ML18033A361

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Effluent & Waste Disposal Semiannual Rept,Jan-June 1988.
ML18033A361
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 06/30/1988
From:
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18033A362 List:
References
NUDOCS 8809080334
Download: ML18033A361 (25)
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ENCLOSURE 1 TENNESSEE VALLEY AUTHORITY SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT BROWNS FERRY NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY THROUGH JUNE 1988 88090803 4. 880831 ppp PDOCK 050002 pDc R

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e ENCLOSURE EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

SUMMARY

JANUARY THROUGH JUNE 1988 The radioactive effluents for the first half of 1988 were normal for a three unit boiling water reactor plant in its third year of an extended outage.

Because of the extended outage, only radionuclides with a long half-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 t particulate matter.

The quantity of radionuclides released in liquid effluents during this extended outage is a significant fraction of the quantities released during normal power operation. 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 10CFR20 Appendix B and 10CFR50 Appendix I limits during the first half of 1988.

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION JANUARY THROUGH JUNE 1988 Re ulato Limits A. Fission and Activation Gases in Gaseous Effluent:

1. The average release rate of fission and activation gases is regulated by the dose limits of 10CFR50 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 to g 5 mrad for gamma radiation and g 10 mrad for beta calendar'uarter radiation; and during any calendar year to g 10 mrad for gamma radiation and g 20 mrad for beta radiation.

B and C. Iodines and Particulates with Half-Lives Greater Than 8 Days in Gaseous Effluents.

1. The average release rate of iodines and particulates in gaseous effluent is regulated by the dose limits of 10CFR50 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 g 7.5 mrem, and during any calendar year to g 15 mrem.

D. Liquid Effluents

1. The average release rate of radioactive liquid effluents is regulated by the dose limits of 10CFR50 Appendix I. The dose 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.

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION JANUARY THROUGH JUNE 1988 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 10CFR20 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 Section 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 10CFR20 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 Sections II. B and C.l. The instantaneous iodine and particulate release rates are limited by the following equation:

+ 94 <1 2.19 35.7 Q3 = The release rate from the building exhaust vents in mCi/sec Q4 = The release rate from the main stack in mCi/sec.

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION JANUARY THROUGH JUNE 1988 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 10CFR 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 mCi/ml total activity.

III. Average Energy Not applicable IV. Measurements and A roximations 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.

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION JANUARY THROUGH JUNE 1988 IV. Measurements and A roximations of Total 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 Units FIRST SECOND uarter A. Liquid

1. Number of batches released 98 109 Each

. 2. Total time period for batch releases 26259 28930 Minutes

3. Maximum time period for a batch release 385 455 Minutes
4. Average time period for batch releases 267 266 Minutes
5. Minimum time period for a batch release 140 5 Minutes
6. Average stream flow during period of release of effluent into a flowing stream 32020 10850 cu.ft./s B. Gaseous None

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY THROUGH JUNE 1988 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES First Second Unit guarter guarter  % Error A. Fission and Activation Products

1. Total Releases Curies 3.62E-02 8.25E-02 9
2. Average Diluted Concentration During Period mCi/ml 8.92E-10 1.88E-09
3. Percent of Applicable Limit (1.00E-7 mCi/ml) 8.92E-01 1.88E+00 B. Tritium
1. Total Releases Curies 2.94E-01 4.40E-01
2. Average Diluted Concentration During Period mCi/ml 7.24E-09 1.00E-08
3. Percent of Applicable Limit (3E-03 mCi/ml) 2.41E-04 3.35E-04 Dissolved and Entrained Noble Gasesl
1. Total Releases Curies 1.60E-03 <2.45E-03 8
2. Average Diluted Concentration During Period mCi/ml 3.94E-11 <5.59E-ll
3. Percent of Applicable Limit (2E-04 mCi/ml) 1.97E-05 D. Gross Alpha Radioactivity
1. Total Releases Curies 9.28E-04 2.69E-04 48
2. Average Diluted Concentration During Period mCi/ml 2.29E-ll 6.14E-12 E. Volume of Waste Release (Before dilution) Liters 1.03E+07 1.15E+07 3 F. Volume of Dilution Water for Period Liters 4.06E+10 4.38E+10 10 G. Total CCW flov for Six Months 117.2 gigagallons 1 Includes Xe-133, Xe-135, and others.

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID RELEASES FOR JANUARY THROUGH JUNE 1988 BATCH MODE

~Isoto 6 First Quarter Second Quarter (Required by Re@ Guide 1.21) Unit Curies Unit Curies Cr-51 <4.62E-03 2.56E-05

2. Mn-54 2.55E-05 1.40E-04 3~ Co-58 <5.11E-04 <8.64E-04
4. Fe-59 <9.44E-04 <1.86E-03
5. Co-60 4.71E-03 1.66E-02
6. Zn-65 1.80E-03 2.62E-03 7 ~ Nb-95 <4.61E-04 <7.67E-04
8. Zr-95 <8.25E-04 <1.37E-03
9. Mo-Tc-99m <4.19E-04 <6.39E-04
10. I-131 <6.03E-04 <9.66E-04 ll. Xe-133 <1.16E-03 <1.93E-03
12. Cs-134 6.45E-03 1.28E-02
13. Ze-135 <3.32E-04 <5.21E-04
14. Cs-137 2.32E-02 5.02E-02
15. Ba-140 <2.22E-03 <3.67E-03
16. La-140 <3.04E-04 <3.54E-04
17. Ce-141, <7.11E-04 <1.14E-03
18. Sr-89 <3.93E-04 <3.05E-04
19. Sr-90 <2.10E-04 <1.81E-04

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID RELEASES FOR JANUARY THROUGH JUNE 1988 BATCH MODE

~toto e First Quarter Second Quarter Others (Not Required by Reg Guide 1.21) Unit Curies Unit Curies

1. Sb-125 1.52E-05 1.81E-04 2 ~ Kr-85 1.60E-03
3. Fe-55 <3e16E-03 This section was prepared principally by K. K. Richards

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY THROUGH JUNE 19881 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES First Second Summation of All Releases U~n t guarter guarter ~% Erro A. Fission and Activation Gases

1. Total Releases Ci <2.55E+02 <2.83E+02 45
2. Average Release Rate for Period mCi/sec <3.24E+Ol <3.60E+01
3. Percent of T.S. Limit

(.15 Ci/sec)

B. Iodines

1. Total Iodine-131 Ci <2.54E-04 <1.40E-04 36
2. Average Release Rate for Period mCi/sec <3.23E-05 <1.78E-05
3. Percent of T.S. Limit (2.19 mCi/sec)

~ c. Particulates Particulates with Half-Lives

>8 days Ci 2.62E-05 1.24E-03 35

2. Avg. Release Rate for Period mCi/sec 3.33E-06 1.58E-04
3. Percent of T.S. Limit 1.52E-04 7.20E-03 (2.19 mCi/Sec)
4. Gross Alpha Radioactivity Ci 1.22E-06 1.18E-06 D. Tritium
1. Total Releases Ci 9.23E-02 1.58E-01 21 2 ~ Average Release Rate for Period mCi/sec 1.17E-02 2.01E-02
3. Percent of T.S. Limit 5.36E-01 9.18E-01 (2.19 mCi/sec)
4. Ground Level Release 9.14E-02 1.58E-01
5. Elevated Release Ci 8.84E-04 1.95E-04 1 Reporting period 182 days.

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY THROUGH JUNE 1988 GASEOUS EFFLUENTS ELEVATED RELEASE First Second Unit guarter guarter Fission Gases Krypton-85m Ci <2.80E-01 <2.42E-01 Krypton-85 <1.11E+02 <9.33E+01 Krypton-87 Ci <5.70E-01 <6.67E-01 Krypton-88 Ci <6.73E-01 <9.90E-01 Xenon-133 Ci <4.50E-01 <6.58E-01 Xenon-135m Ci <5.06E-01 <3.38E-01 Xenon-135 Ci <2.21E-01 <3.03E-01 Xenon-138 Ci <1.50E+00 <2.25E+00 Total for Period Ci <1.15E+02 <9.88E+Ol Iodines Iodine-131 Ci <1.01E-05 <5.46E-06 Iodine-133 Ci <1.49E-04 <5.47E-05 Iodine-135 Ci <1.43E-01 <2.14E-01 Total for Period Ci <1.43E-01 <2.14E-01

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY THROUGH JUNE 1988 GASEOUS EFFLUENTS ELEVATED RELEASE (Continued)

First Second Unit guarter guarter

3. Particulates Sr-891 Ci <1.06E-06 <8.74E-07 Sr-901 <4.21E-07 <3.71E-07 Cs-134 Ci <8.10E-06 <5.39E-06 Cs-137 Ci <5.76E-06 <1.06E-05 Ba-140 Ci <3.10E-05 <2.02E-05 La-140 Ci <9.46E-06 <1.47E-06 Co-60 Ci 2.62E-05 3.13E-05 Total for Period Ci 2.62E-05 3.13E-05 Tritium Ci 8.84E-04 1.95E-04 1 Predicted estimation of releases.

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY THROUGH JUNE 1988 GASEOUS EFFLUENTS GROUND LEVEL RELEASE First Second Unit Quarter Quarter Fission Gases Krypton-85m Ci <3.71E-01 <4.14E-01 Krypton-85 Ci <1.31E+02 <1.74E+02 Krypton-87 Ci <9.36E-01 <1.19E+00 Krypton-88 Ci <1.64E+00 <1.36E+00 Xenon-133 Ci <1.32E+00 <9.99E-01 Xenon-135m Ci <1.05E+00 <2.01E+00 Xenon-135 Ci <4.51E-01 <3.04E-01 Xenon-138 Ci <2.98E+00 <4.21E+00 Total for Period Ci <1.40E+02 <1.85E+02 Iodine-131 Ci <2.44E-04 <1.34E-04 Iodine-133 <8.13E-04 <1.45E-03 Iodine-135 Ci <7.60E-01 <1.39E+00 Total for Period Ci <7.61E-Ol <1.39E+00 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY THROUGH JUNE 1988 GASEOUS EFFLUENTS GROUND LEVEL RELEASE (Continued)'

First Second Unit guarter guarter 3~ Particulates Sr-891 Ci <6.69E-06 <4.81E-05 Sr-901 Ci <3.61E-06 <1.15E-05 Cs-134. Ci <1.64E-04 2.20E-05 Cs-137 Ci <2.67E-04 8.40E-05 Ba-140 Ci <7.61E-04 <1.24E-03 a

La-140 Ci <9.04E-05 <1.33E-04 Co-60 Ci 1.10E-03 Total for Period Ci <1.29E-03 1.21E-03

4. Tritium Ci 9.15E-02 1.58E-01 1 Predicted estimation of releases.

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY THROUGH JUNE 1988 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Solid Waste Shipped Off-Site for Burial or Disposal (Not Irradiated Fuel)

1. Type of Waste Units Amount Error  %
a. Spent resins, filter sludges, m3 1.21E+02 evaporator bottoms, etc. Ci 1.68E+02 1.50E+01
b. Dry compressible waste, m3 2.58E+02 contaminated equip., etc. Ci 1.53E+01 1.50E+Ol c~ Irradiated components, m3 O.OOE+00 control rods, etc. Ci O.OOE+00 N/A
d. Other m3 O.OOE+00 Ci O.OOE+00 N/A
2. Estimate-of major nuclide compositions (by type of waste)
a. Spent resins, filter sludges, evaporator bottoms, etc.

Nuclide Unit Unit

l. Zinc-65 (1) 1.09E+01 Ci 1.83E+01
2. Cesium-137 3.82E+01 Ci 6.41E+01 3~ Cesium-134 (1) 1.08E+Ol Ci 1.81E+01
4. Cobalt:-60 2.67E+Ol Ci 4.48E+Ol
9. Manganese-54 (1) 8.40E-02 Ci 1.41E-01
11. Iron-55 (2) 9.11E+00 Ci 1.53E+01
12. Other Nuclides ( 4.15E+00 Ci 6.96E+00 (1) Measured (2) Estimated through the use of scaling factors EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY THROUGH JUNE 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.

Nuclide Unit Unit Zin -65 1.80E+01 Ci 2.75E+00 2~ Cesium-137 ( 8.65E+00 Ci 1.32E+00

3. Cesium-134 7.11E+00 Ci 1.09E+00 4~ Chromium-51 (2) 1.12E+Ol Ci 1.70E+00
5. Cobalt-60 2.06E+01 Ci 3.14E+00
6. Iron-55 2.48E+Ol Ci 3.79E+00 7~ Iron-59 1.79E+00 Ci 2.74E-Ol
8. Manganese-54 (2) 4.08E+00 Ci 6.24E-Ol
10. Silver-110m (2) 1.22E+00 Ci 1.87E-01 Niobium-95 2.13E+00 Ci 3.26E-01
12. Other Nuclides (2) 4.92E-01 Ci 7.51E-02 (1) Measured (2) 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 Mode of Transportation Destination NONE N/A N/A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY THROUGH JUNE 1988 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (Continued)

C. Waste Sources, Burial Class and Type quantity, Container Type, Total Volume in Cubic Feet and Number of Containers Used.

Type of Type Burial Container Number of Disposal Waste uantit C ass e Containers Volume DEWATERED (Resin)

RX CLEANUP A-LSA A-Stable HIC 1 120.3 B-LSA B-Stable HIC 1 120.3 COND/WASTE A-LSA A-Stable HIC 20 3287.9 B-LSA B-Stable HIC 4 776.4 (Filters) N/A N/A N/A NONE ~ NONE DRY ACTIVE WASTE (Compacted)

DRUM A-LSA A-Unstable STC 241 1807.5 BOX A-LSA A-Unstable STC 45 4185.0 (Uncompacted)

DRUM A-LSA A-Unstable STC 6 45.0 BOX A-LSA A-Unstable STC 31 3111.8 SOLIDIFIED N/A N/A N/A NONE NONE ABSORBED N/A N/A N/A NONE NONE Solidification agent used: NONE Absorbents used: NONE

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