Text

Effluent & Waste Disposal Semiannual Rept,Supplemental Info,First Half 1987. Changes to Offsite Dose Calculation Manual Encl
	ML20238F719
Person / Time
Site:	Sequoyah
Issue date:	06/30/1987
From:	; TENNESSEE VALLEY AUTHORITY
To:	;
Shared Package
ML20238F702	List: ML20238F700; ML20238F719;
References
	NUDOCS 8709160302
	Download: ML20238F719 (26)
	v • d • e

- - _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

4 '

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION I

1ST HALF 1981 l

1.

Regulatory Limits

a. Fission and Activation Gases:

(1) Instantaneous - Nuclide Dependant (all release points) k Shield Building Auxiliary Building Condenser 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.

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 particulate, half-lives >8 Days (1)

Instantaneous - Nuclide Dependant 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. Technical Specifications will not be exceeded until the sum of individual isotope release rate per release rate limit exceeds 1.0.

d.

Liquid effluent: I MPCs1.0 (reference 10CFR20, Appendix B, note 3C, Table II, column 2).

e.

Tritium (1)

Liquid - 53.0E-3 pCi/ml (ref.10CFR20, Table II, column 2)

^

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

Shield Building 53.138E+03 pCi/sec Auxiliary Building 62.555E+04 pCi/sec Service Building sl.165E+03 pCi/sec Condenser Vacuum Exhaust 55.043E+00 pCi/sec NOTE:

These limits are established by TVA based on each vent's design flowrate.

R 9709160302 070829

~~

PDR ADOCK 05000327 R

PDR

e EFFLUENT AND WAS1E DISPOSAL SEM1 ANNUAL REPORT SUPPLEMENTAL INFORMATION 1ST HALF 1987 2.

Maximum Permissible Concentrations a'.

Fission and Activation Gases:

Not Applicable b.

Iodines: Not Applicable c.

Particulate, half-lives >8 days:

Not Applicable d.

Liquid effluents:

sum of indv. MPC ratios s1.0 (ref.10CFR20, Appendix B, Note 1) 3, Average Energy - Not Applicable 4.

Measurements and Approximations of Total Radioactivity l

a.

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

Additional grab samples from the shield, auxiliary, service and condenser vacuum exhausts are taken and analyzed at least monthiy 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 15% within one hour. The vent flowrates for the shield auxiliary, service buildings, and condenser vacuum exhaust are determined and recorded I

once a shift.

The quantity of noble gases released through the shield and auxiliary building 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, the activity released from purging or venting of containment, and the activity released from waste gas decay tank (s).

NOTE:

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

I Whenever an analysis does not identify a radioisotope, a "0.00E-01 1

Ci" is recorded for the release. This does not necessarily mean that no activity was released for that particular radioisotope but that the concentration was below the Technical Specification and i

analysis capability.

Refer to Tables A and B for estimates of these typical values. I

i EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION q

1ST HALF 1987 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 Particulate 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 q

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 samoling 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 shield and auxiliary buildings for all sampling periods.

d.

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

Total gamma isotopic activity concentrations are determined on each batch of liquid effluent prior to' release. The total curie 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 is then determined by summing the activity content of each batch discharged during the month.

l-(2)

Continuous Releases and Periodic Continuous Releases l

(Condensate regenerants, turbine building sump and steam generator blowdown)

I _ _ _ - _ _ _ _

-4 i

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION 1ST HALF 1987 1

4.

Measurements and Approximation 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 Quarter 1st 2nd__

a.

Liquid 1.

Number of batches released (Radwaste only) 56 74 Each 2.

Total time period for batch releases 8310 10331 Minutes 3.

Maximum time period for a batch release 214 188 Minutes-4.

Average time period for batch releases 149 140 Minutes 5.

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

(a)

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

b.

Gaseous (1)-Number of batches released 0

0 Each (2) Total time period for batch releases 0

0 Minutes (3) Maximum time period for a batch release NA NA Minutes (4) Average time period for batch releases NA NA Minutes (5) Minimum time period for a batch release NA NA Minutes 6.

Abnormal Releases a.

Liquid j

Q (1) Number of Releases 0

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

Gaseous (1) Number of Releases 0

0 (2) Total Activity Released 0.00E-01 0.00E-01 Ci j

r;- -

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT IST HALF 1987 LIQUID EFFLUENTS - TOTAL PLANT DISCHARGE Total Total Unit Quarter

% Error Quarter

% Error A.

Fission and Activation Products 1st 2nd i

1.

Total Releases Curies 1.20E-02 1.0E+01 8.30E-02 11.0+01 2.

Average Diluted Conc. During 1.29E-08 7.48E-08 Period of All Identified Isotopes pCi/ml 3.

Percent of Applicable Limit 4.37E-02 2.06E-01 (N MPC 1) 1 NOTE:

Percent of applicable limit is based on identified isotope concentration I

after dilution, related to their appropriate MPC concentration and sum of of all the isotope fractions compared to 1.0.

the isotope fractions compared to 1.0.

B.

Tritium 1.

Total Release Curies 2.06E+01 16.0E+00 2.80E+01 16.0E+00 2.

Average Diluted Conc. During pCi/ml 2.21E-05 2.52E-05 Period 3.

Percent of Applicable Limit 7.36E-01 8.40E-01 (3.0E-03 pCi/ml)

C.

Dissolved and Entrained Gases 1.

Total Release Curies 0.00E-01 il.5E+01 0.00E-01 11.5E+01 2.

Average Diluted Conc. During pCi/ml 0.00E-01 0.00E-01 Period 3.

Percent of Applicable Limit 0.00E-01 0.00E-01 (2.0E-04 pCi/ml)

D.

Gross Alpha Radioactivity 1.

Total Release Curtes 0.00E-01 11.5E+01 0.00E-01 il.SE+01 E.

Volume of Waste Release i

1 (Before Dilution)

Liters 3.39E+08 il.0E+01 3.18E+08 11. 0 E + 01 F.

Volume of Dilution Water for Liters 5.94E+08 il.0E+01 7.92E+08 1.0E+01 Period l - _ - _ - -

f EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT l

H 1ST HALF;1987 l

LIQUID EFFLUENTS - TOTAL PLANT DISCHARGE G.

Isotope Summary

. Required by Technical Specifications /0thers i

i Continuous Mode Batch Mode Nuclide Unit Quarter Quarter Quarter.

Quarter 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 '

3.' Iron-55 Ci 7.54E-04 0.00E-01 3.21E-03 1.60E-02 l

4. Manganese-54 Ci 2.05E-05 0.00E-01 8.08E-05 7.95E-04

5. Cobalt-58 Ci

.0.00E-01 0.00E-01 0.00E-01 4.67E-04

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

7. Cobalt-60 Ci 1.87E-03 3.70E-06 3.09E-03

6. 21 E-02

8. Zinc-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-Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01

11. Cesium-134 Ci 1.45E-03 0.00E-01 5.02E-06 1.40E-04

12. Cesium-137 Ci 1.39E-03 4.14E-05 1.06E-04 3.41E-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 0.00E-01 Others (Specify)

15. Cobalt-57 Ci N/A N/A 1.83E-06 6.71E-05

16. Technetium-99m Ci

. N/A N/A 9.07E-07 N/A i

Total for Period Ci 5.48E-03

4. 51 E-05 6.49E-03 8.30E-02 NOTE:

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

i

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EFFt.UENT AND WASTE DISPOSAL SEMIANNVAL REPORT 1ST HALF 1987 LIQU2D EFFLUENTS - TOTAL PLANT DISCHARGE G.

Isotope Sumary Dissolved Gasses Required by Technical Specifications /Others Continuous Mode Batch Made Nuclide Unit qu3r,te_r Quarter Quarter Quarter 1st 2nd 1st 2nd

' l 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 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 0.00E-01 0.00E-01 6.

Xenon-138 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 il Total for Period Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-Of NOTE:

RefertoTableAforvaluesreportedas0.0{E-01.

a q

L i

i W

3

,g l

s EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1ST HALF 1987 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES (GROUND LEVEL RELEASES)

Suramationfk).f All Releases Total Total Unit Quarter

% Error Quarter

% Error 3

1st 2nd A.

Noble Gases 1.

Total Releases Ci 0.00E-01

11. l E + 01 0.00E-01 tl.lE+01 2.

Average Release Rate for Period pCi/sec 0.00E-01 0.00E-01 3.

Percent of Techict.1 Specification Limit 0.00E-01 0.00E-01 B.

Iodines 1.

Tota i lodine-131 Ci 0.00E-01 il.3E+01 0.00E-01 1.3E+01 i'

2.

Average Release O

Rate for Period pCi/sec 0.00E-01 0.00E-01 a

3.

Percent of Technical Specification Limit

/E q?

(1.60E-01 pCi/sec) 0.00E-01 0.00E.01 C.c Particulate i

1.

Particulate with Ci 1.16E-04

11. 6E +01 8.69E-05 il.6E+01 half-lives

>8 days 2.

Average Release pCi/sec 1.49E-05 1.11E-05 Rate for Period 3.

Percent of fechni-cal Specification.

8.76E-04 5.llE-03 o

p Limit 4.

Gross Alph3'Radt0-Ci 0.00E-01 0.00E-01 i2. l E + 01 activity

)

0. <]ritiun.

1.

Total Release Ci 1.59E+00 1.5E+01 3.65E+00 il.5E+01 1

2.

Average Release pCi/sec 2.04E-01 4.64E-01 Rate for Period 3.

Percent of Technical Specification Limit 6.19E-04 1.41E-03 3.3E+04 pCi/sec) p 41

i EFFLUENT AND WASTE DISPOSAL-SEMIANNUAL REPORT 1ST HALF 1987 l

GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES (GROUND LEVEL RELEASES)

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

Fission Gases Required by Technical Specifications

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 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 0.00E-01 0.00E-01 0.0GE-01 6, Xenon-130 Ci 0.00E-01 0.,00E-01 0.00E-01 0.00E-01 Total for Period Ci 0 90E-01 0.00E-01 0.00E-01 0.00E-01 3

F.

Iodines Required by Technical Specifications

1. Iodine-131 Ci 0.00E-01 0.00E-01 Others (specify Total for Period Ci 0.00E-01 0.00E-01 NOTE:

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

f i

, l l

l EFFLUENT AND WA31E DISPOSAL SEMIANNUAL REPORT 1ST HALF 1987 GASEOUS EFFLUENTS-SUMMATION l.:

ALL RE! EASES j

(GROUND LEVEL RELEASLS) j f

u ii.

Particulate e

t i

Required by Teclinical Specifications /Others

~

' ! 'l '

Nuclide Unit

'i Continuous Mode ge s.te r.

Quarter r

1st 2nd 1.

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

Strontium-90 Ci 0.00E-01 0.00E-01 1

3.

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

Cobalt-58 Ci 0.00E-01 0.00E-01 t

5.

Iron-59 Ci 0.00E-01 0.00E-01 I

6.

Cobalt-60 Ci 1.16E-04 8.69E-05 f

-7.

Zinc-65 Ci 0.00E-01 0.00E-Or P*

8.

Molybdenum-99 Ci 0.00E-01 0.00E 4 i

9.

Cesium-134 Ci 0.00E-01 0.00E-01

/

l 10.

Cesium-137 Ci 0.00E-01 0.00E-Oi I

11.

Cerium-141 Ci 0.00E-01 0.00E-01 12.

Cerium-144 Ci 0.00E-01 0.00E-01 Othert :specify)

Total for Period Ci 1.16E-04 8.69E-05 NOTE: Refer to Table B for values reported as 0.00E-01.

.. m________

J

NOTE:

Instrumentation for measuring flow through unit 1 shield b

building exhaust has b2en inoperable since May 7, 1987. The 1

reason for the delay in returning this instrumentation to

]

operability has been the necessity of having to order a replacement for a defective part.

During this period of inoperability, flows through this exhaust have been estimated i

based on design flows for the exhaust fans.

I

-10a-

EFFLUENT'AND WASTE DISPOSAL' SEMIANNUAL REPORT 1ST HALF 1987 TABLE A LIQUID " TYPICAL LLD" EVALUATION (*)

~

6t (*)

Nuclide Tech Spec. LLD 15 min 30 min 1 hr 2 hr 3 hr Fission and Activation Products Manganese-54

-5.0E-07 7.38E-09 7.38E-09 7.38E-09 7.38E-09 7.39E-09 Cobalt-58 5.0E-07

' 37E-09 6.37E-09 6.37E-09 6.37E-09 6.38E-09

-Iron-59 5.0E-07 1.76E-08 1.76E-08 1.76E-08 1.76E-08 1.76E-08 Cobalt-60 5.0E-07 1.62E-08 1.62E-08 1.62E-08 1.63E-08 1.63E-08 Zinc-65 5.0E-07 2.26E-08 2.26E-08 2.26E-08 2.26E-08 2.26E-08 Molybdenum-99 5.0E-07 4.17E-08 4.18E-08 4.21E-08 4.25E-08 4.29E Cesium-134 5.0E-07 8.28E-09 8.28E-09 8.28E-09 8.28E-09 8.28E-09 Cesium-137 5.0E-07 7.44E-09 7.44E-09 7.44E-09 7.44E-09 7.44E-09 Cerium-141 5.0E-07 1.02E-08 1.02E-08 1.02E-08 1.02E_08 1.02E-08 Cerium-144 5.0E-06 4.21E-08 4.21E-08 4.21E-08 4.21E-08 4.21E-08 Iodine-131 1.0E 7.21E-09 7.22E-09 7.24E-09 7.26E-09 7.29E-09 Dissolved and Entrained Gates Krypton-87 L0E-05 1.'15 E-08 1.32E-08 1.73E-08 2.98E-08 5.14E-08 Krypton-88 1.0E-05 1.82E-08 1.93E-08 2.18E-08 2.78E-08 3.55E-08 Xenon-133 1.0E-05 1.95E-08 1.95E-08 1.96E-08 1.97E-08 1.98E-08 Xenon-133m 1.0E-05 5.21E-08 5.23E-08 5.26E-08 5.33E-08 5.40E-08 Xenon-135 1.0E-05 5.68E-09 5.79E-09 6.02E-09 6.49E-09 7.01E-09 Xenon-138 1.0E g 2.90E-08 6.03E-08 2.62E-07 4.92E-06 9.26E-05 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 I

Specifications LLD limits are met, and these are typical LLD values.

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

(3)

All of these analyses are required to meet Tech. Spec. LLD limits and are individually evaluated to ensure compliance.

l l i

L______-_______-_

I EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1ST HALF 1987 i

TABLE B 6ASE0US " TYPICAL LLD" EVALUATION (*)

at (')

Nuclide Tech. Spec. LLD 15 min 30 min 1 hr 2 hr 3 hr 3

l Noble Gas Krypton-87 1.0E-04 1.77E-07 2.02E-07 2.66E-07 4.59E-07 7.91E-07 Krypton-88 1.0E-04 2.63E-07 2.79E-07 3.15E-07 4.02E-07 5.14E-07 Xenon-133 1.0E-04 2.06E-07 2.06E-07 2.07E-07 2.08E-07 2.09E-07 i

Xenon-133M 1.0E-04 7.66E-07 7.69E-07 7.74E-07 7.84E-07 7.94E-07 Xenon-135 1.0E-04 8.40E-08 8.56E-08 8_.89E-08 9_.60E-08 1.04E-07 Xenon-138 1.0E-04 4.29E-07 8.94E-07 3.88E-06 7.30E-05 1.37E-03

'at( 3)

)

Particulate 15 min 30 min 1 hr 2 hr 3 hr Manganese-54 1.0E-11 2.79E-14 2.79E-14 2.79E-14

2. 79 E-14 2.79E-14 l

Cobalt-58 1.0E-11

2. 41 E-14 2.41E-14 2.41E-14 2.41E-14 2.41E-14 j

Iron-59

1. 0 E-11_

7.03E-14 7.03E-14 7.03E-14 7.03E-14 7.04E-14 Cobalt-60

1. 0 E-11 6.62E-14 6.62E-14

_6_. 62 E-14 6 62E-14 6.62E-14' inc-65

1. 0 E-11 8.99E-14 8.99E-14 8.99E-14 8.99E-14 8.99E-14 Z

Molybdenum-99 1.0E-11 1.76E-13 1.76E-13 1.77E-13 1.79E-13

1. 81 E-13 Cesium-134 1.0E-11 3.11 E-14 3.11 E-14 3.11E-14 3.11 E-14 3.11 E-14 Cesium-137 1.0E-11 2.72E-14 2.72E-14 2.72E-14 2.72E-14 2.72E-14 Cerium-141 1.0E-11 3.17 E-14 3.17 E-14 3.17E-14 3.17 E-1_4_

3.17 E-14

_ Cerium-144 1.0E-11 1.26E-13 1.26E-13 1.26E-13 1.26E

'3_

1.26E-13 Iodine-131 1.0E-11 2.60E-14 2.60E-14 2.61E-14 2.62E-11 2.63E-14 Strontium-89*

1. 0E-11 Strontium-90*

1.0E-11 4

Gross Alphad 1.0E-11 Charcoal Sample Iodine-131 1.0E-12 3.87E-14 3.87E-14 3.88E-14 3.89E-14 3.91E-14 Tritium

1.0E-06 I

NOTES:

(1)

All evaluations are in pCi/cc.

All analyses are performed to ensure that Technical Specifications LLD limits are met, and these are typical LLD values.

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

l I

l l

r (2) at is the time from micpoint of sampling to analysis.

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

(3) at for particulate and charcoal samples is the time from filter removal from sampling apparatus to analysis.

It is j

assumed filters are subjected to an average flow of 2 CFM for a 24-hour period.

(4)

These isotopes are individually evaluated to ensure compliance with Technical Specification LLD limits.

1 1.

l l

e 1

l s'

l o

~

f EFFLUENT AND WASTE'OISPOSAL SEMIANNUAL REPORT 1ST HALF 1987 SOLIO WASTE (RADI0 ACTIVE) 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 m 4.18E+01 11.50E+01

. evaporator bottoms, etc.

Ci-8.36E+02

11. 50E+01

'b.

Dry Active Waste, Compressible

Waste m

1.88E+02

11. 50E+01 Contaminated equip., etc.

Ci 8.98E+01 11.50E+01 c.

Irradiated Components, m

None N/A Control Rods, etc.

Ci None N/A

'd, Other (describe) m*

None Ci None N/A 2.

Estimate of maior nuclide composition (by type of waste) a.

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

(nuclides determined by measurement)

Curies Percent 1.

Tritium 2.37E-01 2.84E+02 2.

Carbon-14 3.38E+00 4.04E-01 3.

Manganese-54 1.79E+01 2.14E+00 4.

Iron-55 3.07E+02 3.67E+01 5.

Cobalt-57 1.03E+00 1.23E-01 6.

Cobalt-58 1.10E+01 1.32E+00 7.

Nickel-59 7.11E-01 8.51E-02 8.

Cobalt-60 2.97E+02 3.55E+01

)

9.

Strontium-90 1.53E-02 1.83E-03

/

10.

Cesium-134 3.63E+01 4.34E+00 11.

Cesium-137 5.33E+01 6.38E-00 12.

Other Nuclides 1.08E+02

1. 29E + 01 l hE

+

1 T

EFFLUENT AND WASTE' DISPOSAL. SEMIANNUAL REPORT l

1ST HALF 1987 SOLIO WASTE (RADIOACTIVE) SHIPMENTS 1

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 l

1. ' Tritium 8.12E-03' 9.04E-03'

2. - Carbon-141 2.08E-01 2.32E-01 3.

Chromium-51 1.10E+00 1.23E+00 4.

Manganese-54 6.74E-01 7.50E-01 5.

Iron-55 7.33E+01 8.16E+01 l-

6. - Cobalt-58 7.17 E +00 7.98E+00

'7. - Iron-59 6.50E-01 7.24E-01 8.

Cobalt-60 3.60E+00 4.01Et00 9.

Strontium-90 9.43E-05 1.05E-04 10.

Zirconium-95' 7.52E-02 8.37E-02

11. Niobium-95 2.02E-01 2.25E-01

12. Cesium-134 1.15E-02 1.28E-02 l

13.

Cesium-137 1.88E-02 2.09E-02

14. Other Nuclides 2.80E+00 3.12E+00 c.

Irradiated Components N/A N/A d.

Other (describe)

N/A N/A _ _ _

cr 1

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1ST HALF 1987

~ SOLID WASTE (RADIOACTIVE) SHIPMENTS

-3.

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

6 LSA Motor freight

Barnwell, South Carolina Number of' Shipments IType Quantity Mode of Transportation Destination b)

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

6 LSA Motor freight

Barnwell, S. C.

Number of Shipments Type Ouantity Mode of Transportation Destination c).

Irradiated components, control rods, etc.

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

4.

Irradia'ted fuel Shipments (Disposition)

Number of Shipments Type Quantity 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 6.

Were any changes made to the process control program?

X Yes No If yes, add as an attachment at the end of report, ( Attachment 2).

7.

Were any major changes made to the radioactive waste systems (liquid, gaseous or solid)?

Yes X

No.

If yes, add an attachment at the end of report in accordance with Technical Specification administrative control 6.15. L i

EFFLUENT AND WASTE DISP 0' SAL SEMIANNUAL REPORT 1ST HALF 1987 0FFSITE DOSE CALCULATION MANUAL CHANGES DESCRIPTION OF_ CHANGE Provisions have been added to the ODCM (Rev. 16) for a monthly tritium offsite dose evaluation for gaseous effluents. A revision of Technical Specification SR 4.11.2.3. necessitates this change.

Tritium dose evaluations have always been performed on a quarterly basis but were never included in the monthly evaluations. The effect of this change on offsite

~

dose calculations is minimal, however; the highest dose calculated for tritium using the quarterly method has been 0.02 mrem (see Attachment 1 for revised pages).

h e - _ _ _ _ _ _ _ _ _ - _ - - _ - _ _ _ _ - - _ - _-_-_ _

I ATTACHMENT 1 i

l I

l

.4-(

} For determining tha bate dosa to air:

D8 I" l "

.I EXni *'DF81 (1.17) n m

_g

. [$'Y

'where:

<3-D8n = beta, dose to: air for sector n, mead.

~

.xht'=airconcentrationofradionuclidel'insectorn,pC1/m3

.DF81 = beta to air dose factor for radionuclides i, mead /yr per pCi/m3 t,

= time period considered, yr The sector having'the highest total dose is then used to check compliance with specification 3.11.2.'2.

1.2,2 Todines. Particulate, and Tritium.

R16 Step 1

. Doses will be calculated using the methodology described in thisJstep. <If 50 percent of.the applicable limits are exceeded, step 2 will be performed.

Equations and assumptions.for' calculating doses from releases'of iodines, particulate, and tritium are as follows:

l R16 Assumptions R

1.

Doses are to be calculated for-the infant thyroid'from milk ingestion and for the child bone.and toen s.i. tract from vegetable ingestion.'

2.

'Real cow locations are considered for the milk pathway and nearest resident-locations with home-use gardens are conside, red for.the. vegetable'

. pathway.

3.

The highest annual-average X/Q and D/Q based on 1972-1975 meteorological data' for ground level releases will.be used for ingestion pathway doses.

4.

No credit is taken for radioactive decay.

S.

Releases of H-3. I-731, and I-133 are considered for the milk pathway.

H-3, Sr-89, Sr-90, Cs-134, and Cs-137 releases are considered for the.

R16 vegetable pathway to the chlid bone.

H-3, Co-58,.and Co-60 releases are' considered for the vegetable pathway to the teen g.i. tract.

6.

.The calculations extrapolate doses assuming that.only 90 percent of the total dose was contributed.

7.

The cow is assumed to graze on pasture grass for the whole year.

l.

l3 i

! Revision 16 e

i__E____._..i____-m---

p o.-

r.

Equotion0;

~

For determining;the' thyroid dose ~from milk ingestion:

'E(QtDF );. D/Q x 10' f (Q DF )X/9 t

.DTU =. 1 T T (1.18)

.(0.9) x 3.15 x 107 Whero:

DTH,=' thyroid dose from H-3, 1-131, and I-133, mrom.

' Qt _._ = j mont.hly release of iodine nuclide i, Cl.

'QT =. monthly release.of H-3, Ci-

. DF ". = nuclide i milk ingestion dose factor to infant, 7.24 x 1011 i-mrem /yr per pCi/m -s for.I-131 and 1.52 x 1020 mrem /yr per 8

pCi/m -s for 1-133.*

8 DFT= H-3 milk ingestion dose factor, 3.53 x 10' arem/yr per pci/cc.*

D/Q = relative deposition rate,.2.96 x 10-'m-r,

/

.X Q relative air concentration, 1.76 x 10-* s/m '

=

a R16 0.9 = fraction of dose expected to be contributed by I-131 and I-133 3.15 x 107

's/yri

=

106 pCi/Ci~.

=

Equation l'.18 then reduces to:

DTH = 1.04x10 so E Qt DFt + 2.19 x 10

QT i

For determining the bone doce from vegetable ingestion:

j i

E(QtDF ) D/Q 10' + Q DFTX 9 (1*19) t T

/

DBC = 1 t

3.15 x 10 (0.9)

]

7 J

whoro:

J DUC = bone dose to child, mrem.

Qt = monthly release of Se or Cs nuclide i Ci.

QT = monthly release of H-3, Ci DFt = Vegetable ingestion dose factor to child, 1

1 2.25 x 10 1, 1.36 x 10 3, 1.59 x 1011, and 2.58 x 1011' -

meem/yr por pCi/m2-s for Sr-89, Se-90, Cs-134, and Cs-137, i

respectively.*

As per Regulatory Guide 1.109 and NUREC/CR-1004 methodologies.

1 Revision 16i I

i

. U,

e l

DFT = vegetable ingestion dose factor for H-3, 4.53 x 10' meem/yr

[

per pCi/cc.*

{

i D/Q = relative deposition rate, 7.10x10-'m-2 j

-~

x/Q = relative air concentration, 2.98 x 10-* s/m'.

I 3.15x107 = s/yr.

i 10' = uCi/C1.

0.9 = fraction of total bone dose expected to be contributed by

)

H-3, Sr-89, Sr-90, co-134, and Cs-137.

Equation 1.19 then reduces to DBC = 2.50 x 10-200 101 DFt + 4. 76 x 10-4 Qr i

For determining the gastrointestinal (g.i.) tract dose from vegetable f

ingestion:

E(Q DF ) D/Q. 106 + (Q DF ) x/Q (1.20) t i T T i

DGI T

(0.9) 3.15 x 107 where:

6 DGIT = teen g.1 tract dose from H-3, co-58, and Co-60, mrom Qt = monthly release of cobalt nuclide i. C1.

QT = monthly release of H-3, Ci.

DFt = Vegetable inhestion dose factor for the teop g.i. tract, 3.87 x 10' meem/yr per pCi/m8-s for Co-58 and 3.31 x 1020 meem/yr per pC1/m -s for co-60.*

8 DFT = vegetable ingestion dose factor for H-3, 2.92 x 10' mrem /yr I

per pCi/cc*.

D/Q = relative deposition rate, 7.10 x 10-' m-8 x/Q relative air concentration, 2.98 x 10-6 s/m'.

=

3.15 x 107 s/yr

=

IOS pC1/Ci

=

0.9 = fraction of total g.i., tract dose expected to be contributed by H-3, Co-58, and co-66 Equation 1.20 then reduces to DCIT 2.50 x 10-20 I

(Q DF ) + 3.07 x 10-* QT

=

t i i

{

As per Regulatory cuide 1.109 and NUREG/CR-1004 methodologies.

I

-15a-Revision 16

TABLE 1.5

[' N DOSE FACTORS

FOR SUBMERSION IN NOBLE CASES R16 y. 2' DFBI DFSI DF 2

DFg Kr-85m

-1.17(+3)3 1.21(+3) 1.46(+3) 3.86(+3)

Kr-85 1.61(+1) 1.69(+1) 1.34(+3) 3.83(+3)

Kr-87 5.92(+3) 6.05(+3) 9.73(+3) 2.01(&4)

Kr-88 1.47(+4) 1.50(+4) 2.37(+3) 5.72(+3) 1 Kr-88+D 2.02(+4) 3.72(+4)

Kr-89 1.66(+4) 1.59(+4) 1.01(+4) 1.88(+4)

{

Xo-131m 9.15(+1) 1.53(+2) 4.76(+2) 2.18(+3)

Xe-133m 2.51(+2).

3.17(+2) 9.94(+2) 2.90(+3)

Ko-133 2.94(+2) 3.46(+2) 3.06(+2) 2.06(+3)

Ee-135m 3.12(+3) 3.30(+3) 7.11(+2) 1.45(+3) 7 's Xe-135 1.81(+3) 1.88(+3) 1.86(+3) 4.84(+3)

Xe-137 1.42(+3) 1.48(+3) 1.22(+4) 2.50(+4)

Xe-138 8.83(+3) 9.00(+3) 4.13(+3) 9.25(+3)

Xe-138+D 2.65(+4) 2.81(+4)

Ar-41 8.84(+3) 9.76(+3) 2.69(+3) 5.54(+3)

I 1.

mrom/yr per pCL/mn 2.

mead /yr por pC1/m8 3.

1.17(+3) = 1.17 x 108 i

j

)

l l

l

Based on methodology presented in " Meteorology and Atomic Energy,"

R16 D.11. S'ade, Chapters 7-4 and 7-5,1968.

Revision -16 l

L__________

A

{

4 J

l I

l 1

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ATIACHMENT 2 i

i r

l t.'.

9_;

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' Process' Control Pronram Channes

-PORC approved changes >to the Process Contro1' Program were made on-February 3, 1987.and May 8, 1987. These changes were made at the direction of our solidification vendor. Chem Nuclear, reviewed and found acceptable by PORC.

The overall conformance of the solidified waste *

.' product to existing criteria was not reduced.

e

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1 i

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1

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1 6'

.]

m p

-.4 O

z fVg

.o

~

a 1

na.

D. N I

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ML20238F719

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