ML18033A914
| ML18033A914 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 06/30/1989 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML18033A913 | List: |
| References | |
| NUDOCS 8909050470 | |
| Download: ML18033A914 (27) | |
Text
e ENCLOSURE 1
TENNESSEE VALLEY AUTHORITY SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT BROWNS FERRY NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY THROUGH JUNE 1989 S909050470 890S30 PDR ADOCK 05000259 PDC
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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT
SUMMARY
JANUARY THROUGH JUNE 1989 The radioactive effluents for the first half of 1989 were normal for a three unit boiling water reactor plant in its fourth year of an extended outage.
Because of the extended
- outage, only radionuclides with a long halE-life (longer than a few months) have not decayed away and are being released to the environment.
The radioactive decay is particularly significant for gaseous effluents because no fission gases or radioactive iodines are being released.
The only radioactive gaseous releases are very small quantities of particulate matter.
The radioactivity being released now in liquid effluents is primarily long half-life radionuclides that have been deposited on the surfaces of piping and components.
During normal outage work this radioactivity is removed by process water that is purified and released.to the river.
The water purification process is unable to remove all the radioactivity before it is released to the river.
The release of radioactive material to the environment from Browns Ferry Nuclear Plant has been a small fraction of the 10 CFR 20 Appendix B and 10 CFR 50 Appendix I limits during the first half of 1989.
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EFFLUENT AND HASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION JANUARY THROUGH JUNE 1989 Re ulato Limits A. Fission and Activation Gases in Gaseous Effluent:
1.
The release of fission and activation gases is regulated by the dose limits of 10 CFR 50 Appendix I.
The air dose to areas at and beyond the site boundary due to noble gases released in gaseous effluents per unit shall be limited during any calendar quarter to g 5 mrad for gamma radiation and g 10 mrad for beta radiation; and during any calendar year to g 10 mrad for gamma radiation and g 20 mrad for beta radiation.
Band C
Iodines and Particulates with half lives greater than eight days in gaseous effluents.
1.
The release of iodines and particulates in gaseous effluent is regulated by the dose limits of 10 CFR 50 Appendix I.
The dose to a member of the public from radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases with half-lives greater than 8 days in gaseous effluent released per unit to area at and beyond the site boundary shall be limited to any organ during any calendar quarter to S 7.5 mrem, and during any calendar year to S 15 mrem.
D. Liquid Effluents 1.
The release of radioactive liquid effluents is regulated by the dose limits of 10 CFR 50 Appendix I.
The doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from each unit to unrestricted areas shall be limited during any calendar quarter to g 1.5 mrem to the total body and 5
mrem to any organ and, during any calendar year to 3 mrem to the total body and
< 10 mrem to any organ.
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EFFLUENT AND MASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION JANUARY THROUGH JUNE 1989 Maximum Permissible Concentrations A. Fission and Activation Gases in Gaseous Effluent 1.
The instantaneous release rate of fission and activation gases is regulated by the dose rate limit of 10 CFR 20 Appendix B.
The dose rate at any time to areas at and beyond the site boundary due to noble gases released in gaseous effluents from the site shall be limited to
< 500 mrem/year to the total body and
< 3000 mrem/year to the skin.
2.
The BFN Offsite Dose Calculation Manual (ODCM) determines the maximum noble gas release rate based upon the dose rate limits in II.A.l.
The instantaneous noble gas release rates are limited by the following equation:
gl
+
g2 1
0.15 14.4 Ql = The release rate from the building exhaust vents in Ci/sec.
Q2 = The release rate from the main stack in Ci/sec.
B and C.
Iodines and Particulates with Half Lives Greater than 8 Days in Gaseous Effluents.
1.
The instantaneous release rate of particulates and iodines is regulated by the dose rate limit of 10 CFR 20 Appendix B.
The dose rate at any time to areas at and beyond the site boundary due to I-131, I-133, H-3 and particulates with greater than eight days half-lives released in gaseous effluents from the site shall be limited to <1500 mrem/yr to any organ.
2 The BFN ODCM determines the maximum particulate and iodine release rate based upon the dose rate limit of II. B and C.l. The instantaneous iodine and particulate release rates are limited by the following equation:
g3
+
Q4
<1 2.19 35.7 Q3 = The release rate from the building exhaust vents in micro Ci/sec Q4 = The release rate from the main stack in micro Ci/sec.
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0 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION JANUARY THROUGH JUNE 1989 D. Liquid Effluents 1.
The concentration of radionuclides in liquid effluents released at any time from the site to unrestricted areas shall be limited to the concentrations specified in 10 CFR 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases.
2.
For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 pCi/ml total activity.
III.
Average Energy Not applicable IV.
Measurements a d rox matio s of Total Radioactivit A. Fission and Activation Gases:
1.
Noble gases in the building vent and stack, gaseous effluent are continuously monitored.
The flow rate of the stack is continuously monitored and the building vent effluent flow rates are calculated once a shift based on the configuration of operating exhaust fans.
The flow rate data is consolidated weekly to determine the volume of airborne effluent released from the plant.
The noble gas monitor data is consolidated monthly to determine the total curies of noble gases released during the month.
2.
Gas grab samples are taken and analyzed monthly to determine the relative noble gas activity concentrations.
This information is used to apportion the total curies of noble gases released between different noble gas radionuclides.
3.
The tritium concentration is determined by the analysis of a monthly grab sample for each release point.
B and C.
Iodines and Particulates 1.
Iodines and particulates are continuously sampled on impregnated charcoal filters and particulate filters, respectively.
The charcoal and particulate samples are replaced at least weekly and analyzed to determine specific activity concentrations.
The specific activity concentrations and vent flow rate data are used weekly to verify that release rate limits were not exceeded.
The specific activity concentrations and total volume of gaseous effluent are used on a monthly basis to determine the total curies of each particulate and iodine released during the month.
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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION JANUARY THROUGH JUNE 1989 IV.
Measureme ts and A
roximat ons o
Tota Radioactivit (Continued) 2.
The gross alpha concentration is determined by analysis of a monthly particulate filter composite sample and strontium -89 and
-90 are determined by analysis of a quarterly particulate filter composite sample for each release point.
D. Liquid Effluents 1.
The gamma ray emitting radionuclide concentrations are determined for each batch by gamma ray spectroscopy analysis of a grab sample.
The allowable release rate is calculated for each batch based upon the known dilution flow.
The flow rate of the liquid effluent is continuously monitored and the total volume released in each batch is determined.
The total gamma activity released in each batch is determined by multiplying the radionuclide concentrations by the total volume discharged.
The total gamma activity released during the month is then determined by summing the gamma activity content of each batch discharged during the month.
2.
The gross alpha and tritium concentrations are measured on a monthly composite sample.
The strontium -89 and -90 and iron -55 are measured on a quarterly composite sample.
V.
Batch Value FIRST SECOND Units A. Liquid 1.
Number of batches released 2.
Total time period for batch releases 3.
Maximum time period for a batch release 4.
Average time period for batch releases 5.
Minimum time period for a batch release 109 144 27563 29983 1157 332 251 263 20 121 Each Minutes Minutes Minutes Minutes 6.
Average stream flew during period of release of effluent into a flowing stream 77953 57767 cu. ft./sec B. Gaseous None
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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 0
Unit First Second guarder guarter
~Error JANUARY THROUGH JUNE 1989 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES A.
Fission and Activation Products 1.
Total Releases Curies 5.74E-02 4.54E-02 9
B.
2.
Average Diluted Concentration During Period 3.
Percent of Applicable Limit (1.00E-7 pCi/ml)
Tritium 1.
Total Releases p Ci/ml 1.37E-09 1.00E-09 1.37E+00 1.00E+00 Curies 2.34E-01 2.12E-01 C.
2.
Average Diluted Concentration During Period 3.
Percent of Applicable Limit (3E-03 pCi/ml)
Dissolved and Entrained Noble Gases>
1.
Total Releases pCi/ml 5.60E-09 4.67E-09 1.87E-04 1.56E-04 Curies
<2.94E-03
<2.63E-03 8
D.
2.
Average Diluted Concentration During Period 3.
Percent of Applicable Limit (2E-04 pCi/ml)
Gross Alpha Radioactivity 1.
Total Releases pCi/ml
<7.01E-ll
<5.79E-11 Curies
- 1. 94E-05
- 2. 60E-04 48 E.
F.
G.
2.
Average Diluted Concentration During Period Volume of Waste Release (Before dilution)
Volume of Dilution Water for Period Total CCW flow for Six Months pCi/ml 4.64E-13 5.73E-12 Liters 1.19E+07 1.23E+07 3
Liters 4.18E+10 4.54E+10 10 114.68 gigagallons 1 Includes Xe-133, Xe-135, and others.
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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID RELEASES FOR JANUARY THROUGH JUNE 1989 BATCH MODE (Required by REG Guide 1.21)
First Quarter Second Quarter Unit Curies 1.
Cr-51 2.
Mn-54 3.
Co-58 4.
Fe-59 5.
Co-60 6.
Zn-65 7.
Nb-95 8.
Zr-95 9.
Mo-Tc-99m 10.
I-131 ll.
Xe-133 12.
Cs-134 13.
Xe-135 14.
Cs-137 15.
.Ba-140 16.
La-140 17.
Ce-141 18.
Sr-89 19.
<7.13E-03 2.11E-05
<8.03E-04
<1.79E-03 1.20E-02 1.07E-03
<7.65E-04
<1.35E-03
<6.27E-04
<9.29E-04
<2.43E-03 6.02E-03
<5.14E-04 3.82E-02
<3.46E-03
<6.15E-04
<1.07E-03
<3.22E-04
<1.48E-04
<6.30E-03 2.67E-05
<7.05E-04
<1.63E-03 8.79E-03
<2.13E-03
<6.96E-04
<1.22E-03
<5.55E-04
<8.48E-04
<1.80E-03 5.11E-03
<4.60E-04 3.15E-02
<2.94E-03
<5.98E-04
<9.67E-04
<3.49E-04
<1.21E-04
~Isoto e
Quarter Others (Not Required by REG Guide 1.21)
First Quarter Unit Curies Second Unit Curies 1.
Sb-125 2.
Fe-55 3.
Ce-144 4.
Co-57 1.65E-04
<3.05E-03 None found.
None found.
2.97E-05
<3.30E-03 2.87E-05 5.60E-06 This section was prepared principally by K. K. Richards
V II E
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY THROUGH JUNE 19891 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES Summation of All Releases Unit First guarrer Second guarrer
% Error A.
Fission and Activation Gases 1.
Total Releases Ci
<3.02E+02
<3.92E+02 45 2.
Average Release Rate for Period pCi/sec
<3.84E+01
<4.63E+01 B;
3.
Percent of T.S. limit2 Iodines 1.
Total Iodine-131 Ci
<3.21E-04
<6.59E-04 36 C.
2.
Average Release Rate for Period pCi/sec
<4.09E-05
<7.78E-05 3.
Percent of T.S. Limit2 Particulates Particulates with half-lives
>8 days Ci
<2.16E-03 1.54E-04 35 2 ~
Avg. release rate for period pCi/sec
<2.75E-04 1.82E-05 D.
3.
Percent of T.S. limit>
4.
Gross alpha radioactivity Tritium Ci 1.59E-06 3.59E-01 1.36E-06 Total release Ci 1.22E-02 2.
3.
Percent of T.S. limit2 4.
Ground level release 5.
Elevated release 1 Reporting period 189 days.
Ci 6.33E-02 1.08E-02 1.46E-03 Average release rate for period pCi/sec 1.55E-03 6.73E-02 7.95E-03 3.59E-01 6.64E-02 9.30E-04 21 2 The dose rate limit for noble gases shall be
< 500 mrem/year to the total body and
< 3000 mrem/year to the skin and the dose rate limit for I-131, I-133, H-3, and particulates with y eight day half-lives shall be
< 1500 mrem/year to any organ.
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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY THROUGH JUNE 1989 GASEOUS EFFLUENTS ELEVATED RELEASE 1.
Fission Gases Unit First guarder Second guarter Krypton-85m Krypton-85 Krypton-87 Krypton-88 Xenon-133 Xenon-135m Xenon-135 Xenon-138 Total for Period 2.
Iodines Ci Ci Ci Ci Ci Ci Ci Ci Ci
<2.82E-01
<1.22E+02
<9.52E-01
<1.15E+00
<7.50E-01
<8.23E-01
<3.63E-01
<2.13E+00
<1.28E+02
<3.01E-01
<1.48E+02
<1.16E+00
<1.37E+00
<9.56E-01
<1.43E+00
<3.60E-Ol
<2.86E+00
<1.56E+02 Iodine-131 Iodine-133 Iodine-135 Total for Period Ci Ci Ci
<4.92E-05
<1.27E-04
<1.17E-01
<1.17E-01
<2.56E-05
<1.48E-04
<1.61E-Ol
<1.61E-01
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY THROUGH JUNE 1989 GASEOUS EFFLUENTS ELEVATED RELEASE (Continued) 3.
4 ~
Particulates Sr-891 Sr-901 Cs-134 Cs-137 Ba-140 La-140 Total for Period Tritium Unit Ci Ci Ci Ci Ci Ci Ci Ci First Quarter
<6.74E-07
<2.68E-07
<4.47E-05
<4.30E-05
<1.48E-04
<1.15E-04
<3.52E-04 1.46E-03 Second guarder
<8.02E-07
<3.09E-07
<5.53E-05
<5.90E-05
<1.10E-04
<7.13E-05
<2.97E-04 9.30E-04 1 Predicted estimation of releases.
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EFFLUE D WASTE DISPOSAL SEMIANNUAL R r
JANUARY THROUGH JUNE 1989 GASEOUS EFFLUENTS GROUND LEVEL RELEASE Fission Gases Unit First guarter Second guarter Krypton-85m Krypton-85 Krypton-87 Krypton-88 Xenon-133 Xenon-135m Xenon-135 Xenon-138 Ci Ci Ci Ci Ci Ci Ci Total for 'Period Ci
<4.82E-01
<1.62E+02
<1.30E+00
<1.61E+00
<1.50E+00
<1.59E+00
<4.69E-01
<3.84E+00
<1.73E+02
<5.93E-01
<2.21E+02
<1.54E+00
<2.16E+00
<1.62E-01
<3.18E+00
<5.81E-01
<6.41E+00
<2.36E+02 2 ~
Iodines Iodine-131 Iodine-133 Iodine-135 Ci
<2.72E-04
<1.33E-03
<1.89E+00
<6.34E-04
<2.89E-03
<4.79E+00 3.
Particulates Sr-891 Sr-901 Cs-134 Cs-137 Ba-140 La-140 Co-60 Total for Period Ci Unit Ci Ci Ci Ci Ci Ci Ci
<1.89E+00 First guarter
<5.34E-06
<2.03E-06
<3.20E-04
<2.65E-04
<9.27E-04
<2.85E-04
<4.79E+00 Second guarter
<8.79E-05
<2.13E-05
<4.51E-04
<7.99E-04
<1.42E-03
<9.21E-04 1.54E-04 Total for Period Ci Ci 1 Predicted estimation of releases.
<1.80E-03 1.08E-02 1.54E-04 6.64E-02
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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF 1988 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (Continued) 2.
Estimate of major nuclide compositions (by type of waste)
(Continued) a.
Dry compressible
- waste, contaminated equipment, etc.
uc ide Unit Unit 2 ~
3 ~
4 ~
5.
6.
7 ~
8.
10.
12.
Zinc-65 Cesium-137 Cesium-134 Chromium-51
(
Cob lt-60 Iron-55 Iron-59 Manganese-54 (1)
Silver-110m (1)
Niobium-95 Other Nuclides (1) 1.80E%01 Ci 2.75E+00 8.65E+00 Ci 1.32E+00 7.11E+00 Ci 1.09E+00 1.12E+01 Ci 1.70E+00 2.06E+Ol Ci 3.14E+00 2.48E+01 Ci 3.79E+00 1.79E+00 Ci 2.74E-01 4.08E+00 Ci 6.24E-01 1.22E+00 Ci 1.87E-01 2.13Ew00 Ci 3.26E-01 4.92E-01 Ci 7.51E-02 (1)
Estimated through the use of scaling factors c.
Irradiated Components, Control Rods, etc.
NONE d.
Other NONE 3.
Solid waste disposition Number of shipments Mode of Transportation Destination 36 Sole Use Truck
- Barnwell, SC Irradiated Fuel Disposition Number of shipments NONE Mode of Transportation N/A Destination N/A
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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF 1988 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (Continued)
C.
Waste Sources, Burial Class and Type quantity, Container Type, Total Volume in Cubinc Feet and Number of Containers Used.
Type of Waste DEWATERED (Resin)
RX CLEANUP COND/WASTE (Filters)
A-LSA B-LSA A-LSA B-LSA N/A A-Stable B-Stable A-Stable B-Stable N/A HIC HIC HIC HIC N/A 1
1 20 4
NONE 120.3 120.3 3287.9 776.4 NONE Type Burial Container Number of Disposal uantit Class T
e Containers Volume DRY ACTIVE WASTE (Compacted)
DRUM BOX A-LSA A-Unstable A-LSA A-Unstable STC STC 241 45 1807.5 4185.0 (Uncompacted)
DRUM A-LSA A-Unstable BOX A-LSA A-Unstable STC STC 6
31 45.0 3111.8 SOLIDIFIED ABSORBED N/A N/A N/A N/A N/A N/A NONE NONE NONE NONE Solidification agent used:
NONE Absorbents used:
NONE