ML19296D380

Effluent & Waste Disposal Semiannual Rept,Jul-Dec 1979.

ML19296D380
Person / Time
Site:	Prairie Island
Issue date:	12/31/1979
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML19296D377	List: ML19296D376 ML19296D380
References
NUDOCS 8003040485
Download: ML19296D380 (9)

Text

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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT July 1, 1979 THROUGH December 31, 1979 Supplemental Information Facility - Prairie Island Nuclear Generating Plant Licensee - Northern States Power Company License Nos. - DPR-42 & DPR-60

1. Regulatory Limits Action is required if the rate of release of radioact.ive materials, when averaged over a three-month period, is such that these quantities, if continued at the same release rate for a year, would exceed twice the design objectives. Design objectives are:

a. Fission and activation gases (and all other radioactive isotopes except halogen and particulate isotopes with half-lives greater than 8 days) in gaseous releases:

3 Qi j 1300 m /sec i i

b. Iodines and particulates with half-lives greater than 8 days in gaseous releases:

3 Qi 5 67 m /sec 1 1

c. Liquid Effluents:

1. Annual total quantity of radioactive materials in liquid waste, excluding tritium and dissolved gases, of 5 Ci per unit.

2. Annual average concentration of radioactive materials in liquid waste, prior to dilution in the Mississippi River, excluding tritium and dissolved gases, of 2 X 10-8p ci/ml.

3. Annual average concentration of tritium in liqug waste, prior to dilution in the Mississippi River, of 5 x 10 uC1/ml.

2. Maximum Permissible Concentrations

a. Fission and activation gases (and all other radioactive isotopes except halogen and particulate isotopes with half-lives greater than 8 days) in gaseous releases:

10 CFR 20, Appendix B, Table 2, Column 1 1

80030d0 W

PINGP 158 Rev. 3

2. Maximum Permissible Concentrations

b. Iodine and particulates with half-lives greater than 8 days in gaseous releases:

10 CFR 20, Appendix B Table 2 Column 1

c. Liquid Effluents:

10 CFR 20, Appendix B. Table 2, Column 2

3. Ave rage Energy Not applicable to Praf fle Island Regulatory Limits.

4. Measurements and Approximations of Total Radioactivity

a. Fission and activation gases Total Geli in gaseous releases: Nuclide Geli

b. lodines in gaseous releases Total Geli Nuclide Geli

c. Particulates in gaseous Total Geli releases: Nuclide Geli

d. Liquid Effluents: Total Gross Beta Gamma Nuclide Geli BATCli RELEASES

a. Liquid QTR 3 QTP 4 Number of Batch Releases 7.40E01 1.04E02 Total Time Period for a Batch Release (br) 1.22E02 2.58E02 Maximum Time for a Batch Release (hr) 2.91E00 6.00E00 Average Time for a Batch Release (hr) 1.65E00 2.49E00 Minimum Time for a Batch Release (hr) 1.16E00 7.67E-01 Ave Mississippi flow during Quarter (CFS) 2.47E04 2.29E04

b. Gaseous QTR 3 QTR 4 Number of Batch Releases 6.00E00 4.00E00 Total Time Period for Batch Releases (hr) 5.95E01 9.97E01 Maximum Time for a Batch Release (hr) 4.80E01 2.29E01 Average Time for a Batch Release (hr) 9.92E00 1.42E01 Funimum Time for a Batch Release (hr) 2.25E00 4.10LUU PINGP 158 ABNORMAL RELEASES Rev. 3

a. Liquid QTR 3 QTR 4 Number of Releases 0 0 Total Activity Released (C1) 0 0 Total Tritium Released (C1) 0 0

b. Gaseous QTR 3 QTR 4 Number of Releases 1.00E00 1.00E00 Total Activity Releases (Ci) 2.26E-02 3.02E01 PINCP 158 TABLE 1A Rev. 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES 4 ST TOTAL UNIT 3 QTR -- QTR -- ERROR %

A. Fission and Activation Gcses Total Release Ci 5.79E01 1.74E02 !50%

Average Release Rate pC1/sec 7.37E00 2.21E01 B. Short Lived Particulate (t1/2 < 8 days)

Total Release Ci 0 8.99E-06 50%

Average Relear.c Rate pCi/sec 0 1.14E-06 C. Tritium Total Release C1 3.48E01 3.07E01 50%

Average Release Rate pC1/sec 4.43E00 3.91E00 Total A 6 E 6 C pCi/see 1.18E01 2.60E01

% of Design Objective  % 3.59E00 2.32E00 D. Iodines Total I1?.1 Ci 1.18E-04 3.94E-04 !50%

Average Release Rate pCi/sec 1.50E-05 5. 01 E- 05 E. Long Lived Particulates 't l/2 > 8 days)

Total Release Ci 1.42E-07 1.14E-06 50%

Average Release Rate pCi/sec 1.81E-07 1.45E-07 Total D & E pCi/sec 1.52h-03 5.02E-05

% of Design Objective  % 2.27E-01 7. 42 E-01 F. Gross Alpha kotal Release ICi l 1.61E-08 l 3.80E-08 100%

PINCP 158 Rev. 3 TABI.E IB EFFLUENT AND WASTE DISPOSAL SEM1 ANNUAL REPORT CASE 0US EFFLUENTS CONTINUOUS HODE BATCH MODE NUCLIDE UNIT QTR 1 QTR 4 QTR 1 QTR 4

1. Fission and Activation Gases Kr85 Ci o O 1.30E00 0 Kr85m Ci 0 0 0 6.47E-02 Kr87 Ci 0 0 0 5.15E-01 Kr88 Ci 0 0 0 0 Xc133 Ci 0 1.31E01 5.62E01 1.51E02 Xe135 Ci 0 3.88E-01 1.52E-02 6.33E00 Xe135n Ci 0 0 0 0 Xe138 Ci 0 0 0 0 Xe131m Ci 0 0 6.09E-03 0 Ar41 Ci 0 0 0 4.18E-02 Xe133m Ci 0 0 3.62E-01 9.13E-01 Total C1 0 1.35E01 5.79E01 1.59E02

2. Iodines 1131 C1 1.10E-04 3.60E-04 0 3.35E-05 1133 C1 4.59E-04 0 0 1.27E-05 1135 Ci 0 0 0 0 Total Ci 5.69E-04 3.60E-04 0 4. 62 E-05 CONTINUOUS MODE BATCH MODE NUCLIDE UNIT QTR 3 QTR 4 QTR 3 QTR 4_

3. Particulates Sr89 Ci 0 0 0 0 Sr90 Ci 0 0 0 u Cs134 Ci 0 0 0 o Cs137 Ci 0 0 0 0 Ba-La140 Ci 0 0 0 0 CoS8 Ci 0 8.58E-07 0 0 Co60 Ci 0 0 0 0 Cd109- Ci 0 0 0 0 Sb124 Ci 0 0 0 0 Na24 Ci 0 0 0 0 C057 Ci 0 0 0 0 Cel44 Ci 0 0 0 0 Zr-ht95 Ci 0 0 0 0 Rb86 Ci 0 0 0 8.99E-06 PINGP 158 Rev. 3 TABLE IB EFFLUENT AND WASTE DISPOSAL SEM1 ANNUAL REPORT GASEOUS EFFLUENTS

3. Particulates Sr85 Ci 0 0 0 0 Mn54 Ci 0 0 0 0 Csl38 Ci 0 0 0 0 Y88 Ci 0 0 0 2.79E-07 Cel41 Ci 1. 4 2 E-0 7 0 0 0 PINGP 158 Rev. 3 TABLE 2A EFFLUENT AND WASTE DISP 0AL SDlIANNUAL REPORT LIQUID EFFLUENTS - SUNNATION OF ALL RELEASES O

UNIT QTR 3_ QTR 4__ R%

A. Fission and Activation Products Total Release W/011-3, Rad Gas, Alpha Ci 4.41E-04 7.65E-03 50 ?.

Average Diluted Concentration pCi/ml 8.32E-13 2.32E-ll

% of T. S. Annual Curie Design Objective  % 4.41E-03 7.65E-02 B. Tritium Total Release Ci 1.80E02 1.35E02 25%

Average Diluted Concentration pCi/ml 3. 40 E-0 7 4.09E-07

% of T. S. Annual Design Objective Conc  % 6.80E00 8.18E00 C. Dissolved and Entrained Gases Total Rele'ase Ci 1.77E-02 3.99E-02 150%

Average Diluted Concentration pCi/ml 3.34E-ll 1.21E-10 D. Gross Alpha C1 2. 81 E-06 1.70E-07 15 0 <.

l Total Release E. Volvec of Waste (Prior to Dilution) l liters l 3.78E07 5.49E07 225% l F. Volume of Dilution Water l liters l 5.30E11 l 3.30E11 150% j PINCP 158 Rev. 3 TABLE 2A

, EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID EFFLUENTS - SUFNATION OF ALL RELEASES Continuous Mode Batch Mode NUCLIDE UNIT QTR 1 QTR 1 QTR 1 QTR L Sr89 C1 0 0 0 0 Sr90 Ci 0 0 0 0 Cs134 Ci 0 0 0 0

~

Cs137 Ci 0 0 0 0 1131 Ci 0 0 0 1.5E-04 CoS8 Ci 0 5.15E-05 2.78E-04 2.68E-03 Co60 Ci 0 0 2.01E-05 8.73E-04 Fe59 Ci 0 0 0 4.16E-04 Zn65 Ci 0 0 0 0 Mn54 Ci 0 0 0 3.62E-05 Cr51 Ci 0 0 0 4.34E-04 Zr-Nb95 Ci 0 0 0 9. 30E- 06 Mo99 Ci 0 0 0 6.75E-05 Ba-la140 Ci 0 0 0 0 Ag110m Ci 0 0 0 0 Na24 Ci 0 0 0 0 W187 C1 0 0 0 0 Sb124 Ci 0 0 0 7. 4 8 E-04 Sr85 Ci 0 0 0 0 Cs136 Ci 0 0 0 0 Zr-Nb97 Ci 0 0 C 0 Cd109 Ci 0 0 0 0 Rb88 Cl 0 0 0 0 SN113 Ci 0 0 0 3.30E-06 1 C 9'J M Ci O O O 9.10E-05 Total Ci 0 5.15E-05 2.98E-04 5.51E-03 Continuous Mode Batch Mode NUCLIDE UNIT QTR 1 QTR i QTR 1 QTR i Xe133 C1 0 2.04E-02 1.76E-02 1.57E-02 Xe133m Ci 0 0 0 0 Xe131m Ci 0 0 0 0 Xe135 Ci 0 3.77E-03 2. 78E-04 7.10E-Ob Kr85m C1 0 0 0 0 Kr85 Ci 0 0 0 0 Kr88 Ci 0 0 0 0 Ar41 Ci 0 0 0 1. 34 E-05 PINGP 158 Rev. 3 TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMLANNUAL REPORT July 1, 1979 through December 31, 1979 Solid Waste and Irradiatted Fuel Shipments A. Solid waste shipped offsite for burial or disposal (not irradiated fuel)

1. Type of Waste Unit 6 !!onth Est. Total Period Error %

a. Spent Resi.is f

b. Dry compressible waste, contaminated ft3 0 equipment, evaporator, bottoms, etc. Ci

c. Irradiated components, control rods, ft3 0 etc. Ci

d. Other (describe) fh 0

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

a. CO-57  % 0.19 Cs-134  % 17.94 Cs-137  % 36.40 Co-58  % 11.83 Mn-54 g 2.38 Co-60 g 31.26

b.  %

c.  %

2

d.  %

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 1 Truck Barnwell, S.C.

B. Irradiated Fuel Shipments (disposition)

None