ML19242D264

Effluent & Waste Disposal Semiannual Rept for Jan-June 1979

ML19242D264
Person / Time
Site:	Prairie Island
Issue date:	06/30/1979
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML19242D258	List: ML19242D257 ML19242D264
References
NUDOCS 7908140765
Download: ML19242D264 (9)

Text

.s .

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January 1,1979 THROUGH June 30, 1979 .

Supplemental Information Facility - Prairie Island Nuclear Generating Plant Licensee - Northern States Power Conpany License Nos. - DPR-42 DPR-60

1. Regulatory Limits Action is required if the rate of release of radioactive materials, when averaged over a three-mont'n period, is such that these quantities, if continued at the same release rate for a year, would exceed twic,e the design objectives. Design objectives are:

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

O i 1 1300 m /sec MPC i

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

Oi 1 67 m /sec MPC 1

c. Liquid Effl~:ents:

1. Annual total quantity of radioactive materials in liquid waste, exclusing 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 10-8 uCi/ml.

3. Annual average concentration of tritium in li prior to dilution in the Mississippi River, of 5 x 10 guid waste, 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:

10CFR20, Appendix B, Table 2, Column 1 , ,,

v _ :,

T 90814074d.

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. Averare Energy Not applicable to Prairie Island Regulatory Limits.

4. Measurements and Approximations of Total Radioactivity

a. Iission and activation gaces Total Geli in gescous releases: Nuclide Geli

b. Iodines in gaseous releases Total Geli Nuclide Geli

c. Particulates in gaceous Total Geli releases: Nuclide Geli

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

a. Liquid QTR 1 QTR 2 Number of Batch Releases 3.3E01  ! 7.0E01 Total Time Period for a Batch Release (hr) 4.66E01 12J2E02 Maximum Time for a Batch Release (hr) 2.50E00 3.47E00 Average Time for a Batch Relcase (hr) 1.41E00 1.60E00 Minimum Time for a Batch Release (hr) 7.50E-01 1.00E00 Ave Mississippi flow during Quarter (CFS) 9.33E03 5.27E04

b. Gaseous QTR 1 QTR 2 Number of Batch Releases 0 3.00E00 Total Time Period for Batch Releases (hr) _

0 6.72E01 Maximum Time for a Batch Release (hr) 0 3.12E01 Average Time for a Batch Release (hr) 0 , 2.24E01 Minimum Time for a Batch Release (hr) 0 1.33E01 1 -

) , ~>

• 1 '*, g

• g m _ . ', ,.

sh ,- - _ . , - with;. , . , *. .,,,*4w.?...-

e t

ABNORMAL RELEASES

a. Liquid QTR 1 QTR 2 Number of Releases -

0 0 -

.s' 1 Total Activity Released (C1) 0 0 ,

Total Tritium Released (Ci) 0 0

' b. Gaseous 1 QTR QTR 2 -

s Number of Releases 0 1.0E00 -

Total Activity Releases (Ci) 0 3.93E00 P

t .

I' ..?

F e h m*$

7 .

-e _

V D

b. -g.- ,

,w-

[*

,4 S

k I

) l i.)

~

i l'

l. \'

e

,- g. . . . . , . . - . . . . .

,

• y , _-

e , .. -

. . . yg . 4 >

TABLE LA EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES UNIT (TR 1 QTR 2 RR R A. Fission and Activation Cases rotal Release Ci 5.1]Uf01 4.14E02 t 50%

Asorage aclease Rate pCi/sec 6.54ECC . 5.27E01 i B. Short Lived Particulates (t1/2 < 8 days)

Total Release C1 -

3. 4 7E-05 50%

Average Relcace Rate pCi/sec -

4.42E-06 C. Tritium Total Release C1 2.53E01 6.54E01 50%

Average Release Rate pCijsec 3.77E00 8.41E00 Total A 6 B & C pCi/sec 9.76E00 6.10E01

% of Design objective  % 3.89E00 2.43E01 D. Iodines Total 1131 Ci 6.30E-05 3.27E-03 50%

Average Release Rate pCi/sec 8.02E-06 4.20E-04 E. Long Li';ed Particulates (t1/2 >8 days)

Total Release C1 2.91E-06 1.32E-05 1 50%

Average Release Rate pCi/sec 3.70E-07 1.68E-06 Total D 6 E pC1/sec 8.39E-06_ 4.22E-04

% of Design Objective  % 1.18E-01 6.27E00 F. Gross Alpha frotal Release Ci 8.50E-09 l 1.19E-08 100%

Note:

" " indicates that relesses were below lower limit of detection (LLD) values.

Mcximum allowed values of LLD are given in the Technical Specifications.

>< .>: ./

TABLE IB EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT CASEOUS EFFLUENTS -

CONTINUOUS MODE BATCH MODE SULLIDE UNIT QTR 1 QTR l QTR 1 QTR g__

1. Fission and Activation Gases C1 -

'O fEr85 -

l Fr85m Ci 7.41E-01 -

0 -

Er87 Ci 1.96E00 -

0 -

Kr88 Ci - -

• O -

Xe133 C1 4.07E01 3.86E02 0 2.07E01 Xe135 Ci 5.62E00 6.68E00 0 2.15E-01 Xe1356 C1 - -

0 -

Xc138 C1 - -

0 -

Xe131m C1 - -

0 -

Ar41 C1 2.41E00 0 2.01E-01 Xe133m C1 5.06E-01 0 7.03E-02 Total Ci 5.14E01 3.93E02 0 2.12E01

2. Iodines 1131 Ci 6.30E-05 3.27E-03 0 -

I133 Ci -

1.43E-04 0 -

1135 C1 - -

0 -

Total Ci 6.30E-05 3.41E-03 0 -

CONTINUOUS MODE BATCH MODE NUCLIDE UNIT QTR 1 QTR _2_ QTR 1 QTR 2_

3. Particulates Sr89' C1 -

0 -

Sr90 Ci - - 0 -

Cs134 Ci - -

0 -

Cs137 Ci - -

0 -

Ba-Lp ",0 - C1 -

- 0 -

CoS8 C1 2.06E-06 1.52E-06 0 -

Co60 Ci 8.42E-07 -

0 -

Cd109 Ci -

0 -

Sb124 C1 -

0 -

Na24 C1 -

- 0 -

C oS 7 C1 -

- 0 -

Cel44 C1 -

1.06E-05 0 -

Zr-h195' Ci -

0 -

Rb8E Ci -

0 M t.3.47E-05 s . -

me

~

TABLE IB EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS

3. Part1 ilates pf!1 C1 - . O '

C1 - . 0 fitM4 Ci _- . .o Es_L.18 YS3 C1

- - 0 8. 70E- 07 Ce139 _

C1 2.12E-07 0 .

1

.c  ! <!

.) I /

TABLE 2A EFFLUENT AND WASTE DISP 0AL SEMIANNUAL REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES UNIT '

QTR 1 QTR 2 p7 A. Fission and Activation Products Total Release W/011-3, Rad Gas, AlpM. C1 1.32E-04 7.74E-04 1 50%

Ave _rfre Diluted Concentration pC1/ml 9.71E-13 6.97E-13 ot T. S. Annual Curic Design Obj e_c_t_ive  % 1.328-03 7.74E-03 B. Tritium

~

Total Releast- Ci 6.78E01 2.42E02 25%

Averane Diluted Concentration pCi/mi 4. 9TE-07 2.18E-07

. of T. S. Annual Desig Objective Co n e_ _  % 9.98ETO 4.36E00 C. Dissolved and Entrained Cases Total Relyase C1 1.53E-02 9.81E-02 150f Average D_iluted Concentration pCi/ml 1.13E-10 8.84E-11 D. Cross Alpha

~

Total Releast Ci l l 3.60E-08 150%

E. Volume of Waste (Prior to Dilution) l lifers 4.03E07 l 4.31E07 125% l F. Volume of Dilution Water llitus l 1.36 Ell l 1.11E12 50% l 7- ,- -

n

" .; " 7 J L.;U

TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Continuous Mode Batch Mode NUCLIDE UNIT QTR l QTR 2_ QTR l__ QTR 2_

l Sr89 C1 - -

l Sr90 Ci - -

Cs134 Ci -

3.80E-06 -

Cs137 C1 -

5.60E-06 -

1131 Ci -

- 6.05E-04 CoS8 C1 -

5.79E-05 2.84E-05 Co60 C1 - 2.62E-05 1.56E-05 1.59E-05 Fe59 C1 -

Zn65 Ci -

Mn54 Ci - - - -

Cr51 C1 - - - -

Z r-Nb 95 C1 - - - -

Mo99 C1 - - - -

Ba-la140 C1 - - - -

Ag110m C1 - - - -

Na24 C1 - - - -

W187' C1 - - - -

Sb124 Ci - -

1.63E-06 -

Sr85 C1 - -

Cs136 C1 - -

Zr-ht97 Ci -

Cd109 Ci - -

Rb88 C1 - -

Cn57 C1 - -

- 5.20E-06 Total Ci -

2.62E-05 1 8.45E-05 6.55E-04 Continuous Mode Batch Mode NUCLIDE UNIT QTR l QTR __1_ QTR __2_ QTR L Xe133 C1 -

1.52E-02 9.75E-02 Xe133m Ci -

5.32E-05 2.95F-04 Xe131m C1 - . - -

Xe135 Ci - -

7.09E-05 2.57E-04 Kr85m Ci - -- - -

Kr85 C1 - _ - -

Kr88 C1 -

. ,;4 "3 s TABLE 3 ,

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Jan. 1. 1979 through June 30. 1979 Solid Waste and Irradiatted Fuel Shipments A. '~ o l i . waste abipped offs;te for b arial or disposal (not irradiated fuel)

1. Type of Waste Unit 6 Month Est. Total

~

Period Error %

.i. Spent Renins ftJ 80 + 257.

C1 19.8 -

b. inry compressible waste, contaminated ft3 558.6

• 257.

c'li: 1 pme n t , evaporator, bottoms, etc. Ci 1.2 -

e. I rratt ia ted components, contiol rods, f t ,3 NONE etc. C.

d. Other (describe) Ih NONE

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

a. CO-60  % 41.9 CO-58  % 20.4 CS-137  % 23.5 CS-134  % 9.4 2

b. CS-137  % 35.4 CS-134  % 24.2 Sh-124  % 23.4 CO-60

% 8.7 2

c. NONE  %

'I ' NONE I

- - - . . - - . . . .- L

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

1 Truck Richland Wash.

B. Irradiatet! Fuel Shipmeats (dispos ttion)

,. 'll