ML18037A814
| ML18037A814 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 12/31/1993 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML18037A811 | List: |
| References | |
| NUDOCS 9404110414 | |
| Download: ML18037A814 (47) | |
Text
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION SECOND HALF 1993 I.
Re ulato 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.
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 millirad (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.
B.
Iodines and Particulates with Half-Lives Greater than Eight Days in Gaseous Effluents.
0 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 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 g 7.5 millirem (mrem),
and during any calendar year to g 15 mrem.
C.
Liquid Effluents 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.
II. Limitation on Dose Rate A.
Fission and Activation Gases in Gaseous Effluent:
- 1. The instantaneous release rate of fission and activati.on gases is based on dose rate limit.
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 Offsite Dose Calculation Manual (ODCM) Section 7.2 determines the maximum noble gas release rate.
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EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION SECOND HALF 1993 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.
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 per year to any organ.
2.
The BFN ODCM Section 7.2 determines the maximum particulate and iodine release rate limit.
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 20.106, 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 per milliliter (ml) total activity.
III.
Measurements and A
roximations of Total Radioactivit General Notch A new computer system was installed and used for November and December releases.
The new system uses the Effluent Management System (EMS) software developed and marketed by the Nuclear Data Division of Canberra Industries, Inc.
This software is used at many nuclear plants to track and report radioactive effluents.
Releases of Fission and Activation Gases using the EMS software is described under the heading-November and December.
The EMS software does not change how Iodines and Particulates or Liquid Effluents are calculated..
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EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION SECOND HALF 1993 III.
Measurements and A
roximations of Total Radioactivit Continued Releases of Fission and Activation Gases for June through October are computed using the methodology described below under the June through October heading.
This methodology was used in the first three quarters of 1993 and in previous years.
A.
Fission and Activation Gases:
June throu h October 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.
ovember and December'.
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 vent flow is calculated for each release.
Gas grab samples of input streams to 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 fission and activation gases are used to calculate the total curies and noble gases released.
2.
The tritium concentration is determined by the analysis of a monthly grab sample for each release point.
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EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION SECOND HALF 1993 III.
Measurements and A
roximations of Total Radioactivit Continued B.
Iodines and Particulates l.
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.
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EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION SECOND HALF 1993 IV.
~Batt A.
Liquid Third Quarter Fourth guarter l.
2 ~
3.
4 ~
5.
6.
Number of batches released (each)
Total time period for batch releases (min.)
Maximum time period for a batch release (min.)
Average time period for batch releases (min.)
Minimum time period for a batch release (min.)
Average stream flow during period of release of effluent into a flowing stream (cubic feet per second) 60 16231 325 270 158 27232 65 16983 350 261 145 36029 B.
Gaseous None V,
ABNORMAL UNPLA D RELEASES 1
NUMBER OF RELEASES TOTAL ACTIVITY A.
Liquid B.
Gaseous None 3.17E-09 pCi/ml None (1) All abnormal/unplanned releases shall be discussed in the summary.
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EFFLUENT AND WASTE DISPOSAL ANNUAL RBPORT LIQUID EFFLUENTS SUMMATION OF ALL RELEASES SECOND HALF 1993 Unit A.
Fission and Activation Products (Does not include Tritium, Gases,'lpha)
Third Quarter Fourth Quarter I Brrer 1.
Total Releases Curies 2.50E-Ol 4.99E-Ol 2.
Average Diluted Concentration Released During Period 3.
Percent of Applicable Limit (1.00E-07 pCi/ml)
B.
Tritium 1.
Total Releases pCi/ml 7.61E-09 1.30E-08 7.61B+00 1.30E+01 Curies 2.39E+00 3.18E+00 2.
Average Diluted Concentration Released During Period 3.
Percent of Applicable Limit (3E-03 pCi/ml)
C.
Dissolved and Entrained Noble Gases 1.
Total Releases pCi/ml 7.26E-08 8.27E-08 2.42B-03 2.76E-03 Curies 2.71E-03 1.24E-02 2.
Average Diluted Concentration Released During Period 3.
Percent of Applicable Limit (2E-04 pCi/ml)
D.
Gross Alpha Radioactivity pCi/ml 8.25E-ll 3.23E-10 4.13E-05 1.61E-04 1.
Total Releases Curies 1.08E-04 ND 2.
Average Diluted Concentration Released During Period E.
Volume of Liquid Waste (Prior to Dilution)
F.
Volume of Dilution Water Used During Period pCi/ml 3.27E-12 Liters 6.77E+06 7.51E+06 Liters 3.28E+10 3.85B+10 10 Gigagallons E2-7 G.
Total CCW flow (1)
Includes Xe-133,,Xe-135, and others 158.3
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EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID RELEASES BATCH MODE SECOND HALF 1993
~Ieoeo e
(Required by Regulatory (REG) Guide 1.21) 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.
Sr-90 Third Quarter Unit Curies 6.38E-03 1.05E-02 9.00E-04 2 '9E-02 8.34E-03 2.54E-03 2.12E-03 1.27E-03 7.06E-03 1.43E-03 3.71E-02 1.11E-04 1.47E-02 7.35E-04 Fourth Quarter Unit Curies 6.59E-02 1.34E-02 3.71E-03 1.71E-02 1.17E-02 ND 3.27E-02 2.62E-03 5.60E-03 4.94E-03 6.82E-03 3.25E-02 1.12E-04 3.95E-03 5.38E-04 E2-8
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EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID RELEASES BATCH MODE SECOND HALF 1993
~Ieoto e
(JOT Required by Regulatory (REG) Guide 1.21) 1.
Fe-55 2.
Na-24 3.
Nb-97 4.
I-133 5.
Sr-92 6.
Ag-110m 7.
Ru-103 8.
Sb-125 9.
Rb-88 10.
Zn-69m Third Quarter Unit Curies 1.02E-01 3.07E-02 2.32E-03 4.58E-05 5.00E-04 1.29E-04 5.01E-05 Fourth Quarter Unit Curies 4.89E-03 2.85E-01 4.17E-04 9.44E-03 9.35E-05 5.30E-04 2.93E-08 3.26E-05 E2-9
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EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES SECOND HALF 1993 (1)
Summation of All Releases A.
Fission and Activation Gases Unit Third Fourth Quarter Quarter
/ Error 1.
Total Releases Curies 3.10E+02 1.55E+02 2.
Average Release Rate for Period pCi/sec 3.94E+Ol 1.97E+Ol 3.
Percent of Technical Specification (TS) limit (2)
B.
Iodines 2.85E-03 1.
Total Iodine-131
& I-133 2.
Average Release Rate for Period 3.
Percent of TS limit (2)
C.
Particulates Ci 1.00E-02 6.43E-03 pCi/sec 1.27E-03 8.19E-04 5.30E-02 36 1.
Particulates with half-lives
> eight days Ci 4.85E-04 3.25E-04 2.
Average release rate for period 3.
Percent of TS limit (2) 4.
Gross alpha radioactivity D.
Tritium Ci 1.69E-07 NCi/sec
- 6. 18E-05
- 4. 13E-05 2.77E-03 1.
Total release 2.
Average release rate for period 3.
Ground level release 4.
Elevated release Ci Ci 4e13Et00 5.71E-Ol 1.84E-01 4.52E-02 Ci 4.31E+00 2.65E+00 pCi/sec 5.48E-Ol 3.38E-Ol 21
~ The applicable limit is expressed in terms of dose.
(1)
Total reporting period is 184 days.
(2)
The dose rate limit for Noble gases shall be
< 500 mrem per year to the total body and
< 3000 mrem per year to the skin and the dose rate limit for I-131, I-133, H-3, and particulates with g eight day half-lives shall be
< 1500 mrem per year to any organ.
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EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS ELEVATED OF ALL RELEASES SECOND HALF 1993 (1) 1.
Fission Gases Kr-85m Kr-85 Kr-87 Kr-88 Xe-133 Xe-135m Xe-135 Xe-138 Others (specify)
Ar-41 Xe-137 Total for Period Unit Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Third Fourth Quarter Quarter 7.04E+Ol 3.72E+Ol 4.33E+01 7.92E+00 8.15E+Ol 5.12E+Ol 7.46B+Ol 3.52E+Ol 2.40E+00 9.17E+00 4.95E-01 6.62E+00 ND 8.79E+00 ND 5.29E+00 2.79E+02 1.55E+02 2.
Iodines I-131 I-132 I-133 I-134 I-135 Total for Period Ci Ci Ci Ci Ci Ci 1.93E-04 1.21E-04 ND ND 7.57E-04 5.96E-04 ND ND 9.50E-04 7.17E-04 (1)
Predicted estimation of releases.
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EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS ELEVATED OF ALL RELEASES SECOND HALF 1993 (1)
Unit Third Fourth Quarter Quarter 3.
Particulates(2)
Sr-89(l)
Sr-90(1)
Cs-134 Cs-137 Ba-140 La-140 Ci Ci Ci Ci Ci Ci 9.67E-06 4.20E-06 ND Others (specify)
Ag-110m Co-60 Cr-51 Na-24 Mn-54 Mo-Tc-99m Y-91m Cs-138 Ba-139 Ci Ci Ci Ci Ci Ci Ci Ci Ci ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND 3.62E-05 3.17E-03 7.46E-03 Total for Period 4.
Tritium Ci Ci 9.67E-06 1.07E-02 1.84E-01 4.52E-02 (1)
Predicted estimation of releases.
(2)
Include all particulate nuclides (even those with half-lives 8 days)
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EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS MIXED MODE LEVEL RELEASE SECOND HALF 1993 (1) 1.
Fission Gases Unit Third Fourth guarter Quarter Kr-85m Kr-85 Kr-87 Kr-88 Xe-133 Xe-135m Xe-135 Xe-138 Others (specify)
Ar-41 Xe-137 Total for Period Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci (3)
(3)
(3)
(3)
(3)
(3)
(3)
(3)
(3)
(3)
(3)
ND ND ND ND ND 2.
Iodines I-131 I-132 I-133 I-134 I-135 Total for Period Ci Ci Ci Ci Ci Ci (3) 4.11E-04 (3)
ND (3) 4.14E-O3 (3)
ND (3)
ND (3) 4.55E-03 (1)
Predicted estimation of releases.
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EFFLUENT AND HASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS MIXED MODE LEVEL RELEASE SECOND HALF 1993 (1)
Unit Third Fourth Quarter Quarter 3.
Particulates(2)
Sr-89(l)
Sr-90(l)
Cs-134 Cs-137 Ba-140 La-140 Ci Ci Ci Ci Ci Ci (3)
ND (3)
ND (3)
ND (3)
ND (3) 8.82E-05 (3) 5.89E-06 Others (specify)
Ag-110m Ba-139 Co-60 Cr-51 Na-24 Mn-54 Mo-Tc-99m Y-91m Cs-138 Ci Ci Ci Ci Ci Ci Ci Ci Ci.
(3)
(3)
(3)
(3)
(3)
(3)
(3)
(3)
(3)
ND 1.34E-02 7.41E-05 1.48E-04 ND 1.01E-06 6.91E-06 1.96E-04 ND Total for Period 4.
Tritium Ci Ci (3) 1.39E-02 (3) 2.04E+00 (1)
Predicted estimation of releases.
(2)
Include all particulate nuclides (even those wi.th half-lives 8 days)
(3)
Since the data was analyzed by the ND6600 counting system the Mixed Mode data is combined with the 3rd quarter Ground Level data.
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EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS GROUND LEVEL RELEASE SECOND HALF 1993 (1)
Unit Third Fourth Quarter Quarter 1.
Fission Gases Kr-85m Kr-85 Kr-87 Kr-88 Xe-133 Ze-135m Ze-135 Xe-138 Others (specify)
Ar-41 Xe-137 Total for eriod Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 1.77E+01 ND ND ND 1.30E+01 ND ND ND ND ND 3.07E+Ol ND 2.
Iodines I-131 I-132 I-133 I-134 I-135 Total for Period Ci Ci Ci Ci Ci Ci 9.69E-04 1.67E-04 ND ND 8.09E-03 9.99E-04 ND ND ND ND 9.06E-03 1.17E-03 (1)
Predicted estimation of releases E2-15
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EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS GROUND LEVEL RELEASE SECOND HALF 1993 (1)
Unit Third Fourth Quarter Quarter 3.
Particulates(2)
Sr-89(l)
Sr-90(l)
Cs-134 Cs-137 Ba-140 La-140 Others (specify)
Ci Ci Ci Ci 2.64E-05 3.42E-06 ND ND 3.18E-05 ND 1.13E-04 ND ND Ag-110m Ba-139 Co-60 Cr-51 Na-24 Mn-54 Mo-Tc-99m Y-91m Cs-138 Ci Ci Ci Ci Ci Ci Ci Ci Ci 2.80E-05 2.45E-Ol 2.12E-04 ND 2.73E-03 6.42E-05 7.37E-05 3.30E-03 ND ND 2.42E-03 ND ND ND ND ND ND ND Total for Period 4.
Tritium Ci Ci 2.52E-Ol 2.42E-03 4.13E+00 5.71E-01 (1)
Predicted estimation of releases.
(2)
Include all particulate nuclides (even those with half-lives- <
8 days)
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EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SECOND HALF 1993 A.
Solid Waste Shipped Offsite For Burial Or Disposal (Not Irradiated Fuel) 1.
Type of Waste Units Amount Error m3 Ci a.
Spent resins, filter 8.55E+01
- sludges, evaporator 1.97E+02 1.50E+01
- bottoms, etc.
- b.
Dry compressible waste m
contaminated equip., etc.
Ci c.
Irradiated components, m3 control rods, etc.
Ci 1
2 '9E+01 2.45E+01 9.91E+00 6.31E+04 1.50E+Ol 1.50E+Ol d.
Other m3 Ci O.OOE+00 O.OOE+00 N/A Dry compressible waste shipped from processor to the burial ground.
24.5 m, 9.15-01 Ci.
These numbers are included in b.
2.
Estimate of major nuclide composition (by waste type) a.
Spent resins, filter sludge, evaporator bottoms, etc.
nuclide l.
Iron 55 (2) 2.
Cobalt-60 (1) 3.
Cesium-134 (1) 4.
Cesium-137 (1) 5.
Nickel-63 (1) 6.
Manganese-54 (1) 7.
Zinc-65 (1) 8.
Silver-llOM (1) 9.
Other
~Perceata e
7.61E+00 3.02E+Ol 4.97E+00 2.13E+Ol 1.40E+Ol 5.49E+00 9.24E%00 5.45E+00 Ci 1.50E+01 5.97E+01 9.82E+00 4.21E+Ol 2.77E+Ol 1.09E+Ol 1.82E+Ol 1.08E+01 2.06E+00 (1) Measured (2) Calculated E2-17
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EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SECOND HALF 1993 (Continued)
A.
Solid Waste Shipped Offsite For Burial Or Disposal (Not Irradiated Fuel) (Continued) 2.
Estimate of major nuclide composition (by waste type) (Continued) b.
Dry compressible
- waste, contaminated equipment, etc.
nuclide l.
Iron-55 (2)
Percenta e
1.34E+01 2.
Chromium-51 (1) 2.13Et01 3.
Cobalt-60 (2) 2.63E+Ol 4.
Manganese-54 (1) 1.00E+01 5.
Cobalt-58 (1) 3.20E+00 6.
Silver-110M (1) 6.70E+00 7.
Zinc-65 (2) 1.90E+Ol l.
Iron-55 (2) 4.87E+01 2.
Cobalt-60 (2) 3.82E+01 3.
Chromium -51 (2) 1.00E+00 4.
Manganese-54 (2) 8.50E+00 5.
Antimomy-124 (2) 2.00E+00 6.
Nickel-63 (2) 2.00E+00 d.
Other c.
Irradiated components, control rods, etc.
Ci 3.23E+00 5.14E+00 6.33E+00 2.35E+00 7.73E-01 1.61E+00 4.59E+00 3.07E+04 2.41E+04 5.36E+02 5.38E+03 1.19E+03 1.18E+03 None (1) Measured (2) Calculated E2-18
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EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SECOND HALF 1993 (Continued)
Solid Waste Disposition Number of
~Shi ments 21 3
10 Mode of T ans ortation Sole Use Truck Sole Use Truck Sole Use Truck Destination
- Barnwell, SC
- Quadrex, Oak Ridge, TN
- SEG, Oak Ridge, TN B.
Irradiated Fuel Disposition Number of
~Shi ments Mode of Trans ortation Destination None C.
Description of Shipments N/A N/A Number of
~Shi ments 13 Type Container Strong Tight Container (STC)
Type Number of
~uantit Containers A-LSA See Note Container Volume See Note Type Waste DAW 10 High Integrity Container (HIC)
HIC HIC HIC HIC A-LSA B-LSA A-LSA B-LSA 10 5.83m3 5.83m3 4.84m3 4.84m3 3.4lm3 Dewatered Resin Dewatered Resin Dewatered Resin Dewatered Resin Irradiated Hardware E2-19
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EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SECOND HALF 1993 (Continued)
C.
Description of Shipments (Continued)
HIC A-LSA Steel Liner 3.4lm3 1.63m3 DAW-Fuel Pool Filters Irradiated Hardware Solidification agents used:
None Absorbents used:
None NOTE:
13 shipments to waste processor contained the following:
Type of
~Packa e
40'ealand (STC) 20'ealand (STC)
"FR" Box (STC)
"B" Box (STC)
Leaded Box (STC)
Number of
~Packa ea 35 Volume Each Lal 72.50 36.25 06.40 02.66 12.90 3.17 4.56 E2-20
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EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT
SUMMARY
OF ABNORMAL/UNPLANNEDRELEASES SECOND HALF 1993 The radioactive effluents for the second half of 1993 were normal for a three unit boiling water reactor plant with one unit operating and the other two in extended outage.
The release of radioactive material to the environment from Browns Ferry has been a small fraction of the 10 CFR 20 Appendix B and 10 CFR 50 Appendix I limits.
There were no unusual nuclides during this period.
There was one abnormal limit liquid batch release which occurred on July 13, 1993, at 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br />.
A Floor Drain Sample Tank (FDST) was released while the Liquid Radwaste Effluent Radiation monitor (0-RM-90-130) was declared inoperable for setpoint adjustments to allow releases during planned Cooling Tower operations.
The Offsite Dose Calculation Manual requires two independent samples of the tank to be analyzed when the monitor is inoperable.
This requirement was not met since the monitor was believed to be operable.
- However, one sample of the tank was analyzed prior to the release.
An evaluation was performed, and it was determined that the radioactive waste in the FDST batch release was very low with respect to the 10 CFR 20 Appendix B, Table II Column 2 for radionuclides.
In addition, the pre-release, post-release, and projected monitor response calculations indicated that the waste activity released to the environs was satisfactory and no isolation would have occurred during the release.
There were no limits exceeded as specified in 10 CFR 20 Appendix B and 10 CFR 50 Appendix I.
An Incident,,Investigation was performed and, it was determined that an unmonitored release did not occur.
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EHCLOSURE 3 TEHHES SEE VALLEYAUTHORITY BROWS FERRY HUCLEAR PLAHT (BFH)
UHITS l~ 2~
AHD 3 IHOPERABLE RADIOLOGICAL EFFLUEHT IHSTRUM1HlTATIOH REPORT
e
INOPERABLE RADIOLOGICAL EFFLUENT INSTRUMENTATION REPORT This report is to comply with Browns Ferry Nuclear Plant Offsite Dose Calculation Manual (ODCM), Sections 1/2.1.1 and 1/2.1.2.
The ODCM requires the exertion of best efforts to return inoperable radiological effluent monitoring instrumentation to an operable status within 30 days.
Failure to return the inoperable instruments to an operable status requires a descri.ption in the next Annual Radioactive Effluent Release Report.
During the reporting period, July 1 through December 31, 1993, there was no airborne instrumentation inoperable for periods greater than 30 days.
The effluent monitors, which have been placed in "out-of-service" status with their effluent streams
- isolated, are not applicable for this report.
During this period, Units 1 and 3 were defueled and Unit 2 operating.
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ENCLOSURE 4 TEHHESSEE VAIL3KAUTHORITY BROWHS FERRY HU~ PLdLHT (BFN)
UHITS 1~
2~
AHD 3 CKLHGES TO THE OFFSITE DOSE CALCULATIONKLHUAL
~ ~
CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL (ODCM)
This report covers the period from July 1, 1993, through December 31, 1993.
During this reporting period, the Radiological Effluent Technical Specification (RETS) manual and ODCM were revised.
The RETS manual consisted of three documents, the Radiological Effluent Manual (REM),
ODCM, and Process Control Program (PCP).
The RETS manual was revised on October 1, 1993, (Revision 14), to incorporate the methodology for dose assessment and setpoint calculations for BFN's new Genie (ND9900) computer system.
Refer to the attached RETS manual pages 34 through 228 for the ODCM changes.
Changes are identified by a bar in the right-hand margin.
On December 1, 1993, TVA deleted the RETS manual in accordance with the guidance provided in Generic Letter 89-01.
As part of this revision, the ODCM and PCP were issued as stand alone documents.
The REM requirements were incorporated into the ODCM.
Refer to the attached ODCM for the changes.
Changes are identified by a bar in the right-hand margin.
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