ML061220636

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Effluent and Waste Disposal Annual Report, 2005
ML061220636
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 12/31/2005
From:
Tennessee Valley Authority
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML061220636 (25)
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Text

ENCLOSURE 3 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)

UNITS 1, 2, AND 3 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2005 E3-1

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT YEAR 2005 Rogulatorv and BFN ODCM Limits A. Fission and Activation Gases in Gaseous Effluent:

The release of fission and activation gases is regulated by the dose limits of 10 CFR 50 Appendix I and BFN Offsite Dose Calculation Manual (ODCM). 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 < 5 millirad (mrad) for gamma radiation and < 10 mrad for beta radiation; and during any calendar year to < 10 mrad for gamma radiation and <. 20 mrad for beta radiation.

B. lodines and Particulates with Half-Lives Greater than Eight Days in Gaseous Effluents.

The release of iodines and particulates in gaseous effluent is regulated by the dose limits of 10 CFR 50 Appendix I and the BFN ODCM. 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 eight days in gaseous effluent released per unit to areas at and beyond the site boundary shall be limited to any organ during any calendar quarter to < 7.5 millirem (mrem), and during any calendar year to < 15 mrem.

C. Liquid Effluents The release of radioactive liquid effluents is regulated by the dose limits of 10 CFR 50 Appendix I and the BFN ODCM. The doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from each unit to unrestricted areas shalM be limited during any calendar quarter to < 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 II. Limitation on Dose Rate A. Fission and Activation Gases in Gaseous Effluent:

1. The instantaneous release rate of fission and activation gases is based on the dose rate limits of 10 CFR 20.1301 and the BFN ODCM. 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 per year to the total body and < 3000 mrem per year to the skin.

2. The BFN ODCM Section 7.2 determines the maximum noble gas release rate.

E3-2

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT YEAR 2005 II. Limitations on Dose Rate (Continued)

B. Iodines and Particulates with Half-Lives Greater than Eight Days in gaseous effluents.

1. The instantaneous release rate of particulates and iodines is regulated by the dose rate limits of the BFN ODCM. The dose rate at any time to areas at and beyond the sit-boundary, due to 1-131, 1-133, H-3 and particulates with greater than eight days half-lives released in gaseous effluents from the site, shall be limited to < 1500 mrem per year to any organ.
2. The BFN ODCM Section 7.3 determines the maximum particulate and iodine dose rates.

C. 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 20.1001 -

20.2402, Appendix B, Table 2, 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 ptCi per milliliter (ml) total activity.
m. Measurements and Approximations of Total Radioactivity A. Fission and Activation Gases:
1. Noble gases in the building vent and stack (elevated) gaseous effluents 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 vent flow is calculated for each release. Gas grab samples of the stack are taken and analyzed weekly. Gas grab samples of in-service vents are taken and analyzed monthly. The specific noble gas activity concentrations and total volume of the gases are used to calculate the total Curies of noble gases released.
2. The tritium concentration is determined by the analysis of a monthly grab sample for each release point.

E3-3

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT YEAR 2005

m. Measurements and Approximations of Total Radioactivity (continued)

B. 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.
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.

C. 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.

D. The Radioactive Gaseous and Liquid Waste Monitoring Sampling and Analysis Program is specified in ODCM Sections 1/2.2.1 and 1/2.2.2.

E3-4

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION 2005 IV. Batch A. Liquid Unitsa l 2 3 4

1. Number of batches released Each 27 47 43 119
2. Total time for batches released Minutes 7859 16065 12748 39603
3. Maximum time period for a batch release Minutes 385 390 360 405
4. Average time period for a batch release Minutes 291 342 296 333
5. Minimum time period for a batch release Minutes 245 260 203 215
6. Average stream flow during period of release into a flowing stream Cubic feet per second 56279 32891 35222 28674 B. Gaseous None C. Abnormal/Unplanned Releases*

Type Number of Total Activity Releases Releases (Curies)

Liquid Three 3.75E-02 Gaseous One 6.75E-02

  • An explanation of any liquid or gaseous abnormal/unexplained release shall be documented in the summary.

E3-5

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES YEAR 2005 Units Ouarter Ouarter OQu a3ter .Quarter Error A. Fission and Activation Proclucts 1 ,2 4 0E (Does not include tritium, gases, Alpha)

1. Total Release Curies 7.26E-02** 1.37E-01** 2.72 E-01 9.30e-02**
2. Average Diluted Concentration Released During Period jiCi/ml 2.95E-09** 3.68E-09** 6.13 E-09 1.00E-09"
3. Percent of Applicable Limit  %

B. Tritium

1. Total Releases Curies 6.07E+00** 1.56E+01 7.22] E+00 1.9)5E+01** 6
2. Average Diluted Concentration Released During Period J.Ci/ml 2.46E-07** 4.20E-07 1.62 E-07 2.10E-07**
3. Percent of Applicable Limit  %

C. Dissolved and Entrained Noble Gases

1. Total Releases Curies 5.00E-04 1.19E-03 4.71]E-04 2.42E-03 8
2. Average Diluted Concentration Released During Period gCi/ml 2.03E-1 1 3.20E-11 1.06 E-1 1 2.60E-1 1
3. Percent of Applicable Limit  %

D. Gross Alpha Radioactivity

1. Total Releases Curies ND* ND ND ND 48
2. Average Diluted Concentration Released During Period pCi/ml ND ND ND ND E. Volume of Liquid Waste to Discharge Canal (Prior to dilution) Liters 3.388E+06 6.36E+06 5.37] E+06 1.51E+07 F. Volume of Dilution Water for Period Liters 2.46E+10 3.72E+10 4.45] E+10 S9.30E+10 G. Total CCW Gigagal. 1.70E+02 1.75E+02 1.911 E+02 1.91E+02
  • NI) -- Not Detected. Dilution flow was not determined for the abnormal release.
    • Includes abnormal release. See documentation in the summary.
      • The applicable limit is expressed in terms of dose. See Enclosure 1, Tables 5 through 8.

E3-6

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID RELEASES FOR YEAR 2005 - BATCH MODE CURIES Isotope Ouarte Ouarter Ouarter Ourter (Required by Regulatory (REG) Guide 1.21) 1** 2** 3 44*

1. Ba-140 N* ND ND N)
2. Ce-141 ND ND ND ND
3. Co-58 2.19E-03 1.47E-03 2.70E-04 ND
4. Co-60 1.96E-02 2.86E-02 2.89E-02 1.64]-02
5. Cr-51 5.99E-03 1.62E-02 ND 3.421 -05
6. Cs-134 7.91E-03 1.71E-02 7.85E-02 2.03]-02
7. Cs-137 1.42E-02 3.28E-02 1.51E-01 4.73E--02
8. Fe-59 1.03E-03 ND ND ND
9. I-131 ND ND 2.26E-05 ND
10. La-140 ND ND ND ND
11. Mn-54 6.02E-03 5.74E-03 3.73E-03 8.15]-04
12. Mo-99 2.1 lE-04 ND ND ND
13. Nb-95 ND ND ND N)
14. Sr-89 ND ND ND ND
15. Sr-90 ND ND ND ND
16. Tc-99m 2.06E-04 ND ND ND
17. Xe-133 4.87E-04 5.02E-04 2.43E-04 1.13:_-03
18. Xe-135 1.31E-05 6.87E-04 2.27E-04 1.28E-03
19. Zn-65 1.27E-02 3.28E-02 3.21E-03 6.493-03
20. Zr-95 ND ND ND ND

.* - Not Detected

    • 1st, 2nd, and 4th quarters contain data from the abnormal releases. See documentation in the summary.

E3-7

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID RELEASES FOR YEAR 2005 - BATCH MODE CRES Isotope Ouarter Ouarter Dw= Quarter Others (Not Required by REG Guide 1.21) 2** 3

1. Ag-110rn 9.38E-04 2.39E-03 6.03E-04 1.01E-03
2. As-76 ND* ND 5.13E-05 6.80E-06
3. Cu-64 ND ND 8.45E-04 ND
4. F-18 3.96E-06 1.22E-05 7.69E-04 2.90E-05 5 Fe-55 1.59E-04 ND 2.51E-04 4.73E-04 6 I-133 ND 4.19E-06 ND ND 7 Mn-56 1.03E-03 ND ND 8.1IE-06 8 Na-24 ND ND 2.68E-03 ND 9 Nb-97 5.35E-05 2.34E-05 4.75E-05 5.60E-05 10 Ru-106 ND ND 1.41E-03 ND 1:L Sr-92 ND 2.90E-05 5.65E-05 3.09E-05

'12 Zn-69m 3.45E-04 ND ND 1.76E-06

  • ND - Not Detected
    • Includes abnormal release.

E3-8

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES YEAR 2005 Units Quarter Ouarer -Quarte-r Quarter Error 2 3 4  %

At. Fission and Activation Gases

1. Total Releases Curies ND** ND ND ND 45
2. Average Release Rate for Period gCi/sec ND ND ND ND
3. Percent of Applicable Limit  %*

B. Iodines

1. Total Iodine-131 Curies 2.12E-03 5.36E-04 9.24E-04 8.73E-04 36
2. Average Release Rate for Period [tCi/sec 2.73E-04 6.82E-05 1.16E-04 1.1OE-04
3. Percent of Applicable Limit  %*

C. Particulates

1. Particulates with half-lives

> eight days Curies 1.42E-03 1.60E-03 8.36E-04 1.41E-04 35

2. AverageReleaseRatefor Period [tCi/sec 1.82E-04 2.03E-04 1.05E-04 1.77E-05
3. Percent of Applicable Limit  %*
4. Gross Alpha Radioactivity Curies ND ND ND ND I). Tritium
1. Total Release Curies 1.32E+01 1.49E+01 1.01E+01 5.57E+00 21
2. Average ReleaseRate for Period gCi/sec 1.69E+00 1.90E+00 1.27E+00 7.01E-01
3. Percent of Applicable Limit  %*
  • Applicable Limits are expressed in terms of dose. See Enclosure 1, Tables 1 through 4.
    • ND - Not Detected.

E3-9

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT YEAR 2005 GASEOUS EFFLUENTS - ELEVATED RELEASE CURIES uarter Quarte Quarter 3uarter 1 2 3 4

1. Fission Gases Kr-85m ND* ND ND ND Kr-85 ND ND ND ND Kr-87 ND ND ND ND Kr-88 ND ND ND ND Xe-133 ND ND ND ND Xe-135m ND ND ND ND Xe-135 ND ND ND ND Xe-138 ND ND ND ND Others (specify)

N-13 ND ND ND ND Total. for Period ND ND ND ND

2. Iodines I-13]. 6.61E-04 1.47E-04 1.84E-04 3.32E-04 I-133 8.05E-04 1.47E-04 3.27E-04 1.46E-04 Total for Period 1,47E-03 2, 93E-04 5.1 1E-04 4.78E-04
  • ND - Not Detected.

E3-10

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT YEAR 2005 GASEOUS EFFLUENTS - ELEVATED RELEASE CURIES Quarte Ouarte Ouarte Ouarter 1 2 3 4

3. Particulates*

Sr-89 3.35E-05 1.49E-05 1.57E-05 I1.85E-05 Sr-91) ND** ND ND ND Cs-134 ND ND ND ND Cs-137 ND ND ND ND Ba-140 1.84E-05 ND 3.14E-06 ND La-I 40 7.40E-06 ND 2.93E-06 ND Others (specifi)

Rb-89 ND ND ND 7.68E-03 Sr-9:1 8.77E-05 ND ND ND Y-91m 2.1OE-04 7.97W-05 6.72E-05 6.40E-05 Cs-138 1.33E-02 1.13E-02 3.22E-02 4.34E-02 Ba-139 2.91E-02 1.22E-02 1.80E-02 1.65E-02 Total for Period* 4.27E-02 2.36E-02 5,03E-02 6.77E-02

4. Tritium lOlE+00 5.92E-01 1.51E+00 3.30E-Ol
  • Includes all nuclides, even those with less than an eight day half-life.
    • ND - Not Detected.

E3-11

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT YEAR 2005 GASEOUS EFFLUENTS - GROUND RELEASE CURIES Quarter Quarter uarter -Qu 1 2 3 4

1. Fission Gases Kr-85m ND* ND ND ND Kr-85 ND ND ND ND Kr-87 ND ND ND ND Kr-88 ND ND ND ND Xe-133 ND ND ND ND Xe-135m ND ND ND ND Xe-135 ND ND ND ND Xe-138 ND ND ND ND Others(specify)

NONE Total for Period ND N ND ND

2. lodines I-131 9.48E-04 1.56E-04 1.52E-04 2.9zLE-04 1-132 ND ND ND ND I-133 2.63E-04 8.61E-06 1.07E-04 5.30E-04 I-135 ND ND ND ND Total for Period 1,211-03 -164E-04 2.59E-04 8.24E-04
  • ND -- Not Detected.

E3-12

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT YEAR 2005 GASEOUS EFFLUENTS - GROUND RELEASE CU`Rl--S Quarter Quarte uarter Dalter

3. Particulates* 1 2 3 4 Sr-89 ND** ND ND ND Sr-90 ND ND ND ND Cs-134 ND ND ND ND Cs-137 ND ND ND ND Ba-140 ND ND ND ND La-140 ND ND ND ND Others (specify)

Y-91 m 7.80E-05 ND 4.76E-06 6.02]_-06 Cs-138 7.74E-03 ND 1.27E-03 3.41]_-03 Ba-139 8.02E-03 9.67E-05 4.07E-03 6.17E-03 Total for Period* 1.58E-02 9.67W-05 5.34E-03 9,58E-03

4. Tritium 3,99E+00 2,79E+00 2.09E+00 9.5113-01
  • Include all nuclides even those with less than an eight day half-life.
    • ND - Not Detected.

E3-13

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT YEAR 2005 GASEOUS EFFLUENTS - MIXED MODE RELEASE*

CURIES uarter Quarter uarter uarte 1 2 3 4

1. Fission Gases Kr-85m ND** ND ND ND Kr-85 ND ND ND ND Kr-87 ND ND ND ND Kr-88 ND ND ND ND Xe-133 ND ND ND ND Xe-135m ND ND ND ND Xe-135 ND ND ND ND Xe-138 ND ND ND ND Others(specify)

NONE it-al for Period N ND ND ND

2. Iodines I-131 5.1 OE-04 2.34E-04 5.88E-04 2.47E-04 I-133 7.35E-04 4.01E-04 9.11E-04 2.71E-04 I-135 ND ND ND ND Total for Period 1,25E-03 6.351-04 1,501-03 5.17E-04
  • The Reactor Building and Radwaste Building are treated as split-level releases.
    • ND - Not Detected.

E3-14

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT YEAR 2005 GASEOUS EFFLUENTS - MIXED MODE RELEASE*

CURIES Quarter uarter uarte 4arter 1 2 3 4

3. Particulates**

Sr-89 ND*** ND ND ND Sr-90 ND ND ND ND Cs- 134 2.03E-04 2.16E-04 4.86E-05 1.13E-05 Cs- 137 4.57E-04 5.06E-04 2.14E-04 5.79E-05 Ba-140 1.02E-05 ND ND ND La- 140 8.46E-06 ND ND ND Others (specify)

Na-24 ND 2.95E-04 5.53E-05 ND Cr-51 3.85E-05 5.72E-05 ND ND Mn..54 5.39E-05 1.21E-04 3.88E-05 1.35E-05 Co-58 5.24E-06 1.74E-05 ND 3.72E-06 Co-50 3.66E-04 4.69E-04 3.43E-04 3.60E-05 Zn-655 6.70E-05 1.91E-04 1.58E-04 ND Se-75 ND 1.49E-06 1.46E-05 ND Y-91m 3.79E-04 ND ND 3.22E-05

  • The Reactor Building and Radwaste Building are treated as split-level releases.
    • Includes all nuclides, even those with less than an eight day half-life.
      • ND - :.Not Detected.

E3-15

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT YEAR 2005 GASEOUS EFFLUENTS - MIXED MODE RELEASE*

CUIRIES uartur -Quarter Ouarter Quarte Particulates** (Continued) I 2 3 4 Others (specify)

Mo-99 3.21E-06 4.09E-06 ND*** ND Tc-99m 3.13E-06 3.99E-06 ND ND Ag-110ni 1.63E-04 5.33E-06 ND ND Cs-138 ND ND ND 1.21E-03 Ba-139 4.74E-03 ND ND 3.17E-03 Total. for Period** 1,89E-03 8,73E-04 4,531-03

4. Tritium 8.18E+00 1.16E+01 6.50E+00 4,291+00
  • The Reactor Building and Radwaste Building are treated as split-level releases.
    • Includes all nuclides, even those with less than an eight day half-life.
      • ND - Not Detected.

E3-16

BROWNS FERRY NUCLEAR PLANT ANNUAL EFFLUENT AND WASTE DISPOSAL REPORT 2005 SOLID WASTE AND IRRADIATED FUEL A. Solid Waste Shipped Off-site for Burial or Disposal (Not Irradiated Fuel)

1. TyDe of Waste Units Amount Error%
a. Spent resins, filters, filter sludge 2.87E+01 evaporator bottoms, etc. Ci 1.49E+03 +/-25.0
b. Dry compressible waste, contaminated equipment, etc.
1. Shipped from site m3 5.03E+03 to processor Ci 6.46E+00 +/-25.0
2. Estimated volume sent to m3 3.11E+02 burial by waste processor Ci 6.46E+00 +/-25.0
c. Irradiated components, control rod m3 3.25E+00 blades & LPRMs with fission chambers Ci 4.69E+04 +/-25.0
d. Other - Unit I CRDs, crane trolley m3 4.73E+02 and trolley parts and combined Ci 1.51E+03 +/-25.0 packages.
2. Estimate of Maior Nuclide Comrosition by Waste Tvye
a. Spent resins, filters, filter sludge, evaporator bottoms, etc.

Nuclide Percentage Curies

1) FE-55 S.17E+0 I 7.69E+02
2) CO-60 1.80E+01 2.68E+02
3) CS-137 9.40E+00 1.40E+02
4) MN-54 5.99E+00 8.91E+01
5) CS-134 5.72E+00 8.52E+01
6) ZN-65 3.96E+00 5.90E+01
7) CR-51 2.04E+00 3.04E+01
8) AG-110M 1.44E+00 2.14E+01
9) CO-58 7.39E-01 1.1OE+01
10) FE-59 6.68E-01 9.95E+00
11) NI-63 2.96E-01 4.41E+00
12) TC-99 3.51E-02 5.22E-01
13) SR-90 2.14E-02 3.18E-01
14) CE-144 7.99E-03 1.19E-0 1
15) MO-99 4.78E-03 7.12E-02
16) PU-241 4.33E-03 6.45E-02
17) NB-95 3.71E-03 5.52E-02
18) 1-131 1.39E-03 2.07E-02
19) CM-242 3.80E-05 5.66E-04
20) SR-89 2.29E-05 3.41E-04
21) CM-243 1.28E-05 1.91E-04
22) CM-244 1.28E-05 1.91E-04
23) PU-238 7.25E-06 1.08E-04
24) NA-24 2.82E-06 4.20E-05 E3-17
b. Dry compressible waste, contaminated equipment, etc.

Nuclide Percentage Curies

1) CO-60 2.75E+O 1 1.78E+00
2) FE-55 2.49E+01 1.61E+00
3) CS-137 2.04E+01 1.32E+00
4) CS-134 1.16E+01 7.49E-01
5) ZN-65 7.17E+00 4.63E-01
6) NI-63 2.80E+00 1.81E-01
7) MN-54 2.58E+00 1.67E-01
8) CR-51 8.57E-01 5.54E-02
9) PU-241 7.92E-01 5.12E-02
10) AG-I lOM 7.04E-01 4.55E-02
14) FE-59 2.38E-01 1.54E-02
12) CO-58 2.00E-01 1.29E-02
13) AM-241 4.61E-02 2.98E-03
14) CE-144 3.36E-02 2.17E-03
15) PU-238 2.15E-02 1.39E-03
16) SB-124 1.56E-02 l.OE-03
17) SR-89 1.44E-02 9.30E-04
18) PU-239 8.84E-03 5.71E-04
19) PU-240 8.84E-03 5.71E-04
20) SR-90 6.30E-03 4.07E-04
21) CM-243 5.188E-03 3.35E-04
22) CM-244 5.18E-03 3.35E-04
23) C-14 2.23E-04 1.44E-05
24) CM-242 1.66E-04 1.07E-05 E3-18
c. Irradiated components, Control Rod Blades & LPRMs with fission chambers Nuclide Percentage Curies
1) FE-55 5.05E+01 2.37E+04
2) CO-60 4.43E+01 2.08E+04
3) NI-63 3.67E+00 1.72E+03
4) MN-54 1.43E+00 6.73E+02
5) NI-59 2.02E-02 9.47E+00
6) CO-58 1.62E-02 7.58E+00
7) ZN-65 1.18E-02 5.55E+00
8) H-3 5.78E-03 2.71E+00
9) C-14 5.50E-03 2.58E+00
10) FE-59 1.26E-04 5.89E-02
11) NB-94 8.63E-05 4.05E-02
12) CS-134 3.45E-05 1.62E-02
13) PU-238 3.433E-05 1.61E-02
14) CS-137 3.37E-05 1.58E-02
15) TC-99 2.66E-05 1.25E-02
16) CR-51 1.54E-05 7.23E-03
17) PU-241 5.99E-06 2.8 1E-03
18) AG-l1lM 2.34E-06 1.lOE-03
19) CM-244 2.377E-07 1.llE-04
20) CM-242 1.46E-07 6.86E-05
21) SR-90 1.05E-07 4.93E-05
22) PU-240 3.67E-08 1.72E-05
23) AM-241 2.66E-08 1.25E-05
24) PU-239 2.56E-08 1.20E-05
25) SB-124 1.86E-08 8.71E-06
26) SR-89 1.03E-08 4.85E-06
27) CE-144 8.35E-09 3.92E-06
28) NP-237 2.49E-09 1.17E-06
29) CM-243 1.30E-09 6.08E-07
30) AM-243 1.14E-09 5.34E-07
31) ZR-95 1.25E-10 5.85E-08
32) U-235 4.69E-1 1 2.20E-08 E3-19
d. Otiler, Unit 1 CRDs, crane trolley and trolley parts, and combined packages.

Nuclide Percentage Curies

1) FE-55 5.25E+01 5.97E+02
2) CO-60 l.91E+01 2.17E+02
3) CS-137 1.20E+01 1.37E+02
4) CS-134 9.67E+00 1.1OE+02
5) MN-54 2.97E+00 3.38E+01
6) ZN-65 2.47E+00 2.81E+01
7) NI-63 6.80E-01 7.73E+00
8) AG-llOM 4.55E-01 5.17E+OO
9) SR-90 3.44E-02 3.91E-O1
10) CR-51 2.66E-02 3.02E-01
11) CO-58 1.81E-02 2.06E-Ol
12) PU-241 1.50E-02 1.71E-01
13) CE-144 7.95E-03 9.04E-02
14) FE-59 3.43E-03 3.90E-02
15) NI-59 3.02E-03 3.43E-02
16) H-3 1.19E-03 1.35E-02
17) LA-140 1.03E-03 1.17E-02
18) C-14 5.99E-04 6.81E-03
19) AM-241 4.57E-04 5.20E-03
20) EU-152 4.56E-04 5.18E-03
21) PU-238 2.74E-04 3.12E-03
22) SB-124 2.06E-04 2.34E-03
23) NB-95 1.48E-04 1.68E-03
24) PU-239 1.44E-04 1.64E-03
25) EU-154 1.39E-04 1.58E-03
26) SB-125 1.04E-04 1.18E-03
27) CM-243 9.85E-05 1.12E-03
28) CM-242 5.99E-05 6.81E-04
29) CM-244 3.46E-05 3.94E-04
30) PU-240 2.89E-05 3.29E-04
31) NB-94 1.30E-05 1.48E-04
32) TC-99 6.63E-06 7.54E-05
33) I-129 1.48E-09 1.68E-08 E3-20
3. Solid Waste Dissosition Number of Shipments Mode of Transportation Destination 6 HIC/Cask, Sole Use Truck Barnwell Waste Management Barnwell, SC 6 HIC/Cask, Sole Use Truck Duratek Consolidation It Services Facility Barnwell, SC 70 64 - Sole Use Truck Duratek 6 - Non-Sole Use Truck Oak Ridge, TN 23 23 -Non-Sole Use Truck Duratek Kingston, TN 4 1 -Sole Use Truck Race, LLC 3 -Non-Sole Use Truck Memphis, TN NOTE: The 12 cask shipments consisted of the following:

Tvne of HIC Number of Packages Volume per Package (m3 )14-170 1 4.84E+00 8-120 9 3.41E+00 3-55 2 1.63E+00 NOTE: The 97 shipments of waste packaged in strong tight packages consisted of the following:

Tve of STC Number of Packages Volume of Packages (m3 )

40'"Sealand" 50 2.95E+03 20' "Sealand" 35 1.03E+03 Other (CRD box, crane trolley, 26 1.5 1E+03 sand blast booth, combined packages).

B. Irradiated Fuel Disposition Number of Shipments Mode of Transportation Destination None N/A N/A E3-21

BROWNS FERRY NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT

SUMMARY

OF ABNORMAL/UNPLANNED RELEASES 2005 The release of radioactive material to the environment from Browns Ferry has been a small fraction oF the 10 CFR 2,) Appendix B and 10 CFR 50 Appendix I limits. There were no limits exceeded as specified in 10 CFR 21) Appendix B and 10 CFR 50 Appendix I.

One abnormal gaseous release and three abnormal liquid releases occurred in 2005. One abnormal liquid release wzs detected in March, 2005 when 2A Residual Heat Removal (RHR) heat exchanger was placed in service during the unit 2 refueling outage. A leak around the RHR heat exchanger floating head expansion joint resulted in contaminated water entering the RHR service water which is discharged to the Tennessee River. The heat exchanger was removed from service and repaired. Post maintenance testing of the heat exchanger resulted in a small release of radioactivity due to contamination of the Service Water side during the repair in May, 2005. This event resulted in 1.25E-02 Curies being released during first quarter, 2.47E-02 Curies during second quarter, and a maximum Effluent Concentration Limit (ECL) fraction of 8.6 7E-01.

All doses associated with this abnormal release were less than 1% of the quarterly limit. Details of this abnormal :release are given in Problem Evaluation Report (PER) 79143.

On March 20, 2005 contamination was discovered in the plant demineralized water system (PER 79C75).

This resulted in a liquid release during first quarter and an airborne tritium release during first and second quarter. A third liquid release occurred when the Auxiliary Decay Heat Removal (ADHR) secondary side was drained in October, 2005 (PER 90671). This system was filled with contaminated demineralized water in March. Since the last four monthly samples had not indicated any detectable radioactivity, the ADIIR secondary loop was drained to the sewage lagoon (normal procedure for draining the ADHR secondary loop). A sample taken of the ADHR catch basin near the completion of the drain down indicated low concentrations of Co-60, Ag-110m, Cs-134, and Cs-137. None of the samples discharged indicated radioactivity, however, a release was calculated using the levels of radioactivity found in the bottom of the basin. Liquid releases were 9.79E-06 Curies for the first quarter and 3.1OE-04 Curies for the fourth quarter.

Airborne tritium releases were 2.07E-02 Curies for the first quarter and 3.1 OE-04 Curies for the second quarter. All doses associated with this abnormal release were less than 1% of the quarterly limit and no ODCM release rate limits were exceeded.

Radioactivity from the abnormal releases is included in the liquid and gaseous release tables and is included in dose calculations.

Onsite ground water monitoring locations were sampled during the year. These locations were not part of BFN Radiological Environmental Monitoring Program (REMP). The purpose of these shallow wells was to monitor for potential leaks from plant equipment. Trace levels of tritium were detected in two of these monitoring locations (PER's 96105 and 96242). The highest concentration for the year was 903 pCi/L.

Investigations are ongoing to identify the source of the tritium and any potential release pathway.

In calendar year 2005, Browns Ferry had no changes to the radwaste system or the Process Control Program (PCP).

E3-22

ENCLOSURE 4 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)

UNITS 1, 2, AND 3 INOPERABLE RADIOLOGICAL EFFLUENT INSTRUMENTATION REPORT 2005 E4 -1

INOPERABLE RADIOLOGICAL EFFLUENT INSTRUMENTATION REPORT 2005 This report is to comply with Browns Ferry Nuclear Plant Offsite Dose Calculation Manual (Offsite I)ose Calculation Manual (ODCM)) Sections 1/2.1.1 and 1/2.1.2. The ODCM requires the exertion of best efforts to return inoperable instruments to operable status within 30 days. Failure to return such instruments to an operable status within the prescribed interval requires a description in the Annual Radioactive Effluent Release Report.

During the reporting period, January 1 through December 31, 2005, one gaseous effluent monitor was out of service for greater than 30 days. Unit 3 Reactor/Turbine/Refuel Building Ventilation Monitor (3-RM-.90-250) was inoperable from November 19, 2004 at 17:06 through the end of the reporting period. Monitor 3-RM-90-250 was retuned to service on February 1, 2005 at 18:30. This was previously reported in the 2004 Inoperable Radiological Effluent Instrument Report and is documented in PER 74315. The monitor's flow measuring system was inoperable. The flow system was obsolete and could not be replaced. New flow control systems were designed and installed. All compensatory measures were completed as required.

The liquid radwaste effluent flow rate instrument [(77-60 loop) ODCM Table 1.1-1] was out of service from February :17, 2005, to September 3, 2005 (PER 81265 and 89288). Browns Ferry Nuclear has not routinely released liquid effluents since 1997. After initiating releases in February 2005, the flow instrument was not declared operable due to inconsistencies in the flow totalizer readings. During all releases, the flow was estimated once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> as required by the ODCM. Two Raw Cooling Water effluent radiation monitors (1-RM-90-132D and 2-RM-90-132D) were out of service for greater than 30 days in 2005 due partially to low flow conditions. The 1-RM-90-132 monitor was out-of service from March 15, 2005 until April 27, 2005 and the 2-RM-90-132D monitor was out of service from February 11, 2005 until April 14, 2005.

Piping was modified to remove ninety degree elbows to improve flow conditions. In addition, I -RM 132D was out-of-service from July 9, 2005 until September 21, 2005. The downscale/inoperable alarm function was disabled during the performance of a work order and was discovered during a surveillance performed on September 20, 2005. Compensatory sampling was initiated and no radioactivity was identified. The alarm function was returned to service on September 21, 2005. There is no indication of release from this discharge point.

Some effluent monitors and flow instrumentation were placed in "out-of-service" status because these monitors' effluent streams were isolated. Therefore, these monitors are not included in this report.

E4-2

ENCLOSURE 5 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)

UNITS 1, 2, AND 3 CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL 2005 E5-1

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