ML20207T619

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Effluent & Waste Disposal Semiannual Rept,Supplemental Info Second Half 1986
ML20207T619
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 12/31/1986
From:
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20207T611 List:
References
NUDOCS 8703240184
Download: ML20207T619 (16)
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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION 2ND HALF Rt

1. Regulatory Limits
a. Fission and Activation Garest (1) Instantaneous - Nuclide Dependant (all release points)

Shield Building Auxiliary Butiding condenser vacuum Exhaust Service Building Ngig Total plant release rate limit per nuclide are established by TVA's l Radiological Control, Radiation Ptotection Branch. These limits are further evaluated to each vent based on des 19ai flowrate. Technical 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 Dependant HOTE: 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. Technical specifications will not be exceeded until the sum of l

individual isotope release rate per release rate limit exceeds 1.0.

d. Liquid effluent: I MPC 61.0 (reference 10CFN20, Appendix B, note 3C, l

Table II, column 2).

l l e. Tritium (1) Liquid - 1 3.0E-3 pCL/ml (ref. 10CFN20, Table II, column 2)

(2) Airborne - (reference 10CFN20, Table II, column 1)

Dhield Building 6 3.138E*03 pC1/sec Auxiliary Building 6 2.555E+04 pC1/sec service Building 6 1.165K403 pC1/sec Condenser Vacuum Exhaust 15.043K400 pC1/sec HQIH: These limits are establinhed by TVA based on each vents design flowrote.

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BFFLUENT AND WASTE DISPOSAL SWIIANNUAL REPORT SUPPLWMNTAL INFORMATION M HALF jf,

2. Maximum Permissible concentrations l a. Fission and Activation Gasest Not Applicable
b. Iodinest Not Applicable
c. particulates, half-lives > 8 days! Not Applicable
d. Liquid effluents: sum of indv. MPC ratios 6 1.0 (ref. 10CFR20, Appendix B, Note 1)
3. Average Energy - Not Applicable
4. Measurements and Approximations of Total Radioactivity
a. Einpion and Activation Gases Airborne affluent gaseous activity is continuously monitored and re:orded. Additional grab samples from the shield, auxiliary, service and condenser vacuum exhausts are taken and analyzed at I 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 a rated thermal power change exceeding 1% within one hour. The vent flowrates for the shield auxiliary, service buildin;s, 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 or ventir.1 of contairveent and releases of waste gas decay tanks are also determined.

The total noble gas activity released for the month is then determined by numsing all of the activity released from each vent for all sampling periods, the activity released from purging or venting of containment, and the activity released from waste gas decay tank (u).

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 "0.00X-01 ci" is recorded for the release. This does not necennarily mean that no activity was released for that particular radioisotope but that the concentration was below the Technical specification and analysis capability. Refer to Tables A and B for estimates of these typical values.

EFFLUENT AND WASTR DISPOSAL SEMIANNUAL REPORT GUPPLEMENTAL INFORMATION 2ND ltALF R$

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 flowrotes 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 shield and auxiliary buildings for all sampling periods.

d. Liquid Effluents (1) llatch (Hadwaste and condensate regenerants to cooling tower blowdown)

Total gamma isotopic activity concentrations are determined on each batch of liquid offluent prior to release. The total curio content 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 in then determined by summing the activity content of each batch discharged during the month.

(2) pontinuousJelletasas and periodic Continuous Relennet!!

(condensate regenerants, turbine building sump and steam generator blowdown) r-EFFLUENT AND WASTE DISPOSAL SEMIANNUAL NEPORT SUPPLEMENTAL INFORMATION 2 R HALF 71

4. t =urements and Approxi= tion of Total Radioactivity (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.

5. Batch Value Units Quarter Quartet 3rd 4th
a. Liquid
1. Number of batches released (Nadweste only) 119 111 Rach
2. Total time period for batch releases 17597 16339 Minutes
3. Maximum time period for a batch release 207 240 Minutes
4. Average time period for batch releases 147 147 Minutes
5. Minimum stream flow during periods of effluent into a flowing streams (a) (a)

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

b. Caseous (1) Number of batches released 5 0 Bach (2) Total time period for batch releases 250 0 Minutes (3) Maximum time period for a batch release 60 0 Minutes (4) Average time period for batch releases 50 0 Minutes (5) Minimum time period for a batch release 35 0 Minutes
6. Abimrmal Releases
a. Liquid 0 0 (1) Number of Releases (2) Total Activity Heleased 0.005-01 1.77E-06 Ci
b. Caseous (1) Number of Releases 0 0 (2) Total Activity Heleased 0.00E-01 0.00E-01 C1

i EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT I l

3E2 HALF H LIQUID EFFLUENTS - TOTAL PLANT DISCHARGE j Total Total M Quarter  % Error Quarter  % Error A. Fission and Activation Products 3rd 4th

1. Total Releases Curies 6.10E-02 11.0E+01 4.75E-02 11.0+01 ,
2. Avera9e Diluted Cond. During l Perlod of All Identifled l Isotopes pCi/mi 4.16E-08 3.695-08
3. Percent of Applicable Limit  % 1.475-01 1.30E-01 1 (NIWC 1) 21 gggt Percent of applicable limit is based on identified isotope concentration '

af ter dilution, related to their appropriate IeC concentration and sum of of all the isotope fractions compared to 1.0. the isotope fractions compared to 1.0.

B. Tritte

1. Total Release Curies 3.43E-01 11.0E+01 4.03E-01 11.0E+01
2. Average Diluted Cond. During pci/ml 2.345-05 3.135-05 (

Perlod

3. Percent of Applicable Limit  % 7.795+01 1.04E+00 l (3.0E-03 pC1/ml) j 1

C. Dissolved and Entrained cases

1. Total Release Curies 5.00E-05 11.$E+01 2.29E-03 11.5E+01 [
2. Average Diluted cond. During pci/ml 3.41E-11 1.785-09  !

Period

3. Percent of Applicable Limit  % 1.705-05 8.89E-04 I (2.0E-04 pC1/ml)

D. Gross Alpha Radioactivity

1. Total Release Curies 0.005-01 11.5E+01 0.00E-01 11.5E+01 E. Volume of Weste Release (Before Dilution) Liters 4.91E+08 11.0E+01 2.48E+08 11.0E+01 Liters F. Volume of Dilution Water for 9.76E+08 11.0Et01 1.04E+09 11.0Et01 Perlod t

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EFFLUENT AND WASTE DISPOGAL SEM1 ANNUAL REPORT 2ND HALF 86 LIQUID EFFLUENTS - TOTAL PLANT DIGCimRGE

0. Isotope nimunary Required by Technical Specifications /Others continuous Mode Batch Mode Nuclide Unit Ouarter Quarter Quarter Quarter 3rd 4th 3rd 4th
1. Strontium-89 C1 0.00E-01 0.00E-ql 0.00E-01 0.00E-01
2. Strontium-90 Ci 0.00E-01 0.00E-01 9 00E-01 9 00E-01
3. Iron-55 Ci 0.00E-01 0.00E-01 8.80E-03 5.175-03
4. Man 9anese-54 Ci 0.00E-01 0.00E-01 3.858-03 8.08K-04
5. Cobalt-58 Ci 0.00E-0( 0.00E-01 1.52E-03 1.83E-03
6. Iron-59 Ci 0.00E-01 g200E-01 0.00E-01 0.00E-01
7. Cobalt-60 Ci 0.09E-01 1.778-06 3.195-02 3.12E-02
8. Zinc-65 Ci 0.00E-01 0.00E-01 4.09E-05 0.005-01
9. Molybdenum-99 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01
10. Iodine-131 Ci 0.00E-01 0.00E-01 9 00E-01 0.00E-01
11. Cesium-134 Ci 0.00E-01 7.10E-04 4.69E-03 2.30E-03
12. Cesium-137 Ci 0.00E-01 1.028-03 1.01E-02 1 21E-03
13. Cerium-141 Ci 0.00E-01 0.00E-01 0.80E-01 0.00E-01
14. Cerium-144 Ci 0.00E-01 0.00E-01 0.00E_g1 0.006-01 others (Specify)
15. Niobium-97 Ci N/A N/A 1.13E-06 2.,92E-05
16. Zinc-69m Cl N/A N/A 5.55E-06 N/A
17. Cobalt-57 Ci N/A N/A N/A 1,838-05
18. Rubidium-86 Ci N/A__, __N/A 8.33E-05 8.40E-05
19. Technicium-99m Ci N/A _ N/A 9.13E-07 _N/A
20. Ruthenium-106 Ci N/A N/A __N/A 2 75E 05 Total for Period Ci 0.00E-01 1.738-03 6.10E-02 1 58E-02 NOTE: Refer to Table A for values reported as 0.00E-01 EFFLUENT AND WACTE DISPOSAL SEMIANNUAL REP 00tT 2ME HPLF ,,H LIQUID EFFLUENTS - TOTAL PLANT DISCHANGE O. Isotope Summary Dissolved Casses Nequired by Technical Specifications /Others t continuous Mode Batch Mode Nuclide Unit Quarter gyarter Quarter Quarter 3rd- idL 3rd 4th
1. Krypton-87 Ci 0.00E-01 0,005-01 0.005-01 0.00E-01 i
2. Krypton-88 Ci 0.005-01 h00K-QL 0.00E-01 0.00E-01
3. Xenon-133 Ci 0.00E-01 0 2 005-01 7.67K-06 0.005-01
4. Xenon-133m Ci R.005-01 0 005_01 4.23E-05 3 97E-05 f
5. Xenon-135 C1 0.005-01 0.005-01 0.005-01 0.005-01 l
6. Xenon-138 Ci 0.005-01 0.005-01 0.00E-01 0.005-01 i Others (specify)
7. Krypton-85 Ci N/A N/A - __N/A 2.11E-03
8. Xenon-131m Ci 0.005-01 0.00E-01 N/A 1.515-04 Total for Period Ci 0.005-01 0.00E-01 5.00E-05 2.295-03 NOTEI Hefer to Table A for values reported as 0.005-01 l

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NFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 3ME HALF Ri i

GASWOUS BFFLURNTS-SUPMATION OF ALL RELEASES l (ONOUND LEVEL RELEASES)

Total Total Summatton of All Releases UDil Querter  % Error WRtet  % Error 3rd 4th A. Fission and Activation Products

1. Total Releases Ci 0.00K-01 11.0K+01 0.00E-01 11.0E+01
2. Average Release Rate for Period pC1/sec 0.00E-01 0.00K-01
3. Percent of Techical Specification Limit  % 0.00K-01 0.00E-01
8. lodines  ;

l

1. Total Iodine-131 Ci 0.00E-01 11.0K601 0.00E-01 11.0E+01 l
2. Average Release Mate for Period pC1/sec 0.00K-01 0.00K-01
3. Percent of Technical Specification Limit (1.60E-01 pct /sec)  % 0.00E-01 0.00K.01 C. Particulates
1. Particulates with C1 1.06E-04 11.5E601 6.02K-05 11.5K+01 half-lives 8 days
2. Average Release pC1/sec 1.335.05 3.57K-06 Nate for Period
3. Percent of Techni-cal Specification  % 7.84K-04 4.06K-04 Limit
4. Gross Alpha Radio- Ci 0.00R-01 11.5M601 0.005-01 11.5Nt01 activity D. Tritium
1. Total Release C1 1.13Mt01 11.0M601 6.16kt00 11.0Nt01
2. Average Nelease pC1/sec 1.428600 7.75K-01 Nate for Period
3. Percent of Technical Specification Limit  % 4.31H-03 2.35K-03 3.3t+04 pC1/nec)

BFFLUENT AND WASTE DISPOSAL SEMIfJINUAL REPORT 2ME HALF ji j GASROUS EFFLUENTS-SUf9tATION OF ALL RELEASES

! (OROUND LEVEL RELEASES)

Continuous Mode letch Molt, -

Unit Quarter gperter Querter Querter 3rd 4th 3rd 4th E. Eission Gases Required by Technical Specifications

1. Krypton-87 CL 0.00E-01 0.00E-01 0.00E-01 R.005-01
2. Krypton-88 Ci 0.005-01 0.00E-01 0.00E-01 0.005-01
3. Xenon-133 C1 0.005-01 0.005-01 hQ05-01 0.00E-01
4. Xenon-133m CL 0.00E-01 0.00E-01 0.00E-01 0.00E-01  ;
5. Xenon-135 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01
6. Xenon-138 Ci 0.00E-01 0.00E-01 0.00E-01 R.00E-01 Total for Period C1 0.00E-01 0.00E-01 0.005-01 0.005-01 F. Iodines Nequired by Technical Specifications
1. Iodine-131 Ci 9dqs-ql 0.005-0J others (specify I

Total for period Ci 9,QgK-91 0.005-01 NOTEI Nefer to Table B for values reported as 0.00E-01.

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RFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 2!!E HALF ((

GASBOUS EFFLUENTS-SUlWIATION OF ALL RELEASES (GROUND LEVEL RELEASES)

G. Particulates Required by Technical Specifications /Others Nuclide Unit continuous Mode Quarter Quarter l 3rd 4th

1. Strontium-89 Ci 0.005-01 0.005-01
2. Strontium-90 C1 0.00E-01 0.005-01
3. Manganese-54 Ci 929qt-El 0.005-01 l
4. cobalt-58 C1 0.00E-01 0.005-01
5. Iron-59 Ci 0.00E-01 Q.00E-01
6. Cobalt-60 C1 1.065-04 1,048-05  ;

1

7. Einc-65 Ci 0.00E-01 0.00E-01 1
8. Molybdenum-99 CL 0.00E-01 0.00E-01 l
9. Cesium-134 Ci 0.00E-ql 0.00E-01
10. Cesium-137 Ci 0.00E-01 1.58E-06
11. Cerium-141 CL 0.005-01 4.33E-08
12. Cerium-144 CL 2299E-01 0.005-01 Others (specify)
13. Cobalt-57 CL N/A - 1.475-07 Total for period CL 1.065-04 6.02M-05 NOTut Nefer to Table B for values reported au 0.00E-01.

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 2ND HALF 86 TABLE A LIQUID " TYPICAL LLD" EVALUATION (#)

At (#) l l

Nuclide Tech. Spec. LLD 15 min 30 min I 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 Molybdenum-99 5.0E-07 7.99E-08 8.01E-08 8.06E-08 8.14E-08 8.23E-08 Cesium-134 5.0E,01 1.16E-08 1.16E-08 1.16E-08 1.16E-08 1.16E-08 Cesium-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 Cerium-144 5.0E-07 8.94E-08 8.94E-08 8.94E-08 8.94E-08 8.94E-08 Iodine-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 7.62E-08 Xenon-133 1.0E-05 2.95E-08 2.96E-08 2.96E-08 2.98E-08 3.00E-08 Xenon-133m 1.0E-05 9.91E-08 9.91E-08 1.00E-07 1.01E-07 1.03E-07 Xenon-135 1.0E-05 1.02E-08 1.04E-08 1.088-08 1.17E-08 1.26E-08 Xenon-138 1.0E-05 6.06E-08 1.26E-07 5.47E-07 1.03E-05 1.94E-04 Tritium (*) 1.0E-05 Gross Alpha 1.0E-07 Strontium-89(*) 5.0E-08 Strontium-90(*) 5.0E-08 Iron-55(*) 1.0E-06 NOTES:

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

l (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 required to meet Tech. Spec. LLD limits and are individually evaluated to ensure compliance.

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 2ND HALF 86 TABLE B GASBOUS " TYPICAL LLD" EVALUATIONO)

At (')

Nuclide Tech. Spec. LLD 15 min 30 min I hr 2 hr 3 hr Noble Gas Krypton-87 1.0E-04 3.758-07 4.308-07 5.648-07 9.73E-07 1.68E-06 Krypton-88 1.08-04 5.868-07 6.238-07 7.048-07 8.98E-07 1.15E-06 Xenon-133 1.0E-04 3.87E-07 3.87E-07 3.888-07 3.90E-07 3.93E-07 Xenon-133M 1.0E-04 1.53E-06 1.538-06 1.54E-06 1.55E-06 1.59E-06 Xenon-135 1.0E-04 1.59E-07 1.62E-07 1.68E-07 1.818-07 1.96E-07 Xenon-138 1.0E-04 9.45E-07 1.978-06 8,54E-06 1.61E-04 3.028-03 Particulates Manganese-54 1.0E-10 3.65E-14 3.65E-14 3.65E-14 3.65E-14 3.65E-14 Cobalt-58 1.0E-10 4.53E-14 4.53E-14 4.545-14 4.548-14 4.548-14 Iron-59 1.0E-10 6.838-14 6.83E-14 6.84E-14 6.64E-14 6.84E-14 Cobalt-60 1.0E-10 6.26E-14 6.26E-14 6.26E-14 6.26E-14 6.26E-14 Zinc-65 1.0E-10 6.688-14 6.688-14 6.68E-14 6.68E-14 6.688-14 Molybdenum-99 1.0E-10 2.95E-13 2.968-13 2.98E-13 3.01E-13 3.04E-13 Cesium-134 1.0E-10 4.31E-14 4.31E-14 4.31E-14 4.318-14 4.31E-14 l Cesium-137 1.08-10 4.87E-14 4.87E-14 4.87E-14 4.87E-14 4.87E-14 6.71E-14 Cesita-141 1.0E-10 6.698-14 6.70E-14 6.70E-14 6.70E-14 Cerium-144 1.0E-10 2.81E-13 2.81E-13 2.818-13 2.81E-13 2.81E-13 l

Iodine-131 1.0E-10 3.61E-14 3.61E-14 3.63E-14 3.63E-14 3.65E-14 Strontium-893 1.0E-11

! Strontium-90s 1.08-11 l

Gross Alpha 1.0E-ll Charcoal sample l Iodine-131 1.08-11 5.02E-14 5.038-14 5.03E-14 5.05E-14 5.07E-14 l

L Tritium

  • 1.0E-06 NOTES: (2) All evaluations are in pCi/cc. All analyses are performed to ensure that Technical Specifications are met in addition to typical LLD values based on a 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) At is the time from midpoint of sampling to analysis.

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

(3) All these analyses are required to cieet Technical Specification LLD limits and are individually evaluated to ensure compliance.

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 2ND HALF 1986 SOLID WASTE (RADIOACTIVE) SHIPMENTS 1-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 m' 1.68E+01 11.50E+01 evaporator bottoms, etc. C1 4.50E+02 11.50E+01
b. Dry Active Waste, Compressible ,

Waste m 1.20E+02 11.50E+01 Contaminated equip., etc. Ci 5.40E+01 11.50E+01

c. Irradiated Components, m' 3.26E+00 il.50E+01 Control Rods, etc. Ci 1.12E+04 11.50E+01
d. Other (describe) m None Ci None N/A s
2. Estimate of major nuclide composition (by type of waste)
a. Spent resin, filter sludges, and evaporator bottoms, etc.

(nuclides determined by measurement)

Curies Percent

1. Tritium 2.20E+02 4.89E+01
2. Carbon-14 3.79E-01 8.42E-02 1 3. Iron-55 1.91E+02 4.24E+01
4. Cobalt-58 8.68E-01 1.938-01
5. Cobalt-60 2.05E+01 4.56E+00
6. Nickel-63 1.47E+01 3.27E+00
7. Strontium-90 1.38E-02 3.07E-03
8. Technetium-99 5.91E-04 1.31E-04
9. Iodine-129 2.06E-05 4.58E-06
10. Cesium-134 8.73E-01 1.94E-01
11. Cesium-137 1.62E+00 3.60E-01

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 2ND HALF 1986 SOLID WASTE (RADIOACTIVE) SHIPMENTS-

2. Estimate of Major Nuclide Composition (by type of Waste) (Continued)
b. Dry Active Waste, dry compressible waste, contaminated equipment, etc,;

(nuclides determined by estimate)

Curies Percent

1. Tritium 4.98E-03 9.22E-03
2. Carbon-14 1.28E-01 2.37E-01
3. Chromium-51 6.81E+01 1.26E+00
4. Iron-55 4.50E+01 8.33E+01
5. Cobalt-58 4.40E+00 8.15E+00
6. Cobalt-60 2.21E+00 4.09E+00
7. Nickel-63 1.51E+00 2.80E+00
8. Technetium-99 1.50E-04 2.78E-04
9. Iodine-129 3.85E-05 7.128-05
c. Irradiated Components
1. Tritium 1.57E+04 1.40E-01
2. Carbon-14 2.59E+02 2.31E-03
3. Maganese-54 1.45E+06 1.29E+01
4. Iron-55 6.82E+06 6.09E+01
5. Cobalt-58 1.25E+04 1.12E-01
6. Nickel-59 2.41E+03 2.15E-02
7. Cobalt-60 2.48E+06 2.21E+01
8. Nickel-63 2.84E+05 2.54E+00
9. Niobium-94 3.97E+00 3.54E-05
10. Silver-110m 5.47E+04 4.88E-01
11. Antimony-125 3.54E+04 3.16E-01
d. Other (describe)

N/A

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 2ND HALF 1986 SOLID WASTE (RADIOACTIVE) SHIPMENTS

3. Solid Waste Disposition Number of Shipments Type Ouantity Mode of Transportation Destination a) Resin, filter sludges, evaoorator bottoms, etc.

4 LSA Motor Freight Barnwell, ..

South Carolina Number of Shipments Type Ouantity Mode of Transportation Destination b) Raw, dry active waste, compressible contaminated equipment, etc.

4 LSA Motor Freight Barnwell, S. C.

Number of Shipments Type Ouantity Mode of Transportation Destination c) Irradiated components, control rods, etc.

2 B Motor Freight Barnwell, S. C.

Number of Shipments Type Ouantity Mode of Transportation Destination d) Other (describe)

None N/A N/A N/A

4. Irradiated Fuel Shipments (Disposition)

Number of Shipments Type Ouantity Mode of Transportation Destination None N/A N/A N/A

5. Solidification of Waste Was solidification performed? X Yes No.

If yes, solidification media: Cement

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 2ND HALF 1986 SOLID WASTE (RADIOACTIVE) SHIPMENTS

6. Process Control Program (PCP)

PORC reviewed and accepted revisions were made to the PCP on 7/23/86 and 12/12/86. This PCP implements the solidification vendor's instructions into plant operating instructions. Changes were made at the direction of that vendor. Changes did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes.

7. Radioactive Waste Treatment Systems i

No major changes were made to the radioactive waste treatment systems during the 2nd half of 1986.

Attached are two safety evaluations, approved by PORC on 2/6/87, for previously made major changes to the radioactive waste treatment system. These changes are the use of a mobile demineralizer system and the use of the condensate demineralizer waste evaporator for routine processing of liquie radwaste. The need for the evgaluation was identified by NRC violations:

50-327/86-28-01 and 50-328/86-28-01.

0321E

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