ML20100J747
| ML20100J747 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 02/23/1996 |
| From: | Pearce L COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20100J748 | List: |
| References | |
| LWP-96-012, LWP-96-12, NUDOCS 9602290239 | |
| Download: ML20100J747 (5) | |
Text
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Osmmonwcalth 1;dison Qimpany Qatad Citico Generating Station
, 22710 206th Asenne North Girdova, 11. 6124P)710 Tel.umas4 224 i LWP-96-012 February 23, 1996 U.S. Nuclear Regulatory Commission Document Control Desk Washington, 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 1995, for Quad Cities Nuclear Power Station.
Also enclosed are erratas for the January thru June 1994, July through December 1994, and January thru June 1995 Radioactive Effluent Reports.
The changes involve the percent of ODCM limit Chimney and Stack under Gaseous Effluents, page 1; section E.
In January 1996, it was discovered that the computer software was calculating dose from only one non-noble gas pathway, that being meat, since January 1, 1994. The software was corrected and the dose reports recalculated. No other values in these Radioactive Effluent Reports are affected.
In all cases, the recalculated percent of limit is less than 0.5 percent.
A copy of this report will be furnished to the NRC Resident Inspector.
Sincerely, COMMONWEALTH EUIS0N QUA041 TIES N EAR POWER STATION
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. al. Pearce Station Manager LWP/JGW/sml Enclosure 96022N02 N 96"0223
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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Supplemental Information 4
Facility Quad Cities Nuclear Power Station Ltcensee Commonwealth Edison Company l.
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.
b.,c.
For Iodine-131, for Iodine-133, and for all radionuclides in particulate form with half-lives greater than 8 days.
I 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.
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.
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i 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 4
Offsite Dose Calculation Manual. The alarm setpoint -is l
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 2.18E-06 uCi/ml
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service water 2.0E-05 uC1/ml 3.
Average Energy The average gamma energy used to calculate the alarm setpoints for the noble gas monitors was 0.705 Mev for the First quarter, and 0.673 Mev for i
the Second quarter.
4.
Measurements and Approximations of Total Radioactivity a.
Fission and Activation Gases:
b.
i 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 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.
4 The average flow at the release points are used to calculate the curies released.
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d.
Liquid Effluents The river discharge tanks are analyzed before discharge by gamma isotopic. A composite representative portion of this sample saved. This is compositeJ with other discharges that occurred every 31 days and is ana',yzed 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 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 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 a.
Liquid 1.
number of releases 15 2.
total time 13,152 minutes 3.
maximum time 960 minutes 4.
average time 877 minutes 5.
minimum time 725 minutes 6.
average stream flow, discharge 54.8 gpm, dilution 3.72E+05 gpm.
b.
Gaseous NONE STMGR\\01296.LWP
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Abnormal Releases a.
Gaseous NONE b.
Liquid On September 14, 1993, a leak was identified on the U-1 "B" RHR Heat Exchanger. Unit One was at full power at this time. The total activity released to the environment from this leak was 1.34E-05 Ci from 7/01/95 to 12/31/95, and was added to the monthly liquid release summary for each month.
In this report, the activity is reported under the " Continuous Liquid Release" column.
This leak is scheduled for repair during early 1996.
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