ML20072P792
| ML20072P792 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 06/30/1994 |
| From: | NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20072P786 | List: |
| References | |
| NUDOCS 9409080219 | |
| Download: ML20072P792 (9) | |
Text
_ _ _ _ _ _ _ _ _ _ _
ATTACHMENT 1 NORTHERN STATES POWER COMPANY MONTICELLO NUCLEAR GENERATING PLANT License No. DPR-22 I
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jan - Jun 1994 Supplemental Information
- 1. Regulatory Limits - Quarterly levels requiring reporting to Nuclear Regulatory Commission A.
Noble Gases :
5 mrad / quarter gamma radiation 10 mrad / quarter beta radiation B.
Long Lived Iodines, Particulates, and Tritium :
7.5 mrem / quarter dose to any organ C.
Liquid Effluents :
1.5 mrem / quarter dose to the total body 5.0 mrem / quarter dose to any organ
- 2. Maximum Permissible Concentrations A.
Noble Gases :
Table II, Column 1 B.
Long Lived Iodines, Particulates, and Tritium :
10 CFR Part 20, Appendix B, Table II, Column 1 C.
Liquid Effluents :
10 CFR Part 20, Appendix B, Table II, Column 2 2.0 E-4 uci/ml for dissul-red and entrained gases
- 3. Average Energy (Not Applicable) 9409080219 940829 PDR ADOCK 05000263 R
PDR L
Page 2
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jan - Jun 1994 Supplemental Information (continued)
- 4. Measurements and Approximations of Total Radioactivty A.
Noble Gases :
Continuous gross activity monitors in Reactor Building Vent and Plant Stack exhaust streams.
Weekly isotopic analysis of exhaust streams.
B.
Iodines in Gaseous Effluent :
Continuous monitoring with charcoal cartridges in Reactor Building Vent and Plant Stack exhaust streams with weekly analysis.
C.
Particulates in Gaseous Effluent :
Continuous monitoring with particulate filters in Reactor Building vent and Plant Stack exhaust streams with weekly analysis.
D.
Tritium in Gaseous Effluent :
Continous monitoring with silica gel cartridges in Reactor Building vent and Plant Stack exhaust streams with weekly analysis.
E.
Liquid Effluents :
Tank sample analyzed prior to each planned release and continuous monitoring of gross activity during planned release.
- 5. Batch Releases A.
Liquid :
- 1. Number of Batch Releases 0
- 2. Total Time Period for Batch Releases 0.0 min
- 3. Maximum Time Period for a Batch Release 0.0 min
- 4. Average Time Period for a Batch Release 0.0 min
- 5. Minimum Time Period for a Batch Release 0.0 min
- 6. Average River Flow During Release 0.0 cf/sec B.
Gaseous :
- 1. Number of Batch Releases 4
- 2. Total Time Period for Batch Releases 3533.0 min
- 3. Maximum Time Period for a Batch Release 1462.0 min
- 4. Average Time Period for a Batch Release 883.3 min
- 5. Minimum Time Period for a Batch Release 320.0 min
Page 3
i EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jan - Jun 1994 Supplemental Information (continued)
- 6. Abnormal Releases A.
Liquid :
1.
Number of Releases 0
- 2. Total Activity Released 0.0 Ci B.
Gaseous :
- 1. Number of Releases 1
2.
Total Activity Released 0.3 Ci
+
Page 4
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jan - Jun 1994 Table 1A Gaseous Effluents - Summation of all Releases l
l Units 1st Qtr 2nd Qtr Est. Total l
l Error, %
A.
Fission & Activation gases l
1.
Total Release Ci 1.65E+02 1.75E+02 2.00E+01 l
{
- 2. Average Release Rate uci/sec 2.12E+01 2.22E+01 l
3.
Percent Tech Spec Qtrly l
Reporting Level l
Gamma Radiation 9.36E-02 1.69E-01 l
Beta Radiation l
3.66E-02 1 5.83E-02 B.
Iodines l
1.
Total 1-131 Release Ci 2.04E-03 3.13E-03 1.00E+01 l l
- 2. Average I-131 Release Rate uci/sec 2.62E-04 3.98E-04 C.
Particulates
- 1. Total Particulates Ci 6.89E-04 6.61E-04 3.00E+01 l
- 2. Average Release Rate uci/sec 8.86E-05 8.41E-05 l
3.
Gross Alpha Radioactivity Ci 2.71E-06 8.47E-06 D.
Tritium l
1.
Total Release Ci 1.25E+01 2.54E+01 1.00E+01 l l
2.
Average Release Rate uci/sec 1.61E+00 3.23E+00 E.
Percent Qtrly Tech Spec Reporting Levels l
1.
Iodines, Particulates, l
l l
l l
and Tritium l
I 3.83E-01 l 4.41E-01 l l
l I
Page 5
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jan - Jun 1994 Table 1B Gaseous Effluents - Elevated Releases l
l l
Continuous Mode l
Batch Mode l
l Nuclides Released l Unit l 1st Otr l 2nd Otr l 1st Otr l 2nd Otr l
1.
Fission Gases l
KR-85M Ci 4.95E-01 1.47E+00 0.00E+00 0.00E+00 l
KR-87 Ci 1.64E+00 3.17E+00 0.00E+00 0.00E+00 KR-88 Ci 1.46E+00 3.93E+00 0.00E+00 0.00E+00 KR-89 Ci 2.47E+00 0.00E+00 0.00E+00 0.00E+00 XE-133 Ci 3.38E+01 3.64E+01 0.00E+00 1.83E-02 XE-133M Ci 5.53E-01 4.35E-01 0.00E+00 0.00E+00 l
XE-135 Ci 9.40E+00 1.59E+01 0.00E+00 4.87E-03 l l
XE-135M Ci 1.29E+01 9.24E+00 0.00E+00 0.00E+00 l l
XE-137 Ci 6.09E+01 5.62E+01 0.00E+00 0.00E+00 l l
XE-138 Ci 3.32E+01 2.55E+01 0.00E+00 0.00E+00 l l
AR-41 Ci 2.74E-02 1.76E-01 0.00E+00 1.08E-03 l l
l l
Total for Period Ci 1.57E+02 1.52E+02 0.00E+00 2.43E-02 l 2.
Iodines l
I-131 Ci 2.94E-04 1.37E-03 0.00E+00 3.56E-08 l l
I-133 Ci 1.73E-03 8.12E-03 0.00E+00 0.00E+06-l I-135 Ci 2.46E-03 4.72E-03 0.00E+00 0.00E+00 l
l Total for Period Ci 4.49E-03 1.42E-02 0.00E+00 3.56E-08 3.
Particulates l
MN-54 Ci 0.00E+00 5.51E-07 0.00E+00 0.00E+00 l l
CO-58 Ci 0.00E+00 9.62E-08 0.00E+00 0.00E+00 l l
CO-60 Ci 2.90E-06 6.33E-06 0.00E+00 0.00E+00 l
ZN-65 Ci 5.29E-07 7.78E-06 0.00E+00 0.00E+00 l
CS-137 Ci 2.06E-06 3.28E-06 0.00E+00 0.00E+00 l
BA-140 Ci 2.57E-04 2.09E-04 0.00E+00 0.00E+00 l
SR-89 Ci 3.69E-05 9.46E-05 0.00E+00 0.00E+00 l
SR-90 Ci 2.24E-07 4.22E-07 0.00E+00 0.00E+00 I
l Total for Period Ci 2.99E-04 3.22E-04 0.00E+00 0.00E+00 i
Page 6
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jan - Jun 1994 Table 1C Gaseous Effluents - Building Vent Releases l
l l
Continuous Mode l
Batch Mode l
l Nuclides Released l Unit l 1st Qtr l 2nd Qtr l 1st Qtr l 2nd Qtr l
1.
Fission Gases l
XE-133 l
Ci 0.00E+00 0.00E+00 0.00E+00 3.96E-02 l l
XE-135 Ci 7.07E+00 1.43E+01 0.00E+00 5.67E-02 l l
XE-135M Ci 9.50E-01 7.80E+00 0.00E+00 7.69E-03 l l
AR-41 Ci 0.00E+00 0.00E+00 0.00E+00 2.13E-02 l l
l l
Total for Period Ci 8.02E+00 2.21E+01 0.00E+00 1.25E-01 l 2.
Iodines l
I-131 Ci 1.74E-03 1.75E-03 0.00E+00 8.82E-07 l l
I-133 Ci 1.57E-02 1.40E-02 0.00E+00 0.00E+00 l l
I-135 Ci 2.71E-02 2.33E-02 0.00E+00 0.00E+00 l l
l l
Total for Period Ci 4.45E-02 3.90E-02 0.00E+00 8.82E-07 l 3.
Particulates l
MN-54 Ci 6.20E-06 3.52E-06 0.00E+00 0.00E+00 l l
CO-60 Ci
- 39E-04 1.28E-04 0.00E+00 9.58E-06 l ZN-65 Ci
'1.12E-04 1.04E-04 0.00E+00 0.00E+00 l CS-137 Ci 2.83E-05 2.84E-05 0.00E+00 0.00E+00 l
)
BA-140 Ci 1.12E-04 5.07E-05 0.00E+00 0.00E+00 l l
SR-89 Ci 1.97E-06 1.43E-05 0.00E+00 0.00E+00 l l
l Total for Period Ci 3.90E-04 3.29E-04 0.00E+00 9.58E-06 l
\\
1 a
Page 7
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jan - Jun 1994 Table 2A Liquid Effluents - Summation of all Releases l
Units l 1st Qtr 2nd Qtr lEst. Total l l
l l Error, % l A.
Fission & Activation products l
- 1. Total Release (not including l l
l l
tritium, gases, alpha)
Ci 0.00E+00 0.00E+00 0.00E+00 l l
- 2. Avg Diluted Concentration uci/ml 0.00E+00 0.00E+00 B.
Tritium l
1.
Total Release Ci 0.00E+00 0.00E+00 0.00E+00 l l
- 2. Avg Diluted Concentration uci/ml 0.00E+00 0.00E+00 C.
Dissolved and Entrained Gases l
1.
Total Release Ci 0.00E+00 0.00E+00 0.00E+00 l l
- 2. Avg Diluted Concentration
.ucl/ml 0.00E+00 0.00E+00 D.
Percent Qtrly Tech Spec Reporting Level l
- 1. Whole Body Dose 0.00E+00 0.00E+00 l
2.
Organ Dose 0.00E+00 0.00E+00 E.
Gross Alpha Radioactivity l
1.
Total Release l
Ci l 0.00E+00 l 0.00E+00 l 0.00E+00~l lF. Volume of Waste Released l
Liters { 0.00E+00 l 0.00E+00 l 0.00E+00 l lF. Volume of Dilution Water Used l Liters l 0.00E+00 l 0.00E+00 l 0.00E+00 l Table 2B Liquid Effluents l
l Continuous Mode l
Batch Mode l Nuclides Released Unit l 1st Qtr l 2nd Otr l 1st Qtr 1 2nd Qtr None Released This Period
Page 8
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jan - Jun 1994 Table 3 Solid Waste and Irradiated Fuel Shipments A.
Solid Waste Shipped Offsite for Burial or Disposal (not irradiated fuel) l 1.
Type of Waste Units l
6-month Est. Total l l
Period Error, % l l
a.
Spent resins, filter sludges, Cu. Meter 1.85E+01 l
l evaporator bottoms, etc.
Ci 1.40E+03 3.70E+01 l l
b.
Dry compressible waste, Cu. Meter 1.05E+01 l
l contaminated equipment, etc.
Ci 4.21E-01 3.50E+01 l l
- c. Irradiat'ed components, Cu. Meter 0.00E+00 l
l control rods, etc.
Ci 0.00E+00 0.00E+00 l l
- d. Other (describe)
Cu. Meter 0.00E+00 l
l l
Ci 1 0.00E+00 l 0.00E+00 l l
2.
Estimate of major nuclide composition (by type of waste) l l
Type A l
Type B Type C Type D l
l Nuclide percent percent percent percent l l
H-3 1.48E-02 2.48E-01 l
l C-14 l 1.10E-02 4.59E-02 l
l l
Cr-51 l 1.04E+00 l l
l Mn-54 l 3.12E+00 l 5.29E+00 l
l Fe-55 l 1.32E+00 l 4.83E+01 l
l l
Co-57 l 1.30E-02 l l
l l
Co-58 l 3.84E-01 l 7.07E-01 l
l l
Fe-59 l 1.89E-01 l 1.85E+00 l
l l
Ni-59 l 7.96E-03 l l
l l
Co-60 l 1.20E+01 l 2.04E+01 l
l l
Ni-63 l 1.47E-02 l 3.96E+00 l l
l l
Zn-65 l 7.69E+01 l 1.79E+01 l l
l l
Sr-89 l 4.85E-02 l 3.58E-02 l l
l l
Sr-90 l 4.92E-03 l 2.97E-02 l l
l l
Nb-94 l 1.40E-04 l l
l l
l Nb-95 l 1.89E-01 l l
l l
l Zr-95 l 2.98E-01 l l
l l
l Tr-99 l 9.38E-05 l 2.41E-05 l l
l l
Ru-103 l 1.55E-01 l l
l l
l Ru-106 l 1.37E+00 l l
l l
l Cd-109 l 3.63E-01 l
l l
l Ag110m l 6.87E-02 l
l Sb-124 l 1.89E-02 l
l Sb-125 l 8.11E-02 l
l l
I-129 l 1.57E-04 1.09E-04 l l
l I-131 1 3.45E-01 l
l l
Cs-134 l 4.67E-01 7.44E-02 l l
l Cs-137 l 8.16E-01 l 4.94E-01 l l
l l
Ba-140 l 3.86E-01 l l
l l
l La-140
. l 3.86E-01 l l
l l
Ce-141 l 8.71E-03 l l
l l
Ce-144 l 6.87E-03 l 6.64E-02 l
l Eu-154 l 1.71E-04 l l
l Eu-155 l 2.62E-04 l l
l l
Np-237 l 6.61E-06 l l
l l
Pu-238 l 2.23E-04 l 2.43E-01 l l
l Pu-239 l 8.67E-05 l 1.20E-01 l l
l l
Am-241 l 2.70E-04 l 2.88E-02 l l
l Pu-241 1 1.91E-02 l 6.49E-02 l l
l Cm-242 l 1.30E-03 l 4.39E-02 l
l Pu-242 l 4.13E-05 l 1.93E-01 l
l Cm-243 l 2.29E-04 l 8.69E-03 l l
l l
l I
l I
l
Page 9
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jan - Jun 1994 i
Table 3 Solid Waste and Irradiated Fuel Shipments 3.
Solid waste disposal l Number of l Mode of Destination l
Shipments Transportation 6
Truck Chem-Nuc Inc., Barnwell, SC.
I I
3.
Irradiated Fuel Shipments l
l
- 1. Disposition ll Number of l Mode of l
Destination l Shipments l Transportation l None This Period C. Shipping Container and Solidification Method j
No.
l Volume l Activity l Type of l Container Solidification l
M3 Ci Waste Code Code l 94-13 3.41E+00 8.03E+02 A
B D
l 94-15 l 3.41E+00 1 4.91E+02 l A
B D
94-17 l 5.83E+00 l 6.17E+01 l A
A D
94-18 l 5.83E+00 l 4.41E+01 l A.
A D
l l 94-10 l 9.10E+00 l 3.91E-01 l B
L N
I l 93-79 1.43E+00 l 2.99E-02 l B
L N
l I l l
1 l
l Container Codes :
Solidification Codes :
l L - LSA C - Cement A-Type A U - Urea Formaldehyde l
B - Type B D - Dewatering l
0 - Large Quantity N - Not Applicalble i
l I
l l
l l