ML20196K584

From kanterella
Revision as of 20:58, 15 December 2020 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Effluent & Waste Disposal Semi-Annual Rept for Period Jan-Dec 1998
ML20196K584
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 12/31/1998
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20196K582 List:
References
NUDOCS 9904020141
Download: ML20196K584 (16)
v • d • e


Text

r

)

QCCP 0100-16 UNIT 1(2)

REVISION 4 ATTACHMENT A (Page 1 of 5)

EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT l

GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Period: July through December 1998 Third Fourth Est. Total l A. FISSION & ACTIVATION GASES UNIT QUARTER QUARTER Error % 1

1. Total Release Ci 1.55E+01 1.41E+01 32.4 l l
2. Average release rate for the period gCi/sec 1.95E00 1.77E00 i 4
3.
  • Percent of ODCM limit Chimney &  % 6.37E-03 6.11E-03 I Stack l2.95E-04 2.82E-04 B. IODINE
1. Total Iodine-131 C1 7.09E-04 7.98E-04 40.0
2. Average release rate for the period pCi/sec 8.92E-05 1.00E-04 C. PARTICULATES
1. Particulates with half-lives >B days Ci 2.62E-03 6.16E-03 30.1
2. Average release rate for the period gCi/sec 3.30E-04 7.75E-04
3. Gross alpha radioactivity Ci 1.92E-06 <LLD D. TRITIUM
1. Total Release Ci 2.73E+01 2.09E+01 8.0
2. Average release rate for the period pCi/sec 3.43E00 2.63E00 E. Iodine 131 & 133, Tritium & Particulate
1. Percent of ODCM limit Chimney & Stack  % 4.05E-01 1.77E-01 NOBLE GAS GAMMA / NOBLE GAS BETA DOSE LIMITS i 1

9904020141 990330 PDR ADOCK 05000254:

h R PDR w l Document Retention: Life of Plant 14

QCCP 0100-16 UNIT 1(2)

REVISION 4 ATTACHMENT A (Page 2 of 5)

EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT MAIN CHIMNEY CASECUS EFFLUENTS CONTINUOUS MODE BATCH MODE NUCLTDES RELEASED THIRD FOURTH THIRD FOURTH

1. Fission gases UNIT QUARTER QUARTER QUARTER QUARTER Kr 85 Ci <LLD <LLD NA NA Kr-85m Cl 2.86E-01 3.66E-01 NA NA Kr-87 Cl 5.88E-01 5.76E-01 NA NA Kr-88 Ci 4.45E-01 5.63E-01 NA NA Xe-133 Ci 5.26E-01 2.18E-01 NA NA Xe-135 Ci 4.81E-01 8.47E-01 NA NA re-135m C1 2.52E00 2.14E00 NA NA Xe-138 Cl 1.04E+01 8.63E00 NA NA Ar-41 2.40E-01 7.49E-01 NA NA Total for Period Cl 1.55E+01 1.41E+01 m m Mmmmm NUCLIDES RELEASED THIRD FOURTH THIRD FOURTH
2. Iodines UNIT QUARTER QUARTER QUARTER QUARTER I-131 Ci 6.90E-04 6.78E-04 NA NA l-133 C1 4.07E-03 2.28E-03 NA NA l-135 Cl 1.08E-03 1.15E-03 NA NA Total for period Ci 5.84E-03 4.11E-03 m m mmmmmm NUCLIDES RELEASED THIRD FOURTH THIRD FOURIP
3. Particulates UNIT QUARTER QUARTEP QUARTER QUARTER Sr 89 Cl 1.57E-04 9.53E-05 NA NA Sr-90 Cl <LLD <LLD NA NA Cs-134 Ci <LLD <LLD NA NA Cs-137 Ci <LLD <LLD NA NA Ba-140 Cl 1.09E-04 (LLD NA NA La-140 Cl 3.22E-05 <LLD NA NA cr-51 Ci <LLD <LLD NA NA Mn-54 Ci <LLD <LLD NA NA Co-58 Ci <tLD <LLr NA NA Co-60 Cl 1.12E-04 2.01E-04 NA NA Mo-99 Ci <LLD <LLD NA NA Ag-110m Cl 1.35E-05 <LLD NA NA 1 131 Ci <LLD <LLD NA NA I 133 Cl 1.96E-04 1.42E-04 NA NA Total for Pericd Cl 6.20E-04 4.38E-04 m M 15

r QCCP 0100-16 UNIT 1(2)

REVISION 4 ATTACHMENT A (Page 3 of 5)

EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT REACTOR VENTILATION GASEOUS EFFLUENTS CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED THIRD FOURTH THIRD FOURTH

1. Fission gases UNIT QUARTER QUARTER QUARTER QUARTER Kr-85 Ci <LLD <LLD NA NA l

kr-85m Ci <LLD <LLD NA NA Kr-87 Ci <LLD <LLD NA NA Kf-88 Ci <LLD <LLD NA NA Xe-133 Ci <LLD <LLD NA NA l

Xe-135 Ci <LLD <LLD NA NA Xe-135m Ci (LLD <LLD NA NA ,

I Xe-138 Ci <LLD <LLD NA NA AR-41 <LLD <LLD hA NA Total for Period Ci <t LD <LLD M M NUCLIDES RELEASED THIRD QUARTER THIRD FOURTH

2. Iodines UNIT QUARTER QUARTER QUARTER QUARTER I-131 Cl 1.91E-05 1.20E-04 NA NA I-133 Cl 5.97E-04 1.38E-04 NA NA I-135 Ci <LLD <LLD NA NA Total for period C1 6.16E-04 2.58E-04 m m

_7.. ,

.... . ;_ . .. .. ._.__.~._.;

NUCLIDES RELEASED THIRD FOURTH THIRD FOURTH

3. Particulates UNIT QUARTER QUARTER QUARTER QUARTER Sr-89 Ci 8.49E-06 2.38E-05 NA NA Sr-90 Ci <LLD <LLD NA NA Cs-134 Ci <LLD <LLD NA NA l

Cs-137 Ci 8.08E-06 3.49E-05 NA NA l Zn-65 Ci <LLD 7.75E-05 NA NA La-140 Ci 6.07E-05 1.61E-05 NA NA Cr-51 C1 3.77E-04 1.88E-03 NA NA l Mn-54 C1 1.34E-04 3.77E-04 NA NA Co-58 Ci 1.52E-04 3.76E-04 NA hA Co-60 Cl 7.08E-04 1.93E-03 NA NA Mo-99 Ci 5.47E-04 1.01E-03 NA NA

  1. g-110m Ci sLLD <LLO NA NA I-131 C1 <LLD <LLD NA NA l I-133 Cf <LLD <LLD NA NA Total for Period Cl 2.00E-03 5.72E-03 m M 16

QCCP 0100-16 UNIT 1(2)

REVISION 4 ATTACHMENT A (Page 4 of 5)

EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES THIRD FOURTH Est. Total A. FISSION & ACTIVATION GASES UNIT QUARTER QUARTER Error %

1. Total Release (not including tritium, Ci 3.33E-03 5.93E-03 5.6 gases & alpha) ,
2. Average diluted concentration during pCi/mL 1.94E-10 4.52E-10 batch discharges for the period
3. Percent of applicable limit *  % 5.03E-03 2.51E-03 2.08E-03 1.06E-03
4. Maximum diluted concentration during pCi/mL 4 54E-10 1.95E-09 batch discharges B. TRITIUM
1. Total Release Ci 7.94E00 8.23E00 4.0
2. Average diluted concentration during pCi/mL 4.64E-07 6.38E-07 batch discharges for the period
3. Percent of applicable limit  % 1.55E-02 2.13E-02 C. DISSOLVED & ENTRAINED GASES
1. Total Release Ci 5.15E-04 3.43E-04 5.6
2. Average diluted concentration during pCi/mL 3.01E-11 2.66E-11 batch discharges for the period
3. Percent of applicable limit t 1.51E-05 1.33E-05 D. GROSS ALPHA ACTIVITY l
1. Total Release Ci <LLD <LLD NA
2. Average diluted concentration during pCi/mL <LLD <LLD batch discharges for the period
r. . --..- _.= n_-

.  ::--.2r ==r: ===c issugg!!sagenes ==_ z emm z E. VOLUME OF WASTE RELEASED (prior to Liters 1.66+06 1.99E+06 dilution)

F. VOLUME OF DILUTION WATER USED Liters 1.71E+10 1.29E+10 DURING BATCH DISCHARGES G. TOTAL VOLUME OF DILUTION Liters 4.96E+11 3.54E+11 WATER USED DURING PERIOD (quarter)

  • Whole Body / Organ (ODCM) l l

l l

i I

QCCP 0100-16 UNIT 1(2)

REVISION 4 ATTACHMENT A (Page 5 of 5)

EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE THIRD FOURTH THIRD FOURTH NUCLIDES RELEASED UNIT QUARTER QUARTER QUARTER QUARTER Sr-89 Ci <LLD <LLD <LLD <LLD Sr-90 Ci <LLD <LLD <LLD <LLD Cs-134 Ci <LLD <LLD 9.99E-05 <LLD Cs-137 Ci <LLD <LLD 9.03E-04 4.21E-04 I-131 Ci <LLD <LLD 3.24E-05 <LLD Co-60 Ci <LLD 2.51E-06* 1.58E-03 2.45E-03 Co-58 Ci <LLD <LLD <LLD 9.52E-05 Fe-59 Ci <LLD <LLD <LLD <LLD Zn-65 Ci <LLD <LLD <LLD <LLD Mn-54 Ci <LLD <LLD 6.43E-05 3.21E-04 Cr-51 Ci <LLD <LLD <LLD 1.83E-03 Zr-95 Ci <LLD <LLD <LLD <LLD Nb-95 Ci <LLD <LLD <LLD <LLD Mo-99 Ci <LLD <LLD <LLD <LLD Ag-110m Ci <Lt.D <LLD <LLD 1.85E-05 Ba-140 Ci <LLD <LLD <LLD <LLD La-140 Ci <LLD <LLD <LLD <LLD Fe-55 Ci <LLD <LLD 5.13E-04 4.71E-07 I-133 Ci <LLD <LLD 1.91E-05 <LLD l As-76 Ci <LLD <LLD 6.56E-05 <LLD Sb-122 Ci <LLD <LLD 2.06E-05 <LLD Sb-124 Ci <LLD <LLD <LLD 5.56E-04 Sb-125 Ci <LLD <LLD 3.47E-05 1.34E-04

! Total for Period Ci <LLD 2.51E-06 3.33E-03 5.83E-03 (above)

Xe-133 Ci <LLD <LLD 2.30E-04 2.31E-04 Xe-135 Ci <LLD <LLD ,

2.85E-04 1.12E-04

=See " Abnormal fieleases" section.

Prepared by: 21 0 " :-

v Date: 3 k2-6 k Y Approved by: om Date: i$ l 18

I Attachment C Quad Cities Station Meteorological Site Quarterly Joint-Frequency Wind Rose Tables for 1998 SVP-99-064 i

l l

r I

I

p i

=

l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL' REPORT l

_ Supplemental Information l

[ ' Facility 'Ouad Cities Nuclear Power Station January - June 1998 Licensee -Commonwealth Edison Comoany

1. Regulatory Limits l a. For Noble Gases:
i Dose rate
1. Less than 50C mrem / year to the whole body
2. Less than 3000 mrem / year to the skin.

l L

Dose Gamma Radiation

1. .Less than or equal to 5 mrad / quarter.

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.

l L 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 l

' Dose

1. Less than or equal to 7.5 mrem / quarter
2. Less than or equal:to 15 mrem / year-.

l

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

l-

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

quarter;

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

.Less than or equal to 20-mrem to any organ during any calendar l; year. i I

l.

l: 1 L cuemsawarr l-t

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

d. For liquid effluents allowable release limits are calculated by 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 4.60E-05 uCi/ml service water 1.0E-05 uC1/ml

3. Average Energy The average gamma energy used to calculate the alarm setpoints for the noble' gas monitors was 0.660 Mev for the First quarter, and 0.553 Mev for the Second quarter.
4. ' Measurements and Approximations of Total Radioactivity
a. ' Fission and Activation ;ses:
b. Iodines:
c. Particulates: 1 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 al)ha analysis. Noble gas grab samples are pulled and analyzed )y gamma isotopic weekly. Tritium samples are pulled and analyzed every month.

l The Sr89/90 and gross alpha curies released values reported are actual. The portion of the " percent of applicable limit" for these contributors is reported based on projections that are used

, in the monthly 00CM calculations. The actual results are not '

! available when the ODCM calculations are performed.

The continuous strip chart recorders for the monitors on the release points are reviewed monthly for spikes and the activity i 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 I

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.

CHBCE&WRFT

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 alphc. 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 1 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 diluted activity released at the discharge bay, from batch discharges.

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 j measurement parameters. The estimated total error percent for the solid waste radwaste curies is 12.3%.
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 l
a. Licpid
1. number of releases 36
2. total time 38,244 minutes  !
3. maximum time 1,203 minutes '
4. average time 1.062 minutes
5. minimum time 695 minutes
6. average stream flow, discharge 48.8 gpm,
dilution 1.79E+05 gpm.
b. Gaseous  ;

NONE m

l i

l

6. Abnormal Relea :s
a. Gaseous
1. A vendor purchased gas standard was used to calibrate the main chimney noble gas monitors since there was not offgas available (both units were shutdown). This vendor purchased  !

gas included Kr85 Xe-127 and Xe-133. The Xe-127 was released into a laboratory fume hood, and ultimately through the main chimney. This release (5.0E-05 ci) was included in the monthly release summary. It is also included in this report,

b. Liquid NONE i

3 l

l 1

l l

i l

l CHEM \EAWRPT

QCCP 0100-16 l UNIT 1(2)

REVISION 4 ATTACHMENT A (Page 1 of 5)

EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Period: January through June 1998 First Second Est. Total A. FISSION & ACTIVATION GASES UNIT OUARTER QUARTER Error t

1. Total Release Ci <LLD 5.15E00 12.4 l
2. Average release rate for the period pCi/sec <LLD 6.55E-01
3.
  • Percent of ODCM limit Chimney & t NA 2.15E-03 Stack NA 9.84E-05 B. IODINE
1. Total Iodine-131 Ci <LLD 1.88E-04 40.0
2. Average release rate for the period pCi/sec <LLD 2.39E-05 l

C. PARTICULATES l 1. Particulates with half-lives >8 days Ci 5.21E-04 9.67E-04 30.1

2. Average release rate for the period pCi/sec 6.70E-05 1.23E-04

, 3. Gross alpha radioactivity Ci 4.73E-07 5.93E-05 l

D. TRITIUM

1. Total Release Ci 2.30E00 7.80E00 8.1
2. Average release rate for the period pCi/sec 2.96E-01 9.92E-01 E. Iodine 131 & 133, Tritium & Particulate I 1. Percent of ODCM limit Chimney & Stack i 2.31E-02 1.26E-01 NOBLE GAS GAMMA / NOBLE GAS BETA DOSE LIMITS I

Document Retention: Life of Plant I

14

~

QCCP 0100-16 l l UNIT 1(2) l l REVISION 4 ATTACHMENT A (Page 2 of 5) l EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT MAIN CHIMNEY CASE 005 EFFLUENTS CONTINUOUS MODE BATCH MODE KUCLIDES RELEASED FIRST SECOND

1. Fission gases UNIT QUARTER QUARTER QUARTER CrJARTER l Kr-85 Ci <LLD 5.03E-03 NA NA Kr-85m Ci <LLD 1.31E-01 NA NA Kr-87 Ci <LLD 1.86E-01 'NA NA Kr-88 Ci <LLD 1.54E-01 NA NA j

Xe-133 Ci <LLD 1.62E-01 NA NA Xe-135 Ci <LLD 2.2SE-01 NA NA Xe-135m Ci <LLD 7.56E-01 NA NA Xe-138 Ci <LLD 3.15EDO NA NA 1

Ar-41 <LLD 3.76E-01 NA NA Xe-127** Ci <LLD 5.00E-05 NA NA Total for Period Ci <t.LD 5.15E00 NA NA m .

NUCl.1 DES F fD FIRST SECOND

2. todines UNIT QUARTER QUARTER QUARTER QUARTER I-11. ,

Cl <LLD 1.88E-04 NA NA I-133 Ci <LLD 9.90E-04 NA NA I

I-135 Ci <LLD <LLD NA NA i Total for period Ci <LLD 1.18E-03 MA NA MMMMM 1 NUCLIDES RELEASED FIRST SECOND

3. Particulates UNIT QUARTER QUARTER QUARTER QUARTER Sr-89 Ci <LLD 7.64E-05 NA NA Sr-90 Ci <LLD <LLD NA NA Cs-134 Ci <LLD <LLD WA NA Cs-137 Ci <LLD <LLD NA NA Ba-140 Ci <LLD <LLD NA NA La-140 Ci <LLD 2.78E-05 NA NA Cr-51 Ci <tLD 5.02E-05 NA NA Mn-54 Ci <LLD <LLD NA NA Co-58 Ci <tLD <LLD NA NA Co-60 Cl 6.83E-05 1.14E-04 NA NA l Mo-99 Ci <LLD <LLD NA NA Ag-110m Ci <LLD 1.69E-05 NA NA I-131 Ci <LLD <llD NA NA I-133 Ci <LLD <LLD NA NA I Total for Period Ci 6.80E-05 2.85E-04 MA NA
    • SEE
  • ABNORMAL RELEASES" IN SUPPLEMEl.1AL INFORMATION SECTION.

15

. QCCP 0100-16 UNIT 1(2)

REVISION 4 ATTACHMENT A (Page 3 of 5)

EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT REACTOR VENTILATION GASEOUS EFFLUENTS CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED FIRST SECOND

1. Fission gases UNIT QUARTER QUARTER QUARTER QUARTER Kr-85 Ci <tLD <tLD NA NA Kr-85m Ci <LLD <LLD NA NA Kr-87 Ci <LLD <LLD NA NA Kr-88 Ci (LLD <LLD NA NA 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 AR-41 <LLD <LLD NA Wa total for Period Ci <LLD <LLD E E NUCLIDES RELEASED FIRST SECOND
2. Iodines UNIT QUARTER QUARTER QUARTEN QUARTER I-131 Ci <LLD <LLD NA NA I 133 Ci <L LD <tLD NA NA I-135 Ci <LLD <LLD NA NA Total for period Ci <LIA <tLD E E m  : - -- - . m - .m 2. - m3--

NUCLIDES RELEASED FIRST SEC00

3. Particulates UNIT QUARTER QUARTER QUAPTER QUARTER Sr-89 Ci <LLD <LLD NA NA Sr-90 Ci <LLD <LLD NA NA Cs-134 Ci <LtD <LLD NA NA Cs-137 C1 4.53E-06 9.41E-06 NA NA Be-140 Ci <tLD <LLD NA NA La 140 Ci <tLD <LLD NA NA Cr-51 Ci <LLD (LLD WA NA Mn-54 Ci 8.50E-06 (LLD NA NA Co-58 Ci <LLD <LLD NA NA Co-60 C1 4.40E-04 6.73E-04 NA NA Mo-99 Ci <LLD <LLD NA NA Ag-110m Ci <LLD <LLD WA NA 1-131 Ci <LLD <LLD NA NA 1-133 Ci <LLD <LLD NA NA l Total for Period Ci 4.53E-04 6.82E-04 m M 1

16 '

l l

r j .

QCCP 0100-16 UNIT 1(2)

REVISION 4 l ATTACHMENT A (Page 4 of 5)

EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES FIRST SECOND Est. Total A. FISSION & ACTIVATION GASES UNIT QUARTER QUARTER Error %

1. Total Release (not including tritium, Ci 1.38E-02 1.09E-02 5.6 gases & alpha)
2. Average diluted concentration during yCi/mL 1.15E-09 7.62E-10 batch discharges for the period
3. Percent of applicable limit *  % 2.48E-02 1.92E-02 1.07E-02 1.06E-02
4. Maximum diluted concentration during pCi/mL 6.88E-09 2.86E-09 batch discharges B. TRITIUM
1. Total Release Ci 2.48E+01 7.47E00 4.1
2. Average diluted concentration during pCi/mL 2.07E-06 5.22E-07 batch discharges for the period
3. Percent of applicable limit  % 6.89E-02 1.70E-02 C. DISSOLVED & ENTRAINED GASES
1. Total Release Ci <LLD 6.21E-06 5.6
2. Average diluted concentration during pCi/mL <LLD 4.34E-13 i batch discharges for the period i
3. Percent of applicable limit  % NA 2.17E-07 D. GROSS ALPHA ACTIVITY
1. Total Release Ci <LLD <LLD NA
2. Average diluted concentration during pCi/mL <LLD <LLD batch discharges for the period E. VOLUME OF WASTE RELEASED (prior to Liters 4.66E+06 2.40E+06 dilution)

F. VOLUME OF DILUTION WATER USED Liters 1.20E+10 1.43E+10 DURING BATCH DISCHARGES G. TOTAL VOLUME OF DILUTION Liters 2.17E+11 2.94E+11 WATER USED DURING PERIOD (quarter)

  • Whole Body / Organ (ODCM) 1 L

17

II

a QCCP 0100-16 l UNIT 1(2)

REVISION 4 ATTACHMENT A (Page 5 of 5)

EFFLUENT & WASTE DISPOSAL SEMI-ANNUAL REPORT LIQUID EFFLUENTS CONTINUOUS MODE BATCH NODE

=

FIRST SECOND FIRST SEL NUCLIDES RELEASED UNIT QUARTER QUARTER OUARTER QUARTt.,<

Sr-89 Ci <LLD <LLD <LLD <LLD Sr-90 Ci <LLD <LLD <LLD <LLD Cs-134 Ci <LLD <LLD <LLD <LLD Cs-137 Ci <LLD <LLD 5.60E-03 5.66E -03 i I-131 Ci xLLD <LLD <LLD <LLD Co-60 Ci <LLD <LLD 5.94E-03 3.30E-03 Co-58 Ci <LLD <LLD 2.98E-05 <LLD Fe-59 Ci <LLD. <LLD <LLD <LLD Zn-65 Ci <LLD <LLD 6.61E-05 <LLD Mn-54 Ci <LLD <LLD 8.62E-04 7.93E-04 Cr-51 Ci <LLD _

<LLD 2.67E-04 <LLD Zr-95 Ci <LLD <LLD  ?.29E-05 <LLD Nb-95 Ci <LLD <LLD 3.10E-05 <LLD Mo-99 Ci <LLD <LLD <LLD <LLD Ag-110m Ci <LLD <LLD 2.59E-05 <LLD Ba-140 Ci <LLD <LLD <LLD <LLD La-140 Ci <LLD <LLD <LLD <LLD Fe-55 Ci <LLD <LLD 8.94E-04 1.17E-03 Unidentified Ci <LLD <LLD <LLD <LLD Sb-124 Ci <LLD <LLD 9.72E-06 <LLD Sb-125 Ci <LLD <LLD 2.71E-05 <LLD Total for Period Ci <LLD <LLD 1.38E-02 1.09E-02 (above)

Xe-133 Ci <LLD <LLD <LLD <LLD Xe-135 Ci <LLD <LLD <LLD 6.21E-06 i

Prepared by: D' ,- Date: '> ) W \ 3 3 Approved by: L . Date:  !#T5 18 j

Attachment E QCAP 0280-01, Revision 3, Process Control Program for Process *ng of Radioactive Wet Wastes at Quad Cities Nuclear Power Statica SVP-99-064 l

f l

i ,

j

!

Retrieved from "https://kanterella.com/w/index.php?title=ML20196K584&oldid=3038450"