ML18033B640

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Semiannual Effluent & Waste Disposal Rept,Jul-Dec 1990.
ML18033B640
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 12/31/1990
From:
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18033B638 List:
References
NUDOCS 9103050325
Download: ML18033B640 (23)
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Text

ENCLOSURE 2 TENNESSEE VALLEY AUTHORITY SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT BROWNS FERRY NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL REPORT JULY THROUGH DECEMBER 1990 9103050325 9'10228 PDR ADOCK 05000259 R PDR

Page 2 of 16 ENCLOSURE 2 EFFLUENT AND WASTE DISPOSAL SENIANNUAL REPORT SUMNARY SECOND HALF 1990 The radioactive effluents for the second half of 1990 were normal for a three unit boiling water reactor plant in its 5th 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 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.

tThe 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 second half of 1990.

Page 3 of 16 ENCLOSURE 2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION SECOND HALF 1990 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 5, 10 mrad for beta 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 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 g 7.5 mrem, and during any calendar year to g 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.

Page 4 of 16 ENCLOSURE 2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION SECOND HALF 1990 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.1. 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:

+ g4 <1 2.19 35.7 Q3 = The release rate from the building exhaust vents in pCi/sec Q4 = The release rate from the main stack in pCi/sec.

Page 5 of 16 ENCLOSURE 2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION SECOND HALF 1990 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. easurements a d A oxi at o s of otal 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.

Page 6 of 16 ENCLOSURE 2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION SECOND HALF 1990 IV. Measurements and A rox mat ons of ota 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 THIRD FOURTH A. Liquid

1. Number of batches released 33 30 Each
2. Total time period for batch releases 9,054 8,302 Minutes
3. Maximum time period for a batch release 318 300 Minutes
4. Average time period for batch releases 274 277 Minutes
5. Minimum time period for a batch release 135 129 Minutes
6. Average stream flow during period of release of effluent into a flowing stream>

B. Gaseous None 1 See Radiological Impact Assessment Report.

0 Page 7 of 16 ENCLOSURE 2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SECOND HALF 1990 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES Third Fourth Unit guarter guarter  % Error A. Fission and Activation Products

1. Total Releases Curies 1.35E-01 7.30E-02 9 2~ Average Diluted Concentration During Period pCi/ml 9.85E-09 5.79E-09
3. Percent of Applicable Limit (1.00E-7 pCi/ml) 9.85E+00 5.79E+00 B. Tritium
1. Total Releases Curies 4.54E-02 4.91E-02
2. Average Diluted Concentration During Period pCi/ml 3.31E-09 3.90E-09
3. Percent of Applicable Limit (3E-03 pCi/ml) 1.10E-04 1.30E-04 Dissolved and Entrained Noble Gasesl
1. Total Releases Curies
2. Average Diluted Concentration During Period pCi/ml
3. Percent of Applicable Limit (2E-04 pCi/ml)

D. Gross Alpha Radioactivity

1. Total Releases Curies
2. Average Diluted Concentration During Period pCi/ml E. Volume of Waste Release (Before dilution) Liters 3.47E+06 3.31E+06 3 F. Volume of Dilution Water for Period Liters 1.37E+10 1.26E+10 10 G. Total CCW flow for Six Months 116 gigagallons Includes Xe-133, Xe-135, and others.

Page 8 of 16 ENCLOSURE 2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID RELEASES FOR SECOND HALF 1990 BATCH MODE

~soto e Third Quarter Fourth Quarter (Required by REG Guide 1.21) Unit Curies Unit Curies Cr-51 2~ Mn-54

3. Co-58
4. Fe-59
5. Co-60 6.23E-03 6.55E-03
6. Zn-65
7. Nb-95
8. Zr-95
9. Mo-Tc-99m
10. I-131 ll. Xe-133
12. Cs-134 1.60E-02 7.45E-03
13. Xe-135
14. Cs-137 1.13E-01 5.88E-02
15. Ba-140
16. La-140
17. Ce-141
18. Sr-89
19. Sr-90 2.81E-05 8.86E-05

~Isoto e Others (Not Required by REG Guide 1.21)

1. Fe-55

Page 9 of 16 ENCLOSURE 2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SECOND HALF 19901 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES Third Fourth Summation of All Releases U~n t Quarter Quarter  % Error A. Fission and Activation Gases

l. Total Releases Ci
2. Average Release Rate for Period pCi/sec
3. Percent of T.S. limit2 B. Iodines
1. Total Iodine-131 Ci 36
2. Average Release Rate for Period pCi/sec
3. Percent of T.S. Limit>

tC. Particulates 1.

2.

3.

Particulates with half-lives

>8 days Avg. release Percent of T.S.

rate for period limit2 Ci pCi/sec 1.16E-04 1.48E-05 1.87E+00 2.82E-05 3.59E-06 1.13E+00 35

4. Gross alpha radioactivity Ci 3.18E-06 1.04E-06 D. Tritium Total release Ci 3.21E-01 1.95E-01 21
2. Average release rate for period pCi/sec 4.08E-02 2.48E-02
3. Percent of T.S. limit2 1.87E+00 1.13E+00
4. Ground level release Ci 3.21E-01 1.95E-01
5. Elevated release Ci 1 Reporting period 189 days.

t2 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.

Page 10 of 16 ENCLOSURE 2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SECOND HALF 1990 GASEOUS EFFLUENTS ELEVATED RELEASE Third Fourth Unit quarter guarter Fission Gases Krypton-85m Ci Krypton-85 Krypton-87 Ci Krypton-88 Ci Xenon-133 Ci Xenon-135m Ci Xenon-135 Ci Xenon-138 Ci ota o Pe od Ci Iodines Iodine-131 Ci Iodine-133 Ci Iodine-135 Ci Total for Period Ci

ENCLOSURE 2 Page ll of 16 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SECOND HALF 1990 GASEOUS EFFLUENTS ELEVATED RELEASE (Continued)

Third Fourth

~Ut ~tarte guarter 3~ Particulates Sr-891 Sr-901's-134 Ci Cs-137 Ci Ba-140 Ci La-140 Ci ota fo Pe od

4. Tritium Ci Predicted estimation of releases.

Page 12 of 16 ENCLOSURE 2 EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT SECOND HALF 1990 GASEOUS EFFLUENTS GROUND LEVEL RELEASE Third Fourth pni.t ~ua ter guuarte; Fission Gases Krypton-85m Ci Krypton-85 Ci Krypton-87 Ci Krypton-88 Ci Xenon-133 Ci Xenon-135m Ci Xenon-135 Ci Xenon-138 Ci ota o Ci Iodines Iodine-131 Ci Iodine-133 Ci Iodine-135 Ci Total for Period Ci

Page 13 of 16 ENCLOSURE 2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SECOND HALF 1990 GASEOUS EFFLUENTS GROUND LEVEL RELEASE Third Fourth Unit guarter guarter 3~ Particulates Sr-891 Ci 3.42E-06 8.63E-07 Sr-901 Ci 7.31E-07 1.84E-07 Cs-134 Ci, Cs-137 Ci 1.12E-04 2.72E-05 Ba-140 Ci La-140 Ci Total for Period Ci 1.16E-04 2.82E-05

4. Tritium 3.21E-01 1.95E-01 Predicted estimation of releases.

Page 14 of 16 ENCLOSURE 2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SECOND HALF 1990 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. Solid Waste Shipped Offsite for Burial or Disposal (Not Irradiated Fuel)

1. Type of waste Units mount Error $
a. Spent resins, filter m3 2.91E+01 sludges, evaporator Ci 6.62E+01 1.50E+Ol bottoms, etc.
b. Dry compressible waste m3 8.53E+01 contaminated equip., etc. Ci 9.44E+00 1.50E+01
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 composition (by waste type)
a. Spent resins, filter sludge, evaporator bottoms, etc.

nuclide Unit Unit

1. Manganese-54(l) O.OOE+00 Ci O.OOE+00
2. Iron-55(2) 3.31E+00 Ci 2.19E+00
3. Cobalt-60(l) 3.24E+01 Ci 2.14E+01
4. Zinc-65(1) 2.94E-Ol Ci 1.95E-01
5. Cesium-134(l) 5.26E+00 Ci 3.48E+00
6. Cesium-137(1) 4.45E+01 Ci 2.94E+01
7. Other Nuclides(2) 1.43E+01 Ci 9.43E+00 (1) Measured (2) Estimated through the use of scaling factors

Page 15 of 16 ENCLOSURE 2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SECOND HALF 1990 SOLID WASTE AND IRRADIATED .FUEL SHIPMENTS (Continued)

2. Estimate of major nuclide composition (by waste type) (Cont'd)
b. Dry compressible waste, contaminated equipment, etc.

Nuclide U~it U~it

1. Manganese-54(2) 8.02E-02 Ci 7.57E-03
2. Iron-55(2) 4.33E+01 Ci 4.08E+00
3. Iron-59(2) 5.00E-04 Ci 4.72E-05
4. Cobalt-60(2) 4.69E+01 Ci 4.43E+00
5. Zine-65(2) 1.92E+00 Ci 1.82E-01
6. Silver-llm(2) 1.60E-03 Ci 1.51E-04
7. Cesium-134(2) 1.11E+00 Ci 1.05E-01
8. Cesium-137(2) 6.01E+00 Ci 5.68E-01
9. Other Nuclides(2) 6.83E-01 Ci 6.45E-02 (1) Measured (2) Estimated through the use of percent abundance
c. Irradiated components, control rods, etc.

NONE

d. Other NONE

Page 16 of 16 ENCLOSURE 2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SECOND HALF 1990 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (Continued)

2. Solid waste disposition Number of Mode of

~Shi ments Trans ortation Destination Sole Use Truck Barnwell, SC B. Irradiated Fuel Disposition Number of Mode of

~Shi ments ra s o tatio Destination NONE N/A N/A C. Waste Sources, Burial Class and Type quantity, Container Type, Total Volume in Cubic Feet and Number of Containers Used.

Type of Type Burial Type of Number of Disposal Waste guan~tt Class ~Conte% e Containers Volume DEWATERED (Resin)

RX CLEANUP B-LSA B-Stable HIC 0.3 61.7 COND/WASTE B-LSA B-Stable HIC 1.7 349.9 A-LSA A-Stable HIC 3.0 617.4 (Filters) N/A N/A N/A NONE NONE DRY ACTIVE WASTE (Compacted)

DRUM N/A N/A N/A NONE NONE BOX N/A N/A N/A NONE NONE (Uncompacted)

DRUM N/A N/A N/A NONE NONE BOX N/A N/A N/A NONE NONE (Processed Offsite)

(TO PROCESSOR) A-LSA A-Unstable STC N/A 21665.0 (TO DISPOSAL) A-LSA A-Unstable STC N/A 3010.6 IRRADIATED COMPONENTS N/A N/A N/A NONE NONE SOLIDIFIED N/A N/A N/A NONE NONE ABSORBED N/A N/A N/A NONE NONE Solidification Agent Used: NONE Absorbent Used: NONE

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