ML20238E834

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Revised Effluent & Waste Disposal Semi-Annual Rept for Jul- Dec 1997
ML20238E834
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 12/31/1997
From:
NORTHERN STATES POWER CO.
To:
Shared Package
ML20238E821 List:
References
NUDOCS 9809020224
Download: ML20238E834 (10)
v • d • e


Text

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Attachment B Revised' Effluent and Waste Disposal Semi-Annual Report for July - December 1997 t

(The attached Report contains 9 pages.)

t-l

' The revision includes corrected radioactive waste shipment data received from a waste processing vendor. Changes have baen sidebarred.

9809020224 980826 FDR ADOCK 05000263; R PDR f,.

NORTHERN STATES POWER COMPANY NONTICELLO NUCLEAR GENERATING PLANT l License No. DPR-22 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1997 Supplemental Information

1. R:gulatory 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, Particulate, and Tritium :

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

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

2. Maximum Permissible Concentrations L A. Noble Gases :

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

L 10 CFR Part 20, Appendix B, Table II, Column 1 l

-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 1997

. 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. 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 :

l'. Number of Batch Releases 3

2. Total' Time Period for Batch Releases 1552.0 min

.3. Maximum-Time Period for a Batch Release 887.0 min

4. Average Time Period for a Batch-Release 517.3 min 5'. Minimum Time Period for a Batch Release 330.0 min

Page 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1997

-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 1

L l

Page 4 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1997  !

Table 1A Gaseous Effluents - Summation of all Releases l Units' 3rd Qtr 4th Qtr Est. Total l Error. %

'A. Fission &-Activation gases l 1. Total Release 'l Ci  ! 6.60E+01 1 1.08E+02 l 2.00E+01 l:

g 2. Averaae Release Rate I uci/sec l 8.31E+00 l 1.35E+01

3. Percent Tech Spec Qtrly Reporting Level

.l Gamma Radiation  % 5.95E-02 8.80E-02 l Beta' Radiation  % 1.84E-02 3.10E-02 j B. Iodines l 1. Total I-131 Release I Ci I 7e05E-04 l 2.46E-03 l 1.00E+01 l l 2. Averace I-131 Release Rate I uci/sec-l 8.87E-05 1 3.10E-04 [

C. Particulate

1. Total Particulate I Ci I 3.13E-04 1 4.17E-04 I 3.00E+01 l
2. Averace Release Rate I uci/sec I 3.93E-05 1 5.24E-05
3. Gross Aloha Radioactivity l Ci I 5.93E-06 1 1.61E-06 D.. Tritium l '1. Total Release I Ci I 3.59E+00 l 5.31E+00 l 1.00E+01 l

'l 2. Averaae Release Rate i uci/sec l 4.52E-01 1 6.68E-01 l E. Percent Qtrly Tech Spec Reporting Levels

.l 1.. Iodines, Particulate, l l l and Tritium I  % 'l 1.04E-01 3.81E-01 l

L-_ _ _ _ - _ _ _ _ _ _ _ - _ - _ - _ _ _ - - _ _ _ - ._ __ _ _ _ _ _ .

F e .

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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1997 Table 1B Gaseous Effluents - Elevated Releases l l l l Continuous Mode Batch Mode l l Nuclides Released I Unit i 3rd Otr I 4th Otr 3rd Otr I 4th Otr l l 1. Fission Gases

[ KR-85M I Ci I 5.48E-03 1 6.24E-01 1 0.00E+00 1 0.00E+00 l ,

l KR-87 I Ci I 7.48E-01 1 1.13E+00 1 0.00E+00 1 0.00E+00 )

KR-88 i Ci I 0.00E+00 1 1.23E+00 1 0.00E+00 l 0.00E+00 '

KR-89 l Ci l 1.41E+00 1 0.00E+00 1 0.00E+00 1 0.00E+00 i

XE-133 I Ci i 1.33E+01 1 3.15E+01 1 0.00E+00 1 0.00E+00 ,

XE-133M I Ci I 3.09E-01 1 2.54E-01 1 0.00E+00 1 0.00E+00 l XE-135 i Ci l 1.96E+00 1 1.03E+01 1 0.00E+00 1 0.00E+00 l l XE-135M i Ci I 4.35E+00 1 6.03E+00 1 0.00E+00 1 0.00E+00 i l XE-137 I Ci l 2.49E+01 1 3.08E+01 1 0.00E+00 1 0.00E+00 l XF-138 I Ci l 1.30E+01 1 1.57E+01 1 0.00E+00 1 0.00E+00 l AR-41 l Ci 1 0.00E+00 l 1.07E-02 1 0.00E+00 1 0.00E+00 l l 1 I I I I l Total for Period l Ci l 6.00E+01 l 9.76E+01 1 0.00E+00 1 0.00E+00

2. Iodines l I-131 1 Ci  ! 3.02E-04 I 8.22E-04 1 0.00E+00 1 0.00E+00 l l I-133 i Ci l 2.69E-03 1 3.49E-03 1 0.00E+00 1 0.00E+00 l I-135 I Ci I 4.30E-03 1 5.45E-03 1 0.00E+00 1 0.00E+00 l l l l I I l l Total for Period l Ci I 7.29E-03 l 9.76E-03 1 0.00E+00 1 0.00E+00 l
3. Particulate l CO-60 l Ci I 3.73E-06 1 1.37E-06 1 0.00E+00 1 0.00E+00 l l SE-75 l Ci 1 0.00E+00 l 4.02E-08 1 0.00E+00 1 0.00E+00 l l CS-137 I Ci i 1.41E-06 1 6.89E-07 1 0.00E+00 1 0.00E+00 [

BA-140 i Ci I 7.69E-05 l 1.20E-04 1 0.00E+00 1 0.00E+00 l SR-89 i Ci I 3.44E-05 I 4.68E-05 1 0.00E+00 1 0.00E+00 l SR-90 I Ci l 3.07E-07 1 2.64E-07 1 0.00E+00 1 0.00E+00 l l l l 1 l l l Total for Period l Ci l 1.17E-04 l 1.69E-04 1 0.00E+00 1 0.00E+00 l t

i

I. . .

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. EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1997 Table 1C Gaseous Effluents - Building Vent Releases I

Ll

' l l Continuous Mode l Batch Mode l Nuclides Released I Unit 1 3rd Otr I 4th Otr i 3rd Otr i 4th Otr j 1. Fission Gases l XE-135 i Ci I 3.26E+00 l 6.53E+00 l 0.00E+00 1 0.00E+00 i

! XE-135M I Ci  ! 2.78E+00 1 3.44E+00 1 0.00E+00 1 0.00E+00 1

! AR-41 1 Ci l 0.00E+00 l 0.00E+00 1 3.70E-03 l 1.28E-03 l i l I l l

1 Total for-Period l Ci I 6.04E+00 1 9.97E+00 1 3.70E-03 1 1.28E-03 ,

I 2. Iodines i

p I I-131 1 Ci l 4.03E-04 1 1.64E-03 ! 0.00E+00 1 0.00E+00 l I-133 i Ci I 3.91E-03 1 1.82E-02 1 0.00E+00 1 0.00E+00 l

I-135 l Ci I 3.76E-03 I 3.21E-02 l 0.00E+00 1 0.00E+00 l I I I I Total for Period l Ci  ! 8.07E-03 1 5.20E-02 1 0.00E+00 l 0.00E+00

~3. Particulate R

,-l MN-54 i Ci 1 0.00E+00 1 1.90E-06 1 0.00E+00 l-0.00E+00 )

l CO-60 l Ci l 1.35E-04 1 7.91E-05 1 2.40E-06 1 0.00E+00 Ll ZN-65 l Ci 1 0.00E+00 1 2.29E-05 1 0.00E+00 l 0.00E+00 1 CS-137 I Ci I 4.10E-05 1 3.42E-05 l 0.00E+00 1 0.00E+00 BA-140 l Ci l 1.20E-05 l 1.05E-04 1 0.00E+00 1 0.00E+00 SR-89 I Ci 1 5.30E-06 1 4.55E-06 1 0.00E+00 1 0.00E+00 SR-90 l Ci i 1.86E-07 I 0.00E+00 1 0.00E+00 l 0.00E+00 1 1 I I I Total for Period l Ci i 1.94E-04 1 2.47E-04 l 2.40E-06 1 0.00E+00 l

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Page 7 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1997 Table 2A Liquid Effluents - Summation of all Releases l

l

j. . l l l I

Units 3rd Qtr l 4th Qtr lEst. Total]

I I Error, % l l A. Fission & Activation products

, l 1. Total Release (not including l l l l tritium, cases, alphal Ci I 0.00E+00 0.00E+00 0.00E+00 l l 2. Ava Diluted Concentration I uci/ml I 0.00E+00 1 0.00E+00 [

B. Tritium

-l 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 l 1 0.00E+00 1 0.00E+00 l C. Dissolved and Entrained Gases l 1. Total Release I 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 D. Percent Qtrly Tech Spec Reporting Level l 1. Whole Body Dose I  % l 0.00E+00 l 0.00E+00 l 2. Orcan Dose I  % 1 0.00E+00 1 0.00E+00 i

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 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 l l Continuous Mode Batch Mode l l Nuclides Released I Unit 3rd Otr I 4th Otr 3rd Otr 1 4th Otr l j None Released This Period

Pago 8 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1997 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. Tota 1l l

a. Spent resins, filter sludges, 1 1 Period l Error. % l l

evaporator bottoms, etc.

lI Cu. Ci Meter l 1.75E+01 l l l

b. Dry compressible waste, I 7.22E+01 1 3.70E+01 l l

contaminated eculoment. etc.

[I Cu. Meter l 2.10E+00 l l l

c. Irradiated components, Ci I 4.75E-02 1 3.50E+01 l l f l

control rods, etc.

lI Cu. Meter l 0.00E+00 l l l Ci I 0.00E+00 1 0.00E+00 l l d. Other (describe) l Cu. Meter l 0.00E+00 l l l 1 Ci I 0.00E+00 1 0.00E+00 l l 2. Estimate of major nuclide composition (by type of waste) l l Type A Type B l Type C l Type D l Nuclide I percent percent I percent I percent

! H-3 l 1.12E+00 'l 1.40E-01 l

j C-14 l 5.72E-01 3.06E-02 l l Mn-54 l 1.67E+00 3.70E+00 l l l l Fe-55 l 4.23E+01 5.60E+01 l l l Co-57 ,

2.52E-02 l l l Co-58 2.40E-01 ! l l ,

l Ni-59 l 1.00E-02 l l l l l Co-60 l 2.01E+01 2.52E+01 l l l Ni-63 l 4.42E-01 l 6.52E-01 l l l Zn-65 l 9.34E+00 l 1.12E+01 l l l Sr-89 l 1.56E+00 l l l l Sr-90 l 1.07E-01 l 1.99E-02 l l l Sb-125 l l 4.08E-02 l l l I-131 l 6.06E+00 l l l l Cs-134 l 8.39E-02 l 2.67E-02 l l l Cs-137 l 1.60E+01 l 2.55E+00 l l l Ba-140 l 6.81E-03 l l l l La-140 l 3.36E-02 l l Ce-141 2.80E-01 l Ce-144 1.00E-02 3.97E-02 l l Pu-238 l 1.20E-02 l l Pu-239 l 9.50E-03 l l l Am-241 l l 2.92E-02 l l l Pu-241 l 4.00E-02 l 2.33E-01 l l l Cm-242 l l 1.01E-03 l l l Cm-243 l l 1.00E-02 l l

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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1997 Table 3 Solid Waste and Irradiated Fuel Shipments 1 3. Solid waste disposal l Number of-l Mode of Destination l Shioments l Transportation l 6 l Truck l Chem-Nuc Inc., Barnwell, SC.

i .l- 1 I B. Irradiated Fuel Shipments I

1. Disposition l Nurber of l Mode of l Destination l

! l-Shioments l Transportation I l None This Period C.. Shipping Container and Solidification Method No. Volume Activity Type of Container Solidification M3 Ci Waste Code Code 97-32 l 5.83E+00 l 2.65E+01 A l A D l 97-33 ' 5.83E+00 2.11E+01 A A D l~97-35 1 5.83E+00 2.46E+01 i A A D l 9716b 9.63E-02 1.49E-02 l B L N l 9723a 1.97E+00 2.36E-02 B L N l l 9716c 2.83E-02 9.00E-03 B L N l  ! I i 1

, 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 l

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