ML14139A088

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Radioactive Effluent Release Report for January 1 - December 31, 2013
ML14139A088
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 05/15/2014
From: Fili K
Northern States Power Co, Xcel Energy
To:
Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML14139A091 List:
References
L-MT-14-012
Download: ML14139A088 (30)
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Text

ENCLOSURE 1 RADIOACTIVE EFFLUENT RELEASE REPORT FOR JANUARY 1 - DECEMBER 31, 2013 22 pages follow

NUCLEAR MANAGEMENT COMPANY MONTICELLO NUCLEAR GENERATING PLANT License No. DPR-22 RADIOACTIVE EFFLUENT RELEASE REPORT Period  : Jan - Dec 2013 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)

Page 2 RADIOACTIVE EFFLUENT RELEASE REPORT Period  : Jan - Dec 2013 Supplemental Information (continued)

4. Measurements and Approximations of Total Radioactivity 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 Monthly 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 I. Number of Batch Releases 1
2. Total Time Period for Batch Releases 40.0 min
3. Maximum Time Period for a Batch Release 40.0 min
4. Average Time Period for a Batch Release 40.0 min
5. Minimum Time Period for a Batch Release 40.0 min
6. Average River Flow During Release 10700.0 cf/sec B. Gaseous
1. Number of Batch Releases 2
2. Total Time Period for Batch Releases 1660.0 min
3. Maximum Time Period for a Batch Release 1315.0 min
4. Average Time Period for a Batch Release 830.0 min
5. Minimum Time Period for a Batch Release 345.0 min

Page 3 RADIOACTIVE EFFLUENT RELEASE REPORT Period Jan - Dec 2013 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

Page 4 RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan - Dec 2013 Table 1A Gaseous Effluents - Summation of all Releases Units 1st Qtr 2nd Qtr Est. Total Error,  %

A. Fission & Activation gases

1. Total Release Ci 1.32E+02 0.OOE+00 2.OOE+01
  • 2. Average Release Rate uci/sec 1.70E+01 0.OOE+00
3. Percent Tech Spec Qtrly Reporting Level Gamma Radiation  % 8.32E-02 0.OOE+00 Beta Radiation 0% 2.09E-02 0.OOE+00 B. lodines
1. Total 1-131 Release Ci 2.15E-03 1.62E-05 1.00E+01
2. Average 1-131 Release Rate uci/sec 2.77E-04 2.06E-06 C. Particulates
1. Total Particulates Ci 1.77E-04 5.09E-05 3.OOE+01
2. Average Release Rate uci/sec 2.28E-05 6.47E-06
3. Gross Alpha Radioactivity Ci 5.27E-07 1.53E-06 D. Tritium
1. Total Release Ci 5.67E+00 3.64E+00 1.00E+01
2. Average Release Rate uci/sec 7.29E-01 4.62E-01_l EB. Carbon-14
1. Total Release Ci 1.20E+00 0.OOE+00 1.OOE+01
2. Averaqe Release Rate I uci/sec 1 1.50E-01 1 0.OOE+00 F. Percent Qtrly Tech Spec Reporting Levels

.. Iodines, Particulates, and Tritium  % 4.78E-01 6.08E-03

Page 5 RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan - Dec 2013 Table 1A Gaseous Effluents - Summation of all Releases Units 3rd Qtr 4th Qtr Est. Total FError;,

A. Fission & Activation gases

1. Total Release Ci 2.21E+02 1 .51E+02 2.00E+00
2. Average Release Rate uci/sec 2.79E+01 1.90E+01
3. Percent Tech Spec Qtrly Reporting Level Gamma Radiation 1.47E-01 8.32E-02 Beta Radiation  % 2.76E-02 2.88E-02
1. Total 1-131 Release Ci 1.36E-03 1.72E-03 l.0OE+01
2. Average 1-131 Release Rate uci/sec 1.71E-04 I 2.16E-04 I C. Particulates
1. Total Particulates Ci 6.87E-04 2.53E-04 3.OOE+01
2. Average Release Rate uci/sec 8.64E-05 3.18E-05

.3. Gross Alpha Radioactivity Ci 8.63E-07 5.93E-07 D. Tritium

1. Total Release Ci 3.37E+00 I 4.55E+00 1.OOE+01
2. Average Release Rate uci/sec 4.24E-01I 5.73E-01_1 E. Carbon-14
1. Total Release Ci 1.20E+00 I 1.80E+00 I 1.OOE+01
2. Average Release Rate I uci/sec I 4.50E-01 I 2.30E-01 F. Percent Qtrly Tech Spec Reporting Levels
1. Iodines, Particulates, and Tritium T 2.73E-01 3.08E-01

Page 6 RADIOACTIVE EFFLUENT RELEASE REPORT Period  : Jan - Dec 2013 Table lB Gaseous Effluents - Elevated Releases Continuous Mode Batch Mode Nuclides Released Unit 1st Qtr 2nd Qtr 1st Qtr 2nd Qtr

1. Fission Gases KR-85M Ci 8.08E-01 0.OOE+00 0.OOE+00 0.OOE+00 KR-87 Ci 1.51E+00 0.OOE+00 3.46E-03 0.OOE+00 KR-88 Ci 2.18E+00 0.OOE+00 0.OOE+00 0.OOE+00 KR-89 Ci 1.28E+00 0.OOE+00 0.OOE+00 0.OOE+00 XE-133 Ci 2.29E+01 0.OOE+00 5.26E-03 0..OOE+00 XE-133M Ci 4.65E-01 0.OOE+00 0.OOE+00 0.OOE+00 XE-135 Ci 1.19E+0.1 0.OOE+00 1.04E-02 0.OOE+00 XE-135M Ci 1.13E+01 0.OOE+00 0.OOE+00 0.OOE+00 XE-137 Ci 4.95E+01 0.OOE+00 0.OOE+00 0.OOE+00 XE-138 Ci 2.48E+01 0.OOE+00 8.79E-03 0.OOE+00

.AR-41 Ci 0.OOE+00 0.OOE+00 7.10E-03 0.OOE+00 Total for 9Period Ci 1.27E+02 0.OOE+00 3.50E-02 0.OOE+00

2. Iodines 1-131. Ci 1.30E-03 4.26E-07 0.OOE+00 0.00E+00 1-133 Ci 8.04E-03 *0.00E+00 4.09E-08 0.OOE+00 1-135 -Ci -1.13E-02 0.'OOE+00 0.OOE+00 0.OOE+00 Total for Period Ci 2.06E-02 4.26E-07 4.09E-08 0.OOE+00
3. Particulates CO-60 Ci 6.32E-07 9.02E-07 0.OOE+00 0.OOE+00 CS-137 Ci 2.48E-07 7.32E-08 0.OOE+00 0.OOE+00 BA-140 Ci 6.62E-05 0.OOE+00 0.OOE+00 0.OOE+00 SR-89 -Ci 8.10E-06 9.06E-07 0.OOE+00 0.OOE+00 SR-90 Ci 1.18E-07 0.OOE+00 0.OOE+00 0.OOE+00 Total for Period Ci 7.53E-05 1.88E-06 0.OOE+00 0.OOE+00

Page 7 RADIOACTIVE EFFLUENT RELEASE REPORT Period  : Jan - Dec 2013 Table lB Gaseous Effluents Elevated Releases Continuous-Mode Batch Mode Nuclides Released Unit 3rd Qtr 4th Qtr 3rd Qtr 4th Qtr

1. Fission Gases KR-85M Ci 9.03E+00 8.30E-01 0.00E+00 0.OOE+00 KR-87 Ci 2.65E+01 1.87E+00 0.00E+00 0.OOE+00 KR-88 Ci 2.73E+01 2.15E+00 0.00E+00 0.00E+00 KR-89 Ci 1.38E+00 8.31E+00 0.OOE+00 0.00E+00 XE-133 Ci 9.30E+00 3.02E+01 0.OOE+00 0.00E+00 XE-133M Ci 1.67E-01 7.31E-01 0.OOE+00 0.00E+00 XE-135 Ci 5.88E+01 7.98E+00 3.46E-04 0.00E+00 XE-135M Ci 1.26E+01 9.29E+00 0.00E+00 0.00E+00 XE-137 Ci 3.54E+01 5.92E+01 0.00E+00 0.00E+00 XE-138 Ci 3.56E+01 2.34E+01 0.OOE+00 0.OOE+00 AR-41 Ci 3.37E-01 0.00E+00 4.09E-03 0.00E+00 Total for Period Ci 2.16E+02 1.44E+02 4.44E-03 0. 00E+00
2. Iodines 1-131 Ci 1.09E-03 1.17E-03 0.OOE+00 0.00E+00 1-133 Ci 7.83E-03 7.46E-03 8.79E-09 0.00E+00 1-135 Ci 1.08E-02 9.01E-03 0.OOE+00 0:00E+00 Total for Period _C1 1.98E-02 1.76E-02 8.79E-09 0.00E+00
3. Particulates CO-0 Ci 4.71E-07 1.63E-07 0.OOE+00 , O.00E+00 CS-137 Ci 1.29E-05 1.65E-07 0.00E+00 0.00E+00 BA-140 Ci 9.65E-05 8.42E-05 0.OOE+00 0.OOE+00 SR-89 Ci 3.95E-04 4.48E-05 0.OOE+00 0.OOE+00 SR-90 Ci 3.70E-07 1.34E-07 0.OOE+00 0.OOE+00 Total for Period Ci 5.06E-04 1.29E-04 0.OOE+00 0.00E+00

Page 8 RADIOACTIVE EFFLUENT RELEASE REPORT Period  : Jan - Dec 2013 Table iC Gaseous Effluents - Building Vent Releases Continuous Mode Batch Mode Nuclides Released Unit 1st Qtr 2nd Qtr Ist Qtr 2nd Qtr

1. Fission Gases XE-133 Ci 5.23E-01 0.0O:E+00 0.OOE+00 0:00E+00 XE-135 Ci 1.56E+00 0.OOE+00 0.OOE+00 0.OOE+00 XE-135M Ci -3.31E+00 0.OOE+00 0.OOE+00 0.OOE+00 XE-138 Ci -2.28E-01 0.OOE+00 0.OOE+00 0.OOE+00 Total for Period Ci 5.62E+00 0.OOE+00 0.OOE+00 O.OOE+00
2. Iodines 1-131 Ci 8.51E-'04 1.57E-05 0.OOE+00 0.OOE+00 1-133 Ci 6.77E-03 0.OOE+00 0.OOE+00 0.OOE+00 1-135 Ci 1.51E-02 0.00E+00 0.OOE+00 0.OOE+00 Total for Period Ci 2.27E-02 1.57E-05 0.OOE+00 0.OOE+00
3. Particulates MN-54 Ci 1.15E-06 2.55E-06 0.OOE+00 0.OOE+00 CO-58 *Ci 1.43E-06 0.OOE+00 0.OOE+00 0.OOE+00 CO-60 Ci 4 41E-05 4.32E-05 0.OOE+00 0.OOE+00 CS-137 Ci 1.22E-05 3.25E-06 0.OOE+00 0.OOE+00 BA-140 Ci 4.33E-05 0.O0E+00 0.OOE+00 0.00E+00 Total for Period Ci 1.02E-04 4.90E-05 0.OOE+00 0.OOE+00

.Page 9 RADIOACTIVE EFFLUENT RELEASE REPORT Period  : Jan - Dec 2013 Table iC Gaseous Effluents - Building Vent Releases Continuous Mode Batch Mode Nuclides Released Unit *3rd Qtr 4th Qtr 3rd Qtr 4th Qtr

1. Fission Gases XE-135 Ci 3.83E+00 4.77E+00 0.OOE+00 0.OOE+00 XE-135M Ci 1.25E+00 2.05E+00 0.OOE+00 0.OOE+00 Total for Period {C_ 5.08E+00 6.82E+00 0.OOE+00 0.OOE+00
2. Iodines 1-131 MCi 2.68E-04 5.44E-04 0.OOE+00 0.OOE+00 1-133 Ci 2.19E-03 4.63E-03 0.OOE+00 0.OOE+00 Total for Period Ci 2.46E-03 5.17E-03 0.OOE+00 0.OOE+00
3. Particulates MN-54 Ci 4.81E-06 0.OOE+00 0.OOE+00 0.OOE+00 CO-58 Ci 3.74E-05 1.27E-06 0.OOE+00 0.OOE+00 CO-60 Ci 4.76E-05 4.13E-05 0.OOE+00,. 0.OOE+00 ZN-65 Ci 1.65E-05 0.OOE+00 0.OOE+00 0.OOE+00 CS-137 Ci 2.15E-05 6.77E-05 0.OOE+00 0.OOE+00 BA-140 Ci 5.36E-05 1.28E-05 0.OOE+00 0.OOE+00 Total for Period Ci 1.81E-04 1.23E-04. 0.OOE+00 0.OOE+00

Page 10 RADIOACTIVE EFFLUENT RELEASE REPORT Period  : Jan - Dec 2013 Table 2A Liquid Effluents - Summation of all Releases Units 1st Qtr 2nd Qtr Est. Total Error,  %

A. Fission & Activation products

1. Total Release (not including tritium, gases, alpha) Ci 0.OOE+00 0.OOE+00 0.00E+00
2. Avg Diluted Concentration i uci/ml 0.OOE+00 0.OOE+00 B. Tritium
1. Total Release Ci 0.OOE+00 0.OOE+00 0.OOE+00
2. Avg Diluted Concentration I uci/ml I 0.OOE+00 0.OOE+00_1 C. Dissolved and Entrained Gases
1. Total Release Ci  : 0.00E+00 0.00E+00 0.OOE+00_1
2. Avg Diluted Concentration uci/ml j 0.OOE+00 0.OOE+00 D. Percent Qtrly Tech Spec Reporting Level
1. Whole Body Dose 0 0.OOE+00 0.0OE+00
2. Organ Dose  % 0.OOE+00 0.OOE+00 E. Gross Alpha Radioactivity
1. Total Release Ci 0.00E+00 0.OOE+00 0.OOE+00 IF. Volume of Waste Released Liters .0.00E+00 0.OOE+00 0.OOE+00 IF. Volume of Dilution Water Used Liters 0.00E+00 0.OOE+00 0.OOE+00 Table 2B Liquid Effluents Continuous Mode Batch Mode Nuclides Released Unit 1st Qtr 2nd Qtr Ist Qtr 2nd Qtr None Released This Period

Page 11 RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan - Dec 2013 Table 2A Liquid Effluents Summation of all Releases Units 3rd Qtr 4th Qtr IEst. Total Error, %

A. Fission & Activation products

1. Total Release (not including tritium, gases, alpha) Ci 0.OOE+00 0.OOE+00 0.OOE+00
2. Avg Diluted Concentration uci/ml 0.OOE+00 0.OOE+00 B. Tritium
1. Total Release Ci 2.08E-03 0.OOE+00 5.OOE+01
2. Avg Diluted Concentration uci/ml 1.31E-07 0.OOE+00 C. Dissolved and Entrained Gases
1. Total Release Ci 0.OOE+00 0.OOE+00 0 OOE+00
2. Avg Diluted Concentration uci/ml 0.I00-E+00 I 0.00E+00 D. Percent Qtrly Tech Spec Reporting Level
1. Whole Body Dose 8.55E-06 0.OOE+00
2. Organ Dose 6 2.57E-06 0.OOE+00 E. Gross Alpha Radioactivity
1. Total Release Ci 0.OOE+00 0.OOE+00 0.OOE+00 IF. Volume of Waste Released Liters 1.32E+04 0.OOE+00 0.OOE+00 IF. Volume of Dilution Water Used Liters 1.59E+07 0.OOE+00 0.OOE+00 Table 2B Liquid Effluents Continuous Mode Batch Mode Nuclides Released Unit 3rd Qtr 4th Qtr 3rd Qtr 4th Qtr

.Tritium Ci 0.OOE+00 0.OOE+00 2.08E-03 0.OOE+00

NRC Regulatory Guide 1.21 Reports Page 1 Report Date: 4/7/2014 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2013 to 12/31/2013 Percent Cutoff: 0 Waste Stream : Resins, Filters, and Evap Bottoms PRD-NA 215 T34A Waste Volume Curies  % Error Class FtA3 MA3 Shipped (Ci)

A 1.70E+02 4.81E+00 3.85E+00 +/-25%

B 0.00E+00 0.00E+00 0.OOE+00 +/- 25%

C 0.00E+00 0.00E+00 0.OOE+00 +/- 25%

All 1.70E+02 4.81E+00 3.85E+00 +/-25%

Waste Stream : Dry Active Waste EPU Metal Waste B25 Box C-Van Insulation & Concrete Insulation Feed Water Pump FW Piping & Parts Cond Pump Motor Ott B0z plant trasn kregular z.plant trasn k20 sealanoplant trasn jniermooal Waste Volume Curies %Error Class FtA3 MA^3 Shipped (Ci)

A 4.73E+04 1.34E+03 1.69E+00 +/-25%

B 0.OOE+00 0.00E+00 0.00E+00 +/-25%

C 0.00E+00 0.00E+00 0.00E+00 +/-25%

All 4.73E+04 1.34E+03 1.69E+00 +/-25%

Waste Stream  : Irradiated Components Waste Volume Curies %Error Class FtA3 MA3 Shipped (Ci)

A 0.OOE+00 0.OOE+00 0.00E+00 +/-25%

B 0.OOE+00 0.00E+00 0.OOE+00 +/-25%

C 0.00E+00 0.00E+00 0.00E+00 +/-25%

All 0.00E+00 0.00E+00 0.00E+00 +/-25%

NRC Regulatory Guide 1.21 Reports Page 2 Report Date: 4/7/2014 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2013 to 12/31/2013 Percent Cutoff: 0 Waste Stream : Other Waste Motor Generator Motoil 3A FW Heater Cond Pump P2 Cooler Lathe & Drill Press Insulation CARV Waste Volume Curies  % Error Class FtA3 MA3 Shipped (Ci)

A 4.05E+03 1.15E+02 5.46E-02 +/-25%

B 0.00E+00 0.00E+00 0.00E+00 +/-25%

C 0.00E+00 0.00E+00 0.00E+00 +/-25%

All 4.05E+03 1.15E+02 5.46E-02 +/-25%

Waste Stream : Sum of All 4 Categories PRD-NA 215 T34A Motor Generator Motc EPU Metal Waste 13A FW Heater B25 Box C-Van Cond Pump Insulation &.Concrete Insulation Feed Water Pump P2 Cooler FWPiping & Parts Waste Volume Curies  % Error Class ) FtA3 MA3 Shipped (Ci)

A 5.16E+04 1.46E+03 5.59E+00 +/-25%

B 0.OOE+00 0.00E+00 0.00E+00 +/-25%

C 0.00E+00 0.00E+00 0.00E+00 +/-25%

All 5.16E+04 1.46E+03 5.59E+00 +/-25%

-Combined Waste Type Shipment, Major Volume Waste Type Shown

NRC Regulatory Guide 1.21 Reports Page 1 Report Date : 4/7/2014 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2013 to 12/31/2013 Number of Shipments Mode of Transportation Destination 1 Hittman Transport EnergySolutions LLC.

2 Landstar Ranger Studsvik Processing Facility Memphis 39 Xcel Energy Trucking Studsvik Processing Facility Memphis

NRC Regulatory Guide 1.21 Reports Page 1 Report Date: 4/7/2014 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2013 to 12/31/2013 Percent Cutoff: 0 Nuclide Name Percent Abundance Curies H-3 0.289% 1.11 E-02 Mn-54 .1.458% 5.61 E-02 Fe-55 7.731% 2.98E-01 Co-58 0.328% 1.26E-02 Co-60 31.150% 1.20E+00 Ni-59 0.019% 7.31E-04 Ni-63 2.433% 9.36E-02 Zn-65 1.837% 7.07E-02 Sr-90 0.282% 1.09E-02 1-129 0.002% 6.68E-05 1-131 0.031% 1.18E-03 Cs-137 54.111% 2.08E+00 Ba-140 0.095% 3.66E-03 La-140 0.000% - 5.54E-11 Ce-141 0.182% 6.99E-03 Ce-144 0.016% 6.13E-04 Pu-238 0.002% 5.87E-05 Pu-239 0.001% 3.58E-05 Pu-240 0.001% 3.58E-05 Pu-241 0.025% 9.77E-04 Am-241 0.006% 2.26E-04 Cm-242 0.000% 4.64E-06 Cm-243 0.001% 5.16E-05 Cm-244 0.001% 5.15E-05 Dry Active Waste Waste Class A Nuclide Name Percent Abundance Curies H-3 0.001% 1.34E-05 C-14 0.003% 4.86E-05 Cr-51 0.000% 6.40E-10 Mn-54 1.696% 2.86E-02 Fe-55 66.550% 1.12E+00 Co-58 0.139% 2.34E-03 Co-60 29.334% 4.94E-01 Ni-63 0.008% 1.41 E-04 Zn-65 0.742% 1.25E-02 Sr-90 0.006% 9.63E-05 Nb-95 0.000% 1.26E-09 Tc-99 0.000% 1.36E-07 Ag-110m 0.000% 3.84E-07 Sb-124 0.000% 2.68E-09 1-129 0.000% 4.92E-07 1-131 0.000% 4.39E-21 Cs-1 34 0.000% .... 8.OOE-06 Cs-137 1.324% 2.23E-02 Ba-140 0.000% 4.07E-15 La-140 0.000% 9.79E-48 Ce-141 0.108% 1.82E-03 Ce-144 0.084% 1.42E-03

NRC Regulatory Guide 1.21 Reports Page 2 Report Date : 4/7/2014 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2013 to 12/31/2013 Percent Cutoff: 0 Th-230 0.005% 8.95E-05 Pu-238 0.000% 1.74E-07 Pu-239 0.000% 8.77E-08 Pu-240 0.000% 8.77E-08 Am-241 0.000% 9.62E-08 Am-243 0.000% 1.61 E-06 Cm-242 0.000% 9.36E-09 Cm-243 0.000% 6.38E-08 Cm-244 0.000% 2.18E-08 Dry Active Waste Waste Class All Nuclide Name Percent Abundance Curies H-3 0.001% 1.34E-05 C-14 0.003% 4.86E-05 Cr-51 0.000% 6.40E-10 Mn-54 1.696% 2.86E-02 Fe-55 66.550% 1.12E+00 Co-58 0.139% 2.34E-03 Co-60 29.334% 4.94E-01 Nk63 0.008% .1.41 E-04 Zn-65 0.742% 1.25E-02 Sr-90 0.006% 9.63E-05 Nb-95 0.000% 1.26E-09

  • Tc-99 0.000% 1.36E-07 Ag-110m 0.000% 3.84E-07 Sb-124 0.000% 2.68E-09 1-129 0.000% 4.92E-07 1-131 0.000% 4.39E-21 Cs-134 0.000% 3.OOE-06 Cs-137 1.324% 2.23E-02 Ba-140 0.000% 4.07E-15 La-140 0.000% 9.79E-48 Ce-141 0.108% 1.82E-03 Ce-144 0.084% 1.42E-03 Th-230 0.005% 8.95E-05 Pu-238 0.000% 1.74E-07 Pu-239 0.000% 8.77E-08 Pu-240 0.000% 8.77E-08 Am-241 0.000% 9.62E-08 Am-243 0.000% 1.61 E-06 Cm-242 0.000% 9.36E-09 Cm-243 0.000% 6.38E-08 Cm-244 0.000% 2.18E-08 Other Waste Waste Class A Nuclide Name Percent Abundance Curies H-3 0.014% 7.56E-06 C-14 0.050% 2.74E-05 Cr-51 0.000% 3.76E-10

NRC Regulatory Guide 1.21 Reports Page 3 Report Date: 4/7/2014 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2013 to 12/31/2013 Percent Cutoff: 0 Mn-54 1.723% 9.40E-04 Fe-55 63.565% 3.47E-02 Co-58 0.134% 7.29E-05 Co-60 30.339% 1.66E-02 Ni-63 0.145% 7.94E-05 Zn-65 0.822% 4.48E-04 Sr-90 0.099% 5.43E-05 Nb-95 0.000% 7.32E-10 Tc-99 0.000% 7.65E-08 Ag-110m 0.000% 2.17E-07 Sb-124 0.000% 1.54E-09 1-129 0.001% 2.77E-07 1-131 0.000% 2.82E-21 Cs-134 0.003% 1.70E-06 Cs-137 2.826% 1.54E-03 Ba-140 0.000% 2.50E-15 La-140 0.000% 7.16E-48 Ce-141 0.103% 5.62E-05 Ce-144 0.081% 4.42E-05 Th-230 . 0092% 5.05E-05 Pu-238 0.000% 9.78E-08 Pu-239 0,000% 4.95E-08 Pu-240 0.000% 4.94E-08 Am-241 0,000% 5.42E-08 Am-243 0.002% 9.1OE-07 Cm-242 0.000% 1 5.31 E-09 Cm-243 0.000% 3.60E-08 Cm-244 0.000% 1.23E-08 Other Waste Waste Class All Nuclide Name Percent Abundance Curies H-3 0,014% 7.56E-06 C-14 0.050% 2.74E-05 Cr-51 0.000% 3.76E-10 Mn-54 1.723% 9.40E-04 Fe-55 63.565% 3.47E-02 Co-58 0.134% 7.29E-05 Co-60 30.339% 1.66E-02 Ni-63 0.145% 7.94E-05 Zn-65 0.822% 4.48E-04 Sr-90 0.099% 5.43E-05 Nb-95 0.000% 7.32E-10 Tc-99 0.000% 7.65E-08 Ag-110m 0.000% 2.17E-07 Sb-124 0.000% 1.54E-09 1-129 - 0.001% 2.77E-07 1-131 0.000% 2.82E-21 Cs-134 0.003% 1.70E-06 Cs-137 2.826% 1.54E-03 Ba-140 0.000% 2.50E-15

NRC Regulatory Guide 1.21 Reports Page 4 Report Date : 4/7/2014 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2013 to 12/31/2013 Percent Cutoff: 0 La-140 0,000% 7.16E-48 Ce-141 0.103% 5.62E-05 Ce-144 0.081% 4.42E-05 Th-230 0.092% 5.05E-05 Pu-238 0.000% 9.78E-08 Pu-239 0.000% 4.95E-08 Pu-240 0.000% 4.94E-08 An-241 0.000% 5.42E-08 Am-243 0.002% 9.10E-07 Cm-242 0.000% 5.31 E-09 Cm-243 0.000% 3.60E-08 Cm-244 0.000% 1.23E-08 Sum of All 4 Categories Waste Class A Nuclide Name Percent.Abundance Curies H-3 0.199% 1. 11 E-02 C-14 0.001% 7.61E-05 Cr-51 0.000% 1.02E-09 Mn-54 1.532% 8.56E-02 Fe-55 26.015% 1.45E+00 Co-58 0.269% 1.50E-02 Co-60 30.595% 1.71E+00 Ni-59 0.013% 7.31E-04 "Ni-63 1.679% 9.39E-02 Zn-65 1 1.497% 8.36E-02 Sr-90 0.197% 1.10E-02 Nb-95 0.000% 1.99E-09 Tc-99 0.000% 2.12E-07 Ag-110m 0.000% 6.01E-07 Sb-124 0.000% 4.22E-09 1-129 0.001% 6.76E-05 1-131 0.021% 1.18E-03 Cs-134 0.000% 4.70E-06 Cs-1 37 37.690% 2.11 E+00 Ba-140 0.066% 3.66E-03 La-140 0.000% 5.54E-11 Ce-141 0.159% 8.86E-03 Ce-144 0.037% 2.08E-03 Th-230 0.003% 1.40E-04 Pu-238 0.001% 5.90E-05 Pu-239 0.001% 3.59E-05 Pu-240 0.001% .3.59E-05 Pu-241 0.017% 9.77E-04 Am-241 0.004% 2.26E-04 Am-243 0.000% 2.52E-06 Cm-242 0,000% 4.66E-06 Cm-243 0.001% 5.17E-05 Cm-244 0.001% 5.15E-05 Sum of All 4 Categories

NRC Regulatory Guide 1.21 Reports Page 5 Report Date 4/7/2014 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2013 to 12/31/2013 Percent Cutoff: 0 Waste Class All

  • Nuclide Name Percent Abundance Curies H-3 0.199% 1.11 E-02 C-14 0.001% 7.61 E-05 Cr-51 0.000% 1.02E-09 Mn-54 1.532% 8.56E-02 Fe-55 26.015% 1.45E+00 Co-58 0.269% 1.50E-02 Co-60 30.595% 1.71 E+00 Ni-59 0.013% 7.31E-04 Ni-63 1.679%. 9.39E-02 Zn-65 1.497% 8.36E-02 Sr-90 0.197% 1.10E-02 Nb-95 0.000% 1.99E-09 Tc-99 0.000% 2.12E-07 Ag-110m 0.000% 6.01 E-07 Sb-124 0.000% 4.22E-09 1-129 0.001% 6.76E-05 1-131 0.021% 1.18E-03 Cs-1 34 0.000% 4.70E-06 Cs-137 37.690% 2.11 E+00 Ba-140 0.066% 3.66E-03 La-140 0.000% 5.54E-11 Ce-141 0.159% 8.86E-03 Ce-144 0.037% 2.08E-03 Th-230 0.003% 1.40E-04 Pu-238 0.001% 5.90E-05 Pu-239 0.001% 3.59E-05 Pu-240 0.001% 3.59E-05 Pu-241 0.017% 9.77E-04 Am-241 0.004% 2.26E-04 Am-243 0.000% 2.52E-06 Cm-242 0.000% 4.66E-06 Cm-243 0.001% 5.17E-05 Cm-244 0.001% 5.15E-05 Resins, Filters, and Evap Bottom Waste Class A Nuclide Name Percent Abundance Curies H-3 0.289% 1.11 E-02 Mn-54 1.458% 5.61 E-02 Fe-55 7.731% 2.98E-01 Co-58 0.328% 1.26E-02 Co-60 31.150% 1.20E+00 Ni-59 0.019% 7.31 E-04 Ni-63 2.433% 9.36E-02 Zn-65 1.837% 7.07E-02 Sr-90 0.282% 1.09E-02 1-129 0.002% 6.68E-05 1-131 0.031% 1.18E-03 Cs-137 54.111% 2.08E+00

NRC Regulatory Guide 1.21 Reports Page 6 Report Date: 4/7/2014 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2013 to 12/31/2013 Percent Cutoff: 0 Ba-140 0.095% 3.66E-03 La-140 0.000% 5.54E-11 Ce-141 0.182% 6.99E-03 Ce-144 0.016% 6.13E-04 Pu-238 0.002% 5.87E-05 Pu-239 0.001% 3.58E-05 Pu-240 0.001% 3.58E-05 Pu-241 0.025% 9.77E-04 Am-241 0.006% 2.26E-04 Cm-242 0.000% 4.64E-06 Cm-243 0.001% 5.16E-05 Cm-244 0.001% 5.15E-05 Resins, Filters, and Evap Bottom Waste Class All

NRC Regulatory Guide 1.21 Reports Page Report Date : 4/7/2014 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2013 to 12/31/2013 Manifest Number Date Shipped Waste Volume Used Burial volume Used 13-168 10/22/2013 Yes13-167 10/21/2013 Yes13-135 7/15/2013 Yes13-126 7/8/2013 Yes13-122 6/24/2013 Yes13-121 6/24/2013 Yes13-111 6/10/2013 Yes13-108 6/10/2013 Yes13-104 6/3/2013 Yes13-101 5/28/2013 Yes 13-99 5/20/2013 Yes 13-95 5/13/2013 Yes 13-89 5/13/2013 Yes 13-92 5/13/2013 Yes 13-94 5/13/2013 Yes 13-85 4/29/2013 Yes 13-84 4/29/2013 Yes 13-83 4/29/2013 Yes 13-78 4/22/2013 Yes 13-77 4/22/2013 Yes 13-69 4/22/2013 Yes 13-63 4/15/2013 Yes 13-72 4/15/2013 Yes 13-70 4/15/2013 Yes 13-54 4/8/2013 Yes 13-61 4/8/2013 Yes 13-60 4/8/2013 Yes 13-48 4/1/2013 Yes 13-37 4/1/2013 Yes 13-47 4/1/2013 Yes 13-43 3/24/2013 Yes 13-42 3/24/2013 Yes 13-46 3/24/2013. Yes 13-41 3/24/2013. Yes 13-38 3/20/2013 Yes 13-33 3/19/2013 Yes 13-35 3/19/2013 Yes

NRC Regulatory Guide 1.21 Reports Page 2 Report Date : 4/7/2014 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2013 to 12/31/2013 Manifest Number Date Shipped Waste Volume Used Burial volume Used 13-29 3/19/2013 Yes 13-25 3/11/2013 Yes 13-18 3/11/2013 Yes 13-11 3/7/2013 *Yes 13-02 1/15/2013 Yes

ENCLOSURE2 OFF-SITE RADIATION DOSE ASSESSMENT FOR JANUARY 1 - DECEMBER 31, 2013 6 pages follow

MONTICELLO NUCLEAR GENERATING PLANT Offsite Radiation Dose Assessment for January 1, - December 31, 2013 An assessment of radiation dose due to releases from the Monticello Nuclear Generating Plant during 2013 was performed in accordance with the Offsite Dose Calculation Manual (ODCM). Computed doses were wet below the 40 CFR 190 Standards and 10 CFR Part 50, Appendix I Guidelines.

Offsite dose calculation formulas and meteorological data from the Offsite Dose Calculation Manual were used in making this assessment. Source terms were obtained from the Radioactive Effluent Release Report for 2013.

The dispersion parameters used in the ODCM are calculated using the computer program XOQDOQ and are based on meteorological data from 1976 to 1978. These dispersion parameters are being recalculated using meteorological data from 2006 to 2010. The calculations are not complete at the time of this report. The impact of these new calculations will have little or no impact on the annual dose to the public.

Offsite Dose from Gaseous Releases (ODCM -08.01 section 2.1.3)

Computed dose due to gaseous releases are reported in Table 1. Critical receptor location and pathways for organ dose are reported in Table 2. Whole body arid organ dose due to gaseous releases are a small percentage of Appendix I Guidelines.

Offsite Dose From Liguid Releases (ODCM -08.01 section 2.1.3)

Dose from liquid releases are listed in Table 1.

Dose is based on release of Turbine Building Normal Waste Sump water containing H-3 in the third quarter.

Whole body and organ dose due to this release are a small percentage of appendix I Guidelines.

Dose to Individuals Due to Their Activities Inside the Site Boundary (ODCM -08.01 section 2.1.3)

Computed dose to the whole body, skin and organ (thyroid), are reported in Table i. There are several groups of concern, Security Officers training at the rifle range at the old EPA station, cleaning contractors at the Receiving Warehouse and XCEL Energy Company transmission and distribution crews working in the substation. Use of a very conservative assumption of 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />s/week spent inside the site boundary by these groups would conservatively represent the most exposed individual. The annual whole body, skin and organ dose was computed using plant stack and reactor building vent X/Q and D/Q values for the Substation (a bounding location due to predominant wind direction and nearness to the release points) as input to the GASPAR code. This computed dose was reduced by the factor of 40/168 to account for limited occupancy.

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Dose to the Likely Most Exposed Member of the General Public from Reactor Releases and Other Nearby Uranium Fuel Cycle Sources (ODCM -08.01 section 2.1.4)

There are no other uranium fuel facilities in the vicinity of the Monticello site. The only artificial source of exposure to the general public in addition to the plant effluent releases is from direct radiation of the reactor and the steam turbines.

An Independent Spent Fuel Storage Facility (ISFSI) was constructed west of the plant in 2007. The initial loading campaign was completed in 2008 with 10 HCM's loaded with spent fuel. There was an additional loading campaign in 2013 with an additional 5 HCM's loaded with spent fuel. Neutron and Gamma monitoring results at the site boundary show no significant differences between these TLD's (Thermoluminescent Dosimeters) and the control TLD's.

Environmental TLD's were used to provide data on direct and skyshine radiation dose and the GASPAR code was used to provide data on dose from airborne pathways.

TLD results from the area of the site boundary and the 5 mile ring show no significant differences between these TLD's and the control TLD's.

Therefore, the likely most exposed member of the general public will not receive an annual radiation dose from reactor effluent releases and all other fuel cycle activities in excess of 40 CFR 190 standards of 25 millirem to the whole body, 75 millirem to the thyroid and 25 millirem to any other organ.

REMP (Radiological Environmental Monitoring Program) samples obtained from all 5 air sample stations and all three vegetation sampling locations during 2013 identified no detectable concentrations of isotopes that could be related to operation of the Monticello Nuclear Generating Plant.

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Changes in Land Use and Non Obtainable Milk or Vegetable Samples (ODCM -08.01 sections 2.1.8 and 2.1.9)

There were changes in land use resulting in changes to the sampling program. Both goat farms used in the sampling program stopped sampling their goats for milk in 2013 and were removed from the program.

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Table 1 Offsite Radiation Dose Assessment - Monticello PERIOD: January 1, through December 31, 2013 ASEUS POSE ,*E'S *LE Guidelines*.

Maximum Site Boundary Gamma Air Dose (mrad/year) 0.00841 10 Maximum Site Boundary Beta Air Dose (mrad/year) 0.00795 20 Maximum Off-Site Dose to Any Organ (mrem/year) 0.0491 15 Maximum Dose to the Likely Most Exposed Member of the General Public (mrem/year)

Whole Body 0.0472 5 Skin 0.0359 15 Max Organ (Thyroid) 0.0491 15 t FQ09 REjLE&S ES, Maximum Off-Site Dose (mrem)

Whole Body 1.28E-07 3 Max Organ (All except bone) 1.28E-07 10 40,CPR 190

,GASEOUS RELEASES LIMITS_____

Maximum Dose to Individuals due to their Activities Inside the Site Boundary (mrem)

Whole Body 0.0187 25 Thyroid 0.0240 75 Max Other Organ (Skin) 0.0230 25 Page 4 of 6

Table 2 Offsite Radiation Dose Assessment - Monticello Supplemental Information PERIOD: January 1, through December 31, 2013 GASVOIfS-REL LA SES Maximum Site Boundary Dose Location (from Reactor Building Vents)

Sector SSE Distance (miles) 0.4 Substation Sector SSE Distance from Plant Stack (miles) 0.2 Distance from Reactor Building Vents 0.2 Critical Receptor Location Sector SE Distance from Reactor Building Vents (miles) 1.1 Pathways Plume, Ground, Inhalation, Vegetable Age Group CHILD Organ THYROID L!Qt"P RELEASE St. Paul Drinking Water Intake Location Pathways Drinking Water Drinking Water, Fish Age Group Infant Adult Organ Whole Body GI Tract Dilution Factor (drinking water) 7:1 7:1 Page 5 of 6

Bases for Radiation Dose Statements Thermoluminescent dosimeters (TLD) are stationed around MNGP to measure the ambient gamma radiation field. Monitoring stations are placed near the site boundary and approximately five (5) miles from the reactor, in locations representing sixteen (16) compass sectors. Other locations are chosen to measure the radiation field at places of special interest such as nearby residences, meeting places and population centers. Control sites are located further than ten (10) miles from the site, in areas that should not be affected by plant operations. The results from the TLD's are reported in the Annual Radiological Environmental Monitoring Report. The results from this effort indicated no excess dose to offsite areas.

Additionally, NUREG-0543, METHODS FOR DEMONSTRATING LWR COMPLIANCE WITH THE EPA URANIUM FUEL CYCLE STANDARD (40 CFR PART 190) states in section IV, "As long as a nuclear plant site operates at a level below the Appendix I reporting requirements, no extra analysis is required to demonstrate compliance with 40 CFR Part 190". The organ and whole body doses reported in Table I are determined using 10 CFR 50 Appendix I methodology. The doses reported are well below the limits of Appendix I.

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