ML20012G461

Effluent & Waste Disposal Semiannual Rept for Jul-Dec 1992. W/930226 Ltr

ML20012G461
Person / Time
Site:	Monticello
Issue date:	12/31/1992
From:	Fey F NORTHERN STATES POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9303020516
Download: ML20012G461 (14)

Text

r Northem States Power Company i

414 Nicollet Mall j IAnneapolis, Minnesota 55401-1927 Telephone (612) 330-5500 ,

February 26,1993 Monticello Technical Specification TS6.7 4A U.S. Nuclear Regulatory Commission Document Control Desk j Washington, D.C. 20555 Monticello Nuclear Generating Plant Docket No. 50-623 License No. DPR-22 i Effluent and Waste Disposal Semiannual Report for July throuch December 1992 i

e in accordance with the Monticello Technical Specifications, Appendix A to Operating License DPR-22, we are . submitting the Effluent and Waste Disposal Semiannual Report covering the last half year of 1992.

The Offsite Dose Calculation Manual (ODCM) and Process Control Program (PCP) Manual are I not attached since they remained unchanged during the reporting period.

t 0\ l Fred L. Fey, Jr., Manager Nuclear Radiological Services FLF:saw ,

Attachment 020113 R

9303020516 921231 PDR ADDCK 05000263

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NORTHERN STATES POWER COMPIEY MONTICELIO NUCLEAR GENERATING PLANT  ;

License No. DPR-22 1

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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT l Period : Jul - Dec 1992 i

Supplemental Information .

1. Regulatory Limits - Quarterly levels requiring reporting to ,

Nuclear Regulatory Commission l

. 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 i

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 I

3. Average Energy (Not Applicable)

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. . Page. 2 i EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT j Period : Jul - Dec 1992  !

Supplemental Information (continued)  ;

4. Measurements and Approximations of Total Radioactivty

's 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 . ,

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

I C. Particulates in Gaseous Effluent : ,

Continuous monitoring with particulate filters in Reactor Building Vent and Plant Stack exhaust streams with weekly analysis. [

i 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

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

5. Batch Releases A. Liquid :

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 3atch Release NA min

, 6. Average River Flow During Release NA cf/sec --

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B. Gaseous :

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 ,

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-EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Pe'riod : Jul - Dec 1992 Supplemental Information (continued)

6. Abnormal Releases A. Liquid :

1. Number of Releases 0

2. Total Activity Released NA Ci B. Gaseous :

1. Number of Releases 1

2. Total Activity Released 0.5 Ci

. . _ .- ... . - . . - - . -_ .. . .= . - - .-- -.

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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT l Period : Jul - Dec 1992 i Table 1A Gaseous Effluents - Summation of all Releases  !

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l Units l 3rd Qtr i 4th Qtr lEst. Totall  !

l l I I I i Error, % l* l 1

A. Fission & Activation gases i

l 3.19E+02 1 2.80E+02 l 2.00E+01 1 Ci  !

l 1. Total Release i l 2. Average Release Rate- l uci/sec l 4.01E+01 1 3.52E+01 1 f l 3. Percent Tech Spec Qtrly l l l l ,

l Reporting Level l l 1 l l

l Gamma Radiation l  % l 3.80E-01 1 2.93E-01 1 -

l Beta Radiation i  % i 9.35E-02 l 7.71E-02 l >

l B. Iodines i

'l 1. Total 1-131 Release l Ci i 1.00E-02 l 1.42E-03 l 1.00E+01 l l

2. Averaae I-131 Release Rate i uci/sec j 1.26E-03 1 1.78E-04 l l

l 3: C. Particulates l 1

l 1. Total Particulates l Ci l 1.88E-03 1 7.37E-04 1 3.00E+01 l l l 2. Average Release Rate I uci/sec l 2.37E-04 i 9.28E-05 l i l 3. Gross Alpha Radioactivity l Ci i 5.70E-06 i 4.21E-06 l l D. Tritium k i

1 1. Total Release l Ci i 3.27E+01 l 2.28E+01 1 1.00E+01 l  ?

l 2. Average Release Rate I uci/sec l 4.11E+00 1 2.86E+00 l E. Percent Qtrly Tech Spec Reporting Levels i

l 1. lodines, Particulates, i 1 l l j l and Tritium (  % i 2.96E+00 1 3.57E-01 l j I

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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1992

. e Table 1B Gaseous Effluents - Elevated Releases j 1

1 l l Continuous Mode j Batch Mode l (

l Nuclides Released i Unit i 3rd Qtr 1 4th Qtr l 3rd Qtr 1 4th Qtr ] l l

1. Fission Gases i KR-85M l Ci I 6.01E-02 1 0.00E+00 1 0.00E+00 1 0.00E+00 l I l KR-87 I Ci l 2.77E+00 1 2.10E+00 l 0.00E+00 1 0.00E+00 l j KR-88 i Ci  ! 1.54E+00 l-9.89E-01 1 0.00E+00 1 0.00E+00 l l KR-89 l Ci I 8.22E+00 l 1.48E+01 1 0.00E+00 l 0.00E+00 l 3 l XE-133 l Ci- l 7.72E+01 1 6.18E+01 1 0.00E+00 1 0.00E+00 l l l

l XE-133M I Ci l 1.83E+00 l 9.04E-01 1 0.00E+00 1 0.00E+00 l l

, l XE-135 i Ci l 8.29E+00 1 9.15E+00 1 0.00E+00 1 0.00E+00 l  :

l XE-135M i Ci i 1.90E+01 1 1.49E+01 1 0.00E+00 1 0.00E+00 l 4

l XE-137 i Ci i 1.08E+02 I 9.85E+01 1 0.00E+00 1 0.00E+00 l l XE-138 i Ci I 5.06E+01 1 4.52E+01 1 0.00E+00 1 0.00E+00 l I i l i l I  !

l l Total for Period i Ci l 2.78E+02 1 2.48E+02 1 0.00E+00 1 0.00E+00 l l i

I i 2. Iodines

) 1-131- I Ci I 6.40E-04 1 3.86E-04 1 0.00E+00 1 0.00E+00 [ j l I-133 I Ci l 3.98E-03 l 2.16E-03 1 0.00E+00 1 0.00E+00 l- l J I-135 i Ci I 6.86E-03 1-3.28E-03 l 0.00E+00 1 0.00E+00 l  ;

1 I l  ! 1 1 I 1

l Total for Period l Ci l 1.15E-02 1 5.82E-03 1 0.00E+00 1 0.00E+00 1  :

. 3. Particulates {

l CO-60 1 Ci I 1.20E-06 I 2.34E-07 1 0.00E+00 1 0.00E+00 1  !

l ZN-65 I Ci i 2.79E-07 1 3.64E-07 I 0.00E+00 J-0.00E+00 l l CS-137 l Ci I 7.44E-06 l 3.67E-06 1 0.00E+00 1 0.00E+00 1  !

l BA-140 i Ci I 3.99E-04 1 3.94E-04 1 0.00E+00 1 0.00Et00 l I l SR-89 i Ci l 1.89E-04 1 1.65E-04 1 0.00E+00 1 0.00E+00 l l l SR-90 l Ci I 5.23E-07 6.98E-07 1 0.00E+00 1 0.00E+00 l I

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l Total for Period l Ci I 5.98E-04 5.64E-04 1 0.00E+00 l 0.00E+00 l l

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I EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT- 'l 2

Period : Jul - Dec 1992 I Table 1C Gaseous Effluents - Building Vent Releases l i

i  ! i Continuous Mode l Batch Mode l l l Nuclides Released i Unit i 3rd Otr l 4th Qtr l 3rd Qtr l 4th Qtr i <

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1. Fission Gases  !

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I1 XE-133 i Ci i 1.38E+00 1 1.67E+00 1 0.00E+00 1 0.00E+00 l  !

l XE-135 i Ci l 1.34E+01 l 1.17E+01 l 0.00E+00 1 0.00E+00 l ,

l XE-135M Ci l 2.66E+01 l 1.79E+01 1 0.00E+00 1 0.00E+00 l 4

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I l Total for Period l Ci l 4.14E+01 1 3.12E+01 1 0.00E+00 l 0.00E+00 l l t  :

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2. Iodines j l I-131 1 Ci I 9.36E-03 1 1.03E-03 1 0.00E+00 1 0.00E+00 l j j l I-133 i Ci I 8.16E-02 1 7.23E-03 I O.00E+00 1 0.00E+00 l i 1.37E-01 l 8.15E-03 l 0.01E+00 1 0.00E+00 l

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l I-135 i Ci l l 1 1 I I I l ,

l Total for Period l Ci l 2.28E-01 1 1.64E-02 1 0.00E+00 1 0.00E+00 l  !

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3. Particulates ,

i l CR-51 1 Ci 1 2.51E-05 l 0.00E+00 1 0.00E+00 1 0.00E+00 l  !

l CO-60 1 Ci i 1.17E-04 l 7.11E-05 l 0.00E+00 1 0.00E+00 l i l ZN-65 l Ci l 3.75E-04 l 1.54E-05 l 0.00E+00 1 0.00E+00 l l l CS-137 l Ci l 7.55E-05 1 3.79E-05 l 0.00E+00 1 0.00E+00 1 i I 5.96E-04 l 3.34E-05 1 0.00E+00 1 0.00E+00 l l BA-140 i Ci ,

i CE-141  ! Ci l 6.06E-05 1 0.00E+00 l 0.00E+00 1 0.00E+00 1  !

l SR-89 i Ci l 3.54E-05 i 1.56E-05 1 0.00E+00 1 0.00E+00 l c l l l I i l i  ;

1 Total for Period l Ci i 1.28E-03 l 1.73E-04 1 0.00E+00 l 0.00E+00 l  ?

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Table 2A Liquid Effluents - Summation of all Releases l l Units 1 3rd Qtr j 4th Qtr lEst. Totall .

1 I l l l-Error, % -l l l

A. Fission & Activation products  ;

i 1. Total Release (not including l l j l l  ;

l tritium, gases, alpha) l Ci l 0.00E+00 l 0.00E+00 1 0.00E+00 l l 1 2. Avg Diluted Concentration l uci/ml l 0.00E+00 1 0.00E+00 l 5 B. Tritium l l 1. Total Release l Ci l 0.00E+00 1 0.00E+00 l 0.00E+00 l l 1 2. Avg Diluted Concentration 1 uci/ml l 0.00E+00 l 0.00E+00 l l C. Dissolved and Entrained Gases l 1. Total Release l Ci l 0.00E+00 l 0.00E+00 1 0.00E+00 l  ;

I 2. Avc Diluted Concentration l uci/ml l 0.00E+00 l 0.00E+00 l l D. Percent Qtrly Tech Spec Reporting Level 'l t

l 1. Whole Body Dose I t l 0.00E+00 ! 0.00E+00 l l 2. Orcan Dose 1 4 1 0.00E+00 l 0.00E+00 l ,

i E. Gross Alpha Radioactivity l

l 1. Total Release i Ci l 0.00E+00 l 0.00E+00 1 0.00E+00 l  !

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

l Table 2B Liquid Effluents l  !  ! Continuous Mode l Batch Mode I r l Nuclides Released 1 Unit ! 3rd Otr ! 4th Otr  ! 3rd Otr l 4th Otr l l i

None Released This Period l i

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. Page 8 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1992 Table 3 Solid Waste and Irradiated Fuel Shipments A. Solid Waste Shipped Offcite for Burial or Disposal (not irradiated fuel) l 1. Type of Waste i Units l 6-month (Est. Totall l l l Period l Error, % 1 1 a. Spent resins, filter sludges, i Cu. Meter i 1.75E+01 l l l evaporator bottoms, etc. I Ci i 1.15E+02 i 3.70E+01 l l b. Dry compressible waste, l Cu. Meter i 1.87E+01 l l l contaminated eauipment, etc. I Ci i 1.83E-01 ! 3.50E+01 1 I c. Irradiated components, i Cu. Meter 1 0.00E+00 l l l control rods, etc. l Ci l 0.00E+00 1 0.00E+01 l l d. Other (describe) l Cu. Meter 1 0.00E+00 1 I l l Ci j 0.00E+00 1 0.00E+01 l j 2. Estimate of major nuclide composition (by type of waste) l l l Type A l Type B l Type C l Type D l l Nuclide i percent I percent l percent l percent l l H-3 1 3.40E-02 1 4.13E-04 l l l l C-14 1 5.80E-02 1 4.18E-04 l l l l Cr-51 l 4.06E-01 i l l l l Mn-54 l 3.45E+00 1 1.03E+01 l l l l Fe-55 l 1.18E+01 1 2.82E+01 l l l l Co-58 1 4.90E-01 1 1.20E+00 l l l l Fe-59 l 1.27E-01 l l l l 1 Co-60 l 2.94E+01 l 5,31E+01 l l l l Ni-63 l 3.05E-01 1 1.21E-01 l l l J Zn-65 1 4.76E+01 l 6.59E+00 l l l 1 3.16E-01 l 2.20E-02 l i Sr-89 l l l Sr-90 1 1.43E-02 l 1.84E-01 I i l l Tc-99 1 1.73E-05 l 4.35E-05 l l l 1 I-129 l 1.15E-05 l 2.77E-05 l l l l I-131 1 3.81E-01 l l l l l l Cs-134 l 1.55E-01 l l l l l

l Cs-137 l 5.04E+00 l 3.80E-01 l l l l Ba-140 1 7.03E-02 l l l l l La-140 1 2.07E-01 l l l 1 l Ce-141 I 8.39E-02 l 5.33E-03 l l l l Pu-238 1 5.87E-04 1 3.21E-04 l l l l Pu-239 1 8.60E-05 l 1.76E-04 l l l l Am-241 1 4.81E-03 l 1.40E-04 l l l l Pu-241 l 2.51E-02 l 2. 69E -02 l l l l Cm-242 l 4.91E-04 j 4 . 51 F.- 0 4 l l l

[ Cm-243 l 2.53E-04 1 7.29E-05 1  ! l l Ce-144 l 4.13E-04 l l , l l 1 l 1 I I i

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i EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1992 ,

I Table 3 Solid Waste and Irradiated Fuel Shipments

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3. Solid waste disposal j l Number of 1 Mode of i Destination i i l Shipments 1 Transportation l l l l 1 1 Truck l US Ecology, Richland, WA. l  :

l 3 i Railway l US Ecology, Richland, WA. l 3 l 5 l Truck i US Ecology, Beatty, NV. [

] l 1 l l 4 -B. Irradiated Fuel Shipments l

1. Disposition

_l Number of i Mode of

• Destination l _

l Shipments i Transportation , l l i

None This Period i

i i C. Shipping Container and Solidification Method l t

l l No. I Volume l Activity l Type of I Container l Soliditication l l 1 M3 i Ci I Waste I Code l Code l  !

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1 92-25 1 5.83E+00 1 5.76E+01 l A i A i D l  ;

l 92-27 l 5.83E+00 l 3.32E+01 1 A l A l D I j

. I 92-33 1 5.83E+00 l 2.46E+01 l A i A- l D l l

) l'92-39 1 1.56E+01 l 8.93E-02 l B i L l N l l l 9231a I 8.86E-01 1 1.16E-02 i B l L j N l .)

l 9231b 1 1.18E+00 l 1.38E-02 l B i L -l N l l 9231c l 5.92E-01 1 5.44E-02 i B l L l N l l 9231d i 2.35E-01 l 7.94E-03 l B 1 L l N N

I l 9231e 1 2.52E-01 1 6.04E-03 l B l L l l ,

1 I i 1  ! 1 I l Container Codes : Solidification Codes :

L - LSA C - Cement {

i A - Type A U - Urea Formaldehyde

B - Type B D - Dewatering  !

Q - Large Quantity N - Not Applicalble 1

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NORTHERN STATES POWER COMPANY MONTICELLO NUCLEAR GENERATING PLANT ,

OFF-SITE RADIATION DOSE ASSESSMENT FOR January 1- December 31, 1992 An assessment of radiation dose due to release from the Monticello i Nuclear Generating Plant during 1991 was performed in accordance l with the Technical Specifications. Computed doses were well below the 40 CFR Part 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 terms were obtained from the two Effluent and Waste Disposal Semiannual Reports prepared for NRC review during the year of 1992.

Off-site Doses from Gdseous Release 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 Liauid Release  !

There were no liquid releases made from the Monticello Plant during the 1992 calendar year.  ;

Doses to Individuals Due to Activities Inside che Site Boundary 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  ;

Figure 3.8.2 of 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 for inhalation pathway (no  ;

other pathway exists). Doses at this location were reported in i Table 1.  ;

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Doses to Most Exposed Member of the General Public from Reactor Releases and Other Uranium Fuel Cycle Bources 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 effluent releases is from direct radiation of the reactor and the steam turbines. MNGP started a hydrogen water chemistry (HWC) program in February 1989. i Prior to the installation of HWC, a study was conducted to determine the direct and skyshine radiation contribution from HWC.

This study determined the maximum exposed member of the public from direct and skyshine radiation to be a residence located 0.6 mile from the reactor at the SW sector. Using conservative assumption, calculations indicated a maximum annual dose of 4 mrem to this residence. However, a review of TLD results from 1987, 1988, 1989, 1990, and 1991 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 were performed by running GASPAR computer codes. Adding the 4 mrem / year to this !

calculation results in a maximum whole body dose of 4.144 mrem / year.

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 Part 190 standards of 25 mrem to the whole body, 75 mrem to the thyroid, and 25 mrem to any other organ.

Raditaion Evironmental Monitoring Program sampline Deviations There were no rilk or vegetable sampling deviations during this ,

reporting period.  !

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i s 6 THM 1 I OFF-SITE RADIATION' DOSE ASSESSMENT - MONTICELLO  !

PERIODI JANUARY 1 throuch DECEMBER 31. 1992-10 CFR Part 50 Appendix I l Guidelines per unit per year-  :

Gaseous Releases l

Maximum Site Boundary l Gamma Air Dose (mrad) 0.133 10  ;

i Maximum Site Boundary '

Beta Air Dose (mrad) 0.0832 20 Maximum Off-site Dose to Any organ (mrem)* i Total 0.564 15  ;

i EPA Field Station 3 (mrem, 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> / week) j Whole Body 0.092 5  !

Organ '

0.230 15 Liquid Releases Maximum Off-site Dose Whole Body (mrem) 0.0 3 i

, Maximum Off-site Dose _!

Organ, Total 0.0 10 j

• Long-lived Particulates, I-131, and H-3

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4 TABLE 2 OFF-SITE RADIATION DOSE ASSESSMENT - MONTICELLO )

SUPPLEMENTAL INFORMATION PERIODr JANUARY 1 throuch DECEMBER 31, 1992 i'

Gaseous Releases Maximum Site Boundary [

Dose Location i (from building vents) j Sector NNW  !

Distance (miles) 0.4 i

EPA Field Station (,

Sector ESE  !

l Distance (miles) 0.3  !

Maximum Off-site Dose Location  ;

Sector SSE l Distance (miles) 1.1  !

Pathways Gamma Air, j Plume,  !

Ground, Inhalation, .

Vegetable -)

Age _ Group Child '

Organ Thyroid 3 Licuid Releases f l

Maximum Off-site Dose  !

Location Downstream j' 1 .

Pathways Drinking Water Drinking Water Fish ,

Age Group Infant Adult l Organ Whole Body GI-LLI 2

Dilution Factor 7.1 7.1  !

(drinking water) '

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