ML20108B393
| ML20108B393 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 12/31/1995 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20108B390 | List: |
| References | |
| NUDOCS 9605030302 | |
| Download: ML20108B393 (26) | |
Text
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ENCLOSURE 1 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT i
FOR THE PERIOD OF JANUARY 1 TO DECEMBER 31,1995 i
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i l-9605030302 960429 PDR ADOCK 05000327 R
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l EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION 1995 k.
1.
REGULATORY LIMITS 4
'A.
Gaseous Effluents 1.
Dose rates due to radioactivity released in gaseous effluents from the
[
site to areas at and beyond the unrestricted area boundary shall be limited to the following:
1 1
1
- a. Noble gases:
- Less than or equal to 500 mrem / year to the total body.
- Less than or equal to 3000 mrem / year to the skin.
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- b. lodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days:
j i
- Less than or equal to 1500 mrem / year to any organ.
l 2.
Air dose due to noble gases released in gaseous effluents to areas at and beyond the unrestricted area boundary shall be limited to the following.~
i
- a. Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation during any calendar quarter.
l
- b. Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation during any calendar year.
l i-3.
Dose to a member of the public from iodine-131, iodine-133, tritium, and i
all radionuclides in particulate form with half-lives greater than eight days i-in gaseous effluents released to areas at and beyond the unrestricted area boundary shall be limited to the following:
f'
- a. Less than or equal to 7.5 mrem to any organ during any calendar quarter.
I
- b. Less than or equal to 15 mrem to any organ during any calendar year.
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a i
' EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION
.1995 B.
Liquid Effluents 1.
The annual average concentration of radioactivity released in liquid effluents to unrestricted areas shall be limited to the concentrations specified in Title.10 of the Code of Federal Regulations, Part 20 (Standards for Protection Against Radiation), Appendix B, Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.0 E-04 microcuries/ milliliter ( Ci/ml) total activity.
2.
The dose or dose commitment to a member of the public from i
radioactivity in liquid effluents released to unrestricted areas shall be limited to;
- a. Less than or equal to 1.5 mrem to the total body and less than or equal to 5 mrem to any organ during any calendar quarter,
- b. Less than or equal to 3 mrem to the total body and less than or equal j
to 10 mrem to any organ during any calendar year.
2.
' EFFLUENT CONCENTRATION LIMITS A.
Liquids
]
- 1.
The Effluent Concentration Limits (ECL) for liquids are those listed in 10 CFR 20, Appendix B, Table 2, Column 2. For dissolved and entrained gases the ECL of 2.0E-04 Ci/miis applied. This ECL is based on the Xe-135 concentration in air (submersion dose) converted to an equivalent concentration in water as discussed in the International 3
Commission on Radiological Protection (ICRP), Publication 2.
i
- These values are used as applicable limits for liquid and gaseous effluents.
B. Gaseous
- 1.
The maximum permissible dose rates for gaseous releases are defined in plant Offsite Dose Calculation Manual (ODCM).
- a. Noble gas dose rate at the unrestricted area boundary:
- Less than or equal to 500 mrem / year to the total body,
- Less than or equal to 3000 mrem / year to skin.
4 l
i 4
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT i
SUPPLEMENTAL INFORMATION 1995 l
{
. b. lodine-131, iodine-133, tritium, and particulates with half-lives greater n
than eight days dose rate at the unrestricted area boundary:
Less than or aqual to 1500 mrem / year to any organ.
"These values are used as applicable limits for liquid and gaseous effluents.
i i
3.
AVERAGE ENERGY i
Sequoyah's ODCM limits the dose equivalent rates due to the release of noble gases to less than or equal to 500 mrem / year to the total body and less than or equal to 3000 mrem / year to the skin. Therefore, the' average beta and gamma energies (E) for gaseous effluents as described in Regulatory Guide 1.21,
" Measuring, Evaluation, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-l
[
Water-Cooled Nuclear Power Plants," are not applicable.
l 4.
MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY i
NOTE: Every effort is made to ensure that effluent releases from Sequoyah are l
conducted such that all Offsite Dose Calculation Manual (ODCM) Lower
+
Limit of Detection (LLD) values are met. Whenever an analysis does not i
identify a radioisotope, s. "0.00E-01 Ci" is recorded for the release. This does not necessarily mean that no activity was released for that particular radionuclide, but that the concentration was below the ODCM l
and analysis LLD. Refer to Tables A and B for estimates of these typical LLD values.
i A.
Fission and Activation Gases i
Airborne effluent gaseous activity is continuously monitored and recorded.
i Additional grab samples from the shield building, auxiliary building, service building, and condenser vacuum exhausts are taken and analyzed at least t
i monthly to determine the quantity of noble gas activity released for the month l
j based on the average vent flowrates recorded for the sample period. Also, j
noble gas samples are collected and evaluated for the shield and auxiliary buildings following startup, shutdown, or rated thermal power change exceeding 15 percent within one hour (sampling only required if dose equivalent 1-131 concentration in the primary coolant or the noble gas activity
)
monitor shows that the containment activity has increased more than a factor j
of 3).
4 4
3 9
r-.
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT f
SUPPLEMENTAL INFORMATION 199fi i
The quantity of noble gases released through the shield and auxiliary building exhausts due to purging or venting of containment and releases of waste gas decay tanks are also determined.
i The total noble gas activity released for the month is then determined by summing all of the activity released from each vent for all sampling periods.
j l
' B.
lodines and Particulates -
j-lodine and particulate activity is continuously sampled. Charcoal and j
particulate samples are taken from the shield and auxiliary building exhausts and analyzed at least weekly to determine the total activity released from the l
plant based on the average vent flowrates recorded for sampling period.
~
Also, particulate and charcoal samples are taken from the auxiliary and shield j
building exhausts once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for 2 days following startup, shutdown, or a rated thermal power change exceeding 15 percent within'one hour. The -
quantity of iodine and particulate released froin each vent during each sampling period is then determined using the average vent flowrates recorded for the sampling period and activity concentration.
j 4
4 The total particulate and iodine activity released for the month is then i
determined by summing all of the activity released from the shield and
[
auxiliary building exhausts for all sampling periods.
C. ' Liquid Effluents Batch (Radwaste and during periods of primary to secondary leakage,
[
condensate regenerants to cooling tower blowdown)
Total gamma isotopic activity concentrations are determined on each batch of liquid effluent prior to release. The total activity of a released batch is j
determined by summing each nuclide's concentration and multiplying by the total volume discharged. The total activity released during a month is then determined by summing the activity content of each batch discharged during the month.
Continuous Releases and Periodic Continuous Releases (Condensate regenerants, turbine building sump and steam generator blowdown) 4 i
i E-r.
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION 1995 Total gamma isotopic activity concentration is determined daily on a composite sample from the condensate system and turbine building sump and weekly for steam generator blowdown. The total activity of the continuous release is determined by summing each nuclide's concentration and multiplying by the total volume discharged. The total activity released during the month is then determined by summing the activity content of each daily and weekly composite for the month.
- 5. BATCH Value 1st 2nd Half Half MQtti A. Liquid (Radwaste only)
- 1. Number of releases 170 204 Each
- 2. Total time period of releases 21,640 28,410 Minutes
- 3. Maximum time period of release 220 581 Minutes
- 4. Average time period of releases 127 139 Minutes
- 5. Minimum time period for release 58 60 Minutes
- 6. Average dilution strea.n flow during 32,862 34,732 CFS release periods - cubic feet /second (CFS)
B. Gaseous (Batches only, containment purges, and waste decay tanks)
- 1. Number of releases 9
15 Each
- 2. Total time period of releases 10,040 17,920 Minutes
- 3. Maximum time period for release 4,064 3,837 Minutes
- 4. Average time period for releases 1,115 1,194 Minutes
- 5. Minimum time period for release 4
60 Minutes 5
5
)
i EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION E
l 1
- 6. ABNORMAL RELEASES Value 1st 2nd Half Half Moita i
i A. Liquid j
1 Number of Releases 0
1 Total Activity Released 0.00E-01 1.20E-06 Ci B. Gaseous Number of Releases 0
0 Total Activity Released 0.00E-01 0.00E-01 Ci i
6
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT i
~
1995 4
LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES A.
Finaion and fat 20d atd
_4th Act'vation Produc*a UDR 9tt Qtt 9tt Qtt
% Error l
5
- 1. Total Rolee' sed
- 2. Average Dimted Curies 3.87E-01 4.08E-01 1.14E+00 1.60E+00 11.8E+01 Conc. Durirsg Period of All identified uCi/ml 1.01E-06 1.18E-06 2.01E-06 4.00E-06 I
lootopes
]
- 3. - Percent of 1.75E+00 1.69E+00 3.56E+00 2.93E+00 l
Applicable s
Limit
( }'ECLs10)
NOTE: Percent of applicable limit is based on identified isotope concentration after dilution, related to their appropriate ECL concentration and sum of all the isotope fractions compared to 10.0.
B.
Trkum
- 1. Total Released Curies 4.52E+02 5.39E+02 2.96E+02 1.78E+02 ti.8E+01
- 2. Average Diluted e
Conc. During 4
Period uCi/ml 1.18E-03 1.56E-03 5.21E-04 4.45E-04
- 3. Percent of Applicable Limit (1.0E-02 uCi/ml) 1.18E+01 1.56E+01 5.21E+00 4.45E+00 l
C.
Diamolved and Entrained Games
- 1. Total Released Curies 9.60E-03 1.13E-02 8.26E-02 3.54E-03 23.9E+01
- 2. Average Diluted Conc. During Period uCi/ml 2.51E-08 3.26E-08 1.45E-07 8.86E-09 3.
Percent of Applicable i
Limit i.
(2.0E-04 uCi/ml) 1.26E-02 1.63E-02 7.27E-02 4.43E-03 l
. D.
Gross Alpha Radioactivity I
- 1. TotalReloosed Curies 0.00E-01 0.00E-01 0.00E-01 0.00E-01 12.0E+01 E.
Volume of Wants i
Released Litors 4.94E+06 4.52E+06 6.32E+06 4.77E+06
- 4.0E+00 d
F.
Volume of Diluhon Water for Period Liters 3.77E+08 3.42E+08 5.62E+08 3.95E+08 11.1E+01 7
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1995 LIQUID EFFLUENTS - TOTAL PLANT DISCHARGE G.
Nuclide SumnlafY (Note: Refer to Table A for ODCM nuclides reported as 0.00E-01)
Required by ODCM/Others Fission and Activation Products Continuous Mode Batch Mode Quarter Quarter Quarter Quarter Nusinds
.V.DH ist 2nd 1st 2nd 1 Strontium-89 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 2.
Strontium-90 Cl 0.00E-01 0.00E-01 0.00E-01 0.00E-01 3.
Iron-55 Cl 0.00E-01 7.51E-04 9.13E-02 9.56E42 4.
Manganese-54 Ci 0.00E-01 0.00E-01 2.81E-03 2.02E-03 5.
Cobalt-58 Cl 1.60E-06 1.58E-06 1.16E-01 1.89E-01 6.
Iron-59 Cl 0.00E-01 0.00E-01 3.45E-04 2.51E-03 7.
Cobalt-60 Ci 6.12E-06 0.00E-01 6.26E-02 4.68E-02 8.
Zinc-65 Ci 0.00E-01 0.00E-01 8.83E-04 1.13E-05 9.
Molybdenum-99 Ci 0.00E-01 0.00E-01 1.10E-03 0.00E-01
- 10. lodine-131 Ci 0.00E-01 0.00E-01 1.51 E-02 1.07E-03
- 11. Cesium-134 Cl 7.57E-07 0.00E-01 6.58E-03 1.08E-02
- 12. Cesium-137 Ci 2.45E-05 1.49E-05 1.27E-02 1.71 E-02
- 13. Cerium-141 Ci 0.00E-01 0.00E-01 8.79E-06 0.00E-01
- 14. Cerium-144 Cl 0.00E-01 0.00E-01 2.21 E-04 0.00E-01
- 15. Antimony-125 Ci 7.45E-07 0.00E-01 4.31 E-02 2.18E-02
- 16. Cobalt-57 Ci 0.00E-01 0.00E-01 1.02E-03 7.59E-04
- 17. Chromium-51 Ci 0.00E-01 0.00E-01 1.10E-02 8.51 E-03
- 18. Niobium-95 Ci 0.00E-01 0.00E-01 4.40E-03 1.42E-03 8
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1995 LIQUID EFFLUENTS - TOTAL PLANT DISCHARGE Continuous Mode Batch Mode Quarter Quarter Quarter Quarter Nuchde UDR 1st 2nd ist 2nd
- 19. lodine-133 Ci 0.00E-01 0.00E-01 1.16E-03 1.35E-04
- 20. Zirconium-95 Cl 0.00E-01 0.00E-01 1.98E-03 3.99E-04
- 21. Technetium-99m Ci 0.00E-01 0.00E-01 9.78E-04 0.00E-01
- 22. Strontium-92 Cl 0.00E-01 0.00E-01 0.00E-01 1.19E-05
- 23. Tellurium-132 Cl 0.00E-01 0.00E-01 4.76E-06 0.00E-01
- 24. Antimony-124 Ci 0.00E-01 0.00E-01 2.09E-03 4.78E-04
- 25. Lanthanum-140 Ci 0.00E-01 0.00E-01 6.41 E-03 3.76E-04
- 26. Sodium-24 Ci 0.00E-01 0.00E-01 3.ts4E-05 0.00E-01
- 27. Niobium-97 Ci 0.00E-01 0.00E-01 0.00E-01 2.79E-05
- 26. Silver-110m Cl 0.00E-01 0.00E-01 3.72E-03 1.61E-03
- 29. Yttrium-91 Ci 0.00E-01 0.00E-01 0.00E-01 6.64E-03
- 30. Barium-139 Cl 0.00E-01 0.00E-01 0.00E-01 3.30E-05
- 31. Barium-140 Ci 0.00E-01 0.00E-01 6/1E-04 0.00E-01
- 32. lodine-135 Cl 0.00E-01 0.00E-01 0.00E-01 3.34E-05
- 33. Ruthenium-103 Ci 0.00E-Oi.
0.00E-01 6.53E-05 0.00E-01
- 34. Tin-113 Cl 0.00E-01 0.00E-01 2.63E-04 3.48E-05
- 35. Yttrium-93 Cl 0.00E-01 0.00E-01 6.44E-05 0.00E-01 i
- 36. Zinc-69m Ci 0.00E-01 0.00E-01 5.43E-06 0.00E-01 Total for Period Ci 3.37E-05 7.68E-04 3.87E-01 4.07E-01 i
^
9
I EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1995 LIQUID EFFLUENTS - TOTAL PLANT DISCHARGE G,
Nuclide Summary (Note: Refer to Table A for ODCM nuclides reported as 0.00E-01)
Required by ODCM/Others Dissolved and Entrained Noble Gases Continuous Mode Batch Mode d
Quarter Quarter Quarter Quarter l
Nuchde Unit 1st 2nd 1st 2nd 1.
Krypton 47 Cl 5.83E-07 0.00E-01 0.00E-01 1.86E-05 i
2.
Krypton 48 Cl 0.00E-01 0.00E-01 0.00E-01 0.00E-01 3.
Xenon 133 Ci 0.00E-01 0.00E-01 8.71 E-03 9.47E-03 4.
Xenon-133m Cl 0.00E-01 0.00E-01 0.00E-01 0.00E-01 l
5.
Xenon-135 Ci 0.00E-01 0.boE-01 6.59E-04 1.80E-03 6.
Xenon-138 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 7.
Krypton 45m Cl 0.00E-01 0.00E-01 0.00E-01 0.00E-01 8.
Xenon-131m Cl 0.00E-01 0.00E-01 2.18E-04 0.00E-01 9.~
Xenon-135m Ci 0.00E-01 0.00E-01 0.00E-01 1.87E-05
- 10. Krypton 45 Cl 0.00E-01 0.00E-01 0.00E-01 0.00E 11. Argon-41 Cl 0.00E-01 0.00E-01 9.83E-06 5.08E-06 Total for Period Ci 5.83E-07 0.00E-01 9.60E-03 1.13E-02 10
l EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT i
1995 LIQUID EFFLUEWTS - TOTAL PLANT DISCHARGE i
G.
Nuchde Summarv (Note: Refer to Table A for ODCM nuclides reported as 0.00E-01) l Required by ODCM/Others j
i j.
Fission and Acthrston Products Continuous Mode Batch Mode Quarter Quarter Quarter Quarter Nuchde UDR 3rd 4th 3rd 4th 1
1.
Strontium-89 Ci 0.00E-01 0.00E-01 0.00E-01 4.51E-04 q
4 2.
Strontium-90 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 3.
Iron-55 Cl 1.36E-03 0.00E-01 9.98E-02 9.40E-02 4,
Manganese-54 Cl 0.00E-01 0.00E-01 1.97E-02 1.34E-02 5.
Cobalt-58 Cl 0.00E-01 5.70E-04 6.32E-01 1.18E+00 l
6.
Iron-59 Ci 0.00E-01 0.00E-01 3.98E-03 2.00E-02
- 7. - Cobalt 40 Cl 0.00E-01 1.67E-05 7.92E-02 8.74E-02 8.
Zinc 45 Ci 0.00E-01 0.00E-01 3.76E-04 9.87E-05 l
9.
Molybdenum-99 Cl 0.00E-01 0.00E-01 3.51 E-04 0.00E-01 l
- 10. lodine-131 Cl 0.00E-01 0.00E-01 2.51E-03 3.91E-04
- 11. Cosium-134 Cl 6.09E-06 1.02E-05 5.14E-02 7.27E-03 l
- 12. Cesium-137 Cl 1.44E-05 2.29F.-05 7.74E-02 1.22E-02
- 13. Cerium-141 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01
- 14. Cerium-144 Ci 0.00E-01 0.00E-01 2.99E-04 1.79E-04
- 15. Antimony-125 Cl 0.00E-01 0.00E-01 3.74E-02 4.62E-02 e
- 16. Cobalt-57 Ci 0.00E-01 0.00E-01 2.37E-03 3.91E-03
- 17. Chromium-51 Ci 0.00E-01 0.00E-01 7.20E-02 6.27E-02
- 18. Niobium-95 Cl 0.00E-01 0.00E-01 2.47E-02 2.49E-02
- 19. lodine-133 Cl 0.00E-01 0.00E-01 1.01 E-03 0.00E-01 i
20, Zirconium-95 Cl 0.00E-01 0.00E-01 1.50E-02 1.51E-02
- 21. Technetium-99m Ci 0.00E-01 0.00E-01 3.24E-04 0.00E-01 1
' 22. Ruthenium-103 Cl 0.00E-01 0.00E-01 9.65E-04 1.41E-03 j
4 i
^
11 4
f EFFLUENT AND WAGTE DISPOSAL ANNUAL REPORT 1995 LIQUID EFFLUENTS - TOTAL PLANT DISCHARGE i
b Continuous Mode -
Batch Mode Quarter Quarter Quarter Quarter i
Nuchde MDB 3rd 4th 3rd 4th
- 23. Antimony-124 Cl 0.00E-01 0.00E-01 3.66E-03 4.48E 03
- 24. Lanthanum-140 Ci 0.00E-01 0.00E-01 3.28E-03 2.19E-03 i
- 25. Sodium-24 Ci 0.00E-01 0.00E-01 9.91 E-05 7.91E-05
- 26. Cesium-138 Ci 0.00E-01 0.00E-01 3.03E-05 0.00E-01 l
- 27. Strontium-92 Ci 0.00E-01 0.00E-01 2.79E-04 0.00E-01
- 28. Niobium-97 Ci 0.00E-01 0.00E-01 7.28E-04 0.00E-01
- 29. Yttrium-91m Cl 0.00E-01 0.00E-01 0.00E-01 2.58E-05 3
- 30. Silver-110m Cl 0.00E-01 0.00E-01 5.97E-03 1.21E-03
- 31. Cesium-136 Ci 0.00E-01 0.00E-01 0.00E-01 7.56E-06
- 32. lodine-132 Cl 0.00E-01 0.00E-01 1.09E-04 0.00E-01
- 33. lodine-135 Ci 0.00E-01 0.00E-01 3.30E-05 0.00E-01
- 34. Manganese-56 Cl 0.00E-01 0.00E-01 5.38E-06 0.00E-01
- 35. Tin-113 Cl 0.00E-01 0.00E-01 2.03E-03 2.45E-03
- 36. Cerium-143 Ci 0.00E-01 0.00E-01 1.96E-05 0.00E-01
- 37. Tellurium-129m Cl 0.00E-01 0.00E-01 1.13E-03 3.15E-04
- 38. Copper-64 Ci 0.00E-01 0.00E-01 5.74E-04 8.48E-04
- 39. lodine-134 Cl 0.00E-01 0.00E-01 2.06E-04 0.00E-01
- 40. Ruthenium-105 Cl 0.00E-01 0.00E-01 1.30E-04 0.00E-01 I
- 41. Tellurium-132 Cl 0.00E-01 0.00E-01 1.86E-04 0.00E-01 Total for Period Cl 1.38E-03 6.20E-04 1.14E+00 1.60E+00 i
1 i
12 1.._
i
- EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1995 LIQUID EFFLUENTS - TOTAL PLANT DISCHARGE i
G.
Nuclide Summary (Note: Refer to Table A for ODCM nuclides reported as 0.00E-01) -
J i
Required by ODCM/Others
)
Continuous Mode Batch Mode Quarter Quarter Quarter Quarter hlugjgit MOR
- 3rd 4th 3rd 4th 1.
Krypton 47 Cl 0.00E-01 0.00E-01 9.96E-06 0.00E-01 2.
Krypton 48 Cl 0.00E-01 0.00E-01 0.00E-01 2.45E-05 3.
Xenon-133 Cl 0.00E-01 0.00E-01 7.89E-02 3.35E-03 i
4.
Xenon-133m Cl 0.00E-01 0.00E-01 2.04E-04 0.00E-01 l
i 5.
Xenon-135 Ci 0.00E-01 0.00E-01 3.21E-03 6.34E-05 6.
Xenon-138 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E 01 7.
Krypton 45m Cl 0.00E-01 0.00E-01 0.00E-01 0.00E-01 8.
Xenon-131m Cl 0.00E-01 0.00E-01 2.57E-04 0.00E-01 i
9.
Xenon-135m Cl 0.00E-01 0.00E-01 0.00E-01 0.00E-01
- 10. Krypton 45 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01
- 11. Argon-41 Ci 0.00E-01 0.00E-01 2.64E-05 1.03E-04 Total for Period Ci 0.00E-01 0.00E-01 8.26E-02 3.54E-03 13
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 4
129.5 TABLE A LIQUID " TYPICAL LLD" EVALUATION ("
I at*
Nucluse ODCM LLD 1 hr 8 hr 32 hr Manganese-54 5.0E 3.36E-08 3.36E-08 3.37E-08 Cobalt-58 5.0E-07 2.53E-08 2.54E-06 2.56E-08 Iron-59 5.0E-07 5.26E-08 529E-08 5.37E-08 Cobalt-60 5.0E-07 4.63E-08 4.63E-08 4.64E-08 Zine-65 5.0E-07 2.95E-08 2.95E-08 2.96E-08 i
Molybdenum-99 5.0E-07 1.55E-07 1.67E-07 2.15E-07 Cesium-134 5.0E-07 1.91 E-08 1.91E-08 1.92E-08 Cesium-137 5.0E-07 3.87E-08 3.87E-06 3.87E-08 Cerium-141 5.0E-07 2.80E-06 2.81 E-08 2.87E-08 i
Cerium-144 5.0E-06 1.11E-07 1.12E-07 1.12E-07 lodine-131 1.0E-06 2.28E-06 2.34E-08 2.55E-08 Krypton-87 1.0E-05 1.16E-07 525E-07 (3)
Krypton-88 1.0E-05 9.95E-08 5.49E-07 (3)
Xenon-133 1.0E-05 4.19E-08 4.36E-08 4.98E-08 1
Xenon-133m 1.0E-05 1.42E-07 1.55E-07 2.13E-07 l
Xenon-135 1.0E-05 2.06E-08 3.50E-08 2.17E-07 Xenon-138 1.0E-05 8.37E-06 (3)
(3)
Nuchde ODCM LLD Tvalca! I i n Tritium 1.0E-05 1.2E-06 Gross Alpha 1.0E-07 2.0E-08 Strontium-89 5.OE-06 3.8E-06 Strontium-90 5.0E-08
^ 4E-08 Iron-55 1.0E-06 1.3E-08 NOTES. (1) LLD values are in uCi/ml.
(2) tt is the time between sample collection and counting time.
(3) T 1/2 too short.
14 s
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT j.tti GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES (GROUND LEVEL RELEASES) l Summahon of All jg 2nd aid 2
Releases MDR Qt Qt Qt Qt
% Error A; Noble Gases l
- 1. Total Released Cl 1.51E+01 1.60E+01 2.92E+01 3.66E+00 ti.1E+01
- 2. Average Release 4
[
Rats of Period pCL/sec 1.94E+00 2.04E+00 3.67E+00 4.61E-01 i
- 3. Percent of i
Apphcable Umit 1.15E-03 1.06E-03 2.00E-03 4.85E-04 l
i J
5.lodmes I
- 1. Totallodme-131 Cl 1.36E-06 0.00E-01 6.54E-06 1.59E-06 11.3E+01 1
- 2. Average Release Rate for Period uCi/sec 1.75E-07 0.00E-01 8.23E-07 2.00E-07 1
5
- 3. ~ Percent of Applicable Limit (1.60E-01 uCi/sec) 1.09E-04 0.00E-01 5.14E-04 1.25E-04 4
4 C. Partculates
~
- 1. Particulates with half-lives >8 days Ci 4.27E-06 0.00E-01 1.04E-05 3.42E-05 11.6E+01
- 2. Average Release Rate for Period uCi/sec 5.49E-07 0.00E-01 1.31E-06 4.30E-06 l
1
- 3. Percentof Applicable Limit 1.65E-05 0.00E-01 1.34E-06 3.12E-05 l
- 4. Gross Alpha Radio-3 activity Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01
- 2.1 E+01 j
D. Trihum i
i-
- 1. Total Release Cl 1.56E+01 2.60E+00 4.50E+00 1.81E+01
- 1.5E+01
- 2. Average Release Rate for Period uCi/sec 2.01 E+00 3.31 E-01 5.66E-01 2.28E+00 3
- 3. Percent of i
Applicable Limit (8.47E+04 uCi/sec) 2.37E-03 3.90E-04 6.68E-04 2.69E-03 l
t i
4 6
?
e 15
~
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT i
1991 GASEOUS EFFLUENTS - SUlm4ATION OF ALL RELEASES.
(GROUND LEVEL RELEASES) 1.
Noble Games
)
Required by l
l ODCIW0thers I
Continuous Mode Batch Mode Quarter Quarter Quador Quarter '.
l 1
Nuclule Mag ist 2nd 1st 2nd V
1
- 1. ' Krypton 47 Cl 0.00E-01 0.00E-01 0.00E-01 0.00E-01, l.
- 2. Krypton-88 Cl 0.00E-01 123E-02 925E-03 1.99E-02
- 3. Xenon-133 C1 2.63E-02 2.36E-02 1.32E+01 1.46E+01 1
- 4. ' Xenon-133m '
Ci 0.00E-01 0.00E-01 223E-01 2.65E-01 2
4
- 5. Xenon-135 Cl 5.64E-01 2.95E-02.
7.96E-01 7.64E-01 4
- 6. Xenon-138 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 7.
Krypton-65 Cl 0.00E-01 0.00E-01 0.00E-01 0.00E-01 i
j
- 8. Argon-41 Ci 6.6ec-03 0.00E-01 2.29E-01 2.34E-01
- 9. Krypton-65m Ci 2.77E-03 3.13E-03 3.11E-02 3.82E-02
- 10. Xenon-131m Cl 0.00E-01 0.00E-01 0.00E-01 0.00E-01 i ~
- 11. Xenon-135m Cl 1.27E-02 4.34E-03 1.16E-02 0.00E-01 Totalfor Period Cl 6.13E-01 729E-02 1.45E+01 1.59E+01 i
J 2.
lodmes l
' 1. lodine-131 Cl 1.36E-06 0.00E-01
- 2. lodine-133 Cl 1.56E-06 0.00E-01 i
^
3.
lodine-135 Cl 0.00E-01 0.00E-01 Total for Period Ci 2.92E-06 0.00E-01 NOTE Refer to Table B for ODCM nuclides reported as 0.00E-01.
l 1
k:
1 16 m
e,-.
e
-=,
- - ~ - -
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1Dk GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES (GROUND LEVEL RELEASES) i 3.
Estimulates RMWW W ODCM/Others Continuous Mode Quarter Quarter i
i.
Nuciede M0il 1st 2nd
- 1. Strontium-89 Cl 0.00E-01 0.00E-01 2.
Strontium-90 Ci 0.00E-01 0.00E-01 3.
Iron-59 Cl 0.00E-01 0.00E-01 4.
Cobalt 40 Cl 4.27E-06 0.00E-01
- 5. Zinc 45 Cl 0.00E-01 0.00E-01 4
6.
Manganese-54 Ci 0.00E-01 0.00E-01 7.
Cobalt-58 Cl 0.00E-01 0.00E-01 i
8.
Molybdenum-99 Ci 0.00E-01 0.00E-01 9.
Cesium-134 Cl 0.00E-01 0.00E-01
- 10. Cesium-137 Cl 0.00E-01 0.00E-01
- 11. Cerium-141 Cl 0.00E-01 0.00E-01
]
- 12. Cerium-144 Ci 0.00E-01 0.00E-01 Total for Period Cl 4.27E-06 0.00E-01 NOTE Refer to Table B for ODCM nuclides reported as 0.00E-01.
t I
e d
k t
17 w
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT l
. inns GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES (GROUND LEVEL RELEASES) 1.
Noble Gases Required by ODCM/Others Continuous Mode _
Batch Mode j
Quarter Quarter Quarter Quarter i
Nuchde Mag 3rd 4th 3rd 4th j
1.
Krypton-87 Cl 8.32E-05 1.10E-04 0.00E-01 0.00E-00 2.
Krypton-88 Cl 5.62E-03 2.73E-03 5.19E-03 0.00E-01 3.
Xenon-133 Ci 6.48E-01 2.85E-02 2.57E+01 2.27E+00 4.
Xenon-133m Cl 0.00E-01 0.00E-01 1.08E+00 8.91E-01 i
5.
Xenon-135 Ci 2.90E-02 2.78E-02 9.73E-01 1.32E-01 6.
Xenon-138 Cl 0.00E-01 0.00E-01 0.00E-01 0.00E-01 7.
Krypton-85 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 8.
Argon-41 Ci 0.00E-01 1.79E-02 6.16E-01 2.56E-01 i
9.
Krypton-85m Cl 2.15E-03 2.80E-03 1.56E-02 1.78E-03 L
- 10. Xenon-131m Ci 0.00E-01 0.00E-01 6.66E 0.00E-01 2
- 11. Xenon-135m Ci 1.55E-02 3.20E-02 0.00E-01 0.00E-01 Total for Period Cl 7.00E-01 1.12E-01 2.85E+01 3.55E+00 i
2.
lodines 1.
lodine-131 Cl 6.54E-06 1.59E-06 2.
lodine-133 Cl 0.00E-01 0.00E-01 3.
lodine-135 Ci 0.00E-01 0.00E-01 i
Total for Period Cl 6.542-06 1.59E-06 i
NOTE Refer to Table B for ODCM nuclides reported as 0.00E-01.
4 18
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1991 GASEOUS EFFLUENTS - SUlWMATION OF ALL RELEASES.
(GROUND LEVEL RELEASES) 4 k
1 -
3.
Particulates Required by ODCIWVothers '
Continuous Mode i
Quarter Quarter l
Nuchde UDR 3rd 4th 1.
Strontium-69 '
' Ci 0.00E-01 '
O.00E-01 l
2.
Strontium-90 Cl 0.00E-01 0.00E-01 3.
Iron-59 Cl 0.00E-01 0.00E-01 1
4.
Cobalt 40 '
Cl 0.00E-01 7.31E-06
- 5. - Zinc-65, Ci 0.00E-01 0.00E-01 6.
Manganese-54 Cl 0.00E-01 0.00E-01 l
7.
Cobalt-56 Cl 1.04E-05 2.22E-05 l
6.
Molybdenum-99 Cl 0.00E-01 0.00E-01 9.
Cesium-134 Ci 0.00E-01 0.00E-01
- 10. ' Cesium-137 Ci 0.00E-01 0.00E-01
- 11. Cerium-141 Cl 0.00E-01 0.00E-01
- 12. Cerium-144 Cl 0.00E-01 0.00E-01
- 13. Niobium-95 Cl 0.00E-01 1.62E 06
- 14. Zirconium-95 Ci 0.00E-01 3.06E-06 Total for Period Cl 1.04E-05 3.42E-05 j
NOTE
- Refer to Table 5 for ODCM nuclides reported as 0.00E-01.
l i
i j
l 19 1
7
\\
g
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT l
.1.EEft TABLEB GASEOUS " TYPICAL" LLD EVALUATKW" Noble Gas a tm Nuclide ODCM LLD 1 hr 1.5 hr Krypton-87 1.0E-04 2.06E-06 2.73E-06 Krypton-88 1.0E 1.61E-06 1.81 E-06
{
Xenon-133 1.0E 04 6.61E-07 6.63E-07 a
Xenon-133m 1.0E-04 2.34E-06 2.35E-06 Xenon-135 '
1.0E-04 3.43E.07 3.56E-07 Xenon-138 1.0E-04 1.40E-04.
6.10E-04 Particulats Samplom 1 hr
' 24 hr 7.0 da Manganese-54 1.0E-10 7.47E-12 3.12E-13 4.46E-14 Cobelt-58 1.0E-10 5.62E-12 2.35E-13 3.46E-14 Iron-59 1.0E-10 1.20E-11 5.02E-13 7.49E 'i4 Cobalt-60 1.0E-10 1.07E-11 4.46E-13 6.38E-14 Zinc-65 1.0E-10 6.71 E-12 2.80E-13 4.03E-14 Molybdenum-99 '
1.0E-10 3.43E-11 1.61E-12 4.70E-13 Cesium-134 1.0E-10 4.25E-12 1.77E-13 2.54E-14
' Cesium-137 -
1.0E-10 8.46E-12 3.54E-13 5.05E-14 Cerium-141 1.0E-10 5.10E-12 2.15E-13 326E-14 Corium-144 1.0E-10 2.01E-11 8.33E-13 1.20E-13 lodine-131 1.0E-10 4.76E-12 2.07E-13 3.77E-14 Charcoal Samole 1
i.
lodine-131 1.0E-11 7.25E-12 3.15E-13 5.74E-14 1
1 (1) LLD values are in Ci/ml.
(2) c.t is the time between sample collection and counting time.
(3) LLD beood on sample time + 30 min sample to analysis.
i I
i 20 I
~
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1991 TABLE B GASEOUS " TYPICAL" LLD EVALUATION")
Nuchde ODCM LLD Tvoical e e n Tri6um 1.0E-06 1.0E-11 Gross Alpha 1.0E-11 1.5E-14 Strontium-69 1.0E-11 1.0E-14 Strontium-90 1.0E-11 1.0E-15 NOTES: (1) LLD values are in uCi/cc.
(2) et for noble gases is the time from sampling to analysis.
t.t for charcoal and particulate samples is the midpoint of sampling to analysis.
21
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1Efft SOLID WASTE (RADIOACTIVE SHIPMENTS)
A.
Solid Weste Shipped O# site for Burial or Disposal (not Irradiated Fuel) 12 Month Est. Tot,
- 1. Type of Waste.
IlDit Period Error %
- a. Spent resins, filter sludges, evaporator m'
1.77E+01 11.00E-01 e
bottoms, etc.
Cl 7.01E+02 i1.5CE+01 3
- b. Dry Active Weste, Compressible Weste m
2.99E+01 11.00E-01 Contaminated Equipment, etc.
Cl 6.04E+00 i1.50E+01
- c. Irradiated C;.,mponents, Control m'
None N/A Rods, etc.
Ci None N/A
- d. Other m'
None N/A Cl None N/A
- 2. Estrnate of Maior Nuclide Composson (by tvoe of waste)
- a. Spent resins, filter sludges, evaporator bottoms, etc.
(nuclides determined by ;nessurement) puries Percent 1, Manganese-54 8.56E+00 1.22E+00
- 2. Iron-55 1.01 E+02 1.45E+01
- 3. Cobalt 40 2.32E+02 3.32E+01
- 4. Nickel 43 3.10E+02 4 42E+01
- 5. Cesium-134 1.17E+01 1.66E+00
- 6. Cesium-137 2.72E+01 3.88E+00
- b. Dry active waste, compressible waste, contaminated equipment, etc.
(nuclides determined by estimate) 1, iron-55 3.35E+00 5.55E+01
- 2. Cobalt-56 1.40E+00 2.32E+01
- 3. Cobalt 40 4.21E-01 6.97E+00
- 4. Nickel-63 3.45E-01 5.72E+00
- 5. Cesium-134 2.03E-01 3.37E+00
- 6. Cesium-137 2.98E-01 4.94E+00 1
- c. Irradiated Components N/A N/A
- d. Other N/A N/A I
22
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT
.itti j
SOLID WASTE (RADIOACTIVE SHIPMENTS)
- 3. Solid Wtste Dispoeillon
- s. Spent resins, filter sludges, evaporator bottoms, etc.
Number of Shioments Type Quantity Mode of Transportabon Dest naton 2
B-LSA Motor Freight Barnwell, SC 2
A-LSA Motor Freight Barnwell, SC j
- b. Dry active waste, compreseible waste, contaminated equipment, etc.
Number of Shloments Tvoo Quannty Mode of Transoortabon Deshnation 106 A-LSA Motor Freight Barnwell, SC
- c. Irradiated components, control rods, etc.
Number of Shioments Type Quantity Mode of Transoortanon Deshnaton 4
None N/A N/A N/A 4
- d. Other: Mechanical Filters, Floor Drain Media 4
Number of Shlomonts Tvoo Quantity Mode of Transportanon Deshnaton l
None N/A N/A N/A
- 4. Irradiated Fuel Shlomonts (Disposebon)
Number of Shloments Tvoe Quantity Mode of Transportanon Deshnabon None N/A N/A N/A
- 5. Sohdificaton of Waste Was solidification performed?
NO If yes, solidification media:
N/A 23
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1995 ATTACHMENT 1.0 INOPERABLE INSTRUMENTATION in accordance with SQN Technical Specification 6.8.4.f.1, the radioactive gaseous effluent monitoring instrumentation channels shown in Table 1.1-2 of the ODCM shall i
be OPERABLE with their alarm / trip setpoints set to ensure that the limits of the ODCM 1
are not exceeded.
During the period between 5/15/95 @ 2000 and 5/17/95 @ 0100, the auxiliary building stack flow monitor 0-F-30-174 has been determined to be inoperable. This period of inoperability was unknown to Operations personnel, so the associated ODCM action to estimate flow rate at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> was not performed During the timeframe of inoperability, 2nd quarter 1995, there was no noble gas, iodine, or particulate fadioactivity identified from the auxiliary building. Routinely, only a small trace of tritium is identified from auxiliary building relea'ses which has negligible impact on any offsite dose.
i i
i a
1 i.
h l
i
[.
i L
24 4
--,-w,
l EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1995
- ATTACHMENT 2.0 ABNORMAL RELEASES
-i i
in accordance with Regulatory Guide 1.21, any abnormal releases should be clearly identified in the annual effluent report and the methods utilized in evaluating any i radioactive effluents and/or offsite dose.
i 3,
Refuelina Water Storace Tank (RWST)
On 9/13/95 @ 2200, the Unit 2 RWST most was sampled and analyzed to contain 4
Co-58 of 3.99E-07 Ci/mi and Co40 of 8.66E-08 Ci/ml. However due to the heavy i
l rainfall, a maximum of 640 gallons from the moat overflowed to the environment prior to being pumped to the radwaste system. The 640 gallons resulted in approxiraately 1.2 pCi of radioactivity being released and only monitored by grab sampling and
' ~
analysis. The radioactivity was reported and evaluated as part of the September dose i
evaluation.
i 1
1 4
d
?
I 25
-