ML20114C051

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Effluent & Waste Disposal Semiannual Rept for Quad-Cities Station for Period 920101 Through 920630
ML20114C051
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 06/30/1992
From: Bax R
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RLB-92-180, NUDOCS 9209010128
Download: ML20114C051 (26)
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, N Commonw alth Edison j [  :

) ouad Cates Nuaar Power St: tion 22710 206 Avenue North

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f Corcova, ?:hnos 61242 9740 Telephone 309/654 2241 RLB-92-180 July 28, 1992 U.S. Nuclear Regulatory Commission Document Control Desk Hashington, D.C. 20555

SUBJECT:

Quad Cities Station Operating Report NRC Dockets (50-254 and 50-265)

Enclosed is the radioactive Effluent Report for January through June i992, for Quad Cities Nuclear Power Station.

Tha Unit One service water monitor was out-of-service Jenuary 1 through April 30, 1992. The monitor was taken out-of-service to investigate a spiking problem associated with the electronics. The monitor was returned to service the same day that the problem was rectified. The required sampling was performed during this time period to continue releases via inis pathway, A copy of this report will be furnished to the NRC Resident Inspector.

Sincerely, COMMONWEALTH EDISON QtiAD CITIES NUCLEAR POWER STATION R. L. Bax Station Manager RLB/JGH/jmk Enclosure l

310077

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STWOR c5 e j

l 9209010128 920630 PDR ADOCK 05000254 R PDR _

EFFLUENT AND HASTE DISPOSAL SEMIANNUAL REPORT Supplemental Information Facility Quad Cities Nuclear Power StatiDD Licensee Commonwealth Edison ComqADY

1. Regulatory Limits
a. For. Noble Gases:

Dose rate

1. Less thar. 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.  !
2. Less than or equal to 10 mrad / year. )

Beta Radiation l

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 mremiquarter
2. Less than or equal to 15 mremiyahr.
d. For Liquid Less than or equal to 3 mrem to the whole body during any calendar quarter.

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.

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

i smaams J

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 frora the Off site Dose Calculation manual. The MPC values used for the monitors were as follows:

radwaste discharge 1.78E-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 monitors was 0.597 Mev for the First quarter and 0.555 Mev for the_Second 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 arri 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 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, swa ns _ _ _

l .

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 sum of the squares of errors for sampling and measurement parameters. The estimated total error percent for the solid radw&ste raries is 11.7%.

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

Samples are analyzed such that the Technical specification LLD 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. total time 8376 minutes .
3. maximum time 870 minutes
4. average time 698 minutes
5. minimum time 495 minutes
6. average _ stream flow, discharge 63.0 gpm, dilution 1.94E+05 gpm
b. Gaseous NONE
6. Abnormal Releases

.a. Liquid On August 9, 1991 a leak developed on the Unit One "B" Residual Heat Removal Heat Exchanger. Unit one was at full power at this time. A total of 1.93E+04 uCi was released from January 1, 1992 thru June 30, 1992. This release was added to the monthly liquid release summary for each of the months January thru June, 1992, sam e ]

b. ' Gaseous On June 11, 1992 the Unit One Charcoal Adsorbers were bypassed untti June 14, 1992, a total of 4,755 minutes. The reason was high offgas flow thus causing a nigh DP on the Adsorbers. The cause of the high flow was identified and corrected by 1015 on June 14, 1992. A total of 3.45E+06 uC1 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 June 1992.

On April 22, 1992 a ventilation door leading to the main chimney was found open by a radiation protection technician. He closed the door and notified the Chemistry Department of the problem. It was determined through sampling that no significant activity was released via this path, and is mentioned here only for accuracy.

1 stum m

)

QCP 100-525 1 Revision 5 ,

EFFLUENT AND HASTE DISPOSAL March 1989 l SEMI-ANNUAL REPORT January - June 1992

)

GASEOUS EFFLUENTS _- SUMMATION _OF /.LL RELEASES i PROCEDURE: -QCP 100-7 Quarter Quarter Est. Total lini t First, Second Error. %

A-. FISSION & ACTIVATION GASES

1. Total Release C1 1.12E+01 1.32E+01 12.4 l
2. Average release rate for Deriod uC1/see 1.42E+00 1.68E+00  !
3. Percent of Tech Spec limtt
  • 1.44E-02 1.23E-02  !

Chimney & stack  % 1.07E-03 1.10E-03 )

8. IODINE l
1. Total Iodine-131 C1 2.35E-04 4.28E-04 31.5
2. Average release rate for Deriod uC1/sec 2.93E-05 5.44E-05

.C.- PARTICULATES

1. Particulates with half-lives o

> 8 days Ci- 8.66E-03 5.02E-03 17.0 2; Average release rate for period uC1/sec 1.10E-03 6.38E-04

~

3. Gross alpha radioactivity Ct 6.20E-06 <LLD D. -TRITIUM

-1. Total Release C1- 1.86E+01 5.66E+00 6.2

2. Average release rate for period uC1/sec 2.37E+00 7.20E-01
_ E. Iodine 131 & 133, Tritium and Particulates Percent of Tech spec Limit Chimney & stack 1 9.21E-01 7.05E-01
  • NOBLE GAS GAMMA / NOBLE GAS BETA DOSE LIMITS j APPROVED JUN 121999 9/0295c- Q.C.O.S.R.

b , . _ _ _.

QCP 100-525

. Revision 5 ,

MAIN CHIMNEY GASEOUS EFFLUENTS I' .

i Continuous Mode Batch Mode '

Quarter Quarter Quarter Quarter Juclides Released Unit First Second

1. Fission gases Kr-85 Ci <LLD <LLD NA NA Kr-85m C1 1.42E+00 3.28E-01 NA. NA Kr-87 C1 2.88E-01 4.35E-01 NA NA Kr-88 C1 1.59E+00 1.96E-01 NA NA Xe-133 Ci 5.61E-01 7.29E-00 NA NA

_Xe-135 C1 1.81E-01 7.90E-01 NA NA Xe-135m C1 1.12E+00 1.64E+00 NA NA Xe-138 C1 4.29E+00 6.65E+00 NA NA Ar C1 1.74E+00 2.42E+00 NA NA Cl Cl C1 l.

Total for' Period C1 1.12E+01 1 32E+01 NA NA 2.- Iodines

-I-131 Cj 2.22E-04. 4.05E-04 NA NA I-133 Cl l '. 24 E-03 2.33E-03 NA -NA I.135- C1 ~ 2.01 E-04 2.18E-04 NA NA Total for Period C1 1.66E-03 2 95E-03 NA. NA 4

. APPROVED i

JUN 121969-i- 9/0295c G '.O.S.R. .

i QCP 100-525  :

~ Revision 5 j HAIN CHIMNEY  ; l GASEOUS EFFLUENTS Continuous Mode Batch Mode Quarter Ouarter Quarter Nuclides Released- Unit First Lecond Quarter 3.- Particulates Sr-89 C1 2.10E-04 1.99E-04 NA NA Sr-90 C1 1.48E-07 3.26E-07 NA NA Cs-134 \ C1 <LLD <LLD NA NA

-Cs-137 Cj <LLD 1.29E-05 NA NA Bg-140 Ci <LLD 1.61E-04 '

NA NA La-140 C1 3.57E-05 2.65E-04 NA NA Cr-51 Ci 5.55E-05 3.80E-05 NA NA Mn-54 C1 2 34E-05 <LLD NA NA Co-58 Ci <llD (LLD NA NA Co-60 C1 1.61E-04 2 71E-04 NA NA I-131 Ci 6.01E-06 8.74E-06 NA NA AQ-110m Ci (LLD <llD NA NA 1 133 C1 1.06E-04 1.75E-04 NA NA MD-99 C1 2.31E-04 1.89E-04 NA NA C1 C1 C1 Total for Period C1 8.29E-04 1 32E-03 NA NA

  • NOTE: Scaled values based on previous 6 mos data, e

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

l .

QCP 100-S25 Revision 5

^

REACTOR VENTILATION l

GASEOUS EFFLUENTS Continuous Mode Batch Mode Quarter Quarter Quarter Quarter

,Nuclides Released Unit F1rst Second

1. Fission gasos Kr-85 , Ci <LLD <LLD NA NI Kr-85m Ci <LLD <LLD NA NA Kr-87 '

Ct <LLD <LLD NA NA

-Kr-88 Ci (LLD <LLD NA Nn ye-133 Ci <LLD <LLD NA NA Xe-135 Ci <LLD <LLD NA NA Xa-135m Ci <LLD <LLD NA NA Xe-138 Ci 5 L,LD <LLD NA NA Ci

. C1 .

Total for Period Ci <LLD <LLD NA NA

2. Iodines I-131 Ci 7.27t-06 1.46E-05 NA NA I-133 Ci 7.21E-06 ,LLD

< NA NA I-105 C1 (LLD <LLD NA NA Total for Period C1 1.45E-05 1.46E-05 NA NA APPROVED J'IN I 21989 9/0295c ggg )

OCP 100-525 Revision 5 REACTOR VENTILATION l GASEOUS EFFLUENTS Continuous Mode Batch Mode

__ Quartdr Quarter Quarter Quarter Nuclides Released Unit- First secc,nd

3. Particulates Sr-89 C1 8.86E-06 1 31E-05 NA NA Sr-90 C1 2.48E-07 2.86E-07 NA NA Cs-134 C1 <LLD <LLD NA NA

_Cs-137 Cl 8.63L-05 2.52E-04 NA NA Ba-140 C1 <LLO <tLD NA NA p 140 Ci (LLD <LLD NA NA Cr-51 C1 1.34E-03 9.01E-05 NA NA Mn-54 C1 1 38E-03 4.17E-04 NA NA Co-58 C1 3.15E-04 1.72E-05 NA NA Co-60 C1 4.46E-03 2.69E-03 NA NA i-131 Ci <lLO <LLD NA NA An-110m Ci sLLD <LLO NA NA Mo-99 C1 9.4BE-05 2.13E-04 NA NA Zn-65 C1 1.43E-04 8.67E-06 NA pA r

C1 C1 Cl Total for Period Cl 7.83E-03 3.70E-03 NA NA

  • NOTE: -Scaled values based--on previous 6 mos. data.

APPROVED JUN 121999 9/0295c .'~

Q.C.O.S.R.

QCP 100-535

, Revision 5 9

LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Quarter Quarter Est. Total Unit First Second Error, t A. FIS$10N & ACTIVATION PRODUCTS

1. Total release (not including ..

tritium, asses. aloha) C1 2.36E-02 1.03E-02 5.6

2. Average diluted concentration durina batch discharaest De*tod uC1/ml 2.79E-09 4.05E-09
3. Percent of applicable limit *  %  :-02, J . 2 8 E-02
4. Meximum diluted concentration durino batch discharges uCi/ml  ; __ +08 4.0$E-09 B. TRITIUM N ll fly 7foI U T R N x M A$ r values are for normal batch relea, .
1. _ Total release C1 8.91E+00 5.07E-01 6.1
2. Average d1 Luted concentration  ;

durina batch discharaes uC1/ml 1.66E-06 4.16E-07

3. Percent of app 11 cable Ilmit 1 5.53E*02 1 37E-02 C. DISSOLVED AND ENTRAINED GASES
1. Totel release C1 5.63E-04 <LLD 5.6
2. Average di uted concentration durina batch discharats uC1/ml 1.05E-10 <LLD
3. Percent of applicable limit i 5.25E-05 0 4

D. GROSS ALPHA RADICACTIVITY

1. -Total Release Ci 5.38E-05 <LLD 14.9
2. Average concentration releasea .

durine batch discharaes uCi/mi 1 00E-11

. <LLD E. VOLUME OF WASTE RELEASED (prior to dilution Liters 1.83E+06 1.89E+05-i F. VOLUME OF DILUTION WATER USED DURING BATCH DISCHARGES _ Liters- 5.38E+09 1.22E+09 G. TOTAL VOLUME OF DILUTION NATER DURING PERIOO (00ARTER) Liters 1.69E+11 4.40E+11 APPROVED

'HHOLE 80DY/ ORGAN 9/0295c JUN 121999 0.C.O.S.R.

  • OCP 100-525

.. Revision 5 LIQUID EFFLUENTS Continuous Mode Batch Mode Quarter Quarter Quarter Quarter Nyc11 des Releared Unit rirst second Sr-89 C1 (LLD <LLD 2.86E-04 2.400-04 3r-90 C1 (LLD <LLD 1.52E-04 7.20E-06 Cs-134 C1 <lLD <LLD 1.70E-05 <LLD

__Cs-137 C1 <LLD <LLD 2.51E-03 1.02E-03 I-131 Ci (LLD <LLD <tLD (LLD Co-58 Cl <LLD <LLD 5.08E-04 1.11E-03

__Co-60 C1 (LLD (LLD 9.91E-03 5 98E-03 re-59 Cg <LLD <LLD (LLD <LLD L

Zn-65 Cg (LLD <LLD 2 36E-04 2.30E-04 Mn-54 C1 (LLD (LLD 1.43E-03 1 32E-03 i

Cr-51 -

Cl <tLD <LLD 6.77E-03 <LLD Zr-95 Ct <tLD (LLD <tLD <tLD Nb-95 Cl <tLD <LLD 3.38E-05 <LLD Mo-99 C1 <LLD <LLD 3.24E-05 <LLD An-110m- Cl <LLD -<LLD 2.47E-05 <LLD 88-104 C1 <LLD <LLD <LLD <LLD Cs-136 C1 (LLD <lLD- <LLD <LLD La-140 C1 <LLD (LLD <LLD <LLD Fe-55 'Ci <LLD- <LLD 1.64E-03 4.14E-04 21dentifled- Ci <LLD (LLD <LLD <LLD Total for Period (above) C1 <LLD <LLD 2.36E-02 - 1.03E 02 Xe-133 Ct <LLD <LLD 2.74E-04 <LLD Xe-135 C1 (LLD <LLD 2.89E-04 <LLD Prepared'by k'b Approved by . b .,

Cheststry Sypervisor 9/0295c I

V \b (final)

APPROVED JUN 121989 Q,C.O.S.R.

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&lAS$ 8 inn if ill I ($l si $$1 8  !!! $1 til t or it kn 101A! IU XV $U h $! N3  !! 1014, j, 16 .05 .00 .00 .H .H .H .H .00 .11 .!! 14 .00 .05 .11 .33 .05 1.!? 1.21 1RU .H .H .H .H .H .H .H .01 .01 .14 .H .05 .06 .01 .01 .00 .61 .II I$0 .H .00 .00 .00 .05 .03 .H .H .05 .H .H .H .05 .H .11 .H .52 .52 t .0! .H .01 .05 .23 .38 .P .3 .52 .Il .H .00 .05 .47 .42 .05 1.33 1.33

!$$ .H .H .H . 0.' .H .38 .H .!I .33 .70 .H .H .14 .H .H .!) 2.43 2.43 4R5 .H .H .H .00 .H .23 .H .11 .33 .14 .H .H .0! .00 .H .00 .id .94

!$ .H .R .H .H .00 .H .00 .H .05 .H .H .H .H .00 .H .H .06 .H 1.34 (H .H .00 .H .H .H .H .05 .H .H .05 .00 .H .H .H .00 .H .09 .H 8H .H .00 .H .H .H .H .05 .00 .00 .00 .H .H .H .05 .H .H .09 .08 1$U .00 .R .H .H .H .00 .H .00 .H .14 .00 .H .00 .H .05 .H .11 .11 h .H .H .H .H .00 .H .H .33 .!) .!! .H .01 .H .H .00 .H 1.13 1:13 2$$ .H .H .00 .H .H .H .H .11 .11 .H .00 .H .00 .H .00 .H .41 .41 4X$ .H .H .H .H .M .H .H .H .H .H .H .00 .H .00 .H .H .H .H

($ .H .H .H .H .H .00 .H .00 .H .H .H .H .00 .H .00 .H .H .H 1.11 101 1.84 1.1: 5.68 5.82 8.H f.11 1.1! f 4l f.H 1.20 4.84 f.fi 2.25 3.14 8.17 1.H IH.H 15.12 6.10 1.12 30.47 21.8111.41 f 61 1H.00 ttH Otraction by Stan111ty n n! Ei iki i  !!! si $$E $ $$t $1 ISI t ut H llt 101Al 31AQlltCLA$$f5-1.74 1.21 .61 .42 .70 .Il .II 1.17 1.13 1.11 .70 47 .61 .45 1.31 1.50 15.82 intrestlyOnstable

.60 .70 .5! .14 .8) .!! .!! .33 .2) .56 .31 .09 .11 .66 .Il .19 8.10 peceratelyUnstable

.4! .47 .42 .28 .!2 .84 .28 .33 .14 .56 .23 .il .14 .05 .75 .38 5.12 $11thtlytestalt 1,81 1.f 4 1.11 2.li 2.72 3.43 1.03 1.55 1.14 2.30 1,41 1.13 .47 1.36 2.54 2.36 H 47 neutral 1.50 1.!? 1.36 1.36 2.fi 1.84 .141.551.122.301.!! .61 .!! .70 .45 1.12 21.11 $11thtly$telt

.54 .li .51 .38 . H 1.92 1.44 1.36 1.03 .il .28 .05 .19 .11 .23 41 11.41 hderately$tcle

.52 .38 .23 .38 .18 .52 .75 1.11 .H 1.13 .51 .tl .14 14 .23 .23 1,61 IntreselyStdlt tudtirecticabytind$pett n HE Xi IF i ($1 l' $$1 $ $$t $r VSt I tu a u t TOTAL IIH $PilD OLAS$15-

.H .H .H .H .00 .00 .H .00 .H .H .H .H .00 .00 .00 .H .H 0ALN

.11 .28 .23 .01 .H .19 .H .05 .H .23 .!! .14 .!) .11 .Il .05 2.63 0.1 3.5 aH

.l4 1.31 .94 .H 1.31 .45 1.27 .52 .58 1.H 1,48 .16 .15 .85 1.!? .75 15.45 3.1 1.5 sph 4.13 3.11 2.13 3.15 3.80 2.63 2.25 3.24 1.14 2.30 1.38 .10 .!! .70 1.50 2.49 15.18 f I 12.5 sH 2.49 1.81 1.?! 1.10 2.41 4.31 1.88 f.25 2.12 2.l! 1.48 1.50 .52 1.31 2.44 3.31 34.65 12.6 11.6 n h

.H .H .01 .09 .38 1.08 .14 .19 1,55 1.62 .!! .14 .38 .35 1.13 .33 1.34 18.8-24.5sH

.H .H .00 .H .H .H .16 .52 .42 .51 .00 ,09 .H .05 .H .H 1.97 > 24.5 nh L

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e Solid RadWaste Semi-Annual Report January 1992 Shipping Date

==

Carriei-

===================,

Site

====

Volume

=

Millicuries

=

01 /92 CHEM NUCLEAR SYSTEMS BARNWELL SC 205.80 14540.00 01 CHEM NUCLEAR SYSTEMS BARNWELL, SC 205.80 898.30 01 /'92 92 CHEM NUCLEAR SYSTEMS BARNWELL, SC 205.80 21640.00 01 92 KINDRICK TRUCKING OUADREX 1290.10 9.19 01 92 CHEM NUCLEAR SYSTEMS U.S. ECOLOGY, WA 349.10 8.72 01 92 RAY-TECH CHANNAHAN 622.50 28.27 01 92 CHEM NUCLEAR SYSTEMS BARNWELL, SC 120.30 53470.00 01 92 CHEM NUCLEAR SYSTEMS DARNWELL, SC 83.40 16670.00 3082.80 107264.48 O

Solid RadWaste Semi-Annual Report February 1992 Shipping Date carrier

========

Site

m==========w. ======

Volume Mil 11 curies

=== =======.

02 92 RAY-TECH CilANNAllAN 675.00 56.28 02 92 CHEM NUCLEAR SYSTEMS BARNWELL, SC 170.80 56412.00 02 92 KINDRICK ThUCKING OUADREX 1290.10 32.91 02 92 CllEM NUCLEAR SYSTEMS BARNWELL, SC 205.80 20720.00 02 92 CriEM NUCLEAH-SYSTEMS. BARNWELL SC 205.80 32660.00 03 92 CHEM NUCLEAR SYSTEMS U.S. EColhGY, WA 517.50 106.57 3065.00 109987.76 W

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Solid RadWaste Semi-Annual Report March 1992 Shipping Date Carrier Site Volume Millicuries

======== ================r=== ===== ...======= ========= =============

03 92 RAY-TECH CHANNAHAN 622.50 27.75 03 92 KINDRICK TRUCKING OUADREX 1290.10 8.39 03 92 CHEM NUCLEAR SYSTEMS BARNWELL, SC 205.80 92250.00 03 92 CHEM NUCLEAR. SYSTEMS BARNWELL SC 170.80 E94.30 03 92 CHEM HUCLEAR SYSTEMS BARNWELL SC 205.80 40180.00 03 92 CilEM NUCLEAR SYSTEMS BARNWELL SC 205.80 917.40 03 92 RAY-TECil CllANNAH 615.00 38.11 03 92 CllEM NUCLEAR SYSTEMS DARNWELL, SC 205.80 416.80 3521.00 134532.75

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Solid RadWaste Semi-Annual Report -

i

-April 1992 i

-Shipping Date

==

Carrier

========

Site

=========,

Volume Millicuries

=== =======

04 10 92 KINDRICK TRUCKING QUADREX 1350.10 23.00 04 15 92 CHEM NUCLEAR SYSTEMS BARNWELL SC 120.30 71390.00

-04 27 92 CHEM NUCLEAR SYSTEMS BARiiWELL, , SC 120.30 24110.00 lbhbI7b hbbh5Ibh i

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Solid RadWaste Semi-Annual Report May 1992 Shipping Date Carrier Site Volume Millicuries

== ==================== ======n========= ========= =======

05 06 92 CIIEM NUCLEAR SYSTEMS BARNWELL, SC 120.20 74950.00 09 07 92 RAY-TECH CHANNAHAN 630.00 44.79 05 08 92 Cl!EM NUCLEAR SYSTEMS DARNWELL, HC 205.80 384.40 OS 13 92 CHEM NUCLEAR SYSTEMS BARNWELL, SC 120.30 156600.00 05 15 92 CHEM NUCLEAR SYSTEMS BARNW%L, SC 120.30 150200.00 05 18 92 CllEM NUCLEAR SYSTEMS BARNWhLL, SC 205.80 360.90 05 30 92 Cl!EM INCLEAR SYSTEMS BARNWELL, SC 120.30 126000.00 05 38 92 KINDRICK TRUCKING QUADREX 390.00 1.29 1912.80 508541.38 W

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o Solid RadWaste Semi-Annual Report June 1992 Shipping Date Carrier Site Volune Millicuries

= =c. == =====a============== ================ =====:==== ============

06 01 92 CHEM NUCLEAR SYSTEMS BARNWELL, SC 120.30 157700.00 06 03 92 CilEM NUCLEAR SVSTEMS BARNWELL, SC 120.30 140200.00 06 10 92 CllEM NUCLEAR f 3TEMS BARNWELL SC 120.30 267100.00 06 12 92 CilEM NUCLEAR SYSTEMS U.S. ECOI.OGY, WA 105.00 471.90 06 17 92 CllEM NUCLEAR SYSTEMS DARNWELL. SC 120.30 527600.00 06 19 92 CIIEM HUCLEAR SYSTEMS D AkNWE LL ~, SC 120.30 235100.00 06 33 92 KINDRICK TRUCKING Q.UADREX 1086.50 87.86 06 24 92 CifEM NUCLEAR SYSTEMS 11ARNWELL, SC 120.30 381000.00 06 36 92 CHEM NUCLEAR SYSTEMS BARNWELL, SC 205.80 559.90 2119.10 1704819.66

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