ML20207F703

Effluent & Waste Disposal Semi-Annual Rept for 980701-981231 for Monticello

ML20207F703
Person / Time
Site:	Monticello
Issue date:	12/31/1998
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML20207F696	List: ML20207F690 ML20207F703 ML20207F715 ML20207F725
References
NUDOCS 9903110310
Download: ML20207F703 (10)

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I Attachment A 1

i Effluent and Waste Disposal Semi-Annual Report for July - December,1998 i

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9903110310 990223 9 PDR ADOCK 05000263--

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NORTHERN STATES POWER COMPANY NONTICELLO NUCLEAR GENERATING PLANT i

License No. DPR-22 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT I

Period : Jul - Dec 1998 i

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l Supplemental Information i

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1. Regulatory Limits - Quarterly levels requiring reporting to

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l Nuclear Regulatory Commission l

L A.,

Noble Gases :

5 mrad / quarter gamma radiation j

10 mrad / quarter beta radiation j

B. Long Lived Iodines, Particulates, and Tritium :

7.5 mrem / quarter dose to any organ l

C. Liquid Effluents :

1.5 arem/ 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) i Il' i

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l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT l

Period : Jul - Dec 1998 i

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l Supplemental Information (continued) f l

4. Measurements and Approximations of Total Radioactivty

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A. Noble Gases :

l Continuous gross activity monitors in Reactor Building Vent'and Plant Stack exhaust streams.

Weekly isotopic analysis of exhaust streams.

I B. Iodines in Gaseous Effluent :

Continuous monitoring with charcoal cartridges in Reactor Building l

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.

l D. Tritium in Gaseous Effluent :

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Weekly. grab samples from Reactor Building Vent and Plant Stack i

exhaust streams.

l E. Liquid Effluents :

Tank sample analyzed prior to each planned release and continuous i

monitoring of gross activity during planned release.

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i 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 2

2. Total Time Period for Batch Releases 1166.0 min

3. Maximum Time Period for a Batch Release 807.0 min

4. Average Time-Period for a Batch Release 583.0 min

5. Minimum Time Period for a Batch Release 359.0 min

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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL-REPORT Period : Jul - Dec 1998 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

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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1998

' Table 1A Gaseous Effluents - Summation of all Releases l

l Units 3rd Qtr l 4th Qtr Est. Totall

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Error. % l A. Fission & Activation gases

1. Total Release l

Ci

! 6.33E+01 1 6.54E+01 l 2.00E+01 l 2.

Averaae Release Rate I uci/sec l 7.96E+00 1 8.23E+00 l

3. Percent Tech Spec Qtrly l

Reporting Level l

l Gamma Radiation l

. 6.13E-02 6.68E-02 l l

Beta Radiation i

I 3.05E-02 2.55E-02 l B. Iodines l

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Total I-131 Release I

Ci l 1.86E-03 l 2.47E-03 1 1.00E+01 l l

2.

Averaae I-131 Release Rate I uci/sec I 2.34E-04 1 3.11E-04 l C. Particulates l

1. Total Particulates l

Ci l 6.61E-04 1 4.55E-04 1 3.00E+01 l l

2.

Average Release Rate i uci/sec l 8.32E-05 I 5.73E-05 l l

3.

Gross AlDha Radioactivity i

Ci l 6.55E-06 1 4.12E-07 l D. Tritium

1. Total Release I

Ci I 3.38E+00 1 3.61E+00 1 1.00E+01 l 2.

Averaae Release Rate I uci/sec I 4.26E-01 l 4.54E-01 l E. Percent Qtrly Tech Spec Reporting Levels l

1. Iodines, Particulates, l

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and Tritium 1 1.39E-01 2.88E-01 l l

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f EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1998 l

Table 1B Gaseous Effluents - Elevated Releases l

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Continuous Mode l

Batch Mode l

l l Nuclides Released i Unit 3rd Otr 1 4th Otr i 3rd Otr i 4th Otr l

1. Fission Gases

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KR-85M l

Ci I 7.34E-02 1.5.01E-01 1 0.00E+00 1 0.00E+00 i

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KR-87 i

Ci I 4.43E-01 1 7.35E-01 1 0.00E+00 l 0.00E+00 l KR-88 I

Ci 1 1.66E-01 l 9.50E-01 1 0.00E+00 1 0.00E+00 KR-89 i

Ci 1 0.00E+00 1 7.81E-01 1 0.00E+00 1 0.00E+00 XE-133 I

Ci i 1.43E+01 1 1.52E+01 1 0.00E+00 1 0.00E+00 l

l XE-133M l

Ci I 6.57E-02 1 1.06E-01 1 0.00E+00 1 0.00E+00 l

XE-135 l

Ci I 6.17E+00 1 7.14E+00 1 0.00E+00 1 0.00E+00 l

XE-135M 1

Ci I 4.33E+00 1 4.08E+00 1 0.00E+00 1 0.00E+00 H l

XE-137 l

Ci l 1.83E+01 1 1.85E+01 1 0.00E+00 1 0.00E+00 H l

XE-138 i

Ci l 1.07E+01 1 9.78E+00 1 0.00E+00 1 0.00E+00 H l

AR-41 l

Ci I 0.00E+00 I 8.69E-03 1 0.00E+00 1 0.00E+00 H

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l Total for Period i Ci I 5.45E+01 1 5.78E+01 1 0.00E+00 1 0.00E+00

2. Iodines l

I-131 l

Ci i 1.20E-03 1 4.45E-04 1 0.00E+00 1 0.00E+00 l I-133 I

Ci I 4.76E-03 I 3.34E-03 1 0.00E+00 1 0.00E+00 l I-135 l

Ci I 6.63E-03 I 5.88E-03 1 0.00E+00 1 0.00E+00 l l

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Total for Period l Ci i 1.26E-02 1 9.67E-03 1 0.00E+00 1 0.00E+00 l

3. Particulates MN-54 i

Ci i 1.65E-07 I 0.00E+00 1 0.00E+00 1 0.00E+00 l CO-60 I

Ci i 1.87E-06 I 8.22E-07 1 0.00E+00 1 0.00E+00 l ZN-65 l

Ci I 3.27E-07 1 0.00E+00 1 0.00E+00 1 0.00E+00 l CS-137 I

Ci l 1.21E-06 1 6.58E-07 1 0.00E+00 l 0.00E+00 BA-140 1

Ci I 5.08E-05 1 4.81E-05 1 0.00E+00 1 0.00E+00 SR-89 I

Ci I 3.10E-05 1 3.83E-05 l 0.00E+00 1 0.00E+00 SR-90 l

Ci i 1.17E-07 l 9.55E-08 I 0.00E+00 1 0.00E+00 i I

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Total for Period l Ci I 8.55E-05 l 8.80E-05 1 0.00E+00 1 0.00E+00 l

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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1998 Ta'ble 1C Gaseous Effluents - Building Vent Releases l

Continuous Mode l

Batch Mode l

Nuclides Released Unit i 3rd Otr 1 4th Otr i 3rd Otr 1 4th Otr l

1. Fission Gases XE-135 I

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! 8.11E+00 1 5.25E+00 1 0.00E+00 1 0.00E+00 l

XE-135M I

Ci I 6.39E-01 1 2.39E+00 1 0.00E+00 1 0.00E+00 I

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Total for Period i Ci I 8.75E+00 1 7.64E+00 1 0.00E+00 l 0.00E+00 2.

Iodines l

I-131 l

Ci I 6.61E-04 l 2.02E-03 1 0.00E+00 1 0.00E+00 l

I-133 i

Ci I 7.55E-03 1 2.11E-02 1 0.00E+00 1 0.00E+00 l

I-135 i

Ci i 1.26E-02 1 3.12E-02 1 0.00E+00 l 0.00E+00 l

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Total for Period l Ci 1 2.08E-02 1 5.44E-02 1 0.00E+00 1 0.00E+00 l l

3. Particulates l

MN-54 i

Ci l 1.15E-05 l 7.17E-06 1 0.00E+00 1 0.00E+00 l

CO-58 i

Ci l 1.42E-06 1 0.00E+00 1 0.00E+00 l 0.00E+00 t

CO-60 i

Ci l 1.54E-04 I 8.02E-05 l 1.21E-06 1 0.00E+00_

ZN-65 l

Ci 1 2.16E-04 I 6.79E-05 1 0.00E+00 1 0.00E+00 l

CS-137 I

Ci l 1.52E-04 1 3.34E-05 l 0.00E+00 1 0.00E+00

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BA-140 1

Ci I 3.79E-05 l 1.71E-04 1 0.00E+00 1 0.00E+00 CE-141 l

Ci 1 0.00E+00 l 2.64E-06 I 0.00E+00 1 0.00E+00 1

j SR-89 I

Ci l 2.77E-06 1 5.23E-06 1 0.00E+00 1 0.00E+00 l

l SR-90 l

Ci 1 0.00E+00 1 7.10E-08 1 0.00E+00 1 0.00E+00 3

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Total for Period l Ci I 5.75E-04 1 3.67E-04 1 1.21E-06 1 0.00E+00 l l

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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT i

Period : Jul - Dec 1998 Table 2A Liquid Effluents - Summation of all Releases l

Units 3rd Qtr l 4th Qtr Est. Totall l-1 Error. % l A. Fission & Activation products i

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1. Total Release (not including l l

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tritium, cases, aloha) l Ci 0.00E+00 l 0.00E+00 0.00E+00 l l

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Ava Diluted Concentration I uci/ml 1 0.00E+00 1 0.00E+00 l B. Tritium l

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Total Release i

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

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Ava Diluted Concentration I uci/ml 1 0.00E+00 1 0.00E+00 l C. Dissolved and Entrained Gases

1. Total Release I

Ci 1 0.00E+00 1 0.00E+00 1 0.00E+00 l 2.

Ava Diluted Concentration I uci/ml 1 0.00E+00 1 0.00E+00 l D. Percent-Qtrly Tech. Spec-Reporting Level l

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Whole-Body Dose' I

1 0.00E+00 1 0.00E+00 l

2.

Oraan Dose I

1 0.00E+00 1 0.00E+00 E. Gross Alpha-Radioactivity l

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Total Release l

Ci l 0.00E+00 1 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 I Liters 1 0.00E+00 1 0.00E+00 1 0.00E+00 l Table 2B Liquid Effluents Continuous Mode Batch Mode Nuclides Released Unit 3rd Otr 1 4th Otr 3rd Otr I 4th Otr None Released This Period i

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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1998 Table 3 Solid Waste and Irradiated Fuel Shipments A. Solid Waste Shipped offsite for Burial or Disposal (not irradiated fuel) l

1. Type of Waste l

Units l

6-month lEst. Total I

I Period i Error. %

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

Ci 0.00E+00 0.00E+00

b. Dry compressible waste, l Cu. Meter l 8.05E+00 l contaminated eauipment, etc.

I Ci 1 2.04E-01 1 3.50E+01 i

c. Irradiated components, l Cu. Meter 0.00E+00 l

control rods, etc.

1 Ci 0.00E+00 0.00E+00

d. Other (describe)

Cu. Meter 0.00E+00 Ci 0.00E+00 0.00E+00

2. Estimate of major nuclide composition (by type of waste) l Type A l

Type B l

Type C l

Type D l

Nuclide i

Dercent l Dercent I percent l Dercent l

H-3 2.20E-01 l l

l C-14 8.75E-02 l l

l Mn-54 l

2.84E+00 l l

Fe-55 4.14E+01 l

l Fe-59 1.47E-05 l

Co-60 2.07E+01 l

l Ni-63 3.36E-01 l

Zn-65 7.57E+00 l

Sr-90 1

2.90E-02 l

Cs-137 l

1.06E+00 Eu-154 l

4.42E-05 Pu-238 l

4.81E-03 Pu-239 3.47E-03 i

Am-241 8.55E-03 i Pu-241 1.28E-01 l Cm-242 1.11E-03 Cm-243 2.81E-03 l

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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1998 Table 3 Solid Waste and Irradiated Fuel Shipments

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

Shipments l Transportation

_l 7

Truck Chem-Nuc Inc., Barnwell, SC.

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Irradiated Fuel Shipments

1. Disposition l Number of l Mode of Destination l

l Shioments i Transportation l

None This Period C. Shipping Container and Solidification Method No.

Volume l Activity Type of Container l Solidification M3 1

Ci Waste Code l

Code 9812D l 2.50E-02 1.40E-03 l B

1 A

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9812E 3.03E-02 3.77E-03 B

A N

9812F 1.76E-01 5.86E-03 B

A N

9812G 6.34E-01 4.16E-02 B

A N

l 9731b 2.15E+00 3.00E-03 B

L N

9812h 1.30E+00 1.32E-02 B

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N 9836a 1.30E+00 5.69E-02 B

A N

9836b 4.28E-01 7.48E-02 B

A N

9836c 5.10E-02 1.77E-03 B

A N

9836d l 1.02E+00 4.59E-02 B

A N

9836e 2.55E-01 1.18E-02 B

A N

9723b 6.80E-01 3.78E-03 B

L N

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Container Codes :

Solidification Codes :

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