ML20080L988

Effluent & Waste Disposal Semiannual Rept,Period:Jul-Dec 1994

ML20080L988
Person / Time
Site:	Monticello
Issue date:	12/31/1994
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML20080L987	List: ML20080L986 ML20080L988
References
NUDOCS 9503030079
Download: ML20080L988 (15)

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Attachment A l

' Effluent and Waste Disposal Semiannual Report l

Period Jul-Dec'1994 I

j 9503030079 950227 DR ADOCK 05000263 PM l

NORTHERN-STATES POWER COMPANY l

MONTICELLO NUCLEAR GENERATING PLANT License No. DPR-22 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT '

Period : Jul - Dec 1994 Supplemental Information.

'1.

Regulatory Limits - Quarterly levels requiring reporting to f

Nuclear Regulatory Commission A.' Noble Gases :

5 mrad / quarter gamma radiation 10 mrad / quarter beta radiation

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B.

Long Lived Iodines, Particulates, and Tritium :

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7.5 mrem / quarter dose to any organ C.

Liquid Effluents l

1.5 mrem / quarter dose to_the total body 5.0 mrem / quarter dose to any organ i

2. Maximum Permissible Concentrations i

.l A. Noble Gases :

10 CFR Part 20, Appendix B, Table II, Column 1 i

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Long Lived Iodines, Particulates, and Tritium :

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10 CFR Part 20, Appendix B, Table II, Column 1 I

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)

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I EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1994

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Supplemental Information (continued) 46, Maasurements and Approximations of Total.Radioactivty i

A. Noble Gases :

Continuous ~ gross activity monitors in Reactor Building Vent and Plant l

Stack exhaust streams.

Weekly isotopic analysis of exhaust streams.

B.

Iodines in Gaseous Effluent :

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continuous monitoring with charcoal ~ cartridges in. Reactor Building Vent and Plant Stack exhaust streams with weekly analysis.

C.

Particulates in Gaseous Effluent :

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Continuous monitoring with particulate filters in Reactor Building i

Vent and Plant Stack exhaust streams with weekly analysis.

D. Tritium in Gaseous Effluent :

'Continous monitoring with silica gel cartridges in Reactor Building f

Vent and Plant Stack exhaust streams with weekly analysis.

i E. Liquid Effluents :

1 Tank sample analyzed prior to each planned release and continuous

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monitoring of gross activity during planned release.

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5. Batch Releases l

l A. Liquid :

1. Nuu.ber 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 l

5. Minimum Time Period for a Batch Release 0.0 min

6. Average River Flow During Release 0.0 cf/sec f

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B. Gaseous :

1. Number of Batch Releases 4

2. Total Time Period for Batch Releases 3137.0 min j

3. Maximum Time Period for a Batch Release 1782.0 min i

4. Average Time Period for a Batch Release 784.3 min i

5. Minimum Time Period for a Batch Release 293.0 min l

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4 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul

~Dec 1994 Supplemental Information (continued)

6. Abnormal Releases

. Liquid :

A.

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 l

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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1994 Table 1A Gaseous Effluents - Summation of all Releases Units 3rd Qtr 4th Qtr Est. Total Error. %

A.

Fission & Activation gases 1.

Total Release Ci 1.06E+02 9.67E+01 2.00E+01 l 2.

Averace Release Rate uci/sec 1.33E+01 1.22E+01 3.

Percent Tech Spec Qtrly Reporting Level Gamma Radiation 8.34E-02 6.14E-02 Beta Radiation 4.13E-02 2.04E-02 B.

Iodines 1.

Total I-131 Release Ci 2.54E-03 8.39E-04 1.00E+01 l 2.

Averace I-131 Release Rate uci/sec 3.19E-04 1.06E-04 C.

Particulates 1.

Total Particulates Ci 8.34E-04 5.52E-04 1 3.00E+01 l 2.

Averace Release Rate uci/sec 1.05E-04 6.94E-05 3.

Gross Aloha Radioactivity Ci 6.41E-06 3.98E-06 D.

Tritium 1.

Total Release Ci 2.11E+01 1.33E+01 1.00E+01 l 2.

Averace Release Rate uci/sec 2.65E+00 1.68E+00 1

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Percent Qtrly Tech Spec Reporting Levels

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Iodines, Particulates, and Tritium 4.28E-01 1.06E-01 l

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f EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1994 Table 1B Gaseous Effluents - Elevated Releases Continuous Mode Batch Mode Nuclides Released Unit 3rd Otr l 4th Otr 3rd Otr l 4th Otr 1.

Fission Gases KR-85M Ci 1.27E-02 1.21E+00 0.00E+00 0.00E+00 KR-87 Ci 7.42E-01 1.79E+00 0.00E+00 0.00E+00 KR-88 Ci 7.96E-01 2.86E+00 0.00E+00 0.00E+00 KR-89 Ci 9.39E-01 0.00E+00 0.00E+00 0.00E+00 XE-133 Ci 3.65E+01 2.50E+01 0.00E+00 8.08E-03 XE-133M Ci 4.70E-01 3.58E-01 0.00E+00 0.00E+00 XE-135 Ci 2.86E+00 1.83E+01 0.00E+00 4.76E-03 XE-135M Ci 5.68E+00 8.12E+00 0.00E+00 0.00E+00 XE-137 Ci 3.04E+01 1.48E+01 0.00E+00 0.00E+00 XE-138 Ci 1.59E+01 1.89E+01 0.00E+00 0.00E+00 AR-41 Ci 0.00E+00 6.46E-02 0.00E+00 1.87E-02 Total for Period Ci 9.43E+01 9.13E+01 0.00E+00 3.15E-02 2.

Iodines I-131 Ci 5.73E-04 5.80E-04 0.00E+00 0.00E+00 I-133 Ci 2.13E-03 2.19E-03 0.00E+00 0.00E+00 I-135 Ci 2.69E-03 1.17E-03 0.00E+00 0.00E+00 Total for Period Ci 5.39E-03 3.94E-03 0.00E+00 0.00E+00 3.

Particulates CR-51 Ci 7.54E-07 0.00E+00 0.00E+00 0.00E+00 MN-54 Ci 1.97E-07 8.40E-07 0.00E+00 0.00E+00 CO-60 Ci 2.79E-06 6.54E-06 0.00E+00 1 47E-07 ZN-65 Ci 4.37E-06 4.66E-06 0.00E+00 0.00E+00 RU-103 Ci 0.00E+00 4.63E-08 0.00E+00 0.00E+00 CS-137 Ci 1.05E-06 2.01E-06 0.00E+00 0.00E+00 BA-140 Ci 1.36E-04 9.73E-05 0.00E+00 0.00E+00 HG-203 Ci 0.00E+00 4.08E-07 0.00E+00 0.00E+00 SR-89 Ci 7.38E-05 0.00E+00 0.00E+00 0.00E+00 SR-90 Ci 4.00E-07 0.00E+00 0.00E+00 0.00E+00 Total for Period Ci 2.19E-04 1.11E-04 0.00E+00 1.47E-07 Analysis of Sr-89 & 90 for the 4th Qtr was not completed in time for this report, results will be included with the next semiannual report.

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EFFLUENT AND' WASTE DISPOSAL-SEMIANNUAL REPORT Period : Jul - Dec 1994 i

Table 1C Gaseous Effluents - Building Vent Releases

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Continuous Mode Batch Mode Nuclides Released Unit 3rd Otr l 4th Otr 3rd Otr 1 4th Otr r

l'.: Fission Gases j

XE-133 Ci 3.94E-01 0.00E+00 7.31E-03 3.24E-03 XE-135 Ci 1.04E+01 4.68E+00 6.01E-03 0.00E400 t

XE-135M Ci 8.29E-01 5.99E-01 0.00E+00

-0.00E+00 AR Ci 0.00E+00 0.00E+00 1.23E-03 1.41E-02 j

Total for Period Ci 1.16E+01 5.28E+00 1.46E-02 1.73E-02 2.

Iodines I-131 Ci 1.96E-03 2.59E-04 0.00E+00 0.00E+00 l

I-133 Ci 1.24E-02 1.32E-03 0.00E+00 0.00E+00 I-135 C1 1.92E-02 2.13E-04 0.00E+00 0.00E+00 l

f Total for Period Ci 3.36E-02 1.79E-03 0.00E+00 0.00E+00 3.

Particulates t

MN-54 Ci 3.91E-06 6.03E-06 0.00E+00 0.00E+00 CO-58 Ci 5.57E-06 0.00E+00 0.00E+00 0.00E+00 CO-60 Ci 1.96E-04 1.45E-04 2.02E-06 0.00E+00 ZN-65 Ci 2.87E-04 2.64E-04 0.00E+00 1.35E-05 CS-137 Ci 6.80E-05 1.18E-05 0.00E+00 0.00E+00 BA-140 Ci 3.24E-05 0.00E+00 0.00E+00 0.00E+00 CE-141 Ci 1.00E-06 0.00E+00 0.00E+00 0.00E+00 SR-89 Ci 1.85E-05 0.00E+00 0.00E+00 0.00E+00

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SR-90 Ci 9.26E-08 0.00E+00 0.00E+00 0.00E+00 l

Total for Period Ci 6.13E-04 4.27E-04 2.02E-06 1.35E-05 Analysis of Sr-89 & 90 for the 4th Qtr was not completed in time for this report, results will be included with the next semiannual report.

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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1994 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, cases, aloha)

Ci 0.00E+00 0.00E+00 0.00E+00 2.

Ava Diluted Concentration uci/ml 0.00E+00 0.00E+00 D. Tritium 1, Total Release Ci 0.00E+00 0.00E+00 0.00E+00 l 2.

Ava Diluted Concentration uci/ml 0.00E+00 0.00E+00 C.

Dissolved and Entrained Gases 1.

Total Release Ci 0.00E+00 0.00E+00 0.00E+00 l 2.

Ava Diluted Concentration uci/ml 0.00E+00 0.00E+00 D.

Percent Otrly Tech Spec Reporting Level 1.

Whole Body Dose 0.00E+00 0.00E+00 2.

Orcan Dose 0.00E+00 0.00E+00 E.

Gross Alpha Radioactivity l

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Total Release l

Ci 1 0.00E+00 l 0.00E+00 1 0.00E+00 l l

lf. Volume of Waste Released l

Liters l 0.00E+00 l 0.00E+00 l 0.00E+00 l l

1 lF. Volume of Dilution Water Used I Liters l 0.00E+00 1 0.00E+00 1 0.00E+00 l i

Table 2B Llquid Effluents Continuous Mode Batch Mode Nuclides Released Unit 3rd Otr I 4th Otr 3rd Otr l 4th Otr None Released This Period l

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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1994 Table 3 Solid Waste and Irradiated Fuel Shipments A. Solid Waste Shipped Offsite for Burial or Disposal (not ir' radiated fuel) 1.

Type cf Waste Units 6-month Est. Total Period Error, %

a. Spent resins, filter sludges, Cu. Meter 0.00E+00 evaporator bottoms, etc.

Ci 0.00E+00 0.00E+00

b. Dry compressible waste, Cu. Meter 0.00E+00 contaminated eauipment, etc.

Ci 0.00E+00 0.00E+00 c.

Irradiated components, Cu. Meter 0.00E+00 control rods, etc.

Ci 0.00E+00 0.00E+00

d. Other (describe)

Cu. Meter 0.00E+00 i

Ci 0.00E+00 0.00E+00

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

Type A Type B Type C Type D Nuclide cercent percent cercent percent

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I EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT h

Period : Jul - Dec 1994 1

Table 3 Solid Waste and Irradiated Fuel Shipments

3. Solid waste disposal Number of Mode of Destination Shioments Transoortation i

B.

Irradiated Fuel Shipments 1.

Disposition Number of Mode of Destination Shloments Trangoortation None This Period C.

Shipping Container and Solidification Method No.

Volume Activity Type of Container Solidification M3 Ci Waste Code Code i

Container Codes :

Solidification Codes :

L - LSA C-Cement A - Type A U - Urea Formaldehyde B - Type B D - Dewatering 0 - Large Quantity N - Not Applicalble i

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Attachment B Off-Site Radiation Dose Assessment for January 1, - December 31, 1994 t

NORTHERN STATES POWER COMPANY MONTICELLO NUCLEAR GENERATING PLANT Off-Site Radiation Dose Assersment for January 1, - December 31,1994 An assessment of radiation dose due to releases from the Monticello Nuclear Generating Plant during 1994 was performed in accordance with the Technical Specifications. Computed doses were well below the 40 CFR 190 Standards and 10 CFR Part 50, Appendix I Guidelines.

Off-site dose calculation fonnulas and meteorological data from the Off-site Dose Calculation Manual were used in making this assessment. Source terms were obtained from the two Semi-Annual Effluent Release Reports for 1994.

Off Site Doses from Gaseous Releases Computed doses due to gaseous releases are reported in Table 1. Critical receptor location and pathways for organ doses are reported in Table 2. Doses, both whole body and organ, are a small percen; age of Appendix I Guidelines.

Off-Site Doses From Liquid Releases There were no Liquid releases in 1994 as listed in Table 1.

Doses to Individuals Due to Activities Inside the Site Houndary 3

Occusionally sportsmen enter the Monticello site for recreational activities, in addition, an Environmental Protection Agency Field Station is located at the Monticello site (see Figure 3.8.1 and 3.8.2 of the Monticello Technical Specifications). Workers at this field station, spending an average of 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> / week, are the most exposed individuals. Whole body doses to these individuals have been computed using stack and vent X/Q values for the Field Station location.

Annual computed doses were reduced by the factor of 40/168 to account for the limited occupancy for workers at this location. Organ doses to workers at the EPA Field Station due to gaseous releases have been computed. Doses at this location are reported in Table 1.

Doxes to Most Ewosed Member of the General Public from Reactor Releases and Other Uranium Fuel Cycle Sources.

There are no other uranium fuel facilities in the vicinity of the Monticello site. The only other artificial source of exposure to the general public in addition to the plant efGuent releases is from direct radiation of the reactor and the steam turbines. MNGP started a hydrogen water chemistry (llWC) program in February 1989. Prior to the installation of IIWC, a study was conducted to determine the direct and skyshine radiation contribution from IIWC.

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Doses to Most Exposed Member of the General Public from Reactor Releases and Other Uranium Fuel Cycle Sources cont...

This study determined the maximum exposed member of the public from direct and sky shine radiation to be a residence located 0.6 miles from the reactor at the SW sector.

Using conservative assumptions, calculations indicated a maximum annual dose of 4 mrem to this residence. Ilowever, a review of TLD results from 1987 through 1994 revealed no noticeable increase in direct and skyshine radiation as a result of the liWC program installed in early 1989.

A calculation of the total annual dose to this residence from all existing pathways of radioactive effluents was performed by running GASPAR computer codes. Adding 4 mrem / year to this j

calculation results in a maximum whole body dose of 4.02 mrem in 1994.

i Therefore, the most exposed member of the general public will not receive an annual radiation i

dose from reactor effluent releases and all other fuel cycle activities in excess of 40 CFR 190 j

standards of 25 mrem to the whole body,75 mrem to the thyroid, and 25 mrem to any other r

organ.

Radiological Environmental Monitoring Program Sampling Deviations t

There were no milk or vegetable sampling deviations during this reporting period. Two Dairy locations did change as a result of farmers going out of buisness. The final dairy sample from the Control Dairy (location; NW sector,323 degrees at 11.5 miles) farm was taken on December i

12,1994. Therefore all samples for 1994 were taken at this location. The monthly control dairy sample was resumed in January 1995 at location; NW sector,321 degrees at 12.5 miles. The liolthaus farm at location; S sector,175 degrees at 4.2 miles sold their dairy herd. The final sample taken at this location was November 8,1994. The highest D/Q dairy farm for 1994 was unaffected by these changes.

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1 Table 1 Off-Site Radiation Dose Assessment - Monticello PERIOD: January 1, through December 31,1994 m.d.. '

110CFR50 App 4I?

iGASEOUS:

' DOSE;

?[ Guidelines per; '

1 RELEASES year;q Max. Site Boundary Gamma Air Dose (mrad) 0.220 10 l

Max. Site Boundary Beta Air Dose (mrad) 0.390 20 Max. Off-site Dose to Any Organ (mrem) 0.050 15 EPA Field Station (mrem,40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> / week) i Whole Body 0.003 5

Organ (skin) 0.005 15 Liquid Releasesi Max. Off-Site Dose Whole Body (mrem) 0.000 3

Max. Off-Site Dose Organ, Total (mrem) 0.000 10 Page 3 of 4 l

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Table' 2 I

Off-Site Radiation Dose Assessment - Monticello Supplemental Information PERIOD: January 1, through December 31,1994 i

Gaseous Releases Max. Site Boundary Dose Location (from building vents)

Sector SSE i

Distance (miles) 0.43 (vent)

EPA Field Station i

Sector SE Distance (miles) 0.26 (Stack) 0.36 (Vent)

Maximum Off-site Dose Location Sector SSV!

Distance 0.70 Pathways

Ground, Inhalation, Vegetable Age Group Child Organ Thyroid Liquid Releases Max. Off-Site Dose Location Downstream Pathways Drinking Drinking Water Water Fish Age Group Infant Adult Organ W. Body GI-LLI Dilution Factor 7.1 7.1 l

(drinking water)

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