ML19341C615

Effluent & Waste Disposal Semiannual Rept for Jul-Dec 1980

ML19341C615
Person / Time
Site:	Prairie Island
Issue date:	02/27/1981
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML19341C609	List: ML19341C608 ML19341C615
References
NUDOCS 8103030835
Download: ML19341C615 (9)

Text

_ _ _

EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL RE? ORT July 1, 1981 THROUGH December 31. 1981 SUPPLEMENTAL INFORMATION Facility - Prairie Island Nuclear Generating ?lant Licensee - Northern States Power Cocoany License Nos. - DPR-42 & DPR-60 1.

Reculatory Limits Action is required if the race of release of radioactive materials, when averaged over a three-month period, is such tha: these quantities, if continued at the same relea.5e rate for a year, would exceed twice the design objectives. Design objectives are:

a.

Fission and activation gases (and all other radioac:ive isotopes except halogen and particulate isotopes wi:h half-lives greatar than 8 days) in gaseous releases:

3 i

01 1

1300 m /see 1MPC.,

b.

Iodines and particulates with half-lives greater :han 8 days in gaseous releases:

01 1

67 m /sec

. MP C, 1

c.

Liquid Effluents:

1.

Annual total quantity of radioactive =aterial in liquid waste, excluding triciu= and dissolved gases, of 5 Ci per unit.

2.

Annual average concentration of radioactive =aterial in liquid waste, prior to dilution in the Mississgppi River, excluding

ri:1us mad dissolved gases, of 2 I 10 aci/=1.

3.

Annual average concentration of tritium in liquid waste, prior to dilution in the 1Essissippi River, of '5 X 10~ ;C1/al.

2.

Maximum Permissible Concentrations a.

Fission and activation gases (and all other radioactive isotopes except halogen and particulate isotopes with half-lives greater than 3 days) in gaseous releases:

10 CFR 20, Appendix 3, Table 2, Column 1

, 1 8103030635

PINGP 158 Rev. 3 2.

Maximum Permissible Concentrations i

b.

Iodine and particulates wi.,1 half-lives greater than 8 days in gaseous releases:

10 CFR 20, Appendix B. Table 2, Colunm 1 c.

Liquid Effluents:

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

3.

Average Energy Not applicable to Prairie Island Regulatory Limits.

4.

Measurements and Approximations of Total Radioactivity-a.

Fission and activation gases Total Geli in gaseous releases:

Nuclide Geli b.

Iodines 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 4

BATCH RELEASES 3

0 a.

Liquid QTR QTR Number of Batch Releases 1.12E02 i

5.0E01 l

Total Time Period for a Batch Release (hr) 1.68E02 7.8E01 Maximum Time for a Batch Release (hr) 2.4E00 2.8E00 Average Time for a Batch Release (hr) 1.30E00 1.36E00 Minimum Time for a Batch Release (hr) 0.0E-01 1.0E00 Ave Mississippi flow during Quarter (CFS) 9.58E03 S.33E03 b.

Gaseous QTR 3 QTR 4 l

Number of Batch Releases 4E00 l

1E00 Total Time Period for Batch Releases (hr) 9.o9E01 3.36E01 Maximum Time for a Batch Release (hr) 4.36E01 3.58E01 4.44E01 3.3dE01 Average Time for a Batch Release (hr)

Minimum Time for a Batch Release (hr)

6. 2 E00 3.3dE01 l

4 1

l l e.

s

~

9. m

&+w r

m y.-

+e=,-

g gwg q

p.w g

,-u.yg9

P!NGP 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

1 Total Activity Releases (C1) 7.16E-01 Z.63E-UL h

m 9 - - _ _ _ _ _ - _ _ _ - _ _ _ _ - _ _ _ _

PINGP 158 TABLE lA Rev. 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT l

GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES UNIT QTR _3_

QTR 4 A.

Fission and Activation Gases rotal Release Ci 9.67E01 2.52E00

+ 50%

IAverage Release Rate pCi/sec l.23E01 3.21E-01 B.

Short Lived Particulate ( t /2 < 8 days) 1 Total Release C1 2.32E-05 0

1 307.

Average Release Rate-121/sec 2.95E-06 0

C.

Tritium Total Release Ci 2.87E01 1.24E01 I 307.

Average Release Rate pCi/sec 3.65E00 1.58E00 Total A & B & C luCi/sec 1*? N 1 t*N9k

"3LUU o*oVL-U'

% of Design Objective l%

D.

Iodines i

7 Total 1131 Ci 1.50E-03 2.56E-06

_ JUL Average Release Rate pCi/sec 1.91E-U4 J.zbE-U/

j E.

Long Lived Particulates ( t1/2 > 8 days)

Total Release Ci 8.34E-06 3.23E-06 I

t 50%

Average Release Rate

'Ci/sec 1.06E-06 4.11E-O' l

l Total D & E pCi/sec 1.91E-04 7.37E-07

% of Design Objective

2. 82 E00

3. 6 3E-0 3 F.

Gross Alpha 4

l Total Release lCi l

3.03E-08 1

0 l

' 100%

l PINGP 158 Rev. 3 TABLE IB EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT GAEEOUS EFFLUENTS CONTINUOUS MODE BATCH MODE l

NUCLIDE UNIT QTR 1 QTR _4'_

QTR 1 QTR 1 f

1.

Fission and Activation Gases Kr85-Ci Kr85m C1 1.38E-02 Kr87 C1 1.09E-02 Kr88 C1 1.77E-02 Xel33~

Ci 7.96E01 1.70E91 2.64E-01 Xel35 Ci 9.81E-03 Xel356 Ci Xel38' Ci 7.27E-03 Xel31m Ci Ar41 Ci 4.14E-03 Xel33m C1 2.26E00

.otal Ci 7.96E01 2,26E00 1.71E01 2.64E-01 2.

Iodines 1131 C1 1.48E-03 2.56E-06 1.67E-05 1133 C1 4.18E-06 1135 Ci Total Ci

1. 4 8E-0 3 2.56E-06 2.09E-05 0

CONTINUOUS MODE BATCH MODE NUCLIDE UNIT QTR l QTR _4_

QTR 1 QTR 4_

3.

Particulates l

Sr89 Ci i

Sr90 Ci i

Cs134 Ci j

Csl37 Ci i

Ba-La140 Ci

{

CoS8 C1 1.51E-06 3.23E-06 l

Cc60 C1 6.83E-06 Cd109 -

Ci Sbl24 Ci

'Ta24 Ci

.o57 C1 Cel44 Ci Zr-Nb95 Ci Rb86 C1 o

PINGP 158 Rev. 3 TABLE IB EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS 3.

Particulates Sr85 Ci 0

0 0

0 4 -

Mn54 ci 0

0 0

0 Cs138 Ci 0

0 0

0 Y88-Ci 0

0 0

0 4

4 1

i l

\\

1 e

i i l l

lt --,.. -

i, PINGP 158 Rev.

3 IABLE 2A EFFLUENT AND WASTF. DISP 0AL SEMIANNUAL REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES UNIT QTR QTR 4_

f0RR A.

Fission and Activation Products 1

en.

J Total Release W/0 H-3, Rad Gas, Alpha C1 2.42E-03 7.42E-03

-- '"~

Average Diluted Concentration

' pci/ml 1.19E-ll 4.34E-11

% of T. S. Annual Curie Design Objective 2.42E-02 7.42E-02 3.

Tritium Total Release Ci 1.80E02 1.01E02 I 25's ~~

Average Diluted Concentration uCi/ml 8.87E-07 5.91E-07

% of T. S. Annual Design Objective Conc 1.77E01 1.18E01 C.

Dissolved and Entrained Gases I 50%

Total Release Ci 3.12E-02 6.08E-04 3.56E-12 Average Diluted Concentration uCi/ml 3_, 5 g g_3 n J.

Gross Alpha I 100%

l j

Total Release lCi 6.85E-07 l 4.10E-07 l

E.

Volume of Waste (Prior to Dilution) l liters l 5.40E07 l 6.28E07 l

- 25%

l l

F.

Volume of Dilution Water l 11ters l 2.03 Ell l 1.71 Ell l

- 50%

i NOTE: Quarter 3 and 4 fission and activation products higher than isotopic analysis dua to sample line crud deposition which was residual from primary to secondary leak.

i a

j e

l _

PINGP 158 Rev. 3 TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELFASES Continuous Mode Batch Mode 4

4 NUCLIDE UNIT QTR j3_

QTR_4__

QTR _3__

QTR __

Sr89 C1 3.58E-06 Sr90 C1 1.aat-v]

Csl34 Ci Cs137 C1 3.86E-05 3./4E-U)

I131 C1 1.25E-04 2.oVE-U)

Co38 Ci 6.55E-04 9.93E-05 3.)UE-04

/.oVb-v)

Co6C Ci 7.79E-05 8.57E-04 6.43E-04 z.coc-u4 Fe39 Ci Za65 Ci Mn54 C1 2.83E-05 4.20E-04 3.UUE-Ua 1.646-U)

Cr51 Ci Zr-Nb95 Ci Mo99 Ci Ba-lal40 Ci Agl10m Ci Na24 Ci W187 Ci 4

'O'-U3

.bl24 -

Ci Sr85 C1 Cal 36 Ci Z r-Nb 9 7 C1 Cd109 Ci Rb 88 C1 Ce-139 C1 1.246-U)

Ce-144 Ci 1.70E-Ch Total C1 9.18E-04 1.38E-03 1.32E-03 5.56E-04 Continuous Mode Batch Mode 4

NUCLIDE UNIT QTR _,3_

QTR 4__

QTR __3 QTR _

f Xel33 C1 1.80E-04

3. 06 E-02 5.60E-04 l

Xel33m Ci Xel31m Ci 1.04E-03 Xel35 Ci 2.33E-04 4.78E-05 Kr85m Ci l

Kr85 Ci KrS8 Ci l.

a PINGP 158 Rev. 3

?

[k TABLE 3 l

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

\\

n Julv 1. 1980 through December 31. 1980 l

Solid Waste and Irradiatted Fuel Shipments 1

4 A.

Solid. waste shipped offsite for burial or disposal (not irradiated fuel) 1.

Type of Waste Unit l 6 Month Est. Total I Period Error %

l 544 a.

Spent. nesins ftJ 150 Ci b.

Dry compressible waste, contaminated ft3 4779 equipmert. evaporator, bottoms, etc.

C1 23.9 i

c.

Irradiated components, control rods, ft3 etc.

Ci None d.

Other (describe) fh y_

f f

2.

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

Co60 65 g I

a.

j CoS8 16.35%

j Cs137 15.25 l

j Misc (Ag110m, Csl34, Zr95) 3.4 l

g 4

l l

4

]

Co60 56. 56.y l

o.

CoS8 l

i 15.10%

l Cs137

,13,9 ;

l Misc ( Csl34. Mn54. Etc.)

13.44%

i i

I J

c.

4 l

d.

I 1

3.

Solid Waste Disposition i

Number of Shipments Mode of Transportation Destination

}

'3 Truck Barnwell. SC j

10 Truck Richland. WA i

B.

Irradiated Fuel Shipments (disposition) i >

1 I

...... ~..

., - -.