ML18032A527

From kanterella
Jump to navigation Jump to search
Effluent & Waste Disposal Semiannual Rept,Jan-June 1987.
ML18032A527
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 06/30/1987
From:
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18032A526 List:
References
NUDOCS 8709030350
Download: ML18032A527 (21)
v • d • e


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

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT J 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.

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 0 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.

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.

Batch First Value Second Units A. Liquid

1. Number of batches released 164 111 Each
2. Total time period for batch releases 32334 24117 Minutes
3. Maximum time period for a batch release 375 380 Minutes
4. Average time period for a batch releases 197 230 Minutes
5. Minimum time period for a batch release 10 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 1st 2nd Unit 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) 3.27E-01 4.06E-01 Tritium
1. Total Releases Curies 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) 5.05E-04 3.96E-04 Dissolved and Entrained Noble Gases'.

Total Releases 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) <7.77E-04 <1.38E-03 Gross Alpha Radioactivity
1. Total Releases Curies 1.91E-04 <3.60E-04 20
2. Average Diluted Concentration During Period pCi/ml 3.39E-12 <8.41E-12 Volume of Waste Release (Before dilution) Liters 1.38E+07 1.00E+07 5 Volume of Dilution Water for Period Liters 5.64E+10 4.28E+10 5 Total CCW flow for Six Months 135 gigagallons

'ncludes Xe-133, Xe-135, and others.

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID RELEASES FOR FIRST HALF 1987 BATCH MODE

~teoto e First Quarter Second Quarter (Required by REG Guide 1.21) Unit Curies Unit Curies Cr-51 <8.35E-03 <9.79E-03

2. Mn-54 2.32E-04 3.89E-04 3~ Co-58 <8.99E-04 <1.00E-03 4 ~ Fe-59 <1.86E-03 <2.16E-03
5. Co-60 1.07E-02 1.11E-02
6. Zn-65 9.87E-03 7.31E-03 7~ Nb-95 <8.40E-04 <1.04E-03
8. Zr-95 <1.48E-03 <1.82E-03
9. Mo-Tc-99m <2.87E-04 <7.66E-04
10. I-131 <1.08E-03 <1.31E-03
11. Xe-133 <2.04E-03 <2.79E-03
12. Cs-134 1.23E-02 1.47E-02
13. Xe-135 <5.92E-04 <7.44E-04
14. Cs-137 3.19E-02 4.74E-02
15. Ba-140 <4.01E-03 <5.08E-03
16. La-140 <3.29E-04 <4.41E-04
17. Ce-141 <1.07E-03 <1.37E-03
18. Sr-89 <2.56E-04 <4.02E-04
19. Sr-90 <7.01E-05 <1.22E-04

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID RELEASES FOR FIRST HALF 1987 BATCH MODE

~Ieoto e First Quarter Second Quarter Others (Not Required by REG Guide 1.21) Unit Curies Unit Curies Sb-125 2.20E-04 1.10E-04

2. Ce-144 3.01E-05 5.97E-05
3. Co-57 1.74E-07 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.

First Second Summation of All Releases Unit guarter quarter' Error A. Fission and Activation Gases

1. Total Releases Ci 3.10E-05 8.17E-03 20
2. Average Release Rate for Period pCi/sec 3.94E-06 8.49E-06
3. Percent of T.S. limit 7.88E-09 1.69E-08 B. Iodines
1. Total Iodine-131 Ci <8.36E-04 <1.22E-03 20
2. Average Release Rate for Period pCi/sec <1.06E-04 <1.55E-04
3. Percent of T.S. Limit 0 C. Particulates Particulates with half-lives

>8 days Ci 4.99E-04 3.90E-04 20

2. Avg. release rate for period pCi/sec 6.35E-05 4.96E-05
3. Percent of T.S. 1.59E-02 1.24E-02
4. Gross alpha radioactivity Ci 4.35E-07 1.21E-06 D. Tritium
1. Total release Ci 4.53E-01 2.12E-01 20 2e Average release rate for period pCi/sec 5.76E-02 2.70E-02 3~ Percent of T.S. 1.56E-01 5.01E-02 Ground level release Ci 4.52E-01 2.11E-01
5. Elevated release Ci 6.88E-04 3.26E-04 Reporting period 182 days.

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF 1987 GASEOUS EFFLUENTS ELEVATED RELEASE First Second Unit guaeter guarter Fission Gases Krypton-85 Ci <2.28E+02 5.30E-03 Krypton-85m Ci <6.79E-01 <7.95E-01 Krypton-87 Ci <1.56E+00 <9.24E+00 Krypton-88 Ci <2.06E+00 <8.29E+00 Xenon-133 Ci 3. 10E-"05 2.87E-03 Xenon-135 Ci <5.50E-01 <2.10E+00 Xenon-135m Ci <2.13E+01 <2.07E+01 Xenon-138 Ci <3.76E+01 C6.80E+01 Total for Period Ci 3.10E-05 8.17E-03 Iodines Iodine-131 Ci <1.06E-05 <3.92E-05 Iodine-133 Ci <2.95E-05 <1.36E-04 Iodine-135 Ci <3.29E-03 <2.00E-03 Total for Period Ci <3.33E-03 <2.18E-03

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF 1987 GASEOUS EFFLUENTS ELEVATED RELEASE (Continued)

First Second Unit quarter quarter Particulates Sr-89 Ci <3.83E-07 <3a19E-07 Ci <9.71E-08 <1.21E-07 .

Sr-90's-134 Ci <1.64E-05 <8.04E-04 Cs-137 Ci <1.83E-05 <6.43E+01 Ba-140 Ci <6.12E-05 <3.56E-04 La-140 Ci <1.98E-05 <2.29E-05 Total for Period Ci <1.16E-04 <6.43E+01 Tritium Ci 6.88E-04 3.26E-04

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF 1987 GASEOUS EFFLUENTS GROUND LEVEL RELEASE First Second Unit guarter quarter Fission Gases Krypton-85 Ci <8.48E+01 <9.58E+00 Krypton-85m Ci <6.07E-01 <2.03E+00, Krypton-87 Ci <1.07E+00 <5.02E+00 Krypton-88 Ci <1.73E+00 <6.33E+00 Xenon-133 Ci <1.46E+00 <6.58E+00 Xenon-135 Ci <5.83E-01 <5.76E-01 Xenon-135m Ci <1.61E+00 <1.39E+Ol Xenon-138 Ci <4.55E+00 <2.94E+Ol Total for Period Ci <9.64E+01 <7.34E+01 Iodines Iodine-131 Ci <8.25E-04 <1.18E-03 Iodine-133 Ci <9.65E-04 <1.90E-03 Iodine-135 Ci <3.06E-01 <8.65E-03 Total for Period Ci <3.08E-01 <1.17E-02 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF 1987 GASEOUS EFFLUENTS GROUND LEVEL RELEASE (Continued)

First Second Unit quarter quarter

3. Particulates Ci <2.67E-06 <4.39E-03 Sr-89'r-90 Ci <5.97E-07 <2.42E-03 Cs-134 Ci <7.92E-04 <3.19E+02 Cs-137 Ci <1.06E-03 <4.58E+02 Ba-140 Ci <1.98E-03 <1.59E-03 La-140 Ci <1.96E-04 <1.79E-05 Co-60 Ci 4.99E-04 3.90E-04 Total for Period Ci 4.99E-04 3.90E-04
4. Tritium Ci 4.52E-01 2.11E-01

'redicted estimation of releases.

EFFLUENT AND WASTE DISPOSAL SENIANNUAL REPORT FIRST HALF 1987 fuel SOLID, NASTE AND IRRADIATED FUEL SHIPMENTS Solid Naste Shipped Off-Site for Burial or Disposal (not i rradiated

)

6 Nonth Error Type of Naste Uni t Period y

a. Spent resins, filter sludges, m3 2.11E+62 evapor ator bot toms, etc ~ Ci 3. 61E+82 1.58E+81
b. Dry compressibl e waste, m3 5 '1E+62 contaminated equip., etc Ci 2. 21E+8 1 1. 58E+8 1
c. Irr adiated components, m3 6. GGE+86 control rods, etc. Ci 8 . GGE+88 N/'A-d ~ Other m3 G.GGE+88 Ci G.GGE+88 MJ'A-2 ~ Estimate of I"laJor Nuc1 ide Composi tions (by type of waste)
a. Spent r esins, f i l ter sludges, evapor ator bot toms, etc.

Nuclide Uni t Uni t

1. Zinc-65 ( 1) 2. 92E+8 1 Ci ( 1) 1. 65E+82
2. Cesium-137 ( 1) 2. 26E+8 1 Ci (1) 7 94E+61

~

3. Cesium-134 (1) 8.94E+88 Ci ( 1) 3. 22E+8 1
4. Coba l t-66 ( 1) 2. 61E+6 1 Ci ( 1) 9. 39E+6 1=
5. Hanganese-54 ( 1), 5. 86E-8 1 Ci ( 1) 2. 47E+68
6. Iron-55 (2) 8.87E+68 Ci (2) 3 28E+81

~

7. Other Nucl ides (2) 4.21E+86 Ci (2) 1 ~ 52E+6 1

( 1) Neasured (2) Estimated thru use of seal ing factors EFFLUENT AND WASTE D I SPOSAL SEt"II ANNUAL REPORT FIRST HALF 1987 SOLID WASTE AND IRRADIATED FUEL SHIPNENTS 'CONTINUED) 2 ~ Estimate of NaJor Nucl ide Composi tions (by type of waste) (con t'd)

b. Dr y compr essible waste, contaminated equipment, .etc.

Nuclide Uni t Uni t

1. Zinc-65 (2) 1 ..5'GE+61 Ci (2) 4 15'E+88

~

2. Cesium-137 (2) 7. 84E+88 Ci (2> 1 .56E+88"-

3 ~ Cesium-134 (2) 7. 84E+88 Ci (2) 1 ~ 56E+88 4 ~ Chr omi um-51 (2) 1 ~ 18E+81 Ci (2) 2.61E+88-

5. Cobalt-69 (2) 1. 84E+8 1 Ci (2) . 4.86E+86
6. Iron-55 (2) 2. 52E+8 1 Ci (2) 5.57E+88.
7. Iron-59 (2) 1. 31E+86 Ci (2) 2. 85'E-6 1
8. t"langanese-54 (2) 4.33E+88 Ci (2) 9.57E-G 1 5'. Si 1 ver-118m (2) 1.38E+88 Ci (2) 2.87E-81
18. Niobium-95 (2) 2. 26E+88 Ci (2) 5 GGE-8

~ 1 11 ~ Other Nucl ides (2) 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 1"lode of Transpor tation Destination 75 Sole Use Trucl: Barnwell, SC B. Irradiated Fuel Disposition Number of Shi pmen ts Node of Transportation Destination NONE NVA Nf'A EFFLUENT AND NASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF 1987 SOLID-NASTE AND IRRADIATED FUEL SHIPMENTS "L

C. Naste Sources, Classification, Type Quanity and Container Type, Volume and flumber Used Type of Type Burial Container Number of Disposal Naste Quani ti ty Class Type Containers Volume-DEWATERED (Resin)

RX CLEANUP B-LSA B-Stable HIC 2 238 RX CLEANUP B-LSA A-Stable HIC 1 119 CONDSf'WASTE A-LSA A-Stable HIC- 8433 (Filters) A-LSA A-Unstable 17H 1 7.5 DRY ACTIVE NASTE (Compacted)

DRUM A-LSA A-Un s t ab e 1 17H 102 765 BOX A-LSA A-Unstable STC 81 7394 (Uncompac ted)

DRUM N/A N/A lib'A NONE Mr'A BOX A-LSA A-Unstable STC 117 1 1385 SOLIDI F I ED N/A t O'A MONE Nt'A ABSORBED N/A tabb'A NONE N/'A Solidification agent or Absorbent used: NONE

Retrieved from "https://kanterella.com/w/index.php?title=ML18032A527&oldid=2418416"