Text

Letter Transmitting Monticello Nuclear Generating Plant - 2003 Radioactive Effluent Release Report, Off-Site Radiation Dose Assessment for 2003, Bypass of Offgas Storage System for Greater than Seven Days, and Offsite Dose Calculation Manua
	ML041450248
Person / Time
Site:	Monticello
Issue date:	05/15/2004
From:	Thomas J. Palmisano; Nuclear Management Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	L-MT-04-031
	Download: ML041450248 (24)
	v • d • e

Monticello Nuclear Generating Plant Committed to NuclearExcelec Operated by Nuclear Management Company, LLC May 15, 2004 L-MT-04-031 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 2003 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, 2003 (Enclosure 1)

Off-Site Radiation Dose Assessment for January 1 - December 31, 2003 (Enclosure 2)

Bypass of Offgas Storage System for Greater than Seven Days (Enclosure 3)

Offsite Dose Calculation Manual (Enclosure 4, provided on CD-ROM)

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

Please contact John Fields at (763) 295-1663 if you require further information.

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

Administrator, Region ll, USNRC (w/o enclosures)

Project Manager, Monticello, USNRC(w/o enclosures)

Resident Inspector, Monticello, USNRC(w/o enclosures)

Minnesota Department of Commerce (w/o enclosures) 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, 2003 13 pages follow

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

Dec 2003 Supplemental Information

1. Regulatory Limits - Quarterly levels requiring reporting to Nuclear Regulatory Commission A. Noble Gases :

5 mrad/ quarter gamma radiation 10 mradlquarter 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)

S Page 2

RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan -

Dec 2003 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 4

2. Total Time Period for Batch Releases 3216.0 min

3. Maximum Time Period for a Batch Release 1357.0 min

4. Average Time Period for a Batch Release 804.0 min

5. Minimum Time Period for a Batch Release 349.0 min

Page 3

RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan -

Dec 2003 Supplemental Information (continued)

6. Abnormal Releases A. Liquid :

1. Number of Releases 1

2. Total Activity Released 0.001 Ci B. Gaseous

1. Number of Releases 0

2. Total Activity Released 0.0 Ci

Page 4

RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan -

Dec 2003 Table 1A Gaseous Effluents -

Summation of all Releases Units 1st Qtr 2nd Qtr Est. Total I

I I

I Error, %

A. Fission & Activation gases

1. Total Release Ci 4.93E+01 3.10E+02 2.OOE+01

2. Average Release Rate uci/sec 6.34E+00 3.94E+01

3. Percent Tech Spec Qtrly Reporting Level Gamma Radiation 4.01E-02 1.93E-01 Beta Radiation 2.62E-02 2.22E-02 B. Iodines

1. Total 1-131 Release Ci 6.07E-04 8.16E-04 1.OOE+01

2. Average I-131 Release Rate l uci/sec I 7.81E-05 I 1.04E-04 C. Particulates

1. Total Particulates Ci 2.10E-04 4.79E-04 3.QOE+01

2. Average Release Rate l uci/sec I 2.70E-05 I 6.10E-05

3. Gross Alpha Radioactivity Ci 6.60E-07 8.74E-07_I D. Tritium

1. Total Release Ci 3.87E+00 3.36E+00 I 1.QOE+01l I I I 2. Average Release Rate I uci/sec I 4.98E-01 I 4.27E-01 I E. Percent Qtrly Tech.Spec Reporting Levels

1. Iodines, Particulates, and Tritium I 8.82E-02 I 1.03E-01

Page 5

RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan -

Dec 2003 Table 1A Gaseous Effluents -

Summation of all Releases Units 3rd Qtr 4th Qtr Est. Tota

Error, A. Fission & Activation gases

1. Total Release Ci 1.04E+03 8.87E+02 2.OOE+01

2. Average Release Rate uci/sec 1.31E+02 1.12E+02

3. Percent Tech Spec Qtrly Reporting Level Gamma Radiation 7.OOE-01 6.04E-01 Beta Radiation 5.55E-02 6.18E-02 B. Iodines

1. Total I-131 Release Ci l 5.78E-04 3.74E-04 I 1.00E+01 l

2. Average I-131 Release Rate l uci/sec I 7.27E-05 I 4.71E-05 C. Particulates

1. Total Particulates Ci 1.11E-03 2.26E-04 3.OOE+01 l

2. Average Release Rate uci/sec 1.39E-04 2.84E-05

3. Gross Alpha Radioactivity Ci 9.42E-07 5.01E-07 D. Tritium

1. Total Release Ci 5.03E+00 4.44E+00 1.OOE+01l

2. Average Release Rate l uci/sec I 6.33E-01 I 5.58E-01 E. Percent Qtrly Tech Spec Reporting Levels

1. Iodines, Particulates, and Tritium I

7.14E-02 5.39E-02

Page 6

RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan -

Dec 2003 Table 1B Gaseous Effluents -

Elevated Releases I

Continuous Mode Batch Mode Nuclides Released Unit 1st Qtr 2nd Qtr 1st Qtr 2nd Qtr

1. Fission Gases KR-85M Ci O.O0E+00 1.30E+01 0.OOE+00 0.OOE+00 KR-87 Ci 4.13E-01 5.07E+01 O.OOE+00 O.O0E+00 KR-88 i

O.00E+00 4.29E+01 O.O0E+00 O.OOE+00 XE-133 Ci 1.77E+01 9.92E+00 0.O0E+00 0.OOE+00 XE-133M Ci 1.51E-01 0.OOE+00 0.O0E+00 0.OOE+00 XE-135 Ci 2.46E+00 8.48E+01 0.OOE+00 0.OOE+00 XE-135M Ci 3.94E+00 2.43E+01 0.0OE+00 0.O0E+00 XE-137 Ci 8.97E+00 1.88E+00 0.O0E+00 0.OOE+00 XE-138 Ci 9.77E+00 7.87E+01 0.OOE+00 0.O0E+00 AR-41 Ci 0.OOE+00 6.80E-01 0.OOE+00 0.0OE+00 Total for Period I Ci 4.35E+01 3.07E+02 0.OOE+00 0.OOE+00

2. Iodines I-131 Ci 2.78E-04 4.37E-04 I 0.OOE+00 I 0.OOE+00 1-133 UCi 2.62E-03 2.85E-03 0.OOE+00 0.OOE+00 1-135 jCi 4.76E-03 3.05E-03 0.OOE+00 0.OOE+00 Total for Period Ci 7.66E-03 6.34E-03 0.OOE+00 0.OOE+00

3. Particulates MN-54 Ci 0.OOE+00 3.13E-07 0.OOE+00 0.OOE+00 CO-58 Ci 0.OOE+00 1.08E-07 0.OOE+00 0.OOE+00 CO-60 Ci 1.40E-06 4.48E-06 0.OOE+00 0.OOE+00 ZN-65 Ci 0.OOE+00 2.86E-07 0.OOE+00 0.OOE+00 SE-75 Ci 0.OOE+00 1.86E-07 0.OOE+00 0.OOE+00 CS-137 Ci 5.01E-07 9.53E-06 0.OOE+00 0.OOE+00 BA-140 Ci 2.36E-05 4.82E-05 0.OOE+00 0.OOE+00 SR-89 Ci 1.92E-05 1.79E-04 0.OOE+00 0.OOE+00 SR-90 Ci 4.47E-08 3.04E-07 0.OOE+00 0.OOE+00 Total for Period Ci 4.47E-05 2.42E-04 O.OOE+00 0.OOE+00

Page 7

RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan -

Dec 2003 Table 1B 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 4.04E+01 3.74E+01 0.OOE+00 0.0OE+00 KR-87 Ci 1.62E+02 1.48E+02 0.OOE+00 0.0OE+00 KR-88 Ci 1.33E+02 1.22E+02 0.OOE+00 0.OOE+00 XE-133 Ci 2.12E+01 1.90E+01 0.OOE+00 0.OOE+00 XE-133M Ci 2.78E-01 2.92E-01 0.OOE+00 0.0OE+00 XE-135 Ci 2.71E+02 2.48E+02 0.OOE+00 0.OOE+00 XE-135M Ci 9.61E+01 7.25E+01 0.OOE+00 0.OOE+00 XE-137 Ci 0.OOE+00 7.46E+00 0.OOE+00 0.OOE+00 XE-138 C__i 3.13E+02 2.25E+02 0.OOE+00 0.OOE+00 AR-41 Ci 1.49E+00 3.02E+00 0.OOE+00 0.OOE+00 Total for Period Ci 1.04E+03 8.82E+02 O.OOE+00 O.OOE+00

2. Iodines I-131 CiT 4.08E-04 2.26E-04 l 0.OOE+00 l 0.OOE+00 I-133 Ci 3.91E-03 2.03E-03 }

0.OOE+00 0.OOE+00 I-135 Ci 6.92E-03 3.66E-03 0.OOE+00 0.OOE+00 Total for Period Ci 1.12E-02 5.91E-03 0.OOE+00 0.OOE+00

3. Particulates CO-57 Ci 9.23E-08 0.OOE+00 0.OOE+00 0.OOE+00 CO-60 Ci 2.63E-06 2.32E-06 0.OOE+00 0.OOE+00 CS-137 Ci 1.47E-05 1.13E-07 0.OOE+00 0.OOE+00 BA-140 Ci 7.42E-05 2.59E-05 0.OOE+00 0.OOE+00 SR-89 Ci 7.51E-04 1.19E-05 0.OOE+00 0.OOE+00 SR-90 Ci 5.49E-07 6.18E-08 0.OOE+00 0.OOE+00 Total for Period iT 8.44E-04 4.03E-05 0.OOE+00 0.OOE+00

Page 8

RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan -

Dec 2003 Table 1C Gaseous Effluents -

Building Vent Releases I Nuclides Released I

I tI Continuous Mode Unit I1st Otr I 2nd Otr I

Batch Mode 1st Otr 1 2nd I

Otr

1. Fission Gases XE-131M Ci 8.33E-02 5.OOE-01 0.OOE+00 0.OOE+00 XE-133 Ci 0.OOE+00 0.OOE+00 0.00E+00 3.53E-03 XE-135 Ci 4.72E+00 2.42E+00 0.O0E+00 6.55E-03 XE-135M Ci 4.82E-01 0.OOE+00 0.OOE+00 0.OOE+00 XE-137 Ci 5.93E-01 0.OOE+00 0.OOE+00 0.OOE+00 AR-.41 Ci 0.OOE+00 0.OOE+00 0.OOE+00 3.27E-02 Total tor Period Ci 5.88E+00 2.92E+00 0.OOE+00 4.28E-02

2. Iodines I-131 Ci 3.29E-04 3.80E-04 0.OOE+00 0.OOE+00 I-133 Ci 3.12E-03 1.55E-03 0.OOE+00 0.OOE+00 Total for Period Ci 3.45E-03 1.93E-03 O.OOE+00 0.OOE+00

3. Particulates MN-54 Ci O.OOE+00 5.69E-06 O.OOE+00 O.OOE+00 CO-58 Ci 0.0OE+00 3.05E-06 0.OOE+00 0.O0E+00 CO-60 Ci 5.96E-05 1.24E-04 0.OOE+00 1.43E-05 ZN-65 Ci 0.OOE+00 2.42E-05 0.OOE+00 0.OOE+00 CS-137 Ci 8.39E-05 6.01E-05 0.OOE+00 0.OOE+00 BA-140 Ci 1.04E-05 4.21E-06 0.OOE+00 0.00E+00 SR-89 Ci 1.14E-05 8.70E-07 0.OOE+00 0.OOE+00 Total for Period Ci 1.65E-04 2.23E-04 0.OOE+00 1.43E-05

Page 9

RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan -

Dec 2003 Table 1C Gaseous Effluents -

Building Vent Releases I'

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

1. Fission Gases XE-135 g

Ci 0.OOE+00 4.14E+00 0.OOE+00 0.OOE+00 XE-135M Ci 0.OOE+00 4.69E-01 0.OOE+00 0.OOE+00 Total for Period Ci 0.OOE+00 4.61E+00 0.OOE+00 0.OOE+00

2. Iodines I-131 Ci 1.70E-04 1.48E-04 0.OOE+00 0.0OE+00 I-133 Ci 1.29E-03 1.03E-03 0.0OE+00 0.OOE+00 Total tor Period

__Ci_

1.46E-03 1.17E-03 0.OOE+00 0.OOE+00

3. Particulates MN-54 Ci 2.05E-06 1.05E-06 0.OOE+00 0.OOE+00 CO-60 Ci 1.69E-04 1.24E-04 0.OOE+00 0.OOE+00 CS-137 Ci 9.06E-05 5.92E-05 0.OOE+00 0.OOE+00 SR-89 Ci 3.62E-08 1.66E-06 0.OOE+00 0.OOE+00 SR-90 Ci 6.64E-10 3.05E-08 0.OOE+00 0.OOE+00 Total for Period Ci 2.62E-04 1.86E-04 0.OOE+00 I 0.OOE+00

¶i Page 10 RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan -

Dec 2003 Table 2A Liquid Effluents -

Summation of all Releases Units 1st Qtr 2nd Qtr Est. Total I

I I

IError, %

A. Fission & Activation products

1. Total Release (not including I

tritium, gases, alpha)

Ci 0.OOE+00 5.07E-07 0.OOE+00 l

2. Avg Diluted Concentration uci/ml 0.OOE+00 7.61E-09 B. Tritium

1. Total Release I

Ci 0.OOE+00 1.06E-03 I 0.OOE+00

2. Avg Diluted Concentration j uci/ml I 0.OOE+00 I 1.59E-05_j C. Dissolved and Entrained Gases

1. Total Release Ci I 0.OOE+00 I 6.58E-08 I 0.OOE+00

2. Avg Diluted Concentration I uci/ml I 0.OOE+00 I 9.88E-10_I D. Percent Qtriy Tech Spec Reporting Level

1.

Whole BodY Dose 0.I00-E+00 I 1.08E-04 l

2. Organ Dose 6

0.OOE+00 3.90E-05 l E. Gross Alpha Radioactivity

1. Total Release Ci 0.OOE+00 0.OOE+00 0.OOE+00 IF. Volume of Waste Released Liters I 0.OOE+00 9.04E+02 0.OOE+00 IF.

Volume of Dilution Water Used Liters I O.OOE+00 6.66E+04 1 0.00E+00 l Table 2B Liquid Effluents Continuous Mode Batch Mode Nuclides Released Unit 1st Qtr 2nd Qtr 1st Qtr 2nd Qtr Mn-54 Ci 0.OOE+00 1.44E-07 0.OOE+00 0.00E+00 Co-58 Ci 0.OOE+00 6.21E-08 0.OOE+00 0.OOE+00 Co-60 Ci 0.OOE+00 1.49E-07 0.OOE+00 0.OOE+00 Zn-65 Ci 0.00E+00 9.68E-08 0.OOE+00 0.OOE+00 I-131 Ci 0.OE+00 5.53E-08 0.OOE+00 0.00E+00 Xe-133 Ci O.OOE+00 6.58E-08 O.OOE+00 0.O0E+00

Page 11 RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan -

Dec 2003 Table 2A Liquid Effluents -

Summation of all Releases l

Units 3rd Qtr 4th Qtr Est. Total I

IIII

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 uciml 0.OOE+00 0.OOE+00 B. Tritium

1. Total Release l

Ci 0.OOE+00 0.OE+00 0.OOE+00

2. Avg Diluted Concentration I uci/ml i 0.00E+00 I 0.00E+00 C. Dissolved and Entrained Gases

1. Total Release I

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

2. Avg Diluted Concentration I uci/m i 0.OOE+00 1 0.OOE+00 D. Percent Qtrly Tech Spec Reporting Level I

1. Whole Body Dose I 0.OOE+00 0.OOE+00 l

2. Organ Dose 0.QOE+00 0.OOE+00 E. Gross Alpha Radioactivity

1. Total Release Ci 0.OOE+00 0.00E+00 I 0.OOE+00 IF.

Volume of Waste Released ILiters 0.OOE+00 0.OOE+00 0.OOE+00 l IF. Volume of Dilution Water Used Liters 0.OOE+00 I 0.OOE+00 0.OOE+00 l Table 2B Liquid Effluents I

Continuous Mode Batch Mode I Nuclides Released I Unit I 3rd Qtr I 4th Qtr 1 3rd Qtr I 4th Qtr None Released This Period

Page 12 RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan -

Dec 2003 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 1.75E+01 evaporator bottoms, etc.

Ci (est) 3.11E+01 3.70E+01 B. Dry compressible waste, Cu. Meter 1.61E+02 contaminated equipment, etc.

Ci (est) 1.82E+00 3.50E+01 C. Irradiated components, Cu. Meter 1.04E+01 control rods, etc.

Ci (est) 5.76E+04 3.50E+01 D. Other (describe)

Cu. Meter 0.OOE+00 Ci 0.O0E+00 0.OOE+00

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

Type A Type B Type C Type D Nuclide percent percent percent percent H-3 1.61E-01 8.78E-01 4.OOE-03 C-14 5.70E-02 1.83E-01 1.66E-02 Cr-51 2.99E-01 2.96E+00 2.17E-01 Mn-54 2.92E+00 3.27E+00 8.96E-01 Fe-55 3.39E+01 5.67E+01 2.80E+01 Co-57 1.73E-03 Co-58 2.82E-01 8.72E-01 2.75E-01 Fe-59 1.36E-01 4.27E-02 Ni-59 6.73E-03 7.29E-02 4.74E-02 Co-60 3.OOE+01 1.82E+01 6.12E+01 Ni-63 9.19E-01 9.47E-01 9.31E+00 Zn-65 3.58E+00 8.81E+00 2.12E-03 Sr-89 2.OOE-02 3.28E-06 Sr-90 9.71E-02 4.12E-02 7.35E-06 Nb-94 1.63E-04 Nb-95 1.09E-02 Zr-95 5.26E-02 Tc-99 1.13E-03 1.25E-04 7.38E-05 Cd-109 8.44E-06 AgllOm 2.24E-01 4.05E-02 2.81E-04 Sb-124 2.27E-02 1.49E-05 Sb-125 6.16E-02 I-129 4.12E-04 I-131 1.61E-01 4.44E-01 Cs-134 1.09E-03 3.09E-06 Cs-137 2.73E+01 5.32E+00 6.34E-05 Ba-140 2.15E-02 2.11E-02 La-140 1.13E-02 Ce-141 1.69E+00 2.99E-06 Ce-144 9.62E-03 2.82E-02 2.99E-06 Pu-238 2.OOE-03 2.45E-03 4.15E-05 Pu-239 7.54E-04 9.63E-04 8.96E-08 Am-241 5.23E-03 6.93E-03 3.63E-07 Pu-241 4.52E-02 9.39E-02 9.86E-06 Cm-242 2.OOE-03 1.61E-03 7.51E-07 Pu-242 2.09E-07 Cm-243 2.27E-03 7.48E-03 2.71E-07 Eu-152 1.42E-02

Page 13 RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan -

Dec 2003 Table 3 Solid Waste and Irradiated Fuel Shipments

3. Solid waste disposal Number of Mode of Destination Shipments Transportation 5

Truck Chem-Nuc Inc., Barnwell, SC.

3 Truck Envirocare, Clive, UT.

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 0309 5.39E+01 3.49E-01 B

L N

0345 5.83E+00 8.33E+00 A

L D

0346 5.83E+00 1.14E+01 A

L D

0347 5.83E+00 1.14E+01 A

L D

0356 5.89E+01 1.79E-01 B

L N

0357 4.85E+01 1.29E+00 B

L N

0365 1.64E+00 1.22E+04 C

B N

0361 1.64E+00 1.18E+04 C

B N

0343 1.64E+00 2.07E+04 C

B N

0359 1.64E+00 1.27E+04 C

B N

0362 3.86E+00 1.72E+02 C

B 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 31,2003 5 pages follow

MONTICELLO NUCLEAR GENERATING PLANT Offsite Radiation Dose Assessment for January 1, - December 31, 2003 An assessment of radiation dose due to releases from the Monticello Nuclear Generating Plant during 2003 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 2003.

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 releases in the second quarter with H-3, Mn-54, Co-58, Co-60, Zn-65, Xe-133 and I-131 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, construction work on the cooling towers and XCEL Energy Company transmission and distribution crews working in the substation. Use of a very conservative assumption of 40 hour4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months 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 number 11 cooling tower location (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 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.

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 Control dairy farm changed from the Goenner Farm, M-10 (out of business) to the Campbell Farm, M-10. Milk samples were unavailable at sample location M-10 (Goenner Farm) on 4/9/03 due to the farmer going out of business. Milk samples were unavailable at sample location M-28 (Hoglund Farm) from 6/4/03 to 9/9/03 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 9/24/03. There were no vegetable samples that could not be obtained during this reporting period.

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Table 1 Offsite Radiation Dose Assessment - Monticello PERIOD: January 1, through December 31, 2003 Maximum Site Boundary Gamma Air Dose (mrad/year) 10 Maximum Site Boundary Beta Air Dose 0.017 (mrad/year) 20 Maximum Off-Site Dose to Any Organ (mrem/year) 0.047 15 Maximum Dose to the Likely Most Exposed Member of the General Public (mrem/year)

Whole Body 0.039 5

Skin 0.073 15 Max Organ (Thyroid) 0.047 15 Maximum Off-Site Dose (mrem)

Whole Body 2.45E-07 3

Max Organ (Liver) 5.55E-07 10 OGFR 0

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

Whole Body 0.02 25 Skin 0.03 75 Max Other Organ (Thyroid) 0.03 25 Page 3 of 5

Table 2 Offsite Radiation Dose Assessment - Monticello Supplemental Information PERIOD: January 1, through December 31, 2002 Maximum Site Boundary Dose Location (from Reactor Building Vents)

Sector SSE Distance (miles) 0.40 Number 11 Cooling Tower Sector NE Distance from Plant Stack (miles) 0.09 Distance from Reactor Building Vents 0.13 Critical Receptor Location Sector SE Distance from Reactor Building Vents (miles) 1.1 Pathways Plume, Ground, Inhalation, Vegetable Age Group CHILD Organ THYROID 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 BVpass of Offgas Storage System for Greater than Seven Days ODCM-03.01, Section 2.4.3 Action states: "With gaseous waste being discharged for more than seven (7) days with an average holdup time of less than 50 hours5.787037e-4 days 0.0139 hours 8.267196e-5 weeks 1.9025e-5 months , document and report MA W ODCM-01.01, Section 2.4.1. C. "

Following plant startup, from a refueling outage the post-recombiner off-gas flow was at an abnormally high level (approx. 59 SCFM) due to high main condenser air inleakage.

At this inleakage rate, the storage system could not meet the ODCM-required average holdup time of 50 hours5.787037e-4 days 0.0139 hours 8.267196e-5 weeks 1.9025e-5 months . On 06/01/03 the seven-day action period was exceeded, which requires documentation per ODCM-01.01, Section 2.4.1.C: "Noncompliance with a CONTROL and associated ACTION, or a Surveillance Requirement SHALL be documented in the annual "Radioactive Effluent Release Report" covering the period of the noncompliance."

An investigation was initiated shortly after plant startup to determine the source of excessive air in-leakage. This investigation included identification of possible in-leakage pathways and systematic helium leak testing of relevant portions of the plant by both plant personnel and a vendor experienced in in-leakage inspections. One inleakage source (Condenser boot seal) was found while the plant was at low power.

Following an exhaustive search in steam areas and other plant areas, the plant ascended to full power.

Following plant startup, from a forced shutdown the post-recombiner off-gas flow was at an abnormally high level (approx. 59 SCFM) due to high main condenser air inleakage.

At this in-leakage rate, the storage system could not meet the ODCM-required average holdup time of 50 hours5.787037e-4 days 0.0139 hours 8.267196e-5 weeks 1.9025e-5 months . On 06/23/03 the seven-day action period was exceeded, which requires documentation per ODCM-01.01, Section 2.4.1.C: "Noncompliance with a CONTROL and associatedACTION, ora Surveillance Requirement SHALL be documented in the annual "Radioactive Effluent Release Report" covering the period of the noncompliance."

During the forced shutdown actions taken to minimize the air in-leakage were unsuccessful.

Cause:

The off-gas storage system was unable to maintain the required holdup 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.

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ENCLOSURE 3 Corrective The condenser inleakage investigation and resulting corrective actions are Actions:

documented in the site's corrective action program. Immediate corrective actions consisted of attempted repair of the Condenser boot seal using spray adhesive sealants. The size and location of the air inleakage caused the sealant application to be ineffective in reducing the air inleakage.

Work orders have been written to replace the Condenser boot seal, which prevents recurrence of major inleakage from this source. This work will be performed no later than the next refueling outage.

From an ALARA perspective it makes little sense at current release rates to shutdown the unit to replace the boot seal. A reactor shutdown followed by a week or more of workin the condenser to replace the boot seal would result in additional plant worker dose. Cycling the plant through a shutdown and restart represents an equipment challenge and could result in the need to repair additional equipment consequently resulting in dose to the workforce that could be avoided. Considering the minimal impact to the public of continued operation at current release rates, it is reasonable to avoid the risk presented by placing the plant through a major shutdown/restart evolution and to continue plant operation until an opportunity to repair or replace the condenser boot seal presents itself.

Significance: During storage system bypass in 2003, release rates were higher than historical. The Gamma air dose for 2003 was 0.022 mrad, which is higher than historical values. The beta air and particulate dose values also increased slightly.

The dose values for 2003 are a small fraction of the dose limits specified in 10CFR50 Appendix I, did not exceed 2% of the annual limits, and do 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 9DCM-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 2

4 4

2 3

1 6

1 0

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

"2003 Offsite File name 001 ODCM lndex.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 10,986 bytes 9,059 bytes 638,221 bytes 70,335 bytes 1,298,618 bytes 98,525 bytes 4,103,729 bytes 14,972 bytes 257,938 bytes 23,520 bytes 192,771 bytes 56,527 bytes 16,719 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 Contact the person identified submission.

in the cover letter for any discrepancies in document Page 1 of 1

ML041450248

Text

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