ML20216B014

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Effluent & Waste Disposal Semi-Annual Rept Period Jan-June 1997
ML20216B014
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 06/30/1997
From:
NORTHERN STATES POWER CO.
To:
Shared Package
ML20216B012 List:
References
NUDOCS 9709050191
Download: ML20216B014 (31)
v • d • e


Text

. .:.-- .

. o-Attachment A Effluent and Waste Disposal Semi-Annual Report, Peiiod January - June,1997 (The attached Report contains 9 pages.) .

)

~6/24/91. JR$ J i \ L ICEN3E\ PER I ODIC . 8 PT\ t FF,R PT ,971 vt 9709050 PDR A g $7 h 263 PDR R

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d a NORTHERN STATES POWER COMPA!&

MONTICELLO NUCLEAR GENERATING PLANT License No. DPR-22 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORf Period : Jan - Jun 1997 Supplemental Information

1. Regulatory 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, 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, Particulates, and Tritium :

10 CFR Part 20, Appendix B, Table II, Column 1 C. Liquid Effluents  :

10 CFR Part 20, Appendix 3, Table II, Column 2 2.0 E-4 uci/ml for dissolved and entrained gases

3. Average Energy (Not Applicable)

. . g .

Page 2 o

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jan - Jun 1997 Supplemental Information (continued)

4. Measurements and Approximations of Total Radioactivty 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 l Vent and Plant Stack exhaust streams with weekly analysis, l

l C. Particulates in Gaseous Effluent :

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

D. Tritium in Gaseous Effluent :

Weekly grab samplea from Reactor Building Vent and P'. ant 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 S. Minimum Time Period for a Batch Release 0.0 min
6. Average River Flow During Release 0.0 cf/ cec B. Gaseous :
1. Number of Batch Releases 1
2. Total Time Period for-Batch-Releases 1423.0 min 3.-Maximum Time Period for a Batch Release 1423.0 min
4. Average Time Period'for a Batch Release 1423.0 min
5. Minimum Time Period for a Batch Release 1423.0 min

, s

-. g _Page 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jan - Jun 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 l

l-.

! i f

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c Page 4 o

. EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jan - Jun 1997 Table 1A Gaseous Effluents - Summation of all Releases Units 1st Qtr 2nd Qtr Est. Total Error. %

A. Fission & Activation gases

1. Total Release Ci 1.003 ,02 5.83E+01
2. Averace Release Rate uci/sec 1.90E+01 2.00E+01 l 7.41E+00 l 3. Percent Tech Spec Qtrly Reporting Level Gamma Radiation  % 1.10E-01 4.75E-02 Beta Radiation  % 3.08E-02 1.81E-02 l -B~. Iodines
1. Total I-131 Release Ci 8.50E-04 9.04E-04
2. Averaae I_l',1 Release Rate uci/sec 1.09E-04 1.00E+01 l 1.15E-04 C. Particulates
1. Total Particulates Ci 2.99E-04 2.73E-04
2. Averace Release Rate uci/sec 3.84E 3.00E+01 l 3.48E-05

__). Gross Alpha Radioactivity Ci 1.97E-06 6.93E-06 D. Tritium

1. Total Release Ci 3.68E+00 2.46E+00
2. Average Release Rate uci/sec 4.73E-01 1.00E+01 l 3.13E-01 E. Percent Qtrly Tech Spec Reporting Levels
1. Iodinea, Particulates, and Tritium  % 1.35E-01 9.26E u

.J Page 5 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jan - Uun 1997 Table 1B Gaseous Effluents - Elevated Releases Continuous Mode Batch Mode Nuclides Released Unit 1st Otr 1 2nd Otr let Otr I 2nd Otr

1. Fission Gases KR-85M 01 6.70E-01 9.35E-01 0.00E+00 0.00E+00 KR-87 Ci 1.13E+00 7.15E-01 0.00E+00 0.00E+00 KR-88 C1 1.30E+00 1.71E+00 0.00E+00 0.00E+00 XE-133 Ci 2.68E+01 1.11E+01 0.00E+00 0.00E+00 XE-133M Ci 3.99E-01 7.99E-01 0.00E+00 0.00E+00 XE-135 Ci 1.15E+01 1.30E+01 0.00E+00 0.00E+00 XE-135M Ci 6.00E+00 3.20E+00 0.00E+00 0.00E+00 XE-137 Ci 3.28E+01 1.46E+01 0.00E+00 0.00E+00 XE-138 C1 1.61E+01 6.83E+00 0.00E+00 0.00E+00 AR-41 Ci 1.73E-02 2.73E-02 0.00E+00 0.00E+00 Total for Period Ci 9.67E+01 5.29E+01 0.00E+00 0.00E+00
2. Iodines I-131 Ci 4.07E-04 6.23E-04 0.00E+00 0.00E+00 I-133 Ci 3.42E-03 2.90E-03 0.00E+00 0.0QE+00 I-135 Ci 6.00E-03 2.42E-03 0.00E+00 0.00E+00 Total for Period Ci 9.83E-03 5.94E-03 0.00E+00 0.00E+00
3. Particulates MN-54 Ci 0.00E+00 6.27E-08 0.00E+00 0.00E+00 CO-60 Ci 1.83E-06 3.98E-06 0.00E+00 0.00E+00 l ZN-65 Ci 0.00E+00 3.66E-07 0.00E+00 0.00F *00 CS-137 Ci 5.19E-07 1.72E-06 0.00E+00 0.00E+00 BA-140 Ci 1.06E-04 3.38E-05 0.00E+00 0.00E+00 SR-89 Ci 3.81E-05 1.92E-05 0.00E+00 0.00E+00 SR-90 C1 1.73E-07 1.51E-07 0.00E+00 0.00E+00 Total for Period Ci 1.46E-04 5.92E-05 0.00E+00 0.00E+00

. / .

Page 6 4

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jan - Jun 1997 Table 1C Gaseous Effluents - Building Vent Releases Continuous Mode Batch Mode

_Hpelides Released Unit ist Otr I 2nd Otr ist Otr l 2nd Otr

1. Fission Gases XE-133 Ci 0.00E+00 0.00E+00 0.00E+00 6.18E-03 XE-135 Ci 5.45E+00 4.14E+00 0.00E+00 5.58E-03 XE-135M Ci 6.55E+00 1.23E+00 0.00E+00 0.00E+0Q_

AR-41 Ci 0.00E+00 0.00E+00 0.00E+00 1.79E-02 Total for Period Ci 1.20E+01 5.38E+00 0.00E+00 2.97E-02

2. Iodines I-131 Ci 4.43E-04 2.82E-04 0.00E+00 0.00E+00 I-133 Ci 3.89E-03 2.05E-03 0.00E+00 0.00E+00 I-135 Ci 2.58E-03 2.39E-03 0.00E+00 0.00E+00 Total for Period Ci 6.91E-03 4.73E-03 0.00E+00 0.00E+00
3. Particulates CO-57 Ci 0.00E+00 6.37E-07 0.00E+00 0.00E+00

, CO-60 Ci 9.53E-05 1.28E-04 0.00E+00 0.00E+00 ZN-65 Ci 0.00E+00 9.97E-06 0.00E+00 0.00E+00 CS-137 Ci 4.68E-05 7.23E-05 0.00E+00 0.00E+00 CE-141 Ci 1.79E-06 0.00E+00 0.00E+00 0.00E+00 SR-89 Ci 8.47E-06 2.79E-06 0.00E+00 0.00E+00 SR-90 Ci 5.82E-10 5.24E-08 0.00E+00 0.00E+00 Total for Period Ci 1.52E-04 2.14E-04 0.00E+00 0.00E+00

/ Page 7 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPOPT Period : Jan - Jun 1997 Table 2A Liquid Effluents - Summation of all Releases Units 1st Qtr 2nd Qtr Est. Total Error. %

A. Fission & Activation products

1. Total Release (not including tritium, cases, aloha) Ci 0.0GP+00 0.00E+00 0.00E+00
2. Avc Diluted Concentration uci/ml 0.00F.+00 0.00E+00 B. Tritium
1. Total Release Ci 0.00E+00 0.00E+00
2. Ava Diluted Concentration uci/ml 0.00E+0.Q_l 0.00E+00 0.00E+00

-C. Dissolved and Entrained Gases

1. Total Release Ci 0.00E+00 0.00E+00
2. Ava Diluted Concentration uci/ml 0.00E+00 0.00E+00 l 0.00E+00 D. Percent Qtrly Tech Spec Reporting Level
1. Whole Body Dose  % 0.00E+00 0.00E+00 2, Orcan Dose  % 0.00E+00 0.00E+00 E. Gross Alpha Radioactivity l 1. Total Release Ci l

1 0.00E+00 1 0.00E+00 l 0.00E+00 l lF. Volume of Waste Released l Liters I 0.00E+00 l 0.00E+00 1 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 Continuous Mode Batch Mode Nuclides Released Unit 1st Otr I 2nd Otr 1st Otr l 2nd Otr None Released This Period

/ Page 8-EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jan - Jun 1997 Table 3 Solid Waste and Irradiated Fuel Shipments A. Solid Waste shipped Offsite for Burial or Disposal (not' irradiated fuel)

1. Type of Waste Units 6-month Est. Total Period Error. %
a. Spent resins, filter sludges, Cu. Meter 0.00E+0L evaporator bottome, etc. Ci 0.00E+00 0.00E+00
b. Dry compressible waste, Cu. Meter 7.17E+00 l contaminated eauipment. etc. Ci 6.62E+00 3.50E+01 l c. Irradiated components, Cu. Meter 0.00E+00 control rods, etc. 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 mayor nuclide composition (by type of waste)

! Type A Type B Type C Type D l Nuclide percent percent percent percent L

H-3 1.39E-01 C-14 3.29E-02 Mn-54 3.69E+00 Fe-55 5.59E+01 Co-57 5.28E-02 Co-60 2.51E+01 Ni-63 6.49E-01 Zn-65 1.11E+01 Sr-89 1.19E-02 Sr-90 4.09E-02 Sb-125 8.06E-02 Cs-134 5.18E-02 Cs-137 2.54E+00 Ce-144 7.66E-02 Pu-238 1.40E-02 Pu-239 8.99E-03 Am-241 2.60E-02 Pu-241 2.35E-01 Cm-242 1.99E-03 Cm-243 1.10E-02

_J

. Page 9 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jan - Jun 1997 Table 3 Solid Waste and Irradiated Fuel Shipments

3. Solid waste disposal Number of Mode of Destination Shioments Transportation 3 Truck Chem-Nuc Inc., Barnwell, SC.

B.-Irradiated Fuel Shipments

1. Disposition Number of Mode of Destination Shioments Transoortation None This Period C. Shipping container and Solidification Method No, Volume Activity Type of Container Solidification M3 Ci Wae Code Code 9706 5.02E+00 6.59E+00 1 A N 96-64 8.55E-01 2.00E-02 E L N 9716a 1.29E+00 1.18E-02 B L N 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

. c

(

Attachment B Effluent and Waste Disposal Semi-Annual Report for the Period of January - June,1996 (The attached Report contains 10 pages.)

9 t

8/26/91 JR3 Ji\ LICENSE \PER10CIC.RPTTEFF,RPT.971

NORTHERN STATES POWER COMPANY MONTICELLO NUCLEAR GENERi\ TING PLANT License No. DPR-22 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jan - Jun 1996 Supplemental Information

1. Regulatory 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, Particulates, and Tritium :

7.5 mrem / quarter dose to any organ l

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, Particulates, and Tritium :

10 CFR Part 20, Append.ix 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 i

2 EFFLUENT AND WASTE-DISPOSAL SEMIANNUAL REPORT l Period : Jac Jun 1996 i

Suppletc. ental Information (continued)

]

i

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

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

1

3. Iodines in Gaseous Effluent i

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

j 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 Gaceous 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 grose activity during planned release.

5. Batch Releases A. Liquid '
1. Number of Latch Releases 0
2. Total Ti.ne 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 ~ 2617.0 min 3.. Maximum Time Period for a Batch Release 2240.0 min
4. Average Time Period for-a Batch Release 1308.5 min
5. Minimum Time Period for a Batch Release 377.0 min

=

l Page 3

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jan - Jun 1996 Supplemental Information (continued)

6. Abnormal Releases A. Liquid
1. Humber of Releases 1
2. Total Activity Released 6.80E-07 C1 B. Gaseous :
1. Number of Releases 0
2. Total Activity Released 0.0 Ci s

Page 4 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period Jan - Jun 1996 Table 1A Gaseous Effluents - Summation of all Releases Units lat Qtr 2nd Qtr Est. Total Error. %

-A. Fission & Activation ganes

1. Total Release Ci 1.05E+02 5.24E+01 2.00E+01 l
2. Averace Release Rate uci/sec 1.33E+01 6.67E+00
3. Percent Tech Spec Qtrly Reporting Level Gamma Radiation  % 7.00E-02 2.89C-02

, Beta Radiation  % 2.82E-02 8.81E-03 B. Iodines

1. Total I-131 Release Ci 1.72E-03 2.26E-03 1.00E+01 l
2. Averace I-131 Release Rate uci/sec 2.19E-04 2.88E-04 C. articulates
1. Total Particulates Ci 3.71E-04 4.95E-04 3.00E+01 l
2. Averace Release Rate uci/sec 4.72E-05 6.30E-05
3. Gross Aloha Radioactivity C1 2.24E-06 5.76E-06 D. Tritium
1. Total Release Ci 7.59E+00 5.38E+00 1.00E+01 l
2. Averace Release Rate uci/sec 9.66E-01 6.84E-01 E. Percent--Otrly Tech Spec Reporting Levels
1. Iodines, Particulates, and Tritium  % 3.37E-01 2.59E Page 5 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jan - Jun 1996 Table 1B Gaseous Effluents - Elevated Releases i

Continuous Mode Batch Mode Nuclides Released Unit 1st Otr I 2nd Otr let Otr l 2nd Otr

1. Fission Gases KR-85M Ci 0.00E+00 2.25E-01 0.00E+00 0.00E+00 KR-87 Ci 7.88E-01 7.14E-01 0.00E+00 0.00E+00 KR-88 Ci 4.34E-01 7.66E-01 0.00E+00 0.00E+00 KR-89 Ci 2.21E+00 1.16E+00 0.00E+00 0.00E+'JO XE-133 Ci 1.66E+01 9.92E+00 0.00E+00 7.08E-03 XE-133M Ci 7.43E-02 0.00E+00 0.00E+00 0.00E400 XE-135 C1 2.57E+00 3.61E+00 0.00E+00 8.75E-03 XE-135M Ci 7.04E+00 4.67E+00 0.00E+00 0.00E+00 XE-137 Ci 4.94E+01 1.97E+01 0.00E+00 0.00E+00 XE-138 C1 1.86E+01 9.65E+00 0.00E+00 0.00E+00 AR-41 Ci 0.00E+00 0.00E+00 0.00E+00 1.18E-02 Total for Period Ci  ! 9.78E+01 5.04E+01 0.00E+00 2.76E-02
2. Iodines I-131 Ci 1.73E-04 1.02E-03 0.00E+00 0.00E+00 1-133 C1 1.04E-0? 4.57E-03 0.00E+00 0.00E+00 1-135 C1 1.55E-03 7.05E-03 0.00E+00 0.00E+00 Total for Period Ci 2.77E-03 '1.26E-02 0.00E+00 0.00E+00
3. Particulates

~ ~ '

CR-51 Ci 0.00E+00 7.32E-07 0.00E+00 0.00E+00 Mh-54 Ci 0.00E+00 4.6:E-07 0.00E+00 0.00E+00 CO-59 Ci 0.00E+00 8.73E-08 0.00E+00 0.00E+00 FE-59 Ci 0.00E+00 2.39E-07 0.00E+00 0.00E+00 CO-60 Ci 3.14E-06 4.86E-06 0.00E+00 0.00E+00 ZN-65 Ci- 8.84E-07 3.21E-06 0.00E+00 0.00E+00 CS-137 Ci 2.30E-05 9.31E-07 0.00E+00 0.00E+00 BA-140 Ci 1.06E-04 5.00E-05 0.00E+00 0.00E+00 SR-89 Ci 4.55E-05 3.94E-05 0.00E+00 0.00E+00 SR-90 C1 2.26E-07 2.10E-07 0.00E+00 0.00E+00 Total for Period C1 1.78E-04 1.00E-04 0.00E&00 0.00E+00

Page 6 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jan - Jun 1996 Table 1C Gaseous Effluents - Duilding Vent Releases Continuous Mode Batch Mode Nuclides Released Unit 1st Otr I 2nd Otr 1st Otr l 2nd Otr

1. Fission Gases XE-135 Ci 5.24E+00 1.1PE+00 0.00E+00 0.00E+00 XE-135M C1 1.70E+00 7.57E-01 0.00E&OO 0.00E400 Total for Period Ci 6.95E+00 1.94E+00 0.00E400 0.00E+00
2. Iodines I I-131 Ci 1.55E-03 1.24E-03 0.00E+00 0.00E+00 1-133 C1 1.36E-02 2.56E-03 0.00E+00 0.00E+00 1-135 Ci 3.23E-02 2.11E-03 0.00E+00 0.00E+01_,

Total for Period Ci 4.75E-02 5.92E-03 0.00E+00 0.00E+00

3. Particulates MN-54 Ci 0.00E+00 9.76E-06 0.00E+00 0.00E+00 CO-60 C1 1.22E-04 1.52E-04 0.00E+00 0.00E+00 ZN-65 C:. 1.03E-05 2.16E-04 0.00E+00 0.00E+00 CS-137 C:. 1.78E-05 1.46E-05 0.00E+00 0.00E+00 BA-140 Ci 3.43E-05 0.00E+00 0.00E+00 0.00E+00 SR-89 Ci 9.11E-06 3.13E-06 0.00E+00 0.00E+00 SR-90 Ci 8.88E-09 5.33E-08 0.00E+00 0.00E+00 Total for Period Ci 1.93E-04 3.95E-04 0.00E+00 0.00E+00

l .

  • Page. 7 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jan - Jun 1996 Table 2A Liquid Effluents - Summation of all Releases Units 1st Qti 2nd Qtr Est. Total Error. %

A. Fission & Activation products

1. Total Release (not including tritium. aases, aloha) Ci 0.00E+00 6.80E-07 0.00E+00

__ 2 . Ava Di]uted Concentration uci/ml 0.00E+00 9.91E-12 B. Tritium

1. Total Release Ci 0.00E+00 0.00E+00
2. Ava Diluted Concentration uci/ml 0.00E+00 0.00E+00 l 0.00E+00 C. Dissolved and Entrained Gases
1. Total Release Ci 0.00E+00 0.00E+00 0.00E+00 l
2. Ava Diluted Concentration uci/ml 0.00E+00 0.00E+00 D. Percent Qtrly Tech Spec Reporting Level
1. Whole Body Dose  % 0.00E+00 0.00E+00 l
2. Oraan Dose  % 0.00E+00 0.00E+00 l E. Gross Alpha Radioactivity l 1. Total Release I C1 1 0.00E+00 l 0.00E+00 1 0.00E+00 l lF. Volume of Waste Released l Liters 1 0.00E+00 l 4.25E+03 1 0.00E+00 l lF. Volume of Dilution Water Used l Liters l 0.00E+00 l 6.86E+07 l 0.00E+00 l Table 2B Liquid Effluents Continuous Mode Batch Mode Nuclides Released Unit let Otr I 2nd Otr 1st Otr 2nd Otr F-18 Ci 0.00E+00 1 6.80E-07 0.00E+00 0.00E+00 I,

m

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT i

Period : Jan - Jun 1996 Table 3 Solid Waste and Irradiated Fuel Shipments A. Solid Waste Shipped Of fsite for Burial or Disposal (not irradiated fuel)

1. Type of Faste Units 6-month Est. Total Period .Mcror, %

l

a. Spent resins, filter sludges, Cu. Meter 0.00E+00 evanorator bottoms. etc. Ci 0.00E+00 0.00E+00
b. Dry compressible waste, Cu. Meter 8.02E+00 contaminated eauinment, etc. Ci 2.88E-01 3.50E+01
c. Irradiated components, Cu. Meter 0.00E+00 control rods, etc. 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 mayor nuclide composition (by type of waste)

Type A Type B Type C Type D Nuclide nercent nercent nercent- nercent H-3 2.58E-01 C-14 3.85E-02 Mn-54 4.57E+00 Fe-55 5.16E+01 Co-57 1.47E-01 Co-58 2.18E-01 Fe-59 5.99E-01 Co-60 2.33E+01 Ni-63 1.56E+00 Zn-65 1.56E+01 Sr-89 1.94E-02 Sr-90 3.57E-02 Tc-99 2.15E-03 Sb-125 3.40E-02 I-129 6.14E-03 Cs-134 7.32E-02 Cs-137 1.53E+00 Ce-144 6.43E-02 Pu-238 5.58E-02 Pu-239 3.02E-02 Am-241 2.36E-02 Pu-241 1.44E-01 Cm-242 1.30E-02 Pu-242 6.00E-02 Cm-243 8.00E-03

. Page 9 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jan - Jun 1996 Table 3 Solid Waste and Irradiated Fuel Shipments

3. Solid waste disposal Number of Mode of Destination

.Shioments Transoortation 26 Truck Chem-Nuc Inc., Barnwell, SC.

B. Irradiated Fuel Shipments '

1. Disposition Number of Mode of Destination Shioments Transoortation None This Period C. Shipping Container and Solidification Method No. I Volume Activity Type of Container Solidification M3 Ci Waste Code Code 9464f 6.51E-01 1.26E-03 B L N 94649 2.83E-03 8.91E-04 B L N 9602a 1.67E-01 2.45b-03 B L N 9602b 2.38E-01 3.72E-03 B L N 9602c 9.63E-02 2.59E-03 B L N 9602d 3.96E-02 1.14E-03 B L N 9602e 3.68E-02 1.47E-03 B L N 9602f 1.42E-02 1.18E-02 B L N 9602g 1.70E-02 2.02E-02 B L N 9602h 2.83E-02 5.92E-03 B L N 9605a 3.14E-01 9.36E-03 B L N 9605b 6.51E-02 2.40E-03 B L N 9605c 8.50E-03 4.93E-02 B L N 9605d 9.06E-01 2.60E-02 B L N 9627a 2.27E-01 2.88E-03 B L N 9627b 2.44E-01 2.91E-03 B -L N 9627c 8.58E-01 9.74E-03 B L N 9627d 3.68E-01 2.99E-03 B L N 9627e 1.04E+00 7.71E-03 B L N 9627f 1.42E-01 1.37E-03 B L N 9638a 4.93E-01 1.83E-02 B L N 9638b 7.84E-01 3.97E-02 B L N 9638c- 8.95E-01 5.66E-02 B L N 9642a 3.79E-01 6.14E-03 B L N 9464h 2.83E-03 2.67E-04 B L N 94641 2.83E-03 4.55E-04 B L N 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

Attachment C Effluent and Waste Disposal Semi Annual Report for the Period of July - December,1996 (The attached Report contains 9 pages.)

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l 8/26/97 JR$ J2 \LICENSt\PERIOCIC.8PT\tr

s' NORTilERN STATES POWER COMPANY i MONTICELLO NUCLEAR GENERATING PLANT l License No. LPR-22 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1996 l

Supplemental Information

! 1. Regulatory Limits - Quarterly levels requiring reporting to l Nuclear Regulatory Commission 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 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)

c Page 2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1996 Supplemental Information (continued)

4. Measurements and Approximations of Total Radioactivty 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. Particulates in-Gaseous Effluent :

Continuous monitoring with particulate filters in Reactor Building I

Vent and Plant Stack exhaust streams with weekly analysis.

D. Tritium in Gaseous Effluent :

Weekly grab samples from Reactor Building Vent and Plant Stack 1 exhaust-streams.

E. Liquid Effluents :

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

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 1555.0 min
3. Maximum-Time Period for a Batch Release 1156.0 min
4. Average Time Period for a Batch Release 777.5 min

-5. Minimum Time Period for a Batch Release 399.0 min h

Page 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1996 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 t

6 k

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, eg-e---gi y .--me L--m-. -, ( ,,-u.. w-y-Mr +-

.c Page 4 e

o EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1996 Table 1A Gaseous Effluents - Summation of all Releases Units 3rd Qtr 4th Qtr Est. Total Error. %

A. Fission & Activation gases

1. Total Release Ci 9.42E+01 1.39E+02
2. Averace Release Rate uci/sec 1.18E+01 2.00E+01 l 1.74E+01
3. Percent Tech Spec Qtrly Reporting Level Gamma Radiation  % 4.47E-02 1.12E-01 Beta Radiation  % 1.47E-02 3.64E-02

-B.: Iodines

1. Total I-131 Release Ci 8.33E-04 9.29E-04
2. Averace I-131 Release Rate uci/sec 1.00E+01 l 1.05E-04_, 1.17E-04 ,

C. Particulates

1. Total Particuletes Ci 4.29E-04 3.93E-04
2. Averace Release Rate uci/sec 3.00E+01 l 5.39E-05 4 . 94 E-05
3. Gross Aloha Radioactivity Ci 7.56E-06 4.09E-Qh_

D. Tritium

1. Total Release Ci 4.67E+00 4.16E+00
2. Averace Release Rate uci/sec 5.87E-01 1.00E+01 l 5.23E-01 E. Percenc Otrly Tech Spec Reporting Levels
1. Iodines, Particulates, and Tritium & 9.96E-02 9.84E-02 j

)

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EFFLUENT AND WASTE DISPOCAL SEMIANNUAL REPORT Period : Jul - Dec 1996 Table 1B Gaseous Effluents - Ele"ated Releases l

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

1. Fission Gases KR-85M Ci 1.42E+00 3.76E+00 0.00E+00 0.00E+00 KR-87 C1 1.28E+00 3.21E+00 0.00E400 0.00E+00 KR-88 Ci 2.51E+00 7.62E+00 0.00E+00 0.00E+00 XE-133 Ci 1.66E+01 2.12E+01 0.00E+00 9.50E-04 XE-133M Ci 1.69E-01 2.54E-01 0.00E+00 0.00E+00 XE-135 C1 2.02E+01 3.94E+01 0.00E+00 5.68E-04 XE-135M Ci 5.52E+00 6.02E+00 0.00E+00 0.00E+00 XE-137 Ci 3.03E+01 3.09E+01 0.00E+00 0.00E+00 XE-138 Ci 1.48E+01 1.51E+01 0.00E+00 0.00E+00 AR-41 Ci 4.61E-02 1.62E-01 0.00E+00 2.56E-03

,_ Total for Period Ci 9.28E+01 1.28E+02 0.00E+00 4.07E-03

, 2. Iodines I-131 C1 4.89E-04 5.74E-04 0.00E+00 0.00E+00 I-133 Ci 3.75E-03 3.12E-03 0.00E+00 0.00E+00 I-135 Ci 6.136-03 4.13E-03 0.00E+00 0.00E+00 Total for Period Ci 1.04E-02 7.82E-03 A.00E+00 0.00E+00

3. Particulates CO-60 Ci 2.59E-06 3.24E-06 0.00E+00 0.00E+00 ZN-65 Ci 2.94E-07 3.99E-07 0.00E+00 0.00E+00 CS-137 C1 1.94E-06 2.00E-06 0.00E+00 0.00E+00 BA-140 Ci 1.01E-04 1.24E-04 0.00E+00 0.00E+00 SR-89 Ci 8.95E-05 7.66E-05 0.00E+00 0.00E+00 SR-90 Ci 2.03E-07 3.70E-07 0.00E+00 0.00E+00 Total for Period Ci 1.95E-04 2.07E-04 0.00E+00 0.00E+00

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i EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1996 Table 1C Gaseous Effluents - Building Vent Releases Continuous Mode Batch Mode Nuclides Released Unit 3rd Otr l 4th Otr 3rd Otr I 4th Otr

1. Fission Gases XE-135 Ci 1.37E+00 7.61E+00 0.00E400 0.00E+00 XE-135M C1 0.00E+00 3.39E+00 0.00E+0S 0.00E+00 AR-41 Ci 0.00E+00 0.00E+00 0.00E;,00 1.93E-03 Total for Period Ci 1.37E+00 1.10E+01 0.00E+00 1.93E-03
2. Iodines I-131 Ci 3.44E-04 3.55E-04 0.00E+00 0.00E+00 1-133 Ci 2.81E-03 2.99E-03 0.00E+00 0.00E+00 Total for Period Ci 3.15E-03 3.35E-03 0.00E+00 0.00E+00
3. Particulates MN-54 Ci 6.71E-06 0.00E+00 0.00E+00 0.00E+00 CO-60 Ci 1.45E-04 1.29E-04 0.00E'00 0.00E+00 ZN-65 Ci 5.42E-05 1.84E-05 0.00E+00 0.00E+00 CS-137 Ci 2.19E-05 2.54E-05 0.00E+00 0.00E+00 BA-140 Ci 0.00E+00 4.64E-06 0.00E+00 0.00E+00 SR-89 Ci 5.12E-06 8.84E-06 0.00E+00 0.00E+00 Total for Period Ci 2.33E-04 1.86E-04 0.00E+00 0.00E+00 l

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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jul - Dec 1996 Table 2A Liquid Effluents - Summation of all Releases Units 3rd Qtr 4th Qtr Est. Total Error. %

A. Fission & Activation products

1. Total Release (not including tritium, cases, aloha) Ci .0.00E+00 0.00E+00
2. Ava Diluted Concentration 0.00E+0Q_

uci/ml 0.00E+00 0.00E+00 B. Tritium

1. Total Release Ci 0.00E+00 0.00E+00 0.00E+00 l
2. Ava Diluted Concentration uci/ml 0.00E+00 0.00E+00 C. Dissolved and Entrained Gases
1. Total Release Ci 0.00E+00 0.00E+00
2. Ava Diluted Concentration uci/ml 0.00E+00 0.00E+00 l l 0.00E+00 l

l D. Percent Qtrly Tech Spec Reporting Level l Whole Body Dose

1.  % 0.00E+00 0.00E+00
2. Oroan Dose  % 0.00E+00 0.00F+00 E. Gross Alpha Radioactivity l 1. Total Release Ci l

l 0.00E+00 l 0.00E+00 l 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 G.00E+00 l Table 2B Liquid Effluents Continuous Mode Batch Mode Nuclides Released Unit 3rd otr 1 4th otr 3rd otr l 4th Otr None Released This Period

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EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT Period : Jul - Dec 1996 Table 3 Solid Waste and Irradiated Fuel Shipments A. Solid Waste Shipped offsite for Burial or Disposal (not irradiated fuel)

1. Type of Waste Units 6-month Est. Total Period Error, %
a. Spent resins, filter sludges, Cu. Meter 2.43E+01 evaporator bottoms. etc. Ci 9.71E+02 3.70E+01
b. Dry compressible waste, Cu. Meter 4.57E+00 contaminated eauinment. etc. Ci 4.03E-01 3.50E401
c. Irradiated components, Cu- Meter 0.00E+00 control-rods. etc. 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 mayor nuclide composition (by type of waste)

Type A Type B Type C Type D  ;

i Nuclide cercent oercent nercent nercent H-3. 8.90E-02 1.41E C-14 1.70E-01 2.69E-02 Cr-51 4.26E-01 Mn-54 6.82E+00 -3.15E+00 Fe-55 5.29E+01 4.28E+01 Co-57 6.65E-02 Co-58 5.77E-01 5.82E-02 Fe-59 5.16E-01 1.55E-01 Co-60 1.51E+01 1.93E+01 Ni-63 3.22E-01 7.47E-01 Zn-65 2.02E+01 1.00E+01 Sr-89 2.31E-01 1.10E-02 Sr-90 2.22E-02 3.04E-02 Tc-99 2.67E-03 Sb-124 5.41E-02 Sb-125 4.63E-02 I-129 7.75E-03 I-131 6.04E-01' Cs-134 2.22E-02 4.70E-02 Cs-137 1.69E+00 1.73E+00 La-140 7.73E-02 Ce-141 8.90E-02 Ce-144 5.85E-02 Pu-238- 2.00E-02 Pu-239 1.18E-02 Am-241 1.99E-02 Pu-241 2.37E-02 1.60E-01 Cm-242 4.41E-03 Pu-242 1.53E-02 Cm-243 8.33E-03 l

, g Page 9 s.

EFFLUENT MJD WASTE DISPOSAL SEMINiNUAL REPORT Period : Jul - Dec 1996 Table 3 Solid Waste and Irradiated Fuel Shipments

3. Solid waste disposal Number of Mode of Destination Shioments Transoortation 22 Truck Chem-Nuc Inc., Barnwell, SC.

I B. Irradiated Fuel Shipments

1. Disposition Number of Mode of Destination Shioments Transportation None This Period C.' Shipping Container and Solidification Method No. Volume Activity Type of Container Solidification M3 Ci Waste Code Code ,,

96-53 5.83E+00 7.71E+01 A A D i 96-55 5.83E+00 7.15E+01 A A D 96-58 3.41E+00 2.30E+02 A A D .

96-59 5.83E+00 6.74E+01 A A D 9605e 3.29E-01 1.12E-02 B L N 9627h 2.83E-02 1.24E-02 B L N 96279 1.302-01 3.73E-02 B L N -[

9638d 7.82E-01 3.69E-02 B L N 9638e 4.53E-01 2.36E-02 .B L N 9638f 4.81E-02 2.05E-02 B L N 9638g 4.81E-02 1.06E-01 B L N 9642b 9.63E-02 1.55E-02 B L N 9642c 2.61E-01 5.52E-03 B L N 19642d 2.01E-01 3.56E-03 B L N  ;

9651 3.41E+00 5.25E+02 A A D 9642e 9.06E-02 1.46E-02 B L N 9642f 2.83E-03 1.20h-02 B L N 9638h- 8.21E-02 2.83E-03 B L N 96381 6.80E-02 1.38E-02 B L N 9535a 9.43F-01 -4.32E-02 B L .N 9535b 6.12E 3.84E B L- N-9535c. 4.00E-01 5.55E-03 B- L N Container Codei : ~ Solidification Codes :

L - LSA C - Cement

.A -' Type A U - Urea Formaldehyde B - Type B D --Dewatering 0 - Large Quantity N - Not'Applicalble

,. - . , , - . - - . . , _ - - - _ . , -- . ~ . . . --- .- _

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