ML20209J122

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Annual Radioactive Effluent Release Rept, for 1998
ML20209J122
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 12/31/1998
From:
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20209J045 List:
References
NUDOCS 9907210130
Download: ML20209J122 (27)
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Text

r ENCLOSURE 1 1

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SEQUOYAH NUCLEAR PLANT I

1998 l

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EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION 1998 l.

REGULATORY LIMITS A.

Gaseous Effluents 1.

Dose rates du'e to radioactivity released in gaseous effluents from the site to areas at and beyond the unrestricted area boundary shall be limited to the following:

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.

b. lodine-131, lodine-133, tritium, and all radionuclides in particulate form with half-lives greater than eight days:

- Less than or equal to 1500 mrem / year to any organ.

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:

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.
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.

3.

Dose to a member of the public from lodino. :31, lodine-133, tritium, and radionuclides in particulate form with half-ims greater than eight days in gaseous effluents released to areas at and beyond the unrestricted area boundary shall be limited to the following:

a. Less than or equal to 7.5 mrem to any organ during any calendar quarter.
b. Less than or equal to 15 mrem to any organ during any calendar year.

B. Liauid 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 1

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION 1998 (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 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 to j

10 mrem to any organ during any calendar year.

il.

EFFLUENT CONCENTRATION LIMITS

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A.

Liauids

  • 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 pCi/ml is 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 Commission on Radiological Protection (ICRP), Publication 2.

  • These values are used as applicable limits for liquid and gaseous effluents.

l B.

Gaseous l

  • 1.

The maximum permissible dose rates for gaseous releases are defined in plant Offsite Dose Calculation Manual (ODCM).

i

a. Noble gas dose rate at the unrestricted area boundary:

l

- Less than or equal to 500 mrem / year to the total body.

- Less than or equal to 3000 mrem / year to skin.

b. lodine-131, lodine-133, tritium, and particulates with half-lives greater than eight days dose rate at the unrestricted area boundary:

- Less than or equal to 1500 mrem / year to any organ.

  • These values are used as applicable limits for liquid and gaseous effluents.

2

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EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION 1998 Ill. AVERAGE ENERGY 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 mremlyear 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-Water-Cooled Nuclear Power Plants," are not applicable.

IV. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY NOTE: Every effort is made to ensure that effluent releases from Sequoyah are conducted such that all ODCM Lower limit of Detection (LLD) values are met. Whenever an analysis does not identify a radioisotope, an "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 and analysis LLD. Refer to Tables A and B for estimates of these typical LLD values.

A.

Fission and Activation Gases Airborne effluent gaseous activity is continuously monitored and recorded.

AdMional grab samples from the shield building, auxiliary building, service building, and condenser vacuum exhausts are taken and analyzed at least monthly to determine the quantity of noble gas activity released for the month based on the average vent flow rates recorded for the sample period. Also, 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 is only required if the 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 of 3).

The quant!!y 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 of the activity released from each vent for the sampling periods.

B.

lodines and Particulates lodine and particulate activity is continuously sampled. Charcoal and particulate samples are taken from the shield and auxiliary building exhausts and analyzed at least weekly to determine the total activity released from the plant based on the average vent flow rates recorded for sampling period.

3

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION 1998 Also, particulate and charcoal samples are taken from the auxiliary and shield 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 from each vent during each sampling period is then determined using the average vent flow rates recorded for the sampling period and activity concentration.

The total particulate and iodine activity released for the month is then determined by summing all activity released from the shield and auxiliary building exhausts for the sampling periods.

C. Liauid 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 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)

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 volurne 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.

V. BATCH Value 1st 2nd Half Half Units A. Liauld (Radwaste only)

1. Number of releases

'T1 81 Each

2. Total time period of releases 8675 11170 Minutes
3. Maximum time period of release 157 280 Minutes
4. Average time period of releases 122 138 Minutes
5. Minimum time period for release 60 75 Minutes
6. Average dilution stream flow during 51,664 25,833 CFS release periods - cubic feet /second (CFS) 4

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION 1998 B. Gaseous (Batches only, containment purges, containment vents, and waste decay tanks)

1. Number of releases 93 77 Each
2. Total time period of releases 58,060 44,700 Minutes
3. Maximum time period for release 20,710 11,900 Minutes
4. Average time period for releases 624 580 Minutos
5. Minimum time period for release 25 17 Minutes VI. ABNORMAL RELEASES Value 1st 2nd Half Half Units A. Liauid Number of Releases 1

0 Total Activity Released 3.25E-01 0.00E-01 Cl B. Gaseous Number of Releases 1

0 Total Activity Released 2.09E-06 0.00E-01 Ci 1

5 J

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1998 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES A.

Fission and 1.s1 2nd 3rd 4th Activation Products Unit Otr Otr Otr Otr

% Error 1.

Total Release'd Curies 1.10E-01 1.49E-01 2.07E-01 1.25E-01 51.8E+01 2.

Average Diluted Period of Ali pCi/ml 8.17E-07 9.02E-07 1.41 E-06 8.95E-07 Identified 3.

Percent of 1.25E+00 1.45E+00 4.05E+00 1.10E+00 Applicable Limit (ECL110)

NOTE: Percent of applicable limit is based on identified isotope concentration after dilution, related to their appropriate ECL concentration and sum of the isotope fractions compared to 10.0.

B.

Tritium 1.

Total Released Curies 3.20E+02 4.71 E+02 7.26E+02 3.88E+02 51.8E+01 2.

Average Diluted Period pCi/mi 2.38E-03 2.85E-03 4.95E-03 2.78E-03 3.

Percent of Applicable 2.38E+01 2.85E+01 4.95E+01 2.78E+01 Limit (1.0E-02 pCi/ml)

C.

Dissolved and Entrained Gases 1.

Total Released Curies 2.44E-01 5.36E-01 2.15E+00 5.08E-02 53.9E+01 2.

Average Diluted Period pCi/ml 1.81 E-06 3.24E-06 1.47E-05 3.64E-07 3.

Percent of Applicable 9.06E-01 1.62E+00 7.33E+00 1.82E-01 Limit (2.0E-04 pCi/ml)

D.

Gross Alpha 1.

Total Released Curies 0.00E-01 0.00E-01 0.00E-01 0.00E-01 52.0E+01 E.

Volume of Waste Released Liters 1.65E+06 2.20E+06 2.67E+06 1.74E+06 14.0E+00 F.

Volume of Difution Water for Period Liters 1.33E+08 1.63E+08 1.44E+08 1.38E+08 51.1 E+01 6

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EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1998 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 Fission and Activation Products Continuous Mode Batch Mode Quader Quader Quader Quader Nuclide Unit 1st 2nd 1st 2nd 1.

Strontium-89 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 2.

Strontium-90 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 3.

Iron-55 Ci 0.00E-01 0.00E-01 1.10E-02 2.99E-02 4.

Manganese-54 Ci 0.00E-01 0.00E-01 7.69E-04 8.72E-04 1

5.

Cobalt-58 Ci 0.00E-01 0.00E-01 4.50E-02 4.15E-02 6.

Iron-59 Ci 0.00E-01 0.00E-01 1.74E-04 9.89E-06

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Cobalt-60 Ci 0.00E-01 0.00E-01 1.16E-02 1.77E-02 8.

Zine-65 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 9.

Molybdenum-99 Ci 0.00E-01 0.00E-01 9.98E-04 1.29E-03

10. todine-131 Ci 0.00E-01 0.00E-01 2.61 E-03 6.14E-03
11. Cesium-134 Ci 0.00E-01 0.00E-01 2.03E-03 3.09E-03
12. Cesium-137 Ci 0.00E-01 0.00E-01 2.92E-03 3.65E-03
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 0.00E-01 1.76E-05
15. Antimony-125 Ci 0.00E-01 0.00E-01 1.40E-02 2.94E-02
16. Cobalt-57 Ci 0.00E-01 0.00E-01 3.80E-04 5.49E-04
17. Chromium-51 Ci 0.00E-01 0.00E-01 1.95E-03 2.41 E-03 i

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18.' Niobium-95 Ci 0.00E-01 0.00E-01 2.29E-04 5.87E-04 4

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EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT i

1998 LIQUID EFFLUENTS -TOTAL PLANT DISCHARGE Continuous Mode Batch Mode Quader Quader Quader Quader Nuclide Unit 1st 2nd 1st 2nd

19. lodine-133 Ci 0.00E-01 0.00E-01 4.44E-04 1.08E-03
20. Zirconium-95 Ci 0.00E-01 0.00E-01 4.61 E-04 7.19E-04
21. Technetium-99m Ci 0.00E-01 0.00E-01 8.65E-04 1.36E-03
22. Strontium-91 Ci 0.00E-01 0.00E-01 0.00E-01 2.87E-05
23. Tellurium-132 Ci 0.00E-01 0.00E-01 0.00E-01 7.07E-06
24. Antimony-124 Ci 0.00E-01 0.00E-01 1.74E-03 1.05E-03
25. Lanthanum-140 Ci 0.00E-01 0.00E-01 1.39E-03 8.89E-04
26. Sodium-24 Ci 0.00E-01 0.00E-01 6.18E-06 0.00E-01

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27. Ruthenium-105 Ci 0.00E-01 0.00E-01 1.36E-04 0.00E-01 l
28. Silver-110m Ci 0.00E-01 0.00E-01 1.08E-02 6.26E-03
29. Cesium -136 Ci 0.00E-01 0.00E-01 0.00E-01 4.84E-05
30. Cesium-138 Ci 0.00E-01 0.00E.-01 0.00E-01 9.12E-06
31. Ruthenium-103 Ci 0.00E-01 0.00E-01 0.00E-01 1.33E-04
32. Barium-139 Ci 0.00E-01 0.00E-01 1.30E-05 3.38E-05
33. Barium-140 Ci 0.00E-01 0.00E-01 2.29E-05 3.43E-05
34. Tin-113 Ci 0.00E-01 0.00E-01 7.87E-05 1.67E-04
35. Tellurium-129m Ci 0.00E-01 0.00E-01 0.00E-01 9.76E-05 Total for Period Ci 0.00E-01 0.00E-01 1.10E-01 1.49E-01 i

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EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1998 LIQUID EFFLUENTS - TOTAL PLANT DISCHARGE G.

Nuclide Summarv (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 Quader Quader Quader Quader Nuclide Unit 1st 2nd 1st 2nd 1.

Krypton-87 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 2.

Krypton-88 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 3.

Xenon-133 Cl 0.00E-01 0.00E-01 2.35E-01 5.16E-01 4.

Xenon-133m Ci 0.00E-01 0.00E-01 1.28E-03 3.09E-03 5.

Xenon-135 Ci 0.00E-01 0.00E-01 2.57E-03 2.83E-03 6.

Xenon-138 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 f

7.

Krypton-85m Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 8.

Xenon-131m Ci 0.00E-01 0.00E-01 4.75E-03 1.44E-02 9.

Xenon-135m Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01

10. Krypton-85 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01
11. Argon-41 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Total for Period Ci 0.00E-01 0.00E-01 2.44E-01 5.36E-01 4

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l EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1998 LIQUID EFFLUENTS - TOTAL PLANT DISCHARGE G.

Nuclide Summarv (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 l

Quader Quader Quader Quader Nuclide Unit 3rd 4th 3rd 4th 1.

Strontium-89 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 2.

Strontium-90 Ci '

O.00E-01 0.00E-01 0.00E-01 0.00E-01 3.

Iron-55 Ci 0.00E-01 0.00E-01 4.65E-03 1.38E-02 4.

Manganese-54 Ci 0.00E-01 0.00E-01 1.41 E-03 3.90E-04 5.

Cobalt-58 Ci 0.00E-01 0.00E-01 9.18E-02 6.48E-02 6.

Iron-59 Ci 0.00E-01 0.00E-01 3.29E-04 2.13E-03

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7.

Cobalt-60 Ci 0.00E-01 0.00E-01 3.25E-02 4.31 E-03 8.

Zinc-65 Ci 0.00E-01 0.00E-01 3.47E-05 9.67E-06 9.

Molybdenum-99 Ci 0.00E-01 0.00E-01 3.53E-05 0.00E-01

10. lodine-131 Ci 0.00E-01 0.00E-01 4.06E-03 8.61 E-04
11. Cesium-134 Ci 0.00E-01 0.00E-01 1.79E-02 3.94E-03 1
12. Cesium-137 Ci 0.00E-01 0.00E-01 1.77E-02 3.03E-03
13. Cerium-141 Ci 0.00E-01 0.00E-01 1.92E-05 1.71 E-04
14. Cerium-144 Ci 0.00E-01 0.00E-01 1.48E-04 7.40E-04
15. Antimony-125 Ci 0.00E-01 0.00E-01 1.19E-02 6.51 E-03
16. Cobalt-57 Ci 0.00E-01 0.00E-01 5.64E-04 3.01 E-04
17. Chromium-51 Cl 0.00E-01 0.00E-01 6.53E-03 1.36E-02
18. Niobium-95 Ci 0.00E-01 0.00E-01 1.88E-03 3.27E-03
19. lodine-133 Cl 0.00E-01 0.00E-01 1.91 E-04 7.50E-06
20. Zirconium-95 Ci 0.00E-01 0.00E-01 1.13E-03 2.12E-03
21. Technetium-99m Cl 0.00E-01 0.00E-01 3.53E-05 0.00E-01 io

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1998 LIQUID EFFLUENTS - TOTAL PLANT DISCHARGE Continuous Mode Batch Mode Quarter Quarter Quarter Quarter Unit 3rd 4th 3rd 4th Nuclide

22. Cerium-143 Ci 0.00E-01 0.00E-01 0.00E-01 1.20E-05
23. Antimony-124 Ci 0.00E-01 0.00E-01 1.25E-03 1.12E-03
24. Lanthanum-140 Ci 0.00E-01 0.00E-01 3.56E-04 9.83E-05
25. Sodium-24 Ci 0.00E-01 0.00E-01 2.19E-06 1.10E-05
26. Cesium-136 Ci 0.00E-01 0.00E-01 1.2SE-04 0.00E-01
27. Silver-110m Ci 0.00E-01 0.00E-01 4.23E-03 9.36E-04
28. lodine-135 Cl 0.00E-01 0.00E-01 6.59E-05 0.00E-01
29. Rubidium-88 Cl 0.00E-01 0.00E-01 1.86E-04 0.00E-01
30. Tin-113 Ci 0.00E-01 0.00E-01 1.19E-04 1.95E-04
31. Tellurium-129m Ci 0.00E-01 0.00E-01 2.58E-03 2.80E-04
32. lodine-132 Ci 0.00E-01 0.00E-01 2.97E-03 6.62E-05
33. Ruthenium-103 Ci 0.00E-01 0.00E-01 3.52E-04 8.57E-04
34. Tellurium-132 Cl 0.00E-01 0.00E 01 2.30E-03 4.53E-05 Total for Period Cl 0.00E-01 0.00E-01 2.07E-01 1.25E-01 11 M

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1998 LIQUID EFFLUENTS - TOTAL PLANT DISCHARGE G.

Nuclide Summarv (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 Quarter Quarter Quarter Quarter Nuclide Unit 3rd 4th 3rd 4th 1.

Krypton-87 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 2.

Krypton-88 Ci 0.00E-01 0.00E-01 3.40E-05 0.00E-01 3.

Xenon-133 Ci 0.00E-01 0.00E-01 2.08E+00 4.46E-02 4.

Xenon-133m Ci 0.00E-01 0.00E-01 1.51 E-02 0.00E-01 5.

Xenon-135 Ci 0.00E-01 0.00E-01 6.68E-03 7.14E-05 6.

Xenon-138 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 7.

Krypton-85m Ci 0.00E-01 0.00E-01 7.36E-05 0.00E-01 8.

Xenon-131m Ci 0.00E-01 0.00E-01 4.20E-02 6.13E-03 9.

Xenon-135m Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01

10. Krypton-85 Ci 0.00E-01 0.00E-01 5.74E-03 0.00E-01
11. Argon-41 Ci 0.00E-01 0.00E-01 9.04 E-06 0.00E-01 l

Total for Period Ci 0.00E-01 0.00E-01 2.15E+00 5.08E-02 i

12

T' EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT t

19.9.8_

l TAdLE A LIQUID " TYPICAL LLD" EVALUATION")

At*

Nuclide ODCM LLD 1 hr 8 hr 32 hr Manganese-54 5.0E-07 3.36E-08 3.36E-08 3.37E-08 Cobalt-58 5.0E-07 2.53E-08 2.54E-08 2.56E-08 Iron-59 5.0E-07 5.26E-08 5.29E-08 5.37E-08 Cobalt-60 5.0E-07 4.63E-08 4.63E-08 4.64 E-08 Zinc-65 5.0E-07 2.95E-08 2.95E-08 2.96E-08 l

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-08 3.87E-08 Cerium-141 5.0E 07 2.80E-08 2.81 E-08 2.87E-08 Cerium-144 5.0E-06 1.11 E-07 1.12E-07 1.12E-07 lodine-131 1.0E-06 2.28E-08 2.34E-08 2.55E-Oe l

Krypton-87 1.0E-05 1.16E-07 5.25E-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 Xenon-133m 1.0E-05 1.42E-07 1.55E-07 2.13E-07 Xenon-135 1.0E-05 2.06E-08 3.50E-08 2.17E-07 Xenon-138 1.0E-05 8.37E-06 (3)

(3)

Nuclide ODCM LLD Tvoical LLD Tritium 1.0E-05 1.2 E-06 Gross Alpha 1.0E-07 2.0E-08 Strontium-89/90 5.0E-08 3.8E-08/1.4E-08 Iron-55 1.0E-06 1.3E-08 NOTES: (1) LLD values are in pCi/ml.

(2) At is the time between sample collection and counting time.

(3) T 1/2 too short.

13 i

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EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1998 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES (GROUND LEVEL RELEASES)

Summation of All 1st 2nd 3rd 4th Releases Unit Otr Otr Qtr Otr

% Error A. Noble Gases

1. Total Released Ci 3.70E+02 7.33E+02 1.12E+03 9.91 E+00 51.1 E+01
2. Average Reiease Rate of Period pCi/sec 4.76E+01 9.32E+01 1.41 E+02 1.25E+00
3. Percent of Limit 2.22E-02 4.91 E-02 8.28E-02 1.20E-03 B. lodines
1. Totallodine-131 Ci 0.00E-01 3.36E-05 3.68E-04 4.27E-05 51.3E+01
2. Average Release Rate for Period pCi/sec 0.00E-01 4.27E-06 4.63E-05 5.37E-06 l
3. Percent of Limit (3.78E-01 pCi/sec) 0.00E-01 1.13E-03 1.22E-02 1.42E-03 C. Particulates

)

f

1. Particulates with half-lives >8 days Ci 0.00E-01 0.00E-01 1.36E-04 3.64E-05 51.6E+01
2. Average Release Rate for Period pCi/sec 0.00E-01 0.00E-01 1.71 E-05 4.58E-06

)

3. Percent of Limit 0.00E-01 0.00E-01 2.61 E-04 4.97E-05
4. Gross Alpha Radio-activity Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 52.1E+01 D. Tritium
1. Total Release Ci 6.92E+00 1.41E+01 5.17E+01 1.10E+01 51.5E+01
2. Average Release Rate for Period pCi/sec 8.90E-01 1.79E+00 6.50E+00 1.38E+00
3. Percent of Limit (6.26E+04 pCi/sec) 1.42E-03 2.86E-03 1.04E-02 2.21E-03 14

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1998 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES (GROUND LEVEL RELEASES).

1.

Noble Gases Required by ODCM/Others Continuous Mode Batch Mode Quarter Quarter Quarter Quarter Nuclidq Unit 1st 2nd 1st 2nd 1.

Krypton-87 Ci 0.00E-01 0.00E-01 9.62E-03 1.29E-01 2.

Krypton-88 Ci 0.00E-01 0.00E-01 5 01E-01 1.28E+00 3.

Xenon-133 Ci 5.49E+00 1.05E+02 3.46E+02 5.74E+02 4.

Xenon-133m Ci 0.00E-01 0.00E-01 4.26E+00 8.27E+00 5.

Xenon-135 Ci 8.86E-02 1.75E+00 6.60E+00 2.12E+01 6.

Xenon-138 Ci 0.00E-01 0.00E-01 0 00E-01 0.00E-01 7.

Krypton-85 Ci 0.00E-01 0.00E-01 6.55E-02 0.00E-01 8.

Argon-41 Ci 0.00E-01 0.00E-01 8.97E-01 1.35E+00 9.

Krypton-85m Ci 0.00E-01 0.00E-01 3 44E-01 1.08E+00

10. Xenon-131m Ci 0.00E-01 1.34E+01 6.13E+00 5.13E+00
11. Xenon-135m Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Total for Period Ci 5.58E+00 1.20E+02 3.65E+02 6.12E+02 2.

lodines 1.

lodine-131 Ci 0.00E-01 3.36E-05 2.

lodine-132 Ci 0.00E-01 0.00E-01 3.

lodine-133 Cl 1.36E-05 3.22E-05 j

Total for Period Ci 1.36E-05 6.58E-05 NOTE: Refer to Table B for ODCM nuclides reported as 0.00E-01.

15

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1998 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES (GROUND LEVEL RELEASES) 3.

Particulates Required by ODCM/Others Continuous Mode Quarter Quarter Nuclide Unit 1st 2nd 1.

Strontium-89 Ci 0.00E-01 0.00E-01 2.

Strontium-90 Ci 0.00E-01 0.00E-01 3.

Iron-59 Ci 0.00E-01 0.00E-01 4.

Cobalt-60 Ci 0.00E-01 0.00E-01 5.

Zinc-65 Ci 0.00E-01 0.00E-01 6.

Manganese-54 Ci 0.00E-01 0.00E-01 7.

Cobalt-58 Ci 0.00E-01 0.00E-01 8.

Molybdenum-99 Ci 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 Ci 0.00E-01 0.00E-01
12. Cerium-144 Ci 0.00E-01 0.00E-01 Total for Period Ci 0.00E-01 0.00E-01 NOTE: Refer to Table B for ODCM nuclides reported as 0.00E-01.

16

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1998 GASEOUS EFFLUENTS -SUMMATION OF ALL RELEASES (GROUND LEVEL RELEASES) 1.

Noble Gases Required by ODCM/Others Continuous Mode Batch Mode Quarter Quarter Quarter Quarter Nuclide Unit 3rd 4th 3rd 4th 1.

Krypton-87 Ci 0.00E-01 0.00E-01 2.36E-01 0 00E-00 2.

Krypton-88 Ci 0.00E-01 0.00E-01 3.68E+00 2.04E-02 3.

Xenon-133 Ci 3.82E+00 1.82E-04 1.01 E+03 8.31 E+00 4.

Xenon-133m Ci 0.00E-01 0.00E-01 2.10E+01 2.21'i-01 5.

J'cen-135 Ci 5.35E-03 1.07E-04 4.84E+01 6.47E-01 6.

Xenon-138 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 7.

Krypton-85 Ci 0.00E-01 0.00E-01 4.94E-01 3.55E-01 8.

Argon-41 Ci 0.00E-01 0.00E-01 2.47E+00 3.10E-01 9.

Krypton-85m Ci 0.00E-01 0.00E-01 2.25E+00 3.49E-02 l

10. Xenon-131m Ci 1.19E+01 0.00E-01 1.43E+01 1.08E-02 i
11. Xenon-135m Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Total for Period Ci 1.58E+01 2.88E-04 1.10E+03 9.91 E+00 l

i 2.

lodines J

1.

lodine-131 Ci 3.68E-04 4.27E-05 2.

lodine-133 Ci 1.33E-05 0.00E-01 3.

lodine-135 Ci 0.00E-01 0.00E-01 Total for Period Ci 3.81E-04 4.27E-05 NOTE: Refer to Table B for ODCM nuclides reported as 0.00E-01.

17

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1998 GASEOUS EFFLUENTS -SUMMATION OF ALL RELEASES (GROUND LEVEL RELEASES) 3.

Particulates Required by ODCM/Others Continuous Mode Quarter Quarter Nuclide Unit 3rd 4th 1.

Strontium-89 Ci 0.00E-01 0.00E-01 2.

Strontium-90 Ci 0.00E-01 0.00E-01 3.

Iron-59 Ci 0.00E-01 0.00E-01 4.

Cobalt-60 Ci 7.96E-06 7.58E-06 5.

Zinc-65 Ci 0.00E-01 0.00E-01 1

6.

Manganese-54 Ci 3.34E-06 0.00E-01 7.

Cobalt-58 Ci 7.54E-05 2.48E-05 8.

Molybdenum-99 Ci 0.00E-01 0.00E-01 9.

Cesium-134 Ci 1.55E-05 0.00E-01

10. Cesium-137 Ci 1.06E-05 1.94E-06
11. Cerium-141 Ci 0.00E-01 0.00E-01
12. Cerium-144 Ci 0.00E-01 0.00E-01
13. Niobium-95 Ci 8.92E-06 1.87E-06
14. Techetium-99m Ci 0.00E-01 0.00E-01
15. Ruthenium-103 Ci 1.40E-05 1.63E-07 Total for Period Ci 1.36E-04 3.64E-05 NOTE: Refer to Table B for ODCM nuclides reported as 0.00E-01.

18

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT l

1998

{

TABLE B GASEOUS " TYPICAL" LLD EVALUATION")

Noble Gas m

gg Nuclide ODCM LLD 1 hr 15 hr Krypton-87 1.0E-04 2.08E-06 2.73E-06 Krypton-88 1.0E-04 1.61 E-06 1.81 E-06 Xenon-133 1.0E-04 6.61 E-07 6.63E-07 Xenon 133m 1.0E-04 2.:AE-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 Particulate Samole*

1 hr 24 hr 7.0 da Manganese-54 1.0E-10 7.47E-12 3.12E-13 4.48E-14 Cobalt-58 1.0E-10 5.62E-12 2.35E-13 3.46E-14 tron-59 1.0E-10 1.20E-11 5.02E-13 7.49E-14 Cobalt-60 1.0E-10 1.07E-11 4.46E-13 6.38E-14 Zine-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 8.48E-12 3.54E-13 5.05E 14 Cenum-141 1.0E-10 5.10E-12 2.15E-13 3.26E-14 Cerium-144 1.0E-10 2.01 E-11 8.33E-13 1.20E-13 lodine-131 1.0E-10 4.76E-12 2.07E-13 3.77E-14 Charcoaf Sample lodine-131 1.0E-11 7.25E-12 3.15E-13 5.74E-14 (1) LLD values are in pCi/ml.

(?) At is the time between sample collection and counting time.

(3) LLD based on sample time + 30 min. sample to analysis.

19

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1998 TABLE B GASEOUS " TYPICAL" LLD EVALUATION"'

Nuclide ODCM LLD Typical LLD Tritium 1.0E-06 1.0E-11 Gross Alpha 1.0E-11 1.5E-14 Strontium-89 1.0E-11 1.0E-14 Strontium-90 1.0E-11 1.0E-15 NOTES- (1) LLD values are in pCi/cc.

(2) At for noble gases is the time from sampling to analysis.

At for charcoal and particulate samples is the midpoint of sampling to analysis.

20

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1998 SOLID WASTE (RADIOACTIVE SHIPMENTS)

A.

Solid Waste Shipped Offsite for Burial or Disposal (not Irradiated Fuel) 12 Month Est Tot.

1. Tvoe of Waste Unit Period Error %
a. Spent Resins, Filter Sludges, Evaporator m*

1.51 E+01 12.00E-01 Bottoms, etc.

Ci 2.21 E+02 11.50E+00

b. Dry Active Waste, Compressible Waste m*

2.18E+01 15.00E-01 Contaminated Equipment, etc.

Ci 7.27E-01 15.00E-03

c. Irradiated Components, Control m*

None N/A Rods, etc.

Ci None N/A

d. Other: Mechanical Filters m*

3.41 E+00 12.00E-02 Ci 1.08E+01 15.00E-01

2. Es.timate of Maior Nuclide Composition (by tvoe of waste)
a. Spent resins, filter sludges, evaporator bottoms, etc. (nuclides determined by measurement)

Curies Percent 1.

Manganese-54 3.87E+00 1.75E+00 2.

Iron-55 1.60E+01 7.22E+00 3.

Cobalt-60 5.12E+01 2.32E+01 4.

Nickel-63 1.11E+02 5.02E+01 5.

Cesium-134 5.73E+00 2.59E+00 6.

Cesium-137 1.01 E+01 4.58E+00 7.

Cobalt-58 1.85E+01 8.38E+00 8.

Carbon-14 8.10E-01 3.70E-01 9.

Cobalt-57 9.97E-01 4.50E-01

10. Nickel-59 1.26E+00 5.70E-01
11. Antimony-125 1.29E+00 5.90E-01
b. Dry active waste, compressible waste, contaminated equipment, etc. (nuclides determined by estimate) 1.

Carbon-14 1.56E-03 2.20E-01 2.

Chromium-51 1.80E-02 2.47E+00 3.

Manganese-54 3.45E-03 4.70E-01 4.

Iron-55 2.93E-01 4.03E+01 5.

Cobalt-57 7.37E-04 1.00E-01 6.

Cobalt-58 1.98E-01 2.72E+01 7.

Iron-59 1.54E-03 2.10E-01 8.

Cobalt-60 7.18E-02 9.88E+00 9.

Nickel-63 5.44E-02 7.49E+00

10. Zirconium-95 2.10E-02 2.89E+00
11. Niobium-95 3.08E-02 4.24E+00
12. Silver-110m 1.16E-03 1.60E-01
13. Tin-113 8.04E-04 1.10E-01
14. Antimony-125 4.52E-03 6.20E-01
15. Cesium-134 3 38E-03 4.60E-01 i
16. Cesium-137 1.45E-02 2.00E+00
17. Cerium-144 8.19E-03 1.13E+00 21

r EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1998 SOLID WASTE (RADIOACTIVE SHIPMENTS)

2. Estimate of Maior Nuclide Composition (by tvoe of waste) (Cont )
c. Irradiated Components N/A N/A
d. Other: Mechanical Filters Curies Percent
1. Cesium-134 4.69E+00 4.33E+01 2.

Cesium-137 5.86E+00 5.41E+01 3.

Iron-55 1.68E-01 1.55E+00 4.

Cobalt-58 4.33E-02 4.00E-01 5.

Carbon-14 3.44E-02 3.20E-01 6.

Tin-113 1.06E-02 1.00E-01

3. Solid Waste Disposition
a. Spent resins, filter sludges, evaporator bottoms, etc.

Number of Shioments Tvoe Quantity Mode of Transoortation Destination 1

>A-LSA ll Motor Freight Barnwell, SC 2

A-LSA 11 Motor Freight Barnwell, SC I

b. Dry active waste, compressible waste, contaminated equipment, etc.

]

Number of Shioments Tvoe Quantity Mode of Transoortation Destination 52*

A-LSA Motor Freight Bamwell, SC

  • 52 of the shipments were shipped by a waste processor.
c. Irradiated components, control rods, etc.

1 Number of Shioments Tvoe Quantity Mode of Transportation Destination None N/A N/A N/A l

d. Other: Mechanical Filters Number of Shioments Tvoe Quantity Mode of Transportation Destination i

1 A-LSA 11 Motor Freight Bamwell, SC 4.

Irradiated Fuel Shioments (Disposition)

Number of Shioments Tvoe Quantity Mode of Transoc:tation Destination None N/A N/A N/A

5. Solidification of Waste Was solidification performed?

NO If yes, solidification media:

N/A 22

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1998 ATTACHMENT 1.0 INOPERABLE INSTRUMENTATION in accordance with SON Technical Specification 6.8.4.f.1, the radioactive liquid effluent monitoring instrumentation channels shown in Table 1.1-1 of the ODCM shall be " OPERABLE" with their alarm / trip setpoints set to ensure that the limits of the ODCM are not exceeded. Ifa radiation monitor is declared inoperable, then effluent releases may continue provided grab samples are collected and analyzed at a specified frequency. If the required instrumentation is out of service for greater than 30 days, it must be reported in the Annual Radioactive Effluent Release Report why the inoperability could not be corrected within the 30 days i

On April 17,1998 at 1745 Eastern daylight time (EDT), the turbine building sump effluent I

radiation monitor (0-RM-90-212) was removed from service and was not retumed to service until June 12,1998 at 1535 EDT. The initial problem with 0-RM-90-212 was that it intermittently initiated a high radiation alarm when there was no radioactivity present to provide for this increase in counts. During this timeframe, increased sampling and analysis were performed as j

required by the ODCM. A problem evaluation report (PER) documented the radiation monitor problems.

Several probierns were identified with the monitor.

The local recorder, which had recently been replaced, was identified as a source of Electro Magnetic induced (EMI) interference for the detector.

' Resistive corrosion had developed on the terminal block connections and relay contacts.

Loose mounting of relay terminal blocks because a previous TVA design had added a relay where there was not quite enough space.

Other radiation EMI susceptibility reduction modifications had not been designed and implemented.

In order to reduce this monitor's susceptibility to EMI and baseline the monitor with new detector and electronics, it was decided to replace the active components and do a design change that would simplify the monitor and add the EMI susceptibility reduction modifications.

These changes and the replacement of components took several weeks because of parts availability and the time it took to issue and approve a design change.

in accordance with SON Technical Specification 6.8.4.f.1, the radioactive gaseous effluent monitoring instrumentation channels shown in Table 1.1-2 of the ODCM shall be " OPERABLE" with their alarm / trip setpoints set to ensure that the limits of the ODCM are not exceeded. If a radiation monitor is declared inoperable, then effluent releases may continue provided grab samples are collected and analyzed at a specified frequency. Any deviation in this requirement is to be reported in the Annual Radioactive Effluent Release Report.

23

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1998 ATTACHMENT 1.0 INOPERABLE INSTRUMENTATION On May 7,1998 at 0435 EDT, Auxiliary Building Vent Radiation Monitor 0 RM-90-101 was tagged out of service to replace a pump starter and repair the sheet metal housing. The clearance was reviewed, approved for issue, and placed without knowing that removing the associated breaker from service rendered the auxiliary building stack flow rate monitor inoperable. The applicable actions were taken for removing the radiation monitor from service.

The flow rate monitor was not intended or expected to be made inoperable as part of the clearance boundary. Discussions with Maintenance personnel concerning the involved maintenance activity failed to identify the oversight. The LCO action tracking log entries were made to reflect the assumed configuration. As a result, the action to estimate the flow was not taken every four hours as required by the ODCM. This condition was identified on May 8,1998, while performing a surveillance at which time it was noted that an associated computer point was found to be a bad point. This point is the auxiliary building vent flow rate indication. The problem was documented in a PER.

On May 9,1998,0-RM-90-101 was aligned for normal operation per the system operation instruction. However, the radiation monitor was not declared operable at that time. The Instrument foreman and the unit supervisors were reviewing the paperwork. On May 9,1998 at 1747 EDT, the radiation monitor was returned to operable status with the exception of the "B" channel (noble gas). There appeared to be a problem with the filter take-up spool.

Accordingly, ODCM Action 42 required noble gas sampling and analysis every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The LCO tracking log was not updated to reflect the changes and applicable action to be taken.

However, the applicable actions were being taken.

On May 11,1998, prior to returning the radiation monitor to operable status, Maintenance personnel requested permission to perform a surveillance on the radiation monitor. The unit supervisor reviewed the LCO tracking log and based on the information therein, assumed that the equipment effected by surveillance was already inoperable and complying with the applicable actions. As part of the surveillance, the radiation monitor iodine and particulate samplers were isolated. This condition was discovered on May 12,1998 at 0120 EDT, during the required noble gas sampling. This condition failed to meet ODCM Actions 44 and 45, the collection of iodine and particulate and verification of sample flow with auxiliary equipment. This problem was documented in a PER.

24

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1998 ATTACHMENT 2.0 ABNORMAL /UNMONITORED RELEASES in accordance with Regulatory Guide 1.21, any abnormal releases should be clearly identified in the Annual Radioactive Effluent Release and the methods utilized in evaluating any radioactive effluents and/or offde dose.

Additional Eauipment Buildina Sump l

On January 20,1998 at 0020 Eastern standard time, it was discovered that the Unit 2 additional equipment building (AEB) sump had overflowed and water was running under the door to the environment. The spill was terminated at 0028 when the AEB sump pumps were started and pumped the sump level down. It was estimated about 648 gallons soaked into the ground over a two hour period. A PER was initiated. Numerous samples were collected and analyzed. The J

Yard Pond down stream of the storm drain was also sampled and no contamination was identified.

The radioactivity level based on a 650-gallon release resulted in approximately 1.44E+02 pCi of fission and activation products being released and 3.25E+05 Ci of tritium.

Potential Release via Power Operated Relief Valves (PORVs)

On May 19,1998 at 1042 Eastern daylight time, Unit 1 experienced a reactor trip. During the unit shutdown, the steam generator PORVs were opened to reduce system temperature and pressure. However, during Unit 1 operation, the steam generators had experienced a small primary-to-secondary leak of 20.00515 gallons / day. Therefore, the opening of the PORVs should have resulted in a small release of radioactivity. An evaluation was performed based on the radioactivity in the reactor coolant system, the leak rate and the time the PORVs were opened to quantify the potential release. Based on this evaluation, approximately 2.09 pCi of noble gas and fission and activation products were released.

Failure to Sample Both Lower & Upper Containment Prior to a Purae As required by ODCM SR 2.2.2.1.1, radioactive wastes shall be sampled and analyzed according to the sampling and analysis program of Table 2.2-2. On May 5,1998, while preparing a release permit to purge Unit 1 upper containment, the decision was made by the Chemistry shift supervisor that since only upper containment was being purged then only upper containment sampling was required. This decision was in direct conflict with the ODCM and the applicable release permit procedure, which required sampling of both upper and lower containment. Since there is relatively very little differences in upper and lower containment atmosphere and the purge only lasted 110 minutes, this error had a very small impact on any offsite dose. A PER was initiated on the failure to follow procedures.

25

i EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1998 ATTACHMENT 2.0 ABNORMAUUNMONITORED RELEASES Conservative Factor for PotentN Error on lodine and Particulate Samplina not used for the Auxiliary Buildina l

As required by ODCM SR 2.2.2.1.2,1he dose rate due to lodine-131, lodine-133, tritium, and for the radionuclides in particulate form w?h half-lives greater than eight days in gaseous effluents shall be determined, in accordance with +he sampling and analysis program specified in Table l

2.2-2. Potential errors in sampling and ai alysis of iodine and particulates within the radiation monitor (e.g., vacuum, potential sample line plate-out, filter media efficiency, etc.) are normally j

taken into account by using a conservative fcctor to over estimate the release. However, on February 12,1999, it was noted that this conservative correction factor was not in our calculation data base. To correct this deficiency, the 1998 data and dose calculations from iodine and particulates samples were increased by 20 percent prior to reporting and calculating any offsite dose. The data base has been correcte.d and documented in a PER.

l 1

26 4

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