L-MT-11-021, Submittal of 2010 Radioactive Effluent Release Report

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Submittal of 2010 Radioactive Effluent Release Report
ML11133A388
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 05/12/2011
From: O'Connor T
Xcel Energy, Northern States Power Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L-MT-11-021
Download: ML11133A388 (31)
v • d • e


Text

Monticello Nuclear Generating Plant 2807 W County Road 75 jXceIEnergy Monticello, MN 55362 May 12, 2011 L-MT-1 1-021 Technical Specification 5.6.2 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket 50-263 Renewed Facility Operating License No. DPR-22 2010 Radioactive Effluent Release Report In accordance with Monticello Nuclear Generating Plant Technical Specificat in Section 5.6.2, the Northern States Power Company, (NSPM) a Minnesota corporation is submitting the following information as enclosures:

  • Radioactive Effluent Release Report for January 1 - December 31, 2010 (Enclosure 1)
  • Off-Site Radiation Dose Assessment for January 1 - December 31, 2010 (Enclosure 2), including Carbon-14 release and dose impact to most exposed member of the public (page 3)

Summary of Commitments This let/Makes no/no1/commitments and no revisions to existing commitments.

1J. O'Connor President, Monticello Nuclear Generating Plant States Power Company - Minnesota Enclosures (3) cc: Administrator, Region III, USNRC (w/o Enclosure 3)

Project Manager, Monticello, USNRC (w/o Enclosure 3)

Resident Inspector, Monticello, USNRC (w/o Enclosure 3)

Minnesota Department of Commerce (w/o Enclosure 3) j34 3

ENCLOSURE I RADIOACTIVE EFFLUENT RELEASE REPORT FOR JANUARY 1 - DECEMBER 31, 2010 22 pages follow

NUCLEAR MANAGEMENT COMPANY MONTICELLO NUCLEAR GENERATING PLANT License No. DPR-22 RADIOACTIVE EFFLUENT RELEASE REPORT Period Jan - Dec 2010 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 RADIOACTIVE EFFLUENT RELEASE REPORT Period Jan - Dec 2010 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
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 2
2. Total Time Period for Batch Releases 1220.0 min
3. Maximum Time Period for a Batch Release 876.0 min
4. Average Time Period for a Batch Release 610.0 min
5. Minimum Time Period for a Batch Release 344.0 min

Page 3 RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan - Dec 2010 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 2010 Table 1A Gaseous Effluents - Summation of all Releases Units 1st Qtr 2nd Qtr Est. Total Error, %

A. Fission & Activation gases

1. Total Release Ci 3.83E+02 3.56E+02 2.0OE+01
2. Average Release Rate uci/sec 4.93E+01 4.53E+01
3. Percent Tech Spec Qtrly Reporting Level Gamma Radiation  % 1.62E-01 1.47E-01 Beta Radiation 0% 4.92E-02 4.74E-02 B. Iodines
1. Total 1-131 Release Ci 3.36E-03 4.03E-03 1.OOE+01
2. Average 1-131 Release Rate uci/sec 4.32E-04 5.12E-04 C. Particulates
1. Total Particulates Ci 6.OOE-04 6.58E-04 3.00E+01
2. Average Release Rate uci/sec 7.71E-05 8.37E-05
3. Gross Alpha Radioactivity Ci 6.43E-07 5.10E-07 D. Tritium
1. Total Release Ci 4.52E+00 4.55E+00 1.OOE+01
2. Average Release Rate 1 uci/sec i 5.82E-01 I 5.79E-01 E. Percent Qtrly Tech Spec Reporting Levels
1. Iodines, Particulates, and Tritium  % 4.20E-01I 5.08E-01

Page 5 RADIOACTIVE EFFLUENT RELEASE REPORT Period  : Jan - Dec 2010 Table lA Gaseous Effluents - Summation of all Releases Units 3rd Qtr 4th Qtr Est. Total Error, %

A. Fission & Activation gases

1. Total Release Ci 3.98E+02 3.47E+02 2.00E+00
2. Average Release Rate uci/sec 5.01E+01 4.36E+01
3. Percent Tech Spec Qtrly Reporting Level Gamma Radiation 1.85E-01 1.53E-01 Beta Radiation %_ 5.35E-02 4.20E-02 B. Iodines
1. Total 1-131 Release Ci 4.10E-03 3.77E-03 J 1.OOE+01
2. Average 1-131 Release Rate uci/sec 5.16E-04 4.74E-04_1 C. Particulates
1. Total Particulates Ci 7.76E-04 5.47E-04 3.00E+01
2. Average Release Rate uci/sec 9.76E-05 6.88E-05
3. Gross Alpha Radioactivity Ci 5.11E-07 6.53E-07 D. Tritium
1. Total Release Ci 6.03E+00 5.08E+00 1.00E+01
2. Averaae Release Rate I uci/sec I 7.58E-01 I 6.39E-01 E. Percent Qtrly Tech Spec Reporting Levels
1. Iodines, Particulates, l and Tritium  % 5.03E-01 6.61E-01

Page 6 RADIOACTIVE EFFLUENT RELEASE REPORT Period Jan Dec 2010 Table lB Gaseous Effluents - Elevated Releases Continuous Mode Batch Mode Nuclides Released Unit 1st Qtr I 2nd Qtr 1st Qtr I 2nd Qtr

1. Fission Gases KR-85M Ci 5.77E-01 6.49E-01 0.OOE+00 0.OOE+00 KR-87 Ci 3.06E+00 3.20E+00 -0.OOE+00 O.OOE+00 KR-88 Ci 2.16E+00 2.39E+00 0.00E+00 O.00E+00 KR-89 Ci 3.62E+01 1.46E+01 O.OOE+00 0.OOE+00 XE-133 Ci 1.20E+02 9.71E+01 0.OOE+00 0.OOE+00 XE-133M Ci 3.20E+00 2.69E+00 0.OOE+00 0.OOE+00 XE-135 Ci 9.93E+00 1.27E+01 O.OOE+00 0.OOE+00 XE-135M Ci 2.47E+01 2.60E+01 0.OOE+00 O.OOE+00 XE-137 Ci 1.23E+02 1.31E+02 0.OOE+00 0.00E+00 XE-138 Ci 5.34E+01 5.80E+01 0.OOE+00 0.O0E+00 Total for Period Ci 3.76E+02 3.49E+02 0.OOE+00 0.OOE+00
2. Iodines 1-131 Ci 2.17E-03 2.56E-03 0.OOE+00 0.OOE+00 1-133 Ci 1.63E-02 1.83E-02 0.OOE+00 0.OOE+00 1-135 Ci 2.62E-02 2.84E-02 0.OOE+00 0.OOE+00 Total for Period Ci 4.47E-02 4.93E-02 0.OOE+00 0.OOE+00
3. Particulates CO-60 Ci 1.28E-06 8.85E-07 0.OOE+00 0.OOE+00 CS-137 Ci 5.21E-07 5.44E-07 0.OOE+00 0.OOE+00 BA-140 Ci 2.10E-04 2.61E-04 0.OOE+00 0.OOE+00 CE-141 Ci 0.OOE+00 5.11E-07 0.OOE+00 0.OOE+00 SR-89 Ci 6.01E-05 6.43E-05 0.OOE+00 0.OOE+00 SR-90 Ci 3.33E-07 3.54E-07 0.OOE+00 0.OOE+00

..Total for Period Ci 2.73E-04 3.28E-04 0.OOE+00 0.OOE+00

Page 7 RADIOACTIVE EFFLUENT RELEASE REPORT Period Jan - Dec 2010 Table lB Gaseous Effluents - Elevated Releases Continuous Mode Batch Mode Nuclides Released Unit 3rd Qtr I 4th Qtr 3rd Qtr I 4th Qtr

1. Fission Gases KR-85M Ci 7.20E-01 1.58E+00 0.OOE+00 0.OOE+00 KR-87 Ci 3.59E+00 5.09E+00 0.OOE+00 0.O0E+00 KR-88 Ci 2.46E+00 .4.84E+00 0.OOE+00 0.OOE+00-KR-89 Ci 2.92E+01 9.25E+00 0.OOE+00 0.OOE+00 XE-133 Ci 8.58E+01 6.15E+01 O.OOE+00 0.OOE+00 XE-133M Ci 2.34E+00 6.26E-01 0.OOE+00 0.OOE+00 XE-135 Ci 1.49E+01 2.98E+01 0.OOE+00 8.32E-04 XE-135M Ci 3.10E+01 3.92E+01 0.OOE+00 0.OOE+00 XE-137 Ci 1.53E+02 1.28E+02 0.OOE+00 0.OOE+00 XE-138 Ci 6.75E+01 6.03E+01 0.OOE+00 0.OOE+00 AR-41 Ci 0.OOE+00 0.OOE+00 0.OOE+00 1.60E-03 Total for Period Ci 3.91E+02 3.40E+02 O.OOE+00 2.43E-03
2. Iodines 1-131 Ci 2.62E-03 2.91E-03 0.OOE+00 1.10E-08 1-133 Ci 1.99E-02 1.54E-02 0.OOE+00 0.OOE+00 1-135 Ci 3.16E-02 2.25E-02 0.OOE+00 0.0OE+00 Total for Period Ci 5.41E-02 4.08E-02 0.OOE+00 1.10E-08
3. Particulates MN-54 Ci 0.OOE+00 3.18E-08 0.OOE+00 0.OOE+00 CO-60 Ci 1.12E-06 1.12E-06 0.OOE+00 0.OOE+00 ZN-65 Ci 0.OOE+00 5.67E-08 0.OOE+00 0.00E+00 CS-137 Ci 1.91E-06 8.37E-07 0.OOE+00 0.OOE+00 BA-140 Ci 2.53E-04 1.93E-04 0.OOE+00 0.OOE+00 CE-141 Ci 3.99E-07 6.72E-08 0.OOE+00 0.OOE+00 CE-144 Ci 1.64E-07 0.OOE+00 0.OOE+00 0.OOE+00 SR-89 Ci 1.39E-04 6.89E-05 0.O0E+00 O.OOE+00 SR-90 Ci 4.26E-07 3.19E-07 0.OOE+00 0.OOE+00 Total for Period Ci 3.96E-04 2.64E-04 0.OOE+00 0.OOE+00

Page 8 RADIOACTIVE EFFLUENT RELEASE REPORT Period  : Jan - Dec 2010 Table iC Gaseous Effluents - Building Vent Releases Continuous Mode Batch Mode Nuclides Released Unit 1st Qtr I 2nd Qtr 1st Qtr I 2nd Qtr

1. Fission Gases XE-133 Ci 4.95E-01 3.04E-01 0.OOE+00 0.OOE+00 XE-135 Ci 5.09E+00 4.98E+00 0.OOE+00 0.00E+00 XE-135M Ci 1.90E+00 2.23E+00 0.OOE+00 0.OOE+00 Total for Period Ci 7.49E+00 7.51E+00 0.60E+00 O.OOE+00
2. Iodines 1-131 Ci 1.19E-03 1.47E-03 0.OOE+00 0.0OE+00 1-133 Ci 1.07E-02 1.37E-02 0.OOE+00 0.OOE+00 1-135 Ci 1.88E-02 2.57E-02 0.OOE+00 0.OOE+00 Total for Period Ci 3.07E-02 4.09E-02 0.OOE+00 0.OOE+00
3. Particulates CO-60 Ci 1.03E-04 9.59E-05 O.OOE+00 0.00E+00 CS-137 Ci 6.94E-05 1.88E-05 0.OOE+00 0.OOE+00 BA-140 Ci 9.90E-05 1.53E-04 0.OOE+00 0.OOE+00 CE-141 Ci 7.18E-07 6.44E-07 0.OOE+00 0.OOE+00 SR-89 Ci 5.46E-05 6.20E-05 0.00E+00 0.OOE+00 Total for Period Ci 3.27E-04 3.31E-04 0.OOE+00 0.OOE+00

Page 9 RADIOACTIVE EFFLUENT RELEASE REPORT Period  : Jan - Dec 2010 Table IC Gaseous Effluents - Building Vent Releases Continuous Mode Batch Mode Nuclides Released Unit 3rd Qtr I 4th Qtr 3rd Qtr I 4th Qtr

1. Fission Gases XE-133 Ci 1.24E-01 3.18E-01 0.OOE+00 2.57E-02 XE-135 Ci 3.99E+00 3.20E+00 0.OOE+00 5.58E-03 XE-135M Ci .3.26E+00 2.97E+00 0.OOE+00 O.OE+.00 XE-138 Ci 3.32E-01 0.OOE+00 0.OOE+00 0.OOE+00 Total for Period Ci 7.70E+00 6.48E+00 0.OOE+00 3.13E-02
2. Iodines 1-131 Ci 1.48E-03 8.53E-04 0.OOE+00 2.48E-06 1-133 Ci 1.47E-02 7.79E-03 0.OOE+00 3.67E-06 1-135 Ci 2.60E-02 1.44E-02 0.OOE+00 O.OE+00 Total for Period Ci 4.22E-02 2.30E-02 0.OOE+00 6.15E-06
3. Particulates CO-60 Ci 9.15E-05 6.98E-05 0.OOE+00 0.OOE+00 CS-137 Ci 2.98E-05 5.95E-05 0.OOE+00 0.OOE+00 BA-140 Ci 1.67E-04 9.77E-05 0.OOE+00 0.OOE+00 SR-89 Ci 9.16E-05 5.58E-05 0.OOE+00 0.OOE+00-Total for Period Ci 3.80E-04 2.83E-04 0.OOE+00 0.00E+00

Page 10 RADIOACTIVE EFFLUENT RELEASE REPORT Period Jan - Dec 2010 Table 2A Liquid Effluents - Summation of all Releases Units 1st Qtr 2nd Qtr Est. Total Error, I 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 O.OOE+00 I B. Tritium
1. Total Release Ci 0.OOE+00 0.OOE+00 0.OOE+00
2. Avg Diluted Concentration uci/ml 0.OOE+00 0.OOE+00 C. Dissolved and Entrained Gases
1. Total Release Ci 0.OOE+00 0.OOE+00 I 0.OOE+00
2. Avg Diluted Concentration uci/ml 0.OOE+00 O.OOE+00_1 D. Percent Qtrly Tech Spec Reporting Level
1. Whole Body Dose %W I 0.OOE+00 0.OOE+00
2. Organ Dose 06 0.OOE+00 O.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 0.OOE+00 0.OOE+00 0.OOE+00 F. Volume of Dilution Water Used Liters 0.OOE+00 0.OOE+00 0.OOE+00 Table 2B Liquid Effluents Continuous Mode Batch Mode Nuclides Released Unit I1st Qtr I 2nd Qtr ist Qtr I 2nd Qtr None Released This Period

Page 11 RADIOACTIVE EFFLUENT RELEASE REPORT Period Jan - Dec 2010 Table 2A Liquid Effluents - Summation of all Releases Units 3rd Qtr 4th Qtr Est. Total Error, 0i 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 0.OOE+00 0.OOE+00 0.OOE+00
2. Avg Diluted Concentration uci/ml 0.OOE+00 0.OOE+00_I C. Dissolved and Entrained Gases
1. Total Release Ci 0.OOE+00 0.00E+00 0.00E+00
2. Avg Diluted Concentration uci/mlI 0.OOE+00 0.OOE+00_1 D. Percent Qtrly Tech Spec Reporting Level
1. Whole Body Dose I  % 0.OOE+00 0.OOE+00
2. Organ Dose  % 0.OOE+00 0.OOE+00 E. Gross Alpha Radioactivity
1. Total Release Ci 0.00E+00 -0.00E+00 0.OOE+00 IF. Volume of Waste Released Liters 0.OOE+00 0.OOE+00 0.OOE+00 IF. Volume of Dilution Water Used Liters 0.OOE+00 0.OOE+00 0.OOE+00 Table 2B Liquid Effluents Continuous Mode Batch Mode Nuclides Released Unit 3rd Qtr I 4th Qtr 3rd Qtr I 4th Qtr None Released This Period

Page 12 RADIOACTIVE EFFLUENT RELEASE REPORT Period  : Jan - Dec 2010 Table 3 Solid Waste and Irradiated Fuel Shipments

  • SEE ATTACHED REPORTS
  • NRC Regulatory Guide 1.21 Reports -Page 1 Report Date : 3/28/2011 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2010 to 12/31/2010 Percent Cutoff: 0 Waste Stream : Resins, Filters, and Evap Bottoms Charcoal and Bead 2009 Condensate ResiiPO09483-16 Cond cWaste. Volume Curies  % Error Class FtA3 MA3 Shipped (Ci)

A .6.74E+02 1.91 E+01 2.59E+01 +/-25%

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

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

All 6.74E+02 1.91E+01 2.59E+01 +/-25%

Waste Stream Dry Active Waste DAW-U-NA DAW-U-NA Cond Demin Elem Asbestos Trash Liner Waste Volume Curies %Error Class FtA3 MA3 Shipped (Ci)

A 7.91E+03 2.24E+02 5.11E-01 +/-25%

B O.OOE+00 0.OOE+00 0.OOE+00 +/-25%

C O.OOE+00 O.OOE+00 0.OOE+00 +/-25%

All 7.91 E+03 2.24E+02 5.11E-01 +/-25%

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

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

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

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

All 0.OOE+00 0.OOE+00 0.OOE+00 +/-25%

NRC Regulatory Guide 1.21 Reports Page 2 Report Date: .- 3/28/2011 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From .01101/2010 to 12/31/2010 Percent Cutoff:. 0 Waste Stream : Other Waste Drywell Sump Water DW Sump Overpack Waste Volume Curies  % Error Class. FtA3 MA3 Shipped (Ci)

A 9.80E+01 2.78E+00 4.44E+00 +/-25%

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

C 0.0OE+00 0.OOE+00 0.OOE+00 +/-25%

All 9.80E+01 2.78E+00 4.44E+00 +/-25%

Waste Stream : Sum of All 4 Categories DAW-U-NA DAW-U-NA Cond Demin Elem Charcoal and Bead Asbestos 2009 Condensate Res Trash Liner P0009483-16 Cond Drywell Sump Water DW Sump Overpack Waste Volume Curies %Error Class FtA3 MA3 Shipped (Ci)

A 8.68E+03 2.46E+02 3.09E+01 +/-25%

B 0.OOE+00 0.OOE+00 0.OOE+00 +i-25%

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

All 8.68E+03 2.46E+02 3.09E+01 +/-25%

-Combined Waste Type Shipment, Major Volume Waste Type Shown

NRC Regulatory Guide 1.21 Reports Page 1 Report Date 3/28/2011 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2010 to 12/31/2010 Percent Cutoff: 0 Resins, Filters, and Evap Bottom Waste Class A Nuclide Name Percent Abundance Curies H-3 0.624% 1.62E-01 C-14 0.472% 1.22E-01 Cr-51 0.016% 4.23E-03 Mf-54 1.599% 4.14E-01 Fe-55 25.023% - .48E+00 Fe-59" 0.006% 1.43E-03 Co-57 0.001% 2.02E-04 Co-58 0.281% 7.29E-02 Co-60 24.888% 6.45E+00 Ni-63 1.599% 4.14E-01 Zn-65 2.506% 6.49E-01 Sr-89 0.724% 1.88E-01 Sr-90 0.454% 1.17E-01 Nb-95 0.007% 1.80E-03 Nb-97 0.000% 2.28E-15 Tc-99 0.178% 4.61E-02 Tc-99m 0.000% 4.74E-21 Ag-1lOm 0.026% 6.81E-03 1-129 0.002% 6.18E-04 1-131 3.603% 9.33E-01 1-133 0.003% 8.06E-04 Cs-134 0.056% 1.45E-02 Cs-1 37 33.278% 8.62E+00 Ba-140 3.090% 8.OOE-01 La-140 0.524% 1.36E-01 Ce-141 0.760% 1.97E-01 Ce-144 0.259% 6.71E-02 Pu-238 0.003% 7.14E-04 Pu-239 0.001% 3.46E-04 Pu-241 0.012% 3.14E-03 Am-241 0.002% 6.29E-04 Cm-242 0.001% 1.34E-04 Cm-243 0.001% 1.91E-04 Cm-244 0.000% 4.15E-06 Resins, Filters, and Evap Bottom Waste Class All Nuclide Name Percent Abundance Curies H-3 0.624% 1.62E-01 C-14 0.472% 1.22E-01 Cr-51 0.016% 4.23E-03 Mn-54 1.599% 4.14E-01 Fe-55 25.023% 6.48E+00 Fe-59 0.006% 1.43E-03 Co-57 0.001% 2.02E-04 Co-58 0.281% 7.29E-02 Co-60 24.888% 6.45E+00 N

NRC Regulatory Guide 1.21 Reports Page 2 Report Date : 3/28/2011 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2010 to 12/31/2010 Percent Cutoff: 0 Ni-63 1.599% 4.14E-01 Zn-65 2.506% 6.49E-01 Sr-89 0.724% 1.88E-01 Sr-90 0.454% 1.17E-01 Nb-95 0.007% 1.80E-03 Nb-97 0.000% 2.28E-15 Tc-99 0.178% 4.61E-02 Tc-99m 0.000% 4.74E-21 Ag-110m 0.026% 6.81E-03 1-129 0.002% 6.18E-04 1-131 3.603%. 9.33E-01 1-133 0.003% 8.06E-04 Cs-134 0.056% 1.45E-02 Cs-137 33.278% 8.62E+00 Ba-140 3.090% 8.OOE-01 La-140 0.524% 1.36E-01 Ce-141. 0.760% 1.97E-01 Ce-144 0.259% 6.71 E-02 Pu-238 0.003% 7.14E-04 Pu-239 0.001% 3.46E-04 Pu-241 0.012% 3.14E-03 Am-241 0.002% 6.29E-04 Cm-242 0.001% 1.34E-04 Cm-243 0.001% 1.91 E-04 Cm-244 0.000% 4.15E-06 Dry Active Waste Waste Class A Nuclide Name Percent Abundance Curies H-3 0.366% 1.87E-03 C-14 0.033% 1.71E-04 Cr-51 9.258% 4.73E-02 Mn-54 6.460% 3.30E-02 Fe-55 32.588% 1.67E-01 Fe-59 1.868% 9.55E-03 Co-58 1.503% 7.69E-03 Co-60 36.125% 1.85E-01 Ni-63 0.726% 3.71 E-03 Zn-65 3.287% 1.68E-02 Sr-89 0.216% 1.1OE-03 Sr-90 0.018% 9.21 E-05 Zr-95 0.403% 2.06E-03 Nb-95 0.737% 3.77E-03 Ru-103 0.170% 8.71E-04 Ag-110m 0.088% 4.49E-04 Sb-124 0.168% 8.62E-04 1-131 0.625% 3.20E-03 Cs-137 4.267% 2.18E-02 Ba-140 0.152% 7.76E-04 La-140 0.001% 4.94E-06 Ce-141 0.208% 1.06E-03

NRC Regulatory Guide 1.21 Reports Page 3 Report Date: 3/28/2011 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2010 to 12/31/2010 Percent Cutoff: 0 Ce-144 0.183% 9.38E-04 Pu-238 0.007% 3.62E-05 Pu-239 0.004% 2.21 E-05 Pu-240 0.000% 4.09E-07 Pu-241 0.501% 2.56E-03 Am-241 0.037% 1.89E-04 Cm-242 0.000% 2.93E-07 Cm-243 0.000% 9.21 E-07 Cm-244 0.000% 9.21 E-07 Dry Active Waste Waste Class All Nuclide Name Percent Abundance Curies H-3 0.366% 1.87E-03 C-14 0.033% 1.71 E-04 Cr-51 9.258% 4.73E-02 Mn-54 6.460%. 3.30E-02 Fe-55 32.588% 1.67E-01 Fe-59 1.868% 9.55E-03 Co-58 1.503% 7.69E-03 Co-60 36.125% 1.85E-01 Ni-63 0.726% 3.71 E-03 Zn-65 3.287% 1.68E-02 Sr-89 0.216% 1.10E-03 Sr-90 0.018% 9.21 E-05 Zr-95 0.403% 2.06E-03 Nb-95 0.737% 3.77E-03 Ru-103 0.170% 8.71E-04 Ag-110m 0.088% 4.49E-04 Sb-124 0.168% 8.62E-04 1-131 0.625% 3.20E-03 Cs-137 4.267% ... 2.18E-02 Ba-140 0.152% 7.76E-04 La-140 0.001% 4.94E-06 Ce-141 0.208% 1.06E-03 Ce-144 0.183% 9.38E-04 Pu-238 0.007% 3.62E-05 Pu-239 0.004%. 2.21 E-05 Pu-240 0.000% 4.09E-07 Pu-241 0.501% 2.56E-03 Am-241 0.037% 1.89E-04 Cm-242 0.000% 2.93E-07 Cm-243 0.000% 9.21 E-07 Cm-244 0.000% 9.21 E-07 Other Waste Waste Class A Nuclide Name Percent Abundance Curies H-3 0.059% 2.64E-03 Mn-54 0.062% 2.75E-03 Fe-55 73.260% 3.25E+00

NRC Regulatory Guide 1.21 Reports Page 4 Report Date: 3/28/20111 Solid Waste.Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream

.During Period From 01/01/2010 to 12/31/2010 Percent Cutoff: 0 Co-60 23.379% 1.04E+00 Nk59 0.043% 1.93E-03 Ni-63 3.058% 1.36E-01 Sr-89 0.000% 1.49E-05 Sr-90 0.001% 5.63E-05 Nb-94 0.009% 3.79E-04 Cs-137 0.073% 3.24E-03 Ce-144 0.018% 8.12E-04 Pu-238 0.005% 2.09E-04 Pu-239 0.002% 8.16E-05 Pu-241 0.028% 1.22E-03 Am-241 0.002% 9.05E-05 Cm-242 0.000% 1.05E-06 Cm-243 0.001% 2.85E-05 Other Waste Waste Class All Nuclide Name Percent Abundance Curies H-3 0.059% 2.64E-03 Mn-54 0.062% 2.75E-03 Fe-55 73.260% 3.25E+00 Co-60 23.379% 1.04E+00 Ni-59 0.043% 1.93E-03 Ni-63 3.058% 1.36E-01 Sr-89 0.000% 1.49E-05 Sr-90 0.001% 5.63E-05 Nb-94 0.009% 3.79E-04 Cs-1 37 0.073% 3.24E-03.

Ce-144 0.018% 8.12E-04 Pu-238 0.005% 2.09E-04 Pu-239 0.002% 8.16E-05 Pu-241 0.028% 1.22E-03 Am-241 0.002% 9.05E-05 Cm-242 0.000% 1.05E-06 Cm-243 0.001% 2.85E-05 Sum of All 4 Categories Waste Class A Nuclide Name Percent Abundance Curies H-3 0.539% 1.66E-01 C-14 0.397% 1.22E-01 Cr-51 0.167% 5.16E-02 Mn-54 1.459% 4.50E-01 Fe-55 32.092% 9.90E+00 Fe-59 0.036% 1.10E-02 Co-57 0.001% 2.02E-04 Co-58 0.261% 8.06E-02 Co-60 24.857% 7.67E+00 Ni-59 0.006% 1.93E-03 Ni-63 1.795% 5.54E-01 Zn-65 2.159% 6.66E-01

NRC Regulatory Guide 1.21 Reports Page 5 Report Date : 3/28/2011 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2010 to 12/31/2010 Percent Cutoff: 0 Sr-89 0.612% 1.89E-01 Sr-90 0.381% 1.18E-01 Zr-95 0.007% 2.06E-03 Nb-94 0.001% 3.79E-04 Nb-95 0.018% 5.56E-03 Nb-97 0.000% 2.28E-15 Tc-99 0.149% 4.61 E-02 Tc-99m 0.000% 4.74E-21 Ru-103 0.003% 8.71E-04 Ag-110m 0.024% 7.26E-03 Sb-124 0.003% 8.62E-04 1-129 0.002% 6.18E-04 1-131 3.035% 9.36E-01 1-133 0.003% 8.06E-04 Cs-134 0.047% 1.45E-02 Cs-137 28.018% 8.64E+00 Ba-140 2.596% 8.01E-01 La-140 0.440% 1.36E-01 Ce-141 0.641% 1.98E-01 Ce-144 0.223% 6.88E-02 Pu-238 0.003% 9.59E-04 Pu-239 0.001% 4.50E-04 Pu-240 0.000% 4.09E-07 Pu-241 0.022% 6.92E-03 Am-241 0.003% 9.09E-04 Cm-242 0.000% 1.36E-04 Cm-243 0.001% 2.20E-04 Cm-244 0.000% 5.08E-06 Sum of All 4 Categories Waste Class All Nuclide Name Percent Abundance Curies H-3 0.539% 1.66E-01 C-14 0.397% 1.22E-01 Cr-51 0.167% 5.16E-02 Mn-54 1.459% 4.50E-01 Fe-55 32.092% 9.90E+00 Fe-59 0.036% 1.10E-02 Co-57 0.001% 2.02E-04 Co-58 0.261% 8.06E-02 Co-60 24.857% 7.67E+00 Ni-59 0.006% 1.93E-03 Ni-63 1.795% 5.54E-01 Zn-65 2.159% 6.66E-01 Sr-89 0.612% 1.89E-01 Sr-90 0.381% 1.18E-01 Zr-95 0.007% 2.06E-03 Nb-94 0.001% 3.79E-04 Nb-95 0.018% 5.56E-03 Nb-97 0.000% 2.28E-15 Tc-99 0.149% 4.61 E-02

NRC Regulatory Guide 1.21 Reports Page 6 Report Date: 3/28/2011 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2010 to 12/31/2010 Percent Cutoff: . 0 Tc-99m 0.000% 4.74E-21 Ru-103 0.003% 8.71 E-04 Ag-i 1Om 0.024% 7.26E-03 Sb-124 0.003% 8.62E-04 1-129 0.002% 6.18E-04 1-131 3.035% 9.36E-01 I-133 0.003% 8.06E-04 Cs-134 0.047% 1.45E-02 Cs-137 28.018% 8.64E+00 Ba-140 2.596% 8.01 E-01 La-140 0.440% 1.36E-01 Ce-141 0.641% 1.98E-01 Ce-144 0.223% 6.88E-02 Pu-238 0.003% 9.59E-04 Pu-239 0.001% 4.50E-04 Pu-240 0.000% 4.09E-07 Pu-241 0.022% 6.92E-03 Am-241 0.003% 9.09E-04 Cm-242 0.000% 1.36E-04 Cm-243 0.001% 2.20E-04 Cm-244 0.000% 5.08E-06

NRC Regulatory Guide 1.21 Reports Page 1 Report Date: 3/28/2011 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2010 to 12/31/2010 Number of Shipments Mode of Transportation Destination 1 Hittman Transport Energy Solutions Bear Creek 1 Hittman Transport Energy Solutions Gallaher Rd.

4 Hittman Transport EnergySolutions LLC.

1 Hittman Transport Studsvik Processing Facility Memphis 6 Xcel Energy Trucking Studsvik Processing Facility Memphis

NRC Regulatory Guide 1.21 Reports Page

. Report Date : 3/28/2011 Solid Waste Shipped Offsite for Disposal and Estimates of Major Nuclides by Waste Class and Stream During Period From 01/01/2010 to 12/31/2010 Manifest Number Date Shipped Waste Volume Used Burial volume Used 10-55 11/30/2010 Yes 10-54 11/8/2010 Yes 10-41 8/6/2010 Yes 10-34 7/20/2010 Yes 10-31 7/8/2010 Yes 10-28 6/25/2010 Yes 10-27 6/11/2010 Yes 10-26 6/9/2010 Yes 10-25 5/25/2010 Yes 10-23 5/18/2010 Yes 10-20 5/12/2010 Yes 10-14 4/16/2010 Yes 10-06 2/5/2010 Yes

ENCLOSURE 2 OFF-SITE RADIATION DOSE ASSESSMENT FOR JANUARY 1 - DECEMBER 31, 2010 6 pages follow

MONTICELLO NUCLEAR GENERATING PLANT Offsite Radiation Dose Assessment for January 1, - December 31, 2010 An assessment of radiation dose due to releases from the Monticello Nuclear Generating Plant during 2010 was performed in accordance with the Offsite Dose Calculation Manual (ODCM). Computed doses were well 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 2010.

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 and organ dose due to gaseous releases are a small percentage of Appendix I Guidelines.

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

Dose from liquid releases are listed in Table 1.

There were no liquid releases in 2010.

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 1. 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. Neutron and Gamma monitoring results at the site boundary show no significant differences between these TLD's 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.

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

There were several changes in land use resulting in significant increases in calculated doses. One onsite monitoring well (M-52) was added to the program in the fourth quarter of 2010 and analyzed for tritium and gamma-emitting isotopes. A residence obtaining Goat Milk for retail sale was identified during performance of the Annual Land Use Census and was added to the program (M- 16, Kitzman Residence). Additionally a Control Goat Milk residence was added to the program (M-17, Greniger Residence). The goat farms were added to the program in October of 2010. Both goat farms are seasonal and only obtain milk samples from March to November. As a result there were no goat milk samples obtained after November 2 4 th for M- 16 and October 2 8th for the control location (M-17). There were no vegetable samples that could not be obtained during this reporting period.

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Carbon 14 C-14 curies generated were determined by calculation, as defined in EPRI "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents". All curies generated will be assumed to be released within the period of interest, with no credit taken for hold-up.

Release (From EPRI Calc, adjusted for power operation only)

Total 1st 2nd 3rd 4th C-14 (Ci) 6.5 1.7 1.7 1.7 1.4 C-14 dose calculations were made using the dose factors and the methodology of Regulatory Guide 1.109.

Dose (based on RG-1.109, growing seasons factored)

Total 1st 2nd 3rd 4th C-14 (mrem) 0.01610 0 0.00632 0.00977 0 The inhalation dose was calculated using all the C-14 calculated to be released.

The other pathways, milk and leafy vegetables, depend on the amount consumed by goats and people; forage for goats and vegetables for people. Incorporation only occurs via photosynthesis. Photosynthesis only incorporates 14C0 2 and only occurs during the growing season. Monticello conservatively chose to use 50% of the C-14 released for this calculation.

Dose to the Critical Receptor is performed in the fall of each year and reported in the Annual Report for that year. The determination of the Critical Receptor uses the source term from the previous year since the source term for the year of the calculation has not been determined yet. The Critical Receptor parameters used in this report do not use C-14 in the calculation since C-14 release was not calculated for 2009.

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Table 1 Offsite Radiation Dose Assessment - Monticello PERIOD: January 1, through December 31, 2010 Maximum Site Boundary (iamma Air Dose U.0 153 (mrad/year) 10 Maximum Site Boundary Beta Air Dose 0.0212 (mrad/year) 20 Maximum Off-Site Dose to Any Organ (mrem/year) 0.1150 15 Maximum Dose to the Likely Most Exposed Member of the General Public (mremlyear)

Whole Body 0.0446 5 Skin 0.0315 15 Max Organ (Thyroid) 0.1150 15 Maximum Off-Site Dose (mrem)

Whole Body 0 3.

Max Organ (All except bone) 0 10 Maximum Dose to Individuals due to their Activities Inside the Site Boundary (mrem)

Whole Body 0.0139 25

. Thyroid 0.0178 75 Max Other Organ (Skin) 0.0192 *25 Page 4 of 6

Table 2 Offsite Radiation Dose Assessment - Monticello Supplemental Information PERIOD: January 1, through December 31, 2010 maximum s1te tsouncary Dose Location (from Reactor Building Vents)

Sector SSE Distance (miles) 0.40 Substation Sector S Distance from Plant Stack (miles) 0.2 Distance from Reactor Building Vents 0.2 Critical Receptor Location Sector SSE Distance from Reactor Building Vents (miles) 3.0 Pathways Plume, Ground, Inhalation, Goat Milk Age Group INFANT Or anTHYROID 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 (REMP).

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 1 are determined using 10 CFR 50 Appendix I methodology. The doses reported are well below the limits of Appendix I.

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