Text

Annual Radioactive Effluent Release Rept for Jan-Dec 1996
	ML20138F238
Person / Time
Site:	Sequoyah
Issue date:	12/31/1996
From:	; TENNESSEE VALLEY AUTHORITY
To:	;
Shared Package
ML20138F231	List: ML20138F227; ML20138F238; ML20138F243; ML20138F253; ML20138F258;
References
	NUDOCS 9705050309
	Download: ML20138F238 (26)
	v • d • e

[

i ENCLOSURE 1 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR TIIE PERIOD OF J.A NUARY I TO DECEMIIER 31,1996 9705050309 970430 PDR ADOCK 05000327 R

pgg

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION 1996 1.

REGULATORY LIMITS 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:

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, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 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 iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives 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.

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION 1996 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 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 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/mlis 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.

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.

2

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION 1996

b. lodine-131, iodine-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.

l 3.

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 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 Lignt-Water-Cooied Nuclear Power Plants," are not applicable.

4.

MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY NOTE: Every effort is made to ensure that effluent releases from Sequoyah are conducted such that all Offsite Dose Calculation Manual (ODCM) Lower Limit of Detection (LLD) values are met. Whenever an analysis does not identify a radioisotope, a "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 j

LLD values.

A.

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

Additional 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 flowrates 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 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 of 3).

3

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION 1996 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.

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.

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 flowrates recorded for sampling period.

Also, particulate and charcoal samples are taken from the auxiliary and shield building exhausts once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 flowrates recorded for the sampling period and activity concentration.

The total particulate and iodine activity released for the month is then 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 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

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION 1996 i

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 Units A. Liquid (Radvmte only)

1. Number of releases 137 143 Each

2. Total time period of releases 17,490 17,910 Minutes

3. Maximum time period of release 232 160 Minutes

4. Average time period of releases 128 125 Minutes

5. Minimum time period for release 73 45 Minutes

6. Average dilution stream flow during 43,000 39,235 CFS release periods - cubic feet /second (CFS)

B. Gaseous (Batches only, containment purges, containment vents, and waste decay tanks)

1. Number of releases 59 65 Each

2. Total time period of releases 42,120 47,430 Minutes

3. Maximum time period for release 4,036 6,274 Minutes

4. Average time period for releases 714 730 Minutes

5. Minimum time period for release 5

29 Minutes 5

o

_. _... - - _ - _.. ~. - _.. _ _ _ _. _ _. _ _ -

___m EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SUPPLEMENTAL INFORMATION 1996

6. ABNORMAL RELEASES Value l

1st 2nd l

Half Half Units i

l A. Liquid l

l Number of Releases 1

0 I

Total Activity Released 1.91 E-05 0.00E-01 Ci B. Gaseous l

Number of Releases 0

0 I

Total Activity Released 0.00E-01 0.00E-01 Ci r

l t

F 4

l l

l 4

6 l

^

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1996 I

LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 1

4 f

A.

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

% Error

.1.

Total Released Curies 6.99E-01 8.47E-01 5.03E-01 3.32E-01

1.8E+01

2. Average Diluted Period of All Cl/ml 1.95E-06 3.41 E-06 1.54E-06 1.13E-06 Identified i

3.

Percent of 5.14E+00 4.67E+00 1.41E+00 1.06E+00 Applicable Limit

( EECLs10)

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.

Tritium 1.

Total Released Curies 4.27E+02 3.29E+02 1.80E+02 3.25E+02 1.8E+01 2.

Average Diluted Period uCi/ml 1.19E-03 1.33E-03 5.50E-04 1.11E-03 3.

Percent of j

Applicable 1.19E+01 1.33E+01 5.50E+00 1.11 E+01 Limit (1.0E-02 uCi/mi)

C.

Dissolved and Entrained Gases 1.

Total Released Curies 6.30E-03 1.63E-02 4.46E-03 8.81E-03

3.9E+01 2.

/.verage Diluted Period uCi/ml 1.75E-08 6.57E-08 1.36E-08 3.00E-08 3.

Percent of Applicable 8.77E-03 3.28E-02 6.81E-03 1.50E-02 Limit (2.0E-04 gCi/ml)

D.

Gross Alpha 1.

Total Released Curies 0.00E-01 0.00E-01 0.00E-01 0.00E-01 22.0E+01 E.

Volume of Waste Released Liters 4.34E+06 3.29E+06 4.37E+06 3.72E+06 24.0E+00 F.

Volume of Difution Water for Period Liters 3.55E+08 2.45E+08 3.23E+08 2.90E+08

1.1 E+01 7

=_

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 Q_ uprter Quarter Quarter Quarter Nuclide Unit ist 2nd 1st 2nd 1.

Strontium-89 Ci 0.00E-01 0.00E-01 2.34E-04 1.64E-04 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 1.22E-01 8.86E-02 4.

Manganese-54 Ci 0.00E-01 0.00E-01 7.72E-03 6.51E-03 5.

Cobalt-58 Ci 4.44 E-05 4.44E-05 2.72E-01 5.82E-01 6.

Iron-59 Ci 0.00E-01 0.00E-01 2.06E-03 3.10E-03 7.

Cobalt-60 Ci 0.00E-01 0.00E-01 1.12E-01 5.03E-02

{

l 8.

Zinc-85 Ci 0.00E-01 0.00E-01 2.46E-05 7.26E-05 l

9.

Molybdenum-99 Ci 0.00E-01 0.00E.01 8.86E-06 2.65E-04

10. lodine-131 Cl 0.00E-01 0.00t-01 7.88E-05 1.97E-03

11. Cesium-134 Cl 3.42E-06 0.00E-01 4.80E-02 2.36E-02

12. Cesium-137 Ci 8.74E-06 1.04E-05 7.61 E-02 3.72E-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 4.91 E-04 0.00E-01 j

15. Antimony-125 Ci 0.00E-01 0.00E-01 3.29E-02 1.54E-02

16. Cobalt-57 Ci 0.00E-01 0.00E-01 2.09E-03 2.2GE-03

17. Chromium-51 Cl 0.00E-01 0.00E-01 4.29E-03 1.26E-02

18. Niobium-95 Ci 0.00E-01 0.00E-01 8.07E-03 4.43E-03 i

8

i EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1996 LIQUID EFFLUENTS - TOTAL PLANT DISCHARGE Continuous Mode Batch Mode Quader Quader Quader Quader Nuclide Unit ist.

2nd 1st 2nd

19. lodine-133 Ci 0.00E-01 0.00E-01 3.15E-05 8.29E-04

20. Zircenium-95 Ci 0.00E-01 0.00E-01 4.28E-03 2.16E-03

21. Technetium-99m Ci 0.00E-01 9.81 E-07 8.86E-06 2.65E-04

22. Strontium-91 Ci 0.00E-01 0.00E-01 0.00E-01 4.15E-05

23. Tellurium-132 Ci 0.00E-01 0.00E-01 0.00E-01 1.42E-04

24. Antimony 124 Cl 0.00E-01 0.00E-01 1.30E-03 5.64E-03 4

25. Lanthanum-140 Ci 0.00E-01 0.00E-01 9.56E-04 5.08E-04

26. Sodium-24 Ci 0.00E-01 0.00E-01 1.61 E-03 1.38E-03

27. Bromine-84 Ci 0.00E-01 0.00E-01 1.64E-05 0.00E-01

28. Silver-110m Ci 0.00E-01 0.00E-01 2.15E-03 3.84E-03 1

29. Yttrium-91 Ci 0.00E-01 0.00E-01 0.00E-01 1.15E-03

30. Cesium-138 Ci 0.00E-01 0.00E-01 0.00E-01 3.55E-05

31. lodine-132 Ci 0.00E-01 0.00E-01 0.00E-01 9.80E-05 i

32. Rubidium-88 Ci 0.00E-01 0.00E-01 0.00E-01 2.63E-05

33. Ruthenium-103 Ci 0.00E-01 0.00E-01 1.72E-05 0.00E-01

34. Tin-113 Cl 0.00E-01 0.00E-01 9.31 E-04 3.52E-04

35. Tellurium-129m Ci 0.00E-01 0.00E-01 0.00E-01 1.88E-03 Total for Period Ci 5.66E-05 5.58E-05 6.99E-01 8.47E-01 9

-... _. ~.

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1996 LIQUID EFFLUENTS - TOTAL PLANT DISCHARGE A

G.

Nuclide Summary (Note: Refer to Table A for ODCM nuclides reported as 0.00E-01) 1 Required by ODCM/Others i

i Dissolved and Entrained Noble Gases Continuous Mode Batch Mode i

Quarter Quarter Quarter Quarter Nuclide Unit 1st 2nd 1st 2nd i

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 l

3.

Xenon-133 Ci 0.00E-01 0.00E-01 5.77E-03 1.60E-02 4.

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

Xenon-135 Ci 0.00E-01 0.00E-01 2.37E-04 2.42E-04 6.

Xenon-138 Cl 0.00E-01 0.00E-01 0.00E-01 0.00E-01 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 2.93E-04 0.00E-01 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 9.96E-06 Total for Period Cl 0.00E-01 0.00E-01 6.30E-03 1.63E-02 j

10 a

.___._._._._m i

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1996 LIQUID EFFLUENTS - TOTAL PLANT DISCHARGE G.

N_uclide 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 i

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

Strontium-89 Ci 0.00E-01 0.00E-01 2.17E-04 1.19E-04 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 1.18E-01 6.96E-02 4.

Mangese-54 Cl 0.00E-01 0.00E-01 1.11 E-02 6.74E-03 5.

Cobalt-58 Ci 2.30E-05 0.00E-01 3.10E-01 1.98E-01 6.

Iron-59 Ci 0.00E-01 0.00E-01 2.11 E-04 2.83E-05 1

i

'7.

Cobalt-60 Ci 0.00E-01 0.00E-01 2.53E-02 4.00E-02 8.

Zinc-65 Ci 0.00E-01 0.00E-01 0.00E-01 1.21E-04 9.

Molybdenum-99 Ci 0.00E-01 0.00E-01 1.12E-04 0.00E-01

10. lodine-131 Cl 0.00E-01 0.00E-01 1.55E-03 8.64E-04

11. Cesium-134 Ci 0.00E-01 0.00E-01 6.42E-03 2.00E-03

12. Cesium-137 Ci 7.10E-06 0.00E-01 1.06E-02 3.16E-03

13. Cerium-141 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01

14. Cerium-144 Cl 0.00E-01 0.00E-01 4.35E-05 0.00E-01

15. Antimony-125 Ci 0.00E-01 0.00E-01 7.53E-03 5.84E-03

16. Cobalt-57 Ci 0.00E-01 0.00E-01 1.57E-03 1.30E-03

17. Chromium-51 Ci 0.00E-01 0.00E-01 3.89E-04 0.00E-01

18. Niobium-95 Ci 0.00E-01 0.00E-01 1.47E-03 7.78E-04

19. lodine-133 Ci 0.00E-01 0.00E-01 6.76E-04 6.69E-05

20. Zirconium-95 Ci 0.00E-01 0.00E-01 2.67E-04 2.38E-04

21. Technetium-99m Cl 0.00E-01 0.00E-01 1.12E-04 0.00E-01 11

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1996 LIQUID EFFLUENTS - TOTAL PLANT DISCHARGE Continuous Mode Batch Mode Quader Quader Quader Quader Unit 3rd 4th 3rd 4th Nuclide

' 22. Zinc-69m Ci 0.00E-01 0.00E-01 6.26E-06 0.00E-01

23. Antimony-124 Cl 0.00E-01 4 00E-01 6.40E-04 1.00E-03

24. Lanthanum-140 Ci 0.00E-01 0.00E-01 1.33E-04 0.00E-01

25. Sodium-24 Ci 0.00E-01 0.00E-01 1.31 E-03 2.00E-04

26. Cesium-138 Cl 0.00E-01 0.00E-01 1.89E-05 1.19E-05

27. Silver-110m Ci 0.00E-01 0.00E-01 4.94E-03 1.62E-03

28. lodine-134 Ci 0.00E-01 0.00E-01 1.20E-04 0.00E-01

29. Manganese-56 Ci 0.00E-01 0.00E-01 4.59E-06 7.88E-06

29. Tin-113 Ci 0.00E-01 0.00E-01 3.01 E-05 9.77E-05 Total for Period Cl 3.01 E-05 0.00E-01 5.03E-01 3.32E-01 12

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT l

1996 LIQUID EFFLUENTS - TOTAL PLANT DISCHARGE G.

Nuclide Summary (Note: Refer to Table A for ODCM nuclides reported as 0.00E-01) i Required by ODCM/Others Dissolved and Entrained Noble Gases Continuous Mode Batch Mode Quader Quader Quader Quader 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 1.13E-05 5.17E-05 3.

Xenon-133 Ci 0.00E-01 0.00E-01 4.37E-03 8.36E-03 4.

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

Xenon-135 Ci 0.00E-01 0.00E-01 7.23E-05 3.95E-04 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 0.00E-01 0.00E-01 8.

Xenon-131m Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 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 8.62E-06 0.00E-01 Total for Period Ci 0.00E-01 0.00E-01 4.46E-03 8.81E-03 i

i l

13

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1996 TABLE A LIQUID " TYPICAL LLD" EVALUATION")

6 t(23 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 4.64E-08 Zinc-65 5.0E-07 2.95E-08 2.95E-08 2.96E-08 Molybdenum-99 5.0E-07 1.55E-07 1.67E-07 2.15E-07 Cesium-134 5.0E-07 1.91 E-08 1.91 E-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-08 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 1.2E-06 Groos Alpha 1.0E-07 2.0E-08 Strontium-89/90 5.0E-08 '

3.8E-08/1.4E-08 fron.55 1.0E-06 1.3E-08 NOTES-(1) LLD values are in uCl/ml.

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

J (3) T 1/2 too short.

14 1

4

.. ~ -.. -. - -. -. -...... -..

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1996 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES (GROUND LEVEL RELEASES)

Summation of All 1st 2nd 3rd 4_th Releases.

Unit Otr Otr Otr Otr

% Error A. Noble Gases I

1. Total Released Ci 6.46E+00 5.45E+00 6.96E+00 1.86E+01

1.1 E+01

[

2. Average Release Rate of Period Ci/sec 8.22E-01 6.93E-01 8.76E-01 2.34E+00 j

3. Percentof Limit 1.39E-03 1.15E-03 8.64E-04 2.05E-03 j

B. lodines

1. Totallodine-131 Ci 0.00E-01 1.23E-06 0.00E-01 3.30E-06

1.3E+01 j

2. Average Release l

Rate for Period pCi/sec 0.00E-01 1.56E-07 0.00E-01 4.15E-07

3. Percentof Limit 1

'(3.78E-01 pCi/sec) 0.00E-01 4.14E-05 0.00E-01 1.10E-04 3

C. Particulates

1. Particulateswith j

half-lives >8 days Ci 0.00E-01 3.92E-05 0.00E-01 3.30E-06 21.6E+01

2. Average Release

?

Rate for Period uCl/sec 0.00E-01 4.99E-06 0.00E-01 4.15E-07

+

i

3. Percent of Limit 0.00E-01 6.13E-06 0.00E-01 5.10E-07

4. Gross Alpha Radio-activity Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 22.1 E+01 D.. Tritium

1. Total Release Cl 1.65E+01 5.60E+00 1.79E+01 2.35E+01

1.5E+01

2. Average Release Rate for Period Ci/sec 2.10E+00 7.12E-01 2.25E+00 2.96E+00

3. Percent of Limit (6.26E+04 Ci/sec) 3.35E-03 1.14E-03 3.60E-03 4.72E-03 N

15 i

i

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1996 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES (GROUND LEVEL RELEASES) i l

1.

Noble Gases Required by ODCM/Others i

Continuous Mode Batch Mode l

Quarter Quarter Quarter Quarter Nuclide Unit 1st 2nd 1st 2nd 1.

Krypton-87 Ci 5.19E-04 1.88E-03 0.00E-01 0 00E-01 2.

Krypton-88 Ci 1.05E-02 3.01 E-03 0.00E-01 0.00E-01 3.

Xenon-133 Ci 4.03E-02 1.60E-01 5.38E+00 4.38E+00 4.

Xenon-133m Cl 0.00E-01 0.00E-01 1.08E-02 2.88E-02 5.

Xenon-135 Cl 3.94E-02 2.89E-02 2.90E-01 2.61 E-01 i

.6.

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

Krypton-85 Ci 0.00E-01 0.00E-01 0.00E-01 5.72E-02 l

8.

Argon-41 Cl 1.89E-01 9.39E-02 4.08E-01 4.17E-01 9.

Krypton-85m Cl 3.07E-03 1.71E-03 4.08E-03 1.03E-03 I

.10. Xenon-131m Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 l

l 1

11. Xenon-135m Ci 8.25E-02 1.10E-02 0.00E-01 0.00E-01 Total for Period Cl 3.66E-01 3.01E-01 6.09E+00 5.15E+00 l

2.

lodines 1.

lodine-131 Ci 0.00E-01 1.23E-06 2.

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

lodine-135 Ci 0.00E-01 0.00E-01 I

j Total for Period Ci 0.00E-01 1.23E-06 j

i NOTE: Refer to Table B for ODCM nuclides reported as 0.00E-01.

l 1

16

.. ~ _ _..

i i

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1996 I

4

{

GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES j

]

(GROUND LEVEL RELEASES) i 1-t 3.

Particulates i

Required by l

ODCM/Others Continuous Mode i

Quarter Quarter j

. Nuclide Unit 1st 2nd I

1. Strontium-89 Cl 0.00E-01 0.00E-01 i-(

2.

Strontium-90 Ci 0.00E-01 0.00E-01 i

I

3. ~ Iron-59 Cl 0.00E-01 0.00E-01 I

i t

4.

Cobalt-60 Ci 0.00E-01 0.00E-01

\\

5.

Zinc-65 Cl 0.00E-01 0.00E-01 4

l 6.

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

Cobalt-58 Ci 0.00E-01 3.92E-05 8.

Molybdenum-99 Cl 0.00E-01 0.00E-01 J

9.

Ceslum-134 Ci 0.00E-01 0.00E-01

10. Cesium-137 Ci 0.00E-01 0.00E-01 s.

11. Cerium-141 Ci 0.00E-01 0.00E-01 i

}

12. Cerium-144 Ci 0.00E-01 0.00E-01 l-1 Total for Period ci 0.00E-01 3.92E-05 NOTE: Refer to Table B for ODCM nuclides reported as 0.00E-01.

i 4

1 i

1 1>

i 4.'

17 s

a 1,

a

i' 1

l EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT l

1996 l

GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES f

l (GROUND LEVEL RELEASES)

I l

l 1.

Noble Gases Required by ODCM'Others Continuous Mode Batch Mode Quader Quader Quader Quader Nuclide Unit 3rd 4th 3rd 4th 1

1.

Krypton-87 Ci 0.00E-01 3.34E-03 0.00E-01 0.00E-00 2.

Krypton-88 Ci 0.00E-01 5.39E-04 0.00E-01 0.00E-01

(

3.

Xenon-133 Ci 6.54E-01 1.76E-02 5.%b+00 1.73E+01 1

4.

Xenon-133m Cl 0.00E-01 0.00E-01 1.24E-01 4.60E-02 I

E. Xenon-135 Ci 2.01 E-02 2.39E-02 2.65E-01 4.77E-01 l

1-6.

Xenon-138 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 l

7.

Krypton-85 Ci 0.00E-01 0.00E-01 6.69E-02 1.05E-01 L

8.

Argon-41 Ci 4.20E-04 3.95E-02 2.89E-01 5.99E-01 f

9.

Krypton-85m Ci 0.00E-01 2.59E-03 1.48E-03 3.22E-03 l

10. Xenon-131m Cl 0.00E-01 0.00E-01 6.52E-03 3.30E 11. Xenon-135m Ci 0.00E-01 1.12E-02 0.00E 0.00E-01 l

Total for Period Ci 6.74E-01 9.87E-02 6.29E+00 1.85E+01 l

2.

lodines 1.

lodine-131 Ci 0.00E-01 3.30E-06 2.

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

lodine-135 Ci 0.00E-01 0.00E-01 l

Total for Period Ci 0.00E-01 3.30E-06 l

l NOTE: Refer to Table B for ODCM nuclides reported as 0.00E-01.

)

l 1

18

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1996 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 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 3.30E-06 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 Cl 0.00E-01 0.00E-01

12. Cerium-144 Cl 0.00E-01 0.00E-01

13. Niobium-95 Ci 0.00E-01 0.00E-01

14. Zirconium-95 Ci 0.00E-01 0.00E-01 Total for Period Cl 0.00E-01 3.30E-06 NOTE: Refer to Table B for ODCM nuclides reported as 0.00E-01.

19

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1996 i

TABLEB GASEOUS " TYPICAL" LLD EVALUATIONW Noble Gas A t<2>

Nuclide ODCM LLD 1 hr 1.5 hr Krypton-87 1.0E-04 2.08E-06 2.73E-06 i

Krypton-88 1.0E-04 1.61 E-06 1.81 E-06 I

Xenon-133 1.0E-04 6.61 E-07

- 6.63E-07 Xenon-133m 1.0E-04 2.34E-06 2.35E-06 i

Xenon-135 1.0E-04 3.43E 07 3.56E-07 Xenon-138 1.0E-04 1.40E-04 6.10E-04 i

Particulate Samole*

i hr 24 hr 7.0 da 1

1 Manganese-54 1.0E-10 7.47E-12 3.12E-13 4.48E-14 j

i Cobalt-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-14 Cobalt-60 1.0E-10 1.07E-11 4.46E-13 6.38E-14 Zinc-65 1.0E-10 6.71E-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 Cerium-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 Charcoal Sample lodine-131 1.0E-11 7.25E-12 3.15E-13 5.74E-14 (1) LLD values are in uCi/ml.

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

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

20 i

J

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1996 TABLE B GASEOUS " TYPICAL" LLD EVALUATION")

Nuclide ODCM LLD Tvoical 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 uCi/cc.

(2) 4t for noble gases is the time from sampling to analysis.

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

21

l

' EFFLUENT AND WASTE DISPOSAL' ANNUAL REPORT 1996 SOLID WASTE (RADIOACTIVE SHIPMENTS)

A.

Solid Waste Shipped Offsite for Burial or Disposal (not Irradiated Fuel)

(

12 Month Est. Tot.

l

1. Tvoe of Waste Qnit Period Error %

a. Spent resins, filter sludges, evaporator m

2.19E+01

5.00E-01 8

bottoms, etc.

Cl 5.65E+02 21.50E+00 l

b. Dry Active Waste, Compressible Waste m

5.75E+01

5.00E-01 8

l Contaminated Equipment, etc.

Cl 7.43E+00 t 5.00E-01 l

c. Irradiated Components, Control m

None N/A 8

l Rods, etc.

Ci None N/A l

d. Other: Mechanical Filters m

6.06E+00 5.00E-01 8

Ci 3.35E+01 5.00E-01

2. Estimate of Maior Nuclide Composition (by tVDe of waste)

a. Spent resins, filter sludges, evaporator bottoms, etc.

(nuclides determined by measurement) l l

l Curies Percent l

1, Manganese-54 1.78E+01 3.16E+00 l

2.

Iron-55 1.20E+02 2.12E+01

(

3.

Cobalt-60 1.36E+02 2.41 E+01 4.

Nickel-63 2.15E+02 3.80E+01 5.

Cesium-134 1.66E+01 2.95E+00 6.

Cesium-137 3.27E+01 5.78E+00 7.

Cobalt-58 1.28E+01 2.27E+00 l

8. Antimony-125 6.18E+00 1.09E+00 I

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

(nuclides determined by estimate) 1.

Iron-55 4.20E+00 5.65E+01 2.

Cobalt-58 1.67E+00 2.25E+01 3.

Cobalt-60 7.05E-01 9.49E+00 l

4.

Nickel-63 6.38E-01 8.59E+00 l

5.

Cesium-137 1.01 E-01 1.35E+00 l

c.

Irradiated Components N/A N/A 22

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT f

h 1996 l

j SOLID WASTE (RADIOACTIVE SHIPMENTS) i

[

2. Estimate of Maior Nuclide Composition (by type of wasteMCont.)

4 i

d. Other: Mechanical Filters Curies Percent

)

1, Chromium-51 4.23E-01 1.29E+00 t

2.

Manganese-54 5.74E-01 1.72E+00 i

3.

Iron-55 2.09E+01 6.24E+01 4.

Cobalt-58 1.05E+00 3.13E+00

)

5. Cobalt-60 7.34E+00 2.19E+01 l

4 6.

Nickel-63 2.18E+00 6.52E+00 l

j

3. Solid Waste Disposition i

l

a. Spent resins, filter sludges, evaporator bottoms, etc.

Number of Shioments Tvoe Quantity Mode of Transportation Destination 3

>A-LSA Motor Freight Barnwell, SC 2

A-LSA Motor Freight Barnwell, SC

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

1 Number of Shioments Tvoe Quantity Mode of Transportation Destination 112*

A-LSA Motor Freight Barnwell, SC

111 of the shipments were shipped by a waste processor.

1

c. Irradiated components, control rods, etc.

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

d. Other: Mechanical Filters Number of Shioments Tvoe Quantity Mode of Transportation Destination 1

>A-LSA Motor Freight

- Barnwell, SC 1

A-LSA Motor Freight Barnwell, SC

4. Irradiated Fuel Shioments (Disposition) l Number of Shioments Tvoe Quantity Mode of Transportation Destination None N/A N/A N/A

5. Solidification of Waste Was solidification performed?

NO If yes, solidification media:

N/A 23

i EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1996 ATTACHMENT 1.0 INOPERABLE INSTRUMENTATION 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 i

may continue provided grab samples are collected and analyzed at a specified frequency. If the required samples are not taken, the non-compliance must be reported in the annual report.

On 10/3/96 @ 1500 Unit 1 Condenser Vacuum Exhaust (CVE) radiation monitor (1-RM-90-119 Low range) was declared inoperable. Based on ODCM compliance requirements, grab samples were being collected and analyzed once/8 hours (ODCM requires once/12 hrs and does not consider the high range radiation monitor as a i

backup). On 10/5/96 @ 0045 a routine noble gas sample was collected and analyzed indicating a decrease in radioactivity being released from the CVE. An investigation revealed that the root valves to the radiation monitor had been isolated as a result of work being performed by the instrument maintenance group in an effort to repair the radiation monitor. A review of the data indicated that the time between accurate representative samples was 35 hours4.050926e-4 days 0.00972 hours 5.787037e-5 weeks 1.33175e-5 months and 10 min. vs the required 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . The i

radioactivity level in the CVE during the time of the event resulted in a dose of approximately 2.0E-04 mrem /yr. The administrative dose rate limit for the CVE based on design flow rates is 7.52E-02 mrem /yr with a site limit of 500 mrem /yr.

Chemistry for the extent of condition for this event (SQ962580PER) conducted a review of all noble gas samples collected from the CVE from 1/1/94 through 12/31/96 when the radiation monitor was inoperable and identified three questionable sample results.

These sample results were similar in dose rate to the 10/5/96 time frame but could not be directly attributed to instrument maintenance work and the position of the root valves of the radiation monitor. Two of the samples were accounted for in following release permits. The third sample in December of 1995 was evaluated indicating approximately 1.07E-04Ci of noble gases and tritium were not accounted for in the quarterly dose evaluation. This noble gas and tritium relative to the total curies released in 1995 of 98.06Ci is negligible.

The sampling procedure has been revised to ensure that when the radiation monitor is inoperable, samples are not collected from this location.

24

EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 1996 ATTACHMENT 2.0 ABNORMAL RELEASES 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 radioactive effluents and/or offsite dose.

Raw Coolina Water Pump Drain Pipina On 6/19/96 @ 1333, a Problem Evaluation Report (SQ961799PER) was initiated due to an unauthorized modification that connected a drain line from the base of the raw cooling water (RCW) booster pumps, located in the Auxiliary Bldg. into the drain piping connected to the yard pond. Since this piping goes directly to the yard pond, it creates the potential for an abnormal and unmonitored radiological effluent release path. While this path existed, it is unlikely for a release to occur. The pump skid forms a basin underneath the pump which collects the seal leak-off water. Since the pump is for the RCW system, the leak-off would not be radioactive. The pump skid is 4-1/2 inches high therefore a spill in the area would require a large volume of liquid before creating a condition that would cause the liquid to enter the RCW drain line. The pumps are also not located in a high traffic area and access to the skid basin for spilling or dumping radioactive liqM is limited. With ease of access to numerous floor drains, it is highly unlikely that someone would dump radioactive liquid into the pump basin.

While investigating this modification a condition was identified (SQ960759PER) that may have resulted in a release of a small amount of radioactive liquid through the RCW booster pump basin drain lines. A valve misalignment in the Unit 1 component cooling system (CCS) surge tank resulted in overflowing the tank. The water sprayed the immediate area around the tank including the RCW booster pumps. It is possible that some of this water settled in the pump basins and was drained through the drain lines.

Based on routine analysis of the CCS heat exchangers there is a small amount of radioactivity (approx.1.0E-06 uCi/ml) in the CCS system. An engineering evaluation of this event estimated that 5,050 gal. of water was lost from the surge tank. Assuming a worse case scenario that the complete volume of water was all released to the yard pond, in conjunction with the relative radioactive concentration in the CCS, this would have resulted in a maximum of 19.1 uCi being released. This potential release, unplanned and unmonitored is considered unacceptable, however, it would have no impact on 10CFR20 compliance and/or offsite dose. The drain's pathway has been corrected and now releases to the Auxiliary Bldg. floor and equipment drain collector tank.

25

ML20138F238

Text

Navigation menu

Search