ML20149J272

Effluent & Waste Disposal Rept,Supplemental Info,For Jan- June 1986

ML20149J272
Person / Time
Site:	Sequoyah
Issue date:	06/30/1986
From:	Wallace P TENNESSEE VALLEY AUTHORITY
To:	Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
NUDOCS 8802220336
Download: ML20149J272 (17)

Text

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,y EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION IST HALF 86 i

1.

Regulatory Lirits

a. Fission and Activation Gases:

(1) Instantaneous - Nuclide Dependant (all release points)

Shield Building Auxiliary Building Condensse Vacuum Exhaust Service building NOTE:

Total plant release rate limit per nuclide are established by TVA's Radiological Control, Radiation Protection Branch. These limits are further evaluated to each vent based on design flowrate.

Techr.ical Specification will not be exceeded until the sum of individual isotope release rate per release rate limit exceeds 1.0.

b. & c.

Iodines and particulates, half-lives > 8 days (1)

Instantaneous - Nuclide Dep adant NOTE: Total plant release rate limit pce nuclide are established by TVA's Radiological Centrol Radiation Protection Branch. These limits are further evaluated to each vent. based on design flowrate. Technical Specifications will not be exceeded until the sum of indb%ual isotope release rate per release rate limit exceeds 1.0.

d Liquid effluent:

[ MPC 6 1.0 (reference 10CFR20, Appendix B note 3C, Table II, column 2).

e.

Tritium (1) Liquid - $ 3.0E-3 pCi/ml (ref.10CFR20. Table II, column 2)

(2) Airborne - (reference 10CFR20. Table II, column 1)

Shield Building 5 3.138E+03 pCi/see Auxiliary Building d 2.555E+04 yC1/see Service Building i 1.165E+03 pCi/see Condenser Vacuum Exhaust 1 5.043E+00 pCi/see NOTE:

These limits are established by TVA based on each vents design flowrate. t,J Q e

8902220336 860 W b

l

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PDR ADOCK 05000327 R

PDR i

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION IST HALF 8),

2.

Maximum Permissible Concentrations a.

Fission and Activation Gases: Not Applicable b.

Iodines: Not Applicable c.

Particulates, half-lives > 8 days: Not Applicable d.

Liquid effluents:

sum of inde. MPC ratios 6. 1.0 (ref. 10CFR20, Appendix B, Note 1) 3.

Average Energy - Not Applicable 4.

Measurements and Approximations of Total Radioactivity a.

Fission.t3 activation Gases Airborne effluent gaseous activity is continuously acnitored and recorded. Additional grab samples from the shleid, auxiliary, service and condenser vacuum exhausts are taken and analyzed at i

i least monthly to determine the quantity of noble gas activity released for the month based on the average vent flowcates recorded for the sample period. Also, noble gas samples are collected and evalveted for the shleid and auxiliary buildings following startup, shutdvsn or a rated thermal power change exceeding 151. within one hour. The vent flowrates for the shield auxiliary, service buildings, and condenser vacuum exhaust are determined and recorded once a shift.

The quantity of noble gases released through the shield and auxiliary building due to purging e venting of containment and releases of waste gas decay tents 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 samp1tng periods, the activity rei n sed from purging or venting of cortsininent, and the activity released from waste gas decay tant (s).

NOTE:

Every effort is made to ensure that all effluents from Sequoyah are conducted such that all Technical Specification LLDs are met.

Whenever an analysis does not identify a radioisotope, a "O.00E-01 C'." is recorded for the release. This does not necessarily mean that no activity was released for that particalar radioisotope but I

that the concentration was below the Technical Specification and analysis capability.

Refer to Tables A and B for estimates of these typical values, f - - - - - - - - _ _ -

i

l EFFLUEKT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION 1st RALF 86 4.

Measurements and Approximation of Total Radioactivity (continued)

When an analysis results in a non-Technical Specification radioisotope being identified in one quarter and not the other, a "N/A" is recorded for the quarter in which it was not identified.

These radioisotopes will not be recorded in Tables A and B since they are not Technical Specifications,

b. & c.

Iodines and Particulates Iodine and particulate activity is continuously monitored and recorded.

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 buildings 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% 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 vent flowrates from the shield and auxiliary buildings are recorded once a shift.

The total particulate and iodine activity released for the month is then determined by summing all of the activity released from the shiald and auxiliary buildings for all sampling periods, d.

Liquid Effluents (1) Batch (Radwaste and condensate regenerants to cooling tower blowdown)

Total gamma isetepic activity concentrations are determined on caeh batch of liquid effluent prior to release.

The total curie enntent of a released batch is determined by cumming each nuellde's concentration and multiplying by the l

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.

(2) Cpe.jriuous Releases and Periodie Continuous Reisases l

(Condensate regenerants, turbine building sump and steam l

generator blowdown) f

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION let HALF 86 4.

Measurements and Approximation of Total Radic.tetivity (continued)

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 curie content 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 month.

l 5.

Batch l

Value Units Quarter Quarter 1st 2nd a.

Liquid 1.

Number of batches released (Radwaste only) 72 80 Each 2.

Total time period for batch releases 10428 11698 Minutes 3.

Maximum time period for a batch release 240 209 Minutes 4.

Average time period for batch releases 145 146 Minutes 5.

Minimum stream flow during periods of effluent into a flowing stream:

(a)

(a)

(a) See Radiological Control Section's portion of semi-annual effluent release report.

b.

Gaseous (1) Number of batches released 13 15 Each (2) Total time period for batch releases 796 770 Minutes (3) Maximum time period for a batch release 131 167 Minutes (4) Average time period for batch releases 99 156 Minutes (5)jMinimumtimeperiodforabatchrelease 71 142 Minutes 6.

Abnormal Releases a.

Liquid (1) Number of Releases 0

0 (2) Total Activity Released 0.00E-01 0.00E-01 Cl b.

Gaseous 0

(1) Number of Releases 0

0 (2) Total Activity Released 0.00E-01 0.00E-01 Ci _ _ _ _ _ _ _ _ ____ _______ _ - -

^

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1st HALF 86 LIQUID EFFLUENTS - TOTAL PLANT DISCHARGE Total Total Unit Quarter 1 Error Quarter 1 Error A.

Fission and Activation Products 1st 2nd 1.

Total Releases Curies 3.47E-02 41.0E+01 2.16E-02 11.0+01 2.

Average Diluted Cond. During Period of All Identified Isotopes uCl/mi S.88E-08 1.60E-08 3.

Percent of Applicable Limit 9.31E-02 5.02E-02 (N MPC i 1)

E 21 NOTE:

Percent of applicable limit is based on identified isotope concentration af ter dilution, related to their appropriate MPC concentration and sum of all the isotope fractions compared to 1.0.

B.

Tritium 1.

Total Release Curles 1.36E+02 11.0E+01 3.53E+01 ti.0E+01 2.

Average Diluted Cond. During pCl/ml 1.52E-04 2.61E-05 Period 3.

Percent of Applicable Limit 5.07E+00 8.72E-01 (3.0E-03 pCi/ml)

C.

Dissolved and Entrained Gases 1.

Total Release Curles 7.48E-04

• 1.5E+01 1.34E-03 il.5E+01 2.

Average Diluted Cond. During yCi/mi 8.36E-10 9.93E-10 Period 3.

Percent of Appilcable Limit 1

4.18E-04 4.96E-04 (2.0E-04 pCi/ml)

D.

Gross Alpha Radioactivity 1.

Total Release Curies 0.00E-01 11.5E+01 0.00E-01 11.5E+01 E.

Volume of Vasto Release (Before Dilution)

Liters 4.31E+08 11.0E+01 5.14E+08 11.0E+01 F.

Volume of Dilution Water for Liters 4.64E+08 11.0E+01 8.36E+08 il.0E+01 Period I

~I EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1st HALF 86 LIQUID EFFLUENTS - TOTAL PLANT DISCHARGE G.

Isotope Summary Required by Technical Specifications /Others Continuous Mode Batch Mode Nuclide Unit Quarter Quarter guarter Qu'arter 1st 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 Ci 0.00E-01 0.00E-01 9.37E-03 4.48E-03

4. Manganese-54 Cl 5.29E-06 0.00E-01 1.75E-03 1.00E-03

5. Cobalt-58 Ci 3.22E-06 2.37E-05 4.30E-03 2.00E-03

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

1. Cobalt-60 C1 4.06E-04 1.68E-05 1.09E 01 9.47E-03

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 0.00E 01 0.00E-01

10. Iodine-131 Cl 0.00E-01 0.00E-01 0.00E-01 0.00E-01

11. Cestem-134 Ci 2.13E-05 2.43E-04 9.67E-04 9.18E-04

12. Cesium-137 C1 4.02E-05 7.03E-04 1.99E-03 1.87E-03

13. Cerium-141 Ci 0.00E-01 0.00E-01 3.83E-06 0.00E-01

14. Cerium-144 Cl 0.00E-01 5.13E-04 0.00E-01 0.00E-01 Others (Specify)

15. Chronium-51 Ci N/A N/A 7.46E-05 4.24E-05

16. Niobium-95 C1

,,N/A N/A 5.08E-05 6.75E-06

17. Niobium-97 Ci N/A N/A N/A 7.43E-09

18. Zine-69m Ci N/A N/A 3.36E-06 N/A

19. Te11urita-132m Ci N/A N/A N/A 3.00E-04

20. Ruthenium-103 Cl N/A N/A 3.56E-06 N/A

21. Yttrium-91 Ci N/A N/A 4.74E-03 N/A

22. Technicium-99m Cl N/A N/A 3.05E-06 N/4

23. Ruthenium-106 Cl N/A N/A 9.04E-05' N/A Total for Period C1 4.76E-04 1.50E-03 3.42E-02 2.01E-02 NOTE:

Refer to Table A for values reported as 0.00E-01

~

FFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1pt HALF _86 LIQUID EFFLUENTS - TOTAL PLANT DISCHARGE G.

Isotope Summary Dissolved Gasses Required by Technical Specifications /Others Continuous Mode Batch Mode Nuclide Unit Quarter Quarter Quarter Quarter 1st 2nd 1st 2nd 1.

Krypton-87 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Krypton-88 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Xenon-133 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 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 2.06E-06 0.00E-01 6.

Xenon-138 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Others (Specify) 7.

Krypton-85 Ci N/A N/A 7.46E-04 1.34E-03 Tetal for Period Ci 0.00E-01 0.00E-01 7.48E-04 1.34E-03 NOTE:

Refer to Table A for values reported as 0.00E-01 l

l l

i i

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT IST HALF 86 l

GASEOUS LFFLUENTS-SUMMATION OF ALL RELEASES l

(GROUND LEVEL RELEASES)

Continuous Mode Batch Mode Unit guarter Quarter guarter Quarter 1st 2nd let 2nd E.

Fission Cases Required by Technical Specifications

1. Krypton-87 C1 0.00E 01 0.00E-01 0.00E-01 0.00E-01

2. Krypton-88 C1 0.00R-01 0.00E-01, 0.00E-01 0.00E-01

3. Xenon-133 Ci 0.00E-01 0.00E-01 4.59E-05 1.24E-02

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

5. Xonon-135 Ci 0.00E-01 0.00E-0_1 0.00E-01 0.00E-01

{

6. Xenon-138 Cl 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Others (Specify)

7. Krypton-85 Cl N/A N/A 7.67E-01 4.31E-01

8. Xenon-131m Ci N/A N/A 1.86E-03 N/A Total for Period C1 0.00E-01, 0.00E-01 7.69E-01 4.43E-01 F.

Iodines-Required by Technical Specifications

1. Iodine-131 Cl 0.00E-01 2.69E-08 Others (specify 4

Total for Period Ci 0.00E-01 2.69E-08 NOTE:

Refer to Table B for values reported as 0.00E.01. <

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT IST HALF 86 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES (GkOUND LEVEL RELEASES)

Total Total Summation of All Releases Unit..

Quarter

% Error Quarter

% Error 1st 2nd A.

Fission and Activation Products 1

Total Releases C1 7.69E-01 11.0E+01 4.43E-01 11.0E+01 2.

Average Release Rate for Period pCi/sec 9.89E-02 5.63E-02 3.

Percent of Techical Specification Limit 2.30E-05 1.32E-05 B.

Iodines 1.

Total Iodine-131 Ci 0.00E-01 il.0E+01 2.69E-08 11.0E+01 2.

Average Release Rate for Period uCi/sec 0.00E-01 3.42E-09 3.

Percent of Technical Specification Limit (1.60E-01 uC1/sec) 0.00E-01 2.14E.06 C.

Particulates 1.

Particulates with C1 2.48E-04 11.5E+01 1.15E-03 11.5E+01 half lives 8 days 2.

Average Release pC1/sec 3.19E.05 1.46E-04 Rate for Period 3.

Percent of Techni-cal Spoelfication 1

9.81E-04 5.73E-03 Limit 4.

Gross Alpha Radio-Ci 0.00E-01 il.5E+01 0.00E-01 11.5E+01 activity D.

Tritium 1.

Total Release C1 4.67E+00 il.0E+01 5.98E+00 ti.0E+01 2.

Average Release pC1/sec 6.01E-01 7.61E-01 Rate for Period 3.

Percent of Technical Specification Limit 1

1.82E-03 2.31E-03 3.3E+04 pCi/sec) l 2

i

+

t EFFLUENT AND VASTE DISPOSAL SEMIANNUAL REPORT l

1ST HALF 86 l-GASF"')S EFFLUENTS-SUKMATION OF ALL RELEASES (GROUND LEVEL RELEASES)

G.

Particulates ReqJired by Technical Specifications /Others Nuclide Unit Continuous Mode Quarter Quarter let 2nd 1.

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

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

Manganese-54 Ci 0.00E-01 8.36E-06 4.

Cobalt-58 C1 1.21E-04 4.60E-04 5.

Iron-59 Ci 0.00E-01 0.00E-01 6.

Cobalt-60 C1 1.21E-04 6.31E-04 7.

Zine-65 Ci 0.00E-01 0.00E-01 8.

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

Cesium-134 Ci 0.00E-01 2.17E-05 10.

Cesium-137 Ci 0.00E-01 2.66E-05 i

11.

Cerium-141 Cl 8.56E-07 0.00E-01 12.

Cerium-144 Ci 0.00E-01_

0.00E-01 Others (Specify) 13.

Tellurium-132 Ci 4.35E-06 N/A 14.

Chronium-51 Ci N/A 1.42E-14 15.

Cobalt-57 Ci N/A 3.55E-06 Total for Period C1 2.47E-04 1.15E-03 NOTE:

Eefer to Table B for values reported as 0.00E-01.

4 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

+

let HALF 81 TABLE A LIQUID "IYPICAL LLD" EVALUATION (2) 6t (a)

Nuclide Tech. Spec. LLD 15 min 30 min 1 hr 2 hr 3 hr Fission and Activation Products Manganese-54 5.0E-07 9.73E-09 9.73E-09 9.73E-09 9.73E-09 9.73E-09 Cobalt-58 5.0E-07 1.22E-08 1.22E-08 1.22E-08 1.22E-08 1.22E-08 Iron-59 5.0E-07 1.74E-08 1.74E-08 1.74E-08 1.75E-08 1.75E-08 Cobalt-60 5.0E-07 1.55E-08 1.55E-08 1.55E-08 1.55E-08 1.55E-08 Zinc-65 5.0E-07 1.70E-08 1.70E-08 1.70E-08 1.70E-08 1.70E-08 M:1ybdenum-99 5.0E-07 7.99E-08 8.01E-08 8.06E-08 8.14E-08 8.23E-08 C:stum-134 5.0E-07 1.16E-08 1.16E-08 1.16E-08 1.16E-08 1.16E-08 Cao'.um-137 5.0E-07 1.33E-08 1.33E-08 1.33E-08 1.33E-08 1.33E-08 Cerium-141 5.0E-07 2.08E-08 2.08E-08 2.08E-08 2.08E-08 2.08E-08 C:rium-144 5.0E-07 8.94E-08 8.94E-08 8.94E-08 8.94E-08 8.94E-08 Icdine-131 5.0E-07 9.83E-09 9.84E-09 9.85E-09 9.89E-09 9.93E-09 Dissolved and Entrained Gases Krypton-87 1.0E-05 2.33E-08 2.67E-08 3.50E-08 6.04E-08 1.04E-07 Krypton-88 1.0E-05 3.90E-08 4.14E-08 4.68E-08 5.97E-08 7.62,E-08 Ionon-133 1.0E-05 2.95E-08 2.96E-08 2.96E-08 2.98E-08 3.00E-08 Ionon-133m 1.0E-05 9.91E-08 9.94E-08 1.00E-07 1.01E-07 1.03E-07 Zenon-135 1.0E-05 1.02E-08 1.04E-08 1.08E-08 1.17E-08 1.26E-08 Ienon-138 1.0E-05 6.06E-08 1.26E-07 5.47E-07 1.03E-05

].94E-04 Tritium (8) 1.0E-05 l

Gross Alpha 1.0E-07 Strontium-89( s )

5.0E-08 Strontium-90( 8 )

5.0E-08 Iron-55( 8 )

1.0E-06 l

l NOTES:

(1)

All evaluations are pCi/ml. All analyses are performed to ensure that Technical Specifications are met, in addition to typical LLD values.

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

This time is utilized to verify that Technical Specification LLDs are met.

(3)

All these analyses are requitad to meet Tech. Spec. LLD limits and are individually evaluated to ensure compliance. However, the 2nd Quarter 1986 Sr-89 Radcaste composite and Condemin composite results exceeded Tech. Spec. LLDs by 4.2% and 531 respectively.

Instrumentation malfunctions were incurred during the analysis period and all composite samplos were expended before resolution of the matter.

Due to plant shutdown in August 1985, Sr-89 and Sr-90 has not been detected in releases since the 3rd Quarter 1985.

No strontium activity was expected this quarter (nor was any apparently detected since the specific activity computer calculations resulted in negative Sr-89 quantitles for both Radweste and Condemin I

composites).

The Sr-90 LLDs (and specific activities) were well below the 5E-08pCl/ml limit.

Since the strontium analysis was performed much later than normal,we suspect that the longer decay time used in the LLD calculation may be a major contributor to the Sr-89 discrepancy. l 47 1

o EFFLUENT AND WASTk T.ISPOSAL SEMIANNUAL REPORT ist HALF 86 TABLE B GASEOUS "TYPICAL LLD" EVALUATION (1)

At (8)

Nuclide Tech. Spec. LLD 15 min 30 min 1 hr 2 hr 3 hr N;ble Gas Krypton-87 1.0E-04 3.75E-07 4.30E-07 5.64E-07 9.73E-07 1.68E-06 Krypton-88 1.0E-04 5.86E-07 6.23E-07 7.04C-07 8 98E-07 1.15E-06 N0non-133 1.0E-04 3.87E-07 3.87E-07 3.88E-07 3.90E-07 3.93E-07 Xenon-133M 1.0E-04 1.53E-06 1.53E-06 1.54E-06 1.56E-06 1.59E-06 X:non-135 1.0E-04 1.59E-07 1.62E-07 1.68E-07 1.81E-07 1.96E-07 X:non-138 1.0E-04 9.45E-07 1.97E-06 d.54E-06 1.61E-04 3.02E-01 Particulates Manganese-54 1.0E-10 3.65E-14 3.65E-14 3.65E-14 3.65E-14 3.65E-14 Ctbalt-58 1.0E-10 4.53E-14 4.53E-14 4.54E-14 4.54E-14 4.54E-14 Iron-59 1.0E-10 6.83E-14 6.83E-14 6.84E-14 6.84E-14 6.84E-14 C:balt-60 1.0E-10 6.26E-14 6.26E-14 6.26E-14 6.26E-14 6.26E-14 Zine-65 1.0E-10 6.68E-14 6.68E-14 6.68E-14 6.68E-14 6.68E-14 M21ybdenum-99 1.0E-10 2.95E-13 2.96E-13 2.98E-13 3.01E-13 3.04E-13 C: slum-134 1.0E-10 4.31E-14 4.31E-14 4 3,1E-14 4.31E-14 4.31E-14 3

C: slum-137 1.0E-10 4.87E-14 4.87E-14 4.87E-14 4.87E-14 4.87E-14 C:sium-141 1.0C-10 6.69E-14 6.70E-14 6.70E-14 6.70E-14 6.71E-14 C:rium-144 1.0E-10 2.81E-13 2.81E-13 2.81E-13 2.81E-13 2.81E-13 Icdine-131 1.0E-10 3.61E-14 3.61E-14 3.62E-14 3.63E-14 3.65E-14 Strontium-89 1.0E-11 Strontium-90 1.0E-11 Crcss Alpha 1.0E-11 Charcoal Sample Iodine-131

_1.0E-11 5.02E-14 5.03E-14 5.03E-14 5.05E-14 5.07E-14 1

Tritium 1.0E-06 NOTES:

(2)

All evaluations are in uCi/cc.

All analyses are performed to ensure that Technical Specifications are met in addition to typical LLD values based on a 2 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> sample period.

Alpha and beta emitters are counted to a set time of 20 minutes.

(2) 6t is the time from midpoint of sampling to analysis.

This time is utilized to verify that Technical Specification LLDs are met.

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT let HALF 1986 SOLID WASTE (RADIOACTIVE) SHIPMENTS A.

Solid Waste Shipped Off-Site for Burial or Disposal (not Irradiated Fuel) 6 Month Est. Tol.

1.

Type of Waste Unit Period Error %

a.

Spent resins, filter sludges m8 7.90E+01 11.50E+01 evaporator bottoms, etc.

Cl 1.51E+03

• 1.50E+01 b.

Dry Active Waste, Compressible Waste m8 2.08E+02 11.50E+01 Contaminated equip., etc.

Ci 1.01E+02 11.50E+01 c.

Irradiated Components, m8 None Control Rods, etc.

Ci None N/A d,

Other (describe) m8 None Ci None N/A 2.

Estimate of major nuclide composition (by type of wastel a.

Spent resin, filter sludges, and evaporator bottoms, etc.

(nuclides determined by measurement)

Curies Percent 1.

Manganese-54 7.37E+01 4.87E+00 2.

Cobalt-58 2.23E+02 1.47E+01 3.

Iron-55 (by est.)

3.91E+02 2.58E+01 4.

Cobalt-60 3.63E+02 2.40E+01 5.

Strontium-90 4.622-02 3.05E-03 6.

Niobium-95 2.48E-02 1.64E-03 7.

Cesium-134 1.43E+02 9.45E+00 8.

Cesium-137 1.59E+02 1.05E+01 9.

Other Nuclides 1.60E+02 1.06E+01.

I l

l l

4 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT let HALF 1986 SOLID WASTE (RADI0 ACTIVE) SHIPMENTS 2.

Estimate of Major Nuclide Composition (by typa of waste) (continued) b.

Dry Active Waste, dry compressible waste, contaminated equipment, etc.;

(nuclides determined by estimate)

Curies Percent 1.

Teltium 9.17E-03 9.04E-03 2.

Carbon-14 2.35E-01 2.32E-01 3.

Chromium-51 1.25E+00 1.23E+00 4.

Manganese-54 7.60E-01 7.50E-01 5.

Iron-55 8.27E+01 8.16E+01 6.

Cobalt-58 8.09E+00 7.98E+00 7.

Iron-59 7.34E-01 7.24E-01 8.

Cobalt-60 4.07E+00 4.01E+00 9.

Strontium-90 1.06E-04 1.05E-04 10.

Zirconium-95 8.49E-02 8.37E-02 11.

Niobium-95 2.28E-01 2.25E-01 12.

Cesium-134 1.30E-02 1.28E-02 13.

Cesium-137 2.12E-02 2.09E-02 14.

Other Nuclides 3.16E+00 3.12E+00

c. Irradiated Components N/A N/A

d. Other (describe)

M/A N/A _ _ _ _ _

\\

3 EFFLUFNT AND WASTE DISPOSAL SEMIANNUAL REPORT let HALF 1986 SOLID WASTE (RADI0 ACTIVE) SHIPMENTS 3.

Solid Weste Disposition Number of Shipments Type Quantity Mode of Transportation Destination a)

Resin, filter sludges, evaporator bottoms, etc.

15 LSA Motor Freight

Barnwell, South Carolina Number of Shipments Type Ouantity Mode of Transportation Destination b)

Raw, dry active warte, compressible contaminated equipment, etc.

3 LSA Motor Freight

Richland, Washington 3

LSA Motor Freight

Richland, Washington Number of Shipments Type Quantity Mode of Transportation Destination c)

Irradiated components, control rods, etc.

None N/A N/A N/A Number of Shipments Type Quantit1 Mode of Transportation Destination d) Other (describe)

None N/A N/A N/A 4.

Irradiated Fuel Shipments (Disposition)

Number of Shipments Type Quantity Mode of Transportation Destination None N/A N/A N/A 5.

Solidification of Weste Was solidification performed?

I Yes No.

If yes, solidific ation media:

Cement.

(-,

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT let NALF 1986 SOLID WASTE (RADI0 ACTIVE) SHIPMENTS 6.

Process Control Program (PCP)

PORC reviewed and accepted revisions were made to the PCP on 1/28/86 and 4/29/86. This PCP laplements the solidification vendor's instructions into plant operating instructions.

Changes were made at the direction cf that vendor.

Changes did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes.

7.

Radioactive Weste Treatment Systems No major changes were made to the radioactive waste treatment systems.

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~, c_5 s 7% en s gw' TENNEOSEE VALLEY AUTHORI Y

--'m Sequoyah Nuclear Plant

& m e,/3, Post Office Box 20 3

b7/ {' K (<b Soddy-Daisy,Tege%{Ee 7

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AUG 2 91986 U.

N e ear Regulatory Commission

'j y

Attn:

Dr. J. Nelson Grace J-J -

Regional Administrator c'f 101 Marietta Street, Suite 3100 A _,

,, y Atlanta, Georgia 30303 ye F ""gg

[%_

Dear Sle:

t In accordance with Sequoyah Nuclear Plant Technical Specification 6.9.1.9 for units 1 and 2, we are submitting the enclosed report of the radiosctive discharges released from Sequoyah during the period of January 1, 1986 through June 30, 1986.

We are also submitting the most recent changes to the ODCM as specified in Tschnical Specification 6.14.2.1.

These changes had been originally submitted in the Sequoyah Nuclear Plant Monthly Operating Report-June 1986.

Very truly yours.

TENNESSEE VALLEY AUTHORITY OR.W P. R. Wallace Plant Manager QiHM I

An Equal Opportunity Employer