ML20153H342

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Effluent & Waste Disposal Semiannual Rept,Supplemental Info for Jan-June 1988
ML20153H342
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 06/30/1988
From:
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20153G840 List:
References
NUDOCS 8809090154
Download: ML20153H342 (24)
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l EFFLUENT AND WASTE DISPOSAL SEM1 ANNUAL REPORT  ;

SUPPLEMENTAL INFORMATION J1t HALF ]191 3 y- 1. Regulatory Limits  !

x. w ~ a. Fission and Activation Gases:

.- -(l) Instastaneous - Nuclide Dependant (all release points) p -

Shield Building Exhaust

>, w.- 4 Auxiliary Building Exhaust ,

- -Condenser Vacuum Exhaust Service Building Exhaust r

NOTE: futal plant release rate limits per nuclide are established by TVA's Radiological Control, Radiation Protection Branch (RCRP8). These .

limits are further evaluated for each vent based on design flowrate. Technical Specification will not be exceeded until the i sum of individual isotope release rate per release rate limit [

exceeds 1.0. i

b. & c. lodines and particulates, half-lives 18 Days  !

(1) Instantaneous - Nuclide Dependant NOTE: Total plant release rate limits per nuclide are established by .

TVA's Radiological Control, Radiation Protection Branch j (RCRP8). These limits are further evaluated for each vent  ;

based on design flowrate. Technical Specification will not be- i

>.,. exceeded untti the sum of individual isotope release rate per . ,

release rate limit exceeds 1.0.

(

m- d. Liquid effluent: I MPCs1.0 (reference 10CFR20, Appendix B, note 3C, I

>~ Table !!, column 2).

j

~. .e. Tritium f

h.-- ,.... .. -(1) Liquid - s3.0E-3 wCi/ml (ref.10CFR20. Table 11, column 2) 1 p --

(2) Airborne - (reference 10CFR20 Table 11, column 1) y Shield Building Exhaust s3.138E+03 pCi/sec l

Auxiliary Building Exhaust s2.555E+04 uCi/sec Service Building Exhaust s1.165E+03 pCi/sec o

Condenser Vacuum Exhaust 15.043E+00 uCi/sec r

NOTE: These limits are established by TVA based on each vent's design I flowrate, eso9o9o154 880823 PDR @

ADOCK 05o00327 R PDC 1 }.6 l l

l p,...., ,

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. i EFFLUENT AND WASTE DISPOSAL SEM1 ANNUAL REPORT SUPPLEMENTAL INFORMAT10N 1st HALF 1191 ,

I

- .- 2. Maximum Permissible Concentrations.

. w.w ~

f w .,- a. ' fission and-Activation Gases: Not Applicable

- -, b. todines: Not Applicable ew r - -c. Particulates, half-lives 48 days: Not Applicable  ;

l

..-.* . d. Liquid effluents: sum of indv. MPC ratios 61.0 (ref.10CFR20,  !

w ,- Appendir 8, Note 1) i

3. Average Energy - Not Applicable t
4. Measurements and Approximations of Total Radioactivity 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 "0.00E-01 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 j Technical Specification and analysis capability. Refer to Tables l A and 8 for estimates of these typical values,

a. Fission and Activation Gases

-w,-.- Airborne offluent gaseous activity is continuously monitored and m.m recorded. Additional grab samples f rom the shield building, e- r - - auxiliary building, service building, and condenser vacuum exhausts

~+- - are taken and analyzed at least monthly to determine the quantity of

-w noble gas activity released for the month based on the average vent

~~ - - -

flowrites recorded for the sample period. Also, noble gas samples

. are collected and evaluated for the shield and auxiliary buildings

-follwing startup, shutdown, or rated thermal power change exceeding m, 15 percent within one hour (sampling only required if dose

-w equivalent I-131 concentration in the primary coolant has increased

+ more than a factor of 3 and the noble gas activity monitor shows w-+ that the containment activity has increased more than a factor of 3). The vent flowrates for the shield building, auxiliary building, service building, and condenser vacuum exhausts are determined and recorded once a shift.

l

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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION 1st HALF 1988

4. Measurements and Approximation of Total Radioactivity (continued)
a. Fission and Activation Gases (continued)

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, the activity released f rom purging or

- . s,. venting of containment, and the activity released f rom waste gas

- . - decay-tank (s).

(*..- b. & c. lodines and Particulates r+ - r- - Iodine and particulate activity is continuously monitored and av- recorded. Charcoal and particulate samples are taken f rom the shield and auxiliary building exhausts and analyzed at least weekly to determine the total activity released f rom the plant based on the average vent flowrates recorded for sampling period.

Also, particulate and charcoal samples are taken f rom the auxiliary and shield building exhausts once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for 2 days following startup, shutdown, or a rated thermal power change exceeding 15 percent within one hour. The quantity of iodine and particulate released f rom 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 f rom the shield and auxiliary building exhausts are recorded once a shif t.

,, The total particulate and iodine activity released for the month is v.. -

then determined by summing all of the activity released from the s #-- shield and auxiliary building exhausts for all sampling periods.

-cu d. Liquid Effluents (1) Batch (Radwaste and condensate regenerants to cooling tower

~ ~ blowdown)

Total gamma isotopic activity concentrations are determined on p , -- - each batch of liquid effluent prior to release. The total curie W. 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.

J

. i t e EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION 1st HALF 1988

4. Measurements and Approximation of Total Radioactivity (continued)

(2) Continuous Releases and Periodic Continuous Releases (Condensate regenerants, turbine building sump and steam generator blowdown)

Total gansna 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) 70 94 Each
2. Total time period for batch releases 9,635 12,797 Minutes
3. Maximum time period for a batch release 170 195 Minutes
4. Average time period for batch releases 138 136 Minutes
5. Minimum stream flow during periods of effluent into a flowing stream: (a) (a)

(a) See RCRPB's annual Radiological Impact Assessment Report.

b. Gaseous 1 Number of batches released 59 74 Each 2 Total time period for batch releases 4071 7657 Minutes 3 Maximum time period for a batch release 420 1428 Minutes 4 Average time period for batch releases 69 103 Minutes 5 Minimum time period for a batch release 15 28 Minutes

. .e EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION 1st HALF 1988 Value Units Quarter Quarter 1st 2nd

6. Abnormal Releases
a. Liquid (1) Number of Releases 0 2 (2) Total Activity Released 0.00E-01 1.07E-06 Ci
b. Gaseous (1) Number of Releases 0 1 (2) Total Activity Released 0.00E-01 4.30E-01 Ci
7. Offsite Dose Calculation Manual (00CM)

Were any changes made to the ODCM during the reporting period?

X Yes No If yes, add an attachment at the end of report. (Attachment 3)  ;

i

r_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ,

e EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1st HALF 1988 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES ist Total 2nd Total A. Fission and Activation Unit - Otr  % Error Otr  % Error Products

1. Total Releases Curies 1.33E-01 11.8 E+01 2.11E-01 11.8 + 01
2. Average Diluted Conc.

During Period of All Identified Isotopes pCi/ml 1.85E-07 2.30E-07

3. Percent of Applicable Limit (IMPCsi)  % 7.14E-01 8.83E-01 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.
8. Tritium
1. Total Release Curies 1.52E+01 -+1. 8 E +01 1.56E+01 +1.8E+01
2. Average Diluted pCi/mi 2.12E-05 1.70E-05 Conc. During Period
3. Percent of Applicable Limit (3.0E-03 pci/ml) % 7.07E-01 5.66E-01 C. Dissolved and Entrained Gases
1. Total Release Curies 0.00E-01 +3.9Et01 8.88E-03 -+3.9E+01
2. Average Diluted pCi/ml 0.00E-01 9.66E-09 Conc. During Period
3. Percent of Applicable 0.00E-01 4.83E-03 Limit (2.0E-04 pCi/ml)  %
0. Gross Alpha Radioactivity
1. Total Release Curies 0.00E-01 12.0E+01 0.00E-01 12.0E+01 E. Volume of Waste Release (Defore Dilution) Liters 2.26E+08 14.0E+00 2.51E+08 14.0E+00 F. Volume of Dilution Liters 4.91E+08 11.1E+01 6.68E+08 11.1E+01 Water f or Period c .

EFFLUENT AND WASTE 01SPOSAL SEMIANNUAL REPORT 1st HALF 1988 LIQUID EFFLUENTS - TOTAL PLANT DISCHARGE G. Isotope Summary (Note: Refer to Table A for values reported as 0.00E-01)

Required by Technical Specification /Others Fission and Activation Products Continuous Mode Batch Mode Nuclide Unit Quarter Quarter Quarter Quarter 15' 2nd 1st 2nd

1. Strontium-89 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01
2. Strontium-90 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01
3. Iron-55 Ci 0.00E-01 0.00E-01 2.50E-02 4.82E-02
4. Manganese-54 Ci 1.62E-05 1.*1E-05 1.62E-04 1.06E-03
5. Cobalt-58 Ci 0.00E-01 4.98E-0; 1.51E-05 1.25E-05
6. Iron-59 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01
7. Cobalt-60 Ci 1.96E-04 6.81E-04 4.69E-02 1.08E-01
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. lodine-131 Ci 0.00E-01 3.20E-06 0.00E-01 4.87E-04
11. Cesium-134 Ci 1.01E-03 1.93E-03 1.33E-02 8.47E-03
12. Cesium-137 Ci 2.38E-03 6.08E-03 3.42E-02 2.34E-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 0.00E-01 0.00E-01 Others (Specify)
15. Antimony-125 Ci 0.00E-01 0.00E-01 9.75E-03 1.21E-02
16. Cobalt-57 Ci 4.87E-07 0.00E-01 1.13E-05 1.36E-05
17. Silver-110m Ci 0.00E-01 0.00E-01 0.00E-01 1,88E-04
18. Technetiam-99m Ci 0.00E-01 3.90E-06 0.00E-01 1.03E-04
19. Zirconium-97 Ci 0.00E-01 0.00E-01 0.00E-01 6.83E-05

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT lil HALF 1988 LIQUID EFFLUENTS - TOTAL PLANT DISCHARGE (CONTINUED)

Continuous Mode 8atch Node Nuclide Unit Quarter quarter Quarter Quarter 1st 2nd 1st 2nd

20. Niobium-95 Ci 0,00E-01 0,00E-01 p,00E-01 3,60E-06
21. Barium-139 Ci 0.00E-01 0.00E-01 0,00E-01 1.55E-07
22. Yttrium-91m Ci 0.00E-01 0,00E-01 0.00E-01 1.88E-08
23. lodine-133 Ci 0,00E-01 5,51E-06 0,00E-01 3,66E-06
24. Chromium-51 Ci 0.00E-01 2.87E-05 0,00E-01 0,00E-01
25. Tellurium-132 Ci 0.00E-01 2,20E-06 0.00E-01 0,00E-01 Total for Period Ci 3,60E-03 8,80E-03 1,29E-01 2.02E-01 r- -

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1st HALF ligg LIQUID EFFLUENTS - TOTAL PLANT DISCHARGE (CONTINUED)

6. Isotope Summary (NOTE: kefer to Table A for values reported as 0.00E-01)

Required by Technical Specification /Others Oissolved and Entrained Noble Gases Continuous Mode Batch Mode Nuclide Unit Quarter Quarter Quarter Quarter ist 2nd 1st 2nd

1. Krypton-87 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01
2. Krypton-88 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01
3. Xenon-133 Ci 0.00E-01 0.00E-01 0.00E-01 8.75E-03
4. Xenon-133m C1 0.00E-01 0.00E-01 0.00E-01 2.24E-05
5. Xenon-135 Ci 0.00E-01 0.00E-01 0.00E-01 1.03E-04
6. Xenon-138 Ci 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Others (Specify)
7. Krypton-85m Ci 0.00E-01 0.00E-01 0,00E-01 5.17E-07 Total for Period Ci 0.00E-01 0.00E-01 0.00E-01 8.88E-03

.g_

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 111 HALF 1988 TABLE A LIQUID ' TYPICAL LLO' EVALUATION (1)

At (a)

Nuclide Tech. Spec. LLO 115 min 30 min 1 hr 2 hr __-3 hr Manganese-$4 5.0E-07 9.1?E-09 9.12E-09 9.12E-09 9.12E-09 ).12E-09 Cobalt-58 5.0E-07 8.21E-09 8.21E-09 8121E-09 8.21E-09 8.22E-09 Iron ~59 5.0E-07 1111L-Q1 1.62E-08 1.62E-08 1.62E-08 1262E-08 Cobalt-60 5.0E-07 1.08E-08 1.08E-08 1.08E-08 1.08E-08 1.08E-08 Zinc-65 5.0E-07 2.14E-08 2.14E-08 2.14E-08 2.14E-08 2.14E-08 Molybdenum-99 5.0E-07 5.24E-08 5.25E-08 5.28E-08 5.34E-08 5.39E-08 Cesium-134 5.0E-07 9.82E-09 9.82E-09 9,82E-09 9.82E-09 9.82E-09 Cesium-137 5.0E-07_ 9.31E-09 9.31E-09 9.31E-09 9.31E-09 9.31E-09 Cert'am-141 5.0E-07 1.06E-08 1.06E-08 1.07E-08 1.07E-08 1.07E-08 Cerium-144 5.0E-06 4.03E-08 4.03E-08 4.03E-08 4.03E-08 4.03E-08 lodine-131 1.0E-06 7.28E-09 7.28E-09 7.30E-09 7.32E-09 7. 3 5 E-09 Krypton-87 1.0E-05 1.6?E-08 1.85E-08 2.43E-08 4.20E-08 7,24E-08 Krypton-88 1.0E-05 2.13E-08 2.21E-08 2.Stt-08 3.21E-08 4.17E-08 Xenon-133 1.0E-05 2.03E-08 2.04E-08 2.04E-08 2.05E-08 2.06E-08 Xenon-133m 1.0E-05 5.05E-08 5.07E-08 5.10E-08 5.17E-08 5.24E-08 Xenon-135 1.0E-05 1 60E-09 5.70E-09 5.93E-09 6.40E-09 6 90E-09 Xenon-138 1.0E-05 2.82E-08 1287E-08 2.55E-07 4.79E-06 9.01E-05 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 111 HALF 1111 TABLE A LIQU10

  • TYPICAL LLD' EVALUATION (*)

(Continued)

Nuclide Tech. Snec. LLO (Others)(s)

Tritium 1.0E-05 Gross Alpha 1. 0E -07 Strontium-89 5.0E-08 Strontium-90 5 . 0E -08_

Iron-55 1.0E-06 l

All evaluations are in yCi/ml. All analyses are performed to NOTES: (a) ensure that Technical Specification LLO limits are met, and these are typical LLO values.

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

(s) All of these analyses are required to meet Technical Specification LLO limits, and are individually evaluated to ensure compliance.

.. , o EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT lit. HALF 1988 GASEOUS EFFLUENTS-SUMMA 110N OF ALL RELEASES (GROUND LEVEL RELEASES) 1st Total 2nd Total Swanation of_ All Releases Unit _Q1r_,  % Error .911  % Error A. Noble Gases

1. Total Releases Ci 0.00E-01 11.1E+01 3.49E+01 +1 .1E+01
2. Average Release Rate for Period Sci /sec 0.00E-01 4.44E+00
3. Percent of Technical Specification Limit  % 0.00E-01 1.50E-03 B. lodines
1. Total lodine-131 Ci 0.00E-01 ~+1. 3 E +01 2.53E-05 11.3E+01
2. Average Release Rate for Period Sci /sec 0.00E-01 3.22E-06
3. Percent of Technical Specification Limit (1.60E-01 vC1/sec)  % 0.00E-01 2.01E-03 C. P_4rticulates
1. Particulates with C1 5.10E-05 +

~1.6E+01 3.08E-05 11.6E+01 half-lives 38 days

2. Average Release vC1/sec 6.49E-06 3.92E-06 Rate for Period Perr,ent of Techni-3.

cal Specification  % 4.89E-04 2.22E-04 Limit l 4. Gross Alpha Radio- Ci 0.00E-01 12.1E+01 0.00E-01 12.1E+01

' activity D. Tritium i 1. Total Release Ci 9.31E-01 +1 .5E+01 2.43E+00 11.5E+01 l 2. Average Release vCi/sec 1.18E-01 3.09E-01 Rate for Period

3. Percent of Technical Specification Limit 5 3.59E-04 9.37E-04 (3.3E+04 vCi/sec) l l

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1st HALF 1988 GASE0US EFFLUENTS-SUMMATION OF ALL RELEASES (GROUND LEVEL RELEASES)

Continuous Mode Batch Mode Unit Quarter quarter Quarter Quarter 1st 2nd 1st __2nd E. Noble Gases Required by Technical Specification /Others

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-Q1 2.60E-01 0.00E-01 3.34E+01
4. Xenon-133m Ci 0.00E-01 0.00E-01 0.00E-01 5.42E-01 ,
5. Xenon-135 Ci 0.00E-01 0.00E-01 0.00E-01 4.85E-01
6. Xenon-138 C1 Q1.00E-01 0.00E-01 0.00E-01 0.00E-01 Others (Specify)
7. Krypton-85 C1 0.00E-01 0.00E-01 0.00E-01 1.43E-01
8. Argon-41 Ci QiO0E-01 Q2901..91 0.00E-01 5.77E-02
9. Krypton-85m Ci 0,00E-01 0.00E-01 Q200E-01 1.56E-0?

Total for Period C1 0.00E-01 21b.Q1-01 Q190E-01 3.46E+01 F. todines

, 1. lodine-131 Ci 0.00E-01 2.53E-05

2. todine-133 Ci 0 1_00E-01 0.00E-Q1
3. todine-135 Ci 0.00E-01 0.00E-01 Total for Period Ci 0.00E-01 2.53E-01 NOTE: Refer to Table B for values reported as 0.00E-01.

1 l

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o o EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT lil HALF litt GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES (GROUND LEVEL RELEASES)

6. Particulates Required by Technical Specification /Others Muclide Unit Continuous Mode Quarter Quarter 1st 2nd
1. Strontium-89 Ci 0.00E-01 0.00E-01
2. Strontium-90 Ci 0.00E-01 0.00E-01
3. Iron-59 Ci 0.00E-01 0.00E-01
4. Cobalt-60 C1 4.72E-05 2.96E-05
5. Zine-65 Ci 0.00E-01 0.00E-01
6. Manganese-54 Ci 0.00E-01 0.00E-01
7. Cobalt-58 Ci 0.00E-01 0.00E-01
8. Molybdenum-99 Ci 0.00E-01 0.00E-01
9. Cesium-134 Ci 0.00E-01 0.00E-01
10. Cesium-137 C1 3.81E-06 0.00E-01
11. Cerium-141 Ci 0.00E-01 0.00E-01
12. Cerium-144 Ci 0.00E-01 0.00E-01 Others (Specify)
13. Cobalt-57 Ci 6.23E-09 3.38E-07
14. Technetium-99m Ci 0.00E-01 8.20E-07
Total for Period Ci 5.10E-05 3.08E-05 NOTE
Refer to Table B for values reported as 0.00E-01.

4 1 , <

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT lLt HALF 1988 TA8LE 8 GASE0US "TYPICAL LLD' EVALUATION (1)

Noble Gas at (8)

Nuclide Tech. Spec. LLD 15 min - 30 min _ 1 hr 2 hr 3 hr Krypton-87 1.0E-04 2.91E-07 3.34E-07 139E-07 1 56E-07 1.30E-06 Krypton-88 1.0E-04 3.59E-07 3.82E-07 4.31E-07 5.51E-07 7.03E-07 Xenon-133 1.0E-04 1.97E-07 1.98E-07 1.98E-07 1.99E-07 2.00E-07 Xenon-133M 1.0E-04 8.75E-07 8.78E-07 8.84E-07 8.95E-07 9.07E-07 Xenon-135 1.0E-04 9.76E-08 9.95E-Qg 1.03E-07 1.12E-07 1.20E-01 Xenon-138 1.0E-04 4.9)E-07 1.03E-06 4.46E-06 8.38E-05 1.58E-03 b rticulate Sample Manganese-54 1.0E-10 3. 88 E-14 3.88E-H 3.88E-14 3.88E-1_4 3.88E-14 Cobalt-58 1.0E-10 3.49E-14 3. 49 E-14 3.49E-14 3.50E-14 3.50E-14 Iron-59 1.0E-10 7. 25E-14 1.25E-14 7. 25 E-14 7.26E-li 7_.26E-14 Cobalt-60 1.0E-10 4.95E-14 4.9 5E-14 4.9 5E-14 4.95E-14 4.95E-14 Zint-65 1.0E-10 9.54E-14 9.54E-14 9. 54 E-14 9.54E-14 9.54E-14 Molybdenum-99 1.0E-10 2.49E-13 2.49E-13 2. 51 E-13 2. 53 E-13 2.56E-13 l

Cesium-134 1.0E-10 4.15E-14 4.15E-14 4.15E-14 4.15E-14 4.15 E-14 l

Cesium-137 1.0E-10 3.85E-14 3.85E-14 3. 8 5 E-14 3.85E-14 3.85E-14 Cerium-141 1.CE-10 3.70E-E 3.70E-14 3. 70 E -14 3.70E-li 3_. 71 E-14 Cerium-144 1.0E-10 1. 32 E-13 1. 32 E-13 L.32E-13 1.32E-13 1. 32 E-13 l lodine-131 10E-10 3.09E-14 3.09E-14 3.09E-14 3.11E-14 3.12 E-14 Strontium-89(s) 1.0E-11 St rontium-90( 3) }.0E-11 Gross Alpha (a) L9E-11

. . +

EFF!; 'h ' -

.F TE DISPOSAL SEMIANNUAL REPORT

.it HALF 1988 TABLE B CA:P)si "TYPICAL LLD" EVALVAT10N(1)

(Continued) at(8)

Charcoal Sample Tech. Spec. LLO 15 min 30 min 1 hr 2 hr __3 hr Iodine-131 1.0E-11 4. 31 E-14 - 4.32E-14 4. 32 E-14 4.34E-14 4.36E-14 Others Tritium (a) 1.0E-06 NOTES (t) All evaluations are in pCi/cc. All analyses are ,

performed to ensure that Technical Specification '

LLD limits are met, and these are typical LLD values. Alpha emitters are counted for a set time of 20 minutes.

(a) at for noble gases is the time from sampling to analysis. At for charcoal and particulate samples is the time from filter removal from sampling apparatus to analysis, assuming an average flow of 2 CFM for a 24-hour sampling period. '

(a) These isotopes are individually evaluated to ensure compliance with Technical Specification LLO limits.

1

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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1st HALF 1988 l

SOLID WASTE (RADIDACTIVE) SHIPMENTS t

A. Solid Waste Shipped Of fsite for Burial or Disposal (not Irradiated Fuel)  !

4 Month :st. Tot.

1. Tvoe of Waste Qnit n Period ;rror % ~ j
a. Spent resins, filter sludges a s 5.27E+01 11.50E+01 evaporator bottoms, etc. Ci 2.43E+01 11.50E+01
b. Dry Active Waste, Compressible Waste, me 3.18E+0? 11.50E+01 Contaminated equip., etc. Ci 5.43E +01 11.50E+01
c. Irradiated Components, m' None N/A I Control Rods, etc. Ci None N/A i f
d. Other (describe) m8 3.41E+00 +1. 50E +01 I Dewatered Mechanical Filters Ci 4.81E-01 11.50E+01
2. Estimate of Major Nuclide Composition (by tvoe of waste)
a. Spent resin, filter sludges, evaporator bottoms, etc. [

(nuclides determined by measurement) v Curies Percent l L

1. Tritium 8.55E-02 3.52E-01 L
2. Carbon-14 2.46E-01 1.01E+00
3. Iron -55 2.21E+00 9.09E+00
4. Nickel-63 6.02E+00 2.48E+01
5. Cobalt-60 1.44E+01 5.93E+01 f
6. Strontium-90 2.72E-01 1.12E+00 i
7. Technetium-99 1.40E-03 5.76E-03 I
8. Cesium-134 3.22E-01 1.33E+00 L
9. Cesium-137 6.92E-01 2.85E+00 l
10. Manganese-54 3.97E-02 1.63E-01 (
11. Cobalt-57 5.11E-03 2.10E-02  !
12. Zine-65 3.29E-03 1.35E-02 {
13. Nickel-59 2.61E-02 1.07E-01 s
14. Iodine-129 1.86E-03 7.65E-03 (
15. Plutonium-238 6.16E-05 2.53E-04 t
16. Plutonium-239 2.24E-05 9.22E-05 5
17. Plutonium-241 2.64E-03 1.09E-02
18. Antimony-125 2.84E-03 1.17E-02
19. Potassium-40 2.87E-03 1.18E-02 i

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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT lil HALF 1111 SOLIO WASTE (RA010 ACTIVE) SHIPMENTS

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

(nuclides determined by estimate) puries Percent

1. Tritium 5.02E-03 9.23E-03
2. Carbon-14 1.29E-01 2.37E-01
3. Chromium-51 6.85E-01 1.26E+00
4. Iron-55 0.00E-01 0.00E-01
5. Cobalt-58 4.53E+01 8.34E+01
6. Cobalt-60 4.43E+00 8.16E+00
7. Nickel-63 2.23E+00 4.11E+00
8. Technetium-99 1.52E+00 2.80E+00
9. Iodine-129 1. 51 E-04 2.78E-04 1
10. Other Nuclides N/A N/A
c. Irradiated Components N/A N/A
d. Other (describe) N/A N/A Dewatered Mechanical Filters
1. Tritium 2.97E-01 6.18E+01
2. Carbon-14 8.66E-04 1,80E-01
3. Manganese-54 5.85E-03 1.21E+00
4. Iron-55 8.01E-02 1.66E+01
5. Cobalt-60 7.28E-02 1.51E+01
6. Nickel-63 2.45E-02 5.08E+00
7. Technetium-99 3.57E-09 7.42E-07
8. lodine-129 1.73E-09 3.60E-07

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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT {

1st HALF 1988 f SOLIO WASTE (RADIDACTIVE) SHIPMENTS [

! l

] 3. Salid Waste Disposition Number of Shipments Type Quantity Mode of Transpo-tation Destination a) Spent resin, filter sludges, evaporator bottoms, etc. [

l 11 A-LSA MajorFreight Barnwell South Carolina Number of Shionents lyse Guantity Mode of Transportation Destinat_ ion l l

b) Dry Active Waste, compressible waste, contaminated equipment, etc.  ;

10 A-LSA Motor Freight Barnwell f South Carolina j I

! Number of Shioments lype Ouantity Mode of Transportation Destination i

c) Irradiated components, control rods, etc.

i N aber of Shioments Type Quantity Mode of Transportation Destination f

, d) 1 Dewatered Motor 'reight Barnwell i

, Mechanical South Carolina  ;

Filters j l 4. Irradiated Fuel Shioments (Disposition)

Number of Shioments Type Quantity Mode of Transportation flestinglion None N/A N/A N/A j 5. Solidification of Weste Was solidification performed? Yes X No i

If yes, solidification media: N/A i i l

6. Were any changes made to the process control program? X Yes No j If yes, add as an attachment at the end of report in accordance with Technical ,

I Specification Administrative Control 6.13. l l l l

i 1. Were any major changes made to the radioactive waste systen.s (liquid, gaseous j or solid)? Yes X _ No. If yes, add an attachment at the end of 4 report in accordance with Technical Specification administrative control 6.15. .

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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT <

lil HALF 1988 ATTACHMENT 1 IN0PERA81.E INSTRUMENTATION

.oursuant to Technical Specification LCO 3.3.3.10, the following inforwation is provided concerning radioactive ef fluent nonttoring instrumentation which was inoperable for greater than 30 consecutive days during the period January 1,1988, through June 30, 1988.

The Turbine Building Station Sump Discharge Monitor. 0-RM-90-212, was declared inoperable on January 5,1988, at 1:05 a.m. and remained inoperable untti March 2,1988, at 8:25 p.m., a total time of 51 days, 19 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br />, and 20 minutes. The reason for this period of inoperability was due to the necessity of w~ ing a design change which allowed the monitor to discharge dir>- y to the Turbine Building Sump instead of discharging back the same header from which flow is diverted into the monitor.

Flow indicator 1-F1-30-242, which measures air flow rate through Unit i Shield Building Exhaust, was declared inoperable on October 31, 1981, for exhaust flow rates of less than 8000 cubic feet per minute and remains inoperable at this time. 2-F1-10-242, which measures air flow rate through Unit 2 Shield Building Exhaust, was declared inoperable for exhaust flow rates of less than 8000 cubic feet per minute on November 25, 1981, and remains inoperable. It was determined that these tuo instruments cannot accurately measure exhaust flow rates that are less than 8000 cubic feet per minute; they are considered operable for flows above 8000 cfm. When inoperable, exhaust flow rates are estimated based on the design flow rates of exhaust fans in operation. Current plans are to replace this instrumentation on both shield building exhausts.

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.= 37. <

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. o EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT s.

1st HALF 1988 ATTACHMENT 2 4

Process Control Program Changes At the direction of the solidification vendor, Chem Nuclear System Inc, Barnwell S.C., the sample calculation sheet for oily waste was revised to f accurately represent the overall height (in inches) of the solidified mass. The previous revision omitted some of the additives in the sample calculation sheet which prevented an accurate ending volume calculation.

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- 4 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT lst HALF 1988 ATTACHMENT 3 1 .-

Following are descriptions of changes made to the Sequoyah Offsite Dose Calculation Manual (00CM) during the period January 1, 1988, to June 30, 1988, and the affected pages. (Revisions 18 and 19)

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SQN CDCM Change Description Fern Deserietion ef chante:

Table 3.1 and Figure 3.6 need to be revised to reflect radiological monitorint requirecents for SQN. Specifically, Rev.the environmental 17 of the SQN. Further, monitoring locations 02 and 23 need t Figure 3.6. These locations were, from Table 3.2 but ir. advertently retained on Figure 3.6in a previous ODCM revi Af f ected pages: 69 through 72, 85.

2perificatien fer chanse: ~

The SQN ODOM must reflect the environmental radiological program for SQN.

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Effects on sateeints and dose caleufations: -

This change vill have no effect on effluent setpoints or dose calculations.

RARC Review:

ate / 8b RARC Chair:an /

r

. ow . . , .

9/2..

Title:

Handling Cf Changes to the SQN Offsite Dose RARC OP 8 Calculation Manual Revision 0

'_. ,? Page 5 of 5

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Appendix 1 SQN ODCM Change Description Form Description of change:(O ~ Addit ten of samo11no locations and analysis frecue. le to reflect the program currently being conducted and to correct typographical errors. (2) Change fish type from white crapple to crapple. (3) Revise figures r

to Indicate the additional sampling locations and to Identify map references.

Pages affected: (1)b/s4 %. 3f) TWc 3,'/ j t7ep6 Td& 3 3, 3 F,p 3,I,3.S 3 3; peloe p,p3 3, q , 3, g , 3, g, ,

Justification for change: (1) The program currently being conducted exceeds the reaulrements of the ODCH. This change would reflect the current program in the

^f'53 00CH. (2) Allows the collection of. black crapple when white crapple are not

. kj" M ave 11able. (3) Identify added locations on the figures.

Analysis of effect of change on dose calculations, projections, or setpoint

. calculations: -

W. e', esangre w111. have no Imoact on dose calculations, projections, or eennte* eniculations.

r Attach marked-up pages from the c ren revision of the SON CDOM which show

.- . 3 the change.

'.. : , k RARC Review: b ='

Date:8 36 RARC Chairman '

/

06790/COC4

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