ML20064B765

Effluent & Waste Disposal Semiannual Rept Jul-Dec 1993

ML20064B765
Person / Time
Site:	Monticello
Issue date:	12/31/1993
From:	Richard Anderson NORTHERN STATES POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9403090012
Download: ML20064B765 (16)

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Northem States Power Compray 414 Nicollet Mall Minneapolis, Minnesota 55401 1927 Telephone (612) 330-5500 February 23, 1994 Technical Specification 6.7.A.4 US Nuclear Regulatory Commission l Attn: Document Control Desk Washington, DC 20555 MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 Effluent and Waste Disposal Semi-Annual Report for Julv Throuch December 1993 In accordance with the Monticello Technical Specifications, Appendix A to l Operating License DPR-22, we are submitting the Effluent and Waste Disposal l Semi-Annual Report for the second half of year 1993.

l l The Offsite Dose Calculation Manual (ODCM) and Process Control Program (PCP)

Manual are not attached since they remained unchanged during the reporting period. There have been no changes in land use which could result in a significant increases in calculated doses.

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

Please contact Marv Engen, Sr Licensing Engir.eer, at (612) 295-1291 if you require further information.

1 Roger O Anderson Director Licensing and Management Issues c: Regional Administrator - III, NRC NRR Project Manager, NRC l Sr Resident Inspector, NRC State of Minnesota Attn: Kris Sanda ,.3 r, p ,,

J Silberg s- ' .d fis Attachment A Effluent and Waste Disposal Semiannual Peport, Period Jul-Dec 1993 Attachment B Off-Site Radiation Dose Assessment for January 1, - December 31, 1993 9403090012 931231 PDR ADOCK 05000263 ,

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l i i Attachment A Effluent and Waste Disposal Semiannual Report Period Jul-Dec 1993 i

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. NORTHERN STATES POWER COMPANY

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MONTICELLO NUCLEAR GENERATING PLANT License No. DPR-22 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1993 Supplemental Information

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

5 mrad / quarter gamma radiation 10 mrad / quarter beta radiation B. Long Lived Iodines, Particulates, and Tritium :

7.5 mrem / quarter dose to any organ C. Liquid Effluents :

1.5 mrem / quarter dose to the total body 5.0 mrem / quarter dose to any organ

2. Maximum Permissible Concentrations A. Noble Gases :

10 CFR Part 20, Appendix B, Table II, Column 1 B. Long Lived Iodines, Particulates, and Tritium :

10 CFR Part 20, Appendix B, Table II, Column 1 C. Liquid Effluents :

10 CFR Part 20, Appendix B, Table II, Column 2 2.0 E-4 uci/ml for dissolved and entrained gases

3. Average Energy (Not Applicable)

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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1993 l

I Supplemental Information (continued) l

4. Measurements and Approximations of Total Radioactivty A. Noble Gases :

I l 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 :

Continous monitoring with silica gel cartridges in Reactor Building Vent and Plant Stack exhaust streams with weekly analysis.

E. Liquid Effluents :

Tank sample analyzed prior to each planned release and continuous monitoring of gross activity during planned release. i

5. Batch Releases l A. Liquid :

l I 1. Number of Batch Releases 0

2. Total Time Period for Batch Releases NA min

3. Maximum Time Period for a Batch Release NA min

4. Average Time Period for a Batch Release NA min

5. Minimum Time Period for a Batch Release NA min

6. Average River Flow During Release NA cf/sec l

B. Gaseous :

1. Number of Batch Releases 0 l

2. Total Time Period for Batch Releases 0.0 min i

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 i

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a EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec- 1993 a

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} Supplemental Information (continued)

6. Abnormal Releases i

A. Liquid :

i 1. Number of Releases 0

j. 2. Total Activity Released NA Ci 1

j B. Gaseous :

1. Number of Releases 0 f Ci j 2. Total Activity Released 0.0 k

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Page 4 l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1993 Table 1A Gaseous Effluents - Summation of all Releases  ;

l l l Units l 3rd Qtr l 4th Qtr lEst. Totall j l l l l l Error, % l A. Fission & Activation gases l 1. Total Release l Ci 1.81E+02 l 1.71E+02 l 2.00E+01 l l 2. Averace Release Rate I uci/sec 2.28E+01 l 2.15E+01 l l 3. Percent Tech Spec Qtrly l l l l l Reporting Level l l l l l Gamma Radiation l  % l 2.14E-01 l 1.18E-01 l l Beta Radiation l  % l 5.60E-02 j 5.00E-02 i B. Iodines l l 1. Total I-131 Release I Ci l 2.79E-03 l 1.85E-03 1 1.00E+01 l l 2. Average I-131 Release Rate l uci/sec l 3.51E-04 1 2.33E-04 l C. Particulates l 1. Total Particulates l Ci l 1.76E-03 l 1.76E-03 1 3.00E+01 l l 2. Average Release Rate uci/sec l 2.22E-04 l 2.21E-04 l l 3. Gross Alpha Radioactivity Ci l 5.84E-06 l 5.37E-06 l D. Tritium l 1. Total Release l Ci l 1.39E+01 l 1.53E+01 l 1.00E+01 l l 2. Average Release Rate l uci/sec l 1.75E+00 l 1.92E+00 l E. Percent Qtrly Tech Spec Reporting Levels l 1. Iodines, Particulates, l l l l l and Tritium l  % l 5.77E-01 l 4.73E-01 l l

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Page 5 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1993 Table 1B Gaseous Effluents - Elevated Releases l l l Continuous Mode l Batch Mode l l Nuclides Released l Unit l 3rd Qtr l 4th Qtr l 3rd Qtr i 4th Qtr l

1. Fission Gases l KR-85M l Ci I 0.00E+00 2.31E-02 1 0.00E+00 1 0.00E+00 l l KR-87 l Ci 1.74E+00 1.39E+00 l 0.00E+00 1 0.00E+00 l l KR-88 l- Ci 1.09E+00 5.04E-01 l 0.00E+00 1 0.00E+00 l l KR-89 l Ci 1.59E+00 0.00E+00 1 0.00E+00 1 0.00E+00 l l XE-133 l Ci l 2.92E+01 4.91E+01 0.00E+00 1 0.00E+00 l l XE-133M Ci i 4.54E-01 8.02E-01 0.00E+00 1 0.00E+00 l l XE-135 Ci l 5.21E+00 3.40E+00 '

O.00E+00 1 0.00E+00 l l XE-135M Ci i 1.16E+01 9.85E+00 l 0.00E+00 l 0.00E+00 l l XE-137 1 Ci i 7.15E+01 6.36E+01 1 0.00E+00 1 0.00E+00 l l l XE-138 l Ci l 3.30E+01 ,

2.84E+01 1 0.00E+00 0.00E+00 l l l l l l l l

l Total for Period l Ci l 1.55E+02 l 1.57E+02 l 0.00E+00 l 0.00E+00 l

2. Iodines l l I-131 l Ci i 1.11E-03 l 4.22E-04 l 0.00E+00 1 0.00E+00 l l l I-133 1 Ci I 5.06E-03 l 4.01E-03 l 0.00E+00 l 0.00E+00 l l I-135 l Ci l 3.97E-03 l 6.24E-03 l 0.00E+00 1 0.00E+00 1 l l l l l l l l Total for Period l Ci i 1.01E-02 l 1.07E-02 l 0.00E+00 l 0.00E+00 l

3. Particulates l MN-54 i Ci 1.i3E-07 l 5.40E-08 I 0.00E+00 0.00E+00 l l CO-60 l Ci 4.97E-06 l 2.45E-06 1 0.00E+00 0.00E+00 l l ZN-65 l Ci 8.82E-06 1 1.52E-06 l 0.00E+00 1 0.00E+00 l l CS-137 i Ci l 1.92E-06 l 1.07E-06 1 0.00E+00 1 0.00E+00 l '

l BA-140 Ci l 2.60E-04 2.13E-04 l 0.00E+00 0.00E+00 l l SR-89 Ci i 1.01E-04 9.39E-05 0.00E+00 0.00E+00 l l SR-90 Ci l 3.90E-07 3.39E-07 0.00E+00 0.00E+00 l

!  ! I I I l l l l Total for Period l Ci ) 3.77E-04 l 3.13E-04 l 0.00E+00 0.00E+00 l 1

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Page 6 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1993 Table 1C Gaseous Effluents - Building Vent Releases l l l Continuous Mode l Batch Mode l 1 Nuclides Released i Unit i 3rd Qtr l 4th E!.r i 3rd Qtr l 4th Qtr i

1. Fission Gases l XE-132 i Ci l 0.00E+00 l 5.02E-01 0.00E+00 1 0.00E+00 l  !

l XE-135 I Ci 9.72E+00 l 1.05E+01 0.00E+00 1 0.00E+00 l l XE-135M l Ci 1.58E+01 l 2.98E+00 0.00E+00 1 0.00E+00 l l l l l 1 l l Total for Period l Ci l 2.55E+01 l 1.40E+01 0.00E+00 l 0.00E+00 l

2. Iodines l I-131 l Ci 1.68E-03 1 1.43E-03 l 0.00E+00 l 0.00E+00 l l I-133 l Ci 1.27E-02 1.15E-02 0.00E+00 1 0.00E+00 l l I-135 Ci l 2.19E-02 2.03E-02 0.00E+00 l G.00E+00 l l l 1 l l Total for Period Ci I 3.64E-02 1 3.32E-02 0.00E+00 i U.00E+00 l

3. Particulates l MN-54 i Ci l 2.64E-06 l 0.00E+00 l 0.00E+0) 0.00E+00 l l Co-60 i Ci l 1.49E-04 l 1.32E-04 I 0.00E+06 0.00E+00 l l ZN-65 i Ci  ! 1.08E-03 l 1.20E-03 1 0.00E+00 0.00E+00 l l CS-137 i Ci l 5.06E-05 l 7.01E-05 1 0.00E+00 0.00E+00 l l BA-140 i Ci I 8.96E-05 l 2.44E-05 1 0.00E+00 0.00E+00 l i 1.83E-05 l 0.00E+00 1 0.00E+00 l l SR-89 l Ci 1.48E-05 l SR-90 l Ci 1.68E-07 1.22E-06 l 0.00E+00 1 0.00E+00 l l l l l l l l Total for Period i Ci i 1.39E-03 1.45E-03 l 0.00E+00 1 0.00E+00 l l

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! Table 2A Liquid Effluents - Summation of all Releases i y

I l l Units l 3rd Qtr l 4th Qtr lEst. Totall l l l Error, %- l

! l l j l j A. Fission & Activation products l ] 1. Total Release (not including l l l l l 4

l tritium, gases, alpha) l Ci 0.00E+00 l 0.00E+00 l 0.00E+00 l 1 l 2. Avg-Diluted Concentration l uci/ml 0.00E+00 1 0.00E+00 l B. Tritium l 1. Total Release l Ci l 0.00E+00 l 0.00E+00 1 0.00E+00 l l l 2. Avg Diluted Concentration l uci/ml l 0.00E+00 l 0.00E+00 l 1

j C. Dissolved and Entrained Gases l l 1. Total Release l Ci I 0.00E+00 l 0.00E+00 1 0.00E+00 l

l 2. Avg Diluted Concentration I uci/ml l 0.00E+00 1 0.00E+00 l i

D. Percent Qtrly Tech Spec Reporting Level l 1. Whole Body Dose l  % l 0.00E+00 l 0.00E+00 1.

j l 2. Organ Dose l  % l 0.00E+00 1 0.00E+00 l f

E. Gross Alpha Radioactivity i

l, l 1. Total Release l Ci l 0.00E+00 l 0.00E+00 1 0.00E+00 l 1

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lF. Volume of Waste Released i Liters l 0.00E+00 l 0.00E+00 l 0.00E+00 l 1

e lF. Volume of Dilution Water Used l Liters 1 0.00E+00 1 0.00E+00 1 0.00E+00 l  ;

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i Table 2B Liquid Effluents

, l l l Continuous Mode l Batch Mode l j l Nuclides Released I Unit l 3rd Qtr 1 4th Qtr l 3rd Otr i 4th Qtr l e

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Page 8 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1993 4

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

! l 1. Type of Waste l Units j 6-month (Est. Totall

l l l Period  ! Error, % l 1 l a. Spent revins, filter sludges, l Cu. Meter l 3.10E+01 l l

j. l evaporator bottoms, etc. l Ci l 8.16E+02 l 3.70E+01 l j l b. Dry compressible waste, l Cu. Meter i 9.71E+00 l l i l contaminated equipment, etc. Ci l 8.95E+00 l 3.50E+01 l l l c. Irradiated components, Cu. Meter l 0.00E+00 l l

.; I control rods, etc. I Ci l 0.00E+00 1 0.00E+01 I i I d. Other (describe) l Cu. Meter l 0.00E+00 l l

, l l Ci l 0.00E+00 1 0.00E+01 1 3

l 2. Estimate of major nuclide composition (by type of waste) l I I Type A l Type B l Type C l Type D 1 3

j l Nuclide l percent I percent l percent I percent l 1 1 H-3 1 2.35E-02 l 3.46E-05 l l l j l C-14 l 1.03E-02 l 4.83E-02 l l l 3 l Mn-54 l 9.81E-01 l 8.03E+00 l l l j l Fe-55 l 8.15E+00 l 4.91E+01 l l l

! l Co-58 l 1.34E-01 1 2.68E-01 l l l l Fe-59 l 6.64E-02 1 6.89E-01 l l l l l Co-60 l 5.38E+00 l 1.75E+01 l l l l Ni-63 l 8.27E-02 l 1.44E+00 l l l

I Zn-65 l 8.18E+01 l 2.22E+01 l l l a

l Sr-89 l 9.02E-02 1 3.37E-02 l l l j l Sr-90 l 1.01E-02 1 5.75E-02 l l l l Tc-99 l 5.92E-05 l 9.39E-05 l l l l I-129 I 3.54E-04 l 1.46E-04 l l l 4

l I-131 1 9.17E-03 1 3.32E-02 l l l

! l Cs-134 l 1.60E-02 l 2.71E-02 l l l

. l Cs-137 l 9.17E-01 1 5.35E-01 l l l l l Ce-141 1 1.93E-02 l 3.33E-05 l l l 6 l Pu-238 l 2.86E-04 l 8.44E-06 l l l l Pu-239 l 1.33E-04 l 4.61E-06 l l l l Am-241 1 4.11E-04 1 3.06E-03 l l l l Pu-241 1 1.52E-02 1 6.70E-04 l l l l Cm-242 l 1.38E-03 l 3.95E-03 l l l

] l Cm-243 1 3.67E-04 l 2.96E-03 l l l I Ce-144 1 3.46E-05 l l l l l l l l l l 1

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! EFFLUEi1T AND WASTE DISPOSAL SEMIANNUAL REPORT 4 Period : Jul - Dec 1993 4 Table 3 Solid Waste and Irradiated Fuel Shipments 1

3. Solid waste disposal l l Number of I Mode of l Destination I

l Shipments ' Transportation l l

I 8 1 Truck l Chem-Nuc Inc., Barnwell, SC. l l l l l l j

j B. Irradiated Fuel Shipments i

1. Disposition

, l Number of l Mode of I Destination 1 l Shipments l Transportation l l j None This Period C. Shipping Container and Solidification Method l No. l Volume l Activity l Type of l Container l Solidification l l l M3 l Ci l Waste i Code l Code l

l 93-66 l 5.84E+00 1 8.83E+00 l B l A l N l i

i l 93-69 l 4.84E+00 1 2.02E+02 l A l A l D l l 93-71 l 4.84E+00 l 1.37E+02 l A l A l D l

1 93-72 l 4.84E+00 l 1.77E+02 l A l A l D l l l 93-73 l 4.84E+00 l 1.68E+02 l A l A l D l l 93-74 l 5.83E+00 l 7.41E+01 l A l A l D l i I 93-77 l 5.83E+00 l 5.76E+01 l A l A l D l

_ .l 93-65 I 3.87E+00 l 1.21E-01 l B l L l N l

! l I l l l l I l Container Codes : Solidification Codes :

J L - LSA C - Cement l

! A - Type A U - Urea Formaldehyde "'

i B - Type B D - Dewatering Q - Large Quantity N - Not Applicalble

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Attachment B Off-Site Radiation Dose Assessment for January 1, - December 31, 1993 1

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NORTilERN STATES POWER COMPANY MONTICELLO NUCLEAR GENERATING PLANT Off Site Radiation Dose Assessment for January 1, - December 31,1993 An assessment of radiation dose due to releases from the Monticello Nuclear Generating Plant during 1993 was perfonned in accordance with the Technical Specifications. Computed doses were well bebw the 40 CFR 190 Standards and 10 CFR Part 50, Appendix I Guidelines.

Off-site dose calculation formulas and meteorological data from the Off-site Dose Calculation Manual were used in making this assessment. Source temis were obtained from the two Semi-Annual Effluent Release Reports for 1993.

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 percentage of Appendix I Guidelines.

Off Site Doses From Liquid Releases Doses from Liquid releases are listed in Table 1. ,

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Doses to Individuals Due to Activities Inside the Site Iloundary  !

Occasionally 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.

Doses to Most Exposed 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 l

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. MNGP started a hydrogen water chemistry (HWC) program in February 1989. Prior to the installation of HWC, a study was conducted to determine the direct and skyshine radiation contribution from HWC.

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I- Doses to 51ost Exposed Niember of the General Public from Reactor Releases and Other j Uranium Fuel Cvele 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. However, a review of TLD results from 1987 through 1992 revealed no noticeable increase in direct and skyshine radiation as a result of the HWC program installed in early 1989.

A calculation of the total annual dose to this residence from all existing pathways of radioactive effluents was perfonned by running GASPAR computer codes. Adding 4 mrem / year to this calculation results in a maximum whole body dose of 4.03 mrem in 1993.

Therefore, the 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 mrem to the whole body,75 nuem to the thyroid, and 25 mrem to any other organ.

Radiological Environmental N1onitorine Program Sampline Deviations There were no milk or vegetable sampling deviations during this reporting period.

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9 Table 1 Off-Site Radiation Dose Assessment - Monticello PERIOD: January 1, through December 31,1993

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1 RELEASES 4 ;yesrs 1 Max. Site Boundary Gamma Air Dose (mrad) 0.24 10 l Max. Site Boundary Beta Air Dose (mrad) 0.48 20 Max. Off-site Dose to Any Organ (mrem) 0.06 15 l

EPA Field Station l

(mrem,40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> / week)

Whole Body 0.04 5

! Organ (skin) 0.05 15 Oguki RelenesT Max. Off-Site Dose Whole Body (mrem) 0.00 3 Max. Off-Site Dose Organ, Total (mrem) 0.00 10 1 Page 3 of 4 I 1

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Table 2 l Off-Site Radiation Dose Assessment - Monticello )

Supplemental Information PERIOD: January 1, through December 31,1993 .

1 Gaseous Releases ,

Max. Site Boundary Dose Location (from building vents)

Sector SSE Distance (miles) 0.43 EPA Field Station Sector SE Distance (miles) 0.26 (Stack) l 0.36 (Vent)

Maximum Off-site Dose Location Sector SSW Distance 0.70 Pathways Ground,  ;

Inhalation, t Vegetable Age Group Child Organ Thyroid Liquid Releases Max. Off-Site Dose Location Downstream Pathways Drinking Drinking Water W ater Fish Age Group Infant Adult l Organ W. Body GI-LLI Dilution Factor 7.1 7.1 (drinking water) j Page 4 of 4 )'

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