ML20238E824

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Effluent & Waste Disposal Semi-Annual Rept for Jan-June 1998
ML20238E824
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 06/30/1998
From:
NORTHERN STATES POWER CO.
To:
Shared Package
ML20238E821 List:
References
NUDOCS 9809020220
Download: ML20238E824 (10)
v • d • e


Text

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Attachment A Effluent and Waste Disposal Semi-Annual Report for January - June 1998 (The attached Report contains 9 pages.)

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NORTHERN STATES POWER COMPANY MONTICELLO NUCLEAR GENERATING PLANT License No. DPR-22 l

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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jan - Jun 1998 l

Supplemental Information

, 1.-Regulatory Limits - Quarterly levels requiring reporting to

Nuclear Regulatory Commission L A. Noble Gases

5 mrad / quarte r gamma radiation 10 mrad / quarter beta radiation B.'Long Lived Iodines, Particulate, 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, Particulate, and Tritium :

i 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) l

Page 2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jan - Jun 1998 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. 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. Particulate 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 :

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

5. B:tch 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 i B. Gaseous :
1. Number of Batch Releases 2 2.. Total Time Period for Batch Releases 1722.0 min
3. Maximum Time Period for a Batch Release 1432.0 min
4. Average Time Period for a Batch Release 861.0 min
5. Minimum Time Period for a Batch Release 290.0 min

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' EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jan - Jun 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 l

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Page 4 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jan - Jun 1998 Table 1A Gaseous Effluents - Summation of all Releases l Units l 1st Qtr l 2nd Qtr lEst. Total l I I I I Error. % l A. Fission & Activation gases l 1. Total Release l Ci l 7.84E+01 1 3.44E+01 1 2.00E+01 l j

2. Averaae Release Rate I uci/sec 1 1.01E+01 1 4.37E+00 , j
3. Percent Tech Spec Qtrly Reporting Level Gamma Radiation ,  % l 7.82E-02 2.87E-02 l Beta Radiation  % l 2.42E-02 1.26E-02 l B.. Iodines l 1. Total I-131 Release I Ci I 4.71E-03 1 5.65E-04 l 1.00E+01 l l 2. Averace I-131 Release Rate I uci/sec l 6.06E-04 1 7.18E-05 l C. Particulate
1. Total Particulate l Ci I 7.28E-04 1 3.28E-04 1 3.00E+QL_l
2. Average Release Rate I uci/sec i 9.36E-05 1 4.17E-05
3. Gross Aloha Radioactivity l Ci I 7.36E-07 1 4.84E-07 D. Tritium l 1. Total Release I Ci I 4.88E+00 1 2.37E+00 1 1.00E+01 l l- 2. Averaae Release Rate I uci/sec l 6.27E-01 1 3.01E-01 l E. Percent Qtrly Tech Spec Reporting Levels
1. Iodines, Particulate, l l l and Tritium I  % 1 5.46E-01 4.24E-02 l l 1 l

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Page 5 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT
Period
Jan - Jun 1998 Table 1B Gaseous Effluents - Elevated Releares l l Continuous Mode l Batch Mode [
Nuclides Released i Unit I ist Otr 1 2nd Otr I 1st Otr 1 2nd Otr l
1. Fission Gases l KR-87 I Ci I 9.88E-01 1 3.24E-01 1 0.00E+00 1 0.00E+00

, J KR-88 i Ci I 9.24E-02 1 5.23E-02 1 0.00E+00 1 0.00E+00 XE-133 I Ci l 2.30E+01 1 1.07E+01 1 0.00E+00 1 0.00E+00 XE-133M I Ci I 0.00E+00 1 1.08E-01 1 0.00E+00 1 0.00E+00 XE-135 I Ci l 3.09E+00 1 7.93E-01 1 0.00E+00 1 0.00E+00 XE-135M I Ci I 6.66E+00 1 2.30E+00 1 0.00E+00 1 0.00E+00 l XE-137 i Ci l 1.66E+01 1 1.11E+01 1 0.00E+00 1 0.00E+00 l XE-138 i Ci l 1.83E+01 1 5.29E+00 1 0.00E+00 1 0.00E+00 [

l l I i l l Total for Period l Ci I 6.87E+01 1 3.07E+01 1 0.00E+00 1 0.00E+00 l

2. Iodines
l. I-131 l Ci 1 4.62E-04 1 3.42E-04 1 0.00E+00 1 0.00E+00 l i  ! I-133 I Ci I 3.13E-03 l 2.67E-03 1 0.00E,00 1 0.00E+00 l

[ I-135 I Ci 1 5.05E-03 1 4.77E-03 1 0.00E+00 1 0.00E+00 l l l 1 I I i l l Total for Period l Ci l 8.64E-03 I 7.78E-03 1 0.00E+00 1 0.00E+00 l 30 Particulate MN-54 i Ci I 3.58E-07 I 3.04E-07 1 0.00E+00 1 0.00E+00 CO-58 I Ci I 7.94E-08 1 0.00E+00 1 0.00E+00 1 0.00E+00 CO-60 1 Ci I 7.83E-06 l 2.77E-06 1 0.00E+00 1 0.00E+00 ZN-65 i Ci I 6.99E-07 l 2.41E-07 1 0.00E+00 1 0.00E+00 SE-75 i Ci i 1.41E-07 I 4.69E-08 1 0.00E+00 1 0.00E+00 l CS-137 i Ci l 6.49E-07 l 1.14E-07 1 0.00E+00 1 0.00E+00 l BA-140 1 Ci I 6.98E-05 1 4.73E-05 1 0.00E+00 1 0.00E+00 l l -SR-89 I Ci I 3.P7E-05 1 0.00E+00 1 0.00E+00 1 0.00E+00 l 2

l l SR-90 i Ci l 2.82E-07 1 0.00E+00 1 0.00E+00 1 0.00E+00 l l l 1 1 I I l l Total for Period l Ci l 1.18E-04 1 5.07E-05 1 0.00E+00 1 0.00E+00 l l Analysis of Sr-89 & 90 for the 2nd Qtr was not completed in time for l this report, results will be included with the next semiannual report, f

Page 6 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT l

, Period : Jan - Jun 1998 l l

Table 1C Gaseous Effluents - Building Vent Releases l l

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l l Nuclides Released i Unit I ist Otr I 2nd Otr I ist Otr i 2nd Otr l

1. Fission Gases I l XE-133 i Ci 1 0.00E+00 1 0.00E+00 1 6.35E-03 1 0.00E+00 l l XE-135 i Ci 1 5.99E+00 l 3.00E+00 1 6.56E-03 1 0.00E+00 l j l XE-135M I Ci I 3.62E+00 1 7.08E-01 1 0.00E+00 1 0.00E+00 }

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' l AR-41 l Ci 1 0.00E+00 1 0.00E+00 l 9.43E-03 1 1.61E-03 i l l l l l l I l

l Total for Period l Ci I 9.61E+00 1 3.70E+00 l 2.23E-02 1 1.61E-03 l

2. Iodines l l I-131 l Ci I 4.25E-03 1 2.23E-04 1 0.00E+00 1 0.00E+00 l l l I-133 I Ci l 3.82E-02 1 8.47E-04 1 0.00E+00 1 0.00E+00 l )

l I-135 i Ci I 7.08E-02 1 0.00E+00 1 0.00E+00 1 0.00E+00 l l l l l l l l l l Total for Period l Ci i 1.13E-01 1 1.07E-03 1 0.00E+00 1 0.00E+00 l

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3. Particulate j l MN-54 i Ci i 1.38E-05 1 2.02E-05 1 0.00E+00 1 0.00E+00 l l l CO-58 I Ci l 1.09E-06 l 1.68E-06 1 0.00E+00 1 0.00E+00 l l l CO-60 I Ci l 2.34E-04 1 9.67E-05 I 9.92E-06 1 0.00E+00 l l

l ZN-65 l Ci I 5.48E-05 l 1.23E-04 1 0.00E+00 1 0.00E+00 l l CS-137 I Ci 1 5.36E-05 1 3.56E-05 1 0.00E+00 1 0.00E+00 l l BA-140 l Ci l 2.28E-04 1 0.00E+00 1 0.00E+00 1 0.00E+00 l l CE-144 I Ci I 8.82E-06 1 0.00E+00 1 0.00E+00 1 0.00E+00 l

' l SR-89 i Ci I 4.89E-06 1 0.00E+00 1 0.00E+00 1 0.00E+00 l l SR-90 I Ci I 8.76E-08 1 0.00E+00 1 0.00E+00 1 0.00E+00 l

l I I I I I l l Total for Period l Ci I 5.99E-04 1 2.77E-04 1 9.92E-06 1 0.00E+00 l Analysis of Sr-89 & 90 for the 2nd Qtr was not completed in time for )

this report, results will be included with the next semiannual report. )

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Page 7 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jan - Jun 1998 Table 2A Liquid Effluents - Summation of all Releases l l Units l 1st Qtr l 2nd Qtr lEst. Totalj l l l l l Error. % l A. Fission & Activation products l 1. Total Release (not including l l l l l l tritium, cases, alpha) l Ci 1 0.00E+00 1 0.00E+00 1 0.00E+00 l l 2. Ava Diluted Concentration I uci/ml 1 0.00E+00 1 0.00E+00 l B. Tritium l 1. Total Release l Ci I 0.00E+00 1 0.00E+00 1 0.00E+00 l l__?. Ava Diluted Concentration I uci/ml 1 0.00E+00 1 0.00E+00 l C. Dissolved and Entrained Gases

1. Total Release l Ci I 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 1. Whole Body Dose I  % 1 0.00E+00 1 0.00E+00 l l 2. Organ Dose I  % 1 0.00E+00 1 0.00E+00 l E. Gross Alpha Radioactivity l 1. Total Release , , , l , Ci 1 0.00E+00 1 0.00E+00 1 0.00E+00 l lF. Volume of Waste Released I L.iters 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 l l l Continuous Mode l Batch Mode l l Nuclides Released i Unit I ist Otr I 2nd Otr l 1st Otr I 2nd Otr l None Released This Period I

Page 8 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jan - Jun 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 l l I 1 Period l Error. %

l a. Spent resins, filter sludges, Cu. Meter 9.24E+00 i

[ evaoorator bottoms, etc. Ci 2.18E+02 3.70E+01

.l b. Dry compressible waste, l Cu. Meter l 1.36E+01 l l l contaminated eauipment, etc. I Ci l 3.75E-02 l 3.50E+01 l l c. Irradiated components, Cu. Meter l 0.00E+00 l l control rods, etc. Ci 1 0.00E+00 1 0.00E+00 l

d. Other (describe) l Cu. Meter l 0.00E+00 l 1 Ci 1 0.00E+00 0.00E+00 l l 2. Estimate of major nuclide composition (by type of waste) 1 l l Type A l Type B l Type C l Type D l Nuclide I percent I cercent I percent I cercent l H-3 l 1.22E-01 l 1.96E-01 l C-14 1.09E-01 l 6.37E-02 l Cr-51 3.49E-01 l l Mn-54 1.39E+01 3.73E+00 l Fe-55 l 8.85E+00 5.58E+01 l Co-57 3.23E-02 Co-58 2.45E+00 Fe-59 8.09E-01 l l

Ni-59 1.50E-03 l l Co-60 3.55E+01 2.62E+01 Ni-63 5.93E-01 5.78E-01 Zn-65 3.41E+01 1.08E+01 Sr-89 1.23E-01 9.13E-04 Sr-90 1.90E-02 1.74E-02 '

Ag110m l 7.82E-01 Sb-124 l 1.02E-01 Sb-125 l 4.43E-02 '

I-131 l 1.65E-01 l l

i Cs-134 l 2.20E-02 3.23E-02 l Cs-137 l 1.70E+00 2.14E+00 . l Ba-140 l 8.50E-03 l l

Ce-141 l 6.10E-02 l Ce-144 l 5.17E-02 l Pu-238 l 1.08E-02 Pu-239 7.97E-03 Am-241- l 2.09E-02 Pu-241 '

2.00E-02 2.12E-01 Cm-242 l 3.40E-03 5.64E-04 Cm-243 l 1.50E-04 7.75E-03 1

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Page 9 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jan - Jun 1998 Table 3- Solid Waste and Irradiated Fuel Shipments

3. Solid waste diaposal Number of Mode of Destination l Shioments Transportation

' l 7: l . ruck l Chem-Nuc Inc., Barnwell, SC. l l 1 l j i

'B. Irradiated-Fuel Shipments j 1

'1. Disposition.

.l: Number of l . Mode of l Destination l 6 l'Shioments 1 Transportation 1 l l None This Period C. Shipping Container and Solidification Method No. .-l Volume l Activity Type of Container l Solidification l I M3 i Ci Waste Code l Code l

, 98-35 3.41E+00 l 1.85E+02 A l A D l 98-34 5.83E+00-l 3.26E+01 A A D 16  ! 3.46E-01 l 2.08E-02 B L N 9812A 3.77E-01 l 2.08E-03 B l L N 9812B 5.10E-02 2.48E-03 .B L N 9812C , 7.56E-01 8.73E-03 B' L N l 9731a l 1.21E+01 1 3.43E-03 l B L N I I I  !

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Container Codes : Solidification Codes :

L - LSA C - Cement A - Type A U - Urea Formaldehyde l p B - Type B D - Dewatering Q - Large Quantity N -'Not Applicalble i  !

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