ML20071A937

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Effluent & Waste Disposal Semiannual Rept for Jul-Dec 1993
ML20071A937
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 12/31/1993
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML17181A210 List:
References
NUDOCS 9403040163
Download: ML20071A937 (11)
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Text

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, EFFLUENT AND WASTE PISPOSAL SEMIANNUAL REPORT Supplement al Information j Facility Quad Cities Nuclear Power 3tation Licensee Commonwealth Edison Company  !

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1. Regulatory Limits i
a. For Noble Gases: )

Dose rate i l

1. Less than 500 mrem / year to the whole body.  !

l 2. Less than 3000 mrem / year to the skin. l l

Dose Gamma Radiation j

1. Less than or equal to 5 mrad / quarter. I
2. Less than or equal to 10 mrad / year. I Beta Radiation l 1. Less than or equal to 10 mrad / quarter.

l 2. Less than or equal to 20 mrad / year. l l b.,c. For Iodine-131, for Iodine-133, and for all radionuclides in l particulate form with half-lives greater than 8 days.

l Dose Rate i

1. Less than 1500 mrem / year Dose
1. Less than or equal to 7.5 mrem / quarter
2. Less than or equal to 15 mrem / year.

i d. For Liquid l

Less than or equal to 3 mrem to the whole body during any calendar l quarter.

Less than or equal to 10 mrem to any organ during any calendar l quarter.

Less than or equal to 6 mrem to the whole body during any calendar year.

l Less than or equal to 20 mrem to any organ during any calendar l year.

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l STMGR\01794.GGC l

9403040163 940221 PDR ADDCK 05000254 R PDR

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2. Maximum Permissible Concentration i

For fission and activation gases, iodines, and particulates.

a.,b.,c.,

with halflives greater than 8 days, allowable release limits  !

are calculated by solving equations 10.1 and 10.2 from the '

Offsite Dose Calculation Manual. The alarm setpoint is  ;

conservatively set at approximately 10% of the 10CFR20 limit.

d. For liquid effluents allowable release limits are calculated by l solving equations 10.3 and 10.4 from the Offsite Dose Calculation ,

manual. The MPC values used for the monitors were as follows-radwaste discharge 1.78E-05 uCi/ml service water 2.0E-05 uCi/ml  !

3. Average Energy The average gamma energy used to calculate the alarm setpoints for the l

! noble gas monitors was 0.676 Mev for the Third quarter and 0.754 Mev for  ;

the Fourth quarter.  ;

4. Measurements and Approximations of Total Radioactivity l
a. Fission and Activation Gases-
b. Iodines: }
c. Particulates:

l The main chimney and reactor building ventilation exhaust systems  ;

are continually monitored for iodines and particulates. These. i samples are pulled every 7 days .and analyzed by gamma isotopic.  !

The particulate papers are composited every 31 days and sent to a  !

vendor for Sr 89-90 and gross alpha analysis. Noble gas grab -('

samples are pulled and analyzed by gamma isotopic weekly. Tritium samples are pulled and analyzed every month.

The continuous strip chart recorders for the monitors on the release points are reviewed monthly for spikes and the activity l released is calculated. An additional calculated activity for noble gases is added to the Main chimney release each month. This calculation is done because most of the grab samples show less than the lower limit of detection due to the low amount of activity and the large dilution flow at the sample point. The calculation takes into account the normal offgas train and the gland steam contribution to the release.

The average flow at the release points are used to calculate the curies released, i

STMOR\01794.GGC l

d. Liquid Effluents The river discharge tanks are analyzed before discharge by gamma  !

isotopic. A composite representative portion of this sample . .

saved. This is composited with other discharges that occurred every 31 days and is analyzed for tritium and gross alpha. The batch composites are composited quarterly and sent to a vendor. for ,

Sr 89-90 and Fe 55. The discharge bay is sampled every 31 days. t and analyzed by gamma isotopic, for tritium and gross alpha. It is sampled quarterly and sent to a vendor for Sr 89-90 and Fe 55 analysis. -

The tank volumes and activities are used to calculate the. curies .

released for the River Discharge Tank. The total water released i during the quarter and the activity is used to calculate the diluted activity released at the discharge bay,_from batch '

discharges.

e. Estimated Total Error Percent i The estimated total error percents were calculated by taking the  !

square root of the sum of the squares of errors for sampling and  ;

measurement parameters. The estimated total error percent for the  ;

solid radwaste curies is 12.3%. i f.

Less than the ' lower limit of detection'(<LLD). f Samples are analyzed such that the Technical Specification LLD l requirements are met. When a nuclide is not detected during the  ;

quarter then <LLD is reported.  !

5. Batch Releases  !

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a. Liquid
1. number of releases 43
2. total time 34,405 minutes l
3. maximum time 895 minutes
4. average time 800 minutes
5. minimum time 615 minutes
6. average stream flow, discharge 63.3 gpm, dilution 3.40E+05 gpm i
b. Gaseous NONE STMGRW1794. OOC l
6. Abnormal Releases
a. Gaseous On December 2, 1993, the Unit Two adsorbers were inadvertently bypassed for approximately one minute. The effluent monitors showed no increase in activity, and the short time period did not allow grab samples to be pulled. The release was small and not quantifiable and is reported here for accuracy only.
b. Liquid On September 14, 1993, a leak was identified on the U-l "B" RHR Heat Exchanger. Unit One was at full power at this time. The total activity released to the environment from this leak was 3.82E-02Ci from 09/14/93 to 12/31/93, and was added to the monthly liquid release summary for each month.
c. On November 12, 1993, a Barrier Load Test Assembly (BLTA) Shipment was made to G.E. Nuclear in Vallecitos, CA. The shipment consisted of 6 barrier fuel rods. General Electric will do testing on the fuel rods and they will dispose of them. This item is only mentioned here for accuracy.

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STMGR\01794.GGC l

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  • QCP 100-S25 Revision 5 March 1989

. CGE EFFLUENT AND WASTE DISPOSAL

. SEMI-ANNUAL REPORT July-December 1993 GASE0US EFFLUENTS - SUMMATION OF ALL RELEASES PROCEDURE: QCP 100-7 Quarter Quarter Est. Total Unit Third Fourth Error, %

A. FISSION & ACTIVATION GASES

1. Total Release Ci 1.11E+01 8.89E00 12.4
2. Average release rate for period uCi/sec 1.40E00 1.12E00
3. Percent of Tech Spec limit
  • 4.56E-03 3.72E-03 Chimney & stack  % 1.97E-Oo 1.69E-04 l

B. IODINE l

1. Total Iodine-131 Ci 2.85E-04 2.45E-04 40.0
2. Average release rate for period uCi/sec 3.59E-05 3.08E-05 C. PARTICULATES -
1. Particulates with half-lives

> 8 days Ci 4.20E-03 5.38E-03 39.1

2. Average release rate for period uCi/sec 5.28E-04 6.77E-04
3. Gross alpha radioactivity Ci 4.24E-06 1.14E-06**

D. TRITIUM l 1. Total Release Ci 1.08E+01 8.30E00 6.2

2. Average release rate for period uCi/sec 1.36E00 1.04E00 E. IODINE 131 & 133, TRITIUM AND PARTICULATES l

Percent of Tech Spec Limit 7.36E-02 1.49E-01 Chimney & Stack  %

  • N0BLE GAS GAMMA / NOBLE GAS BETA DOSE LIMITS
    • PROJECTED VALUE BASED ON PREVIOUS SIX MONTHS AVAILABLE DATA cmuuwscu 1

,' QCP 100-S25 Revision 5 CGE MAIN CHIMNEY

. GASE0US EFFLUENTS Continuous Mode Batch Mode Quarter Quarter Quarter Quarter Nuclides Released Unit Third Fourth Third Fourth

1. Fission gases Kr-85 Ci < LLD < LLD NA NA Kr-85m Ci 9.53E-01 3.00E-01 NA NA Kr-87 C1 2.45E-01 3.16E-01 NA NA Kr-88 Ci 7.72E-01 3.62E-01 NA NA Xe-133 Ci 1.15E00 2.51E-01 NA NA Xe-135 Ci 2.59E-01 2.49E-01 NA NA Xe-135m Ci 1.24E00 1.41E00 NA NA I Xe-138 Ci 5.10E00 5.82E00 NA NA j Ar-41 Ci 1.41E00 1.83E-01 NA NA I Ci C1 Ci Total for Period Ci 1.11E+01 8.89E00 NA NA
2. Iodines I-131 Ci 2.85E-04 2.34E-04 NA NA I-133 Ci 1.87E-03 1.38E-03 NA NA I-135 Ci 4.54E-04 1.21E-03 NA NA Total for Period Ci 2.61E-03 2.82E-03 NA NA cutu uu m oco3 2

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.' QCP 100-S25 Revision 5 CGE  :

I MAIN CHIMNEY

. GASE0US EFFLUENTS

, Continuous Mode Batch Mode Quarter Quarter Quarter Quarter Nuclides Released Unit Third Fourth Third Fourth j 3. Particulates i

Sr-89* Ci 1.54E-04 1.36E-04 NA NA Sr-90* Ci 4.50E-07 4.50E-07 NA NA l

Cs-134 Ci < LLD < LLD NA NA Cs-137 Ci < LLD 4.63E-06 NA NA I

Ba-140 Ci 1.12E-04 1.47E-04 NA NA l La-140 Ci 5.13E-05 1.20E-04 NA NA l Cr-51 Ci 4.75E-05 < LLD NA NA Mn-54 Ci 1.41E-05 < LLD NA NA Co-58 Ci < LLD < LLD NA NA i

Co-60 Ci 2.84E-04 2.52E-04 NA NA I-131 Ci < LLD 6.33E-06 NA NA l

Ag-110m Ci < LLD 9.27E-06 NA NA I-133 Ci 3.00E-04 3.19E-04 NA NA Mo-99 Ci 3.22E-04 6.17E-05 NA NA Ci Ci Ci Total for Period Ci 1.29E-03 1.06E-03 NA NA PROJECTED VALUE BASED ON PREVIOUS SIX MONTHS AVAILABLE DATA 1

l cuarmu>sc93 3

- QCP 100-S25 Revision 5 CGE REACTOR VENTILATION

. GASEOUS EFFLUENTS Continuous Mode Batch Mode Quarter Quarter Quarter Quarter Nuclides Released Unit Third Fourth Third Fourth l

1. Fission gases Kr-85 Ci < LLD < LLD NA NA Kr-85m Ci < LLD < LLD NA NA Kr-87 Ci < LLD < LLD NA NA Kr-88 Ci < LLD < LLD NA NA l

Xe-133 Ci < LLD < LLD NA NA Xe-135 Ci < LLD < LLD NA NA Xe-135m Ci < LLD < LLD NA NA Xe-138 Ci < LLD < LLD NA NA Ci Ci Total for Period Ci < LLD < LLD NA NA l

2. Iodines I-131 Ci < LLD 4.43E-06 NA NA 1

1-133 Ci 2.41E-05 7.88E-05 NA NA I-135 Ci < LLD < LLD NA NA Total for Period Ci 2.41E-05 8.32E-05 NA NA carmuu>cco 4

' QCP 100-S25

~ Revision 5 CGE REACTOR VENTILATION

..- GASE0US EFFLUENTS Continuous Mode Batch Mode  ;

Quarter .- Quarter Quarter Quarter l Nuclides Released Unit Third Fourth Third Fourth' i i

3. Particulates '

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Sr-89* Ci 3.48E-06 4.97E-06 NA NA Sr-90* Ci < LLD < LLD NA NA

]

Cs-134 Ci < LLD < LLD NA - NA l Cs-137 Ci- < LLD 4.87E-05 'NA NA 3 i

Ba-140 Ci < LLD < LLD~ NA NA i La-140 Ci < LLD < LLD NA NA Cr-51' Ci 1.24E-03 1.14E-04 NA NA Mn-54 Ci 1.55E-04 6.09E-04 NA NA Co-58 Ci 6.01E-05 1.67E-04 NA NA Co-60 Ci 7.13E-04 2.55E-03 NA NA i

I-131 Ci < LLD < LLD NA NA  !

Ag-110m Ci 3.11E-05 < LLD NA- NA l Mo-99 Ci 6.32E-04 7.96E-04 NA NA l I-133 Ci 5.06E-05 2.94E-05 NA NA l

! Zn-65 Ci 2.77E-05 I

< LLD NA NA l Ci -

Ci 1

Total for Period Ci 2.91E-03 4.32E-03 NA NA i l

  • PROJECTED VALUE BASED ON PREVIOUS SIX MONTHS AVAILABLE DATA I

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l curmutascu 5 1

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.' QCP 100-S25 l Revision 5 i CGE l

, LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Quarter Quarter Est. Total Unit Third Fourth Error. % i A. FISSION & ACTIVATION PRODUCTS

1. Total release (not including tritium, gases, alpha) Ci 1.89E-02 3. 23 E-02 5.6
2. Average diluted concentration ,

during batch discharges period 7.91E-10 1.60E-09 uCi/ml 1.23E-01 1.46E-02  !

3. Percent of applicable limit *  % 3.48E-02 1.90E-02
4. Maximum diluted concentration during batch distnarges uCi/ml 9.02E-09 3.93E-08 B. TRITIUM
1. Total Release Ci 1.63E+01 1.49E+01 4.0  ;
2. Average diluted concentration during batch discharges uCi/ml 6.82E-07 7.38E-07 ,

! 3. Percent of applicable limit  % 2.25E-02 2.46E-02 f 1

C. DISSOLVED AND ENTRAINED GASES ,

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1. Total Release Ci 1.14E-04 1.02E-04 5.6
2. Average diluted concentration  ;

during batch discharges uCi/ml 4.77E-12 5.05E-12 l 3. Percent of applicable limit  % 2.39E-06 2.53E-06 D. GROSS ALPHA RADI0 ACTIVITY

1. Total Release Ci < LLD < LLD NA
2. Average concentration released < LLD < LLD during batch discharges uCi/ml E. VOLUME OF WASTE RELEASED (prior to dilution) Liters 3.29E+06 4. 95E+ 06 F. VOLUME OF DILUTION WATER USED l DURING BATCH DISCHARGES Liters 2.39E+10 2.02E+10 G. TOTAL VOLUME OF DILUTION WATER DURING PERIOD (QUARTER) Liters 3.93E+11 3.94E+11
  • WHOLE BODY / ORGAN ouuxtocco 6

.' QCP 100-S25 i Revision 5 i CGE l

LIQUID EFFLUENTS Continuous Mode Batch Mode Quarter Quarter Quarter Quarter !

Nuclides Released Unit Third Fourth Third Fourth Sr-89 Ci < LLD < LLD 1.86E-05 1.53E-05 Sr-90 Ci < LLD < LLD 1.41E-05 2.46E-06 Cs-134 Ci < LLD < LLD < LLD < LLD Cs-137 Ci < LLD < LLD 2.58E-03 7.77E-04 I-131 Ci < LLD < LLD < LLD < LLD l Co-58 Ci < LLD < LLD 1.52E-04 1.85E-03 t

Co-60 Ci < LLD < LLD 1.15E-02 1.87E-02 Fe-59 Ci < LLD < LLD < LLD 2.93E-04 Zn-65 Ci < LLD < LLD < LLD 1.10E-04 Mn-54 Ci < LLD < LLD 4.48E-04 5.71E-03 j Cr-51 Ci < LLD < LLD 1.94E-03 1.68E-03 As-76 Ci < LLD < LLD < LLD 5.13E-05 Nb-95 Ci < LLD < LLD < LLD 6.74E-06 Mo-99 Ci < LLD < LLD < LLD < LLD Ag-110m Ci < LLD < LLD 2.17E-04 5.95E-04 Ba-140 Ci < LLD < LLD < LLD < LLD Sb-124 Ci < LLD < LLD 1.97E-05 < LLD La-140 Ci < LLD < LLD < LLD 2.16E-05 i'

Fe-55 Ci < LLD < LLD 1.83E-03 2.47E-03 Sb-125 Ci < LLD < LLD 1.53E-04 < LLD  ;

Total for Period (above) Ci < LLD < LLD 1.89E-02 3.23E-02 l Xe-133 Ci < LLD < LLD 5.46E-05 2.78E-05 Xe-135 Ci < LLD < LLD 5.98E-05 7.45E-05 l

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Prepared by , Approved by hnm 0 OL % el_

Q Chemistry Supervisor (final) cennnaren 7

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