVEMBER DECEMBER

~ 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 Co-60 Cr-51 Cs-134 mCi mCi mCi mCi 8.96 E-02 4.80 E-01

(<1. 3 E-07) 6.37 E-02

~ 1.35 E-Ol 3.80 E-.01

(<l. 5 E-07) 8.63 E-02 3.77 E-02 3.95 E-01

(<1.1 E-07) 3.68 E-.02 4.88 E+00 8.03 E+00 2.14 E+00 4.15 E-Ol 4..51 E+00 5.15 E+00 1.33 E+00 5-96 E-Ol 3.28 E+00 2.28 E+00 9.13 E-01 2-74 E-Ol Cs-136 Cs-137 I-131

, mCi.

mCi mCi

(<l. 6 E-08) 1.45 E-01

(<1.4 E-OS)

(<1. 7 E-08) 1.57 E-01

(<1.8

. E-08) 8.07 E-02

(<1. 4 E-OS) 9.56 E-Ol

(<3. 0 E-OS)

(<1.8 E-08)

(<3.6 E-08) 1.22 E+00.

1.48 E+00 4 45 E 0 1:47 E-01

(<2. 1 E-08)

(<1.8 E-,OS)

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 Mo-99 mCi.

(<1.8 '-08) mCi

(<1=. 1 E-07)

(<2. 1 E-OS)

<1. 2 E-07)

(<2.0 E-08) 3.41 E-Ol

(<1.2 E-07).

(<2.4 E-07) 2.64 E-Ol

(<1.4 E-07 1.49 E"01 I

Nb-95 Ru-103 mCi mCi

(<l. 6 E-08)

(<1.5 E-OS)

(<1.8 E-08)

<1.7 E-08)

(<1.6 E-OS)

(<1.5. E-08) 5.30 E-01 5.20 E-01 1.86 E-Ol 9.85 E-02 6.50 E-02

(<2.1 E-08)

Sb-124

'b-125 mCi mCi

(<1.4 E-08)

(<4.9 E-08)

<2.3 E-08)

<5.6 E-08)

(<1.6 E-08)

(<4.9 E-08) 7.99 E-,02 1.43 E-Ol

(<2'7

~ E-08)

(<2. 5-E-08)

<6.4 E-Sr-89

~ Sr-90 mCi mCi

.3. 2 E-03

2. 9 E-03 1.4 E-03 1.4 E-03

(<3.0 E-OO) 1.7 E-02 7.45 E-02 7.66 E-02 1.95 E-01

(<3.5 E-09) 5.58 E-03 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 Ba-140 Co-58 Co-60 Cs-134 Cs-136 Unit mCi mCi mCi mCi mCi JULY 9 '

E+00 6.3 E-01 AUGUST 1.72 E+00 SEPTEMBER 1.06 E+00 OCTOBER 3.04 E-01 1.22 E+OQ NOUEMBER 4.29 E+00

~

6.10 E+00 4.47 E+00 2'1 E+00 5.65 E-01 DECEMBER 2'1 E-ol.

7.78 E-01 2'1 E+00 1.63 E-Ol Cs-137 Cs-138 F-18 I-131 I-132 mCi mCi mCi mCi 1.17 E+00

9. 1 E-01

5. 5 E-01

5. 6

~ E-ol F 47 E+00 5'4 E-Ol 6'6 E+00 1 ~ 0 E+00 6'6 E-01 7'5 E-ol 1.25 E-Ol 5.38 E-01 1 ~ 23 E-Ol 5.08 E-ol 3.

5

+

4.00 E+Ol-5'8 E+Ol 3.46 E+Ol 4-29 E+Ol 6.27 E+00 I-133 T.-134 mCi mCi 2'8 E+00 9.17 E+00 F 81 E+00 3'5 E+00 F 88 E-Ol 2,34 E>>01 8'5 E+Ol 6.07 E+Ol I-135 La-140 Mn-54 Mo-99 Na-24 mCi mCi mCi mCi 9.0 E-03 3.3 E"02 7'0 E+00 2'8 E-01 1 ~ 34 E+00 1.17 E+00 6.46 E+Ol 8;58 E-Ol 5.40 E-Ol 5.98 E-ol 1.03 E+Ol 1.11 E-Ol 2.1 E-02M Sr-89 Sr-90 mC '.

2.7 E-02 1.0 E-.02 3 ~ 9 E-02 1 ~ 5 E-02 2 '

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

Total Kr-85 Xe-131m Xe-133 Xe-133m Xe-135 mCi mCi mCi mCi mCi JULY 6.74 E+00 AUGUST 4.91 E+00

(<1.3 E-06)

(<1.3 E-06) 2.49 E+00-.

1.03 E+00

(<2.6 E-07)

(<2.7 E-07)

(<2.9 E-08)

(<2.9 E-08)

SEPTEHBER 4.89 E+00,i

(<1.2 E-06) 1.91 E+00

(<2.5 '-07)

(<2.8 E-08)

OCTOBER 3.52 E+Ol

( <1. 6 E-06) 1.16 E+Ol

(<3.4 E-07)

(<3.9 E-08)

NOVR1BER

(<6. 7 E-06)

~

1.50 E+Ol 3.82 E+Ol

(<1.7 E-07) 1.05 E+Ol DECEHBER 2.20 E+Ol

'<1.4 E-06) 1.45 E+Ol

(<2.9 E-07)

(<3.2 E-08)

Waste'isposal System Kr-85 Xe-131m mCi mCi 6.74 E+00 4.91 E+00

(<1. 3 E-06)

(<1. 3 E-06) 4;89 E+00

( <1. 2 E-06) 3.52 g+Ol

(<1.6: E-06)

(<6. I E-06)

( <9. 2 E-07) 2.20 E+Ol

(<l.4 E-06)

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 Xe-133m Xe-135 mCi mCi

( <2. 6 E-07)

( <2. 7 E-07)

(<2.'9 E-08)

(<2.9 E-08)

(<2.5 E-07)

(<2.8 E-08)

(<3.4 E"07)

(<3.9 E-08) 3.3.8 E-Ol

(<3.2 E-08)

(<1.7 E-07)

(<2.9 E 07)

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

1980 Table XI, Report of Radioactive Effluents!

Airborne Page 1

JULY AUGUST SEP'/EMBER

~ OCTOBER NOVEMBER DECEMBER

h. Pission and Activation Gases 1.

Total 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

3. Cross Alpha Radioactivity (Ci) 9 4 E p9 2.6 E-05 1.6 E-05~

7.5 E-09

. 4.6 E-09 2.1 E-04 2.8 E-08

2. 9 E"03

5. 5 E-08 5.9 E-OS 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

l. Pission and Activation Gases '%)

2, '-131 and Part '(tl/2>8d)

(/)

Quarter III 4.7 E-01 3.9 E-03 Quarter IV 2.5 E+00 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 Co-60 Cs-134 Ci Ci Ci

(<3.1 E-14) 5.5 E-05

(<3.0 E-14)

2. 9 E-06 6.'1 E-05 1.2-E-06

(<2.2 E-14) 3.1 E-05

(<2.4 E-14) 1.8 E-04 3.0 E-04

(<6.0 E-14) 6.4 E-03 2.0 E-03 8.7 E-05 1.7 E"05 1.0 E-04 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 I-131 Ci Ci

2. 9 E-06 5.6 E-06

(<1.4 E-14)

(<1.5 E-14)

'<3.0 E-14)

(<1.4'-14)

, 1.3 E-05

(<3.1 E-14) 9.1 E-05'.7 E-05 1.3.

E-05.

9. 7 E-07 La-140 Mn-54 Ci Ci

(<1.1 E-$ 4)

(<1.0 E-14)

(<2.5 E-14)

(<3.9 E-14)

(<9. 2 E-15)

(<2.0 E-14)

I 1.3 E-06 8.0 E-06 4.8'-06 3.1 E-06 9.0 E-06

(<2.3 E-14)

Sr-89 Sr-90 Ci Ci 3.2 E-05

7. 4 E-07 5.2 E-06 1.7 E-06 6.9 E-06 8.1-E-07 5.2 E-06

(<5.3 E-16 5.2 E 06

<4.2 E-16 5.2 E-06

<5.3 E-16 Total Un'<'I'. ~

lT~ tmhnvn Ci 9.06 E-05 vas I hewer vervain sv t.

3.87 E-05 7.76 E-05 i ~

~ 4~wdl4 ~ 4

~

Banal 5.1G E-04 8.66 E-03 1-42 E-04

198Q Table II Airborne Releases Gaseous Page 3

Fission and Activation Gases Isotope JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Ar-41 Kr-85 Ci Ci 6.87 E-Ol

(<4.3 E-05) 1.60 E+Ol 9.05 E"02 8.36 E+00 4.80 E-01

( 4.9 E-05) 1.52 E-Ol 2.91 E+00 8.50 E-Ol

.31 E-01

'8.55 E-Ol Kr-85m Kr-87 Ci

(<4.9 E-07) 6.3 E-03

(<8. 7 E-07)

(<9. 7 E-07)

(<1.6 E-07) '.2 E-04

(<3.3 E-07)

(<9.5 E-07) 1.01 E+00 Q.93 E-01 9.35 E-03

(<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 Xe-133 Ci Ci 8.29 E+Ol 6.54 E+Ol

(<2.2. E"05)

(<8.2 E-05)

(<7.6 E-06) 5.98 E-02 2.63 E+02 1.07 E+02 1.44 E-01 1.75 E+03 7.46 E-Ol 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 Xe-135m Ci Ci 4.53 E-01 1.33 E-ol 1.20 E+00'.68 E-01 2.8 E-02 I

.(<1. 5 E-06) 5.55 E-Ol 2.76 E-Ol 6.04 E+00 6.98 E+00 2.05 E-Ol 7.24 E-02 Xe-138'i

(<1. 3 E-06)

(<1. 6 E-06)

(<4.4 E-07)

(<7. 7 E-06) 3.37 E+00

(<1.7 E-06)

Total 8.43 E+Ol 8.34 E+Ol 2.72 E+02 1.08 E+02 '.77

@+03 4.87 E+02 Halopens (Gaseous)

Isotope I-131 I-133 Unit Ci

, JULY 6.2

'E-05

1. 6 E-04 AUGUST 9.9 E-05 8;0 E-04 SEPTEMBER 6.7 E-05 4.3 E-04 OCTOBER 1.1 E-04 7.3 E-05 NOVEMBER 4.1 E-02 7.7 E-03 DECEMBER 1.7 E-03

<3.4 E-14 I-135 Br-82 Total Ci Ci

(<7.-9 E-14) 2.2 E-04 Ci

(<1.1 E-13) 3.6 E-04 2.8 E"05 1.29 E-03

.6.0 E-05 2.2 E-05 5.8 E-04 5.0 E-05

(<4.1

.E-14) 2.3 E-04

5. 3 E-02 1.7 E-03 3.7 E-03

(<5.6 E-14) 1.0 E-04

'<4.0

-E-14)

NOTE:. Numbers in parenth eses represent maximum sensit eel ivity'in. Cil

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

7/08/80 7/10/80 7/14/80 7/16/80 7/21/80 7/23/80'/04/80 8/11/80 8/25/80 8/27/80 9/03/80 9/08/80 9/10/80 9/15/80 9/17/80 9/23/80 9/29/80 10/06/80 10/08/80 10/14/80

, 10/21/80 10/27/80 11/04/80 11/06/80 ll/12/80 11/18/80 11/24/80 12/01/80 12/04/80 12/08/80

'12/23/80

0. 644

3. 219

0. 388 0.010 0.011 0.007 2.736 1.931 0.966 0.317 0.012 0.241 0.009 1.127 0.003 0.010

14. 245

1. 980

0. 179 0.143 0.009

1. 080

1. 288 0.805

0. 004

0. 008

0. 546

4. 678

4. 253 0.002 12.876 170 170 1,100 "525 525 525 170 170

'70 1,100 525 170 525 170 525 412.5 150 150 525 525 525 150 170 170 525 525 1,100 170 170 525 170 Buried in Barnwell, SC I~

31 Shipments 53.727 12,502.5 On site as of January 1, 1980 16.500 3,700