ML18032A527
| ML18032A527 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 06/30/1987 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML18032A526 | List: |
| References | |
| NUDOCS 8709030350 | |
| Download: ML18032A527 (21) | |
Text
ENCLOSORE 1
TENNESSEE VALLEY AUTHORITY SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT BROWNS FERRY NUCLEAR PLANT EFfLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY THROUGH JUNE 1987 j
8709030350 85000259(
@gal ggQCK 0
@gal R
J EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION FIRST HALF 1987 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 calendar quarter to
< 5 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 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 live 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
< 7.5 mrem, and during any calendar year to 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 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
< 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.
0837k
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION FIRST HALF 1987 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 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.
BSC 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 II.
B and C.l. The instantaneous iodine and particulate release rates are limited by the following equation:
Q3
+
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.
0 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION FIRST HALF 1987 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 Part 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.
~ 1 III. 'verage Energy Not applicable IV.
Measurements and A
roximations of Total Radioactivit A. Fission and Activation Gases:
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.
BGC Iodines and Particulates 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 FIRST HALF 1987 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 tota1 volume released in each batch is determined.
The total gamma activity released in each batch is determined by multilying 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.
~
Batch Value Units First Second
- 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.
A.
Liquid 1.
Number of batches released 2.
Total time period for batch releases 164 111 Each 32334 24117 Minutes 3.
Maximum time period for a batch release 375 4.
Average time period for a batch releases 197 5.
Minimum time period for a batch release 10 380 Minutes 230 Minutes 10 Minutes 6.
Average stream flow during a period of release of effluent into a flowing stream 63500 27300 ft'/S B.
Gaseous None
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF 1987 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES Unit 1st 2nd guarter quarter X Error Fission and Activation Products 1.
Total Releases Curies 6.53E-02 8.11E-02 20 2.
Average Diluted Concentration During Period pCi/ml 1.16E-09 1.90E-09 3.
Percent of Applicable Limit (20 Ci/quarter)
Tritium 1.
Total Releases Curies 3.27E-01 4.06E-01 8.55E-01 5.08E-01 20 2.
Average Diluted Concentration During Period pCi/ml 1.52E-08 1.19E-08 3.
Percent of Applicable Limit (3E-03 pCi/ml)
Dissolved and Entrained Noble Gases'.
Total Releases 5.05E-04 3.96E-04 Curies
<2.63E-03
<3.54E-03 20 2.
Average Diluted Concentration During Period pCi/ml
<4. 66E-1 1
<8. 27E-11 3.
Percent of Applicable Limit (6E-06 pCi/ml)
Gross Alpha Radioactivity 1.
Total Releases Curies
<7.77E-04
<1.38E-03 1.91E-04
<3.60E-04 20
2.
Average Diluted Concentration During Period Volume of Waste Release (Before dilution)
Volume of Dilution Water for Period Total CCW flow for Six Months
'ncludes Xe-133, Xe-135, and others.
Liters Liters 1.38E+07 1.00E+07 5
5.64E+10 4.28E+10 5
135 gigagallons pCi/ml 3.39E-12
<8.41E-12
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID RELEASES FOR FIRST HALF 1987 BATCH MODE
~teoto e
(Required by REG Guide 1.21)
First Quarter Unit Curies Second Quarter Unit Curies 2.
3 ~
4 ~
5.
6.
7 ~
8.
Cr-51 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb-95 Zr-95 10.
I-131 11.
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 9.
Mo-Tc-99m
<8.35E-03 2.32E-04
<8.99E-04
<1.86E-03 1.07E-02 9.87E-03
<8.40E-04
<1.48E-03
<2.87E-04
<1.08E-03
<2.04E-03 1.23E-02
<5.92E-04 3.19E-02
<4.01E-03
<3.29E-04
<1.07E-03
<2.56E-04
<7.01E-05
<9.79E-03 3.89E-04
<1.00E-03
<2.16E-03 1.11E-02 7.31E-03
<1.04E-03
<1.82E-03
<7.66E-04
<1.31E-03
<2.79E-03 1.47E-02
<7.44E-04 4.74E-02
<5.08E-03
<4.41E-04
<1.37E-03
<4.02E-04
<1.22E-04
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID RELEASES FOR FIRST HALF 1987 BATCH MODE
~Ieoto e
Others (Not Required by REG Guide 1.21)
First Quarter Unit Curies Second Quarter Unit Curies 2.
Sb-125 Ce-144 3.
Co-57 2.20E-04 3.01E-05 1.74E-07 1.10E-04 5.97E-05 3.05E-07 This section was prepared principally by K. Richards.
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF 1987'ASEOUS EFFLUENTS SUMMATION OF ALL RELEASES.
Summation of All Releases Unit First guarter Second quarter' Error A.
B.
Fission and Activation Gases 1.
Total Releases Ci 3.
Percent of T.S. limit Iodines 1.
Total Iodine-131 Ci 2.
Average Release Rate for Period pCi/sec 3.10E-05 8.17E-03 3.94E-06 8.49E-06 7.88E-09 1.69E-08
<8.36E-04
<1.22E-03 20 20 2.
Average Release Rate for Period pCi/sec
<1.06E-04
<1.55E-04 C.
3.
Percent of T.S. Limit Particulates 0
Particulates with half-lives
>8 days Ci 4.99E-04 3.90E-04 20 D.
2.
Avg. release rate for period 3.
Percent of T.S.
4.
Gross alpha radioactivity Tritium 1.
Total release pCi/sec 6.35E-05 4.96E-05 1.24E-02 1.21E-06 1.59E-02 4.35E-07 Ci 2.12E-01 2.70E-02 5.01E-02 2.11E-01 3.26E-04 4.53E-01 Ci 2 e Percent of T.S.
3 ~
1.56E-01 4.52E-01 6.88E-04 Ci Ground level release 5.
Elevated release Ci Average release rate for period pCi/sec 5.76E-02 20 Reporting period 182 days.
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF 1987 GASEOUS EFFLUENTS ELEVATED RELEASE Fission Gases Unit First guaeter Second guarter Krypton-85 Krypton-85m Krypton-87 Krypton-88 Xenon-133 Xenon-135 Xenon-135m Xenon-138 Total for Period Ci Ci Ci Ci Ci Ci Ci Ci Ci
<2.28E+02
<6.79E-01
<1.56E+00
<2.06E+00
- 3. 10E-"05
<5.50E-01
<2.13E+01
<3.76E+01 3.10E-05 5.30E-03
<7.95E-01
<9.24E+00
<8.29E+00 2.87E-03
<2.10E+00
<2.07E+01 C6.80E+01 8.17E-03 Iodines Iodine-131 Iodine-133 Iodine-135 Total for Period Ci Ci Ci Ci
<1.06E-05
<2.95E-05
<3.29E-03
<3.33E-03
<3.92E-05
<1.36E-04
<2.00E-03
<2.18E-03
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF 1987 GASEOUS EFFLUENTS ELEVATED RELEASE (Continued)
Particulates Sr-89 Sr-90's-134 Cs-137 Ba-140 La-140 Total for Period Tritium Unit Ci Ci Ci Ci Ci Ci Ci Ci First quarter
<3.83E-07
<9.71E-08
<1.64E-05
<1.83E-05
<6.12E-05
<1.98E-05
<1.16E-04 6.88E-04 Second quarter
<3a19E-07
<1.21E-07
<8.04E-04
<6.43E+01
<3.56E-04
<2.29E-05
<6.43E+01 3.26E-04
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF 1987 GASEOUS EFFLUENTS GROUND LEVEL RELEASE Fission Gases Krypton-85 Krypton-85m Krypton-87 Krypton-88 Xenon-133 Xenon-135 Xenon-135m Xenon-138 Iodines Iodine-131 Iodine-133 Iodine-135 Unit Ci Ci Ci Ci Ci Ci Ci Ci Total for Period Ci Ci Ci Ci Total for Period Ci First guarter
<8.48E+01
<6.07E-01
<1.07E+00
<1.73E+00
<1.46E+00
<5.83E-01
<1.61E+00
<4.55E+00
<9.64E+01
<8.25E-04
<9.65E-04
<3.06E-01
<3.08E-01 Second quarter
<9.58E+00
<2.03E+00,
<5.02E+00
<6.33E+00
<6.58E+00
<5.76E-01
<1.39E+Ol
<2.94E+Ol
<7.34E+01
<1.18E-03
<1.90E-03
<8.65E-03
<1.17E-02 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF 1987 GASEOUS EFFLUENTS GROUND LEVEL RELEASE (Continued) 3.
Particulates Sr-89'r-90 Cs-134 Cs-137 Ba-140 La-140 Co-60 Unit Ci Ci Ci Ci Ci Ci Ci First quarter
<2.67E-06
<5.97E-07
<7.92E-04
<1.06E-03
<1.98E-03
<1.96E-04 4.99E-04 Second quarter
<4.39E-03
<2.42E-03
<3.19E+02
<4.58E+02
<1.59E-03
<1.79E-05 3.90E-04 Total for Period Ci Tritium Ci 4.
'redicted estimation of releases.
4.99E-04 4.52E-01 3.90E-04 2.11E-01
Type of Naste a.
Spent resins, filter sludges, evapor ator bot toms, etc
~
b.
Dry compressibl e waste, contaminated equip.,
etc c.
Irradiated components, control rods, etc.
Uni t m3 Ci m3 Ci m3 Ci 6 Nonth Period 2.11E+62
- 3. 61E+82 5 '1E+62
- 2. 21E+8 1
- 6. GGE+86 8. GGE+88 EFFLUENT AND WASTE DISPOSAL SENIANNUAL REPORT FIRST HALF 1987 SOLID, NASTE AND IRRADIATED FUEL SHIPMENTS Solid Naste Shipped Off-Site for Burial or Disposal (not i
fuel
)
rradiated Error y
1.58E+81
- 1. 58E+8 1
N/'A-d
~
Other m3 Ci G.GGE+88 G.GGE+88 MJ'A-2
~
Estimate of I"laJor Nuc1 ide Composi tions (by type of waste) a.
Spent r esins, fi l ter sludges, evapor ator bot toms, etc.
Nuclide
- 1. Zinc-65
( 1) 2.
( 1) 3.
Cesium-134 (1) 4.
Coba l t-66
( 1)
- 5. Hanganese-54
( 1),
- 6. Iron-55 (2)
- 7. Other Nucl ides (2)
Uni t
- 2. 92E+8 1
- 2. 26E+8 1
8.94E+88
- 2. 61E+6 1
- 5. 86E-8 1
8.87E+68 4.21E+86 Uni t Ci
( 1)
- 1. 65E+82 Ci (1) 7
~ 94E+61 Ci
( 1) 3. 22E+8 1
Ci
( 1)
- 9. 39E+6 1=
Ci
( 1)
- 2. 47E+68 Ci (2) 3 ~ 28E+81 Ci (2) 1
~ 52E+6 1
( 1) Neasured (2) Estimated thru use of seal ing factors EFFLUENT AND WASTE DI SPOSAL SEt"IIANNUAL REPORT FIRST HALF 1987 SOLID WASTE AND IRRADIATED FUEL SHIPNENTS 'CONTINUED) 2
~
Estimate of NaJor Nucl ide Composi tions (by type of waste) b.
Dr y compr essible
- waste, contaminated equipment,.etc.
(con t'd)
Nuclide Uni t Uni t
- 1. Zinc-65 (2) 2.
Cesium-137 (2) 3
~ Cesium-134 (2) 4
~
Chr omi um-51 (2)
- 5. Cobalt-69 (2)
- 6. Iron-55 (2)
- 7. Iron-59 (2)
- 8. t"langanese-54 (2) 5'.
Si 1 ver-118m (2)
- 18. Niobium-95 (2) 11
~ Other Nucl ides (2) 1..5'GE+61 Ci (2) 4
- 7. 84E+88 Ci (2>
1
~ 15'E+88
.56E+88"-
- 7. 84E+88 1
~ 18E+81 Ci (2) 1
~ 56E+88 Ci (2) 2.61E+88-
- 1. 84E+8 1
- 2. 52E+8 1
Ci (2)
. 4.86E+86 Ci (2) 5.57E+88.
- 1. 31E+86 Ci (2)
- 2. 85'E-6 1
4.33E+88 Ci (2) 9.57E-G 1
1.38E+88 Ci (2) 2.87E-81
- 2. 26E+88 Ci (2) 5
~ GGE-8 1
- 2. 31E+88 Ci (2) 5'. 11E-8 1
( 1)
I"leas ur ed (2> Estimated thru dose to curie and scaling factors c.
Irradiated Components, Control
- Rods, etc NONE d.
Other NONE 3.
Solid Waste Disposition Number of Shi pmen ts 75 B. Irradiated Fuel Disposition Number of Shi pmen ts NONE 1"lode of Transpor tation Sole Use Trucl:
Node of Transportation NVA Destination
- Barnwell, SC Destination Nf'A EFFLUENT AND NASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF 1987 SOLID-NASTE AND IRRADIATED FUEL SHIPMENTS C.
Naste
- Sources, Classification, Type Quanity and Container and flumber Used "L
- Type, Volume Type of Naste Type Burial Container Number of Quani ti ty Class Type Containers Disposal Volume-DEWATERED (Resin)
RX CLEANUP RX CLEANUP CONDSf'WASTE (Filters)
B-LSA B-LSA A-LSA A-LSA B-Stable HIC A-Stable HIC A-Stable HIC-A-Unstable 17H 2
1 1
238 119 8433 7.5 DRY ACTIVE NASTE (Compacted)
DRUM BOX A-LSA A-LSA A-Uns t ab 1 e 17H A-Unstable STC 102 81 765 7394 (Uncompac ted)
DRUM BOX N/A A-LSA N/A lib'A A-Unstable STC NONE 117 Mr'A 1 1385 SOLIDIF I ED N/A t O'A MONE Nt'A ABSORBED N/A tabb'A NONE N/'A Solidification agent or Absorbent used:
NONE