ML20135E654

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Effluent & Waste Disposal Semi-Annual Rept for Period Jul- Dec 1996
ML20135E654
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 12/31/1996
From:
NORTHERN STATES POWER CO.
To:
Shared Package
ML20135E653 List:
References
NUDOCS 9703100082
Download: ML20135E654 (10)
v • d • e


Text

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i Attachment A i

l Effluent and Waste Disposal Semi-Annual Report, l j Period July-December 1996 l 1 l i ,

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! (The attached Report contains 9 pages.)

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1 9703100082 DR 970228 ADOCK 05000263 PDR

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NORTHERN STATES POWER COMPANY MONTICELLO NUCLEAR GENERATING PLANT

, , License No. DPR-22 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1996 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 :  :

10 CFR Part 20, Appendix B, 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 dissolved and entrained gases

3. Average Energy (Not Applicable)

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'r g, 7. Page 2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

. , Period : Jul - Dec 1996 l l

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Supplemental Information (continued) I i

4. Measurements and Approximations of Total Radioactivty i l

I 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 :

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 Relear et A. Liquid :
1. Number of Batch Releases 0 2.'iotal 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 I

B. Gaseous : i

?. . Number of Batch Releases 2 ,

2. Total Time Period for Batch Releases 1555.0 min '
3. Maximum Time Period for a Batch Release 1156.0 min
4. Average Time Period for a Batch Release 777.5 min
5. Minimum Time Period for a Batch Release 399.0 min

,., 1 Page 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

. Period : Jul - Dec 1996 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 0
2. Total Activity Released 0.0 Ci

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,., 1 Page 4 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

. Period : Jul - Dec 1996 l Table 1A Gaseous Effluents - Summation of all Releases Units 3rd Qtr 4th Qtr Est. Total Error. %

A. Fission & Activation gases

1. Total Release Ci 9.42E+01 1.39E+02 2.00E+0i[l ,
2. Averace Release Rate uci/sec 1.18E+01 1.74E+01 i
3. Percent Tech Spec Qtrly Reporting Level Gamma Radiation  % 4.47E-02 1.12E-01 1 Beta Radiation  % 1.47E-02 3.64E-02 ,

B. Iodines

1. Total I-131 Release Ci 8.33E-04 9.29E-04 1.00E+01 l
2. Average I-131 Release Rate uci/sec 1.05E-04 1.17E-04 C. Particulates
1. Total Particulates Ci 4.28E-04 3.69E-04 3.00E+01 l Averace Release Rate uci/sec
2. 5.38E-05 4.64E-05
3. Gross Alpha Radioactivity Ci 7.56E-06 4.09E-06 D. Tritium
1. Total Release Ci 4.67E+00 4.16E+00 1.00E+01 l ,
2. Averace Release Rate uci/sec 5.87E-01 5.23E-01 i E. Percent Qtrly Tech Spec Reporting Levels  ;
1. Iodines, Particulates, and Tritium  % 9.96E-02 9.84E-02 l

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A Page 5 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

. . Period : Jul - Dec 1996  ;

1 Table 1B Gaseous Effluents - Elevated Releases Continuous Mode Batch Mode l Nuclides Released Unit 3rd Otr l 4th Otr 3rd otr I 4th Otr I l

1. Fission Gases KR-85M Ci 1.42E+00 3.76E+00 0.00E+00 0.00E+00 KR-87 Ci 1.28E+00 3.21E+00 0.00E+00 0.00E+00 l KR-88 Ci 2.51E+00 7.62E+00 0.00E+00 0.00E+00 XE-133 Ci 1.66E+01 2.12E+01 0.00E+00 9.50E-04 XE-133M Ci 1.69E-01 2.54E-01 0.00E+00 0.00E+00 XE-135 Ci 2.02E+01 3.94E+01 0.00E+00 5.68E-04 XE-135M Ci 5.52E+00 6.02E+00 0.00E+00 0.00E+00 l XE-137 Ci 3.03E+01 3.09E+01 0.00E+00 0.00E+00 1 XE-138 Ci 1.48E+01 1.51E+01 0.00E+00 0.00E+00 AR-41 Ci 4.61E-02 1.62E-01 0.00E+00 2.56E-03 Total for Period Ci 9.28E+01 1.28E+02 0.00E+00 4.07E-03 1
2. Iodines I-131 Ci 4.89E-04 5.74E-04 0.00E+00 0.00E+00 I-133 Ci 3.75E-03 3.12E-03 0.00E+00 0.00E+00 I-135 Ci 6.13E-03 4.13E-03 0.00E+00 0.00E+00 Total for Period Ci 1.04E-02 7.t2E-03 0.00E+00 0.00E+00
3. Particulates CO-60 C1 2.59E-06 3.24E-06 0.00E+00 0.00E+0C ZN-65 Ci 2.94E-07 3.99E-07 0.00E+00 0.00E+00 CS-137 Ci 1.94E-06 2.00E-06 0.00E+00 0.00E+00 BA-140 Ci 1.01E-04 1.24E-04 0.00E+00 0.00E+00 SP-89 Ci 8.91E-05 5.75E-05 0.00E+00 0.00E+00 Sh-90 Ci 2.01E-07 2.08E-07 0.00E+00 0.00E+00 Total for Period Ci 1.95E-04 1.88E-04 0.00E+00 0.00E+00

) Page 6 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

, Period : Jul - Dec 1996 Table 1C Gaseous Effluents - Building Vent Releases

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Continuous Mode Batch Mode Nuclides Released Unit 3rd Otr 1 4th Otr 3rd Otr i 4th Otr

1. Fission Gases XE-135 Ci 1.37E+00 7.61E+00 0.00E+00 0.00E+00 i XE-135M Ci 0.00E+00 3.39E+00 0.00E+00 0.00E+00 i AR-41 Ci 0.00E+00 0.00E+00 0.00E+00 1.93E-03 i Total for Period Ci 1.37E+00 1.10E+01 0.00E+00 1.93E-03
2. Iodines I-131 Ci 3.44E-04 3.55E-04 0.00E+00 0.00E+00 I-133 , Ci 2.81E-03 2.99E-03 0.00E+00 0.00E+00 Total for Period Ci 3.15E-03 3.35E-03 0.00E+00 0.00E+00
3. Particulates i

MN-54 Ci 6.71E-06 0.00E+00 0.00E+00 0.00E+00 CO-60 Ci 1.45E-04 1.29E-04 0.00E+00 0.00E+00 ZN-65 Ci 5.42E-05 1.84E-05 0.00E+00 0.00E+00 CS-137 Ci 2.19E-05 2.54E-05 0.00E+00 0.00E+00 BA-140 Ci 0.00E+00 4.64E-06 0.00E+00 0.00E+00

SR-89 Ci 5.05E-06 3.84E-06 0.00E+00 0.00E+00 Total for Period Ci 2.33E-04 1.81E-04 0.00E+00 0.00E+00 i

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Page 7 EFFLUENT AND WASTE DISPOSAL SEMIANMd.'sL REPORT l

. Period : Jul - Dec 19.06 I I

Table 2A Liquid Effluents - Summation of all Releases l i

Units 3rd Qtr 4th Qtr Est. Total Error. %

A. Fission & Activation products

1. Total Release (not including tritium, cases, alnha) Ci 0.00E+00 0.00E+00 0.00E+00
2. Ava Diluted Concentration uci/ml 0.00E+00 0.00E+00 B. Tritium

( 1. Total Release Ci 0.00b+00 0.00E+00 l 0.00E+00 l

2. Ava Diluted Concentration uci/ml 0.00E+00 0.00E+00 l C. Dissolved and Entrained Gases
1. Total Release Ci 0.00E+00 0.00E+00 0.00E+00 l
2. Ava Diluted Concentration uci/ml 0.00E+00 0.00E+00 D. Percent Qtrly Tech Spec Reporting Level
1. Whole Body Dose  % 0.00E+00 0.00E+00 l 2. Oraan Dose  % 0.00E+00 0.00E+00 E. Gross Alpha Radioactivity l 1. Total Release l Ci l 0.00E+00 i 0.00E+00 1 0.00E+00 l lF. Volume of Waste Released l Liters l 0.00E+00 l 0.00E+00 l 0.00E+00 l lF. Volume of Dilution Water Used I Liters l 0.00E+00 1 0.00E+00 1 0.00E+00 l Table 2B Liquid Effluents Continuous Mode Batch Mode Nuclides Released Unit 3rd Otr i 4th Otr 3rd Otr I 4th Otr None Released This Period i

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Page 8 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

{ Period : Jul - Dec 1996 i

i Table 3 Solid Waste and Irradiated Fuel Shipments A. Solid Waste Shipped Offsite for Burial or Disposal (not irradiated fuel)

1. Type of Waste Units 6-month Est. Total
Period Error, %

i a. Spent resins, filter sludges, Cu. Meter 2.43E+01 I evaporator bottoms, etc. Ci 9.71E+02 3.70E+01

b. Dry compressible waste, Cu. Meter 2.62E+00 l'

contaminated eauipment. etc. _

Ci 3.16E-01 3.50E+01

c. Irradiated components, Cu. Meter 0.00E+00 control rods, etc. Ci 0.00E+00 0.00E+00
d. Other (describe) Cu. Meter 0.00E+00 Ci 0.00E+00 0.00E+00
2. Estimate of major nuclide composition (by type of waste)

Type A Type B Type C Type D Nuclide cercent oercent percent percent H-3 8.90E-02 1.79E-01 C-14 1.70E-01 3.43E-02 Cr-51 4.26E-01 Mn-54 6.82E+00 4.00E+00 Fe-55 5.29E+01 5.45E+01 Co-57 8.43E-02 Co-58 5.77E-01 7.32E-02 Fe-59 5.16E-01 1.95E-01 Co-60 1.51E+01 2.45E+01 Ni-63 3.22E-01 9.47E-01 Zn-65 2.02E+01 1.27E+01 Sr-89 2.31E-01 1.40E-02 Sr-90 2.22E-02 3.87E-02 Tc-99 3.41E-03 l Sb-124 5.41E-02 Sb-125 5.91E-02 I-129 9.89E-03 I-131 6.04E-01 Cs-134 2.22E-02 5.97E-02 Cs-137 1.69E+00 2.21E+00 La-140 7.73E-02 Ce-141 8.90E-02 <

Ce-144 7.44E-02 Pu-238 2.53E-02 Pu-239 1.50E-02 i Am-241 2.53E-02 i Pu-241 2.37E-02 2.04E-01  !

Cm-242 5.58E-03 Pu-242 1.93E-02 Cm-243 1.06E-02 i

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, , Period : Jul - Dec 1996 Table 3 Solid Waste and Irradiated Fuel Shipments

3. Solid waste disposal Number of Mode of Destination Shioments Transoortation 19 Truck Chem-Nuc Inc., Barnwell, SC.

l B. Irradiated Fuel Shipments

1. Disposition Number of Mode of Destination Shioments Transoortation None This Period C. Shipping Container and Solidification Method No. Volume Activity Type of Container Solidification M3 Ci Waste Code Code 96-53 5.83E+00 7.71E+01 A A D ,

96-55 5.83E+00 7.15E+01 A A D l 96-58 3.41E+00 2.30E+02 A A D 96-59 5.83E+00 6.74E+01 A A D i 9605e 3.29E-01 1.12E-02 B L N l 9627h 2.83E-02 1.24E-02 B L N l 96279 1.30E-01 3.73E-02 B L N 9638d 7.82E-01 3.69E-02 B L N 9638e 4.53E-01 2.36E-02 B L N 9638f 4.81E-02 2.05E-02 B L N 9638g 4.81E-02 1.06E-01 B L N 9642b 9.63E-02 1.55E-02 B L N l 9642c 2.61E-01 5.52E-03 B L N i 9642d 2.01E-01 3.56E-03 B L N 9651 3.41E+00 5.2SE+02 A A D 1 9642e 9.06E-02 1.46E-02 B L N i 9642f 2.83E-03 1.20E-02 B L N 9638h 8.21E-02 2.83E-03 B L N 96381 6.80E-02 1.38E-02 B L N 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

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