ML091540519

Enclosures 1 and 2 - Radioactive Effluent Release Report and Off-Site Radiation Dose Assessment for January 1 - December 31, 2008

ML091540519
Person / Time
Site:	Monticello
Issue date:	05/14/2008
From:	O'Connor T Northern States Power Co, Xcel Energy
To:	Office of Nuclear Reactor Regulation
References
FOIA/PA-2010-0209, L-MT-09-037
Download: ML091540519 (21)

Text

ENCLOSURE 1 RADIOACTIVE EFFLUENT RELEASE REPORT FOR JANUARY 1 -DECEMBER 31, 2008 NUCLEAR MANAGEMENT COMPANY MONTICELLO NUCLEAR GENERATING PLANT License No. DPR-22 RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan -Dec 2008 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 2008 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 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 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 1357.0 min 3. Maximum Time Period for a Batch Release 996.0 min 4. Average Time Period for a Batch Release 678.5 min 5. Minimum Time Period for a Batch Release 361.0 min Page 3 RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan -Dec 2008 Supplemental Information (continued)

6. Abnormal Releases A. Liquid : 1. Number of Releases

2. Total Activity Released 0 0.0 Ci B. Gaseous : 1. Number of Releases

2. Total Activity Released 0 0.0 Ci Page 4 RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan -Dec 2008 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. 43E+02 2 .54E+02 2.0E0l1 2. Averaqe Release Rate uci/sec 1. 84E+01 3 .23E+01 3. Percent Tech Spec Qtrly Reporting Level Gamma Radiation 066.43E-02 1.15E-01 Beta Radiation %_ _ 2.34E-02 3.89E-02 B. Iodines 1. Total 1-131 Release Ci 8.45E-04 2.19E-03 1.OOE+01 2. Average 1-131 Release Rate uci/sec 1.09E-04 2.79E-04 C. Particulates

1. Total Particulates Ci 2.87E-04 1.52E-03 3.OOE+01 2. Average Release Rate uci/sec 3.70E-05 1.93E-04 3. Gross Alpha Radioactivity Ci 1.14E-06 4.79E-07 D. Tritium 1. Total Release Ci 6.05E+00 6.29E+00 1.OOE+01 1 2. Averaqe Release Rate I uci/sec I 7.78E-01 I 7.99E-01 E. Percent Qtrly Tech Spec Reporting Levels 1. Iodines, Particulates, I and Tritium % 1.34E-01 3.69E-01 Page 5 RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan -Dec 2008 Table 1A Gaseous Effluents

-Summation of all Releases Units 3rd Qtr 4th Qtr Est. Total Error, %A. Fission & Activation gases 1. Total Release Ci 2.65E+02 3.97E+02 2.OOE+01 2. Average Release Rate uci/sec 3.34E+01 5.OOE+0l 3. Percent Tech Spec Qtrly Reporting Level Gamma Radiation

% 1.34E-01 3.07E-01 Beta Radiation

%6 3.83E-02 8.06E-02 B. Iodines 1. Total 1-131 Release Ci 4.19E-03 5.08E-03 L1.OOE+01 2. Average 1-131 Release Rate uci/sec 5.27E-04 6.39E-04 C. Particulates

1. Total Particulates Ci 5.88E-04 8.71E-04 3.OOE+01 2. Average Release Rate uci/sec 7.40E-05-[

1.10E-04 3. Gross Alpha Radioactivity Ci 5.51E-07 5.78E-07 D. Tritium 1. Total Release Ci 9.07E+00 9.87E+00 l1.OOE+01 I 2. Average Release Rate I uci/sec 1 1.14E+00 I 1.24E+00-I E. Percent Qtrly Tech Spec Reporting Levels 1. Iodines, Particulates, and Tritium 5.35E-01 0 .0E+00 Page 6 RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan -Dec 2008 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 4.08E-01 4.22E-01 0.OOE+00 0.OOE+00 KR-87 Ci 2.09E+00 2.47E+00 0.OOE+00 0.OOE+00 KR-88 Ci 1.59E+00 1.74E+00 0.OOE+00 0.00E+00 KR-89 Ci 6.22E+00 1.73E+01 0.00E+00 0.OOE+00 XE-133 Ci 3.64E+01 7.55E+01 0.OOE+00 0.OOE+00 XE-133M Ci 5.77E-01 2.16E+00 0.OOE+00 0.OOE+00 XE-135 Ci 4.94E+00 1.23E+01 0.OOE+00 0.OOE+00 XE-135M Ci 9.03E+00 1.97E+01 0.OOE+00 0.OOE+00 XE-137 Ci 5.16E+01 7.81E+01 0.OOE+00 0.OOE+00 XE-138 Ci 2.66E+01 3.68E+01 0.OOE+00 0.OOE+00 Total for Period Ci 1.39E+02 2.46E+02 0.OOE+00 0.OOE+00 2. Iodines 1-131 Ci 4.63E-04 1.13E-03 0.OOE+00 0.OOE+00 1-133 Ci 4.40E-03 1.22E-02 0.OOE+00 0.OOE+00 1-135 Ci 8.13E-03 2.26E-02 0.OOE+00 0.OOE+00 Total for Period Ci 1.30E-02 3.60E-02 0.OOE+00 0.OOE+00 3. Particulates CO-60 Ci 6.32E-07 5.61E-07 0.OOE+00 0.OOE+00 BA-140 Ci 5.02E-05 1.01E-04 0.OOE+00 0.OOE+00 SR-89 Ci 1.72E-05 2.63E-06 0.OOE+00 0.OOE+00 SR-90 Ci 1.24E-07 9.68E-09 0.OOE+00 0.OOE+00 Total for Period Ci 6.81E-05 1.04E-04 0.OOE+00 0.OOE+00 Page 7 RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan -Dec 2008 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 4.73E-01 8.02E-01 1.09E-01 0.OOE+00 KR-87 Ci 2.65E+00 4.07E+00 0.OOE+00 0.OOE+00 KR-88 Ci 1.70E+00 2.69E+00 3.76E-02 0.OOE+00 KR-89 Ci 2.91E+01 5.62E+01 0.OOE+00 0.OOE+00 XE-133 Ci 6.77E+01 7.93E+01 2.07E+01 1.33E-02 XE-133M Ci 1.87E+00 2.31E+00 4.01E-01 0.OOE+00 XE-135 Ci 1.08E+01 1.26E+01 3.G6E+00 0.OOE+00 XE-135M Ci 1.17E+01 2.OOE+01 0.OOE+00 0.OOE+00 XE-137 Ci 7.16E+01 1.38E+02 0.OOE+00 0.OOE+00 XE-138 Ci 3.42E+01 5.78E+01 0.OOE+00 0.OOE+00 Total for Period Ci 2.32E+02 3.74E+02 2.49E+01 1.33E-02 2. Iodines 1-131 Ci 2.49E-03 1.75E-03 5.64E-07 7.11E-09 1-133 Ci 1.54E-02 1.81E-02 1.60E-06 0.OOE+00 1-135 Ci 2.67E-02 3.39E-02 9.75E-07 0.OOE+00 Total for Period Ci 4.46E-02 *5.37E-02 3.14E-06 7.11E-09 3. Particulates CR-51 Ci 3.23E-06 0.OOE+00 0.OOE+00 0.OOE+00 MN-54 Ci 1.35E-07 0.OOE+00 0.OOE+00 0.OOE+00 CO-58 Ci 8.13E-08 0.OOE+00 0.OOE+00 0.OOE+00 CO-60 Ci 1.13E-06 0.OOE+00 0.OOE+00 0.OOE+00 ZN-65 Ci 1.62E-07 0.OOE+00 0.OOE+00 0.OOE+00 NB-95 Ci 4.91E-08 0.OOE+00 0.00E+00 0.OOE+00 CS-137 Ci 3.10E-06 9.85E-08 0.OOE+00 0.OOE+00 BA-140 Ci 1.67E-04 1.81E704 0.OOE+00 0.OOE+00 CE-141 Ci 2.42E-07 7.69E-08 O.OOE+00 0.OOE+00 CE-144 Ci 9.77E-07 1.81E-07 0.OOE+00 0.OOE+00 SR-89 Ci 1.75E-04 6.83E-05 0.00E+00 O.OOE+00 SR-90 Ci 3.41E-07 4.58E-07 O.OOE+00 O.OOE+00 Total for Period Ci 3.51E-04 2.50E-04 O.OOE+00 O.OOE+00 Page 8 RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan -Dec 2008 Table 1C 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-135 Ci 3.47E+00 5.81E+00 0.OOE+00 0.OOE+00 XE-135M Ci 0.OOE+00 1.73E+00 0.OOE+00 0.OOE+00 Total for Period Ci 3.47E+00 7.54E+00 0.OOE+00 0.OOE+00 2. Iodines 1-131 Ci 3.81E-04 1.06E-03 0.OOE+00 0.OOE+00 1-133 Ci 2.55E-03 9.38E-03 0.OOE+00 0.OOE+00 1-135 Ci 0.OOE+00 1.51E-02 0.OOE+00 0.OOE+00 Total for Period Ci 2.93E-03 2.55E-02 0.OOE+00 0.OOE+00 3. Particulates CO-60 Ci 7.91E-05 1.22E-04 0.OOE+00 0.OOE+00 CS-137 Ci 9.07E-05 3.91E-05 0.OOE+00 0.OOE+00 BA-140 Ci 2.37E-05 9.76E-05 0.OOE+00 0.OOE+00 SR-89 Ci 2.58E-05 1.15E-03 0.OOE+00 O.OOE+00 SR-90 Ci 0.OOE+00 8.40E-06 0.OOE+00 0.OOE+00 Total for Period Ci 2.19E-04 1.41E-03 0.OOE+00 0.OOE+00 Page 9 RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan -Dec 2008 Table 1C 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 1.49E+00 2.00E+00 0.OOE+00 0.OOE+00 XE-135 Ci 4.22E+00 9.04E+00 0.OOE+00 0.OOE+00 XE-135M Ci 2.94E+00 1.23E+01 0.OOE+00 0.OOE+00 XE-138 Ci 0.OOE+00 2.62E-01 0.OOE+00 0.OOE+00 Total for Period Ci 8.65E+00 2.36E+01 0.00E+00 0.OOE+00 2. Iodines 1-131 Ci 1..70E-03 3.33E-03 0.00E+00 O.OOE+00 1-133 Ci 1.19E-02 3.81E-02 0.00E+00 0.OOE+00 1-135 Ci 1.92E-02 9.04E-02 0.OOE+00 O.OOE+00 Total for Period Ci 3.28E-02 1.32E-01 0.OOE+00 0.OOE+00 3. Particulates CR-51 Ci 0.OOE+00 2.69E-06 0.OOE+00 0.OOE+00 CO-60 Ci 4.10E-05 4.21E-05 0.OOE+00 0.OOE+00 CS-137 Ci 2.54E-05 3.02E-05 0.OOE+00 0.OOE+00 BA-140 Ci 1.27E-04 4.40E-04 0.OOE+00 0.OOE+00 CE-141 Ci 1.20E-06 6.10E-06 0.OOE+00 0.OOE+00 SR-89 Ci 4.20E-05 9.97E-05 0.OOE+00 0.OOE+00 Total for Period Ci 2.37E-04 6.21E-04 0.OOE+00 0.OOE+00 Page 10 RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan -Dec 2008 Table 2A Liquid Effluents

-Summation of all Releases Units 1st Qtr 2nd Qtr Est. Total UnitsError, A. Fission & Activation products 1. Total Release (not including tritium, gases, alpha) Ci 0.00E+00 0.OOE+00 0.00E+00 2: Avg Diluted Concentration uci/ml 0.00E+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 0.00E+00_I C. Dissolved and Entrained Gases 1. Total Release Ci 0.OOE+00 0.OOE+00 0.OOE+00 2. Avg Diluted Concentration uci/ml 0.00E+00 0.OOE+00 D. Percent Qtrly Tech Spec Reporting Level 1. Whole Body Dose % I0.OOE+00 0.OOE+00_2. Organ Dose % 0.OOE+00 0.OOE+00 E. Gross Alpha Radioactivity

1. Total Release Ci 0.OOE+00 0.OOE+00 0.00E+00 F. Volume of Waste Released Liters 0.00E+00 0.OOE+00 0.OOE+00 IF. Volume of Dilution Water Used7 Liters I 0.OOE+00 I 0.OOE+00 I 0.00E+00 Table 2B Liquid Effluents Continuous Mode Batch Mode Nuclides Released Unit I1st Qtr. 1 2nd Qtr 1st Qtr I 2nd Qtr None Released This Period Page 11 RADIOACTIVE EFFLUENT RELEASE REPORT Period Jan -Dec 2008 Table 2A Liquid Effluents

-Summation of all Releases Units 3rd Qtr 4th Qtr Est. Total Error, '6 A. Fission & Activation products 1. Total Release (not including.1 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 0.0OE+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.OOE+00 0.OOE+00 D. Percent Qtrly Tech Spec Reporting Level 1. Whole Body Dose % I 0.OOE+00 0.OOE+00 2. Organ Dose 36 0.OOE+00 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 0.00E+00 0.OOE+00 0.OOE+00 IF. Volume of Dilution Water Used7 Liters 0.OOE+00 0.OOE+00 0.OOE+00 Table 2B Liquid Effluents Nuclides Released Continuous Mode Batch Mode Unit 3rd Qtr I 4th Qtr 3rd Qtr I 4th Qtr None Released This Period Page 12 RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan -Dec 2008 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 12-month Est. Total Period Error, A. Spent resins, filter sludges, Cu. Meter 1.17E+01 evaporator bottoms, etc. Ci (est) 2.03E+01 3.70E+01 B. Dry compressible waste, Cu. Meter 2.63E+02 contaminated equipment, etc. Ci (est) 9.OOE+00 3.50E+01 C. Irradiated components, Cu. Meter 7.05E+00 control rods, etc. Ci (est) 2.86E+04 3.50E+01 D. Other (describe)

Cu. Meter 1.57E+01 Ci (est) l.25E+01 3.50E+01 2. Estimate of major nuclide composition (by type of waste)Type A Type B Type C Type D Nuclide percent percent percent percent H-3 5.56E-01 5.63E-01 3.04E-03 C-14 7.42E-01 7.02E-01 9.49E-03 Cr-51 4. 87E-04 Mn-54 3.83E+00 3.86E+00 1.83E+00 3.18E+00 Fe-55 2.50E+01 2.51E+01 4.56E+01 3.41E+01 Co-58 2.66E-01 2.80E-01 9.39E-02 Fe-59 8.28E-05 Ni-59 1.32E-04 2.55E-02 Co-60 2.94E+01 2.99E+01 4.60E+01 3.76E+01 Ni-63 1.53E+00 1.49E+00 5.38E+00 1.03E+00 Zn-65 3.11E+00 3.23E+00 2.50E-03 4.59E+00 Sr-89 1. 49E-03 Sr-90 5.20E-02 5.61E-02 6.24E-06 Tc-99 5.28E-06 2.50E-05 Agll0m 2.61E-0l ,262E-01 Sb-124 1.OOE-02 9.56E-03 Sb-125 3.50E-02 3.25E-02 Cs-134 1. 39E-04 Cs-137 3.50E+01 3.42E+01 1.12E-04 1.82E+01 Ba-140 1.OOE-03 6.63E-03 Ce-141 2.20E-02 2.46E-02 Ce-144 1.53E-01 1.52E-01 Np-237 5 47E-06 Pu-238 1.OOE-03 1.09E-03 Pu-239 1.OOE-03 1.03E-03 Am-241 5.00E-03 5.28E-03 Pu-241 2.20E-02 2.64E-02 4.24E-05 Cm-242 1.OOE-03 9.78E-04 Cm-243 2.30E-02 1.99E-03 Page 13 RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan -Dec 2008 Table 3 Solid Waste and Irradiated Fuel Shipments 3. Solid waste disposal Number of Mode of Destination Shipments Transportation 3 Truck Chem-Nuc Inc., Barnwell, SC.4 Truck Envirocare, Clive, UT.6 Truck RACE Inc., Memphis, TN.B. Irradiated Fuel Shipments 1. Disposition Number of Mode of Destination ShipmentsI Transportation None This Period C. Shipping Container and Solidification Method No. Volume Activity Type of Container Solidification M3 Ci Waste Code Code 08-06 3.79E+01 1.49E-01 B L N 08-07 5.89E+01 2.40E-01 B L N 08-15 5.83E+00 8.48E+00 A L D 08-11 4.26E+01 4.75E-03 B L N 08-13 5.83E+00 8.51E+00 B L D 08-18 3.78E+00 8.92E+01 C B N 08-21 1.64E+00 1.27E+04 C B N 08-31 1.64E+00 1.58E+04 C B N 08-38 5.89E+01 4.92E-02 B L N 08-59 4.70E+00 1.25E+01 D A N 08-62 1.10E+01 1.09E-02 D L N 08-66 5.89E+01 4.81E-02 B L N 08-69 5.83E+00 1.18E+01 A L D Waste type Codes : A -Spent resins, sludges B -Dry waste, equipment C -Irradiated components D -Other (describe)

Container Codes L -LSA A -Type A B -Type BQ -Large Quantity Solidification Codes C -Cement U -Urea Formaldehyde D -Dewatering N -Not Applicalble Table 5.3 MISSED COLLECTIONS AND ANALYSES All required samples were collected and analyzed as scheduled with the following exceptions:

Collection Reason for not Sample Analysis Location Date or conducting REMP Plans for Preventing Type Period as required Recurrence AP/AI Beta, M-02 5/28/2008 Sampler pump failure, Sampler pump was 1-131 open fuse. replaced.AP/AI Beta, M-05 7/9/2008 Sampler pump failure, Sampler pump was 1-131 sampler head leakage. replaced.Ml Gamma, M-28 4/9/2008-Hoglund Farm no longer Pasture grass collections 1-131 12/31/2008 in the dairy business, were initiated at locations M-41, M-42, M-43 in Sept. 2008 TLD Ambient M-01B 1st. Qtr. Missing in the field None required.Gamma 2008 TLD Ambient M-01S 2nd. Qtr. Missing in the field None required.Gamma 2008 TLD Ambient M-01S 4th. Qtr. Missing in the field None required.Gamma 2008 BO Gamma M-08, Oct., 2008 Collection missed due to None required.M-09 unsafe river conditions.

SW Surface Water M-08 Jan, Feb, Mar, Missed due to unsafe ice. None required.Gamma 2008 M-08 Dec, 2008 Three of five weekly samples None required.missed due to unsafe ice.14 ENCLOSURE 2 OFF-SITE RADIATION DOSE ASSESSMENT FOR JANUARY 1,- DECEMBER 31, 2008 MONTICELLO NUCLEAR GENERATING PLANT Offsite Radiation Dose Assessment for January 1, -December 31, 2008 An assessment of radiation dose due to releases from the Monticello Nuclear'Generating Plant during 2008 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 2008.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.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 atthe newReceiving 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 (abounding 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.

Page I of 5 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. Preoperational monitoring for gamma and neutron dose has been completed.

The initial loading campaign was completed in 2008 with 10 HCM's loaded with spent fuel.Environmental TLDs 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 no changes in land use resulting in significant increases in calculated doses. Milk samples were unavailable at sample location M-28 (Hoglund Farm) after 4/09/08 due to the farm going out of business.

Land use census results show that there were no other indicator sample locations to replace this farm. As a result of the last dairy farm going out of business, control milk samples at location M- 10 were discontinued at the end of 2008. Vegetation sampling was initiated at locations M-41, M-42 and M-43 in September 2008 as a replacement for milk sampling.Page 2 of 5 Table 1 Offsite Radiation Dose Assessment

-Monticello PERIOD: January 1, through December 31,2008 Maximum Site Boundary (amma Air Dose (mrad/year) 10 Maximum Site Boundary Beta Air Dose 0.018 (mrad/year) 20Maximum Off-Site Dose to Any Organ (mrem/year) 0.084 15 Maximum Doseto the Likely Most Exposed Member of the General Public (mrem/year)

Whole Body 0.036 5 Skin 0.035 15 Max Organ (Thyroid) 0.084 15 Maximum Off-Site Dose (mrem)Whole Body 0.00 3 Thyroid 0.064 75Max Other Organ (Skin) 0.048 25 Page 3 of 5 Table 2 Offsite Radiation Dose Assessment

-Monticello Supplemental Information PERIOD: January 1, through December 31, 2008 Mviaximum bite bounclary Dose Location (from Reactor Building Vents)

Sector Distance (miles)SSE 0.40 Substation Sector S Distance from Plant Stack (miles) 0.2 Distance from Reactor Building Vents 0.2 Critical Receptor Location Sector SSW Distance from Reactor Building Vents (miles) 0.64 Pathways Plume, Ground, Inhalation, Vegetable Age Group CHILD Organ THYROID St. Paul Drinking Water Intake Location Pathways Drinking Water Drinking Water, FishAge Group Infant Adult Organ Whole Body GI Tract Dilution Factor (drinking water) 7:1 7:1 Page 4 of 5 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 arelocated 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 effortindicated 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.Page 5 of 5