ML20029B055

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Effluent & Waste Disposal Semiannual Rept for Jul-Dec 1991. W/910226 Ltr
ML20029B055
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 12/31/1990
From: Bax R
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9103050301
Download: ML20029B055 (21)
v • d • e


Text

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i e

's RLB-90-63 february 26, 1991 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 July through December, 1990, for Quad Cities Nuclear Power Station.

The U-1 service water monitor was out of service for 87 days from 10-30-90 to 1-25-91. The monitor was taken out of service t:) investigate the cause of some spikes on the control room chart recorder. Initial investigation was not able to pinpoint the cause. An Eberline service representative was contacted and contracted to come on-site and assist in the investigation. He suggested that we install a specific capacitor, and the spiking problem would then be rectifled. The Instrt; ment Maintenance Department p rformed this task and tested the systen. The problem did not go away. Upon further investigation, two computer boards were found to be bad. These boards were then replaced, and the problem was rectified. The required sampling was per armed during this time period to continue releases via this pathway.

A copy of this report will be furnished to the NRC Resident inspector.

Sincerely, COMMONHEALTH EDISON QUAD CITIES NUCLEAR POWER STATION f,h:.c. b~

R. L. Bax Station Manager RLB/ RAH /vmw clo3000301 911231 4 PDR ADOCK 0D00 i STMGR 50 rffA 040240 i\3

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(p . d-t- QCP 100-S25

. . - Revision 5 EFFLUENT AND WASTE DISPOSAL 1~ Ma rc h~~1989' SEMI-ANNUAL REPORT Julv-December TU91 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES PROCEDURE: QCP 100-7 l Quarter Quarter Est. Total l Unit Third Fourth Error. 1 A. FISSION & ACTIVATION GASES

1. Total Release Cl 1.68E01 1.34 E01 12.4
2. Average release rate for period uCl/see 2.11E00 1.69 E00
3. Percent of Tech Spec limit ' t.49E-02 1. 26 E-0; Chimney & stack  % i.44E-03 5.14E-04 B. IODINE
1. Total lodine-131 Cl 3.13E-03 7.67E-04 31.3 l
2. Average release rate for ostlod uCl/sec 3.94E-04 9.65E-05 C. PARTICULATES
1. Particulates with half-lives

> 8 days C1 1.11E-02 1.24E-02 16.8

2. Average release rate for period uC1/see 1.40E-0: 1.56E-0:
3. Gross aloha-radioactivity Cl (LLD <LLD **

D. TRITIUM

1. Total Release C1 2.99E01 4.17E01 6.24
2. Average release rate for period uC1/see 3.76E00 5.25E00 E. Iodine 131 & 133 Tritium and Particulates Percent of Tech spec Limit Chimney & stack 1 1.51E00 2.740-01
  • NOBLE GAS GAMMA / NOBLE GAS BETA DOSE LIMITS
    • projected value based on previous 6 months APPROVED JUN 121999 9/0295c Q.C.O.S.R.

QC# 100-S25 Revision 5 MAIN CHIMNEY GASEOUS EFFLUENTS l Continuous Mode Batch Mode Quarter Quarter Quarter Quarter Nuclides Released Unit Third Fourth

1. Fission gases Kr-85 Cl <LLD < 1.L 0 Kr-85m C1 2.56E-01 1.71E-02 Kr-87 C1 4.83E-01 4.50E-01

'Kr-88 C1 3.17E-01 2.84E-01 Xe-133 C1 1.78E00 4.COE-01 Xe-135 Cl 4.61E-01 4.23E-01 Xe-135m Cl 2.49E00 2.26E00 i

Xe-138 Cl 1.09E01 9.10E00 Ar-41 Cl 1.06E-01 2.01E-01 '

Cl i Cl Cl Total for Period Cl 1.68E01 1.15E01

2. Iodines I-131 Ci s.55E-04 6.02E-04 I-133 C1 1.62E-03 1.998-03 I-135 Cl 5 . ' '[i- 0 4 1.63E-03 Total for Period C1 2.69E-03 4.22E-03 i

APPROVED l JUN 121969 9/0295c Q.C.O.S.R.

l l .

QCP 100-525 Revision 5 MAIN CHIMNEY l GASEOUS EFFLUENTS Continuous Mode Batch Mode Quarter Quafter Quarter Quarter Nuclides Released Unit third MG ,

3. Particulates Sr-89
  • Cl 7.11E-04 1. 51 E-0 4 Sr-90
  • 5.94E-07 8.68E-07 Ci Cs-134 C1 <LLD <LLD

.CS-137 Ci <LLD <LLD Ba-140 C1 2.69E-04 1.13D-04 La-140 C1 5.66E-04 4.40E-04 Cr-51 Ci < L ::.n 1.02E-04 Mn-54 C1 <tto <LLo

- Co-58 Ci <tto <nto Co-60 C1 4.13E-05 1.13E-04 I-131 Cl <LLn 1.6sE-04 AQ-110m C1 <LLn <LLD

-unon C1 5.50E-05 1.03E-04 T173 C1 1.86E-04 8.31E-04 IJ35 C1 <LLD 1.33E-03 Fe50 Ci <LLD 1.29E-05 C1 Total for Period C1 1.83E-03 3.36E-03

  • Projected value based on last six months availabic data l

l APPROVED

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

l

_QCP 100-S35 f

Revision 5 t

REACTOR VENTILATION l

GASEOUS EFFLUENTS Continuous Mode 8atch Mode Quarter Quarter Quarter Quarter Nucildes Released Unit Third Fourth ._

l. Fission gases Kr-85 C1 (LLD <LLD Kr-85m C1 <LLD <LLD Kr-87 Ci <LLD <LLD Kr-88 Ci <LLD <LLD Xe-133 C1 <LLD <LLD Xe-135 C1 <LLD <LLD Xe-135m C1 <LLD <LLD Xe-138 Ci (LLD <LLD C1 <LLD <LLD Ci <LLD <LLD

. Total for Period C1 <LLD <LLD l .

l- 2. Iodines I-131 C1 2.57E-03 <LLD I-133 C1 1.22E-03 6.17E-05 I-135 C1 1.62E-03 (LLD Total for Period C1 5.41E-03 6.170-05 APPROVED JUN 121999 9/0295c G.C.O.S.R.

QCP 100-S25

, Revision 5 REACTOR VENTILATIOh l GASEOUS EFFLUENTS Continuous Mode Batch Mode Quarter Quarter Quarter Quarter Nuclides Released Unit Third Fourth

3. Particuls'is
  • 7.09E-06 .l.44E-05 Sr-P9 C1
  • 1.000-06 6.37E-07 Sr-90 C1 Cs-134 Cl <LLD <LLD ,

.Cs-137 Ct <LLD 6.90E-05 8a-140 CI <LLD <LLD La-140 C1 3.54E-05 <LLD Cr-51 C1 5.040-03 3.98E-03 Mn-54 C1 2.050-04 1.78E-03 Co-58 C1 1.10E-04 2.01E-04 Co-60 Ci 1.29E-03 2.19E-03 l- I-131 C1 <LLD <LLD Ag 110m Ci <LLD <LLD l 7.n65 Cl <LLD 1.87E-05 Mo99 Cl 2.I1E-03 7.83E-04 T133 Ci 3.92E-05 <LLD T135 Cl 4.31E-04 <LLD C1 <LLD <LLD Total for Period C1 9.27E-07 9.04E-03

'* Projected value based on last six months L available data APPROVED JUN 121999 9 0295c Q.C.O.S.R.

QCP 100-S25

, Revision 5 LIQUIO EFFLUENTS - SUMMATION OF ALL RELEASES Quarter Quarter Est. Total Unit 'th i rcl Fourth Error. %

A. FISSION & ACTIVATION PRODUCTS

1. Total release (not including tritium, cases, alpha) C1 3 .14 E-0 3 5.58E-03 4.4
2. Average diluted concentration durtno batch discharaesr period uC1/mi 3.62E-0! 1.47E-0!

8.85E-02 9.90E-0]

3. Percent of applicable limit *  % 4.20E-0: 4.38E-0
4. Maximum diluted concentration -

durina batch discharaes uCi/ml 3.78E-09 7.1?n-no B. TRITIUM

1. Total release Cl }.15r-01 2,42E00 6.1
2. Average diluted concentration during batch discharaes uC1/ml 1.12P-07 7.70r-01
3. Percent of applicable limit  % 4.40E-03 2.57E-0:

C. DISSOLVED AND ENTRAINED GASES

1. Total release Cl mo 6.59E-04 4.4 l 2. Average diluted concentration durino batch discharaes uC1/mi < I,t .n 1.74E-10
3. Percent of aDolicable limit  % 0.00E00 8.69F-05 D. GROSS ALPHA RADIOACTIVITY
l. Total Release C1 < I,1, n 1. 4 4 n-m 14.9
2. Average concentration released durino batch discharces uCi/mi < r,1,n s.12E-1:

E. VOLUME OF MASTE RELEASE 0 (prior to dilution Liters 1.08E 05 6.03E 05 F. VOLUME OF DILUTION HATER USED DURING BATCH DISCHARGES Liters 8.68E 08 3.79E O!

l G. TOTAL VOLUME OF OILUTION l WATER DURING PERI 00 (OUARTER) Liters 5.08E ll 2.48E 13 APPROVED

  • WHOLE B00Y/0RGAN 9/0295c JUN 121989 C' . C. O.S. R.

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

QCP 100-525

. Revlsion 5 LIQUID EFFLUENTS Continuous Mode Batch Mode Quarter Quarter Quarter Quarter Nuclides Released Unit Third Pnurth Sr-89 C1 __

<LLD <LLD 1.62E-05 2.78E-05 Sr-90 C1 <LLD <LLD 2.38E-06 5.73E-06 Cs-134 Cl <LLD <LLD <LLD <LLD Cs-137 C1 <LLD <LLD 1.62E-04 1.88E-04 I-131 Cl <LLD <LLD <LLD <LLD Co-58 Ci <LLD <LLD 1.41E-04 6.83E-05 Co-60 C1 <LLD <LLD 2.17E-03 3.41E-03 Fe-59 C1 <LLD <LLD <LLD <LLD Zn-65 Cl <LLD <LLD 2.17E-04 <LLD Mn-54 Cl <LLD <LLD 1.08E-04 6.48E-04 Cr-51 C1 <LLD <LLD 8.348-05 8.30E-04 Zr 95 C1 <LLD <LLD <LLD <LLD Nb-95 C1 <LLD <LLD <LLD <LLD

-Mo-99 Cl <LLD <LLD (LLD <LLD Ao-110m C1 <LLD <LLD <LLD <LLD Ba-104 C1 <LLD <LLD <LLD <LLD C5-136 C1 <LLD <LLD < I.r.D < ht.D La-140 C1 <LLD <LLD < f,r.D < t.I,D Fe-55

  • Ct <LLD <LLD 2.38E-04 3.75E-04 Unldentlfitd As-76 C1 <LLD <LLD <LLD 3.!7E-05 Total for Period (above) C1 <LLD e tt.D 3.14E-03 5.58E-03 Xe-133 C1 < I.L D <LLD <LLD 2.031'-04 Xe-135 C1 <LLD <LLD <LLD 4.56E-04 Prepared by bsNkD Approved by nuh b e o*_

Chemistry Supervisor p' - ' Y v.1

\.J (final) APPROVED 9/0295c

  • Scaled in value based on last six months available data.

M

EFFLUENT AND HASTE DISPOSAL SEMIANNUAL REPORT Supplemental Information Fac11ity QUAD _C111nJudur_Eower_S_tallon Licensee CornmQaweAlltLE.dl50.n_CornpAAy

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

1. Less than or equal to 5 mrad / quarter.
2. Less than or equal to 10 mrad / year Bata 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.

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

STMGR 50

2. Maximum Permissible Concentration a.,b.,c. For fission and activation gases, todines, and particulates with halfilves 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 uCl/ml

3. Average Energy The average gamma energy used to calculate the alarm setpoints for the noble gas monitors was 0.339 Mev for the Third quarter and 0.580 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 ganma isotopic every 7 days. Tritium samples are pulled and analyzed every 31 days.

The continuous strip chart recorders for the monitors on the release points are reviewed monthly for spikes and the activity released 15 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, STMGR 50

d. Liquid Effluents The river discharge tants 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 88-90 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,
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 a quarter then <LLD is reported.

5. Datch Releases
a. Liquid
1. number of releases 5
2. total time 3.02E0b .ninutes
3. maximum time 8.93E02 minutes
4. average time 6.05E02 minutes
5. minimum time 4.60E02 minutes
6. average stream flow, discharge 6.21E01 gpm, dilution 3.97E05 gpm.
b. Gaseous NONE
6. Abnormal Releases
a. Liquid NONE
b. Gaseous NONE l

l STMGR 50

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. ,_ .. . __. _ _ . _ _ _ _ -. _ . ~ . . _ . _ . .

e SOLID RADIOACTIVE HASTE

SUMMARY

UNITS 1/2 QUAD CIT.IES STATION JULY 1990 DATE CARRIER SITE VOLUML MILL 1CJRIES 07/05/90 CHEM NUCLEAR SYSTEMS BARNWELL, SC 205.80 13600.00 07/09/90 CHEM. NUCLEAR SYSTEMS- BARNWELL- SC 205.80 L4560.00 07/13/90 RAY-TECH CHANNi\ FAN 592.50 512.80 07/16/90 CHEM . NUCLEAR SYSTEMS BARNWELL, SC 205.89 34750.00 07/23/90 CHEM NUCLEAR SYSTEMS CHANNAHAN 205.80 13110.01 07/25/90 KINDRICK TRUCKING CUADREX 1011.50

...____,_._ _ _ . .64.5, 2427.20 76597.37 l

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LOLED RADIOACTIVE WASTE

SUMMARY

UNITS 1/2 QUAD CITIES STATION AUGUST 1990 DATE CARRIER SITC VOLUME MILLICQlIrd  !

- 08/06/90 CHEM NUCLEAR SYSTEMS CHANNAHAN 200.80 .2280-00 08/10/90 U.S. ECOLOGY U.S. ECOLOGY, WA 495.00 6N 87 08/13/90 CHEM NUCLEAR SYSTEMS BARNWELL, SC 205.80 12796,0t 08/20/90 CHEM NUCLEAR SYSTEMS BARNWELL, SC 205.PQ 11940.00 1112.40 37159.87 d

4 -

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(

SOLTD RADIOACTIVE WASTE

SUMMARY

UNITS 1/2 QUAD CITIES STATION SEPTEMBER 1990 DATE CARRIER SITE VOLUME MILLICURIES 09/04/90 CHEM NUCLEAR SYSTEMS BARNWELL, SC 205.80 38790.00 09/17/90 CHEM NUCLEAR SYSTEMS BARNWELL, SC 205.80 28810.00 09/24/90 CHEli NUCLEAR SYSTEMS BARNWELL, SC 205.80 21870.00 617.40 89470.00 l

k 6

. . . . . i

SOLID RADIOACTIVE WASTE

SUMMARY

UllITS 1/2 QUAD CITIES STATION OCTOBER 1990 DATE CARRIER SITE VOLUME MILLICURIES

......... ................... ....c....... .. ......... ............

10/09/90 CHEM NUCLEAR SYSTEMS BARNWLLL, SC 205.80 20360.00 10/11/90 KINDRICK TRUCKING QUADRr.X 1161.50 123.90 10/15/90 CHEM NUCLEAR SYSTEMS BARNWELL, SC 205.80 9979.00 10/24/90 Ci!EM NUCLEAR SYSTEMS BARNWELL, SC 203.80 8388.00 10/31/90 CllEM NUCLEAR SYSTEMS U.S. ECOIDGY, WA 205.80 876.78 1984.70 40327.68

i SOLID RADIOACTIVE WASTE

SUMMARY

UllITS 1/2 QUAD CITIES STATIO!1 110VEMBER 1990 DATE CARRIER SITE VOLUME MI LLICURIES 11/05/90 CHEH liUCLEAR SYSTEMS BAR!iWELL, SC 205.80 8002.00 11/09/90 RAY-TECll CilA1111AllA!1 660.00 577.60 11/19/90 CllEM liUCLEAR SYSTEMS BAR!iWE LL, SC 205.80 16620.00 11/26/90 U.S. ECOLOGY U.S. ECOLOGY, WA 474.60 760.68 11/29/90 KI!1DRICK TRUCKIliG QUADREX 1067.20 398.20 2613.40 27158.48 i

)

SOLID RADIOACTIVE WASTE

SUMMARY

UNITS 1/2 QUAD CITIES STATION DECEMBER 1990 DATE CARRIER SITE VOLUME MI LLICURI ES 12/4/90 CHEM NUCLEAR SYSTEMS BARNWELL, SC 83.40 64380.00 12/4/90 CHEM NUCLEAR SYSTEMS BARNWELL, SC 83.40 33200.00 12/6/90 KINDRICK TRUCKING QUADREX 2080.00 22.60 12/6/90 CHEM NUCLEAR SYSTEMS BARNWELL, SC 03.40 48440.00 12/13/90 CHEM HUCLEAR SYSTEMS U.S. ECOLOGY, WA 105.00 1114.59 12/17/90 RAY-TECH U.S. ECOLOGY, WA 495.00 339.71 12/20/90 CHEM NUCLEAR SYSTEMS BARNWELL, SC 205.80 67840.00 12/21/90 RAY-TECH CHANNAHAN 660.00 311.20 12/27/90 KINDRICK TRUCKING QUADREX 2000.00 2.26 12/27/90 KINDRICK TRUCKING QUADREX 1131.5') 85.83 7007.50 215736.19 h.

, i

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