ML20071D169
| ML20071D169 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 08/31/1981 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20071D165 | List: |
| References | |
| NUDOCS 8303090220 | |
| Download: ML20071D169 (104) | |
Text
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SEQUOYAH NUCLEAR PLANT UNITS 1 & 2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Supplemental Information First Half 1981 F303090220 810831 PDR ADOCK 05000327 R
PDR 2
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION FIRST HALF 1981 1.
Regulatory Limits a.
Fission and Activation Gases:
(1) Instantaneous -
$ 2.2E+04 pCi/sec Auxiliary Building 5 1.16E+04 pCi/sec Condenser Vacuum Exhaust i 1.47E+03 pCi/sec Service Building 5 4.0E+02 pCi/sec NOTE: Limits established by TVA's Radiological Hygiene Branch such that technical specifications will not be violated unless the total plant release rate exceeds the sum of the individual vent re-lease rates as noted above.
- b. & c.
Iodines and particulates, half-lives >8 days (1)
Instantaneous -
Shield Building 5 6.2E-02 pCi/cc Auxiliary Building 5 6.1E-01 pCi/cc NOTE:
Limits established by TVA's Radiological Hygiene Branch such that technical specifications will not be violated unless the total plant release rate exceeds the sum of the individual vent release rates as noted above.
d.
Liquid effluent:
I MPC 5 1.0 (ref. 10 CFR 20, Appendix B, note 3C, Table II, column 2).
e.
Tritium (1) Liquid - $ 3.0E-3 pCI/cc (ref. 10 CFR 12 Table II, column 2)
(2) Airborne -
(ref. 10 CFR 20, Table I, column 2)
Shield Building i 2.0E-07 pCi/cc (Ref. 10 CFR 20, Table II, Column 1)
Auxiliary Building i 2.0E-07 pCi/cc (Ref. 10 CFR 20, Table II, Column 1)
Service Building 5 9.0 pCi/sec (Established by Radiological Hygiene Branch)
Condenser Vacuum Exhaust 5 4.46E+02 pCi/sec (Established by Radiological Hygiene Branch)._
r EFFLUENr AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION (CONTINUED)
FIRST RALF 1981 2.
Maximum Permissible Concentrations a.
Fission and Activation Gases: Not Applicable b.
Iodines: Not Applicable Particulates, half-lives >8 days: Not Applicable c.
d.
Liquid effluents:
sum of indv. MPC ratios i 1.0 (ref. 10 CFR 20, Appendix B, note 1) 3.
Average Energy - Not Applicable 4.
Measurements and Approximations of Total Radioactivity a.,
- b. & c.'
Fission and Activation Gases, Iodines, and Particulates:
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 exisusts are taken and analyzed at least monthly to detenmine the quantity of noble gas activity released for the month based on the average vent flowrates re-corded for the sampling period. Also, noble gas samples are collected and evaluated for the shield and auxiliary buildings following 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 ex-haust are determined and recorded twice a shift.
The quantity of noble gases released through the shield build-ing 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 each 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 gamma isotopte analyses.
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION FIRST !IALF 1981 4.
Measurements and Approximations of Total Radioactivity (Continued)
- b. & c.
Iodines and Particulates Iodine and particulate activity is continuously monitored and re-corded.
Charcoal and particulate samples are taken frcm the shield auxiliary building exhausts and analyzed at least weekly to deter-mine 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 7 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 average vent flowrates recorded for the sampling period and acti-vity concentration.
The vent flowrates form the shield and auxiliary buildings are recorded twice a shift.
The total particulate and iodine activity released for the month is then determined by summing all of the activity released from the shield and auxiliary buildup for all sampling periods.
Allowance is made for a plus or minus one sigma counting error associated with the gamma isotopic analyses, d.
Liquid Effluents - Fission and Activation Products - Dissolved and Entrained Gases (1) Batch - Radwaste Total gamma isotopic activity concentrations are determined on each batch of liquid effluent prior to release.
The total curie content of a released batch is determined by summing 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 of each batch discharged during the month.
A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION FIRST HALF 1981 4.
Measurements and Approximations of Total Radioactivity (Continued)
(2) Batch - Condensate Demineralizer System Total gamma isotopic activity concentrations are determiaed on each batch of liquid effluent during the release. The sample for analysis is collected at 20% level of each tank.
A small number of samples have indicated the presence of activity which is being attributed to contamination of sampling and analysis containers and not as primary-to-secondary leaking. This problem is now being addressed by a complete separation and disposal of all sampling and analysis containers following their use.
When a primary-to-secondary leak has been affirmed, the total curie content of a released batch will be determined prior to release by summing each nuclide's concentration and multiplying by the total volume discharged.
The total activity released during the month will be deter-mined by summing the activity content of each batch dis-charged during the month.
(3) Continuous Releases - Turbine Building Sump and Steam Generator Blowdown The turbine building sump and steam generator blowdown (when going to the cooling tower blowdown) are sampled on a daily basis. A composite sample is then prepared proportionate to the daily release volume and analyzed weekly. The presence of activity reflected in this report is also being attributed to sample contamination during analysis.
When a primary-to-secondary leak has been affirmed the total curie content of a release period will be determined by summing each nuclide's concentration and multiplying by the total volume discharged. The total activity released during the month will then be determined by summing the content of each weekly composite.
Liquid Effluents - Gross Alpha, P-32 and H-3 e.
A monthly composite of all four release points is prep'ared and analyzed for gross alpha, P-32 and H-3.
The monthly composite is prepared from each batch or release period proportionate to volume released. A weighted decay correction is applied to the P-32 analysis only.
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION FIRST HALF 1981 4.
Measurements and Appreximations of Total Radioactivity (Continued) f.
Liquid Effluents - SR-89 and SR-90, Fe-55 A quarterly composite of all four release points is prepared from the monthly composite and analyzed for SR-89, SR-90 and Fe-55.
A weighted decay correction is applied to the SR-89 and SR-90 analysis. The midpoint of the quarter is used in the analysis of Fe-55. 4 n
.m.-
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION FIRST HALF 1981 4.
Measurements and Approximations of Total Radioactivity (Continued)
Allowance is made for plus or minus one sigma counting error associated with the total gamma isotopic analyses.
5.
Batch Value Units 1st 2nd Quarter Quarter a.
Liquid (1) Number of batches released 302 400 Each (2) Total time period for batch releases 38,581 61,827 Minutes (3) Maximum time period for a batch release 1,743 456 Minutes (4) Average time period for batch releases 127 156 Minutes (5) Minimum time period for a batch release 15 22 Minutes (6) Average stream flow during periods of effluent into a flowing stream:
(a)
(a)
(a) See Radiological Hygiene Branch's portion of semi-annual effluent release report.
b.
Gaseous (1) Number of batches released 6
19 Each (2) Total time period'for batch releases 7,488 17,078 Minutes (3) Maximum time period for a batch release 3,798 1,440 Minutes (4) Average time period for batch releases 1,248 899 Minutes (5) Minimum time period for a batch release 80 60 Minutes 6.
Abnormal Releases a.
Liquid (1) Number of Releases 0
0 (2) Total Activity Released 0.00E-01 0.00E-01 Ci. -.
.=
1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION FIRST HALF 1981 7
6.
Abnormal Releases (Continued) b.
Gaseous (1) Number of Releases 0
0 (2) Total Activity Released 0.00E-01 0.00E-01 Ci E
.I e
i I
4' i
)
l I
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF 1981 BATCH LIQUID EFFLUENTS - RADWASTE Ist Total 2nd Total Unit Quarter
% Error Quarter
% Error A.
Fission and Activation Products 1.
Total Releases Curies 1.25E+00
+1.0E+01 1.60E-01 11.0E+01 2.
Average Diluted Conc. During Period of All Identified Isotopes pCi/ml 1.12E-06 9.04E-08 3.
Percent of Applicable Limit 5.18E+00 2.29E+00 (N MPC < 1) i=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 3.96E+00 11.0E+01 2.29E+01 1.0E+01 2.
Average Diluted Conc. During Period pCi/ml 3.55E-06 1.29E-05 3.
Percent of Applicable Limit (3.0E-03 pCi/ml) 1.18E-01 4.31E-01 C.
Dissolved and Entrained Gases 1.
Total Release Curies 8.40E-01
+1.5E+01 1.26E+00 11.5E+01 2.
Average Diluted Conc. During Period pCi/ml 7.53E-07 7.12E-07 3.
Percent of Applicable Limit (2.0E-04 pCi/ml) 3.77E-01 3.56E-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 Rele.ase (Before Dilution)
Liters 6.03E+06
+1.0E+01 9.30E+06
+1.0E+01 F.
Volume of Dilution Water for Period Liters 1.11E+09 11.0E+01 1.76E+09 11.0E+01 - - -
i EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF 1981 BATCH LIQUID RELEASES - RADWASTE l
First Second G.
Isotope Summary Curies Quarter Quarter 1.
Strontium-89 1.62E-03 0.00E-01 2.
Strontium-90 0.00E-01 3.36E-04 3.
Cesium-134 0.00E-01 4.41E-03 4.
Cesium-137 3.02E-05 1.75E-02 5.
Iodine-131 9.90E-03 7.96E-03 6.
Cobalt-58 4.22E-01 2.97E-02 7.
Cobalt-60 3.28E-02 2.60E-03 8.
Iron-59 3.44E-02 1.83E-03 9.
Zinc-65 2.50E-04 1.83E-05 10.
Manganese-54 2.71E-01 6.10E-03 11.
Chromium-51 1.90E-01 2.23E-02 12.
Zirconium-Niobium-95 4.55E-02 1.75E-03 13.
Molybdenum-99 0.00E-01 0.00E-01 14.
Technetium-99m 4.94E-05 9.61E-05 15.
Barium-Lanthanum-140 2.48E-02 1.8.9E-03 16.
Cerium-141 0.00E-01 0.00E-01 17.
Sodium-24 1.01E-04 1.06E-04 18.
Fluorine-18 0.00E-01 0.00E-01 Total for Period 1.03E+00 9.66E-02..
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF 1981 BATCH LIQUID RELEASES - RADWASTE First Second G.
Isotope Summary Curies Quarter Quarter Others (Not Required for Reg. Guide 1.21) 1.
Xenon-133 7.96E-01 1.25E+00 2.
Xenon-135 3.24E-04 1.30E-03
- 3. -Iodine-133 1.84E-03 1.02E-04 4.
Cesium-136 0.00E-01 1.39E-03 5.
Argon-41 7.20E-06 1.29E-06 6.
Xenon-131m 4.32E-02 1.02E-02 7.
Cerium-144 1.72E-02 0.00E-01 8.
Rhodium-105 1.87E-05 1.61E-03 9.
Tellurium-132 0.00E-01 8.15E-07 10.
Tungsten-187 5.02E-03 0.00E-01 11.
Phosphorus-32 1.88E-01 8.19E-03 12.
Iron-55 1.41E-03 5.17E-02 Total for Period 1.05E+00 1.32E+00 T-l
I EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF 1981 i
BATCH LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES CONDENSATE REGENERANTS (TO TURBINE BUILDING SUMP) 1st Total 2nd Total Unit Quarter
% Error Quarter
% Error A.
Fission and Activation Products 1.
Total Releases Curies 1.03E-02 11.0E+01 1.00E-02 11.0E+01 2.
Average Diluted Conc. During Period of All Identified Isotopes pCi/ml 1.04E-06 8.34E-07 3.
Percent of Applicable Limit 3.43E+00 2.78E+00
( MPC < 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 3.27E-02 11.0E+01 0.00E-01 1.0E+01 2.
Average Diluted Conc. During Period pCi/ml 3.30E-06 0.00E-01 3.
Percent of Applicable Limit (3.0E-03 pCi/ml) 1.10E-01 0.00E-01 C.
Dissolved and Entrained Gases 1.
Total Release Curies 9.92E-03 11.5E+01 4.51E-05 11.5E+01 2.
Average Diluted Conc. During Period pCi/ml 1.00E-06 3.76E-09 3.
Percent of Applicable Limit (2.0E-04 pCi/ml) 5.00E-01 1.88E-03 D.
Gross Alpha Radioactivity 1.
Total Release Curies 0.00E-01 11.5E+01 0.00E-01 11.5E+01 E.
Volume of Waste Relg-e (No Dilution)
Liters 9.91E+06 11.0E+01 1.20E+07 11.0E+01 1
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF 1981 BATCH LIQUID RELEASES CONDENSATE REGENERANTS (TO TURBINE BUILDING SUMP)
First Second G.
Isotope Summary Curies Quarter Quarter 1.
Strontium-89 0.00E-01 0.00E-01 2.
Strontium-90 0.00E-01 0.00E-01 3.
Cesium-134 0.00E-01 0.00E-01 4.
Cesium-137 0.00E-01 0.00E-01 5.
Iodine-131 0.00E-01 0.00E-01 6.
Cobalt-58 9.58E-04 0.00E-01 7.
Cobalt-60 6.93E-05 4.54E-06 8.
Iron-59 1.05E-04 0.00E-01 9.
Zinc-65 0.00E-01 0.00E-01 10.
Manganese-54 5.62E-05 0.00E-01 11.
Chromium-51 2.62E-03 0.00E-01 12.
Zirconium-Niobium-95 2.05E-04 0.00E-01
- 13. Molybdenum-99 0.002-01 0.00E-01 14.
Technetium-99m 0.00E-01 0.00E-01 15.
Barium-Lanthanum-140 0.00E-01 0.00E-01 16.
Cerium-141 0.00E-01 0.00E-01 17.
Sodium-241 1.04E-031 1.00E-021 18.
Fluorine-18 0.00E-01 0.00E-01 Total for Period 5.05E-03 1.00E-02 1Special steam generator moisture carryover test. 4
. _, _ - - _ ~ _ _..
i EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF 1981 BATCH LIQUID RELEASES CONDENSATE REGENERANTS (TO TURBINE BUILDING SUMP)
First Second G.
Isotope Summary Curies Quarter Quarter Others (Not Required for Reg. Guide 1.21) 1.
Xenon-133 9.92E-03 4.51E-05 2.
Xenon-135 0.00E-01 0.00E-01 3.
Iodine-133 0.00E-01 0.00E-01 4.
Cesium-136 0.00E-01 0.00E-01 5.
Manganese-56 0.00E-01 0.00E-01 6.
Antimony-122 0.00E-01 0.00E-01 7.
Cerium-144 6.41E-06 0.00E-01
)
8.
Copper-64 0.00E-01 0.00E-01 1
9.
Arsenic-76 0.00E-01 0.00E-01 i
10.
Arsenic-74 0.00E-01 0.00E-01 4
11.
Phosphorus-32 0.00E-01 0.00E-01 12.
Iron-55 5.28E-03 0.00E-01 Total for Period 1.52E-02 4.51E-05 l 1
.m.
U
.__m.
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF 1981-CONTINUOUS LIQUID RELEASES (Turbine Building Sump)
Ist Total 2nd Total Unit Quarter
% Error Quarter
% Error A.
Fission and Activation Products 1.
Total Releases Curies 6.92E-01
+1.0E+01 3.04E-02
+1.0E+01 2.
Average Diluted Conc. During Period of All Identified Isotopes pCi/ml 3.33E-06 6.39E-08 3.
Percent of Applicable Limit 1.99E+00 4.15E+00
({MPC<1) t=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.
1 B.
Tritium 1.
Total Release Curies 1.98E-01
+1.0E+01 2.43E-01 1.0E+01 2.
Average Diluted Conc. During Period pCi/ml 9.52E-07 5.11E-07 3.
Percent of Applicable Limit (3.0E-03 pCi/ml) 3.17E-02 1.70E-02 C.
Dissolved and Entrained Gases 1.
Total Release Curies 0.00E-01 11.5E+01 1.61E-02 11.5E+01 2.
Average Diluted Conc. During Period pCi/ml 0.00E-01 3.38E-08 3.
Percent of Applicable Limit (2.0E-04 pCi/ml) 0.00E-01 1.69E-02 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 (No Dilution)
Liters 2.08E+08
+1.0E+01 4.76E+08
+1.0E+01 l
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORI FIRST HALF 1981 CONTIN 00US LIQUID RELEASES (Turbine Building Sump)
First Second G.
Isotope Summary Curies Quarter Quarter 1.
Strontium-89 0.00E-01 0.00E-01 2.
Strontium-90 0.00E-01 0.00E-01 3.
Cesium-134 0.00E-01 0.00E-01 4.
Cesium-137 0.00E-01 3.16E-03 5.
Iodine-131 0.00E-01 5.83E-03 6.
Cobalt-58 2.71E-01 1.51E-02 7.
Cobalt-60 0.00E-01 0.00E-01 8.
Iron-59 0.00E-01 0.00E-01 9.
Zinc-65 0.00E-01 0.00E-01 10.
Manganese-54 0.00E-01 6.30E-03 11.
Chromium-51 3.73E-01 0.00E-01 12.
Zirconium-Niobium-95 2.88E-02 0.00E-01 13.
Molybdenum-99 0.00E-01 0.00E-01 14.
Technetium-99m 0.00E-01 0.00E-01 15.
Barium-Lanthanum-140 0.00E-01 0.00E-01 16.
Cerium-141(I) 0.00E-01 0.00E-01 17.
Sodium-24 0.00E-01 0.00E-01 18.
Fluorine-18 0.00E-01 0.00E-01 Total for Period 6.73E-01 3.04E-02 l
1 ;
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF 1981 CONTINUOUS LIQUID RELEASES (Turbine Building Sump)
First
'Second G.
Isotope Summary Curies Quarter Quarter Others (Not Required for Reg. Guide 1.21) 1.
Xenon-133 0.00E-01 1.61E-02 2.
Xenon-135 0.00E-01 0.00E-01 3.
Iodine-133 0.00E-01 0.00E-01 4.
Cesium-136 0.00E-01 0.00E-01 5.
Manganese-56 0.00E-01 0.00E-01 6.
Antimony-122 0.00E-01 0.00E-01 7.
Antimony-124 0.00E-01 0.00E-01 8.
Copper-64 0.00E-01 0.00E-01 9.
Arsenic-76 0.00E-01 0.00E-01 10.
Arsenic-74 0.00E-01 0.00E-01 2
11.
Phosphorus-32 1.92E-021 0.00E-01 12.
Iron-55 0.00E-01 0.00E-01 Total for Period 1.92E-02 1.61E-02 1Reported in Special Report 81-3,._
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF 1981 BATCH LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES STEAM GENERATOR BLOWDOWN 1st Total 2nd Total Unit Quarter
% Error Quarter
% Error-A.
Fission and Activation Products 1.
Total Releases Curies 8.85E-04
+1.0E+01* 0.00E-01
+1.0E+01 2.
Average Diluted Conc. During Period of All Identified Isotopes pCi/ml 2.44E-08 0.00E-01 3.
Percent of App'licable Limit 1.22E-01 0.00E-01 (N MPC < 1) i=1 NOTE: Percent of applicable limit is based on identified isotope concentration af ter 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 0.00E-01
+1.0E+01 0.00E-01 1.0E+01 2.
Average Diluted Conc. During Period pCi/ml 0.00E-01 0.00E-01 3.
Percent of Applicable Limit (3.0E-03 pCi/ml) 0.00E-01 0.00E-01 C.
Dissolved and Entrained Gases 1.
Total Release Curies 0.00E-01
+1.5E+01 0.00E-01
+1.5E+01 2.
Average Diluted Conc. During Period pCi/ml 0.00E-01 0.00E-01 3.
Percent of Applicable Limit (2.0E-04 pCi/ml) 0.00E-01 0.00E-01 D.
Gross Alpha Radioactivity 1.
Total Release Curies 0.00E-01
+1.5E+01 0.00E-01
+1.5E+01 E.
Volume of Waste Release (Before Dilution)
Liters 3.44E+06
+1.0E+01 5.82E+05 11.0E+01 F.
Volume of Dilution Water for Period Liters 3.29E+07
+1.0E+01 1.27E+07
+1.0E+01 '
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF 1981 BATCH LIQUID RELEASES STEAM GENERATOR BLOWDOWN First Second G.
Isotope Summary Curies Quarter Quarter 1.
Strontium-89 0.00E-01 0.00E-01 2.
Strontium-90 0.00E-01 0.00E-01 3.
Cesium-134 0.00E-01 0.00E-01 4.
Cesium-137 0.00E-01 0.00E-01 t'
5.
Iodine-131 0.00E-01 0.00E-01 6.
Cobalt-58 0.00E-01 0.00E-01 7.
Cobalt-60 0.00E-01 0.0.0E-01 8.
Iron-59 0.00E-01 0.00E-01 9.
Zinc-65 0.00E-01 0.00E-01 10.
Manganese-54 0.00E-01 0.00E-01 11.
Chromium-51 0.00E-01 0.00E-01 12.
Zirconium-Niobium-95 0.00E-01 0.00E-01 13.
Molybdenum-99 0.00E-01 0.00E-01 14.
Technetium-99m 0.00E-01 0.00E-01 15.
Barium-Lanthanum-140 0.00E-01 0.00E-01 16.
Cerium-141 0.00E-01 0.00E-01 17.
Sodium-24 0.00E-01 0.00E-01 18.
Fluorine-18 0.00E-01 0.00E-01 Total for Period 0.00E-01 0.00E-01 ;
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF 1981 BATCH LIQUID RELEASES STEAM GENERATOR BLOWDOWN First Second G.
Isotope Summary Curies Quarter Quarter Others (Not Required for Reg. Guide 1.21) 1.
Xenon-133 0.00E-01 0.00E-01 2.
Xenon-135 0.00E-01 0.00E-01 3.
Iodine-133 0.00E-01 0.00E-01 4.
Cesium-136 0.00E-01 0.00E-01 5.
Manganese-56 0.00E-01 0.00E-01 6.
Antimony-122 0.00E-01 0.00E-01 7.
Antimony-124 0.00E-01 0.00E-01 8.
Copper-64 0.00E-01 0.00E-01 9.
Arsenic-76 0.00E-01 0.00E-01 10.
Arsenic-74 0.00E-01 0.00E-01 11.
Phosphorus-32 8.85E-041 0.00E-01 1
12.
Iron-55 0.00E-01 0.00E-01 Total for Period 8.85E-04 0.00E-01 1Reported in Special Report 81-3.
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF 1981 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES (Ground Level Releases)
Ist Total 2nd Total Summation of All Releases Unit Quarter
% Error Quarter
% Error A.
Fission and Activation Products 1.
Total Releases Ci 4.07E+03 11.0E+01 6.25E+02
+1.0E+01 2.
Averags Release Rate for Period pCi/sec 5.23E+02 7.95E+01 3.
Percentc7TechnicalSpgeifi-cation Lim;t (2.6 x 10 pCi/sec) 2.35E-01 3.57E-02 B.
Iodines 1.
Total Iodine-131 Ci 1.16E-08
+1.0E+01 7.44E-04
+1.0E+01 2.
Average Release Rate for Period pCi/sec 1.49E-09 9.46E-05 3.
Percent of Technical Specifi-cation Limit (1.141E-01 pCi/sec) 6.37E-07 4.05E-02 C.
Particulates 1.
Particulates with half-lives >8 Days Ci 1.16E-02
+1.5E+01 5.45E-04
+1.5E+01 2.
Average Release Rate for Period pCi/sec 1.49E-03 6.93E-05 3.
Percent of Technical Specifi-cation Limit (1.277E-01 pCi/sec) 1.17E+00 5.43E-02 4.
Gross Alpha Radioactivity Ci 0.00E-01 0.00E-01 D.
Tritium 1.
Total Release Ci 2.75E-02
+1.0E+01 1.28E-01
+1.0E+01 2.
Average Release Rate for Period pCi/sec 3.54E-03 1.63E-02 3.
Total Volume Discharged From Site CC 8.43E+14 9.32E+14
+1.0E+01 4.
Percent of Technical Specifi-cation Limit (2.0E-07 pCi/cc) 1.63E-02 6.87E-02.
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF 1981 GASEOUS EFFLUENTS GROUND LEVEL RELEASE First Second 1.
Fission Gases Unit Quarter Quarter Krypton-85 Ci 0.00E-01 0.00E-01 Krypton-85m Ci 0.00E-01 3.86E-01 Krypton-87 Ci 0.00E-01 0.00E-01 Krypton-88 Ci 0.00E-01 0.00E-01 Xenon-133 Ci 4.06E+03 5.56E+02 Xenon-135 Ci 8.30E-02 6.29E+01 Xenon-135m Ci 0.00E-01 0.00E-01 Xenon-138 Ci 0.00E-01 0.00E-01 Others (Specify) Xe-131m Ci 8.23E-00 2.18E-01 Argon-41 Ci 0.00E-01 2.55E+00 Unidentified Xe-133m Ci 4.93E-02 3.39E+00 Total for Period 4.07E+03 6.25E+02 2.
Iodines Iodine-131 Ci 1.16E-08 7.44E-04 Iodine-133 Ci 0.00E-01 1.54E-03 Iodine-135 Ci 0.00E-01 0.00E-01 Total for Period 1.16E-08 2,28E-03. _
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF 1981 GASEOUS EFFLUENTS GROUND LEVEL RELEASE First Second 3.
Particulates Unit Quarter Quarter Strontium-89 Ci 0.00E-01 1.53E-07 Strontium-90 Ci 0.00E-01 2.05E-07 Cesium-134 Ci 0.00E-01
- 0. 00E-i'l Cesium-137 Ci 0.00E-01 0.00s al Barium-140 Ci 0.00E-01 0.00E-01 Zirconium-95 Ci 0.00E-01 0.00E-01 Niobium-95 Ci 0.00E-01 1.96E-13 Cobalt-58 Ci 0.00E-01 6.13E-06 Technetium-99m Ci 1.16E-02 0.00E-01 Chromium-51 Ci 1.22E-05 0.00E-01 Iron-59 Ci 0.00E-01 0.00E-01 Cobalt-60 Ci 0.00E-01 0.00E-01 Others (Specify) Rb-88 Ci 0.00E-01 5.39E-04 Lanthanum-140 Ci 0.00E-01 0.00E-01 Total for Period Ci 1.16E-02 5.45E-04 l __
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF 1981 SOLID WASTE (RADI0 ACTIVE) SHIPMENTS A.
Solid Waste Shipped Off-Site for Burial or Disposal (not Irradiated Fuel)
First Second 1.
Type of Waste Unit Quarter Quarter 3
a.
Spent resins, filter sludges, m
9.03E+00 1.812E+00 evaorator bottoms, etc.
Ci 1.264E-01 6.70E-01 b.
Contaminated equip., etc.
Ci 0.00E+00 0.00E+00 c.
Irradiated Components,_ Control Rods, etc.
None None d.
Other (describe) Boxes and Drums Boxes 0.00E 2.3E+0'1 Drums 0.00E-01 3.47E+02 Ci 0.00E-01 1.83E+00 2.
Estimate of major nuclide composition (by type of waste) 1st 2nd Quarter Quarter a.
1.
Chromium-51 1.08E+01 1.44E+01 1.37E-02 9.81E-02 2.
Zine-65 0.00E-01 0.00E-01 0.00E-01 0.00E-01 3.
Iodine-131 7.00E-01 4.8E+00 8.80E-04 3.27E-02 J
4.
Cesium-137 6.00E-01 3.2E+00 7.5E-04 2.18E-03 5.
Cesium-134 0.00E-01 2.0E-01 0.00E-01 1.2E-03 6.
Cobalt-58 6.71E+01 2.43E+01 8.48E-02 1.66E-01 7.
Cobalt-60 7.4E+00 2.4E+00 9.36E-03 1.64E-02 j
8.
Zirconium-95 0.00E-01 1.1E+00 0.00E-01 7.48E-03 9.
Niobium-95 0.00E-01 1.6E+00 0.00E-01 1.07E-02 4 m-
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF 1981 SOLID WASTE (RADI0 ACTIVE) SHIPMENTS 2.
Estimate of major nuclide composition (by type of waste)-
First Second First Second Q3arter Quarter Unit Quarter Quarter b.
10.
Lanthanum-140 0.00E-01 0.00E-01 0.00E-01 0.00E-01 11.
Antimony-124 0.00E-01 0.00E-01 0.00E-01 0.00E-01
- 12. Strontium-90 0.00E-01 0.00E-01 0.00E-01 0.00E-01 13.
Manganese-54 1.17E+01 3.24E+01 1.48E-02 2.21E-01 14.
Silver-110M 0.00E-01 0.00E-01 0.00E-01 0.00E-01 15.
Iron-59 9.0E-01 1.0E+00 1.13E-03 6.49E-03 16.
Other Nuclides 8.0E-01 1.41E+01 1.02E-03 1.00E-01 c.
Irradiated Components, Control Rods, etc.
1.
Chromium-51 0 00E-01 1.07E+01 0.00E-01 1.96E-01 2.
Zinc-65 0.00E-01 0.00E-01 0.00E-01 0.00E-01 3.
Iodine-131 0.00E-01 7.0E-01 0.00E-01 1.28E-02 4.
Cesium-137 0.00E-01 6.0E-01 0.00E-01 1.09E-02 5.
Cesium-134 0.00E-01 0.00E-01 0.00E-01 0.00E-01 6.
Cobalt-58 0.00E-01 6.72E+01 0.00E-01 1.227E+00 7.
Cobalt-60 0.00E-01 7.4 +00 0.00E-01 1.35E-01 8.
Zirconium-95 0.00E-01 0.00E-01 0.00E-01 0.00E-01 9.' Niobium-95 0.00E-01 0.00E-01 0.00E-01 0.00E-01 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF 1981-SOLID' WASTE (RADIOACTIVE) SHIPMENTS
- 2. Estimate of major nuclide composition (by type of waste)
First Second First Second Quarter Quarter Unit Quarter Quarter d.
10.
Lanthanum-140 0.00E-01 0.00E-01 0.00E-01 0.00E-01 11.
Antimony-124 0.00E-01 0.00E-01 0.00E-01 0.00E-01 12.
Strontium-90 0.00E-01 0.00E-01 0.00E-01 0.00E-01 13.
Manganese-54 0.00E-01 1.17E+01 0.00E-01 2.14E-01 14.
Silver-110M 0.00E-01 0.00E-01 0.00E-01 0.00E-01 15.
Iron-59 0.00E-01 9.0E-01 0.00E-01 1.65E-02 16.
Other Nuclides 0.00E-01 8.0E-01 0.00E-01 1.46E-02 3.
Solid Waste Disposition Number of Shipments Mode of Transportation Destination First Second Quarter Quarter 1
2 Sole Use - Truck Chem Nuclear Systems, Inc.
Barnwell, SC B.
Irradiated Fuel Shipments (Disposition)
Number of Shipments Mode of Transportation Destination First Second Quarter Quarter None None N/A N/A l
i i :
. - ~. -.
D SEQUOYAH NUCLEAR PLANT UNITS 1 & 2 PROCESS CONTROL PROGRAM CHANGES
i The Sequoyah Nuclear Plant Process Control Program (PCP) was first issued and approved by the Commission in February, 1980. At the time of issuance, l
TVA had contracted with ANEFCO, Inc. to provide solidification services for Sequoyah. The PCP thus developed and approved reflected ANEFCO's urea-formaldehyde solidification process.
On July 15, 1980, the Sequoyah Plant Operations Review Committee (PORC) approved a change to the Sequoyah PCP. This change consisted only of the addition of an appendix which further detailed the ANEFC0 process and its use with the Sequoyah radwaste systems. Therefore, since there was no " process" change it was deemed not reportable.
In September, 1980, a contract was negotiated with Chem-Nuclear Systems, Inc. to provide for Sequoyah solidification services.
Chem-Nuclear provided TVA with a PCP upon issuance of the contract but it was not approved by the Plant Operations Review Committee until February,1981.
Between September, 1980 and February, 1981, no solidification was per-formed at Sequoyah. Final documentation, a formality, took until August, 1981 due to a document control handling error.
Attachment A of this report presents the currently approved Sequoyah PCP.
It includes a PCP for the Chem-Nuclear system as well as the ANEFC0 system.
Either system can be used but contractually, only the Chem-Nuclear system will be used until a new contract is let.
The Chem-Nuclear system utilizes the urea-formaldehyde solidification process. Therefore, it has been determined that the change to the Chem-Nuclear system did not reduce the overall conformance of the solidified waste product as compared to the ANEFC0 system previously approved for use by the Commission.
APPENDIX A
--m e
m e.
~
m
Sequoyth Nuclear Plant DISTRIBUTION 1C Plant Master File Plant Superintendent SURVEILLANCE INSTRUCTION Assistant Plant Supt. (Oper.)
Assistant Plant Supt. (Maint.)
Assistant Plant Supt. (H&S)
Administrative ^ Supervisor Maintenance Supervisor (M)
SI h19 Assistant Maintenance Supervisor (M)
Maintenance Supervisor (E)
Assistant Maintenance Supervisor (E)
Maintenance Supervisor (I) 1U. Results Supervisor 1C Operations Supervisor SOLID RADI0 ACTIVE '4ASTE TREATMENT 1U.Quolity Assurance Supervisor SYSTEM-OPERASILITY Health Physics Supervisor
' t.
7ERIFICATION Public Safety Services Supv.
Chief Storekeeper Preop Test Program Coordinator 1C Outage Director lu. Chemical Engineer (Results)
IC, Radiochem Laboratory Instrument Shop Reactor Engineer (Results)
Instrument Engineer (Maint. I)
Mechanical Engineer (Results) 10 Plant Services Supervisor 1C. Training Center Coordinator Prepared By:
John T. Dills Public Safety Services - SNP 1C Shif t Engineer's Office Revised By:
D. A. Fraser 1C Unit Control Room Health Physics Laboratory Submitted By:
LTaxetu J4.
IU.Nucir Document Control Unit Supervisor OsJ 1U Plant Superintendent, WBNP Plant Superintendent, BFNP PORC Review:
e/c/ si Plant Superintendent, BENP Date' 1U. NEB-K NRC-IE:II Approved By:
w rh Resident NRC Inspector - SNP Plant Manager lg NSRS-K Technical Support Center Date Approved:
g /c,/ g/
- 10. Unit Control Room #2
/ '
ly. Compliance Section Staff Supervisor Rev. No.
Date Revised Pages Rev. No.
Date Revised Pages 0
2/11/80 ALL 1
7/15/80 5-21, Add 22-Th 2
1/29/81 2
s,/gro a-w 3
The last page of this instruction is Number 74
SQNP SI h19 Paga 1 cf 1
.Rev. 0 1.0 SCOPE 1.1 Description 2.1.1 Establish and document the quarterly solid radwaste requirements in the Technical Specifications.
1.2 Objective 1.2.1 Satisfy surveillance requirements for the solid radwaste system at least once per 92 days as follows:
a.
Verification of the existence of a valid contract for solidification to be performed by a con' ~ actor in accor-
~
dance with a process control program (SR 4.113.1.b) 1.3 Frequency - 92 days 1.3.1 All Modes a.
Verify the existence of a valid solidification contract for processing radioactive vastes.
2.0 INSTRUCIIONS 2.1 Verify that the solidification contract in Appendix A of SI-h19 is a valid contract by verifying that the expiration date is still applicable for solidifying radioactive vastes. Record the expiration date on data sheet 2.0.
2.2 Verify that the vaste solidification vendor is using the process control progra= (plan) as described in Appendix B of SI h19 to solidify radioactive wastes.
Record verification (yes or no) on data sheet 2.0.
2.3 Record date that step 2.1 and 2.2 were performed.
3.0 ACCEPTANCE CRITERIA 3.1 Acceptance criteria is given on the data sheet for each parameter monitored.
h.0 ACTION REQUIRED l
4.1 The lead chemical laboratory analyst (SE 5) will review and approve the completed SI and will evaluate if data collected is valid and meets the acceptance critiera as noted in the surveillance instruction and acknow-ledges by signing the data coversheet.
_l-
SQNP s
SI-419 Data Cover Sheet P2ge 1 of 1 Rev. 2 SOLID RADIOACTIVE WASTE TREATMENT SYSTEM - OPERABILITY VERIFICATION Unit 0 Performed By Date Analyst (s)
Data Reviewed and Approved:
Date Lead Chemical Analyst (SES)
..[
Instruction No.
Data Sheet No.
Pages SI-419 2.0 Were Technical Specification criteria satisfied?
yes no If criteria were not satisfied, notify the shift engineer who completes the fol-lowing:
Was a limiting condition for operation violated?
yes (explain in remarks) no (explain in remarks)
Verified By Date Shift Engineer Reason for test:
Required by schedule Other (explain) a Review and Aproval of Test Results Date Cognizant Chemical Engineer QA Review of Test Results QA Staff Date Remarks:
9r
SQNP SI k19 Data Shnt 2.0 Page 1 of 1 Rev. O Unit 0 Procedure Acceptance Analyst Sten Descriution Data Criteria Initials 2.1 Expiration date of
/
/
Date for step 2.3 contract for processing MO DATE YEAR prccedes date for solid radwaste with step 2.1.
(Vendor I.D.)
2.2 Process control YES/NO YES
~
plan verified (circle one) 2.3 Perfor=ance date NA of SI step 2.1 and 2.2.
NOTE:
If date for step 2.3 supercedes date for step 2.1 or value for step 2.2 is NO, then i= mediately notify the chemical engineering associate (SE6) or cognizant chemical engineer to verify the vaste solification contract (Appendix A) is presently applicable and that the vendor is using the approved process.
Control program (plan) as described in Appendix B of SI-419 for processing radioactive vaste for soliditation. Record date, time and person notified and any recommended corrective actions on datasheet.
REMARKS:.-
SQNP Rev. 3 TCNNESSEE VALLCY AU'i.euhtTY-37_hig page 1 of 7
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- r SI-h19 Page 3 of T Schedule of Pricepm A aev. 3 Ne, m68-18049 Fago No.
1 l
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Bidders quotation snall be based on the materials manpower and equipment necessary to complete the requirements of Schedule I items 1-5 and Schedule II J
items 1-5.
All work shall be done in accordance with the attached specification.
This agreement shall be an Indefinite Quantity Term j
Contract (IQT).
Therefore, no maximum or minimum amounts are guaranteed..
I q
~
TVA resarve: the right to make multiple awards, and/or to award by scnedule.
$8000.00.olus 38000.00 olus (-
Schedule I (Where applicable, Contractor shall quote i tem for cotn Demand and Full-Time _ service)
Demand full-Time L belov; I
A.
pental and set-up of mobile solidification unit.
5600/ day t$5000.00/lo.
B.
Services of operator (Dollars / hour)
$30.00 /hr.
- ,30.00 /hr. (See 42 be -
C. Solidification services utilizing masonry cement as a solidification agent. (Dollars per cubic foot of waste as measured at the connection between 3
the TVA nuclear plant and Contractor's equipment).
515.60'f t S 15.60 /ft.3 (See
- 3 be 0.
Transportation (Shipping Cask without liner) 52595.Chipmen d2695.Codioment (See Attachment 1) l
! item 6
$4170.00 iner $1170.00/ liner be:
E.
Disposable liner Schedule II (Where applicable, Contractor shall quote for ooth Oemand and Full-Time service) 58000.00.plus 38000.00 al us (F..
item 4' s
A.
Same as above
$735/ day 12.SC0/Mc;.
I B.
Same as above
$ 30.07hr.
L 30.00 /Fr. (See
- 2 bc:
C.
Solidification services utilizing the DOW Chemica' solidification process for low-level radioactive wastes. (Dollars per cubic foot of waste as measured at the connection between the TVA nuclear plant and Contractor's equipment).
$75.00 /F t. 3 1 75.00 /rt.3 (p item D.
Transportation (shipping cask without liner)
$2695.0 adip-l 2695.00'd h i p-(See Attachment 1) mdnt j
dent (Sa l
- 5 E.
Disposable liner 58585.00i ner j 858S.00G iner Note: (Transportation shall be from Sequoyah Nuclear Plant near Daisy, TN.
to the Chem Nuclear Disposal Facility near Barnwell, SC).
' A SCSI (OP 9 73)
Chem-Nuclear Systems, Inc.
..oce.
SQHP SI h19 Pa62 k of 7 APPENDIX A Rev. 3 Na,81P60,100449 Schedule of Pn.ces Pago No.
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.....u Overtime Bidder shall state: $30.00/ hour Hours constituting regular workday 8
a.m. to 5<
p.m.
i
-Days constituting regular work week if other than j
Moncay througn Friday.
NA
.i i
Quality Assuranca.
Thirty (30) days from date of awa'rd, A.
i the Contractor shall satisfy all 0A requirements
{
speci fied by. TVA.
Should Contractor fail to i
satisfy the aforementioned requirements, TVA reserves the right to terminate the contract at no cost.
i I
Contractor shall notify TVA when 70% of award amount mas been !
used.
l i.
Full time use 58.000.00 fee is a one time charca.
l Ocmand use 58,000.00 fee is per set up if the unit l
leaves Sequoyah Station between solidifications.
I For Ocv Solidification a metering batch tank is I
required.
Should this service be elected a minimum 3 year rental period at an additional 58,760.00/ month will be required or CNSI will sell batch tank equipmen't l
to TVA for $400,000.00.
I As stated herein pricing is based on a minimum 40 houd work week.
Pricing ~ is based on minimum of 95 cu.ft. of radwaste per liner.
Transportation based on use of CNSI licensed 21-300 cask.
Transportation based on use of CNSI licensed 14-195 or 21-300 casks.
I Pricing is based on minimum of 110 cu.f t. of radwaste l per liner.
I i
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4
' A SG)I [QP 9 831 Chem-Nuclear Systems, Inc.
~
SqNP sI_h19 Page 5 of T CHANGE OF CONTRACT APPEADIX ATMis occCK vn r,c o,$'s.Wi cds6 c25 v.ir=1 vErcoOR Coot FTATC c' rec'~44TilY T'iA H E F C H v.NW!.Q.
' CHAR.Gt.
. OOC Aaaress sie comanvascation except invoices to 39 OlEI)OalT.M4S 1
t.O TENNCSSEE VAL. LEY AUTHORITY oVYlNG COOC OlviSION Or PURCHA$lNO CCt.*MODITY CC'4.
CH Ar4G3 AMOUNT -
Cn.is.n.o s.. T.nne.... m ot L IE I D I t1 i 5 9951 No chance
'v E rv 00 A H E e e.
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Telem 33 4417 Tesepnoce 635 755 3011 1/12/31 11 *6 R0 thr-ANSWER 8ACK TVAPURTRPCTA ACCOUNT NO.
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- .!.c o,.r. s.7ss.Ju4 1711M 3-12D I
p H Q.T.C T CCNTRACT NUMBER must De snown on ad invoteen, naci.ases. inimoins raa.,s.aa
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Feauovah Nucle'ar P1 ant r o,,....ne.nc..
TO if Chem-Nuclear Systems, Inc.
ONSITE "0 BILE SOLIDIFIC.A 240 Stoneridge Drive, Suite 100 SEP. VICES FOR P.ADI0 ACTIVE Colunbia, SC 29210 The attacM d Schedule III is hereby made a part of the contract.
t Also, on page 2 of Schedule of Prices, Oualf tv Assurance does read:
Thirty (30) days frem date of award,....
Should reed:
Ninety (90) days from date of award,....
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- .1:.iL... d.S U.";i A.l other terms and conditions of the original Contract and Drevious chanics of contract (if any). shall Jpply.
NOT TO EXCEED TcemtsscE vALLCY AUrl10RITY Previous Total 5100.000 civision 63purcnasir 9 y
/
,j correct Total No change h/jf gy
/ru,j (68) David H. MarkT,urenwas Asant
/mc TVA 394 (Op.7 80).
coni,.cior Coair.ci eiie a,-..--.~.-.
SOEP 81-k19 SCHSDULC 0F PRICES APPENDIX A llo,
Wl834M Page 6 of 7 pg g (;g,---
p e
Articles or Services Guantitv Unit Uni t Price. Amour Schedule III (Where applicable, Contractor shall quote for both Demand ano Full Time Service)
'l 512,000 plus 58,000 Demand Full Time A. Rental and set up cf Mobile Solidification unit.
5500.00/ day
$5,000.0C/40.
B. Services of Operation.(Dollars / hour)
- 2 530.00/hr S23.00/hr?
C. Solidificatien services utilizing Urea Formalde-
- 3 hyde es a solidification agent.
(Dollars per 530.00
$30.00 cuoic foot of waste as measured at the connection between the TVA Nuclear Plant and Contractors eouipment).
D. Tr'ansportatica (shioping cask without liner)
^4 (See Attacnment 1) 52.770.00 52,770.00 E. Disposable liner
$3.370.00 53.870.00
- 1 See Item No.1 of Page 2 Schecule of Prices pervicusly submi".ted.
l
- 2 See item No. 2 of Page 2 Schedule of Prices previcusly submi".ted.
- 3Pricingisbasedonminimumof200cu.ft.ofrac.!vaste per l ner.
i l
- 4 See Item No. 4 of Page 2 Schedule of Prices previcusly submitted.
I NOTE: Availability of urea formaldenyde solidificctjan unit for demand type service is cased on beior Mleased from servige by anothcr utilF:y.
This utility expects.. 'le tion of services ddring week of 15 qecember 1980.
Upon relea :
e.L :e Nentioned unit woul d be broug!): to sequoyah days. Availability cf Full Timd servi'ces Nuclear Statior m
remains negotia. ..
k Chem !uclcar Systems, Inc.
CHder
nei Rev. 3 SI h19 APPENDIX A-Cl?ANGE OF CCiNTRACT Page 7 Of 7 <Twis otoex To se covet.rTro av Tvai l
VENOOR COCE S TATE O64 COUNTRY TV A 54 C> t R E;41.E f 40.
CMat4GE
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an common. cation e= cent.nvoius to 39 81P68-180449 2
TENNESSEE VALLCY AUTHORITY BUVING CQQE COWOOITY CCOE CHANGC AIAOt<NT $
OsvtSlofd oF ovoCHASING Chattanooga. Tennessee 374o1 L i E lD IW j5 9951
,fo chance I
v cNua.4 we.,e nsNws tiv.
unArwGE LA T.
viseOA.4Ars;E cuir T... s s.e a i r Tei.on ne sis.rss.aot t 2/25/81 11/26/80 -
ANSWE R SACi<.T VA PU R T R FC TA ACCOUNT NO.
4/24/gl j
Teiecooier e.as.rs5 2:24 711053-1i20 i
l i
PROJECT CONTR ACT NUMUER must ce snown on a" invo c.i. o c= aces, inion.n, o.a.rs ana Se9noYah Nuclea* Plant l
corr inoneence.
To ONSITE POSILE SOLIQ}FICATIO Cherr-Nucicar Systc=s, Inc.
SERVICES FOR RADI0 ACTIVE WA 240 Stoneridge Drive, Suite 100 Coluc61a, SC 29210 The ter= of the centract is hereby e:: tended fro = February 24, 1981, through April 24, 1981.
l All other terrns ano concitions of the original contract and previous criances of contract (if any). shait acety.
NOT TO EXCEED Mansficid-7X TENNESSEE VALLEY AUTHORITY Previous Total $100,000.00 civision os purcnasing correct Total-
- I change By [ OE d>~
s (68)' David H.' Marks,
~
' a ' c a ' 5'a' A"'
u
/me TVA 394 (0p.7 4o' Contractor Contras9 arHO em/[dlc>_ eceova qua G f f 080 -_---------------
@GWP1 GO f ?9 --- - -
--A-
SQNP SI h19 APPENDIX B Page 1 of 1 Rev. O CHEM-NUCLEAR SYSTEMS, I'tC.
PROCESS C0flTROL PROGRAM e l, O
e D
t 4
. / /-
3 SQHP SI h19 APPENDIX 3 - PART I Page 1 of 1 Rev. 3 PART.I.
Chem-Muclear Systems, Inc., Process Control Program Using CNSI Portable Solidification System (Typical)
' i 9
11 A
SQNP
-SI 419 APPENDIX B - PART I Page l of 1 Rev. 3 TABLE OF CONTENTS 1.0 PURPOSE 2.0 SYSTEM DESCRIPTION 2.1 klaste Transfer System 2.2 Dewatering System 2.3 UF Transfer System 2.4 Catalyst Addition System 2.5 Ai.e Soaring System
-L 2.5 Off-Gas Vent System 2.7 Pneumatic Control Panel 2.8 Electrical Control Console I
3.0 SAMPLE COLLECTION AND ANALYSIS 3.1 Samole Procedure Overview and Implementation 3.2 Obtaining Test Specimens 3.3 3acole Analysis 4.0 TEST SCLIDIFICATION AND ACCEPTANCE CRITERIA 4.1 General Solidification Considerations 4.2 Test Solidification a.3 Solidification Acceptability a.4 Alternate Solidification Parameter Selection i
i
?
I i
4 A
W-
SQNP SI h19 Pasp3 l or 7 APPENDIX B - PART I Rev. 3 1.0 The purpose of the Process Control Program is to:
Provice assurance of the satisfactory solidification of wet radioactive waste and absence of significant free water in such waste prior to transport and disposal.
i 20 SYSTEM DESCRIPTION The Portable Solidification Unit utilizes urea formaldehyde to convert all type of wet radioactive waste (filter sludges, spent resins, evaporator botte=s, boric acid solutions, and-sodium sulfate solutions) into a solid matrix.
Sulfuric acid is added to a homogeneous mixture of wet radioactive waste and urea formaldehyde until solidification occurs.
The Portable Solidification System consists of the following subsystems:
waste transfer, dewater, catalyst addition, air sparging, ano off-gas vent system.
The unit also contains a pneumatic control panel and an electric control panel.
2.1 Waste Transfer System 2.1.1 The major components of the waste transfer system are a 2-inch, teflon-lined hose with an outer stainless steel
~
braiding and manual md air-operating ball valves.
4 2.1.2 Valve WS-1 (plant isolation) is an air-operated ball valve which will shut on a high level in the disposable liner.
2.1.3 Valve WS-3 and WS-4 (sample valves) and WS-2 (waste con-tainer isolation) are manually operated ball valves.
2.2 Dewaterino System 2.2.1 The purpose of the dewatering system is to remove slurry water from the disposable container before solidification.
j 2.2.2 The major components of 'the dewatering system are:
1.
A 1-1/2-inch air-driven, diaphragm-operated positive displacement pump.
2.
A pressure gauge is located on both the suction and i
discharge side of the dewater pump.
3.
Tne Eaction hose for the dewater pump is a 1-1/2-inch rutier suction hose.
The discharge hose is a 1-1/2-inch tcflon-lined hose with an outer steel braiding for over
~
pressure protection.
4.
Both sample and flush connection are available for the dewater system.
j 5.
All valves in the dewater system are manually operated ball valves.
~
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SGIF SI h19 APPENDIX B - PART I-Page 2 of C) 2.3 UF Transfer System 2.3.1 The purpose of the UF system is to store the UF until needed and then transfer UF to the disposable liner so it can be used in ' solidification.
2.3.2
-The major components of the UF systems are:
1.
UF stowage container which is usually a' spare 300-cubic foot liner equipped with a PVC (polyvinyl chloride) stand pipe.
2.
A 1-1/2-inch air-driven, diaphragm-operated positive displacement pump.
d !.
3.
Tha pump is equipped with a suction and discharge pressure gauge and flush and sample connection.
2.4 Catal'est Addition System 2.4.1 The function of the catalyst addition system is to transfer the catalyst from the shipping container to the disposable liner for solidification.
2.;.2 The major components of the catalyst addition system are:
1.
The catalyst transfer pump is a 3/4-inch centrifugal, constant-speed pump.
The pump is. equipped with a metering '
valve for regulating discharge flowrate and a recircula-tion line back to the suction side of the pump.
2.
Check valves are placed in both the catalyst transfer line and the air sparging header to prevent any acid backing into the pneumatic control panel.
2.5 Air Scarcing System 2.5.1 The function of the air sparging system is to mix the urea formaldehyde and radioactive waste and for drawing off free liquid remaining in the liner after solidification.
2.5.2 The major components of the air sparge system are the air sparge header which is placed inside the disposal liner,
'the control regulator, and gauge located at the pneumatic control panel.
2.6 Off-gas Vent System 2.5.1 The purpose of the off-gas vent system is to create a slight vacuum at the top of the liner to draw off radioactive airborne i contamination and discharge it through the plant's stack gas system.
2.6.2 The major components of the off-gas vent system are the blower which is used to take a suction on the liner, a 1-1/2-inch spiroflex hose, and a vacuum breaker which will open a 1 psig to prevent the blower hose from collapsing.
_ne-s
.SQNP SI-419
?xv. 3 APPE3 DIX 3 - PART I Pass 3 of 9 2.6.3
- The blower is normally mounted on the stand' with valve WS-1 dnd the samplefvalves.
2.7 Pneumatic Control Panel 1
- 2. 7.1 The purpose of the pneumatic control panel is to line uo and deliver pressurized air at 100 + 20 psig for the follo. wing functions.
1.
Sparge Air 2.
Fill Head Cooling j
3.
Camera Air 4.
Plant Waste Connections 1
S.
UF and Dewater Pump Control
- I-2.7.2 All functions are equipped with a pressure regulator and a pressure gauge except fill head cooling air ano camera air.
2.7.3 The pneumatic control panel is equipped witn an air dryer for 4
removing moisture from the supply air.
2.3 Electrical Control Console 2.3.1 The purpose of the electrical control conscle is to provide power and indication for the following components:
1.
Pump and Valve Indication and Operation 2.
Level Indication i
3.
Radiation level read-out 4.
Remote Viewing Camera 5.
Acid Pump 6.
Off-gas Vent Blower 2.8.2 Pumo and Valve Indication and Operation i
1.
Valve indication is supplied for valve WS-1 (plant isolation) at the electrical control console.
The valve can be operated in either local or remote control.
2.
An interlock is installed on the filling head to prevent WS-1 from being opened unless the fill head is positioned correctly on the barrel top liner and shut on a high j
pressure in the disposable liner.
i 3.
Valve WS-1 will shut automatically on a high-high level t
condition in the disposable liner.
4 A red indicating light is on the electrical control con-sole to indicate valve WS-1 is open ano a green light exists to show wnen WS-1 is shut.
i 5.
There is a 30-second time delay built in *.nc automatic closing device for US-1 to allow the operator time to prevent a premature closing of valve US-1.
US-1 will shut automatically on a high-high level condition in i
the disposable liner.
+r SI h19 Page 4 of 9 APPENDIX B - PART I Rev. 3 2.3.3 Level Indication i.
Four different level positions are supplied.
They are dewater level which is yellow, waste level which is black, UF level which is white and high levei wnich is red.
The levei probes connect to the filling nead by means of dis-posa'ble dual banana jacks wnich are color coded for each level setpoint.
2.
The level inside the disposable liner is incicated on the electrical control console by a series of level indi-cators. A level indicator exists for each probe (dewater, waste,UF,high).
There is also a selector switch which will energize the dewater probe when in the sludge posi-tion.
A white indicator shows when the correct level
~
has been obtained.
'i 2.3.4 A remote radiation detector monitors the waste passing through the waste transfer hose and may be positioned at any desired location.
2.3.5 The electrical control console contains a remote television monitor for viewing the contents of the disposaDie liner.
2.3.6 The acid pump and vent blower controls are identical in design anc operation.
They consist of an off/on switch and a red indication light to show unen the equicment is energized and are equipped with overloac circuits.
2.9 Fill Head Assembly 2.9.1 The fill head assemoly is mounted atoc the dispesable liner and directs the flow of was te, catalyst, UF, anc air to the liner.
2.9.2 The fill head is equipped with an adjustacle hign level switch which will shut valve WS-1 on a high level.
The high level switch is a float-type switch.
2.9.3 A camera is mounted in the fill head and directed into the disposable liner.
3.0 SAMPLE COLLECTION AND ANALYSIS 3.1 3 amole Procedure Overview and Imolementation 3.1.1 This Section and Section 4.0 of the Process Control Program establish the program of samoling, analysis, test solidifi-cation, and evaluation which is necessary to ensure complete solidification of eccn type of wet radioactive waste.
3.1.2 Batch is defined as the waste required to fill one disposable liner to the level of the waste level probe.
3.1.3 If any test specimen fails to solidfy, the batch in the liner should not be solidified until a new test specimen can be obtained, alternative solidification parameters be deter-mined, and a subsequent test verifies solidification.
.d
3Q3P SI-h19 Page dior g APPENDIX B - PART I Rev. 3 3.1.4 If the first test specimen from a batch of waste fails to verify solidification, a sample will tua collected and analyzed '
in accordance with the Process Control Program fren each conse-cutive batch of the same type of wet waste until-three (3) consecutive test specimens demonstrate solidification.
At this point, the sampling requirement is again every tenth batch of each type of wet waste.
2.2 Obtainino Test Specimens 3.2.1 Radiolooical Precautions 1.
All samples must be handled with proper radiological considerations to minimize employee exposure and to prevent the spread of contamination.
3;
~
2.
A " clean" and " contaminated" control area should be set up to prevent contamination spread.
3.
Any requirements set forth by the facility's Health Physics Depar: ment must be compiled with.
4.
Disposal of comoleted test samoles will be in the liner to be solidified.
1 3.2.2 Data Sheet PCP-1 l.
Data Sheet PCP-1 (Attachment 1) will be used to collect data from each test specimen and will be maintained on file with the current sheet on top.
A copy of Cata Sheet PCP-1 will be maintained for each of the types of wet radioactive waste.
2.
The following information is required on cach tsst specimen:
1.
pH of waste 2.
Waste oil content (percent visual) 3.
Waste /UF ratio.
4 UF/ Acid ratio 3.
The follcwin; inferraticn uill be recuirea fcr all solidification evolutions.
1.
Waste type 2.
Batch number 3.
Level probe setpoints 4
Sparge air pressure, flowrate, sparging time 5.
Total waste received 6.
Total UF added 7.
Total acid catalyst added 4
The batch number will range from 1 througn 10 and cn eacn tenth batch of each type of wet radioactive waste, a new set of process parameters will be determined.
This prac-tice will be followed for each type of wet radioactive waste.
SQNP SI-419 APPENDIX 3 - PART I P
Page h of 9 3.2.3 Samplino ContinuoMf"Trdhsfers of Waste 1.
Evaporator bottoms or other hot samples should be collected and tested as quickly as possible to lessen the crystalliza-tion of any boric acid which may be present.
2.
Resins and other sludges should be collected in wide-mouth bottles or other such containers from which the sample may be readily removed.
3.
In the cases of resins or other waste in which large volume:
of flush water are involved, several consecutive samoles ma have to be taken and the flush water decanted from the samp
~
before a sufficient quantity of sample is obtained;*f-4.
Sample volumes should normally be 1 liter.
However, if rad tion levels make this impractical, smaller sample may be ob tained as appropriate.
5.
Obtain the sample from either valve WS-4 after sufficient w -
has been transferred to the liner so that a representative pie is in the transfer line, or from the plant's routine sa:
point for the waste involved before its being transferred.
the sample is collected at valve WS-4 at least 1/5 of the a:
cipated volume of waste to be transferred should have been received before taking the sample.
3.2.4 Samolino Multiole Transfers of Haste Per Batch 1.
The sampling techniques of 3.2.3 above are applicable.
2.
Each sample of the partial batch will be placed in appro-priate storage until the entire batch of waste has been transferred to the liner.
3.
For each partial transfer an estimate of the volume will be made.
i 4.
Prepare a composite sample by determining the fraction which each transfer contributed to the total batch.
Using the total samole volume required,'mul tiply each transfer fraction by this volume to give the volume of each sample which is to be added to the composited sample.
4 3.3 Samole Analysis 3.3.1 General Sample Analysis Considerations 1
l.
Specific techniques for chemistry analysis are not includec.
in this PCP since there are several acceptable procedures for many of the analyses that may be required.
2.
The solicification agents will require certain analysis and are included in this section for convenience.
3.
All analytical results are to be recorded on Data Sheet Pr?-l maintained for that purpose.
%UP Page 7 of i SI-Rsv. 3 H B - PM I For each new UFEpment, and periodically during storage, 3.3.2 analyze a sample for specific gravity and pH.
3.3.3 Each container of catalyst should be analyzed before use for.
specific gravity and color (visual).
3.3.4 Evaporator bottoms should be analyzed for:
1.
pH 2.
Oil (percent visual) 3.
Baron 3.3.5 Filter and other sludges should be analyzed for pH and visually checked for percent oil.
3'.3.6
~ Resin beads will be characterized by analyzing the wateb surrounding the beads for pH.
~
3.3.7 All waste should undergo a qualitative test for foaming upon the addition of the catalyst.
This can be accomplished by ddding the catalyst to a small quantity of the waste in a beaki and visually observing the results. Add antifoaming agent as needed to waste to eliminate foaming action.
4.0 TEST SOLIDIFICATIOL Af4D ACCEPTAtlCE CRITERIA 4.1 General Solidification Considerations 4.1.1 The standard ratios of UF/ waste that are to be used on the first test solidification (unless other data shows 'different ratios shoul be used) are as follows:
1.
Resin beads or other waste with a high precentage of solid material with a defined shape, use a ratio of 1 to
]
2.
Filter sludges, evaporator bottoms, or other waste with e i
high percentage of dissolved or suspended solids use a ratio of 1 to 2.
4.1.2 If the pH of any waste was less than three, a caustic should be added to increase the pH to greater than three before the addition of the UF, Record the sample size and the amount of caustic added.
4.1.3 If foaming occurred in the waste sample, an antifoaming agent should be added to the waste before the addition of the UF.
Record the sample size and the amount of antifoaming agent added.
4.1.4 If-visual oil checks indicate concentrations greater than 1 percent, attempts to remove the oil should be initiated by skimming the top of the liquid or by the addition of demulsi-fication agent (s).
- W
8@#
Page 9 of 9 SI-h19 Rev. 3 APPEiVDTX B - PART I 4.2 Test Solidification 4.2.1 The waste sample should have the required pretreatment accom-plished before the test solidification.
4.2.2 Prepare the test solidification vessel (normally a 1,000-ml disposable beaker) with'a mixing device.
This may be a dis-
- posable magnetic stirrer, a.miniatire air sparge system or other mechanical means of mixing ae waste to UF.
a l
4.2.3 Transfer a known representative vo'ume of the waste (approxi-mately 400 ml) to the test solidification vessel.
4.2.4 Add the appropriate volume of UF as determined by the appli-cable ratio.
4.2.5 Mix the waste and UF thorcughly.
Then begin the catalyst addition until a pH of approximately 2 is obtained, then stop the addition of the catalyst.
4.2.6 As soon as the mixture begins to thicken. stop the mixing and allow the sample to remain undisturbed for at least 30 minutes.
4.2.7 If any free-liquid is noted on the top of the sample, transfer -
the liquid, by draining, into a clean, disposable volumetric beaker and record the amount of the liquid transferred.
Calcr late and record the percent of free-liquid present.
4.3 Solidification Acceotability 4.3.1 The sample solidification will be considered acceptable if the amount of free-liquid was, equal to or less than 0.5 percent by volume or 1 gallon, whichever is less.
q 4.3.2 The waste solidification will be considered acceptable from a solid mass standpoint if it is evident from its physical appearance that the solidified waste will maintain its shape if moved from the vessel.
This may be determined, for example by simply prodding with a stick or other rigid device and i
observing significant resistance to penetration.
4.3.3 If one or more of the above tests fails to meet the stated criteria, additional solidification parameters must be deter-mined.
This will also require the initiation of the additione solidification testing requirements for the next three batch types of waste which fail to solidify.
4.4 Alternate Solidification Parameter Selection 4.4.1 If unacceptable solidification resulted from excessive foamint the following items should be explored to reduce subsecuent foaming.
Solidification testing, as specified in Step 4.3 above, must be repeated and results recorded.
1.
Adding additional or different antifoaming agent 2.
Lowering the pH of the waste before the addition of the i 3.
Reduce the addition rate of the catalyst
SI-419 APPENDQ: B - PART.I'
)
Page y of 9 Rev. 3 4.4.2 If unacceptable solidification resulted from excessive free-liquid or a too-soft matrix, the UF/ Waste ratios should be adjusted in increments of 0.5.
For example, if the UF/ waste ratio was 1 to 3 and the results were unsatisfactory, a ratio of 1 to 2.5 should be used.
Solidification testing as speci-fied in Step 4.3 above'must be repeated and results recorded.
4
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- a4E SI-419 APPEDIX B - PART II Page 1 of 1 Rev. 3 FART II, Chem-ituelear Systems, Inc., Operating Procedures for the Portable Solidification Units (Typical)
~
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SQ3P SI-419 APPEIDIX B - PART II Page 1 of 1 Rev. 3 TABLE OF CONTENTS i.0 OPERATIfiG PROCEDURE 1.1 Scope 1.1.1 Applicability 1.2 Prerequisites 1.3 Precautions 1.4 Detailed Procedure 1.4.1 Normal Operation 1.5 Reference Drawings i-l, l
___-______-_____-_____________________________n_s%
~ 52 SI-h19 APPENDIX 3 - PART II 1.0 OPERATIflG PROCEDURE P"C' I
- 10 Rev. 3 1.1 Scoce q
This document provides instructions riecessary.for the operation of the Portable Solidification Unit during normal operation, resin transfer and dewatering, and system startup and securing.
1.'l.1 Aoolicability The instructions contained in this procedure are to be used by the operators of the Portable Solidification Units.
1.2 Prerecuisites ei..
1.2.1 The radioactive waste disposal system shall be in the shutdown mode of the operation before commencing Portable Solidification Unit startup.
1.2.2
?!ew level setpoints for waste and urea formaldehyde will be determined by a test solidification of each tenth batch of each type of wet radioactive waste (filter sludges, spent resins, evaporator bottoms, boric acid solutions, and soaium sulfate solutions).
1.3 Precautions-1.3.1 At all times, the operator will follow the proper radiological precautions, to minimize the spread of contamination and to limit personal exposure to ionizing radiation.
1.3.2 When performing a dewatering evolution, the air sparge must be in operation.
This is to prevent the resin from settling out and forming a semi-solid mass which will prevent adequate dewatering.
1.3.3 When dewatering a resin slurry, ensure that the proper filter screens are installed on the dewatering header.
1.3.4 If at any time during the operation of the Portable Solidificatil Unit you cannot maintain normal parameters, secure operation anc contact the plant chemical engineer for assistance.
1.3.5 During all processing evolutions, the PSU operator (s) will. wear assigned dosimetry.
1.3.6 During all operations of the PSU, the PSU operator (c) shall wear-the proper clothing as required by Special Work Permit (SWP).
1.3.7 A radiation and contamination survey shall be performed after maintenance on any part of the PSU which could release contami-nation, and anytime good radiological precautions and procedures require surveys to be performed.
The plant Health Physics Section shall perform this survey.
n
-u SQUP SI-bl9 Rev. 3-APPENDIX B - PART II Page 2. of iG 1.3.8 When receiving a resin slurry for dewatering only (no solidification) every effort must be made to ensure all water has been removed from the liner before transfer.
1.3.9 Before receiving waste, check the integrity of all hoses and transfer lines to ensure all lines are in operational condition.
1.3.10 Liners shall be shipped as soon as possible af ter solidification to reduce radiation levels in the area of the PSU (preferably within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> af ter solidification).
1.4 Detailed Procedures 1.4:1 "ormal Ooeration 1.4.1.1.
Initial Conditions See Chem-Nuclear Systems, Inc., Operation Procedure SD-0P-001.
NOTE:
STEPS 1.4.1.1.1 THROUGH STEPS 1.4.1.1.22 MAY SE PERFORMED IN ANY SEQUENCE.
1.
Health Physics shall survey the area for surface contamination and radiation levels.
2.
Position the PSU, polymer stowage tank, and dispo:
liner (s) in the assigned position.
3.
Establish the following plant services to the PSU-1.
Electrical power; 480 volts, 70 amps 2.
Service air; 25 SCFM at 100 i 20 psi 3.
Connect Pll to Jil-5.
Connect P6 to J6 6.
Connect P13 to J13 7.
Connect P7 to J7 9.
Connect P10 to J10 l
10.
Connect P8 to J8 11.
Connect P9 to J9 12.
Connect P5 to J5 13.
Connect P12 to a convenient receptacal 4.
Verify that the required amount of polymer, H,SO.
disposable liners, and lids are available.
t 5.
Obtain an SWP f rom the Health Physics Section.
6.
Establish control areas in the vicinity of the PS-as specified by the SWP.
7.
Connect the polymer transfer line between the pol; stowage tank and the suction side of the polymer :
fer pump.
s;UP' SI k19 8.
Using a crane, lift the filling head from its stowage tray !
APPSD H 3 - PART II and place into position for connection of the following:
Page 3 of 14 Rev. 3 1.
UF transfer hose 2.
Waste transfer hose 3.
Dewater suction hose 4.
Blower suction hose 5.
Catalyst transfer hose 6.
J2 to plug P2
^
7.
J3 to plug P3 8.
J1 to plug P1 9.
J15 to plug P15 9.
If necessary, remove valve WS-1 from the plant connection stand.
e i.
10.
Following proper radiological precautions, remove any blank flanges from Loth valve WS-1 and utilities radwaste-connection.
11.
Attach valve WS-1 and the sample spool piece to the utili ties radwaste connection and tighten securely.
12.
Following proper radiological precautions, connect radwas1 connection hose to the sample side of valve WS-1 and to valve WS-2 on the fill head assembly and tighten securely:
13.
Connect the polymer transfer line to UF pump discharge valve, UF-1, and to UF liner isolation valve, UF-7.
14.
Place the catalyst pump stand and the catalysc container in the assigned position.
15.
Following proper safety precautions, connect the catalyst transfer line to the catalyst liner isolation valve, CT-5 and catalyst pump discharge valve,-CT-1.
16.
Connect catalyst suction hose and stand pipe to the sucti side of the catalyst suction pump and install stand pipe and catalyst container.
17.
Install the catalyst recirculation line between valve CT and catalyst storage container.
18.
Connect the dewatering suction hose to the dewatering suction valve, DW-1, and to the dewater liner isolation valve 0W-7.
19.
Connect the dewa'.or return line to the dewater pump dis-charge valve, DW-6, to the utility's dewater return connection.
20.
Connect the discharge of the off-gas vent blower to the utili ty's vent system.
21.
Connect the suction of the off-gas vent blower to the fi' head assembly.
22.
Make up the air sparging header and install the level lec at the setpoints determined by the most recent test solidification.
.,.a SI-h19 APPENDIX 3 - PART II 1.4.1.2 Systems Preoperationa1 Checks Page 4 of.10
-Rev. 3 1.
Remove the inspection port from the cask lid and remove the barrel top from the disposable liner.
Inspect the cask and liner for damage and foreign material.
NOTE:
IF A CASK IS NOT USED, STEP 1.4.1.2.1 MAY BE OMITTED 2.
Place the air sparge heat:er assembly inside the disposab' 1iner and adjust the level heads to the setpoints define <
by the current test specimen.
3.
Position the solidification filling head over the disposi liner opening.
Leave enough clearance so that the sparg-header and level leads can be installed in their connect' on the filling head assembly.
1 4.
Following proper radiological precautions, insert the ait soarging header into the connection on the filling head assembly.
5.
Following oroper radiological precautions, insert the let leads into the lead connector points as follows:
~
1.
Green - Ground 2.
Yellow - Dewa ter 3.
Black - Waste 4.
White - UF 6.
Place the controi power switch in the on position.
7.
Position the filling head on the disoosable liner.
Veri;-
proper position by checking that the filling head positic, light on the electrical control panel is energized.
8.
Actuate main air selector switch on the control console and check available air pressure. Air pressure should be-100 + 20 psig.
9.
Check for proper operation of valve WS-1 by taking it frc fully open to the fully shut position from the control cc sole and locally at the valve station.
10.
Energize TV camera, TV monitor, and container light.
11.
Check for proper operation of. alarms and alarm lights at the control panel.
12.
Obtain from the plant's radwaste system operator the approximate amount of waste to be transferred.
13.
Perform the following valve lineu1:
1.
Shut or check shut valves WS-1, WS-3, WS-4, CT-5, DW-2 DW-5, UF-2, UF-5, and CT-2.
2.
Open or check open valves WS-2, CW-7, UF-7, CT-3, OW-1, CW-6, UF-6, and UF-1.
-~
W.i?.
SI419 APPERDIX B - PART II 3.
Check the metering position of CT-1 (valve CT-1 shou Page.Sor la be set to allow a transfer rate of 5.0 gpm. A trans-Rev. 3 rate of 5.0 gpm corresponds to a valve setting of 2.'
If valve CT-1 is not in the proper positica, adjust valve CT-1 to the proper position.
4.
Place valve SA-1 in the UF pump position.
- 14. Open valve WS-l from the electrical control console and start the off-gas vent blower.
Inform the radioactive waste system operator that the solidification system is ready to receive waste.
1.4.1.3 Radioactive Liouid Waste fransfer and Discosable Liner Fillinc' 1.
Before receiving radioactive waste, verify the preopera-tional checks are complete.
1 2.
Verify that the transfer of radioactive waste has begun 'c viewing the TV monitor and inform the client's Radioacti'.
Waste System Operator that you are receiving waste. Rect date and time you cegan receiving waste in the radwaste 1.
3.
Record fixed monitor radiation readings on an hourly bas-and record in the radwaste log.
4.
When the waste reacnes the waste level setpoint, shut
~
valve WS-1 and inform the plant radwaste system operator to secure transfer.
5.
When the transferring operation is complete, inform the plant radioactive waste system operator to perform the necessary valve lineup to flush the waste transfer line.
6.
When the radioactive waste system operator reports that he is ready to flush, open valve WS-l.
7.
Continuously monitor liner level during flushing operati 3.
Monitor the waste transfer header for radiation levels.
adequate flushing has taken place, the radiation levels the waste transfer header should arroximate background.
If radiation levels are significantly greater than back,
ground, further flushing is required.
9.
Af ter adequate flushing has taken place, shut valve WS-i 10.
Obtain the volume of waste received and record in the Ic and on Data Sheet PCP-l.
- 11. Actuate air sparge selector switch on the pneumatic cont console and increase pressure by adjusting the regulatir valve until a gentle rolling motion is noticed on the surface of the liquid by viewirg the remote monitor.
12.
Start UF transfer pump by increasing the air pressure t:
the speed cJntrol regulator from the electrical control console.
-,a
sonP SI-49
- 13. Monitor the liner for UF flow and continue addino UF until APPDDIX 3 - PART II the proper polymer to waste mixture has been achieved.
Page 6 of la Rev. 3 14.
Continue sparging for a total sparging time of at least I hour and at least 15 minutes of sparging after all UF has been added.
This ensures good mixing of the polymer and waste.
15.
After sparging for the necessary time, commence catalyst addition using the following procedure:
1.
Start the catalyst transfer pump and add catalyst unt a noticeaole increase in the mixture's viscosity is visible in the remoue TV monitor.
2.
Verify that solidification has occurred and the rolli motion of the liquid has stopped by viewing tWe remot TV monitor.
L Secure the catalyst transfer pump and open valve CT-2 to drain any residual catalyst from the catalyst line 4.
After all residual catalyst has been returned to the stowage container, shut valve CT-2.
5.
Determine the volume of catalyst added for :;olidifica tion.
Record on Data Sheet PCP-1.
16.
Connect catalyst transfer line to dewater pump flush conne tion and operate dewater pump ur.til all free liquid is removed from container and pumped back to plant.
17.
Secure air sparging and secure the off-gas vent blower.
18.
Secure main air selector switch.
19.
Secure TV camera and monitor.
20.
Following proper radiological precautions, raise the filling head away from the disposable liner and place in its stowage location.
21.
Check the quality of the matrix by visual inspection and by checking for hardness.
22.
Install the lid on the disposable liner.
l.4.2 Resin. Sludge, and Miscellaneous Media 1.
Preoperational Checks 1.
Perform Steps 1.4.1.1.1 through 1.4.1.2.2.
2.
Place a CUSI-approved dewatering header inside the disposable liner.
3.
Position solidification filling head over the disposa liner opening.
Leave enough clearance so that the sparging header, dewatering header, and level leads c be adapted to their fill head connections.
SCNP SIch,19 APPENDIX 3 - PART II 4.
Following proper precautions insert the sparging header, Page.7 or 10 dewatering header, and level leads into their fill head Rav. 3 connections.
.5.
Place SA-1 in the dewater position.
6.
Perform Steps 1.4.1.2.3 througn 1.4.1.2.13.
NOTE: AT THIS POINT, THE PORTABLE SOLIDIFICATION UNIT IS READY TO RECEIVE AND DEWATER RESIN SLUDGE OR '
MISCELLANE0US MEDIA.
2.
Waste Transfer and Disposable Liner Fillina j
l.
Perform Steps 1.4.1.3.1 and 1.4.1.3.2.
- l.
l 2.
Actuate the air sparge selector switch on the pneumatic control panel and increase pressure by adjusting the regulating valve until a gentle rolling motion is noticed on the surface of the slurry by viewing the remote monitoi; 3.
When waste reaches the 2-foot level, start the dewatering pump from the control console.
This is performed by slow' increasing the air pressure to the speed control regulatoi NOTE:
IF SOLIDIFICATION IS NOT REQUIRED BY THE TECHNICAL SPECIFICATIONS THE LINER fMY BE FILLED TO WITHIN 3 INCHES OF THE TOP 0F THE LINER.
i 4.
Continue pumping until the pump loses suction and suction cannot be regained.
NOTE:
IF AT ANY TIME RESIfl SHOWS UP IN THE SUCTION OR DISCHARt 0F THE DEWATERING PUMP, SECURE THE PUMP AND ISCLATE THE SYSTEM.
DO NOT CONTINUE OPERATING THE SYSTEM UNDER ANY CONDITIONS.
INFORM THE PLANT CHEMICAL ENGINEER OF THE CONDITION.
5.
Monitor radiation of the solidification unit operating c
space and waste header during operation.
3.
Solidification of Resins. Sludaes, and Miscellaneous Media 1.
When the dewatered media reaches the setpoint defined by the most recent test solidification, shut valve WS-1 and secure the dewatering pump.
Inform the radwaste system operator to secure pumping and line up to flush.
2.
When the radwaste system operator reports that he is ready to flush, open valve WS-l.
3.
When the radiation levels on the waste transfer hose approach background. shut valve WS-1 and inform the rad s. l system operator to secure flushing operations.
NOTE:
IF SOLIDIFICATION IS NOT TO BE PERFORMED, PROCEED TO i
STEP 1.4.2.3.9.
i
. _., - - - -. _ -. _,. ~
.~.
APPZDDIX 3 - FART II Paga.6 or 10 Rev. 3 4.
Place valve SA-1 in the UF pump position.
5.
Start the UF transfer pump from the control panel by slowly increasing air pressure to the s ;eed regulator.
6.
Monitor the UF flow and continue adding UF until the waste to polymer ratio defined by the most recent test solidification has been achieved.
Secure UF transfer pump.
NOTE:
DURING UF ADDITION, MONITOR CONTENTS OF THE LINER FOR FOAMING.
IF F0AMING EXISTS, SECURE OF ADDITION AND INFO:
THE PLANT CHEMICAL ENGINEER OF THE PROBLEM.
7.
Continue sparging for a total time of at least I hour and at least 15 minutes af ter securing UF addition.
' e-8.
Af ter sparging the necessary time, commence catalyst addi-tion using the following procedure.
1.
Start the catalyst transfer pump and add catalyst-until a noticeable increase in the mixture's viscosite is visible in the remote TV monitor.
2.
Verify that solidification nas occurred and the rolling motion of the '.iouid has stopped by viewing the remote T'l moni tor.
3.
Secure the catalyst transfer pump and cpen valve CT-2.
Af ter all residual catalyst has been drained to the catalyst stowage container, shut valve CT-2.
9.
Secure air sparge system and secure the off-gas vent blower.
10.
Secure main air selector switch, 11.
Secure TV camera and monitor.
12.
Following proper radiological precautions, raise the filling head away from the disposable liner and place the filling head in its stowage location.
- 13. Check the quality of the matrix by visual inspection and by checking for hardness.
14.
Install the lid on the disposable container.
1.5 Reference Drawings (Furnished by Chen-Nucicar Systems, Inc.)
387-101 (P&ID Portable Solidification) 1-184-121 (Sparging Assembly Disposal Container) 2-387-300 Rev. 8 (Control Panel Layout & :nterconnect Diagram Portable Solid Unit) 387-300 Rev. B (Control Panel Layout & Interconnect Diagram Portable Solid Unit) m
- a
30;;?
SI lQ APPENDIX B PART II ATTACHMEtlT 1 Tage 9 of 10 Ray. 3 DATA SHEET PCP-1 Shipment #
Batch #
1.0 Solidification chemical test and acceptance criteria.
Complete and sign below as applicable.
1.1 Urea Formaldehyde Hydrometer test results:
The acceptance criteria -- between 1.280 and 1.319.
1.2 Viea fornialdehyde pH N-The acceptance criteria -- Detween 7.4 and 7.7 pH units.
1.3 Acid catalyst (sulfuric acid)
Hydrometer test results:
Specific gravity acceptance criteria -- sulfuric acid > 1.83 1.4 Acid catalyst color acceptance criteria -- clear Operator Date i;0TE:
If any acceptance criteria is out of specification, contact the plant chemical engineer for assistance.
2.0 Verify the solidification of at least one representative test sample from at least every tenth batch of each type of wet radioactive waste. Indicate below the type of waste.
Haste Type 3.0 Sample Collection - Refer to PCP Appendix A, Section 3.2.3, " Waste Sample Collection and Analysis" 3.1 Obtain sample (
l liter) from va'lve W-4 for a continous single transfer or from TI-16 sample point.
3.2 Obtain a sample ( l liter) of each transfer from valve W-4 during multi-transfers of resins.
3.3 Prepare a composite sample from multi-transfer effluents.
Refer to PCP Appendix A, Section 3.2.4, " Sample Multiple Transfers of Was 4.0 Sample Test Results and Pretreatment 4.1 Ph of Waste
. if 43, refer to PCP Appendix A, Section 4.1.2.
Then complete step 4.2 below.
Otherwise, skip step 4.2.
4.2 Sample volume ml Type / volume of caustic added ml Resulting pH
- at
_ - -. _ ~
SCIP SI h19, APPENDIX 3 - PART II
. Paga,10 of -10 4.3 Waste oil content S: ifli l% refer to PCP Appendix A, Section
'Rev. 3 4.1.4.
1 4.4 Waste boron content ppm 4.5 Type / Volume of antifoaming agent ml (refer to Appendix A, Section13.3.7 and 4.l.3) 5.0 Test Solidification (if applicable)
~'
Prerequisite:
Steps 1.0, 2.0, 3.0, and 4.0 must be completed and procer signatures affixed to this form.
1.
Volume of waste ( : 400 ml) ml 2.
Volume of Urea-formaldehyde al 3.
Volume of Acid Catalyst ml
-l 4.
Total Volume ml 5.
Waste / Urea formaldehyde ratio 6.
Urea formaldehyde / acid catalyst ratio 1
6.0 Free-Standing Water Refer to PCP Appendix 0, Section 4.2.7 J
6.1 Volume of decanted water al 1
(
6.2 Total Volume of sample (taken from Step 5.0.4) ml 6.3 Free-standing water 5
7.0 Test Solidification Acceptability Steps 5.0 and 6.0 must be completed.
7.1 Step 6.3 above must be less than 1%.
If 6.3 is greater than 15, refer to PCP Appendix A, Section 4.3
)
7.2 Visual physical appearance:
Verify that the solidified waste will maintain its shape when removeo from the container.
If it will not, refer to PCP Appendix A, Section 4.3 Opera tor Date 8.0 Batch Solidification i
i 1.
Waste type i
2.
Estimated volume (s) of waste transfer --------
gal.
3.
Volume of urea formaldehyde added ------
gal.
4.
Volume of acid catalyst added ----------
gal.
i 5.
Volume of caus tic added ----------------
gal.
6.
Volume of antifoaming agent added ------
gal.
7.
Level probe setpoint(s)-----------------
8.
Sparging - air pressure ----------------
ps1.
f l o wra t e --------------- -----
scfm time ------------------------
minutes i
9.0 Verify solidification has gone to completion and there is $ l gallon of water on the surface.
/
Chemical Engineer Date i*
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o Table 1:
p!! Measurements by mis. of Catalyst for 200 ml. Slurries of Water / A -SET X
Y l
M1'. of 25% vr..
0 Sodium Bisulfste pH of Slurrv 0 70 F'.
Estimated oH 2
2.4 2.4 4
1.7 1.7 6
1.5 1.5 l
8 1.4 1.4 10 1.3 1.3 Equation for curvilinear fit of raw data.
Shown in Figura 1.
Y = 1.02522 + (.0415589X)
Index of Determination =.99724 X
Y 0
M1. of 3N H,504 pH of Slurrr 0 70 7.
Estimated oH O
~
1 2.7 2.7 2
1.9 1.9 3
1.6 1.6 4
1.4 1.5 6
1.4 1.3 10'
- 1. 2' 1.2 Equation for curvilinear fit of raw data.
Shown in Figure 1.
Y. = 1.05443 + (1.64827/X)
Index of Decemination =.99304 o
e
, 8 e
- r
~
o g
9
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S C. M V Al-O?
' ~
e pge '.3 E oC,70 b.I n
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700 and 90 F. Cel Times by pl! of Water /
SET-Slurries catalyzed with 25% Sodium Bisulkate t
?.
X Y
{
Slurry pH Q 70 F.
0 tstng 25% we.
Cel Time G 70 F.
Estimated 0
Sodium Elsulfate Solution (mins. )
Cel Time G 70 F.
2.4 19 19.4 1.7 11 9.3 1.5 5
5.7
^^
1.4 4
5.0
~
1.3 4
3.5.
~
Equation _ for curvilinear fit of raw data.
Shown in Figure 2.
~
i Y = -15.2101 + (14.4304X)
Index of Determinacion =.97226 X
~ Y Slurry pH G 70 F.
Using 25 wt.
Cel Time G 900F.
Estimated 3)
Sodium 31 sulfate Solution (mins.)
Cel Time G 900F.
2.4 16 15.3 1.7 5
6.8
,3 3.8 1.5 1.4
,4 3.2 1.3 3
1.9 Equation for curvilinear fit of raw data.
Shown in Figure 2.
Y = -13.8506 + (12.1519X)
Index of Determination =.94999 2
O g
' 'g
..e O
- 39
30 MP U
S194W Qqe.% e4 "To k.ev.I
. \\t
- Tabic 3.
sad 90 F. Cel Times by pH of Vater / A-SET 0
0 70
' Table 3.
Slurries Catalyzed with 3N Sulfuric Acid Y
Estimated X
Gel Time 0 70*F.
Gel Time 6 70 F.
0 Slurry pH G 70 F.
(mins.)
(mins.)
Using 3'I 11,50. _
133.7 118 2.7 21.1 24 1.9 8.5 9
-u 1.6 4.2 6
1.4 4.2 3.5 1.4 1.9 1.5 1.2
~
Shown in Figure 3.
Equation for curvilinear fit of raw data.
Y =.719384 (X 5.26018) Index of Determir.ation =.97931 Estimated Y
x Gel Time G 90 F.
Ge1. Time Q 90 F.
0 Slurry pH @ 90 F.
(mins.)
(mins.)
Using 3N H9504 12.9 13 19 7.9 8
1.6 4.5 5
1.4 4.5 3.5 1.4 1;2 1.5 1.2 Shown in Figure 3.
Equation for curvilinear fit of raw data.
Y = -18.9786 + (16.7857X)
Index of Determination =.98248 h
g he
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'.Qu.\\
g ANEFCO INC. ECOPAC SYSTEM
~
PROCEDURE FOR OH-SITE SOLIDIFICATION OF LOW-LEVEL RADIOACTIVE WASTE AT SEQUOYAH NUCLEAR PLANT
.,t.
P CONTRACT 80P68-161957 ANEFCO CODE B-123 This Procedure describes general operation of the ECOPAC system and the necessary interfacing with Sequoyah Nuclear Plant systems.
l.
1/31/80 Rev.
f
~
i w m me 44 N.j \\ _ r::::L"LL d
p wqmsse cw
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be it t 0-9 70 SCOPE:
Qey, l 1.0 The purpose of this procedure is to describe the general
\\
operations, precautions, and interfacing for the removal and packaging of resin and liquid radwaste from the Sequoyah Nuclear Plant (SNP).
PREREGUISITES:
2.0 All radiation protection standards will be in accordance
' I-with the Radiological Safety Policy and Program of Sequoyah Nuclear Plant, and Code of Federal Regulations, Title 10, ENERGY; Part 20, Standards for Protection Against Radiation.
2.1 All ECOPAC equipment will be checked prior to this operation by the ANEFCO field supervisor.
2.2 Radiation work permit must be completed.
PRECAUTIONS; 3.0 Traumatic safety is of' primary concern throughout the entire operation.
3.1 Radiation limits established by Health Physics section and 10 CFR 20, will be monitored.
l l
3.2 The limiting radiation factors, as applied to this procedure, are the readings on the side of the transfer vehicle.
Dose rates on shielded container will be limited to DOT regulations I
for sole use veh'icle, 200 mr/hr. contact and 10 nr/hr at six feet from truck body.
3.3 Area barriers (l'e. radiation signs} will be posted per 10 CFR :
l i
O it::::. C N ma w
Li $
y_
,. m, n,.-n -
SCNP SI.hg4 Age 41 e4 Qad.t 3.4 wipe tests (i.e. smearable loose contamination) will be performed prior to work and at the finish of the job to establish that this area is within the limits as prescribed by the applicable regulation.
3.5. Waste transfer piping and hose will be blown free when transfer is completed to prevent subsequent plugging, contamination buildup within the lines, and to reduce area
- l.
background radiation levels.
3.6 All ECCPAC connecting hoses will be disconnected and stored when operations are completed.
OPERATIONAL PROCEDURE (Utilize 4.0 thru 4.8 for both Resin and Boric Acid solidification) 4.0 Position cask with empty' disposable liner inside auxiliary build _ng access bay alongside the ANEFCO ECOPAC solidification system.
4.1 Attach ECOPAC loading arm to the liner 2" male dry-break connector.
Verify that the ultra-sonic level detector fits properly into liner port and seal OPW quick disconnect.
4.2 Connect the loading aan acid line to the liner 1/2" male dry-break connector.
4.3 Connect the dewatering system hose to the ECOPAC system u.r compressor outlet.
4.4 Connect two air hoses from plant service air to the EC ' ?AC system.
110 VAC.
4.5 Connect both electrical supplies to ECOPAC system.
60 h:; 220 VAC 3 phase, 60 hz).
i' double Couple U-F tank to the 1 1/2" Sandpiper pump using 4.6 OPW female quick-disconnect hose. -
4 I
N k_ h~ c.
=.5 46, f-tsu 3----~~v-1
SbND s 7.
4 W Q,, 43 og *ro Qev.
4.7 Couple U-F Sandpiper pump to ECOPAC system using 25' double OPW female quick-disconnect hose.
4.8 Attach air supply from ECOPAC system outlet to the U-F Sandpiper pump.
RESIN SOLIDIFICATIOE 5.0 Slide hose containment over resin-t--
i.sse prior to attaching hose to SNP discharge fi' JCV SCO.., g chree absorbant pads 5.0.1 Tapa hose containment to host e
into the containment, then tr seal the containment to a
SNP pipe (refer to drawing SNP-1).
5.1 Connect the SNP resin. outlet hose to the catch tank top s
inlet quick-disconnect and contain per drawing SNP-1.
5.2 Connect the resin catch tank discharge pump outlet (Moyno) to the ECOPAC system utilizing the 25' female quick disconnect
. flanged hose an'd contain per drawing S,P-1.
N 5.3 Connect the resin catch tank well point to the dewatering pump and contain per drawing SNP-1.
5.4 Attach dewatering pump discharge hose to SNP valve number f-CV-770 one. cemple'be-5.5 ANEFCO will indicate when
-9asierr batch of resin can be pumped by SNP to the catch tank.
5.6 SNP should flush / clear resin hose prior to step 5,7 to lower the dose rate as low as reasonably achievable.
Supply 110 vac to the dewatering pump and dewater resin through, 5.7 SNP valve #FtV 'TI tjal Water recovered by dewatering system from catch tank will be pumped to SNP receivingt line.
Supply 220vac,-3 phase 60h.toresinforwarding{!oynopump 5.8 from ECOPAC system.
t.i,). T# Es(W am?m 47 W
S&WP SI-4 t9 Page, 4 A OS 70 E.c, v. I
~
5.9 Connect air sparge hose from ECOPAC system to resin catch tank and sparge for a minimum of 30 minutes prior.to transfer for solidification.
5.10 ANEFCO personnel to solidify the dewatered resin according do the ANEFCO ECOPAC process control plan.
When resin solidification is completed, disconnect the SNP resin outlet hose to the catch tank top inlet and contain per drawing SNP-1.'
Store hose in assigned location.
5.11 Disconnect the catch tank discharge p' ump (Moyno) outlet hose to the ECOPAC system and contain per drawing SNP-1.
Store hose in proper location.
5.12 Disconnect loading arm waste dry-break connector, acid dry-break connector, and ultra-sonic level detector.
Contain opening with safety drip bags.
5.13 Health Physics Technician will monitor radiation levels and condition of solidified waste in the liners, 5.14 Seal full liners.
Paint one liner cap'with temporary sealed cap for indentification at burial site for subsequent inspection.. Seal other liner caps with lock-cement (permanent).
5.15 Seal cask cover.
BORIC ACID / EVAPORATOR BOTTOMS (Liquid Wastes) 6.0 Slide hose containment over bori: acid-transfer hose prior to attaching hose to SNP discharge line number 6.1 Tape hose containment to hose, add (3) three absorbant pads 1
into the containment then tape and seal the containment to SNP pipe (refer. to drawing SNP-1).
Connect the boric acid transfer hose to the ECOPAC system 6.2 waste inlet and contain per drawing SNP-1.
m en
- Q3qr c
S sn SI A R
% 46 o% 70 Qsv.t 6.3 ANEFCO will notify SNP when ECOPAC system is ready to receive
\\
liquid wastes.
Fdv ~17-40 2.
6.4 SNP to open valve number j\\
for transfer of waste to ECOPAC system.
6.5 iNEFC'O personnel will solidify the liquid wastes according to the ANEFCO ECOPAC Process Control + ten. Preyam.
6.6 ANEFCO will verba ny notify SNP upon receipt of one complete 1.
batch of boric acid so that SNP can terminate pumping waste by closing valve number FCV-77 *i Z, 6.7 After notifying SNP operator, ANEFCO will flush ECOPAC system YdvoDh using SNP domin water -M SNP valve number FCV-77 'Or.
6.8 Disconnect the boric acid transfer hose f$om both the ECOPAC vM v6 F(V-77-'! 0 7.
waste inlet and the SNP discharge lineAnumber A using the containment method illustrated in drawing SNP-1 Store hoses.
in proper location.
6.9 Disconnect loading arm waste dry-break connector, acid dry-break connector, and ultra-sonic level detector.
Contain op'enings with safety drip bags.
6.10 Health Physics technicianswill monitor radiation levels,.
6.11 Seal full liners.
Paint one liner cap with temporary seal for identification at the burial site for' subsequent inspection.
Seal other liner caps with lock-ccment (permanent),
6.12 Seal cask cover.
l l
1
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... e BORIC ACib-SOLIDIFICATION SCHEMATIC 51
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Pg 49 ot '73 EXPERIMENTAL SIMULATIONS OF RADIOACTIVE ley.\\
WASTF. AND A-SET RESIN
- FORMULAT.T.ONS Experimental formulations for the solidification of selected simulated wastes with A-Set Resin has been determined.
These" formulations,
, attempt; to incorporate, a relatively maximum quantity of waste while consistently producing a solidified product.
Solidified products were obtained for all waste types tested although some difficulties were encountered at high waste to solidification agent ratios for
/
sulfate wastes to UF.
The addition of suf ficient acid catalyst -
to waste-UF mixtures to achieve a pH of 1.5 0.5 was found to produce a more rapid and consistent polymedzation and also permit a higher waste to UF ratio for most wastes. Care should be exercised to assume that a thorou'gh homogeneous blend is achieved.
Mixing equipment must be kept free from foreign matter and cured adhesive build-up.
The free standing water in simulated wastes solidified with UF was measured and found to vary from zero to 25.4 wt.%.
Adjustment of the waste to UF mixture pH to 1.5t 0.5 by the addition of sufficient acid catalyst resulted in a significant reduction in the quantity of free standing water.
The free standing water was found to have a pH approximating that of'the water to UF mixture after iddition of the catalyst.
Thepolymehzationreactionisacidcatalyzedandisbothtemperature and pH dependent.
Low waste to UF mixture pH and high ambient temperature decrease the time required for solidification.
A pH of 1.5 0.5 in the waste-UF mixture is desirable; however, the amountofcatalyst'neededmustbedeterminedforeach)falte.
Such m.ixtures will begin to gel in several minutes and are generally well solidified within thirty minutes.
Dilute solutions of strong acids maybe used to adjust the pH of highly buffered waste-UF mixtures.
The use of strong acid solutions must be done with care to avoid premature gelling of the mixture.
ConcentvafLdsoduimsulfatewastesmaycauseerraticsettinginUF.
Additions of less than ten weight percent sodium sulfate or small amounts of calcium chloride are reported to eliminate this problem.-
The addition of 2 wt.% calcium chloride to UF containing sodium l eacock, H.W.
and Riches, J.W.,
Naste Solidification-Cement or H
.Ureaformaldehyde, American Society of Mechanical Engineers, 74-WA/NE-9, 1974.
- RegisteredThademark 5.3
. L \\,' r ='?r -- L -Q -
-r
SQMP SI- @
% c $0 o4 70
%.i sulfate wastes was found to increase the permissible waste /A-set Resin ratio.. The addition of sufficient cataly'st to produce a pH of 1.5* 0.5 in the waste-UF mixture allows an increase in the waste /UF ratio for most wastos.
TABLE 1
-A Simulated Waste Tyocs Included in the Experimental Proaram 1.
Bead Rosin Waste 2.
BWR Precoat Filter Cake a.
Powdered Resin b.
Diatomaceous Earth
~
3.
Forced Recirculation Evaporator Concentrates -
a.
BWR Chemical Regenerative Waste b.
PWR Chemical Regenerative Waste c.
Boric Acid Waste d.
Decontamination Waste 4.
Thin Film Evaporator Concentrates
'BWR Chemical Regenerative Waste a.
b.
PWR Chemical Regenerative Waste c.
Bor.ic Acid Waste d.
Decontamination Waste 54 7.......
1.
i
6Q WP SI. A tel
$\\ o Q '7 0 s
64.i
\\
TA31.E 2 Simulated Waste Tormulations 1.
br.AD MSIN WASTE e
Material Weight Percent, s 50 Water
' Bead Resin (2KN-150)*
5").
700T 4 /,
Temperature PH
. 7
.:n 2a.
BWR PRECOAT FILTER CAXE (WITH POWDERED RESIN)
Weight Percent Material
. _in Filter Cak'e, s wa'ter 50.
Anion Powdered Ecsin (PAO)b 20.
Cation Fowdered Ket.in (PCH)b 5.
20.
CrudC Sodica chloride 5.
C 7C F Temperature
- pH 7
2b.
BWR FRICOAT FILTER CAXE (WITH DIA70.9CF.OUS T.'JTH)
Weight Percent Material In Filter Cake, s Water 50.
Diatomaceous Earth 40.
Crude go, 70*T
. Temperature
~
pH
}
3a.
BWR CHEMICAL EIGE!.~ERATIVE WASTE OF A FOACED RECIRCULATIOtt EVAPORATOR Weight Percent Material in n aoorator Bottens, s 75.
Water Sodium sulfate 22.9 Sodium Chloride 2.0 Crude o,1 370*P Temperature 6
pH e
O Gt N D SI A tch e
Ap. 5 'J. c4 70 iE.ev. \\
CR TwR CHF.HCAL RECDfERATIVC WASTE OF A TORCED MECIRCUT 3b.
Weight Percent in Evaporator Bottoms. %
)aterial
. v' 73.4 Water Sodium Sulfate 9.6 Ju. onium Sulfate 2.0 sodiwa Chloride 0.1 CrudC 0
170 7 Tcir.pe1 a t ur e 2.5 to 4.0 PH NR BORIC ACID WASTE OF A FORCED RECIRCU1ATIort EVJJORA 3c.
Weight Percent t
in Evaoorator Bottoms,
?!aterial 87.9 Water 12.0 Boric Acid O.1 C
0 Caud 170 T Tc-epera ture
- -3.5 PH Decor. tar.I!!ATION WASTE OF A FORCED RECIRCULATION ENAPOFA1C 3d.
Weight Percent 4
in Evaporator Pottoms.
}:aterial s
,8 0.
Water g,4 d
FUTEK-700 5.
EDTA 5.
Citric Acid 0.2 C
Crud 0.2 Hydtaulic Cil No. 2 0.2 Lubricating Oil No. 20 170 r Tosperature 5
pH FII.M E".'APCRA'!CR E}1 CHEMICAL FIGENZPATIVE WASTE 07 A THIt:
da.
Weight Percent
_in Evaporator Botto:ss.
r.aterial 50.
Water 45.8 Sodium Sulfate 4.0 Sodium Ch3oride 0.2 C
Czvd 150 to 250*r
~
Tenperature 6
PH 56
bk M9 SI-A m Qe. 3 % o Sr 70
.kkV. I
\\
Ab.
Nd CHTEICAL RECEf 7.RATIVE WAS.TE. O. F A 114.I.N..F.II.M EVAJ'OT<ATO._R Weight Percent Mat'erial in Evanorator Pattoms, s Water 50 Sodium Sulfate 29.
A.:nonium sulfate 16.8 Sodium Chloride 4.0 Crud 0.2 C
Tcmperature 150 to 2500r pH 1.8 to 4.0
.g 4c.
BOMTC ACID WASTE OF A 11tItt PII.M EVAPOPAltR Weight Percent Material in Evaoorator Ecttoms, s
~
Water 50.
Boric Acid 49.8 C
Crud 0.2 Terapera tur e 150 to 2500F pH
- .2.5 to 3.5 44.
T;ECONTAMItu.TICN WASTE OF A THIN PII.M EVAPORA1CR
. Weight Percent Material in Evaporator Bottoms, s Water 50.
htTEK-700d 20 EDTA 9.8 Citric Acid 19.
CnadC 0.2 Hydraulic 011 12o. 2 0.5 Lubricating oil No. 20 0.5 0
150 to 250 T Te.:spera ture pH 5
a Td a ar.d Hans Co.,
Philadelphia, Pa. 19105 b Ecodyne Corp., Union, N.J. 07083 C fine air cleaner test dust no. 3542094, AC Spark Plug Divisicn, General r.otors Corp., Flint, Michigan 48556 d coEpound for the dissolution of calciuo sulfate scale, Nuclear Technology l
Corp., hston, Conn. 06231 l
l I
f7 i
s a
e e
6kM9 s.t - A w
,Pqe 54 et to b.\\
\\-
TABLE 4 Tormulations for the Soldification. of BWR and PWR Vastes Using A-Set Resin.
25 Wt.% Sodium Bisulfate (A.nhydrous)
Agueous Cata1 st Solution Added to 2.0_ Volume I of the Waste-UF Mixture 1
Weight Katio Approximate V st e_,Ty,pe Wa st e t o A-Se t Solidification Time Co=:e n t s 3
' l' 1.
Ecad Resin 2.2 15 minutes 2.
EVR Precoat
-te Filter Cake a.
Fovdered Resin 2.0 15 minutes b.
Uf ato=aceous Earth 2.0
,30 minutes 3.
Forced Recirculation Evaporator Concentrates a.
SVR Chemical 1.2 25 minutes Regenerative Raste b.
PWR Chemical 1.2 20 minutes Regenerative Waste c.
Soric Acid Waste 1.0 15 minutes d.
Decontamination Vasta 1.1 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> s
4 Thin Film Evaporator se Conc e n tra t es a.
EVR Chemical.
1.0 30 minutes 2 ut.% CaC12 added Regenerative Uaste 1.2 30 minutes b.
PVR Checical 0.7 30 minutes 1.5 30 minutes 2 ve.% CaC12 added l
Regenerative Waste c.
Soric Acid Waste 1.0 30 minutes d.
Decontamination Waste 1.5 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 1
1 d
' 6C. MD T*
s Am
@cge 56 09' 70 k.e. \\
\\
TAB LE__ 5_
Tormtations for the Solidif f eation of BWR and PWR Wastes Using i
- A - 5'e t Resin.
Suffidient 25 Wt.: Sodium 31 sulfate (Anhydrous) l A_gueous CataA st Solution Added to Achieve _oM = 1.5 0.5 in the Waste-UF Mixture Weight Ratio Approximate Volume I Waste Type _
Vaste to UF Solidifi,c,a, tion Time
!!aHS0g Solution Added 1.
had Resin 2.2 15 minutes 1.8
~
2.
l'.~R P r e c o Tilt er Cake a.
Powdered resin 2.0 15 minutes 1.9 b.
Diato accous Earth 2.0 15 minutes 3.0 3.
Forced Kecirculation Evaporator Concentra tes 3VR 'Chenical 1.3 15 minutes
,3.1 a.
Kegenerative Waste b.
PL*R Chemical 1.3 15 minutes 2.9 Regenerative Waste c.
Soric Acid Waste 1.2 10 minutes 0.8
- d.
Decontamination W4ste 1.2 30 c,inute's 10.5 4 " Win Film Evaporator Concentrates a.
EVR Chemical 1.5 20 minutes
- 1. 5 Regenerative Waste b.
FWA Chemical 1.0 20 minutes 1.7 Kegenerative Waste c.
Soric Acid k*aste 1.2 20 minutes 1.4
.d.
Decontamination Waste 1.5 30 minutes 13.3 i
e O
W 59 e
N#
- t..e Technical Service Report SI-4 \\9
%e, Se o% ~70 kev. l Data and Dir.cussion_:
Tabics 1 through 3 as described below show the raw data obtained in these catalyst. studies of A.%t Resin 2 as well.
es their conversion to a curvilinear fit in graphing.
Table 1:
pl! Heasurements by mis. of Catalyst for 200 ml. Slurrics of IJater/CASCO-RESIN 2 Table 2:
700 and 900F. Cel Times by pil of Water /A-Set somin' 2 Slurries Catalyzed with 25% Sodium Bisulfate and 900F. Cel Times by pH of' Water /A.%te % sin' 2 Slurries Table 3:
700 Catalyzed with 3N Sulfuric Acid L
Figures 1 through 3 attached are graphical portrayals of Tables 1 through 3 and nsed no further description.
e 9
9 g
4 e
e G
8 4 'e e
- )
O e
g S
S e
ee 8
O e
O e
8 e
e e
6 e
e e
a e
e e
e e
g e
)
9 4
g 9
, = -
Teclinica,1 Snrvice iteporc
- 3. g e
a>1, 4 M Cage 57 of 7e tev.I e
for pit !!casure..:nts by mis. of Catalyst Table 1:
200 ud. Slurries of Water /A, Set Fasin 2 Y
., X til.,of 25% uc.
Sodium Bisulfate pit of S1::rry 0 70 F.
Estimated pil 0
2.4 2.4 2
1.7 1.7 4
1.5 1.5
' I' 6
1.4 1.4
~
8 1.3 1.3 10 Shown in Figure 1.
Equation for curvilinear fic of raw data.
Y = 1.02522 + (.0415589X)
Index of Determination =.99724 Y
0 Estimated oH X
pH of Slur:v @ 70 F.
111. of 3N 11,504 2.7 2.7 1
1.9 1.9 2
1.6 1.6 3
1.5 1.4 4
1.3 1.4 6
1,2 10
1, 2' Shown in Figure'1.
Equation' for curvilinear fit of raw data.
~
Y = 1.05443 + (1.64827/X)
Indax of Deter:aination =.99304 e
s e
O 3
G/-
I,.
SC ND Tschnical Service Report SI 46
&ge.5.9 of 70 Qev.I.
and 90*F. Cel Times by pit of yater/A-Set Rosin 2 0
Slurries Catalyzed wich 25% Sodium' Bisulf ate 70 Table 2.
Y X
Estimated Slurry )H 0 70 F.
Gel Time G 70 F.
0 Us'ing 25% vt.
(mins.)
Col Time f 70 F.
Sodiu.t F.isulfate Solution 19.4 19..
93 2.4 11 5.7 1.7 5
'A 5.0 1.5 4
~
3.5 1.4 4
.:o 1.3 Shown in Figure 2.
Equuion, for curvilinear fit of rau data.
Y = -15.2101 + (14.4304X)' Index of Determination =.97226
~
Y
'I X
0 Estimated Slurry pH G 70 F.
Cel Time 0 90 F.
Cel Time G 90 F.
0 Using 25% vt.
(mins.)
Sodium Bisulfate Solution
.s 15.3 '
j 16 6.8 2.4 5
1.7
", ' 3.8
,3 3.3 1.5
,4 1.9 1.4 3
1.3 Shawn in Figure 2.
Equation for curvilinear fit of rav data.
Index of Determination =.94999 Y = -13.8506 + (12.1519X) h e
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