Text

Effluent & Waste Disposal Semiannual Report, for Jul to Dec 1991
	ML20092L065
Person / Time
Site:	Quad Cities
Issue date:	12/31/1991
From:	; COMMONWEALTH EDISON CO.
To:	;
Shared Package
ML20092L059	List: ML20092L051; ML20092L065;
References
	NUDOCS 9202260143
	Download: ML20092L065 (29)
	v • d • e

._ - .__ ___ - .. . . _ - . _ - - -. - . .-.

EFFLUENT AND HASTE DISPOSAL SEMIANNUAL REPORT Supplemental Information facility Quad Citie.1_ Nuclear Power _Sittt10D Licensee Comonwealth_ Edison _Comitny

1. Regulatory Limits

a. For Noble Gases:

Dose rate

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

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

Dose Gamma Radiation L 1. Less than or equal to 5 mrad / quarter.

l 2. Less than or equal to 10 mrad / year.

Beta Radiation

1. Less than or equal to 10 mrad / quarter.

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

Dose Rate

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.

d. For Liquid Less than or equal to 3 mrem to the whole body during any calendar year.

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

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9202260143 920116 PDR ADOCK 05000254 R PDR

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2, Maximum Permissible Concentration a.,b. c., for fission and activation gases, iodines, and particulates 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 one half of the most conservative value from the two equations.

d. For 11guld effluents allowable release limits are calculated by solving equation 10.3 from the Offsite Dose Calculation manual. The MPC values used for the monitors were as follows:

radwaste discharge 4.46 E-05 uC1/ml service water 2.0E-05 uCi/ml

3. Average Energy The average gamma energy used to calculate the alarm setpoints for the noble gas monitor 3 was 0.586 Hev for the Third quarter and 0.570 Mev for the fourth quarter.

4. Measurements and Approximations of Total Radioactivity

a. fission and Activation Gases:

b. Iodines:

c. Particulates:

The main chimney and reactor building ventilation exhaust systems are continually monitored for iodines and particulates, These 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 released is calculated. An addition \1 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, amon m __

_ . . . . __ .- _ _ . _ _ . . . ____.m. _.__ _..

1

d. Liquid Effluents The river discharge tanks are. analyzed before discharge by gamma isotopic. A composite sample is taken during discharge. 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 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 during the quarter and the activity is used to calculate the curies released for the discharge bay.

e. Estimated Total Error Percent The estimated total error percents were calculated by taking the square root of the som of the squares of errors for sampling and measurement parameters. The estimated total error percent for the solid radwaste curies is 11.7%.

f. Less than the lower limit of detection (<LLD).

Samples are analyzed such that the Technical Specification LLO requirements are met. When a nuclide is not detected during the quarter then <LLD is reported.

5. Batch Releases

a. . Liquid

1. number of releases 2

2. total time 1081 minutes

3. maximum time 546 minutes 4 '. average time 541 minutes

5. ' minimum time 535 minutes

6. average stream flow, discharge 63.7 gpm, dilution 3.75 E+05 gpm

b. Gaseous NONE

6. Abnormal Releases

a. Liquid

! On August 9, 1991 a leak developed on the Unit One "B" Residual Heat l Removal Heat Exchanger. Unit one was at full power at this time. A l total of 3.58 E+04 uC) was released between August 9, 1991 and l December 31, 1991. This release was added to the monthly liquid release summary for each of the months August thru December, 1991, stumum . , . - -

In October 1991, approximately 6,000 gallons of EDTA boiler cleaning 4

solution was shipped to a facility in Oak Ridge, Tennessee for incineration. The total activity shipped offsite was calculated to be 6.37E401 uC1.

b. Gaseous On December 31, 1991 the Unit One Charcoal Adsorbers were bypassed from 1445 to 1812. The cause was high offgas flow thus causing a high The cause of the high flow was identified and DP on the Adsorbers.

corrected by 1812. A total of 1.00 E+06 uCi of activity was released during the time the charcoal Adsorbers were bypassed. This release was added to the Noble Gas release summary for the month of December, 1991.

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QCP 100-525 Revision 5 EFFLUENT AND WASTE DISPOSAL March 1989 SEMI-ANNUAL REPORT aulv - December 1991 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES PROCEDURE: QCP 100-7 Quarter Quarter Est. Total Unit Third l'ou r t h Error, %

A. FISSION & ACTIVATION GASES

1. Total Release C1 1.170+01 1.32E+01 _ _

8.7

2. Average release rate for period uCi/sec 1.47E00 1.66E00

3. Percent of Tech Spec limit

1.13E-02 1.35E-02 Chimney & Stack % T~. TUN 1.47e-oa B. IODINE

1. Total Iodine-131 Ci 5.05E-04 4.13E-04 31.8

2. Average release rate for period uC1/sec 6.35C-05 5.20E-05 C. PARTICULATES

1. Particulates with half-lives

> 8 days C1 3.68E-03 4.62E-03 17.7

2. Average release rate for period pCi/sec 4.64E-04 5.81E-04

3. Gross alpha radioactivity C1 <LLD <LLD D. TRITIUM

1. Total Release C1 2.97E01 3.96E01 6.2

2. Average release rate for period uCi/sec 3.74E00 4.98E00 E. Iodine 131 & 133, Tritium and Particulates

' Percent of Tech spec Limit Chimney & stack 1 9.56E-01 5.13E-01

NOBLE GAS GAMMA /N0BLE GAS BETA DOSE LIMITS

- Projected value based on previous six months available data.

APPROVED JUN 121989

' C ~~

Q.C.O.S.R.

. QCP 100-S25 Revision 5 MAIN CHIMNEY l GASEOUS EFFLUENTS Continuous Mode Batch Mode Quarter Quarter Quarter Quarter Nuclides Released Unit "I'hird Fourth __

1. Fission gases Kr-85 C1 (LLD < l.l.D Kr-85m C1

.98E-01 3.28E-01 Kr-87 C1 5.820-01 5.871:-01 Kr-88 C1 2.82E-01 4.72E-01 Xe-133 C1 4.87E-01 7.041:-01 Xe-135 C1 3.45E-01 7.85E-01 Xe-135m C1 1.61E00 1.91E00 Xe-138 Ci 7.97E00 8.16E00 Ar-41 Cl 1.84E-01 2.65E-01 Xe-131M Ci <LLD 8.96E-03 C1 Cl Total for Period C1 1.17E+01 1.32E+01

2. Iodines I-131 C ', '.730-04 2.76E-04 I-133 C1 2.60E-03 1.41E-03 I-135 C1 1.06E-03 < L I.D Total for Period C1 4.13E-03 1.69E-03 APPROVED JUN 121989 9/0295c Q.C.O.S.R.

QCP-100-S25-Revision 5 i

t MAIN CHIMNEY l GASEOUS EFFLUENTS Continuous Mode Batch Mode Quarter Quarter Quarter Quarter Nuclides Released Unit Third Fourth

3. Particulates Sr-89 C1 9.8]E-05 1.61E-04 Sr-90 C1 <LLD <LLD Cs-134 Ci <LLD <LLD Cs-137 Ci <LLD <LLD Ba-140 Cl 8.73E-05 4.06E-05 La-140 C1 4.06E-04 1.42E-04 l

Cr-51 C1 <LLD <LLD Mn-54 Ci <LLD 1.03E-05 Co-58 Ci <LLD < 1,L D Co-60 Ci 2.73E-04 1.850-04 I-131 Ci 1.03E-05 2.79E-05 Ag-110m Ci <LLD <LLD I-133 Ci 1.21E-04 5.97E-04 Mo-99 Ci 3.88E-05 1.69E-04 Ci C1 C1 .,

Total for Period Ci 1.03E-03 1.33E-03

APPROVED i

l JUN 121989 9/0295c Q.C.O.S.R.

- - -. .. - - _ . . . ~ - ..

OCP 100-S25 Revision 5 REACTOR VENTILATION l GASEOUS EFFLUENTS Continuous Mode Batch Mode Quarter Quarter Quarter Quarter Nuclides Released Unit Third l'ou r t h

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

Xe-133 Ci <LLD <LLD Xe-135 Ci <LLD <LLD Xe-135m C1 <LLD <LLD Xe-138 Ci <LLD <LLD C1 C1 Total for Period Ci <LLD <LLD

2. Iodines I-131 C1 2.12E-b5 1.74E-05 I-133 Cl 1.59E-04 "t.45E-04 I-135 Ci < 1.L D <LLD Total for Period C1 1.80E-04 1 62E-04 APPROVED JUN 121989 9/0295c Q.C.O.S.R.

. OCP 100-525 Revision 5 REACTOR VENilLATION l GASEOUS EFFLUENTS Continuous Mode Batch Mode Quarter Quarter Quarter Quarter Nuclides Released Unit Thinl l'ourih

3. Particulates Sr-89 ,_

Cl 1, t .ty 7.021:-07 Sr-90 C1 ' t.LD 1,1. 0 Cs-134 C1 ~ 01 t) < 1 1.D Cs-137 C1 3.461:-04 4.361'-07 Ba-140 C1 1. l . D < l.LD La-140 __

Ci up L 1. D

_Cr-51 Ci 1.1. n 6 . ? 81:- 0 4 _._

Hn-54 _C i , 2.691:-05 9.001:-05 Co-58 Ci 5.431:-06 6.911:-05 Co-60 Ci 6.571:-04 7.451:-04 1-131 Ci :Ll D 9.I91:-05 Aa-110m C1 <LLD <LLD Mo-99 Cl 1.571:-03 '. 4 7 1;- 0 3 1-133 Ci 4.341:-05 1.851-04

!;b-95 C1 < LI.D 4.7111-06 Ci Ci

, Total for Period C1 ? . 6 5):~ 0 3 3.? 41:-0 1 i APPROVED JUN 121989 9/0295c Q.C.O.S.R.

QCP 100-525

. Revision S LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES

~

Quarter Quarter Est. Total Unit Thi ni l'ou r t h Error. %

A. FISSION & ACTIVATION PRODUCTS

~~

1. Total release (not including ..

. tritium, gases, alpha) -

C1 2.561:-03 9. 611:- 0 J 7.2

2. Average diluted concentration during batch discharges period pCi/ml '

941:-09 ';.351:-09 9.171;-03 3.740-02

,_3 . Percent of appitcable limit

1 1.'fiil5(i1 I.~6TlIT02

4. Maximum diluted concentration during batch discharges pCi/ml 1. 9 41:-6 % . 3y 0 9

*! Jot u s A1, A3 an<l DJ f or bot h quart era 2 ne l utle aci.ivity B. TRITIUM from U-1 Itlut lix l e a r. . All other valuca are for no rin a l bntch releace.

1. Total release Ci '.200-01 4.0412-01 6.1

2. Average diluted ccncentration durino batch discharges _pCi/ml 3 ' 61:-07 7.501:-07

3. Percent of appilcable limit % 7.191 -O h2. 5 01:- 0 2 C. DISSOLVED AND EilRAINED GASES

1. Total release Ci < !.00 < LI.D !UA

2. Average diluted concentration during batch discharges pC1/ml (LLD < !.l .D

3. Percent of applicable limit % U 11 D. GROSS ALPHA RADICACTIVITY .

1. Total Release C1 < LI.D <LLD IUA

2. Average concentration released during batch discharges pCi/ml (LLD < bLD _

E. VOLUME OF HASTE RELEASED (prior to dilution Liters 1.28n05 1.331:05

i. VOLUME OF DILU110N HATER USED DURING BATCH DISCHARGES Liters 1.021:09 3.051:08 G. TOTAL VOLUME OF DILUTION WATER DURING PERIOD (QUARTER) Liters 4.901.:11 6.701:11 APPROVED

HHOLE BODY / ORGAN 1 9/0295c JtJN 121989 M .O.S.R.

QCP 100-525 Revision 5 LIQUID EFFLUENTS Continuous Mode Batch Mode Quarter Quarter Quarter Quarter Nuclides Relealed Unit Thi n1 l'ou r t h Third l'ourih Sr-89 C1 110 ~ i.LD 2 . 2 0 1:- 0 5 1.381-04 Sr-90 Ci 4 M.D 1. D ? . 4 71:- O ft ! . 0 91:- O 5 CS-134 C1 - tio 1.1. D i.:11-0; <LLD

__Q_s - 13 7 _C1 < LLD Lt D 1.641:-04 7 . 7 21:- O L I-131 C1 Lu, -tu> <LLD 11D Co- 5'J, C1 : L u) ' u) 2.441:-06 1.001:-04

.Co-60 C1 ttD <LLD

.: . 0 01:- 0 3 6.921:-03 Fe-59 Ci ~ 110 - L1 D < 11D < nod 2n-65 C1 -

1D <: LD 6.011:-05 3.651:-05 Mn-54 C1 LLD lih '.061:-04 7.581:-04 Cr-51 Ci 'i.LD M .D < llD '.871:-04 Zr-95 Ci : 1. t . D < 11D <LLD < l.l D Nb-95 _Ci < LI.D <LLD ' LLD

' LI.D t4o-99 C1 M .D : 1.L D <LLD < Ll D Aq-110m Ci <LLD < 1 LD < LI.D : L L D ____

Ba-14 0 Ci <LLD <LLD LLD <LLD Cs-136 Ci ' t .t .D ' LI D <LLD 1LD La-140 Ci <LLD < LI.D <LLD 'LLD Fe-55 Ci .LLD < LI.D :.701:-04 4 . 7 8 t:- 0 4

_ Unidentified C1 <LLD < LI D <LLD 'LLD Total for Period (above) Ci < I1D (LLD . 561:-03 9.611:-03 Xe-133 C1 <LLD < l.LD <LLD <LLD Xe-135 Ci <LLD <LLD ':LLD <LLD Prepared by bl . 7hf)\Cbb Approved by had O. D e ,s t-( Chemistry Supervisor

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b (final) APPROVED 9/0295c JUN 121969 i

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- . - . - . - . _ - - - - . - . - -. - . = . _ . - - - . . - - -.. ._. - -.

f SOLID _RAQWASTE SEM-ANNVAL REPORI JULY 1991 Shipping ,

Date Carrier Site Volune HilliCuries ;

e....... ..................... ................... ......... ............ i 07/09/91 KINDRICK TRUCKING QUADREX 1290.10 181.80 1 07/15/91 CHEM NUCLEAR SYSTEMS BARNWELL, SC 205.80 18 W .00 07/22/91 CHEM NUCLEAR SYSTEMS BARNWELL, SC 205.80 15 ;.00 07/29/91 CHEM NUCLEAR SYSTEMS BARNWELL, SC 205.80 91s5.00 .

07/31/91 HITTMAN WESTINGHOUSE, PA 1040.00 3.09 2947.50 43280.49 f

, ,. .- , . + _ . - . . . , - . , . . , . . . . _ _ _ . . . _ - . . . . . . . . . . . . _ _ , . _ . . . ~ _ . . , , . . . . . . . - . _ . . .,_..,_.,..~._.,.-c-,.-,.-

. _-. _ . -.--..___.__-w ._...... _ ..-.. ._ . _ __ . _ _ . . _ . - - _ . _ _ _ _ _ _ _ _ . _ _ _

SQUD_ MDW.ASIE_SiliLAN$l%L _REPORI i

i AUGUST 1991 Shipping Date Carrier Site Volume HilliCuries 08/05/91 CHEM NUCLEAR SYSTEMS BARNWELL, SC 205.00 11030.00 08/07/91 HITTMAN SCIENilFIC ECOLOGY 1290.10 07.66 08/13/91 CHEM NUCLEAR SYSTEMS BARNWELL, SC 205.80 37670.00 08/19/91 CHEM NUCLEAR SYSTEMS BARNWELL, SC 205.80 29620.00 08/21/91 KINDRICK TRUCKING QUADREX 1290.10 27.69 3197.60 78435.35 n

my ...,--+-w,9>m- s%.-i.---w w4,,w,- m-q,rC-g= rwre D- i--yn -*==m---e' e i ms vin--r ,-*tm*a pa www,.rw*. -wMr*

Fwi mm4 y w*-M+ '9e--'-St4-vt1Fww% 9yTew's-= '7+pwP* 'D+'-rF"$1"'

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50 LID MDWASTE SEH]-R4WAL _REEORI SEPTEMBER 1991 Shipping Date Carrier Site Volune Mil 11 Curies 09/05/91 RAY-TECH CHAf4t4AHAN 22.50 7.10 09/05/91 RAY-TECH CHANNAHAN 570.00 281.72 09/10/91 CHEM NUCLEAR SYSTEMS BARNWELL, SC 205.00 16700.00 09/23/91 CHEM NUCLEAR SYSTEMS BARNWELL, SC 205.00 8992.00 "ibbi$ib ~ "i5555$65 F

k I

I

10 LIP RQGSIE SWL-ANNEL_RRORI OCTOBER 1991 Shipping Date Carrier Site Volune HilliCuries

........ ..................... ................... ......... .r..........

10/07/91 CHEM 14UCLEAR SYSTEM $ BARNWELL, SC 205.00 10310.00 10/21/91 CHEM llVCLEAR 5YSTEMS BARIJWELL, SC 205.00 18750.00 10/24/91 CHEM l1UCLEAR SYSTEMS BARNWELL, SC 205.00 $03.90

~ 55f!55 "" "i6555 55 i

Sn]D RADWASTE SEMI-ANWAL REPJRI NOVEMBER 1991 Shipping Date Carrier Site Volune Millicuries 11/04/91 CHEM NUCLEAR SYSTEMS BARNWELL, SC 205.00 10230.00 11/12/91 CHEM NUCLEAR SYSTEMS BARNWELL, SC 205.00 11770.00 11/17/91 CHEM NUCLEAR SYSTEMS BARHWELL, SC 170.80 483.30 11/18/91 CHEM nJCLEAR SYSTEMS BARNWELL, SC 205.80 9252.00 11/21/91 KINDRICK TRUCKING QUADREX 981.50 57.70 11/25/91 CHEM NUCLEAR SYSTEMS BARNWELL, SC 205.80 14810.00 11/27/91 RAY-1ECH CHANNAHAN 022.50 344.10 2598.00 54947.16

e

's lallL_RAIWlilE SEMI-ANWAL REPORI i

DECEMBER 1991 l

Shipping Date Carrier Site Volune Hillicuries 12/03/91 CHEM NUCLEAR SYSTEMS U.S. ECOLOGY, WA 105.00 1053.50 12/09/91 CHEM NUCLEAR SYSTEMS BARNWELL, SC 205.80 16000.00 12/11/91 CHEM NUCLEAR SYSTEMS U.S. ECOLOGY, WA 345.00 0.15 12/13/91 CHEM NUCLEAR SYSTEMS U.S. ECOLOGY, WA 105.00 812.17 !

12/16/91 CHEM NUCLEAR SYSTEMS BARNWELL, SC 205.80 21310.00 l 966.60 40063.82 TOTALS: 11331.20 272331.62 l

, -

ML20092L065

Text

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