ML20216B762

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Effluent & Waste Disposal Semi-Annual Rept for July-Dec 1997
ML20216B762
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 12/31/1997
From:
NORTHERN STATES POWER CO.
To:
Shared Package
ML20216B750 List:
References
NUDOCS 9803130183
Download: ML20216B762 (10)
v • d • e


Text

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Attachment A Effluent and Waste Disposal Semi-Annual Report for July - Decen:ber 1997 l

(The attached Report contains 9 pages.) j 2/26/98 s!s Ja\ LICENSE \ PERIODIC.RPT\tFF_RPT.912 9001130183 980226 '

(DR ADOCK 05000263 PDR

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

1. Rsgulatory 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 IOJines, 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, P ' iculates, and Tritium :

10 CFR Part 20, Appen.. 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)

. Page 2 i

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

Supplemental Information (continued)

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

)

Continuous gross activity monitors in Reactor Building Vent and Plant l l Stack exhaust streams. Weekly isotopic analysis of exhaust streams.

l 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 :

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 I

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 Iain
6. Average River Flow During Release 0.0 cf/sec B. Gaseous :
1. 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

3

. Pcga 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1997 f

Supplemental Information (continued) l

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

)

Page 4 f.

l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1997 Table 1A Gaseous Effluents - Summation of all Releases t l

l l Units 3rd Qtr l 4th Qtr lEst. Total l l l Error. %

A. Fission & Activation gases l 1. Total Release I Ci I 6.60E+01 1 1.08E+02 1 2 . 0 0 E+ Q1_ l l 2. Average Release Rate I uci/sec ! 8.31E+00 1 1.35E+01 l

3. Percent Tech Spec Qtrly l l l Reporting Level l l Gamma Radiation l  % l 5.95E-02 l 8.80E-02 l Beta Radiation I  % 1 1.84E-02 1 3.10E-02 ,

B. Iodines

1. Total I-131 Release I Ci I 7.05E-04 l 2.46E-03 l 1.00E+01 l l 2. Averace I-131 Release Rate I uci/sec ! 8.87E-05 l 3.10E-04 l C. Particulates l l 1. Total Particulates I Ci I 3.13E-04 1 4.17E-04 1 3.00E+01 l l 2. Average Release Rate I uci/sec I 3.93E-05 I 5.24E-05  ;

l 3. Gross Alpha Radioactivity i Ci I 5.93E-06 1 1.61E-06 j i J l D. Tritium l

l 1. Total Release l Ci I 3.59E+00 I 5.31E+00 l 1.00E+01 l  ;

l 2. Averace Release Rate I uci/sec l 4.52E-01 l 6.68E-01 l  !

l E. Percent Qtrly Tech Spec Reporting Levels l 1. Iodines, Particulates, l l l l l and Tritium 1  % I 1.04E-01 1 3.61E-01 l l

Page 5 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1997 -

1 l

Table 1B Gaseous Effluents - Elevated Releases l

{

l l Continuous Mode l Batch Mode l l Nuclides Released I Unit 3rd Otr 1 4th Otr I 3rd Otr i 4th Otr l

1. Fission Gases L KR-85M l 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 l KR-88 I Ci 1 0.00E+00 1 1.23E+00 1 0.00E+00 1 0.00E+00 KR-89 i Ci l 1.41E+00 1 0.00E+00 1 0.00E+00 1 0.00E+00 l XE-133 l Ci i 1.33E+01 1 3.15E+01 1 0.00E+00 1 0.00E+00 1 XE-133M I Ci I 3.09E-01 l 2.54E-01 1 0.00E+00 1 0.00E+00 l XE-135 I Ci l 1.96E+00 l 1.03E+01 1 0.00E+00 1 0 Q0E+00 l XE-135M I Ci I 4.35E+00 I 6.03E+00 1 0.00E+00 I atqQE+00.l )

XE-137 i Ci l 2.49E+01 1 3.08E+01 1 0.00E+00 1 0.00E+00 l XE-138 i Ci l 1.30E+01 1 1.57E+01 1 0.00E+00 1 0.00E+00 l J AR-41 1 Ci 1 0.00E+00 1 1.07E-02 1 0.00E+00 1 0.00E+00 l 1 I I i 1 l Total for Period l Ci I 6.00E+01 1 9.76E+01 1 0.00E+00 1 0.00E+00 l

2. Iodines I-131 l Ci I 3.02E-04 I 8.22E-04 1 0.00E+00 1 0.00E+00 I-133 I Ci l 2.69E-03 1 3.49E-03 1 0.00E+00 1 0.00E+00 I-135 i Ci I 4.30E-03 1 5.45E-03 1 0.00E+00 1 0.00E+00 I I I I I Total for Period l Ci i 7.29E-03 1 9.76E-03 1 0.00E+00 1 0.00E+00 ,
3. Particulates CO-60 i Ci I 3.73E-06 1 1.37E-06 1 0.00E+00 1 0.00E+00 l SE-75 i Ci 1 0.00E+00 l 4.02E-08 1 0.00E+00 1 0.00E+00 l CS-137 l Ci l 1.41E-06 1 6.89E-07 I 0.00E+00 1 0.00E+00 l BA-140 I Ci I 7.69E-05 1 1.20E-04 1 0.00E+00 1 0.00E+00 l SR-89 I Ci 1 3.44E-05 1 4.68E-05 1 0.00E+00 1 0.00E+00 SR-90 I Ci I 3.07E-07 i 2.64E-07 1 0,00E+00 1 0,00E+00 '

I I I I l Total for Period l Ci l 1.17E-04 l 1.69E-04 1 0.00E+00 1 0.00E+00

  • Pege 6 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1997 Table IC Gaseous Effluents - Building Vent Releases l l l Continuous Mode l Batch Mode l l Nuclides Released i Unit 1 3rd Otr I 4th Otr i 3rd Otr 1 4th Otr l
1. Fission Gases l XE-135 i Ci 1 3.26E+00 1 6.53E+00 1 0.00E+00 1 0.00E+00 l l XE-135M I Ci 1 2.78E+00 1 3.44E+00 1 0.00E+00 1 0.00E+00 l l AR-41 l Ci I 0.00E+00 1 0.00E+00 1 3.70E-03 1 1.28E-03 l l l l l l l l l Total for Period l Ci I 6.04E+00 1 9.97E+00 1 3.70E-03 1 1.28E-03 l
2. Iodines I-131 l Ci I 4.03E-04 l 1.64E-03 1 0.00E+00 1 0.00E+00 I-133 I Ci I 3.91E-03 l 1.82E-02 1 0.00E+00 1 0.00E+00 I-135 I Ci I 3.76E-03 1 3.21E-02 1 0.00E+00 1 0.00E+00 l l l 1 l l j Total for Period i Ci I 8.07E-03 1 5.20E-02 1 0.00E+00 1 0.00E+00 l
3. Particulates l MN-54 I Ci 1 0.00E+00 1 1.90E-06 1 0.00E+00 1 0.00E+00 l l CO-60 1 Ci l 1.35E-04 I 7.91E-05 1 2.40E-06 1 0.00E+00 l l ZN-E5 l Ci I 0.00E+00 1 2.29E-05 1 0.00E+00 1 0.00E+00 l l CS-137 I Ci l 4.10E-05 1 3.42E-05 1 0.00E+00 1 0.00E+00 l l BA-140 1 Ci l 1.20E-05 1 1.05E-04 1 0.00E+00 1 0.00E+00 l l SR-89 i Ci 1 5.30E-06 1 4.55E-06 1 0.00E+00 1 0.00E+00 l l SR-90 i Ci i 1.86E-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 1.94E-04 I 2.47E-04 l 2.40E-06 1 0.00E+00 l I

Pags 7 l .

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

, l l Units 3rd Qtr 4th Qtr Est. Total l l l 1 Error. % l A. Fission & Activation products i 1. Total Release (not including l l l l l tritium. cases, aloha) l Ci  ! 0.00E+00 1 0.00E+00 1 0.00E+00 l .

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

l 1. Total Release i Ci 1 0.00E+00 l 0.00E+00 1 0.00E+00 l l 2. Ava Diluted Concentration i uci/ml I 0.00E+00 1 0.00E+00 [

C. Dissolved and Entrained Gases

1. Total Release i 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. Orcan Dose I  % 1 0.00E+00 1 0.00E+00 l E. Gross Alpha Radioactivity l 1. Total Release i Ci I 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 l 0.00E+00 l lF. Volume of Dilution Water Used I Liters 1 0.00E+00 1 0.00E+00 l 0.00E+00 l Table 2B Liquid Effluents i

l l Continuous Mode Batch Mode l l Nuclides Released Unit i 3rd Otr 1 4th Otr 3rd Otr i 4th Otr  !

None Released This Period 1

l

F. .

Page 8 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1997 Table 3' Solid Waste and Irradiated Fuel Shipments (Estimates)

A. Solid Waste Shipped Offsite for Burial or Disposal (not irradiated fuel) l 1. Type of Waste Units l l 6-month lEst. Totall l

a. Spent resins, filter sludges, l l Period i Error. % l evaDorator bottoms. etc.

Cu. Meter l 1.75E+01 l Ci I 7.22E+01 3.70E+01 l

b. Dry compressible waste, l Cu. Meter l 2.10E+00 contaminated eauipment, etc. l I Ci I 4.36E-02 3.50E+01 l L c. Irradiated components, control rods, etc.

l Cu. Meter 0.00E+00 l l I Ci 0.00E+00 1 0.00E+00 l

d. Other (dascribe) Cu. Meter ] 0.00E+00 l Ci 1 0.00E+00 1 0.00E+00 l
2. Estimate of major nuclide composition (by type of waste) l Type A l Type B l Type C l Type D Nuclide i Dercent I percent I Dercent l Dercent l H-3 l 1.12E+00 l 1.40E-01 l C-14 l 5.72E-01 '

3.06E-02 ]

Mn-54 l 1.67E+00 '

3.70E+00 Fe-55 l 4.23E+01 5.60E+01 l Co-57 2.74E-02 l Co-58 2.40E-01 l Ni-59 1.00E-02 Co-60 2.01E+01 2.52E+01 Ni-63 l 4.42E-01 6.52E-01 l l Zn-65 9.34E+00 1.12E+01 . l l Sr-89 1.56E+00 l l l l Sr-90 1.07E-01 ,

1.81E-02 l l l Sb-125 4.44E-02 l l I-131 6.06E+00 l Cs-134 l 8.39E-02 2.90E-02 l L Cs-137 1.60E+01 2.55E+00 l Ba-140 6.81E-03 l  !

La-140 3.36E-02 l  !

Ce-141 2.80E-01 Ce-144 1.00E-02 4.32E-02 Pu-238 1.22E-02 Pu-239 9.45E-03 Am-241 2.92E-02 l Pu-241 l 4.00E-02 l 2.33E-01 "

Cm-242 l 1.10E-03 Cm-243 l 1.00E-02 I I I I

  • Page 9

! EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1997 Table 3' Solid Waste and Irradiated Fuel Shipments (Estimates)

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

6 l Truck l Chem-Nuc Inc., Barnwell, SC.

j l l B. Irradiated Fuel Shipments

1. Disposition Number of l Mode of l Destination l Shipments l Transportation I l None This Period C. Shipping Container and Solidification Method No. l Volume Activity l Type of l Container Solidification i 1 M3 Ci I Waste I Code Code l 97-32 l 5.83E+00 l 2.65E+01 l A l A '

D l 97-33 5.83E+00 2.11E+01 l A l A D l 97-35 5.83E+00 2.46E+01 l A l A D l 9716b l 9.63E-02 1.49E-02 l B l L , N l 9723a l 1.97E+00 1.97E-02 l B l L N l l 9716c l 2.83E-02 9.00E-03 l B l L N l l l l l l l 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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