ML20216B762
| ML20216B762 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 12/31/1997 |
| From: | NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20216B750 | List: |
| References | |
| NUDOCS 9803130183 | |
| Download: ML20216B762 (10) | |
Text
.
Attachment A Effluent and Waste Disposal Semi-Annual Report for July - Decen:ber 1997 l
(The attached Report contains 9 pages.)
j 2/26/98 s!s Ja\\ LICENSE \\ PERIODIC.RPT\\tFF_RPT.912 9001130183 980226 '
(DR ADOCK 05000263 PDR
NORTHERN STATES POWER COMPANY NONTICELLO NUCLEAR GENERATING PIANT License No. DPR-22 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1997 Supplemental Information
- 1. Rsgulatory 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 IOJines, 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 :
10 CFR Part 20, Appendix B, Table II, Column 1 B. Long Lived Iodines, P
' iculates, and Tritium :
10 CFR Part 20, Appen..
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 dissolved and entrained gases
- 3. Average Energy (Not Applicable)
Page 2
i EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1997 Supplemental Information (continued)
- 4. Measurements and Approximations of Total Radioactivty A. Noble Gases :
)
Continuous gross activity monitors in Reactor Building Vent and Plant l
Stack exhaust streams.
Weekly isotopic analysis of exhaust streams.
l 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 :
Weekly grab samples from Reactor Building Vent and Plant Stack exhaust streams.
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 Iain
- 6. Average River Flow During Release 0.0 cf/sec B. Gaseous :
- 1. Number of Batch Releases 3
- 2. Total Time Period for Batch Releases 1552.0 min
- 3. Maximum Time Period for a Batch Release 887.0 min
- 4. Average Time Period for a Batch Release 517.3 min
- 5. Minimum Time Period for a Batch Release 330.0 min
3 Pcga 3
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1997 f
Supplemental Information (continued) l
- 6. Abnormal Releases A. Liquid :
- 1. Number of Releases 0
- 2. Total Activity Released 0.0 Ci B. Gaseous :
- 1. Number of Releases 0
- 2. Total Activity Released 0.0 Ci
)
Page 4
f.
l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1997 Table 1A Gaseous Effluents - Summation of all Releases t
l Units 3rd Qtr l 4th Qtr lEst. Total l
l l Error. %
A. Fission & Activation gases l
1.
Total Release I
Ci I 6.60E+01 1 1.08E+02 1 2. 0 0 E+ Q1_ l l
2.
Average Release Rate I uci/sec ! 8.31E+00 1 1.35E+01 l
- 3. Percent Tech Spec Qtrly l
l l
Reporting Level l
l Gamma Radiation l
l 5.95E-02 l 8.80E-02 l
Beta Radiation I
1 1.84E-02 1 3.10E-02 l
B.
Iodines 1.
Total I-131 Release I
Ci I 7.05E-04 l 2.46E-03 l 1.00E+01 l l
2.
Averace I-131 Release Rate I uci/sec ! 8.87E-05 l 3.10E-04 l C.
Particulates l
l 1.
Total Particulates I
Ci I 3.13E-04 1 4.17E-04 1 3.00E+01 l l
2.
Average Release Rate I uci/sec I 3.93E-05 I 5.24E-05 l
3.
Gross Alpha Radioactivity i
Ci I 5.93E-06 1 1.61E-06 j
i J
l D. Tritium l
l
- 1. Total Release l
Ci I 3.59E+00 I 5.31E+00 l 1.00E+01 l l
2.
Averace Release Rate I uci/sec l 4.52E-01 l 6.68E-01 l l
E.
Percent Qtrly Tech Spec Reporting Levels l
1.
Iodines, Particulates, l
l l
l l
and Tritium 1
I 1.04E-01 1 3.61E-01 l l
Page 5
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1997 1
Table 1B Gaseous Effluents - Elevated Releases l
{
l l
Continuous Mode l
Batch Mode l
l Nuclides Released I Unit 3rd Otr 1 4th Otr I 3rd Otr i 4th Otr l
- 1. Fission Gases L
KR-85M l
Ci I 5.48E-03 1 6.24E-01 1 0.00E+00 1 0.00E+00 l KR-87 I
Ci I 7.48E-01 1 1.13E+00 1 0.00E+00 1 0.00E+00 l KR-88 I
Ci 1 0.00E+00 1 1.23E+00 1 0.00E+00 1 0.00E+00 KR-89 i
Ci l 1.41E+00 1 0.00E+00 1 0.00E+00 1 0.00E+00 l
XE-133 l
Ci i 1.33E+01 1 3.15E+01 1 0.00E+00 1 0.00E+00 1
XE-133M I
Ci I 3.09E-01 l 2.54E-01 1 0.00E+00 1 0.00E+00 l XE-135 I
Ci l 1.96E+00 l 1.03E+01 1 0.00E+00 1 0 Q0E+00 l XE-135M I
Ci I 4.35E+00 I 6.03E+00 1 0.00E+00 I atqQE+00.l
)
XE-137 i
Ci l 2.49E+01 1 3.08E+01 1 0.00E+00 1 0.00E+00 l XE-138 i
Ci l 1.30E+01 1 1.57E+01 1 0.00E+00 1 0.00E+00 l J
AR-41 1
Ci 1 0.00E+00 1 1.07E-02 1 0.00E+00 1 0.00E+00 l 1
I I
i 1
l Total for Period l Ci I 6.00E+01 1 9.76E+01 1 0.00E+00 1 0.00E+00 l 2.
Ci I 3.02E-04 I 8.22E-04 1 0.00E+00 1 0.00E+00 I-133 I
Ci l 2.69E-03 1 3.49E-03 1 0.00E+00 1 0.00E+00 I-135 i
Ci I 4.30E-03 1 5.45E-03 1 0.00E+00 1 0.00E+00 I
I I
I I
Total for Period l Ci i 7.29E-03 1 9.76E-03 1 0.00E+00 1 0.00E+00
- 3. Particulates CO-60 i
Ci I 3.73E-06 1 1.37E-06 1 0.00E+00 1 0.00E+00 l SE-75 i
Ci 1 0.00E+00 l 4.02E-08 1 0.00E+00 1 0.00E+00 l CS-137 l
Ci l 1.41E-06 1 6.89E-07 I 0.00E+00 1 0.00E+00 l BA-140 I
Ci I 7.69E-05 1 1.20E-04 1 0.00E+00 1 0.00E+00 l SR-89 I
Ci 1 3.44E-05 1 4.68E-05 1 0.00E+00 1 0.00E+00 SR-90 I
Ci I 3.07E-07 i 2.64E-07 1 0,00E+00 1 0,00E+00 I
I I
I l
Total for Period l Ci l 1.17E-04 l 1.69E-04 1 0.00E+00 1 0.00E+00
Pege 6
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1997 Table IC Gaseous Effluents - Building Vent Releases l
l l
Continuous Mode l
Batch Mode l
l Nuclides Released i Unit 1 3rd Otr I 4th Otr i 3rd Otr 1 4th Otr l
1.
Fission Gases l
XE-135 i
Ci 1 3.26E+00 1 6.53E+00 1 0.00E+00 1 0.00E+00 l l
XE-135M I
Ci 1 2.78E+00 1 3.44E+00 1 0.00E+00 1 0.00E+00 l l
AR-41 l
Ci I 0.00E+00 1 0.00E+00 1 3.70E-03 1 1.28E-03 l l
l l
l l
l l
l Total for Period l Ci I 6.04E+00 1 9.97E+00 1 3.70E-03 1 1.28E-03 l 2.
Ci I 4.03E-04 l 1.64E-03 1 0.00E+00 1 0.00E+00 I-133 I
Ci I 3.91E-03 l 1.82E-02 1 0.00E+00 1 0.00E+00 I-135 I
Ci I 3.76E-03 1 3.21E-02 1 0.00E+00 1 0.00E+00 l l
l 1
l l
j Total for Period i Ci I 8.07E-03 1 5.20E-02 1 0.00E+00 1 0.00E+00 l
- 3. Particulates l
MN-54 I
Ci 1 0.00E+00 1 1.90E-06 1 0.00E+00 1 0.00E+00 l l
CO-60 1
Ci l 1.35E-04 I 7.91E-05 1 2.40E-06 1 0.00E+00 l l
ZN-E5 l
Ci I 0.00E+00 1 2.29E-05 1 0.00E+00 1 0.00E+00 l l
CS-137 I
Ci l 4.10E-05 1 3.42E-05 1 0.00E+00 1 0.00E+00 l l
BA-140 1
Ci l 1.20E-05 1 1.05E-04 1 0.00E+00 1 0.00E+00 l l
SR-89 i
Ci 1 5.30E-06 1 4.55E-06 1 0.00E+00 1 0.00E+00 l l
SR-90 i
Ci i 1.86E-07 1 0.00E+00 1 0.00E+00 1 0.00E+00 l l
l 1
1 I
I l
l Total for Period l Ci l 1.94E-04 I 2.47E-04 l 2.40E-06 1 0.00E+00 l
Pags 7
l i
l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1997 Table 2A Liquid Effluents - Summation of all Releases j
l l
l Units 3rd Qtr 4th Qtr Est. Total l l
l 1
Error. % l A. Fission & Activation products i
- 1. Total Release (not including l l
l l
l tritium. cases, aloha) l Ci
! 0.00E+00 1 0.00E+00 1 0.00E+00 l 1
2.
Ava Diluted Concentration I uci/ml I 0.00E+00 1 0.00E+00 l B. Tritium I
I l
l 1.
Total Release i
Ci 1 0.00E+00 l 0.00E+00 1 0.00E+00 l l
2.
Ava Diluted Concentration i uci/ml I 0.00E+00 1 0.00E+00 [
C. Dissolved and Entrained Gases 1.
Total Release i
Ci I 0.00E+00 1 0.00E+00 1 0.00E+00 l 2.
Ava Diluted Concentration I uci/ml 1 0.00E+00 1 0.00E+00 l D. Percent Qtrly Tech Spec Reporting Level l
- 1. Whole Body Dose I
1 0.00E+00 1 0.00E+00 l l
2.
Orcan Dose I
1 0.00E+00 1 0.00E+00 l E. Gross Alpha Radioactivity l
- 1. Total Release i
Ci I 0.00E+00 l 0.00E+00 1 0.00E+00 l lF. Volume of Waste Released i
Liters 1 0.00E+00 1 0.00E+00 l 0.00E+00 l lF. Volume of Dilution Water Used I Liters 1 0.00E+00 1 0.00E+00 l 0.00E+00 l Table 2B Liquid Effluents i
l l
Continuous Mode Batch Mode l
l Nuclides Released Unit i 3rd Otr 1 4th Otr 3rd Otr i 4th Otr None Released This Period 1
l
F.
Page 8
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1997 Table 3' Solid Waste and Irradiated Fuel Shipments (Estimates)
A. Solid Waste Shipped Offsite for Burial or Disposal (not irradiated fuel) l
- 1. Type of Waste l
Units l
6-month lEst. Totall l
l l
Period i Error. % l
- a. Spent resins, filter sludges, Cu. Meter l 1.75E+01 l
evaDorator bottoms. etc.
Ci I 7.22E+01 3.70E+01 l
- b. Dry compressible waste, l Cu. Meter l 2.10E+00 l
contaminated eauipment, etc.
I Ci I 4.36E-02 3.50E+01 l L
- c. Irradiated components, l Cu. Meter 0.00E+00 l l
control rods, etc.
I Ci 0.00E+00 1 0.00E+00 l
- d. Other (dascribe)
Cu. Meter ] 0.00E+00 l Ci 1 0.00E+00 1 0.00E+00 l
- 2. Estimate of major nuclide composition (by type of waste) l Type A l
Type B l
Type C l
Type D Nuclide i
Dercent I percent I Dercent l Dercent l H-3 l 1.12E+00 l 1.40E-01 l C-14 l 5.72E-01 3.06E-02 ]
Mn-54 l 1.67E+00 3.70E+00 Fe-55 l 4.23E+01 5.60E+01 l
Co-57 2.74E-02 l
Co-58 2.40E-01 l
Ni-59 1.00E-02 Co-60 2.01E+01 2.52E+01 Ni-63 l 4.42E-01 6.52E-01 l
l Zn-65 9.34E+00 1.12E+01.
l l
Sr-89 1.56E+00 l
l l
l Sr-90 1.07E-01 1.81E-02 l l
l Sb-125 4.44E-02 l
l I-131 6.06E+00 l
Cs-134 l 8.39E-02 2.90E-02 l
L Cs-137 1.60E+01 2.55E+00 l
Ba-140 6.81E-03 l
La-140 3.36E-02 l
Ce-141 2.80E-01 Ce-144 1.00E-02 4.32E-02 Pu-238 1.22E-02 Pu-239 9.45E-03 Am-241 2.92E-02 l
Pu-241 l 4.00E-02 l 2.33E-01 Cm-242 l
1.10E-03 Cm-243 l
1.00E-02 I
I I
Page 9
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1997 Table 3' Solid Waste and Irradiated Fuel Shipments (Estimates)
- 3. Solid waste disposal l
Number of Mode of l
Destination l
Shioments Transportation l l
6 l
Truck l
Chem-Nuc Inc., Barnwell, SC.
j l
l B.
Irradiated Fuel Shipments
- 1. Disposition Number of l Mode of l
Destination l
Shipments l Transportation I l
None This Period C.
Shipping Container and Solidification Method No.
l Volume Activity l Type of l Container Solidification i
1 M3 Ci I
Waste I
Code Code l 97-32 l 5.83E+00 l 2.65E+01 l A
l A
D l
97-33 5.83E+00 2.11E+01 l A
l A
D l
97-35 5.83E+00 2.46E+01 l A
l A
D l
9716b l 9.63E-02 1.49E-02 l B
l L
N l
9723a l 1.97E+00 1.97E-02 l B
l L
N l
l 9716c l 2.83E-02 9.00E-03 l B
l L
N l
l l
l l
l l
Container Codes :
Solidification Codes :
L - LSA C - Cement A - Type A U - Urea Formaldehyde B - Type B D - Dewatering Q - Large Quantity N - Not Applicalble l
1