ML051360163

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Transmittal of Monticello Nuclear Generating Plant, 2004 Radioactive Effluent Release Report
ML051360163
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 05/09/2005
From: Thomas J. Palmisano
Nuclear Management Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
FOIA/PA-2010-0209, L-MT-05-042
Download: ML051360163 (23)
v • d • e


Text

Monticello Nuclear Generatinq Plant Committed to Nucear sce Operated by Nuclear Management Company, LLC May 9, 2005 L-MT-05-042 Technical Specification 6.7.A.4 Technical Specification 6.8.A.3.c U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Monticello Nuclear Generating Plant Docket 50-263 License No. DPR-22 2004 Radioactive Effluent Release Report In accordance with Monticello Nuclear Generating Plant Technical Specification Sections 6.7.A.4 and 6.8.A.3.c, the Nuclear Management Company, LLC is submitting the following information as enclosures:

  • Radioactive Effluent Release Report for January 1 - December 31, 2004 (Enclosure 1)
  • Off-Site Radiation Dose Assessment for January 1 - December 31, 2004 (Enclosure 2)
  • Bypass of the Off-Gas Storage System (Enclosure 3)

This letter contains no new NRC commitments, nor does it modify any prior commitments.

I n

r ar Thomas J. Palmisano Site Vice President, Monticello Nuclear Generating Plant Nuclear Management Company, LLC Enclosures (4) cc

Administrator, Region Ill, USNRC (w/o Enclosure 4)

Project Manager, Monticello, USNRC (w/o Enclosure 4)

Resident Inspector, Monticello, USNRC (wfo Enclosure 4)

Minnesota Department of Commerce (w/o Enclosure 4) 2807 West County Road 75

  • Monticello, Minnesota 55362-9637 Telephone: 763-295-5151
  • Fax: 763-295-1454

ENCLOSURE 1 RADIOACTIVE EFFLUENT RELEASE REPORT FOR JANUARY 1 - DECEMBER 31, 2004 13 pages follow

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

Dec 2004 Supplemental Information

1. Regulatory Limits -

Quarterly levels requiring reporting to Nuclear Regulatory Commission A. Noble Gases 5 mrad/ uarter 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)

I)

!Page 2

RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan -

Dec 2004 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 1350.0 min
3. Maximum Time Period for a Batch Release 908.0 min
4. Average Time Period for a Batch Release 675.0 min
5. Minimum Time Period for a Batch Release 442.0 min

Page 3

RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan -

Dec 2004 Supplemental Information (continued)

6. Abnormal Releases A. Liquid :
1. Number of Releases
2. Total Activity Released B. Gaseous :

I 7.42E-06 Ci

1. Number of Releases
2. Total Activity Released 0
0. 0 Ci

RADIOACTIVE EFFLUENT RELEASE REPORT Page 4

RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan -

Dec 2004

.Table 1A Gaseous Effluents -

Summation of all Releases' Units 1st Qtr 2nd Qtr Est. Total Error, %-

A. Fission & Activation gases

1. Total Release Ci 8.44E+02 4.54E+02 2.OOE+01l
2. Average Release Rate uci/sec 1.08E+02 5.77E+01
3. Percent Tech Spec Qtrly Repoiting Level Gamma Radiation 5.62E-01 2.92E-01 Beta Radiation 5.20E-02 3.51E-02 B. Iodines I. Total 1-131 Release Ci 3.15E-04 4.37E-04 I 1.OOE+01 l
2. Average 1-131 Release Rate l uci/sec I 4.05E-05 1 5.56E-05 C. Particulates
1. Total Particulates Ci 1.64E-04 2.22E-04 I 3.OOE+01 l
2. Average Release Rate I uca/sec 1 2.11E-05 1 2.82E-05
3. Gross Alpha Radioactivit Cl 8.22E-07 7.44E-07 D. Tritium
1. Total Releasel Ci 4.75E+00 13.65E+00 1.OOE+01 l
2. Average Release Rate I uci/sec I 6.11E-01 I 4.64E-01 E. Percent Qtrly Tech Spec Reporting Levels
1. Iodines, Particulates, l

l and Tritium I

I 5.68E-02 I 6.41E-02

Page 5

RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan -

Dec 2004 Table 1A Gaseous Effluents - Summation of all Releases Units 3r Qtr 4th Qtr Est. Total 7

7~Error,%

A. Fission & Activation gases

1. Total Release Ci 3.54E+01 3.72E+01 2.OOE+01
2. Average Release Rate uci/sec 4.46E+00 4.68E+00
3. Percent Tech Spec Qtrly Reporting Level Gamma Radiation t

1.68E-02 1.71E-02 Beta Radiation 4.90E-03 8.32E-03 B. Iodines l1. Total I-131 Release Ci I3.42E-04 3.64E-04

.O1.00E+01

2. Average I-131 Release Rate I uci/sec I 4.31E-05 1 4.58E-05_1 C. Particulates
1. Total Particulates Ci I3.10E-04 1 5.15E-04 1 3.00E+01 l
2. Average Release Rate uci/sec I3.90E-05 1 6.47E-05
3. Gross Alpha RadioactivitY Ci 1.01E-06 4.70E-07 D. Tritium
1. Total Release Ci 4.16E+00 3.63E+00 I 1.OOE+01 1 2. Average Release Rate I uci/sec I 5.24E-01 I 4.56E-01 I

E. Percent Qtrly Tech Spec Reporting Levels

1. Iodines, Particulates, I

and Tritium I

I 6.60E-02 I 9.54E-02

Page 6

RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan -

Dec 2004 Table 1B Gaseous Effluents -

Elevated Releases Uni Continuous Mode Batch Mode Nuclides Released 1st Qtr 2nd Qtr 1st Qtr 2nd Qtr

1. Fission Gases KR-85M Ci 3.86E+01 2.01E+01 0.OOE+00 0.OOE+00 KR-87 Ci 1.48E+02 7.64E+01 0.OOE+00 0.0O-E+00 KR-88 Ci 1.26E+02 6.63E+01 0.OOE+00 0.0O0E+00 XE-133 Ci 2.01E+01 2.14E+01 0.OOE+00 0.0OE+00 XE-133M Ci 0.OOE+00 2.69E-01 0.OOE+00 0.OOE+00 XE-135 Ci 2.61E+02 1.41E+02 0.OOE+00 0.OOE+00 XE-135M Ci 6.16E+01 3.07E+01 0.OOE+00 0.OOE+00 XE-137 Ci 0.OOE+00 4.86E+00 0.OOE+00 0.OOE+00 XE-138 Ci 1.83E+02 8.84E+01 0.OOE+00 0.OOE+00 AR-41

_Ci 2.57E+00 1.OOE+00 O.OOE+00 O.OOE+00 Total for Period 8.42E+02 4.50E+02 0.OOE+00 0.00E+00

2. Iodines I

I -13 1 ICi I 2.11E-04 I 3.45E-04 I 0.00E+00 I 0.00E+00I 1-133 Ci 2.14E-03 l 2.57E-03 l 0.OOE+00 l0.OOE+00 I-135 Ci 4.20E-03 4.48E-03 0.OOE+00 0.OOE+00 Total for Period Ci 6.55E-03 7.40E-03 0.OOE+00 0.OOE+00

3. Particulates MN-54 Ci 0.OOE+00 5.70E-08 0.0OE+00 0.OOE+00 CO-60 Ci 2.46E-06 2.75E-06 0.00E+00 0.OOE+00 CS-137 Ci 4.69E-07 1.90E-07 0.OOE+00 O.OOE+00 BA-140 Ci 2.93E-05 1.58E-05 0.OOE+00 0.OOE+00 SR-89 Ci 1.20E-05 1.82E-05 0.OOE+00 0.OOE+00 SR-90 Ci 1.23E-07 5.89E-08 0.OOE+00 0.OOE+00 Total for Period C_

4.44E-05 3.71E-05 0.OOE+00 0.OOE+00

Page 7

RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan -

Dec 2004 Table 1B Gaseous Effluents -

Elevated Releases I

ontinuous Mode Batch Mode Nuclides Released Unit 3rd Qtr 4th Qtr 3rd Qtr 4th Qtr

1. Fission Gases

-KR-85M Ci O.OOE+00 1.99E-02 0.OOE+00 0.OOE+00 KR-87 Ci 2.43E-01 1.36E-01 O.OOE+00 0.OOE+00 KR-89 Ci 5.93E-01 O.00E+00 O.OOE+00 O.00E+00 XE-133 Ci 1.67E+01 2.13E+01 0.OOE+00 0.OOE+00 XE-133M Ci 2.97E-01 5.66E-01 0.OOE+00 0.OOE+00 XE-135 Ci 3.15E+00 3.15E+00 0.OOE+00 0.0OE+00 XE-135M Ci 3.OOE+00 2.54E+00 0.OOE+00 0.OOE+00 XE-137 Ci 2.24E+00 3.64E+00 0;OOE+00 0.OOE+00 XE-138 Ci 8.05E+00 3.79E+00 0.OOE+00 0.OOE+00 Total for Period Ci 3.42E+01 3.51E+01 0.OOE+00 0.OOE+00

2. Iodines 1-131 Ci 2.47E-04 1.66E-04 O.OOE+00 0.OOE+00 I-133 Ci 2.54E-03 1.65E-03 0.OOE+00 0.OOE+00 I-135 Ci 4.69E-03 2.88E-03 0.OOE+00 0.OOE+00 Total for Period ___Ci 7.47E-03 4.70E-03 0.OOE+00 O.OOE+00
3. Particulates CO-60 Ci 4.65E-06 8.14E-06 0.OOE+00 0.OOE+00 CS-137 C-0.OOE+00 5.85E-08 0.OOE+00 0.O0E+00 BA-140 Ci 2.07E-05 2.13E-05 0.OOE+00 0.OOE+00 SR-89 Ci 8.04E-06 7.60E-06 0.OOE+00 0.OOE+00 SR-90 Ci 3.88E-08 4.08E-08 0.OOE+00 0.OOE+00 Total for Period Ci 3.34E-05 3.72E-05 0.OOE+0O 0.OOE+00

Page 8

RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan -

Dec 2004 Table IC Gaseous Effluents -

Building Vent Releases IContinuous Mode Batch Mode Nuclides Released 2nd Qtr 1st Qtr 2nd Qtr NucldesRelesed UnitI1s Cotinuous Qoetat M

1. Fission Gases XE-135 Ci 2.13E+00 3.60E+00 0.OOE+00 2.57E-03 AR-41 Ci O.OOE+00 O.OOE+00 O.OOE+00 8.95E-03 Total for Period

__ Ci 2.13E+00 3.60E+00 0.OOE+00 1.15E-02

2. Iodines 1-131 Ci 1.04E-04 9.22E-05 0.OOE+00 0.OOE+00 I-133 Ci 8.64E-04 6.50E-04 0.OOE+00 0.OOE+00 Total tor Period Ci 9.68E-04 7.42E-04 0.O0E+00 0.00E+00Q
3. Particulates MN-54 Ci 0.OOE+00 1.44E-06 0.O0E+00 0.OOE+00 CO-60 Ci 7.86E-05 9.26E-05 0.OOE+00 0.OOE+00 CS-137 Ci 4.07E-05 7.17E-05 0.OOE+00 0.OOE+00 SR-89 Ci 7.24E-08 1.91E-05 0.OOE+00 0.OOE+00 SR-90

-- Ci 1.33E-09 0.OOE+00 0.OOE+00 0.OOEi00 Total tor Period C

1.19E-04 1.85E-04 0.O0E+00 O.00EQ+00

Page 9

RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan -

Dec 2004 Table 1C Gaseous Effluents -

Building Vent Releases IContinuous M-odae Batch Mode Nuclides Released Unit 3rd Qtr 4th Qtr 3rd Qtr 4th Qtr

1. Fission Gases XE-135 Ci 1.21E+0 0 2.14E+00 0.OOE+00 0.OOE+00 Total for Period jTCi 1.21E+00 2.14E+00 O.OOE+00 0.OOE+00
2. Iodines 1-131 Ci 9.57E-05 1.98E-04 0.OOE+00 0.OOE+00 I-133 Ci 7.32E-04 2.53E-03 0.OOE+00 0.OOE+00 I-135 Ci 0.OOE+00 2.90E-03 0.OOE+00 0.OOE+00 Total for Period Ci 8.27E-04 5.63E-03 0.OOE+00 0.OOE+00
3. Particulates CR-51 Ci 0.OOE+00 1.17E-05 0.OOE+00 0.00E+00 CO-60 Ci 1.69E-04 2.76E-04 0.OOE+00 0.OOE+00 ZN-65 Ci 0.OOE+00 1.46E-05 0.OOE+00 0.OOE+00 CS-137 Ci 1.05E-04 1.36E-04 0.OOE+00 0.OOE+00 BA-140 Ci 0.OOE+00 2.25E-05 0.OOE+00 0.OOE+00 CE-141 Ci 0.OOE+00 2.46E-06 0.OOE+00 0.OOE+00 SR-89 Ci 3.21E-06 1.43E-05 0.OOE+00 0.OOE+00 SR-90 Ci 2.87E.-09 8.79E-08 0.OOE+00 0.OOE+00 Total tor Period Ci 2.77E-04 4.77E-04 0.OOE+00 0.O0E+00

Page 10 RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan -

Dec 2004 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.OQE+00 0.OOE+00

2. Avg Diluted Concentration uci/mi I 0.OOE+00 I0.OE+00 B. Tritium
1. Total Release Ci 0.OE+00 0.OOE+00 0.OE+00 l
2. Avg Diluted Concentration l uci/mi I 0.OOE+00 1 0.00E+00 C. Dissolved and Entrained Gases
1. Total Release I

Ci 0.OOE+00 I0.OOE+00 I 0.00E+00

2. Avg Diluted Concentration I uci/ml I 0.00E+00 I 0.00E+00 D. Percent Qtrly Tech Spec Reporting Level I. Whole Body Dose

%0.OOE+00 I0.OOE+00

2. Organ Dose I

I 0.OOE+00 I0.OOE+00 E. Gross Alpha Radioactivity

1. Total Release I

Ci I 0.OOE+00 1 0.OOE+00 I 0.OOE+00 l IF. Volume of Waste Released I

Liters 0.OOE+00 0.OOE+00 l0.OE+00 l IF. Volume of Dilution Water Used Liters 0.OOE+00 0.OOE+00 l.QOE+00_l Table 2B Liquid Effluents 1st Qtr 2n Qr 1s tr 2d t NRUnit Continuous Mode Batch Mode Nuclides Releas n

d 2nd Qi P

st Qtr o

2nd Qtr None Released This Period-

Page 11 RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan -

Dec 2004 Table 2A Liquid Effluents -

Summation of all Releases Units 3rd Qtr 4th Qtr Est. Total Error,-%

A. Fission & Activation products

1. Total Release (not including tritium, gases, alpha)

Ci 0.OQE+00 0.OOE+00 0.OOE+00

2. Avg Diluted Concentration uci/ml I 0.IOE+00 0.OOE+O0 B. Tritium
1. Total Release I

Ci I 0.OOE+00 7.42E-06 3.OOE+01l

2. Avg Diluted Concentration l uci/ml I 0.OQE+00 I 6.65E-10 C. Dissolved and Entrained Gases
1. Total Release Ci 0.00E+00 0.OOE+00 0.OOE+00
2. Avg Diluted Concentration l uci/mi I 0.OOE+00 I 0.OOE+00 D. Percent Qtrly Tech Spec Reporting Level
1.

Whole Body Dose I

10.OOE+00 1.29E-08

2. Organ Dose

%0.OOE+00 3.88E-09 l E. Gross Alpha Radioactivity l 1. Total Release Ci 0.OE+00 0.OOE+00 0.OOE+00 l IF. Volume of Waste Released Liters 0.OE+00 3.92E+03 3.OOE+01 l IF. Volume of Dilution Water Used I Liters 0.OOE+00 1.12E+07 I 3.OOE+01 I Table 2B Liquid Effluents IContinuous Mode Batch Mode Nuclides Released I Unit 3rd Qtr I 4th.Qtr 3rd Qtr I 4th Qtr None Released This Period

Page 12 RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan -

Dec 2004 Table 3 Solid Waste and Irradiated Fuel Shipments A. Solid Waste Shipped Offsite for Burial or Disposal (not irradiated fuel)

1. Type ot Waste Units 12-month Est. Total Period Error, %

A. Spent resins, filter sludges, Cu. Meter 3.41E+00 evaporator bottoms, etc.

Ci (est) 2.64E+02 3.70E+01 B. Dry compressible waste, Cu. Meter 1.51E+02 contaminated equipment, etc.

Ci (est) 3.81E+00 3.50E+01 C. Irradiated components, Cu. Meter O.0OE+00 control rods, etc.

Ci 0.OOE+00 0.OOE+00 D. Other (describe)

Cu. Meter O.OOE+00 Ci O.OOE+00 0.OOE+00

2. Estimate ot ma jor nuclide composition (by type ot waste)

Type A Type B Type C Type D Nuclide percent percent percent percent H-3 2.OOE-03 2.02E+01 C-14 1.00E-03 4.43E-01 Cr-51 7.95E-01 9.96E-01 Mn-54 2.87E+00 1.95E+00 Fe-55 6.43E+01 5.37E+01 Co-57 1.47E-03 Co-58 4.22E-01 3.45E-01 Fe-59 1.04E-01 2.16E-02 Ni-59 5.OOE-03 6.22E-02 Co-60 2.72E+01 1.30E+01 Ni-63 7.07E-01 7.99E-01 Zn-65 3.20E+00 4.11E+00 Sr-89 2.34E-04 Sr-90 6.OOE-03 2.89E-02 Nb-95 1.72E-03 Zr-95 1.58E-02 AgllOm 5.17E-01 9.60E-03 Sb-124 6.37E-03 Sb-125 6.28E-02 I-131 4.83E-03 Cs-134 8.32E-03 Cs-137 l.19E-01 3.47E+O0 La-140 6.07E-01 Ce-141 6.37E-01 Ce-144 2.OOE-03 3.12E-02 Pu-238 1.OOE-03 2.15E-03 Pu-239 2.10E-03 Am-241 1.00E-03 7.34E-03 Pu-241 1.20E-02 7.67E-02 Cm-242 1.OOE-03 5.22E-04 Cm-243 1;.10E-03 Eu-152 1.55E-02 Eu 1~.5

Page 13 RADIOACTIVE EFFLUENT RELEASE REPORT Period Jan -

Dec 2004 Table 3 Solid Waste and Irradiated Fuel Shipments

3. Solid waste disposal Number of Mode of Destination Shipmients Transportation 1

Truck Envirocare, Clive, UT.

1 Truck Permafix Inc., Gainesville, FL.

3 Truck RACE Inc., Memphis, TN.

B. Irradiated Fuel Shipments

1. Disposition Number of Mode of Destination Shipments I Transportation None This Period C. Shipping Container and Solidification Method No.

Volume Activity Type of Container Solidification M3 Ci Waste Code Code 0408 6.21E+01 3;50E-01 B

L N

0413 3.22E+01 1.60E+00 B

L N

0423 3.41E+00 2.64E+02 A

-A D

0431 5.12E+01 1.84E+00 B

L N

0433 5.44E+00 1.90E-02 B

L N

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 B Q -

Large Quantity Solidification Codes :

C -

Cement U -

Urea Formaldehyde D -

Dewatering N -

Not Applicalble

ENCLOSURE 2 OFF-SITE RADIATION DOSE ASSESSMENT FOR JANUARY 1 - DECEMBER 31, 2004 5 pages follow

MONTICELLO NUCLEAR GENERATING PLANT Offsite Radiation Dose Assessment for January 1, - December 31, 2004 An assessment of radiation dose due to releases from the Monticello Nuclear Generating Plant during 2004 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 2004..

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 is based on release of Turbine Building Normal Drain Sump water released in the fourth quarter with H-3 activity present. Whole body and organ dose due to liquid releases 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 1. There are several groups of concern, Security Officers training at the rifle range at the old EPA station, Security Officers at the Interim Barrier Fence Gate House 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 Security Officers Training trailer located near the old EPA station (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.

Page 1 of 5

Dose to the Likely Most Exposed Member of the General Public from Reactor Releases and Other Nearbv Uranium Fuel Cvcle 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.

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. The Critical Receptor location changed from the Trefethen residence to the Wise residence due to Mr. Wise planting a garden this year. Milk samples were unavailable at sample location M-28 (Hoglund Farm) from 6/30/04 to 10/20/04 due to the farm being temporarily out of business. Land use census results show that there were no other indicator sample locations to replace this farm. Milk production and sampling has resumed at the Hoglund farm starting 10/18/04. There were no vegetable samples that could not be obtained during this reporting period.

Page 2 of 5

Table.1 Offsite Radiation Dose Assessment - Monticello PERIOD: January 1, through December 31, 2004 Boundary GU (mrad/vear) 10 Maximum Site Boundary Beta Air Dose 0.01 (mradlyear) 20 Maximum Off-Site Dose to Any Organ (mrem/year) 0.03 7 15 Maximum Dose to the Likely Most Exposed Member of the General Public (mremlyear)

Whole Body 0.022 5

Skin 0.037 15 Max Organ (Skin) 0.037 15 Maximum Off-Site Dose (mrem)

Whole Body 1.94E-10 3

Max Organ (All except bone) 1.941-10 10 Maximum Dose to Individuals due to their Activities Inside the Site Boundary (mrem)

Whole Body 0.009 25 Skin 0.011 75 Max Other Organ (Thyroid) 0.009 25 Page 3 of 5

Table 2 Offsite Radiation Dose Assessment - Monticello Supplemental Information PERIOD: January 1, through December 31, 2004 Maximum Site Boundary Dose Location (from Reactor Building Vents)

Sector SSE Distance (miles) 0.40 Security Training Trailer Sector ESE Distance from Plant Stack (miles) 0.3 Distance from Reactor Building Vents 0.4 Critical Receptor Location Sector SSW Distance from Reactor Building Vents (miles) 0.64 Pathways Plume, Ground, Inhalation, Vegetable Age Group CHILD Organ St. Paul Drinking Water Intake Location Pathways Age Group Drinking Water Drinking Water, Fish Organ Infant Adult Dilution Factor (drinking water)

Whole Body GI Tract 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 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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ENCLOSURE 3 Bypass of Off-Gas Storage System As discussed in last year's report, the Off-Gas Storage System was placed in by-pass due to condenser air in-leakage exceeding the capacity of the Off-Gas Storage System compressor. In May 2004, application of an adhesive sealant to the condenser boot seal, reduced condenser air in-leakage sufficiently to permit the Off-Gas Storage System to be returned to service.

Cause:

Following the spring 2003 refueling outage, the Off-Gas Storage System was unable to maintain the required holdup time due to high air in-leakage through the condenser boot seal. The high air in-leakage exceeded the capacity of the Off-Gas Storage System compressors, requiring the Off-Gas Storage System to be bypassed.

Corrective Several attempts were made with limited success in 2003 to reduce Actions:

condenser air in-leakage by application of an adhesive sealant.

Therefore, at the beginning of 2004 the Off-Gas Storage System remained in by-pass due to condenser air in-leakage exceeding the capacity of the compressor.

On May 21, 2004, plant power was reduced for repairs to a Condensate Pump. While power was reduced the adhesive sealant was again applied to the condenser boot seal to attempt to reduce the condenser air in-leakage. This application sufficiently reduced condenser air in-leakage to levels, which permitted the Off-Gas Storage System to be returned to service. On May 26, 2004, release rates returned to historical levels.

The condenser boot seal was replaced during the spring 2005 refueling outage.

Significance: During the period that the Off-Gas Storage System was by-passed in 2004, release rates were higher than historical. The Gamma air dose for 2004 was 0.013 mrad, which was higher than historical values. The beta air and particulate dose values also increased slightly.

The dose values for 2004 were a small fraction of the dose limits specified in 10 CFR 50 Appendix I, did not exceed 2 percent of the annual limits, and did not impose upon the health and safety of the public.

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ENCLOSURE 4 OFFSITE DOSE CALCULATION MANUAL The Offsite Dose Calculation Manual for the Monticello Nuclear Generating Plant is comprised of the following documents:

Document Number ODCM-INDEX ODCM-HISTORY ODCM-01.01 ODCM-02.01 ODCM-03.01 ODCM-04.01 ODCM-05.01 ODCM-06.01 ODCM-07.01 ODCM-08.01 ODCM-APP-A ODCM-APP-B ODCM-APP-C Title Offsite Dose Calculation Manual Index ODCM-History Introduction Liquid Effluents Gaseous Effluents Liquid Effluent Calculations Gaseous Effluent Calculations Dose From All Uranium Fuel Cycle Sources Radiological Environmental Monitoring Program Reporting Requirements Appendix A Appendix B Appendix C Revision 3

0 3

4 6

2 4

1 7

2 0

1 0

One (1) CD-ROM is included in this submission. The CD-ROM labeled "Monticello Offsite Dose Calculation Manual 2004" contains the following thirteen (13) files:

File name 001_ODCM Index.pdf 002_ODCM-History.pdf 003_ODCM-01.01.pdf 004_ODCM-02.01.pdf 005_ODCM-03.01.pdf 006_ODCM-04.01.pdf 007_ODCM-05.01.pdf 008_ODCM-06.01.pdf 009_ODCM-07.01.pdf 010_ODCM-08.01.pdf 011_ODCM-APP-A.pdf 012_ODCM-APP-B.pdf 013_ODCM-APP-C.pdf Size of file 28,515 bytes 31,314 bytes 60,518 bytes 109,387 bytes 116,855 bytes 132,933 bytes 272,810 bytes 35,679 bytes 676,329 bytes 45,669 bytes 218,550 bytes 73,684 bytes 35,859 bytes Sensitivity level Publicly available Publicly available Publicly available Publicly available Publicly available Publicly available Publicly available Publicly available Publicly available Publicly available Publicly available Publicly available Publicly available Page 1 of 1

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