ML20092L283

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Errata to Semi-Annual Effluent Rept,For Jan-Dec 1994
ML20092L283
Person / Time
Site: Braidwood  Constellation icon.png
Issue date: 12/31/1994
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20092L251 List:
References
NUDOCS 9509270133
Download: ML20092L283 (14)
v • d • e


Text

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EFFIDElff AND WASTE DISPOSAL SEMIANNUAL REPORT l

Supplemental Information January - December 1994 Facility: ERAIDWOOD NUCLEAR POWER STATION Licensee: CCamADNWEALTH EDISON CCRIPANY

1. Regulatory Limits
a. For Noble Gases:

Dose Rate

1) Less than 500 mrom/ year to the whole body.
2) Less than.3000 mrom/ year to the skin.

Dome F - tm n=d4ation

1) Less than or equal to 5 mrad / quarter.
2) Less than or equal to 10 r.r:.6/ year.

Beta nadiation

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 ~1.5 mram/ quarter.
2) Less than or equal to 15 mram/ year.
d. For Liould
1) Less than or equal to 3 mrem to the whole body during any calendar quarter.
2) Less than or equal to 10 mrom to any organ during any calendar quarter.
3) Less than or equal to 6 mrom to the whole body during any calendar year.
4) Less than or equal to 20 mrom to any organ during any calendar year.

.2. Maximum Permissible Concentration

.a., b.,c., For fission and activation gases, iodines, and particulates with half-lives greater than 8 days, allowable release

, limits are calculated by solving equations 10.1 and 10.2 from the Offsite Dose Calculation Manual.

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d. For liquid effluents, allowable release limits are calculated by solving equations 10.3 and 10.4 from the offsite Dose Calculation Manual.
3. Average Energy The average gamma energy for the Braidwood noble gas waste streams were 0.070 MeV for Unit 1 and 0.061 HbV for Unit 2. The average beta energy for Braidwood noble gas waste streams were 0.109 MeV for Unit 1 and 0.106 MeV for Unit 2.
4. Measurements and Approximations of Total Radioactivity
a. Fission and Activation Gases:
b. Iodines:
c. Particulates:

The Auxiliary Building ventilation exhaust system is continually monitored for iodines and particulates. These samples are pulled every 7 days and analyzed by gamma isotopic and gross alpha.

Noble gas and tritium glab samples are pulled and analyzed by gamma isotopic weekly.

The average flow at the release points are used to calculate the curies released.

d. Liould Effluents The liquid release tanks are analysed before discharge by gamma isotopic and tritium. A composite representative portion of this sample saved. This is composited, every 31 days, with other discharges that occurred 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. Circulating Water Blowdown, 1 Condensate Polisher Sump and Waste Water Treatment are composited quarterly and sent to a vendor for Sr-89/90 and Fe-55 analvsis. 1 The tank volumes and activities are used to calculate tt .uries released for the liquid release tanks. The total water released and the activity is used to calculate the diluted activity released at the discharge point from batch discharges.
e. 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.

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BRAIDWOOD NUCLEAR POWER STATION f SEMI-ANNUAL EFFLUENT REPORT FOR 1994  ;

LIQUID RELEASES [

UNIT I (Docket Number 50-456) .

SUMMATION OF ALL RELEASES j l Units l- 1st Qtr l 2nd Otr l 3rd Qtr l 4th Qtr l - Total l A. Fission and Activation Prodnets . ,

1. Total Activity Released Ci 2.02E-01 9.82E-02 3.80E-02 1.78E-01 5.16E 41
2. Average Concentration Released - uCi/mi 8.62E-08 2.82E-08 3.07E-08 6.30E-08 - 5.22E-08

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1. Total Activity Released Ci 1.79E+02 1.16E+02 2.20E+02 1.03E+02 6.18E+02 l 2.. Average Concentration Released uCi/ml - 7.63E-05 3.33E-05 1.<8E-04 3.65E-05 6.25E-05 l
3. % of Limit (lE-3 uCi/ml) .  % 7.63E+00 3.33E+00 1.78E+01 3.65E+00 6.25E+00  ;

C. Dissolved Noble Gases

1. Total Activity Released Ci 5.36E-02 5.74E-03 3.40E-03 1.49E-04 6.29E-02 i
2. Average Concentration Released uCi/ml 2.29E-08 1.65E-09 2.75E-09 5.28E-11 6.36E-09 ,
3. % of Limit (2E-4 uCi/ml)  % 1.15E 02 8.25E 04 1.38E-03 2.64E-05 3.18E-03

- D. Gross Alpha

1. Total Activity Released Ci 1.31E-04 <LLD <LLD <LLD 1.31 E-64
2. Average Concentration Released uCi/ml 5.60E-11 <LLD <LLD <LLD 1.32E-11 E. Volume of Releases
1. Volume of Liquid Waste to Discharg liters 4.66E+06 3.39E+06 6.03E+06 3.19E+06 1.73E+07
2. Volume of Dilution Water liters 2.34E+09 3.48E+09 1.23E+09 2.82E+09 9.87E+09 Note: LLD Values are included in Appendix A of this report.

Note: % Limit Values are included in Appendix B of this report.

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BRAIDWOOD NUCLEAR POWER STATION SEMI-ANNUAL EFFLUENT REPORT FOR 1994 LIQUID RELEASES UNIT I (Docket Number 50-456) l BATCH MODE l Units l 1st Qtr l 2nd Qtr l 3rd Qtr l 4th Qtr l Total l lNuclides From Batch Releases H3 Ci 1.79E+02 1.16E+02 2.20E+02 1.03E+02 6.18E+02 ]

Na-24 Ci 5.63E-05 <LLD <LLD <LLD 5.63E-05 1 Ar-41 Ci <LLD <LLD <LLD 8.10E-06 8.10E-06 j Cr-51 Ci 8.76E-03 1.42E-02 9.41 E-04 3.41E-02 5.80E-02 Mn-54 Ci 2.23E-03 1.14E-03 1.79E-03 1.70E-03 6.86E-03 Fe-55 Ci 4.39E-02 2.08E-02 7.81E-04 2.52E-02 9.07E-02 -l Co-57 Ci 2.02E-04 8.14E-05 8.62E-05 9.56E-05 4.65E-04 Co-58 Ci 7.52E-02 4.02E-02 1.20E-02 6.63E-02 1.94 E-01 Fe-59 Ci 1.55E-03 1.44E-03 5.61E-05 4.76E-03 7.81E-03 Co-60 Ci 1.73E-02 5.81E-03 7.66E-03 9.98E-03 4.08E-02 Ni-65 Ci <LLD <LLD <LLD <LLD <LLD Zn-65 Ci <LLD 1.38E-05 1.38E-05 8.57E-05 1.13E-04 Br-82 Ci <LLD <LLD 8.63E-06 <LLD 8.63 E-06 Kr 85 Ci 1.10E-03 <LLD 2.31E-03 <LLD 3.41 E-03 Kr-85m Ci <LLD <LLD <LLD <LLD <LLD Kr-88 Ci <LLD <LLD <LLD <LLD <LLD Sr-89 Ci <LLD 8.92E-05 <LLD <LLD 8.92 E-05 Sr-90 Ci <LLD <LLD <LLD <LLD <LLD Sr92 Ci 2.99E-05 2.19E-05 1.29E-05 7.63E-04 8.28E-04 l Nb-95 Ci 8.98E-04 2.03E-03 8.80E4)4 2.38E-03 6.19E-03 {

Zr-95 Ci 5.76E-04 1.20E-03 3.04E-04 1.53E-03 3.61 E-03 Zr-97 Ci <LLD 2.10E-04 3.56E-06 8.63E-05 3.00 E-04 Mo-99 Ci <LLD <LLD <LLD <LLD <LLD Tc 99m Ci 1.44E-05 <LLD <LLD <LLD 1.44 E-05 Ru-105 Ci 1.98E-04 <LLD 6.70E-06 <LLD 2.05E-04 Ag-110m Ci 5.52E-05 1.29E-03 3.49E-04 2.21E-03 3.90 E-03 Sn-113 Ci 1.13 E-04 1.59E-04 3.75E-05 1.65E-04 4.75E-04 Snll7m Ci <LLD 7.42E-05 <LLD 6.47E-05 1.39E-04 Sb-122 Ci 1.04E-03 <LLD 1.44E-05 2.75E-04 1.33 E-03 l

'Sb-124 Ci 3.93E-03 1.20E-03 4.00E-04 1.86E-03 7.39E-03 Sb-125 Ci 1.28E-02 6.28E-03 8.65E-03 9.28E-03 3.70E-02 Sb-126 Ci 1.20E-04 <LLD <LLD 1.40E-04 2.60E-04 1 131 Ci 3.09E-03 6.34E-04 1.82E-04 <LLD 3.91 E-03 1-132 Ci <LLD <LLD <LLD <LLD <LLD Te-132 Ci <LLD <LLD <LLD <LLD <LLD l-133 Ci 3.74E-05 1.38E-05 <LLD 1.03 E-03 1.08 E-03 Xe-133 Ci 5.21E-02 5.72E-03 1.07E-03 1.40E-04 4.90E4)2 Xe-133m Ci 2.42E-04 <LLD <LLD <LLD 2.42E-04 Cs-134 Ci 3.08E-03 3.65E-04 1.27E-03 6.05E-05 4.78E-03 Xe-135 Ci 1.42E-04 1.89E-05 1.30E-05 <LLD 1.74 E-04 1135 Ci <LLD <LLD <LLD <LLD <LLD Cs-136 Ci 3.81 E-04 <LLD <LLD 1.89E-04 5.70E-04 Cs-137 Ci 4.50E-03 7.74E-04 2.52E-03 4.02E-04 8.20E-03 Ba\La-140 Ci 3.37E-06 3.82E-05 <LLD 8.47E-05 1.26 E-04 Cc-144 Ci <LLD 4.76E-05 <LLD <LLD 4.76 E-05 Hf 181 Ci 4.68E-04 <LLD <LLD , 4.28E-05 5.11E-04 W 187 Ci <LLD 2.21E-05 <LLD l <LLD 2.21E-05 l

BRAIDWOOD NUCLEAR POWER STATION SEMI-ANNUAL EFFLUENT REPORT FOR 1994 LIQUID RELEASES j UNIT I (Docket Number 50-456)

CONTINUOUS MODE lNuclides From Continuous Releases l Units l 1st Qtr l 2nd Qtr l 3rd Qtr l 4th Qtr l Total l H-3 Ci <LLD <LLD <LLD <LLD <LLD l Na-24 Ci <LLD <LLD <LLD <LLD LLD Ar 41 Ci <LLD <LLD <LLD <LLD <LLD Cr 51' Ci <LLD <LLD <LLD <LLD <LLD Mn-54 Ci <LLD <LLD <LLD <LLD <LLD Fe-55 Ci <LLD <LLD 4.80E-05 2.55E-05 7.35E-05 l Co-57 Ci <LLD <LLD <LLD <LLD <LLD Co-58 Ci <LLD <LLD <LLD 1.53E-02 1.53E-02 Fe-59 Ci <LLD <LLD <LLD <LLD <LLD Co-60 Ci 2.22E-02 <LLD <LLD <LLD 2.22 E-02 Ni-65 Ci <LLD <LLD <LLD <LLD <LLD Zn-65 Ci <LLD <LLD <LLD <LLD <LLD Br-82 Ci <LLD <LLD <LL.D <LLD <LLD Kr 85 Ci <LLD <LLD <LLD <LLD <LLD Ci <LLD <LLD <LLD <LLD <LL,D Kr-85m Kr-88 Ci <LLD <LLD <LLD <LLD <LLD St89 Ci <LLD <LLD <LLD <LLD <LLD j Sr-90 Ci <LLD <LLD <LLD <LLD <LLD Sr-92 Ci <LLD <LLD <LLD <LLD <LLD Nb-95 Ci <LLD <LLD <LLD <LLD <LLD Zr-95 Ci <LLD <LLD <LLD <LLD <LLD Zr-97 Ci <LLD <LLD <LLD <LLD <LLD Mo-99 Ci <LLD <LLD <LLD <LLD <LLD Tc-99m Ci <LLD <LLD <LLD <LLD <LLD Ru-105 Ci <LLD <LLD <LLD <LLD <LLD Ag-llom Ci <LLD <LLD <LLD <LLD <LLD Sn-l l3 Ci <LLD <LLD <LLD <LLD <LLD Sn-ll7m Ci <LLD <LLD <LLD <LLD <LLD Sb-124 Ci <LLD <LLD <LLD <LLD <LLD l Sb-125 Ci <LLD <LLD <LLD <LLD <LLD Sb-126 Ci <LLD <LLD <l.LD <LLD <LLD l-131 Ci <LLD <LLD <LLD <LLD <LLD l132 Ci <LLD <LLD <LLD <LLD <LLD Te-132 Ci <LLD <LLD <LLD <LLD <LLD l-133 Ci <LLD <LLD <LLD <LLD <LLD Xe-133 Ci <LLD <LLD <LLD <LLD <LLD Xe-133m Ci <LLD <LLD <LLD <LLD <LLD Cs-134 Ci <LLD <LLD <LLD <LLD <LLD Xc-135 Ci <LLD <LLD <LLD <LLD <LLD l-135 Ci <LLD <LLD <LLD <LLD <LLD Cs 137 Ci <LLD <LLD <LLD <LLD <LLD Ba\La 140 Ci <LLD <LLD <LLD <LLD <LLD Cc-144 Ci <LLD <LLD <LLD <LLD <LLD Hf-181 Ci <LLD <LLD <LLD <LLD <LLD W-187 Ci <LLD <LLD <LLD <LLD <LLD I

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  • ' i BRAIDWOOD NUCLEAR POWER STATION  ;

SEMI-ANNUAL EFFLUENT REPORT FOR 1094 LIQUID RELEASES UNIT 2 (Docket Number 50-457)

SUMMATION OF ALL RELSASES l Units l 1st Qt' l 2nd Qtr l 3rd Qtr l 4th Qtr l Total l A. Fission and Activation Products

1. Total Activity Released Ci 2.02E-01 9.82E-02 3.80E 02 1.78E-01 5.16E-01
2. Average Concentration Released uCi/ml 8.62E-08 2.82E-08 3.07E-08 6.30E-08 5.22E-08 B. Tritium
1. Total Activity Released Ci 1.79E+02 1.16E+02 2.20E+02 1.03E402 6.18E+02
2. Average Concentration Rele-d uCi/ml 7.63E-05 3.33E-05 1.78E-04 3.65E-05 6.25E-05
3. % of Limit (3E-3 uCi/ml)  % 7.63E+00 3.33E+00 1.78E+01 3.65E+00 6.25E+00 C. Dissolved Noble Gases
1. Total Activity Released Ci 5.36E-02 5.74E-03 3.40E-03 1.49E-04 6.29E-02
2. Average Concentration Released uCi/ml 2.29E-08 1.65E-09 2.75E-09 5.28E-11 6.36E-09
3. % of Limit (2E-4 uCi/ml)  % 1.15E-02 8.25E-04 1.38E-03 2.64E-05 3.I8E 03 D. Gross Alpha
1. Total Activity ",, eleased Ci 1.31E-04 <LLD <LLD <LLD 1.31E-04 l
2. Average Concemration Released uCi/ml 5.60E-l I <LLD <LLD <LLD 1.32E-11  !

E. Volume of Releases

1. Volume ofl'iquid Waste to Discharge liters 4.66E+06 3.39E+06 6.03EM6 3.19E+06 1.73E+07 ,
2. Volume of Dilution Water liters 2.34E+09 3.48E409 1.23E+09 2.82E+09 9.87E+09 l F Note: LLD Values are included in Appendix A of this report.

Note: % Limit Values are included in Appendix B of this report.

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BRAIDWOOD NUCLEAR POWER STATION SEMI-ANNUAL EFFLUENT REPORT FOR 1994 LIQUID RELEASES UNIT 2 (Docket Number 50-457)

BATCH MODE lNuclides From Batch Releases l Units l lst Qtr l 2nd QE l 3rd Qtr l 4th Qtr l Total l H-3 Ci 1.79E+02 1.16E+02 2.20E+02 1.03E+02 6.18E+02 l Na-24 Ci 5.63EJ)5 <LLD <LLD <LLD 5.63E-05 Ar-41 Ci <LLD <LLD <LLD 8.10E-06 8.10E-06 Cr 51 Ci 8.76E-03 1.42E-02 9.41E-04 3.41E-02 5.80E-02 Mn-54 Ci 2.23E 03 1.14E-03 1.79E-03 1.70E-03 6.86E-03 Fe 55 Ci 4.39E-02 2.08E-02 7.8) E-04 2.52E 02 9.07E-02 l Co-57 Ci 2.02E-04 8.14E-05 8.62E-05 9.56E-05 4.65 E-04 Co-58 Ci 7.52E-02 4.02E4)2 1.20E-02 6.63E4)2 1.94 E-01 Fe-59 Ci 1.55E-03 1.44E4)3 5.61E-05 4.76E-03 7.81 E-03 Co-60 Ci 1.73E4)2 5.81 E-03 *. 66E-03 9.98E-03 4.08E-02 Ni-65 Ci <LLD <LLD <LLD <LLD <LLD Zn-65 Ci <LLD 1.38E-05 1.38E-05 8.57E4)5 1.13E-04 Br-82 Ci <LLD <LLD . ;3 E-06 <LLD 8.63E-06

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Kr-85 Ci 1.10E-03 <LLD 2.31 E-03 < LIP 3.41 E-03 Kr-85m Ci <LLD <LLD (LLD <LLD <LLD Kr-88 Ci <LLD <LLD <LLD <LLD <LLD St-89 Ci <LLD 8.92E-05 <LLD <LLD 8.92 E-05 Sr-90 Ci <LLD <LLD <LLD <LLD <LLD Sr-92 Ci 2.99E-05 2.19E 05 1.29E-05 7.63E-04 8.28 E-04 Nb-95 Ci 8.98E4)4 2.03E-03 8.80E-04 2.38E-03 6.19E-03

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Zr-95 Ci 5.76E-04 1.20E-03 3.04E-04 1.53E-03 3.61 E-03

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Zr-97 Ci <LLD 2.10F414 3.56E-06 8.63 E-05 3.00E-04 Mo-99 Ci <LLD <LLD <LLD <LLD <LLD Tc-99m Ci 1.44E-05 <LLD <LLD <LLD 1.44 E-05 Ru-105 Ci 1.98E-04 <LLD 6.70E46 <LLD 2.05E-04 Ag llom Ci _; 1.13E-04 5.52E-05 1.29E-03 3.49E-04 2.21E-03 1.65E-04 3.90E-03 4.75E-04 Sn-113 Cf . 1.59E-04 3.75E-05 Sn-117m Ci <LLD 7.42E-05 <LLD 6.47E-05 1.39E-04 Sb-122 Ci 1.04E-03 <LLD 1.44E-03 2.75E-04 1.33 E-03 l Sb-124 Ci 3.93E4)3 1.20E-03 4.00E-04 1.86E-03 7.39E-03 Sb-125 Ci 1.28E-02 6.28E-03 8.65E-03 9.28E-03 3.70E-02 Sb-126 Ci 1.20E-04 <LLD <LLD 1.40E-04 2.60E-04 I 131 Ci 3.09E-03 6.34E-04 1.82E-04 <LLD 3.91E 03 1132 Ci <LLD <LLD <LLD <LLD <LLD Te-132 Ci <LLD <LLD <LLD <LLD <LLD I-133 Ci 3.74E-05 1.38E-05 <LLD 1.03E4)3 1.08E-03 Xc-133 Ci 5.21 E-02 5.72E-03 1.07E-03 1.40E-04 5.90E-02 Xe-133m Ci 2.42E-04 <LLD <LLD <LLD 2.42E-04 Cs-134 Ci 3.08E-03 3.65E-04 1.27E-03 6.05E-05 ___ 4.78E-03 Xe-135 Ci 1.42E-04 1.89E-05 1.30E-05 <LLD 1.74 E-04 1135 Ci <LLD <tLD <LLD <LLD <LLD Cs-136 Ci 3.81 E-04 <LLD <LLD 1.80E-04 5.70E-04 Cs 137 Ci 4.50E4)3 7.74E-04 2.52E-03 4.02E-04 8.20E-03 Ba\La 140 Ci 3.37E4)6 3.82E-05 <LLD 8.47E-05 1.26E-64 Cc-144 Ci <LLD 4.76E-05 <LLD <LLD 4.76E-05 Hf-181 Ci 4.68E-04 <LLD <LLD 4.28E-05 5.11 E-04 W-187 Ci <LLD 2.21E-05 <LLD <LLD 2.21E 05 1

BRAIDWOOD NUCLEAR POWER STATION SEMI-ANNUAL EFFLUENT REPORT FOR 1994 LIQUID RELEASES UNIT 2 (Docket Number 50-457)

CONTINUOUS MODE lNuclides From Continuous Releases l Units l lst Qtr l 2nd Qtr l 3rd Qtr l 4th Qtr l Total l H-3 Ci <LLD <LLD <LLD <LLD <LLD l Na 24 Ci <LLD <LLD <LLD <LLD <LLD Ar-41 Ci <LLD <LLD <LLD <LLD <LLD '

Cr-51 Ci <LLD <LLD <LLD <LLD <LLD Mn-54 Ci <LLD <LLD <LLD <LLD <LLD Fe-55 Ci <LLD <LLD 4.30E-05 2.55E-05 7.35E-05 l Co 57 Ci <LLD <LLD <LLD <LLD <LLD Co-58 Ci <LLD <LLD <LLD 1.53E-02 1.53E-02 Fe-59 Ci <LLD <LLD <LLD <LLD <LLD Co-60 Ci 2.22E-02 <LLO <LLD <LLD 2.22 E-02 Ni-65 Ci <LLD <LLD <LLD <LLD <LLD Zn-65 Ci <LLD <LLD <LLD <LLD <LLD Br-82 Ci <LLD <LLD <LLD <LLD <LLD Kr 85 Ci <LLD <LLD <LLD <LLD <LLD Kr 85m Ci <LLD <LLD <LLD <LLD <LLD Kr 88 Ci <LLD <LLD <LLD <LLD <LLD  ;

i Sr-89 Ci <LLD <LLD <LLD <LLD <LLD Sr-90 Ci <LLD <LLD <LLD <LLD <LLD Sr-92 Ci <LLD <LLD <LLD <LLD <LLD j Nb-95 ,

Ci <LLD <LLD <LLD <LLD <LLD Zr 95 Ci <LLD <LLD <LLD <LLD <LLD Zr-97 Ci <LLD <LLD <LLD <LLD <LLD Mo-99 Ci <LLD <LLD <LLD <LLD <LLD Te-99m Ci <LLD <LLD <LLD <LLD <LLD Ru-105 Ci <LLD <LLD <LLD <LLD <LLD Ag-110m Ci <LLD <LLD <LLD <LLD <LLD Sn-113 Ci <LLD <LLD <LLD <LLD <LLD Snll7m Ci <LLD <LLD <LLD <LLD <LLD

, Sb-124 Ci <LLD <LLD <LLD <LLD <LLD 4 Sb-125 Ci <LLD <LLD <LLD <LLD <LLD Sb-126 Ci <LLD <LLD <LLD <LLD <LLD l 131 Ci <LLD <LLD <LLD <LLD <LLD I132 Ci <LLD <l_LD <LLD <LLD <LLD Te-132 Ci <LLD <LLD <LLD <LLD <LLD l-133 Ci <LLD <LLD <LLD <LLD <LLD Xe-133 Ci <LLD <LLD <LLD <LLD <LLD Xe 133m Ci <LLD <LLD <LLD <LLD <LLD Cs-134 Ci <LLD <LLD <LLD <LLD <LLD Xe 135 Ci <LLD <LLD <LLD <LLD <LLD I-135 Ci <LLD <LLD <LLD <LLD <LLD Cs-137 Ci <LLD <LLD <LLD <LLD <LLD Ba\l..a 140 Ci <LLD <LLD <LLD <LLD <LLD Cc-144 Ci t <LLD <LLD <LLD <LLD <LLD Hf-181 Ci <LLD <LLD <LLD <LLD <LLD W-187 Ci <LLD <LLD <LLD <LLD <LLD

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BRAIDWOOD NUCLEAR POWER STATION SEMI ANNUAL EFFLUENT REPORT FOR 1994 t

GAS RELEASES

, UNIT I (Docket Number 50-456)

SUMMATION OF ALL RELEASES I

l Units l 1st Qtr l 2nd Qtr l 3rd Qtr l 4th Qtr l Total l l

' A. Fission and Activation Gas Releases

1. Total Release Activity Ci 1.76E+02 5.02E+01 3.81E+00 5.10E+00 2.35E+02 i r 2. Average Release Rate uCi/sec 2.23E+01 6.37E+00 4.83E-01 6.47E 01 7.45E+00 l B. Iodine Releases i
1. Total 1-131 Activity Ci 5.89E-05 1.55E-04 9.64E-07 <LLD 2.15E-04
2. Average Release Rate uCi/sec 7.47E-06 1.97E-05 1.22E-07 <LLD 6.82E-06 l ,

C. Particulate (* 8 day half-life) Releases .

1. Gross Activity Ci <LLD <LLD <LLD <LLD <LLD  ;
2. Average Release Rcte uCi/sec <LLD <LLD <LLD <LLD <LLD
3. Gross Alpha Activity Ci 2.53E-07 4.61E-07 1.61E-07 2.16E-07 1.09E-06 D. Tritium Releases
1. Total Release Activity Ci 1.02E+00 1.22E+00 7.38E-01 4.69E+00 7.67E+00
2. Average Release Rate uCi/see 1.29E-01 1.55E 01 9.36E-02 5.95E-01 2.43E 41 l E. Sum of Iodine, Particulate (> 8 day half-life),

and Tritium Releases.

l1. Total Release Activity l Ci l 1.02E+00 l 1.22E+00 l 7.38E-01 l 4.69E+00 l 7.67E+00 l Note: LLD Values are included in Appendix A of this report.

Note: % Limit Values are included in Appendix B of this report.

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,- .- , _ _2 ti L BRAIDWOOD NUCLEAR POWER STATION i SEMI-ANNUAL EFFLUENT REPORT FOR 1994 - ,

1 . GAS RELEASES  !

UNIT I (Docket Number 50-456) l!

BATCH MODE l f l i

'l Units l 1st Qtr -l 2ndQtr 1 3rd Qtr l 4th Qtr. l Total l l

- l

(  !

A. Particulate ( > 8 day half-life) Releases  ;

I l

j . Mn 54 Ci '

O.00 1 0.00 0.00 0.00 0.00  ;

Co-58 Ci 0.00 0.00 0.00 0.00 0.00

-l Fe-59 Ci 0.00 0.00 0.00 0.00 0.00 f l

0.00 0.00 0.00 0.00 0.00 Co-60 Ci ,

Sr-89 Ci 0.00 0.00 0.00 0.00 0.00  ;

i St Ci 0.00 0.00 0.00 0.00 0.00  !

Zr-95 Ci 0.00 0.00 0.00 0.00 0.00 [

Ru 103 Ci 0.00 0.00 0.00 0.00 0.00 j

- Cs-134 Ci 0.00 0.00 0.00 0.00 0.00 j

$ Cs-137 Ci 0.00 0.00 0.00 0.00 0.00

'~

Ba\La 140 Ci 0.00 0.00 0.00 0.00 0.00 Cc 144 Ci 0.00 0.00 0.00 0.00 0.00 1 4 Others (Specify) Ci 0.00 0.00 0.00 0.00 0.00 i

! B. Tritium Releases l1. Total Release Activity l Ci l 1.01E+00 l 9.68E-02 l 4.33E-02 l 6.65E 02 l 1.22E+00 l C. Fission and Activation Gas Releases Ar-41 Ci 3.6IE-02 3.41E-02 7.29E 02 8.78E 02 2.31E-01 4 Kr-85 Ci 1.30E-01 5.89E-01 <LLD <LLD 7.19E-01 Kr-85m Ci 5.23E-01 3.16E-03 3.90E-04 <LLD 5.27E-01

[ Kr 87 Ci <LLD <LLD <LLD <LLD <LLD

! Kr-88 Ci 2.98E 01 <LLD <LLD <LLD 2.98E-01 1 Xe-131m Ci 1.88E+00 6.49E 01 3 2.14E-02 6.0$E-03 2.56E+00 Xe 133 Ci 1.44E+02 4.53E+01 2.08E400 3.76E+00 1.95E+02 Xe-133m Ci 1.95E+00 2.99E-01 1. !8E-02 2.99E-02 2.29E+00 Xe 135 Ci 6.26E+00 1.04E+00 2.33E-02 9.34E-02 7.42E+00 Xe-135m Ci <LLD <LLD <LLD <LLD <LLD

]- Xe-138 Ci <LLD <LLD <LLD <LLD <LLD

-lOthers (specify) Ci <LLD <LLD <LLD <LLD <LLD D. Iodine Releases 1-131- Ci 0.00 0.00 0.00 0.00 0.00 1-132 Ci 0.00 0.00 0.00 0.00 0.00

. 1-133 Ci 0.00 0.00 0.00 0.00 0.00 I-134 Ci 0.00 0.00 0.00 0.00 0.00 1135- Ci 0.00 0.00 0.00 0.00 0.00 Others (specify) Ci 0.00 0.00 0.09 0.00 0.00

1

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BRAIDWOOD NUCLEAR POWER STAT ON SEMI-ANNUAL EFFLUENT REPORT FOR 1994

~

GAS RELEASES UNIT I (Docket Number 50-456)

CONTINUOUS MODE l Units l 1st Qtr l 2nd Qtr l 3rd Qtr l 4th Qtr l Total l A. Particulate ( > 8 day half-life) Releases .

Mn-54 Ci <LLD <LLD <LLD <LLD <LLD Co-58 Ci <LLD <LLD <LLD <LLD <LLD Fe-59 Ci <LLD <LLD <LLD <LLD <LLD Co-60 Ci <LLD <LLD <LLD <LLD <LLD Sr-89 Ci <LLD <LLD <LLD <LLD <LLD Sr-90 Ci <LLD <LLD <LLD <LLD <LLD Zr-95 Ci <LLD <LLD <LLD <LLD <LLD Ru-103 Ci <LLD <LLD <LLD <LLD <LLD Cs-134 Ci <LLD <LLD <LLD <LLD <LLD

< <LLD <LLD <LLD Cs-137 Ci <LLD _ l.LD <LLD Ba\La-140 Ci <LLD <LLD <LLD <LLD Cc-144 Ci <LLD <LLD <LLD <LLD <LLD , 1 Others (Specify) Ci <LLD <LLD <LLD <LLD <LLD l B. Tritium Releases l1. Total Release Activity l Ci l 1.47E-02 l 1.12E+00 l 6.94E-01 l 4.62E+00 l 6.45E+00 l C. Fission and Activation Gas Releases Ar-41 Ci <LLD <LLD <LLD <LLD <LLD Kr-85 Ci <LLD <LLD <LLD <LLD <LLD Kr-85m Ci <LLD <U .D <LLD <LLD <LLD Kr-87 Ci <LLD <i.LD <LLD <LLD <LLD Kr-88 Ci <LLD <LLD <LLD <LLD <LLD Xe-131m Ci <LLD <LLD <LLD <LLD <LLD Xe-133 Ci 1.71E+01 2.32E+00 1.60E+00 1.13E+00 2.22E+01 Xe-133m Ci <LLD <LLD <LLD <LLD <LLD i Xc-135 Ci 4.14E+00 <LLD <LLD <LLD 4.14E+00 Xe-135m Ci <LLD <LLD <LLD <LLD <LLD Xe-138 Ci <LLD <LLD <LLD <LLD <LLD Others (specifv) Ci <LLD <LLD <LLD <LLD <LLD D. Iodine Releases 1-131 Ci 5.89E-05 1.55E-04 9.64E-07 <LLD 2.15E-04 1-132 Ci <LLD <LLD <LLD <LLD <LLD I133 Ci 1.82E-06 1.72E-05 <LLD <LLD 1.90E-05 I4 34 Ci <LLD <LLD <LLD <LLD <LLD I-135 Ci <LLD 1.61E-05 <LLD <LLD 1.6 t E-05 Others (sp:cify) Ci <LLD <LLD <LLD <LLD <LLD

e -

BRAIDWOOD NUCLEAR POWER S1 ATION SEMI-ANNUAL EFFLUENT REPORT FOR 1994 GAS RELEASES

UNIT 2 (Docket Number 50-457)

SUMMATION OF ALL RELEASES l Units l 1st Qtr l 2nd Qtr l 3rd Qtr l 4th Qtr l Total l A. Fission wd Activation Gas Releases

1. Total Release Activity Ci 8.30E+02 4.51E+02 1.18E+00 6.79E-01 1.28E403
2. Average Release Rate uCi/sec 1.05E+02 5.72E+01 1.50E-01 8.61E-02 4.06E+01 .l, '

B. Iodine Releases

1. Total 1-131 Activity Ci 1.75F-03 1.87E-03 8.20E-07 1.64E-05 3.64E-03
2. Average Release Rate uCi/sce 2.22E-04 2.37E-04 1.04E-07 2.08E-06 1.15E-04 l C. Particulate (> 8 day half-hfe) Releases
1. Gross Activity Ci 2.36E 12 <LLD l <LLD <LLD 2.36E-12 1
2. Average Release Ratt, uCi/sec 2.99E-13 <LLD <LLD <LLD 7.48E-14 l
j. 3. Gross Alpha Activity Ci <LLD 5.06E-07 2.42E 08 <LLD 5.30E-07 q

' 1 D. Tritium Releases

1. Total Release Activity ' 8.40E+00 6.88E+00 8.30E+00 2.68E+01 Ci 3.19E+00
2. Average Release Rate i uCi/sec 4.05E-01 1.07E+00 8.73E-01 1.05E+00 8.50E-01 l E. Sum of lodine Particulate (> 8 day half-life),

and Tritium Releases.

l1. Total Release Activity l Ci l 3.19E+00 l 8.40E+00 l 6.88E+00 l 8.30E+00 l 2.68E+01 l  ;

Note: LLD Values are included in Appendix A of this report.

Note: % Limit Values are included in Appendix B of this report.

l I

v

  • da -

' ~ , , . . . ,

BRAIDWOOD NUCLEAR POWER STATION SEMI-ANNUAL EITLUENT REPORT FOR 1%4 GAS RELEASES UNIT 2 (Docket Number 50-457)

BATCH MODE I l Units l 1st Qtr l 2nd Qtr l 3rd Qtr l 4th Otr l Total l A. Particulate ( > 8 day half-life) Releases Ci 0.00 0.00 0.00 0.00 0.00 I Mn-54

=

Co-58 Ci 0.00 0.00 0.00 0.00 0.00 Fe 59 - Ci 0.00 0.00 0.00 0.00 0.00  !

Co-60 Ci 0.00 0.00 0.00 0.00 0.00  :

Sr Ci 0.00 0.00 0.00 0.00 0.00 l Sr-90 Ci 0.00 0 00 0.00 0.00 0.00 1 Zr Ci 0.00 0.00 0.00 0.00 0.00 {

Ru 103 Ci 0.00 0.00 0.00 0.00 0.00 i Cs-134 Ci 0.00 0.00 0.00 0.00 0.00  :

Cs-137 Ci 0.00 0.00 0.00 0.00 0.00  !

Ci 0.00 0.00 0.00 0.00 0.00 Ba\La-140 -f Cc-144 Ci 0.00 0.00 0.00 0.00 0.00 l Others (Specifv)

)

l B. Tritium Releases ,

i l1. Total Release Activity l Ci l 2.7 t h-01 l 8.00EMO l 4.09E-02 l 4.81E-01 l 8.79EMO l' C. Fission and Activation Gas Releases l

Ar-41 Ci 4.63E-02 2.42E-02 6.99E-02 2.43E-02 1.65E-01 i Kr-85 Ci 1.66E+00 1.34E+00 <LLD <LLD 3.00EMO l Kr-85m Ci 9.19E 02 1.09E-01 4.71E-04 1.94E-04 2.02E-01 f Kr-87 Ci <LLD <LLD <LLD <L1D <LLD '

Kr-88 Ci 4.36E-02 5.06E 03 <LLD <LLD 4.87E-02 Xe-131m Ci 3.43E+00 5.6] E+00 2.09E-03 2.50E-04 9.04E+00

l. ,

} Xe-133 Ci 3.73E+02 3.41E+02 1.07E+00 6.40E nl 7.16EM2 j

i. Xe-133m Ci 3.38E+00 1.39E+00 1.%E 03 3.05E 03 4.78E+00 1 l

Xe-135 Ci 2.34E+03 1.14E+00 3.64E-02 1.22E-02 3.53EMO

{ <LLD Xe-135m Ci <LLD <LLD <LLD <LLD Xe-138 Ci <LLD <LLD <LLD <LLD <LLD Others (specify)-

~

l

'D. Iodine Releases f

I-131- Ci 6.23E-08 0.00 0.00 0.00 6.23FA8  !

I-132 Ci 0.00 0.00 0.00 0.00 0.00 i I I-133 Ci 1.10E 08 0.00 0.00 0.00 1.10E-08 1-134- Ci - 0.00 0.00 0.00 0.00 0.00 'l I-135 Ci 0.00 0.00 0.00 0.00 0.09 I Others (specifv) l L  ;

i

e
e' ~ c u. .

c A'.'

  • BRAIDWOOD NUCLEAR POWER STATION SEMI-ANNUAL EFFLUENT REPORT FOR 1994 GAS RELEASES UNIT 2 (Docket Number 50-457)

CONTINUOUS MODE l Units l Ist Qtr l 2nd Qtr l 3rd Qtr l 4th Qtr l Total - l A. Particulate ( > 8 day half-life) Releases ,

Mn-54 Ci <LLD- <LLD <LLD <LLD <LLD Co-58 Ci <LLD <LLD <LLD <LLD <LLD-Fe-59 Ci <LLD <LLD <LLD <LLD <LLD Co 60 Ci- <LLD <LLD <LLD <LLD <LLD Sr-89 Ci <LLD <LLD <LLD <LLD <LLD St-90 Ci 2.36E-12 <LLD <LLD <LLD 2.36E-12 Zr-95 Ci <LLD <LLD <LLD <LLD <LLD Ru-103 Ci <LLD <LLD <LLD <LLD <LLD Cs-1.14 Ci <LLD <LLD <LLD <LLD <LLD Cs-117 Ci <I I n <LLD <LLD <LLD <LLD-

~~

Ba\La-l40 Ci <LLD <LLD <LLD <LLD <LLD Cc-144 Ci <LLD <LLD <LLD <LLD <LLD Others (Specify) 2 B. Tritium Releases b l1.TotalRelease Activity l Ci l 2.92E+00 l 4.02E-01 l 6.84E+00 l 7.82E+00 l 1.80E+01 l j l

1

! C. Fission and Activation Gas Releases I

Ar-41 Ci <LLD <LLD <LLD <LLD <LLD Kr-85 Ci <LLD <LLD <LLD <LLD <LLD Kr-85m Ci <LLD <LLD <LLD <LLD <LLD Kr-87 Ci <LLD <LLD <LLD <LLD <LLD Kr-88 Ci <LLD <LLD <LLD <LLD <LLD

<LLD <LLD Xe-131m Ci <LLD <LLD <LLD

Xe-133 Ci 4.22E+02 9.75E+01 <LLD <LLD 5.20E+02 Xe-133m Ci <LLD <LLD <LLD <LLD <LLD l

Xc-135 Ci 2.40E+01 2.43E+00 <LLD <LLD 2.64E401 l

Xe-135m Ci <LLD <tLD <LLD <LLD <LLD Xe-138 Ci <LLD <LLD <LLD <LLD <LLD i Others (specifv)

  1. f I D. Iodine Releases L

1 I-131 Ci 1.75E 03 1.87E 03 8.20E 07 1.64E-05 3.64E-03 I-112 Ci 7.76E-06 <LLD <LLD <LLD 7.76E-06  ;

I-133 Ci 2.48E 04 3.88E-05 <LLD 3.05E-05 3.17E-04 j '

I-134 Ci <LLD <LLD <LLD <LLD <LLD ,

1135 - Ci <LLD <LLD <LLD <llD <LLD i Others (specify) l t, . ,

1 1  ;

.(

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