ML20034E709
| ML20034E709 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 01/27/1993 |
| From: | Bax R COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20034E710 | List: |
| References | |
| RLB-93-024, RLB-93-24, NUDOCS 9303010229 | |
| Download: ML20034E709 (5) | |
Text
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ouad Cities Nuclear Power Station 4.,*
-- 22710 206 Avenue North i
Cordova, lilinois 61242-9740 Telephone 309/654-2241 RLB-93-024 1
January 27, 1993 i
U.S. Nuclear Regulatory Commission Document Control Desk Hashington, D.C.
20555 l
SUBJECT:
Quad Cities Station Operating Report NRC Dockets (50-254 and 50-265)
Enclosed is the radioactive Effluent Report for July through December 1992, for Quad Cities Nuclear Power Station.
A copy of this report will be furnished to the NRC Resident Inspector Sincerely, COMMONHEALTH EDISON QUAD CITIES NUCLEAR POWER STATION lEStationManager
'. L. Bax RLB/JGH/aas Enclosure i
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y EFFLi t ' AND WASTE DISPOSAL. SEMIANNUAL REPORT Supplemental Informttion facility Quad Citigg_huclear Power Statt_on Licensee Commonwealth Edison Comp.aDy i
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 C
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 mren/ 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 l
quarter.
Less than or equal to 10 mrem to any organ during any calendar-quarter, f
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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s 2.
Maximum Permissible Concentration a.,b..c.,
for fission and activation gases, iodines, and particulates with half 11ves greater than 8 days', allowable release limits l
are calculated by solving equations 10.1 and 10.2 from the Offsite Dose Calculation Manual.
The alarm setpoint is.
conservatively set at approximately 107. of the 10CFR20 limit.
d.
For 11guld effluents allowable release limits are calculated by.
l solving equations 10.3 and 10.4 from the Offsite Dose Calculation o
manual.
The MPC values used for'the monitors were as follows:
j radwaste discht.rge 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 0.624 Mev for the Third quarter and 0.676 Mev for the Fourth quarter.
4.
Measurements and Approximations of Total Radioactivity a.
Fission and Activation Gases:
b.
c.
Particulates:
The main chimney and reactor building ventilation exhaust systems are-continually monitored for lodines 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
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The calculation takes into account the i
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.
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Liquid Effluents
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The river discharge tanks are analyzed'before discharge by: gamma isotopic.
'A compostic 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 t'he l'
square root of the sum of the squares of errors for sampling and measurement parameters.
The estimated total error percent for the solid radwas+e curies is 12.3%.
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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 <tLD is reported.
5.
Batch Releases
[
a.
Liquid
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1.
number of releases 4 2.
total time 3010 minutes 3.
maximum time. 905 minutes 4.
average time 753 minutes 5.
minimum time 380 minutes 6.
average stream flow, discharge 61.9 gpm, dilution: 4.35E+05 gpm' l
b.
Gaseous NONE 6.
Abnormal Releases a.
Liquid
.t On. August 9,.1991 a leak developed on the Unit'One"B" ResidualfHeat' Removal Heat Exchanger.. Unit one wasLat full power at.this time.
The' leak vas repaired when the: Unit was' shut-down inL0ctober 1992 for_a-refueling outage. A total of 5.26E+03 uCi was released from July l',
1992'thru December 31, 1992.
This release wasfadded to the.nonthly-liquid release summ;r. for-each month.
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b.
Gaseous
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On September 15, 1992, two contractors on site became contaminated, (see R.O.R. 4 02-17), while removing some insulation from around an access cover plate on the Radwaste exhaust duct work located on the i
Radwaste building roof. The access cover plate was determined to be i
leaking and the insulation was acting as'a filter, thus becoming contaminated.
It was determined that no significant activity was released to the. environment, and this event is mentioned.here only for accuracy.
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