ML061290244

From kanterella
Jump to navigation Jump to search
Radioactive Effluent Release Report for January 1 - December 31, 2005
ML061290244
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 12/31/2005
From:
Nuclear Management Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
FOIA/PA-2010-0209, L-MT-06-032
Download: ML061290244 (32)
v • d • e


Text

ENCLOSURE I RADIOACTIVE EFFLUENT RELEASE REPORT FOR JANUARY 1 - DECEMBER 31, 2005 13 pages follow

NUCLEAk MANAGEMENT COMPANY MONTICELLO ZUCLEAR GENERATING PLANT License No. DPR-22 RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan - Dec 2005 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, Par iculates, and Tritium 10 CFR Part 20. AnndixB Tablh II. Couiimn 1 I -- - - - - -I -

C. Liquid Effluents 10 CFR Part 20, Appendix , Table II, Column 2 2.0 E-4 uci/ml for dissplt ed and entrained gases

3. Ave rage Energy (Not Applicable)

Page 2 RADIOAqTVE EFFLUENT RELEASE REPORT Period : Jan - Dec 2005 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. 1 lWeekly 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 i Tank sample analyzed prior to each planned release and continuous monitoring of gross adtivity during planned release.

5. Bat:ch Releases A. Liquid
1. Number of Batch Releases 0
2. Total Time Period if or Batch Releases 0.0 min
3. Maximum Time Perioq foi a Batch Release 0.0 min
4. Average Time PeriocIfo6 a Batch Release 0.0 min
5. Minimum Time Perioc6 fot a Batch Release 0.0 min
6. Average River Flow during Release 0.0 cf/sec B. Gaseous  :
1. Number of Batch Rf 2
2. Total Time Period 1700.0 min
3. Maximum Time Peril a Batch Release 1360.0 min
4. Average Time Peric a Batch Release 850.0 min
5. Minimum Time Peric a Batch Release 340 .0 min

Page 3 RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan - Dec 2005 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 2005 Table 1A Gaseous Effluents - Summation of all Releases Units 1st Qtr 2nd Qtr Est. Total Error, %

A. Fission & Activation gases

1. Total Release Ci 3.85E+01 2.46E+01 2.OOE+01 l
2. Average Release Rate uci/sec 4.95E+00 3.13E+00
3. Percent Tech Spec Qtrly Reporting Level Gamma Radiation  % 2.32E-02 1.20E-02 Beta Radiation  % 9.59E-03 2.84E-03 B. Iodines
1. Total I-131 Release Ci 4.82E-04 1.94E-04 1.OOE+01 l
2. Average I-131 Release Rate uci/sec I 6.20E-05 2.46E-05_1 C. Particulates
1. Total Particulates Ci 2.83E-04 1.80E-04 3.00E+01
2. Averaqe Release Rate I uci/sec 3.64E-05 2.29E-05
3. Gross Alpha Ra ioactivity Ci 6.66E-07 4.54E-07 D. Tritium
1. Total Release Ci 3.58E+00 2.38E+00 1.O0E+01
2. Average Release Rate I uci/sec I 4.61E-01 3.03E-01 E. Percent Qtrly Tech Spec Reporting Levels
1. Iodines, Particulates, I and Tritium 7.70E-02 2.38E-02

1.

Page 5 RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan - Dec 2005 Table 1A Gaseous Effluents - Summation of all Releases Units 3rd Qtr 4th Qtr Est. Total hError, 11__  %

A. Fission & Activation gases

1. Total Release :4 Ci 3.34E+01 2.94E+01 2.OOE+01
2. Averaqe Release Rate Ll_ uci/sec 4.21E+00 3.69E+00
3. Percent Tech Spec Qtrly l Reporting Level Gamma Radiation i
  • 1.96E-02 2.05E-02 Beta Radiation _ _ 8.45E-03 9.03E-03 B. Iodines
1. Total I-131 Release IL Ci 3.09E-04 1.89E-04 1.OOE+01
2. Average I-131 Release Rate uci/sec 3.89E-05 2.38E-05 C. Particulates
1. Total Particulates iC 1.64E-04 9.82E-05 3.00E+01 l
2. Average Release Rate II uci/sec 2.06E-05 1.24E-05
3. Gross Alpha Radioactivity Ci 3.15E-07 4.37E-07 I

D. Tritium I11 II 1. Total Release I I

Ci I 4.46E+00 I

I 3.39E+00 I I I 1.OOE+0l I 1

2. Average Release Rate I I: I uci/sec I 5.61E-01 I 4.26E-01 I I E. Percent Qtrly Tech Spec R 4 porting Levels
1. Iodines, Particulates, il and Tritium 1_P!
  • 2.28E-02 1.04E-02

Page 6 RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan - Dec 2005 Table 1B Gaseous Effluents - Elevated Releases Continuous Mode Batch Mode Nuclides Released Unit 1st Qtr 2nd Qtr 1st Qtr 2nd Qtr

1. Fission Gases KR-85M Ci j1.07E+00 1.06E-02 O.OOE+00 O.OOE+00 KR-87 Ci I1.21E+00 1.87E-01 O.00E+0T O.OOE+00 KR-88 CI l~2.47E+00 O.OOE+00 O.00E+00 O.00E+0o XE-133 Ci i1.68E+01 1.03E+01 0.00E+00 0.00E+00 XE-133M Ci i3.40E-01 3.82E-02 0. ooE+o0 o. 00E+00 XE-135 Ci i9.27E+00 8.46E-01 0.OOE+00 0.OOE+00 XE-135M CiT 7.62E-01 2.08E+00 0.OOE+00 0.00E+00 XE-137 Ci 1.90E+00 1.12E+00 0.00E+00 0.00E+00 XE-138 Ci 1.93E+00 9.08E+00 0.00E+00 0.OOE+00 AR-41 CiT 1.03E-01 O.OOE+00 O.OOE+00 O.OOE+00 Total for Period ICi 3.59E+01 2.37E+01 0.OOE+00 0.00E+00
2. Iodines I-131 I-133 I-135 Ci i

Uir

_ r 2.06E-04 1.69E-03 2.86E-03 1.29E-04 1.31E-03 2.49E-03 0.00E+00 0.OE+00

_).O00E+00 0.OOE+00 0.00E+00 O.OOE+00 Total for Period Ci 4.75E-03 3.93E-03 0.00E+00 0.00E+00

3. Particulates MN-54 -Ci 1.50E-07 2.46E-07 O.OOE+00 O.0OE+00 CO-60 Ci 5.74E-06 3.30E-06 0.OOE+00 0.OOE+00 CS-137 Ci 1.33E-07 1.96E-07 0.OOE+00 0.OOE+00 BA-140 -C 11.01E-05 9.44E-06 0.OOE+00 0.OOE+00 SR-89 Ci 11.28E-06 4.43E-06 O.OOE+00 0.OOE+00

__ SR-90 Ci 16.80E-09 7.09E-08 0.0OE+00 0.OOE+00 SE-75 Ci [l3.59E-11 2.27E-12 0.00E+00 0.00E+00 Total tor Period - Ci I1.74E-05 1.77E-05 O.OOE+0O O.OOE+00

Page 7 RADIOACTIVE EFFLUENT RELEASE REPORT Period  : Jan - Dec 2005

i,
1!E Table 1B Gaseous Effluents - Elevated Releases P

s .

4 ,i

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

1. Fission Gases KR-87 Ci 6.l0E-02 8.15E-02 0.OOE+00 0.OOE+00 KR-88 .0-0M +0- 3 .88EOE+

KR-89 Ci I0.00E+00 4.88E-01 O.OOE+00 O.00E+00 XE-133 Ci i2.13E+01 1.37E+0 0.OOE+00 0'.00E+00 XE-133M Ci ii6.60E-02 3.77E-02 0.00E+00 0.00E+00 XE-135 Ci l1.14E+00 1.22E+00 0.OOE+00 0.OOE+00 XE-135M Ci ll2.03E+00 2.39E+00 0.O0E+00 0.OOE+00 XE-137 Ci i 1.08E+ 0 2.52E+00 0.00E+00 0.OOE+00 XE-1'38 Ci i 5.29E+00 6.29E+-00 0.00E+00 0.OOE+'00 Total tor Period __ Ci _ 3.09E+01) 2.68E+01 O.OOE+00 O.OOE+00

2. Iodines I-131 Ci ii2.10E-04 1.22E-04 0.OOE+00 0.OOE+00 I-133 Ci L.98E-03 1.12E-03 0.00E+00 0.00E+00 I-135 Ci ,l3.59E-03 2.03E-03 0.00E+00 0.O0E+00 Total tor Period Cl .!5.78E-03 3.28E-03 0.00E+00 0.OOE+00
3. Particulates CO-60 l Ci il.03E-06 5.69E-07 0.OOE+00 0.OOE+00 BA-140 l Ci 0i.50E-05 9.47E-06 0.00E+00 0.OOE+00 SR-89 I Ci '5.40E-06 3.07E-06 0.OOE+00 0.00E+00 SR-90 Ci i3.6lE-08 2.18E-08 0.00E+00 0.OOE+00 Total tor Period Ci II2 .1SE-05 1.31E-05 0. OOE+00 0.OOE+00

Page 8 RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan - Dec 2005 Table 1C! Gaseous Effluents - Building Vent Releases s1 t NCd Rontinuous Mode Batch Mode Nuclides Released IUnit ,l"st Qtr l2nd Qtr l1st Qtr l2nd Qtr

1. Fission Gases XE-133 jCi 0.00E+00 j 6.03E-01 0.OOE+00 I 0.OOE+00 XE-135 Ci 2.57E+00 3.46E-01 3.83E-3 0.OOE+00 AR-41 Ci Q.00E+00 0.OOE+00 9.07E-03 0.0OE+00 Total for Period __Ci _ 2.57E+00 9.49E-01 1.29E-02 0.OOE+00
2. Iodines F 1-131 Ci 2.76E-04 6.48E-05 0.OOE+00 0.OOE+00 I-133 Ci F 9.22E-04 4.61E-04 0.OOE+00 0.OOE+00 I-135 S.19E-04 5Ci 0.OOE+00 0.OOE+00 0.OOE+00 Total for Period ____Ci 1.72E-03 5.26E-04 0.00E+00 0.OOE+00
3. Particulates MN-54 Ci 1.30E-05 9.42E-06 0.00E+00 0.0OE+00 C0-58 Ci 4.36E-06 0.O0E+00 0.OOE+00 0.OOE+00 CO-60 Ci 1.53E-04 9.33E-05 1.01E-05 0.00E+00 ZN-65 Ci 3.98E-05 3.48E-05 0.0OE+00 0.0OE+00 CS-137 Ci 3.41E-05 2.22E-05 0.00E+00 0.00E+00 BA-140 Ci .02E-05 0.OOE+00 0.OOE+00 0.OOE+00 CE-141 Ci 4.97E-07 0.OOE+00 0.00E+00 0.OOE+00 SR-89 Ci F3.11E-07 2.38E-06 0.0OE+00 a.OOE+00 SR-90 C_ i 1.91E-09 2.53E-07 0.OOE+00 0.O0E+00 Total for Period Ci_ 2.55E-04 1.62E-04 1.01E-05 0.OOE+00

Page 9 RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan - Dec 2005 Table 1C Gaseous Effluents - Building Vent Releases Continuous Mo e Batch Mode Nuclides Released Unit 3rd Qtr 4th Qtr 3rd Qtr 4th Qtr

1. Fission Gases XE-135 Ci 2.35E+00 2.58E+00 0.OOE+00 0.OOE+00 XE-135M Ci J1.60E-01 0.OOE+00 0.00E+00 0.OOE+00 Total for Period Ci 2.51E+0 2.58E+00 0.OOE+00 0.OOE+00
2. Iodines I-131 1 .96E-05 6.75E-05 I 0.OOE+00 0.OOE+00 I-133 _ Ci _ 7.29E-04 5.29E-04 0.OOE+00 0.OOE+00 Total for Period _ Ci _ 8.28E-04 5.96E-04 0.OOE+00 0.OOE+00
3. Particulates CO-60 Ci lI7.17E-05 5.48E-05 0.OOE+00 0.OOE+00 ZN-6S C1 0:2.52E-05 0.00E+00 - 0.00E+00 - 0.OOE+00 CS-137 Ci ip4.07E-05 2.76E-05 0.00E+00 0.O0E+00 SR-89 C 4.82E-06 2.63E-06 0.00E+00 0.OOE+00 SR-90 Ci ii8.62E-09 2.65E-08 0.OOE+00 0.OOE+00 Total for Period I Ci 1_1.42E-04 8.50E-05 O.OOE+00 0.OOE+00

Page 10 RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan - Dec 2005 Table 2A Liquid Effluents - Summation of all Releases Units 1st Qtr 2nd Qtr Est. Totall I I I__ I Error, %_I A. Fission & Activation products

1. Total Release (not including tritium, gases, alpha) Ci 0.OOE+00 0.IOE+00 0.OOE+00 I
2. Avg Diluted Concentration I uci/m.

m 0.OOE+00 I 0.QOE+00 I B. Tritium I1. Total Release Ci 0.OOE+00 0.OOE+00 0.00E+00 l

2. Avg Diluted Concentration uci/ml 0. OE+00 0.0 E+00 C. Dissolved and Entrained Gases l 1. Total Release Ci 0.OOE+00 0.00E+00 0.OOE+00 I l 2. Avg Diluted Concentration I uci/mi I 0.OOE+00 0.00E+00 D. Percent Qtrly Tech Spec Reporting Level
1. Whole Body Dose  % 0.OOE+00 0.00E+00
2. Organ Dose  ! 0.00E+00 0.OOE+00 E. Gross Alpha Radioactivity
1. Total Release Ci 0.OOE+00 0.OOE+00 0.OOE+00 I IF. Volume of Waste Released in Liters j0.OOE+00 0.OOE+00 0.OOE+00 I IF. Volume of Dilution Water Used I Liters 0.00E+00 I 0.OOE+00 0.00E+00 l Table 2B Liquid Effluents Continuous Mode Batch Mode Nuclides Released Unit 1st Qtr I 2nd Qtr 1st Qtr I 2nd Qtr Non l R

.eleased This Period

Page 11 RADIOACTIVE EFFLUENT RELEASE REPORT Period

  • Jan - Dec 2005 Table 2A Liquid Effluents - Summation of all Releases Units 3r Qtr 4th Qtr Est. Total Error, %

A. Fission & Activation products

1. Total Release (not including tritium, gases, alpha) i 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 OE+00 0.OOE+00
2. Avg Diluted Concentration uci/ml 1.OOE+00 0.00E+00 C. Dissolved and Entrained Gases
1. Total Release Ci 0.00E+00 0.OOE+00 0.OQE+00 l
2. Avg Diluted Concentration uci/mi 0.OOE+00 0.OOE+00 D. Percent Qtrly Tech Spec Reporting Level
1. Whole Body Dose I 0.OOE+00 0.OOE+00 l l 2. Organ Dose . %0.OOE+00 0.0E+00 E. Gross Alpha Radioactivity!
1. Total Release Ci 0.OOE+00 0.00E+00 I 0.OOE+00 l IF. Volume of Waste Released Liters 0.OOE+00 0.OOE+00 7 0.OOE+00 IF. Volume of Dilution Water Used Liters I O.OOE+OO I O.OOE+OO I O.OOE+O0 i Tab.e 2B Liquid Effluents 1,

I: Continuous Mode Batch Mode I Nuclides Released

_ I-Unit 3rd Qtr I 4th Qtr I 3rd Otr I 4th Qtr I No ee Released This Period

'r I! !I Ei

Page 12 RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan - Dec 2005 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) 6.29E+01 3.70E+01 B. Dry compressible waste, Cu. Meter 3.20E+02 contaminated equipment, etc. Ci (est) 1.60E+00 3.50E+01 C. Irradi ated components, Cu. Meter u.OOE+00 control rods, etc. Ci 0.OOE+00 0.OOE+00 D. Other (describe) Cu. Meter 0.O0E+00 Ci 0.OOE+00 0.OOE+00

2. Estimate of ma or nuclide composition (by type or F

waste)

Type A Type B Type C Type D Nuclide percent percent I percent ,

percent H-3 9. 81E-02 1.13E-01 _

C-14 7.84E-02 2.30E-01 Cr-51 1. 91E+00 Mn-54 3.34E+00 2.70E+00 Fe-55 4.37E+01 6.52E+01 Co-57 1.81E-02 Co-58 2.76E-01 9. 16E-01 Fe-59 6.85E-01 Ni-59 7.29E-03 9. 73E-02 Co-60 2. 83E+01 1.46E+01 Ni-63 9. 78E-01 9. 86E-01 Zn-65 1. 10E+01 6.51E+00 Sr-89 8.OOE-03 Sr-90 3. 14E-02 5.28E-02 Nb-95 7. 63E-02 Zr-95 4.31E-01 Tc-99 3.55E-04 Ag11Om 1.06E-O0 1.18E-01 Sb-124 1.84E-01 Sb-125 1, 6.07E-01 Cs-134 8.32E-02 Cs-137 1. 19E+01 2.50E+00

,i 1.41E+00 Ce-141 Ce-144 4. 71E-03 2.76E-01 Pu-238 1. 00E-03 3.09E-03 Pu-239 3.55E-0. 2.72E-03 Am-241 2. 35E-03 8.89E-03 Pu-241 2.11E-02 1.20E-01 Cm-242 1.00E-03 1.73E-03 Cm-243 1.00E-03 1.66E-03 Eu-152 1.40E-01 il

1 ii

4 Page 13 RADIOACTIVE EFFLUENT RELEASE REPORT Period : Jan - Dec 2005 Table 3 Solid Waste and Irradiated Fuel Shipments

3. Solid waste disposal I Destination

_ Envirocare, Clive, UT.

RACE Inc., Memphis, TN.

II B. Irradiated Fuel Shipments

1. Disposition I -- ..- -- .. -

Numoer or Maoe or Destination Shipments Transportation _

None This Period C. Shipping Container and Solidification Method No. Volume Activity Type ot Container Solidification M3 Ci Waste Code Code 05161 6.16E+01 5.62E-01i B L N 0548 3.81E+01 2.16E-01 B L N 0549 3.81E+01 2.70E-01 B L N 0550 5.89E+01 1.25E-01 B L N 0551 5.89E+01 1.47E-02 B L N 0561 6.42E+01 4.16E-01 B L N 0563 5.83E+00 1.71E+01 A L D 0564 5.83E+00 2.23E+01 A L D 0565 5.83E+00 2.35E+01 A L D Waste type Codes : Container Codes : Solidification Codes :

A - Spent resins, sludges f L - LSA C - Cement B - Dry waste, equipment A- Type A U - Urea Formaldehyde C - Irradiated components B - Type B D - Dewatering D - Other (describe) i N - Not Applicalble Q ag Qatt

b i ENCLOSURE 2 OFF-SITE RADIATION DOSE ASSESSMENT FOR JANUARY 1 - DECEMBER 31, 2005 5 pages follow

I MONTICELLO NUCLEAR GENERATING PLANT Offsite Radiation Dose Assessment for January 1, - December 31, 2005 An assessment of radiation dose due to releases from the Monticello Nuclear Generating Plant during 2005 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 2005.

f

! ,.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 Boundarn (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 in the SAB and Warehouse 5 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.

Page 1 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. Milk samples were unavailable at sample location M-28 (Hoglund Farm) from 6/29/05 to 10/05/05 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 10/20/05. 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, 2005 Maximum Site Boundary Gamma Air Dose 0.003 (mrad/year) 10 Maximum Site Boundary Beta Air Dose 0.003 (mrad/year) 20 Maximum Off-Site Dose to Any Organ (mrem/year) 0.025 15 Maximum Dose to the Likely Most Exposed Member of the General Public (mrem/year)

Whole Body 0.016 5 Skin 0.025 15 Max Orean Skin 0.025 15 Maximum Off-Site Dose (mrem)

Whole Body 0.00 3 Max Or an (All except bone) 0.00 10 Maximum Dose to Individuals due to their Activities Inside the Site Boundary (mrem)

Whole Body 0.015 25 Thyroid 0.016 75 Max Other Organ (Skin) 0.019 25 Page 3 of 5

Table 2 Offsite Radiation Dose Assessment - Monticello Supplemental Information PERIOD: January 1, through December 31, 2005 Maximum Site Boundary 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 SSW Distance from Reactor Building Vents (miles) 0.64 Pathways Plume, Ground, Inhalation, Vegetable Age Group CHILD Organ SKIN 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 4 of 5

- e~ e -

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.

Page 5 of 5

Is - I ENCLOSURE 4 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, thyroid and organ (skin), 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 <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 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 1 of5

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.

Page 2 of 5

Table 1 Offsite Radiation Dose Assessment - Monticello PERIOD: January 1, through December 31,2003 Boundary Ji (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 Oran Thoid) 0.047 15 Maximum Off-Site Dose (mrem)

Whole Body 2.45E-07 3 Max Or gan (Liver) 5.55E-07 10 Maximum Dose to Individuals due to their Activities Inside the Site Boundary (mrem)

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

Table 2 Offsite Radiation Dose Assessment - Monticello Supplemental Information PERIOD: January 1, through December 31, 2003 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 Oran 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.

Page 5 of 5

ENCLOSURE 5 OFF-SITE RADIATION DOSE ASSESSMENT FOR JANUARY 1 - DECEMBER 31, 2004 9

5 Pages Follow

11 i 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, thyroid and organ (skin), 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 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 ThD'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 ua (mrad/year) 10 Maximum Site Boundary Beta Air Dose 0.01 (mrad/year) 20 Maximum Off-Site Dose to Any Organ (mrem/year) 0.037 15 Maximum Dose to the Likely Most Exposed Member of the General Public (mrem/year)

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) 1.94E-10 10 Maximum Dose to Individuals due to their Activities Inside the Site Boundary (mrem)

Whole Body 0.009 25 Thyroid 0.009 75 Max Other Organ (Skin) 0.011 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 SKIN 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.

Page 5 of 5

Retrieved from "https://kanterella.com/w/index.php?title=ML061290244&oldid=2665025"