ML20072C310
| ML20072C310 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 03/01/1983 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17345A972 | List: |
| References | |
| NUDOCS 8303080391 | |
| Download: ML20072C310 (17) | |
Text
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i RADIOACTIVE EFFLUENT RELEASE DATA JULY 1982 THROUGH DECEMBER 1982 SUBMITTED BY NUCLEAR CHEMISTRY DEPARTMENT TURKEY POINT PLANT FLORIDA POWER & LIGHT COMPANY DISTRIBUTION
- 3. L. DANEK A.3. GOULD (3)
D.W. HAASE E.R. LAPIERRE 3.5. WADE R.3. FRECHETTE FILE 8303000391 830301 PDRADOCK05000g R
SEMIANNUAL REPORT OF RADIOACTIVE EFFLUENT RELEASES, PTP UNITS 3 & 4 7/82 - 12/82 Introduction All liquid and airborne discharges to the environment during this reporting period were analyzed in accordance with Technica! Specification requirements. The minimum frequency of analysis as required by Safety Guide 21 was met or exceeded.
Liquid Releases 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 2x 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 viantity 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. -
7/82 - 12/82
- 2. The reported values in Table 1, 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 1, page 4 are for the waste disposal system only and pages 5 and 6 are 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 (-).
- 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 of accumulation. The composites were analyzed for gamma emmitting isotopes on a multichannel analyzer attached to a high resolution Gr.(Li) detector, and for Sr-89 and Sr-90, using a chemical separation and subsequent beta determination with a 2x gas flow proportional counter.
Tritium was determined by use of liquid scintillation techniques and gross alpha radioactivity was determined by use of a 2n 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 fusion 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 2
a .
~.
7/82 - 12/82
,, dissolved gases released. If more than one batch of effluent was analyzed, the concentrations were weighted in an appropriate manner. The l
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 cf secondary system batch releases were analyzed individually for gamma emitting isotopes. Analysis of a representative composite for tritium was made for releases which occurred due to primary to secondary leakage.
- 7. The ap;,licable limit for release of radioactive materialin liquid waste is five i curies per quarter excluding tritium and dissolved gases.
l 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 i in airborne releases are:
a) Gamma spectrum analysis for fission and activation gases, i
ll 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 tritium using liquid scintillation techniques.
3
7/82 - 12/82 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 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 airborm 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 waste during quarter x 100%
% of Limit =
(.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 m3, where Q; = release rate of ith nuclide, Ci/sec MPCI sec and MPCi = maximum permissible concentration of the ith nuclide, Ci/m3 The release rate, Qj, was determined by dividing the total activity released in Cl, for the ith nuclide (ty, > 8d), during the calendar quarter by the seconds in the quarter.
4
7/82 - 12/82 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 MPC for each isotope.
The percent of applicable limit was determined as follows':
x 100%
E
% of Limit = MPCi 10,000 m3 / sec
- 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 cCi/sec, 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 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 (-).
~
5
i NUCLEAR CHEMISTRY PROCEDURE NC-3 .
l PREPARATION OF THE MONTHLY " PRELIMINARY REPORT ON RADI0 ACTIVE RELEASES" AND THE l YEAR 1982 "RADI0 ACTIVE EFFLUENT RELEASES" PORTION OF THE SEMIANNUAL CPERATING REPORT PAGE 1 i
i TABLE I Report of Radioactive Effluents: Liquid Julv Annust September October Novembe r December l
]llA.GrossRadioactivity(8-3) j 1. Total Release (mC1) l 1.01 E402 l 6. 2 3 E401 l 1.19 E402l 5.99 E40ll 1. 73 E401 l 2.81 E401l jl 2. Avg Concentration During Releases (pCi/ml) l 5.1 E-10 l 2.0 E-10 l 4.5 E-10l '2.3 E-10l 1.2 E-10l 1.6 E-10 l jl ,.3. Avg Concentration for Month (pCi/ml) l 4.2 E-10l 1.9 E-10 l 4.3 E-10l 2.1 E-10l 9.9 E-11l 1.6 E-10 l '
s - '
F._ Max Concentration Released (uC1/ml) 1.7 E-08 l 9.9 E-09 l 9.2 E-09 1.1 E-08l 1.7 E-08i 7.6 E-09
- 5. Percent of Technical Specification Limit for Total Activity Released (f.) 5.6 E400 2.1 E400 llB. Tritium l
- l 1. Total Release (C1) l 4.18 E401 l 1.35 E401 l 5.67 E401l 6.32 E401l 4.94 E401l 9.09 E401l
- 2. Avg Concentration During Releases (pC1/ml) l 2.1 E-07l 4.4 E-08 l 2.4 E-07l 3.4 E-07l ll 2.1 E-07l 5.2 E-07 l i ll 3. Avg Concentration for Month (pCi/ml) l 1.7 E-07l 4.1'1908 l 2.1 E-07l 2.4 E-07l 2.8 E-07l 5.1 E-07l,
)jC.DissolvedNobleGas l' ll 1. Total Release (mC1) l -4.13 E401 l 1.69 E401 l 1.12 E402l 1.01 E402l 8.50 E402l 4.45E+02l ll 2. Avg Concentration During Releases (uCi/ml) l 2.1 E-10 l 5.5 E-11 l 4.2 E-10] 3.8'E-10l 5.9 E-09l 2.6 E-09 l 1
- l 3. Avg Concentration for Month (uC1/ml) l 1.7 E-10 l 5.2 E-11 l 4.1 E-10l 3.8 E-10l 4.9 E-09l 2.5 E-09 l '
l D. Gross Alpha Radioactivity ___l l 1. Total Release (mci) l(<1.2 E-08)l(< 1. 2 E-08) l(<9.9 E-09)[<1.4 E-08) l (< 7. 3 E-09}(<1.0 E-08)l
.l 2. Avg Concentration During Releases (uC1/ml) l(<6.1 E-20)l( <3.9 E-20) l(<3. 7 E-20)I<5.3 E-20)l(<5.1 E-203(<5.7 E-20)l
!l l
- 3. Avg Concentration for Month (uci/ml) l(<5.0 E-20)l(<3. 7 E-20) l(<3.6 E-20)(<5.3 E-20)l(<4.2 E-203(<5.6 r-00)l ll E. Volumes l l 1. Vol of Liquid Waste to Discharge (Liters) l 1.41 E407 l 2.26 E407 l 2.46 E407l 3.59 E407l 1,74 E+07l 3.69 E407 l l 2. Vol of Dilution Water During Rel. (Liters) l 1.98 E+11 l 3.08 E+11 l 2.65 E+11l 2.65 E+11 l 1,44 E+11l 1. 74 E+11 l ll 3. Vol of Dilution Water for Month (Liters) l 2.40 E+11 l 3.26 E+11 l 2.74 E+11l 2.6s E+11l 1.74 E+11l 1. 79 E+11 l NOTE: Numbers in parentheses represent maximum sensitivity in_pCi/ml.
HUCLEAR CHEMISTRY PROCEDURE NC-3 -
PREPARATION OF Tile. MONTH 1 Y " PRELIMINARY REPORT ON RADI0 ACTIVE RELEASES" AND THE YEAR 1982 "RADIDACTIVE EFFLUENT RELEASES" PORTION OF TiiE SEMIANNUAL OPERATING REPORT PAGE 2 ,
TABLE I Report of Radioactive Effluents: Liquid - Total isotope Unit July August Sep tember October November Decembe r Ag-110m mci 4.13 E-02 2.52 E-01 1.15 E-01 8.85 E-02 8.04 E-02 (<1.1 E-07)
Bu-140 mci 6.97 E-01 (<6 . 3 E-0 7) (<2.9 E-07) (<6.3 E-07) ( <4 . 2 E-07) (<6.1 E-07)
Co-58 mci 3.69 E+00 1.08 E+01 1.84 E+00 6.28 E+00 2.94 E+00 7.35 E+00 Co-60' mci 3.43 E+00 2.79 E+00 2.55 E+00 6.79 E+00 2.89 E+00 8.76 E400 Cr-51 mci 3.65 E-01 5.71 E-01 4.99 E-01 ( <9 . 3 E-07) ( <6 . 4 E-0 7) (<7.9 f-0 7)
Cs-134 mC1 3.36 E+00 5.06 E+00 2.94 E+00 5.79 E+00 2.87 E+00 2.14 E+00 Cs-136 mci 4.65 E-01 (<1.1 E-0 7) 4.32 E-01 1.9 E-01 (<9.5 E-08) 1 (<2.1 E-07)
Cs-137 mci 6.68 E+00 9.75 E+00' 6.15 E+00 1.03 E+01 5.57 E+00 4.00 E+00 Cs-138 mci 1.78 E+00 --
1.07 E+00 -- -- --
F -18 mci 2.82 E+00 6.31 E-01 5.19 E-01 1.09 E-01 1.02 E-01 2.2 E-01 I -131 mCL 4.66 E+01 2.49 E+01 8.74 E+01 2.21 E+01 1.83 E+00 4.29 E+00 1 -132 mci 2.60 E+00 2.68 E-01 2.82 E-01 -- -- --
i I -133 mci 1.55 E+01 5.16 E+00 1.38 E+01 4.04 E+00 4.06 E-01 3.45 E-01 I -134 mci 1.05 E+00 -- -- -- -- --
~
I -135 mci 4.89 E+00 6.85 E-01 6.47 E-01 2.6 E-01 -- --
La-140 mci 9.97 E-02 2.96 E-02 (<2.5 E-08) (<3.7 E-08) (<3.6 E-08) (<4.0 E-08)
Mn-54 mci 8.34 E-01 2.05 E-01 2.7 E-02 8.94 E-02 (< 6. 7 E-08) (<9.9 E-08)
Mo-99/Tc-99m mci 4.04 E+00 3.79 E-01 (<3.5 E-0 7) 7.94 E-01 (<2.9 E-0 7) (<5.4 E-07)
NOTE: Numbers in parentheses represent maximum sensitivity in pCi/ml.
NUCLEAR CHEMISTRY PROCEDURE NC-3 PREPARATION OF.THE MONTHLY " PRELIMINARY REPORT ON RADI0 ACTIVE RELEASES" AN0'THE YEAR 1982 "RADI0 ACTIVE EFFLUENT RELEASES"-PORTION OF THE SEMIANNUAL OPERATING REPORT PAGEj3 TABLE I Report of Radioactive Effluents: Liquid - TOTAL isotope Unit July August September J October Novembe r Decembe r Na-24 mci 1.61 E-01 -- -- -- -- --
Nb-95 mci 1.31 E-01 3.24 E-02 9.00 E-02 (<9.6 E-08) 8.5 2 E-02 (<1.1 E-07) i Sb-124 mci (<5.6 E-08) 1.79 E-01 (<3.9 E-08) (<5.8 E-08) (<4.9 E-08) (<7.2 E-08)
Sb-125 mci (<1.4 E-07) (<3.5 E-07) (<l.4 E-07) (<3.5 E-0 7) 8.5 2 E-02 (<2.6 E-0 7) 1 Sr-89 mci 1.25 E400 6.0 E-01 1.1 E-01 3.11 E+00 3.7 E-01 1.0 E+00 Sr-90 mci 5.1 E-02 (<5.9 E-09) 1.7 E-02 (<l.7 E-08) 2.2 E-02 (<5.4 E-09) 1 Zr-95 mC1 2.18 E-02 (<1.4 E-07) 5.4 E-02 (<1.7 E-07) (<1.3 E-0 7) (<l.8 E-0 7) '
1 1
4 l
i t
i Total mci 1.01 E+02 6.23 E401 1.19 E402 5.99 E+01 1.73 E+01 2.81 E+01 i ,
! NOTE: Numbers in parentheses represent maximum sensitivity in pCi/ml.
NUCLEAR CilEMISTRY PROCEDURE NC-3 PREPARATION OF Tile MONTilLY " PRELIMINARY REPORT ON RADIDACTIVE RELEASES" AND Tile YEAR 1982 "RADI0 ACTIVE EFFLUENT RELEASES" PORTION OF Tile SEMIANNUAL OPERATING REPORT PAGE 4 4
TABLE I Report of Radioactive Effluents: Liquid - WASTE DISPOSAL SYSTEM lsotope Unit July l August l September October l November Decembe r 1 An-110m mci 4.13 E-02 2.52 E-01 1.15 E-01 8.85 E-02 8.04 E-02 (<1.1 E-07)
Ba-140 moi (<2.8 E-0 7) (<6.3 E-07) (<2.9 E-0 7) (<6.3 E-07) (<4.2 E-07) (<6.1 E-07) .
a Co-58 mci 2.91 E+00 9.99 E+00 1.6 2 E+00 5.80 E+00 2.86 E+00 5.50 E+00 Co-60 mci 1.13 E+00 2.59 E+00 1.18 E+00 4.40 E+00 2.48 E+00 6.67 E+00 Cr-51 mci 3.65 E-01 5.71 E-01 4.99 E-01 (<9.3 E-07) (<6.4 E-0 7) (<7.9 E-07)
Cs-134 mci 3.65 E-01 4.60 E+00 1.48 E+00 4.65 E+00 2.81 E400 1.91 E+00
__Cg-137 mci 6.41 E-01 8.08 E+00 2.63 E400 8.21 E+00 5.28 E+00 3.49 E+00 1 -131 mci 1.07 E+00 1.38 E+00 1.19 E+00 1.05 E+00 8.08 E-01 1.75 E+00 La-140 mci (<3.8 E-08) 2.96 E-02 (<2.5 E-08) (<3.7 E-08) (<3.6 E-08) (<4.0 E-08)
Mn-54 mci 7.9 E-02 7.51 E-02 1.63 E-02. 8.94 E-02 (<6.7 E-08) (<9.9 E-08)
Mo-99 /Tc-99 m mci 5.96 E-01 3.79 E-01 (<3.5 E-0 7) 7.94 E-01 (<2.9 E-0 7) (<5.4 E-0 7) -
Nb-95 mci 1.31 E-01 3.24 E-02 9.00 E-02 (<9.6 E-0 8) 8.5 2 E-02 (<1.1 E-07)
Sb-124 mci (<5.6 E-08) 1.79 E-01 (<3.9 E-08) (<5.8 E-08) (<4.9 E-08) (<7.2 E-08)
Sb-125' mci (<1.4 E-07) (<3.5 E-07) (<1.4 E-07) (<3.5 E-07) 8.52 E-02 (<2.6 E-0 7)
Sr-89 mCL 2.5 E-01 1.9 E-01 1.1 E-01 3.4 E-01 1.6 E-01 (<5.4 E-09)
Sr-90 mC1 5.1 E-02 (<5.2 E-09) 1.7 E-02 (<1.7 E-08) (<6.0 E-09) (<4.0 E-09)
Zr-95 mci 2.18 E-02 (<1.4 E-07) 5.40 E-02 (<1.7 E-07) (<1.3 E-07) (<1.8 E-07) 1 Total mci 7.65 E+00 2.83 E+01 9.00 E+00 2.54 E+01 1,46 E+01 l
1.93 E+01 NOTE: Numbers in parentheses represent maximum sensitivity in pCi/ml.
i i
NUCLEARCHEMISTRYPROCEdURENC-3 PREPARATION OF Tile MONTilLY " PRELIMINARY REPORT ON RADIDACTIVE RELEASES" AND THE YEAR 1982 "RADIDACTIVE EFFLUENT RELEASES" PORTION OF Tile SEMIANNUAL OPERATING REPORT PAGE5-
- TABLE I i
Report of Radioactive Effluents: Liquid - Secondary System Isotope Unit July August i September October November i December Ba-140 mci 6.97 E-01 -- -- -- -- --
' Co-58 mC1 7.78 E-01 8.05 E-01 2.18 E-01 4.77 E-01 7.5 E-02 1.85 E+00 i
Co-60 mci 2. 30 E+00 1.95 E-01 1.37 E+00 2.39 E+00 4.1 E-01 2.09 E+00 Cs-134 mCL 2.99 E+00 4.63 E-01 1.46 E+00 1.14 E400 6.2 E-02 2.3 -E-01 Cs-136 mci 4.65 E-01 --
4.32 E-01 1.9 E-01 -- --
{
1 Cs-137 mci 6.04 E+00 1.67 E400 3.52 E+00 2.13 E+00 2.9 E-01 5.06.E-01 l
Cs-138 mC1 1.78 E+00 --
1.07 E+00 -- -- --
. F -18 mC1 2.82 E+00 6.31 E-01 5.19 E-01 1.09 E-01 1.0 2 E-Ol' 2.2 E-01 y
I -131 mCL 4.55 E401 2.35 E+01 8.6 2 E+01 2.10 E+01 1.02 E400 2.54 E+00
$ i -132 mci 2.60 E+00 2.68 E-01 2.82 E-Ol' -- -- --
i I -133 mCL 1.55 E+01' 5.16 E+00 1.38 E+01 4.04 E+00 4.06 E-01 3.45 E'-01 j T -134 mci 1.05 E+00 -- -- -- -- --
I -135 mci 4.89 E+00 6.85 E-0) 6.47 E-01 2.6 E-01 -- --
i 4 La-140 mci 9.97 E-02 -- -- -- -- --
h Mn-54 met 7.55 E-Ol' 1. 30 E-01 1.1 E-02' -- -- --
Mo-99/Tc-99m mci 3.44 E+00 - -- -- -- --
i
{ Nn-24 mci 1.61 E-01 -- -- --
i Rr-RO mci 1.0 E400 4.1 E-01 (<1.4 E-0 8) 2.77 E400 ,
2.1 E-01 1.0 E+00 NOTE: Numbers in parentheses represent maximum sensitivity in pC1/ml.
me n - -
NUCLEAR CHEMISTRY PROCEDURE NC-3' .'
PREPARATION OF THE MONTHLY " PRELIMINARY REPORT ON RADIDACTIVE RELEASES" AND Tile.
} YEAR1982 "RADI0 ACTIVE EFFLUENT RELEASES" PORTION OF Tile SEMIANNUAL OPERATING REPORT PAGE 6 i
TABLE I Report of Radioactive Effluents: . Liquid - SECONDARY SYSTEM isotope Unit July August September October Novembe r December Sr-90 mci (<1.2 E-08) (<5.9 E-09) (<8.2 E-09) (<7.9 E-09)- 2.2 E-02 (<5.4 E-09) i i
i 1
i t
i j
1 Total mci 9.29 E+01 3.39 E+01 1.10 E+02 3.45 E+01 2.60 E+00 8.78 E+00 i
NOTE: Numbers in parentheses represent maximum sensitivity in pCi/ml. ,
NUCLEAR CHEMISTRY PROCEDURE NC-3 .
PREPARATION OF THE MONTHLY " PRELIMINARY REPORT ON RADI0 ACTIVE RELEASES" AND THE
- YEAR 1982 "RADI0 ACTIVE EFFLUENT RELEASES" PORTION OF THE SEMIANNUAL OPERATING REPORT" PAGE , 7 ' ,
TABLE I i l Report of Radioactive Effluents: Liquid - Dissolved Gas Iotal July August l Sep tembe r October Novembe r Decembe r Kr-85 mci (<4.4 E-06) (<2.8 E-05) (<8.2 E-06) (<l.1 E-05) (<5.7 E-05) (<6.8 E-06)
Xe-131m mci 3.4 E-01 (<3.1 E-06) 7.9 E+00 (<l.8 E-06) 1.8 E+01 8,00 E+00-Xe-133 mci '4.0 E+01 1.69 E+01 9.1 E+01 9.9 E+01 8.24 E+02 4. 35 E+02 1
- Xe-133n mci 3.0 E-01 (<8.4~ E-07) 3.7 E+00 (<3.8 E-0 7) 6.4 E400 2.1 E+00 l Xe-135 mci 6.4 E-01 (<l.1 E-07) 9.1 E+00 1.6 E+00 1.2 E+00 1.4 E-01 Waste Disposal System l Kr-85 mci (<4.4 E-06) (<2.8 E-05) (<8.2 E-06) (<l.1 E-05) (<5.7 E-05) ,
(<6.8 E-06)
Xe-131m mci 3.4 E-01 (<3.1 E-06) 7.9 E+00 (<l.8 E-06) 1.8 E +01 8.00 E+00
, Xe-133 mci 4.0 E+01 1.69 E+01 9.1 E+01 9.9 E+01 8.24 E+02 4. 35 E+02 mci 3.0 E-01 (<8.4 E-07) 3.7 E400 (<3.8 E-07) 6.4 E400 2.1 E+00 Xe-133m Xe-135 mci 6.4 E-01 (<1.1 E-07) 9.1 E+00 1.6 E+00 1.2 E+00 1.4 E-01 Secondary System I i
Kr-85 mci -- -- -- -- -- --
Xe-131m mci -- -- -- -- -- --
i Xe-133 mci -- -- -- 4 -- -- --
mci -- --
Xe-133m -- -- -- --
i Xe-135 mci -- -- --
NOTE: Numbers in parentheses represent maximum sensitivity in pCi/ml.
1
, -- . -- - _ n
NUCLEAR CHEMISTR) PROCEDURE NC-3 .
PREPARATION-0F THE MONTHLY " PRELIMINARY REPORT ON RADI0 ACTIVE RELEASES" AND THE
- YEAR 1982 "RADI0 ACTIVE EFFLUENT RELEASES" PORTION OF THE SEMIANNUAL OPERATING REPORT PAGE 1 TABLE II Report of Radioactive Effluents: Airborne A. Fission and Activation Gases July August September ! October November l December
- 1. Total Release (C1) 3.01 E403 9.11 EM 2 2.36 E403 1.55 - E403 9.98 E402 8.27 E402
- 2. Avg Release Rate for Period (uCi/sec)- 1.24 E+03 3.02 E402 9.75 E402 5.13 E402 4.12 E402 3.42 E+02
- 3. Max Release Rate for Period (pCi/sec) 5.5 E404 5.0 E404 5.7 E404 5.3 E+04 2.5 E404 1.0 E404
- Maximum airborne release rate averaged over one hour for each month. Technical Specifications imit is 6.7 E+04 pCi/sec averaged over one hour.
B. Iodine - 131
- 1. Total Iodine - 131 (C1) 3.7 E-02 1.24 E-02 8.93 E-03 3.1 E-02 3.6 E-02 6.3 E-03
- 2. Avg Release Rate for Period (uC1/sec) 1.5 E-02 4.1 E-03 3.7 E-03 1.0 E- 02 1.5 E-02 2.6 E-03 C. Particulates l 1. Particulates (with t1/p>8_ days) (C1) 3.00 E-04 2.64 E-04 4.2 E-05 4.8 E-04 6.8 E-04 1.38 E-04 l 2. Avg Release Rate for Period (pC1/sec) 1.24 E-04 8.74 E-05 1.7 E-05 1.6 E-04 2.8 E-04 5.70 E-05
- 3. Gross Alpha Radioactivity (C1) 1.9 E-09 2.4 E-08 1.5 E-08 4.5 E-08 5.5 E-08 9.6 E-08 D. Tritiun
- 1. Total Release (Ci) 2.69 E-01 1.96 E-01 1.45 E-01 2.29 E-01 4.74 E-02 2.03 E-02
! 2. Avg Release Rate for Period (uCi/sec) 1.11 E-01 6.49 E-02 5.99 E-02 7.58 E-02 1. 96 E-0 2 8.39 E-03 E. Percent of Applicable Limit QUARTER III QUARTER IV
- 1. Fission and Activation Gases (%) 6.6 E+00 3.5 E400 i
- 2. 1-131 and Part (t1/2>8d) (5) l 7.3 E-01 9.2 E-01 NUTE: Numbers in parentheses represent maximum sensitivity in pCi/ml.
NUCLEAR CHEMISTRY PROCEDURE NC-3 PREPARATION OF THE MONTHLY " PRELIMINARY REPORT ON RADI0 ACTIVE RELEASES" AND THE WEAR 1982 "RADI01.CTIVE EFFLUENT RELEASES" PORTION OF THE SEMIANNUAL OPERATING REPORT PAGE 2 TABLE II Airborne Releases - Particulates <
isotope Unit '
July August September l October l November l De cembe r Ba-140 Ci 5.6 E-06 (<1.8 E-13) (<7.8 E-14) 2.0 E-05 (<2.5 E-13) (<1.1 E-13)
Co-57 C1 (<1.7 E-14) (<1.3 E-14) (<1.1 E-14) 3.5 E-07 (<2.6 E-14) (<9.0 E-15)
Co-5 8 Ci 4.5 E-05 9.5 E-05 4.6 E-07 2.2 E-04 4.2 E-05 4.2 E-05 Co-60 C1 7.9 E-05 4.5 E-05 3.0 E-05 5.1 E-05 3.8 E-05 4.4 E-05 Cr-51 Ci (<3.1 E-13) 4.1 E-06 (<1.3 E-13) 1.2 E-05 (<4.2 E-13) (<l.7 E-13)
Cs-134 C1 3.0 E-05 2.6 E-05 (<2.6 E-14) 2.6 E-05 7.1 E-05 4.3 E-06 Cs-136 C1 1.7 E-05 6.3 E-06 (<3.3 E-14) 9.4 E-06 2.6 E-05 (<3.6 E-14) 1.4 'E-05 Cs-137 Ci 7.1 E-05 6.5 E-05 2.2 E-06 4.9 E-05 1.3 E-04 1 -131 C1 4.4 F.-05 1.8 E-05 6.5 E-06 5.4 E-05 3.7 E-04 3.1 E-05 La-140 C1 (<6.3 E-14) 2.4 E-06 (<4.7 E-14) 1.4 E-05 (<7.0 E-14) (<2.7 E-14)
Mn-54 C1 4.0 E-06 (<3.7 E-14) (<3.1 E-14) 1.2 E-05 2.4 E-06 1.0 E-06 Nb-95 Ci 6.7 E- 07 (<2.8 E-14) (<2.7 E-14) 3.1 E-06 (<4.7 'E-14) (<2.9 E-14)
\
Ru-103 C1 (<4.4 .E-14) (<3.5 E-14) (<1.8 E-14) 3,8 E-06 (<5.4 E-14) (<2.6 E-14)
Sr-89 C1 3.2 E-06 2.3 E-06 2.3 E-06 1.47 E-06 1.6 E-06 1.0 E-06
.' Sr-90 C1 3.8 E-07 2.5 E-07 2.5 E-07 4.8 E-07 5.1 E-07 L 2.5 E-07 t
Total C1 3.00 E-04 2.64 E-04 4.2 E-05 4'. 8 E-04 6.8 E-04 1.38 E-04 NOTE; fumbers in parentheses represent maximum sensitivity in pCi/ml.-
NUCLEAR CHEMISTRY PROCEDURE NC-3 .'
PREPARATION OF Tile MONTHLY " PRELIMINARY REPORT ON RADI0 ACTIVE RELEASES" AND THE YEAR 1982 "RADIDACTIVE EFFLUENT RELEASES" PORTION OF Tile SEMIANNUAL OPERATING REPORT PAGE 3 TABLE II Airborne Releases - Gaseous Fission and Activation Ga es July August September October November December Ar-41 Ci 1.15 E400 5.92 E+00 9.4 E-01 1.22 E400 1.39 E400 1.21 E-01 Kr-85 Ci 5.17 E400 2.10 E400 1.35 E400 4.09 E-01 4.64 E400 2.54 E400 Kr-85m. Ci 7.95 E-01 5.59 E-01 2.62 E400 8.81 E-01 4.03 E-01 1.29 E-01 Kr-87 Ci 4.03 E-03 1.70 E-01 2.20 E-01 2.51 E-01 1.49 E-01 1.55 E-02 Kr-88 Ci 6.20 E-01 6.8 E-01 2.29 E400, 8.67 E-01 5.68 E-01 1.03 E-01 Xe-131m Ci 1.70 E401 2.44 E400 7.83 E400- 5.06 E400 4.53 E400 2.15 E400 Xe-133 Ci 2.95 E403 8.87 E402 2.30 E403 1.5 2 E403 9.76 E402 8.19 E402 Xe-133m Ci 1.74 E401 4.59 E+00 1.42 E401 9.00 E400 2.82 E400 1.37 E400 Xe-135 Ci 1.81 E401 7.27 E400 3.28 E401 1.47 E401 7.39 E400 1.65 E400 Xe-135m Ci 6.30 E-02 2.0 E-01 2.56 E-01 1.5 E-01 6.89 E-02 (<9.1 E-05)
Xe-138 C1 ( <l . 7 E-04) 1.01 E-01 ( <1.5 E-04) ( <1. 2 E-04) ( <1.4 E-04) ( <1.1 E-04) 3.01 E403 9.11 E402 2.36 E403 1.55 E403 9.98 EiO2 8.27 E402 Total C1 Italogens (Gaseous)
Isotope Unit July August Sep tembe r October Novembe r December I-131 Ci 3.7 E-02 1.24 E-02 8.93 E-03 3.1 E-02 3.6 E-02 6.3 E-03 1-133 Ci 2.0 E-02 5.1 E-03 1.91 E-03 6.5 E-03 4.2 E-02 3.0 E-04 I-135 C1 3.1 E-03' 3.4 E-04 3.4 E-05 ( <3.4 E-13) 3.4 E-03 (<5.7 E-13)
Br-82 Ci 9.9 E-04 5.1 E-04 1.1 E-03 7.5 E-04 (<3.2 E-13) (<9.8 E-14)
Total Ci 6.1 E-02 1.84 E-02 1.20 E-02 3.8 E-02 8.1 E-02 6.6 E-03 Note: Numbers in parentheses represent maximum sensitivity in pC1/ml.
[
PADI0 ACTIVE WASTE REPORT
,, JULY 1, 1982 to DECEMBER 31, 19S2 LATE OF SHIPMENT CURIES CU. FT. DISPOSITION 07-13-S2 .048 840 Buried in Barnwc11, SC 08-10-82 .052 735 "
08-17-S2 3.306 170 "
08-26-82 .071+ 1050 Buried in llanford, WA 09-08-82 4 .6 74 , 170 Buried in Barnwell, SC 09-12-82 1.699 170 " "
09-17-82 91.837 84 '"
09-28-82 175.5 84 "
10-05-82 .096 1050 Buried in Hanford, WA 10-07-82 .052 '
1050 "
10-12-82 .033 840 Buried in Barnwell, SC '
10-26-82 .043 1050 Buried in Hanford, WA 11-02-82 .100 1050 Buried in Barnwell, SC 11-09-82 .122 1050 , Buried in Hanford, WA 11-23-82 .065 1050 "
11-30-82 .051 1050 "
12.-06-82 52830 170 Buried in Barnwell, SC 12-07-82 .048 1050 Buried in Hanford, WA 12-08-82 .082 , 1050 "
12-09-82 .573 170 Buried in Barnwell, SC 12-13-82 5.934 170, "
12-15-S2 .817 170 "
12-16-82 .090 200 12-20-82 .078 735 24 Shipments 291.201 Curies 15208 Cu. Ft.
ON SITE AS OF JANUARY 1,1983 128.326 Curies 2584 Cu. Ft.
1 1
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