ML20149J324
| ML20149J324 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah |
| Issue date: | 12/31/1985 |
| From: | Wallace P TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20149J297 | List: |
| References | |
| NUDOCS 8802220357 | |
| Download: ML20149J324 (23) | |
Text
_ __
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% IA 107 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT --
SUPPLEMLNTAL INFORMATION
.Ya-g=
I C'jMNNd 1.
Regulatory Limits a.
Fission and Activation Gases:
(1). Instantaneous - Nuclide Dependant (all release points)
Shield Building Auxiliary Building Condenser Vacuum Exhaust Service Building NOTE:
To plant release rate limit per nuc*ide are established by Health Physics Technical Assistance Section. These lim-are further evaluated to each vent based on design Glow rate. Technical Specification will not be exceeded until the
/
sum of individual isotope release rate per release race limit exceeds 1.0.
- b. & c.
Iodines and particulates, half-lives >8 days (1)
Instantaneous - Nuclide Dependant NOTE: Total plant release rate limit per nuclide are estab-lished by TVA's Health Physics Technical Assistance J'
Section. These limits are further evaluated to each vent based on design flow rate. Technical Specifica-tions will not be exceeded until the sum of individual isotope release rate per release rate limit exceeds 1.0.
d.
Liquid effluent: I MPC $ 1.0 (reference 10CFR20, Appendix E, note 3C, Table II, column 2).
e.
Tritium 5-(1)
Liquid - 1 3.0E-3 pCI/mL (ref. 10CFR20, Table II, column 2)
(2) Airborne - (reference 10CFR20, Table II, column 1)
?. ~.
Shield Building 53.423E+03 pCi/sec Auxil'iary Building 12.787E+04 pCi/see Service Building 11.271E+03 pCi/sec CondEn'serVacuumExhaust$5.501E+00pCi/see 9
NOTE:
These limits are established by TVA based on each vents design flowrate.
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8802220357 860228 PDR ADOCM 05000327 R
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e EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION 2nd HALF 85 2.
Maximum Permissible Concentrations
(
a.
Fission and Activation Gases:
Not Applicable b.
Not Applicable c.
Particulates, half-lives > 8 days:
Not Applicable d.
Liquid effluents:
sum of indv. MPC ratios < 1.0 (ref.10CFR20, Appendix B, Note 1) 3.
Average Energy - Not Applicable
_4.
Measurements and Approximations of Total Radioactivity a.
Fission and Activation Gases Airborne effluent gaseous activity is continuously monitored and recorded.
Additional grab samples from the shield, auxiliary, service and condenser vacuum exhausts are taken and analyzed at least monthly to determine the quantity of noble gas activity released for the month based on the average vent flowrates recorded for the sample period.
Also, noble gas samples are collected and evaluated for the shield and auxiliary buildings fol-loving startup, shutdown or a rated thermal power changes exceeding 15%
within one hour.
The vent flowrates for the shield auxiliary, service buildings, and condenser vacuum exhaust are determined and recorded once i shi'ft.
The quantity of noble gases released through the shield and auxiliary building due to purging or venting of containment and releases of waste gas decay tanks are also determined.
The total noble gas activity released for the month is then determined by summing all of the activity released from cach vent for all sampling periods, the activity released from purging or venting of containment, and the activity released from waste gas decay tank (s).
Allowance is made for a plus or minus one sigma counting error associated with the samma isotopic analyses.
2-
3
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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION 2nd MALT 45
\\
- 4. 3 Measurements and Approximation of Total Radioactivity (continued) t
- b. & c.
Iodines and Particu16tes Iodine and particulate as-tivity is continuously monitored and re-corded.
Charcoal and particulate samples are taken from the shield and auxiliary building exhausts and analyzed at least weekly to de-termine the total activity released from the plant based on the average vent flowrates recorded for sampling period.
Also, particulate and charcoal samples are taken from the auxiliary and shield buildings once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for 2 days following startup, shutdown or a rated thermal power change exceeding 15% within one hour.
The quantity of iodine and particulate released from each vent during each sampling period is then determined using the aver-age vent flowrates recorded for the sampling period and activity concentration.
The vent flowrate
' rom the shield and auxiliary buildings are re-corded once a shi..
The total particulate and iodine activity released for the morth is then determined by summing all of the activity released from the shield and auxiliary buildings for all sampling periods.
Allowance is made for a plus or minus one sigma counting error associated with the samma isotopic analyses, d.
Liquid Effluents (1) Batch (Radwaste and condensate regenerants to cooling tower blowdown) l Total samma isotopic activity concentrations are determined on each batch of liquid effluent prior to release.
The to-tal curie content of a released batch is determined by sus-mius each nuclide's concentration and multiplying by the total volume discharged.
The total activity released during a month is then determined by summing the activity content l
of each batch discharged during the month.
l l
l i
k EFFLUENT AND WASTE DISPOSAL SEMIANNUAL R2 PORT SUPPLEMENTAL INFORMATION 2nd HALF 85 4.
Measurements and Approximation of Total Rauloactivity (continued)
(2) Continuous Releases and Periodic continuous _Re'reasec (Condensate regeneraats, turbine building sump and steam generator blowdown)
Total gamma isotopic activity concantration is determined daily on a composite sample from the condensate system and turbine building sump and weekly for steam generator blow-down.
The total curie content of the continuous release is determined weekly by summing each nuclide's concentration and multiplying by the total volume discharged.
The total activity released during the month is then determined by summing the activity content of each daily and weekly com-i posite for month.
Allowance is made for plus or minus one sigma counting error associated with the total gamma isotopic analyses.
5.
Batch Value Units 4
Quarter Quarter 3rd 4th a.
Liquid I
1.
Number of batches released 112 94 Each 2.
Total time period for batch releases 16826 13284 Minutes 3.
Maximum time period for a batch release 270 657 Minutes 4.
Average time period for batch releases 150 425 Minutes i
5.
Minimum stream flow during periods of effluent into a flowing stream:
(a)
(a)
(a) See Radiological Health Technial Assistance Section's portion of semi-annual effluent release report.
]
b.
Gaseous (1) Number of batches released 129 2
Each 1
(2) Total time period for batch releases 24290 368 Minutes 1
(3) Maximum time period for a batch release 2865 258 Minutes (4) Average time period for batch releases 188 184 Minutes (5) Minimum time period for a batch release 30 110 Minutes 4-l
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L EFFLUENT AND WASTE DISPOStL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION 2nd HALF 85 6.
Abnormal Releases t
i Value Units
- Quarter, Quarter 3rd 4th a.
Liquid i
(1) Number of Releases 0
0 (2) Total Activity Released 0.00E-01 0.00E-01 Ci l
b.
Gaseous (1) Number of Releases 0
0 (2) Total Activity Released 0.00E-01 0.00E-01 Ci I
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EFTLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT c
2no KALF _85 BATCH LIQUID EFFLUENTS RADWASTE 3rd Total 4th Total Unit Quarter
% Error Quarter
% Error A.
Fission and Activation Products 1.
Total Releases Curtes 5.80E-01 11.0E+01 3.88E-01 11.0+01 2.
Average Diluted Cond. During Period of All Identified i
Isotopes pCi/ml 3.77E-07 4.88E-07 3.
Percent of Applicable Limit 3.03E+00 3.30E-01 (N MPC < 1)
I 1st NOTE:
Percent of applicable limit is based on identified isotope concentration after dilution, related to their appropriate MFC concentration and sum of all the isotope fractions com-pared to 1.0.
B.
Tritium 1.
Total Release Curies 1.09E+02 tl.0E+01 1.47E+02 11.0E+01 2.
Average Diluted Cond. During pCi/ml 7.09E-05 1.85E-04 Period 3.
Percent of Applicable Limit 2.36E+00 6.16E+00 (3.0E-03 pCi/al) i C.
Dissolved and Entrained Gases t
1.
Total Release Curtes 2.34E-01 t!.5E+01 2.69E-03 it.5E+01 6
2.
Average Diluted Cond. During pCi/ml 1.52E-07 3.38E-09 Period 3.
Percent of Applicable Limit 7.61E-02 1.69E-03 (2.0E-04 pei/ml)
D.
Gross Alpha Radioactivity 1.
Total Release Curies 0.00E-01 11.5E+01 0.00E-01
+1.5E+01 E.
Volume of Waste Release L
(Before Dilution)
Liters 7.01E+06 11.0E+01 5.77E+06 tl.0E+01 i
F.
Volume of Dilution Water for Liters 1.53E+09
+1.0E+01 7.90E+08 it.0E+01 Period i
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EFTLUENT AND WASTE DISPOSAL SEMIANWUAL REPORT 2nd HALF 85 BATCH LIQUID RELEASES RADWASTE 3rd 4th G.
Isotope ' Summa ry U
Quarter 0:uarter 3
Required by Technical Specifications 1.
Phosphorus-32 Ci 5.93E-02 W E-03 2.
Manganese 54 C1 2.16E-02 4.96E-03 3.
Iron-55 C1 3.83E 01 2.50E-02 4.
Cobalt-58 C1 2.48E 01 2.32E-02 5.
Iron-59 Ci 5.01E-03 0.0dE-01 6.
Cobalt-60 Ci 1.41E-01 2.87E-02 7.
Zinc-65 Ci 3.07E-09 2.62E-03 8.
Strontius -89 Cl 7.47E-04 0.00E-01 9.
Strontium-90 Ci 0.00E-01 0,.00E-01 10.
Molybdenum-99 Ci 0.00E-01 0.00E-01 11.
Iodine-131 Ci 9.65E-03 1.86E-04 12.
Cesium-134 C1 1.24E-02 3.57E-03 13.
Cesium-137 C1 1.75E-02 4.88E-03 14.
Cerium-141 Ci 0.00E-01 0.00E 01 15.
Cerium-144 Ci 5.64E-04 0.00E-01 Ot.hers (Specify)
- 16. Niobium-95 C1 8.17E-03 7.92E-04 17.
Zirconium-95 Ci 3.56E-01 1.08E-03 18.
Chromium-51 C1 2.58E-02 7.16E-04 1
l
- 19. Cobalt-57 Ci 2.73E 03 7.82E-05 20.
Silver !!Om Ci 2.86E 03 0.00E-01 i
21.
Iodine-133 Ci 5.47E 04 0.00E-01 l
j l i+
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~ EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPOdT i
2nd liA!J 85
[
BATCH L1 QUID RELEASES RADWASTE G.
Isotope Summary Unit Quarter _
Quarter i
22.
Yttrium-91 Ci 2.64E-03 0.00E,01
- 23. Tellurium-132 C1 1.31E 05 1.67E-06 24.
Ruthenium-106 Ci 9.37E-05 9.48E-05
[
f
- 25. Niobium-97 Ci 3.57E-04 0.00E-01
}
- 26. Antimony-125 Ci 3.64E-04 0.00E-01
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27.
Strontium-92 Ci 3.00E-04 0.00E-01 i
- 28. Rubidium-86 Ci 0.00E-01 6.32E !
Total for Period Ci 9.47E 01 9.70E 02 i
a Dissolved Gases j
I Required by Technical Specifications
[
1.
Krypton-87 Ci 0.00E-01 0.00E-01 il 2.
Krypton-88 Ci 0.00E-01 0.00E-01 j
3.
Xenon-133 C1 2.29E-01 0.000-01 i
j 4.
Xenon-133M Ci 2 29E-03 0.00E-01 j
5, Xenon-135 C1 2.06E-03 0.00E-01 l
l 6.
Xenon-138 Ci 0.00E-01 0.00E-0]__
f 1
i j
Other (Specify)
(
.i 7.
Argon-41 Ci 2.33E-04 1.17E-06 l
t j
8.
Krypton-135m Ci 0.00E 01 7.55E-05 f
i 9.
Krypton-SS Ci 0.00E 01 2.61E-03 l
10.
Krypton-85m Ci 0.00E-01 1.16E-06 f
]
- 11. Xenon-138 Ci 1.47E-04 0.00E-01 i
Total for Period Ci 2.34E-01 2.69E-03 i
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. _., - -. -,, - _ -. _ _ _ _.. ~. -,. _,
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 2nd HALF 85 BATCH LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES CONDENSATE REGENERANTS 3rd Totel 4th Total Unit Quarter
% Error Quarter
% Error A;
Fission and Activation Products 1.
Total Releases Curies 6.98E-02 11.0E+01 1.75E-05 1.0E+01 2.
Average Diluted Cond. During Period of All Identified pCi/ml 7.67E-07 2.56E-07 Isotopes 3.
Percent of Applicabla Limit 8.02E+00 2.07E+00 (N MPC 5 1)
I 1=1 NOTE:
Percent of applicable limit is based on identified isotope concen-tration after dilution, related to their appropriate MPC concen-tration and sum of all the isotope fractions compared to 1.0.
B.
Tritium 1.
Total Release Curies 7.82E-01 11.0E+01 1.45E-03 1.10E+01 2.
Average Diluted Cond. During Period pCi/ml 8.59E-06 2.12E-05 3.
Percent of Applicable Limit (3.0E-03 pCi/ml) 2.86E-01 7.07E-01 C.
Dissolved and Entrained Gases 1.
Total Release Curies 5.22E-04 11.5E+01 0.00E-01 11.5E+01 2.
Average Diluted Conc. During Period pCi/ml 5.74E-09 0.00E-01 3.
Percent of Applicable Limit (2.0E-04 pCi/ml) 2.b,2-03 0.00E-01 D.
Gross Alpha Radioactivity 1.
Total Release Curies 0.00E-01 11.5E+01 0.00E-01 11.5E+01 E.
Volume of Waste Release (Before Dilution)
Liters 1.42E+7
!1.0E+01 6.84E+04 1.0E+01 F.
Volume of Dilution Water For Period Liters 7.68E+7 11.0E+01 0.00E-01 11.0E+01 (if applicable)
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tg EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 2nd RALF 85 BATCH L1 QUID RELEASES CONDENSATE REGERANTS 3rd 4th D
G.
Isotope Summary Unit Quarter Quarter Required by Technical Specifications 1.
Phosphorus-32 Ci 0.00E-01,_
0.00E-01 2.
Manganese-54 Ci 1.29E-03 0.00E-01 3.
Iron-55 Ci 0.00E-01 0.00E-01 4.
Cobalt-58 Ci 2.35E-03 0.00E-01 5.
Iron-59 Ci 0.00E-01 0.00E-01 6.
Cobalt-60 Ci 1.12E-03 0.00E-01 7.
Zine-65 Ci 0.00E-01 0.00E-01 8.
Strontium-89 Ci 0.00E-01 0.00E-01 9.
Strontium-90 Ci 0.0GE-01 0.00E-01 10.
Molybdenum-99 Ci 0.00E-01 0.00E-01 11.
Iodine-131 Ci 5.70E-04 0.00E-01 12.
Cesium-13 Ci 3.33E-02 8.94E-06 13.
Cesium-137 Ci 3.09E-02 8.52E-06 14.
Cerium-141 Ci 0.00E-01 0.00E-01 15.
Cerium-144 Ci 5.35E-05 0.00E-01 Others (Specify) 16.
Sodium-24 Ci 1.07E-05 0.00E-01 17.
Niobium-95 Ci 1.60E-04 0.00E-01 18.
Iodine-133 Ci 6.67E-05 0.00E-01 Total for Period Ci 6.98E-02 1.75E-95 Sb
7 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 2nd HALF 85 BATCH LIQUID' RELEASES CONDENSATE REGENERANTS.
3rd
' 4th G.
Isotope Summary Unit Quarter quarter Dissolved Gases Required by Technical Specifications 1.
Krypton-87 Ci 0.00E-01 0.00E-01 2.
Krypton-88 Ci 0.00E-01 0.00E-01 3.
Xenon-133 Ci 1.07E-04 0.00E-01 4.
Xenon-133m Ci 0.00E-01 0.00E-01 5.
Xenon-135 Ci 1.79E-05 0.00E-01 6.
Xenon-138 Ci 0.00E-01 0.00E-01 Other (Specify) 7.
Xe-131m Ci 3.98E-04 0.00E-01 s
Total for Period Ci 5.23E-04 0.00E-01
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 2nd HALF 85 CONTINUOUS LIQUID RELEASE TURBINE BUILDIN0 SUMP 3rd Total 4th Total Unit Qusrter
% Error Quarter
% Error A.
Fission and Activation Products y, e r.JD r
."W
==
Ng 1.
Total Release Curies 2.;0: 34L !1.0E+01 9.67E-04 1.0E+01 2.
Average Diluted Conc. During Period of all Identified pCi/ml 8.19E-08 2.59E-09 Isotopes 3.
Percent of Applicable Limit 7.80E-01 2.09E-02 (N MPC $ 1)
I 1 = 1 NOTE:
Percent of applicable limit is based on identified isotope concentration after dilution, related to their appropriate MPC concentration and sum of all the isotope fractions com-pared to 1.0.
B.
Tritium 1.
Total Release Curies 1.14E+00 11.0E+01 9.09E-02 11.0E+01 2.
Average Diluted Cond.
During Period pCi/ml 3.62E-06 2.44E-07 3.
Percent of Applicable Limit,(3.0E-03 pC/iml) 1.21E-01 8.12E-03 C.
Dissolved and Entrained Gases 1.
Total Release Curies 8.06E-03 11.5E+01 2.88E-03 11.5E+01 2.
Average Diluted Conc.
During Period pCi/ml 2.56E-08 7.72E-09 3.
Percent of Applicable Limit (2.0E-04 pCi/ml) 1.28E-02 3.86E-03 D.
Gross Alpha Radioactivity 1.
Total Release Curies 0.00E-01 1.5E+01 0.00E-01 11.5E+01 E.
Volume of Waste Release (No Dilution)
Liters 3.15E+08 11.0E+01 3.73E+08 11.0E+01 EFFLUENT AND WASTE DISPOSAL SENIANNUAL REPORT 2nd RALF 85 i
CONTINUOUS LIQUID RELEASES Turbine Building Sump 3rd 4th G.
Isotope Summary Unit Quarter Quarter Required by Technical Specifications 1.
Phosphorus-32 Ci 0.00E-01 0.005-01 2.
Manganese-54 Ci 0.00E-01 0.00E-01 3.
Iron-55 Ci 0.00E-01 0.00E-01 4.
Cobalt-58 Ci 0.00E-01 0.00E-01 5.
Iron-59 Ci 0.00E-01__
0.00E-01 6.
Cobalt-60 Ci 0.00E-01 0.00E-01 7.
Zinc-65 Ci 0.00E-01 0.00E-01 8.
Strontium-89 Ci 0.00E-01 0.00E-01 9.
Strontium-90 Ci 0.00E-01 0.00E-01 10.
Molybdenum Ci 0.00E-01 0.00E-01 11.
Iodine-131 Ci 6.64E-04 0.00E.01 12.
Cesium-134 Ci 0.CJE-01 4.85E-04 13.
Cesium-137 Ci 9.12E-04,,
4.82E-04 14.
Cerium-141 Ci 1.15E-02 0.00E-01 15.
Cerium-144 Ci 5.60E-04 0.00E-01 Others (Specify) 16.
Tellurium-132 Ci 1.44E-04 0.00E-01 Total for Period Ci 1.3RE-02 9.67E-04 1 i
i
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 2nd RALF 85 CONTINUOUS LIQUID RELEASES TURBINE BUILDING SUMP 3rd 4th G.
Isotope Summary Unit Quarter Quarter Dissolved Gases Required by Technical Specifications 1.
Krypton-87 Ci 0.00E-01 0.00E-01 2.
Krypton-88 Ci 0.00E-01 0.00E-01 3.
Xenon-133 Ci 3.99E-03 1.30E-03 4.
Xenon-133m Ci 0.00E-01 1.10E-03 5.
Xenon-135 Ci 3.31E-05 3.27E-04 6.
Xenon-138 Ci 0.00E-01 0.00E-01 Other (Specify) 7.
Krypton-85m Ci 0.00E-01 3.27E-04 8.
Xenon-131m Ci 4.04E-03 0.00E-01 Total for Period Ci 8.06E-03 3.05E-03 t {
I EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 2nd HALF 85 BATCH LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES STEAM GENERATOR BLOWDOWN 3rd Total 4th Total Unit Quarter
% Error Quarter
% Error A.
Fission and Activation Products 1.
Total Releases Curies 8.51E-03 1.0E+01 0.00E-01 11.0E+01 2.
Average Diluted Conc. During Period of All Identified Isotopes pCi/ml 1.25E-07 0.00E-01 3.
Percent of Applicable Limit (N MPC $ 1) 1.99E+01 0.00E-01 I
1=1 NOTE:
Percent of applicable limit is baded on identified isotope concen-tration af ter dilution, related to their appropriate MPC concentra-tion and sum of all the isotope fractions compared to 1.0.
3.
Tritium 1.
Total Release Curies 5.41E-02 1.0E+01 0.00E-01 11.0E+01 2.
Average Diluted Conc.
During Period pCi/ml 7.95E-07 0.00E-01 3.
Percent of Applicable Limit (3.0E-03 pCi/ml) 2.65E-02 0.00E-01 C.
Dissolved and Entrained Gases 1.
Total Release Curies 6.53E-04 1.5E+01 0.00E-01 1.5E+01 2.
Average Diluted Conc.
During Period pCi/ml 9.59E-09 0.00E-01 3.
Percent of Applicable Limit (2.0E-04 pCi/ml) 4.80E-03 0.00E-01 D.
Gross Alpha Radioactivity 1.
Total Release Curies 0.00E-01 11.5E+01 0.00E-01 1.5E+01 E.
Volume of Waste Release (Before Dilution)
Liters 1.88E+06 11.0E+01 0.00E-01 11.0E+01 F.
Volume of Dilution Water for Period Liters 6.62E+07 11.0E+01 0.00E-01 11.0E+01 l
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 2nd KALF 85 BATCH LIQUID PILEASES STEAM GENERATOR BLOWDOWN 3rd 4th G.
Isotope Summary Unit Quarter Quarter Required by Technical Specifications 1.
Phosphorus-32 Ci 6.22E-05 0.00E-01 2.
Manganese-54 Ci 2.39E-04 0.00E-01 3.
Iron-55 Ci 0.00E-01 0.00E-01 4.
Cobalt-58 Ci 2.15E-04 0.00E-01 5.
Iron-59 Ci 0.00E-01 0.00E-01 6.
Cobalt-60 Ci 1.09E-04 0.00E-01 7.
Zinc-65 Ci 0.00E-01 0.00E-01 8.
Strontium-89 Ci 1.47E-04 0.00E-01 9.
Strontium-90 Ci 0.00E-01 0.00E-01 10.
Molybdenum-99 Ci 0.00E-01 0.00E-01 11.
Iodine-131 Ci 3.97E-03 0.00E-01 12.
Cesium-134 Ci 1.79E-03 0.00E-01 13.
Cesium-137 Ci 1.95E-03 0.00E-01 14.
Cerium '.41 Ci 0.00E-01 0.00E-01 l
l 15.
Cerium-144 Ci 0.00E-01 0.00E-01 1
Others (specify) 16.
Cesium-136 Ci 1.21E-04 0.00E-01 Total for Period Ci 8.60E-03 0.00E-01
.4 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 2nd HALF 85 BATCH LIQUID RELEASES STEAM GENERATOR BLOWDOWN 3rd 4th G.
Isotope Susunary Unit Quarter Quarter Dissolved Gases Required by Technical Specifications 1.
Krypton-87 Ci 0.00E-01 0.00E-01 2.
Krypton-88 Ci 0.00E-01 0.00E-01 3.
Xenon-133 Ci 0.00E-01 0.00E-01 4.
Xenon-133m Ci 0.00E-01 0.00E-01 5.
Xenon-135 Ci 0.00E-01 0.00E-01 6.
Xenon-138 Ci 0.00E-01 0.00E-01 Others (Specify) l Total for Period Ci 0.00E-01 0.00E-01 1
i i
.}7
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 2nd RALF 85
^
GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES (0round Level Releases) 3rd Total 4th Total Summation of All Releases Unit Quarter 5 Error Quarter
% Error A.
Fission and Activation Products 1.
Total Releases Ci 8.21E+02 tl.0E+01 1.72E+00 tl.0E+01 2.
Average Release Rate for Period pCi/see 1.03E+02 2.16E-01 3.
Percent of Technical Spec-ification Limit 3.27E-02 2.16E-05 B.
Iodines 1.
Total Iodine-131 Ci 5.25E-04 11.0E+01 6.05E-05 1.0E+01 2.
Average Release Rate for pCi/sec 6.60E-05 7.61E-06 Period 3.
Percent of Technical Spec-ification Limit (7.80E-02 8.57E-02 9.76E 03 pCi/sec)
C.
Particulates 1.
Particulates with half-Ci 3.03E-04 11.5E+01 1.89E-04 11.5E+01 lives > 8 days 2.
Average Release Rate for pCi/sec 3.81E-05 2.38E-05 Period 3.
Percent of Technical Spec-ification Limit 6.38E-04 4.00E-04 4.
Gross Alpha Radioactivity Ci 0.00E-01 0.00E-01 D.
Tritium 1.
Total Release Ci 8.72E+00 11.0E+01 2.17E+01 11.0E+01 2.
Average Release Rate pCi/see 1.10E+00 2.73E+00 for Period 3.
Percent of Technical Spec-ification Limit (3.6E+04 3.06E-03 7.58E-03 pCi/sec)
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 2nd RALF 85 GASEOUS EFFLUENTS GROUND LEVEL RELEASE (GROUND LEVEL RELEASES)
Continuous Mode Batch Mode 3rd 4th 3rd 4th Unit Quarter Quarter Quarter Quarter E.
Fission Gases Required by Techical Specifications
- 1. Krypton-87 Ci 2.59E-01 0.00E-01 0.00E-01 0.00E-01
- 2. Krypton-88 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01
- 3. Xenon-133 Ci 3.80E+02 0.00E-01 4.26E+02 0.00E-01
- 4. Xenon-133m Ci 0.00E-01 0.00E-01 6.02E+00 0.00E-01
- 5. Xenon-135 Ci 1.34E+00 0.00E-01 4.89E+00 0.00E-01
- 6. Xenon-138 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Others (Specify) 7.
Krypton-85m Ci 2.03E-01 0.00E-01 6.19E-02 0.00E-01 8.
Krypton-85 Ci 0.00E-01 0.00E-01 4.27E-01 0.00E-01 9.
Xenon-131M Ci 0.00E-01 0.00E-01 0.00E-01 1.72E+00 10.
Argon-41 Ci 0.00E-01 0.00E-01 1.95E-01 0.00E-01 Total for Period Ci 3.82E+02 0.00E-01 4.38E+02 1.72E+00 F.
Iodines Required by Technical Specifications
- 1. Iodine-131 Ci 0.00E-01 0.00E-01 5.27E-04 6.05E-05
- 2. Iodine-133 Ci 0.00E-01 0.00E-01 2.66E-04 0.00E-01 e
- 3. Iodine-135 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Total for Period Ci 0.00E-01 0.00E-01 7.93E-04 6.05E-05 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 4
2nd HALF 85 GASEOUS EFFLUENTS GROUND LEVEL RELEASE Continuous Mode Batch Mode 3rd 4th 3rd 4th G.
Particulates Unit Quarter Quarter Quarter Quarter Required by Technical Specifications i
- 1. Manganese-54 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01
- 2. Cobalt-58 Ci 1.79E-04 1.16E-04 0.00E-01 0.00E-01
- 3. Iron-59 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01
- 4. Cobalt-60 Ci 5.94E-05 6.86E-05 0.00E-01 0.00E-01
- 5. Zine-65 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01
- 6. Strontium-89 Ci 1.26E-09 0.00E-01 0.00E-01 0.00E-01
- 7. Strontium-90 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01
- 8. Molybdenum-99 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01
- 9. Cesium-134 Ci 2.80E-05 0.00E-01 0.00E-01 0.00E-01
- 10. Cesium-137 Ci 3.61E-05 3.57E-06 0.00E-01 0.00E-01
- 11. Cerium-141 Ci 0.00E-01 4.26E-08 0.00E-01 0.00E-01
- 12. Cerium-144 Ci 0.00E-01 8.21E-07 0.00E-01 0.00E-01 Others (specify) 13.
Cobalt-57 Ci 3.10E-09 5.71E-08 0.00E-01 0.00E-01 Total for Period Ci 3.03E-04 1.89E-04 0.00E-01 0.00E-01
-20
a EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 2nd HALF 85 SOLID WASTE (RADIOACTI'IE) SHIPMENTS A.
Solid Waste Shipped Of f-Site for Burial or Disposal (not Irradiated Fuel) 6 Month Est. Tol.
1.
Type of Waste Unit Period Error %
3 a.
Spent resins, filter sludges, m
1.31E+02 1.50E+01 evaporator bottoms, etc.
Ci 1.02E+03 1.50E+01 b.
Dry Active Waste, Compressible 3
Waste m
1.96E+02 1.50E+01 Contaminated equip., etc.
Ci 6.37E+01 1.50E+01 3
c.
Irradiated Components, m
None Control Rods, etc.
Ci None N/A 3
d.
Other (describe) m None C1 None N/A 2.
Estimate of major nuclide composition (by type of waste) a.
Spent resin, filter sludges, and evaporator bottoms, etc.
(nuclides determined by measurement)
Curies Percent a.
1.
Tritium 1.34E+01 1.31E+00 2.
Carbon-14 2.85E+00 2.78E-01 3.
Chromium-51 1.12E+00 1.09E-01 4.
Manganese-54 6.54E+01 6.39E+00 5.
Cobalt-58 3.04E+02 2.97E+01 6.
Iron-59 1.99E-01 1.94E-02 l
7.
Cobalt-60 3.43E+02 3.35E+01 I
l 8.
Nickel-63 1.01E+02 9.87E+00 9.
Strontium-90 7.57E-02 7.40E-03 10.
Zirconium-95 1.19E-01 1.16E-02 11.
Niobium-95 2.59E-01 2.53E-02 12.
Iodine-131 4.79E-01 3.68E-02 13.
Cesium-134 8.14E+01 7.96E+00 14.
Cesium-137 9.81E+01 9.59E+00 15.
Other Nuclides 1.16E+01 1.13E+00 21-
+
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 2nd HALF 85 SOLID WASTE (RADI0 ACTIVE) SHIPMENTS 2.
Estimate of Major Nuclide Composition (by type of waste)
(continued) b.
Dry Active Waste, dry compressible waste, contaminated equipment, etc ;
(nuclides determined by estimate)
Curies Percent 1.
Tritium 3.60E-00 5.65E+00 2.
Carbon-14 1.09E-01 1.71E-01 3.
Chromium-51 6.74E-01 1.06E+00 4.
Iron-55 3.85E+01 6.04E+01 5.
Manganese-54 1.36E-01 2.14E-01 6.
Cobalt-58 1.16E+01 2.53E+01 7.
Iron-59 3.35E-01 5.26E-01 8.
Cobalt-60 2.61E+00 4.10E+00 9.
Strontium-90 2.24E-03 3.52E-03 10.
Zirconium-95 3.87E-02 6.08E-02 11.
Niobium-95 1.54E-02 2.42E-02 12.
Iodine-131 4.23E-02 6.64E-02 13.
Cesium-134 1.97E-01 3.09E-01 14.
Cesium-137 1.63E-01 2.56E-01 15.
Other Nuclides 1.20E+00 1.88E+00 c.
Irradiated Components N/A N/A d.
Other (describe)
N/A N/A.
r-o 1
1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 2nd HALF 85 SOLID WASTE (RADIOACTIVE) SHIPMENTS 3.
Solid Waste Disposition Number of Shipments Type Quantity Mode of Transportation Destination a)
Resin, filter sludges, evaporator bottoms, etc.
18 LSA Motor Freight Barnwell, South Carolin 2
LSA Motor Freight Richland, Washington Number of Shipments Type Quantity Mode of Transportation Destination b)
Raw, dry active vaste, compressible contaminated equipment, etc.
8 LSA Motor Freight Richland, Washington Number of Shipments Type Quantity Mode of Transportaion Destination c)
Irradiated components, control rods, etc.
Number of Shipments Type Quantity Mode of Transportaion Destination d)
Other (describe)
Number of Shipments Type Quantity Mode of Transportaion Destinati_on 4.
Irradiated Fuel Shipments (Disposition)
Number of Shipments Type Quantity Mode of Transportaion Destination None N/A N/A N/A 5.
Solidification of Waste Was solidification performed?
X Yes No If yes, solidification media:
Cement Changes were made to the Process Control Programs as documented in Sequoyah Nuclear Plant Radwaste Handling and Shipping Instruction 05..