ML20056F843
| ML20056F843 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 08/12/1993 |
| From: | Bax R COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20056F844 | List: |
| References | |
| RLB-93-106, NUDOCS 9308310197 | |
| Download: ML20056F843 (4) | |
Text
v Commonwealth Edison Quad Cities Nuclear Power Station 22710 206 Avenue North Corcova, Illinois 61242 Telephone 309/654-2241 RLB-93-106 l
August 12. 1993 U.S. Nuclear Regulatcry Commission Document Control Desk Washington. D.C.
20555 l
SUBJECT:
Quad Cities Station Operating Report NRC Dockets (50-254 and 50-265)
Enclosed is the radioactive Effluent Report for January through June 1993. for Quad Cities Nuclear Power Station.
l A copy of this report will be furnished to the NRC Resident Inspector.
Sincerely.
COMMONWEALTH EDISDN QUAD CITIES NUCLEAR POWER STATION t
t R. L. Bax Station Manager RLB/JGW/jmk i
Enclosure i
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smcRaim3 nts 9308310197 930812 E
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EFFLUENT AND HASTE DISPOSAL SEMIANNUAL REPORT Supplemental Information Facility Qua.d_Citietliu.cle3r Power _Sta_ tion L1censee Commonwe31tlLEdhoD_ Comp 30y 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.
Beta Radiation 1.
Less than or equal to 10 mrad / quarter.
2.
Less than or equal to 20 mrad / year.
I 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.
Fcr 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.
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2.
Maximum Permissible Concentration a..b.,c.,
For fission and activation gases, lodines, and particulates j
with halflives greater than 8 days, allowable release limits i
are calculated by solving equations 10.1 and 10.2 from the I
Offsite Dose Calculation Manual.
The alarm setpoint is j
conservatively set at approximately 10% of the 10CFR20 limit.
I d.
For liquid effluents allowable release limits are calculated by solving equations 10.3 and 10.4 from the Offsite Dose Calculation i
manual.
The MPC values used for the monitors were as follows:
i radwaste discharge 1.78E-05 uC1/ml i
service water 2.0E-05 uC1/ml 3.
Average Energy The aveiage gamma energy used to calculate the alarm setpoints for the l
noble gas monitors was 0.624 Mev for the Third quarter and 0.676 Mev for i
the Fourth quarter.
l t
1 4.
Measurements and Approximations of Total Radicactivity l
i l
a.
Fission and Activation Gases:
I b.
l c.
Particulates:
i
)
1 The main chimney and reactor building ventilation exhaust. systems are l
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 l
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 j
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 j
flow at the sample point, The calculation takes into account the j
i norrnl offgas train and the gland steam contribution to the release.
The average flow at the release points are used to calculate the curies released.
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d.
Liquid Effluents-i j
The river discharge tanks are analyzed before discharge by gamma 1
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.
l 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 i
released for the discharge bay.
i 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 i
solid radwaste curies is 12.37..
f.
Less than the lower limit of detection (<LLD).
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.
l 5.
Batch Releases l
4 l
a.
Liquid j
i 1.
number of releases 10 l
2.
total time 8245 minutes l
3.
maximum time 883 minutes j
4.
average time 825 minutes 5.
minimum time 683 minutes j
6.
average stream flow, discharge 63.2 gpm, dilution 4.48E+05 gpm i
1 b.
Gaseous j
N0t'"
6.
Abnormal teleases f
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i a.
None.
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