ML19337A211

Effluent & Waste Disposal Semiannual Rept for Jan-June 1980

ML19337A211
Person / Time
Site:	Prairie Island
Issue date:	08/28/1980
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML19337A209	List: ML19337A208 ML19337A211
References
NUDOCS 8009090302
Download: ML19337A211 (9)

Text

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EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT 1 Jan 1980 THROUGH June 30, 1980 SUPPLEMENTAL INFORMATION Facility - Prairie Island Nuclear Generating Plant Licensee - Northern States Power Company License Nos. - DPR-42 & DPR-60 1.

Regulatorv Limits Action is required if the rate of release of radioactive materials, when averaged over a three-month period, is such that these quantities, if continued at the same release race 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 MPC 1300 m /sec 41 g

b.

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

67 m /sec Qi i

i c.

Liquid Effluents:

1.

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

2.

Annual average concentration of radioactive material in liquid waste, prior to dilucion in the Mississgppi River, excluding tritium and dissolved gases, of 2 X 10 pC1/ml.

Annua 1' average concentration of tritium in liqug waste, prior 3.

to dilution in the Mississippi River, of 5 X 10 pC1/ml.

2.

Maximum Permissible Concentrations Fission and activation gases (and all other radioactive isotopes except a.-

halogen and particulate isotopes with half-lives greater than 8 days) in gaseous releases:

10 CFR 20,' Appendix B, Table 2, Column 1 4009090 M4,

' T n;

' 's

. 2. ;

Maximum Permissible ~ Concentrations b '.'. - Iodine.and particulates.with half-lives greater than 8 days in gaseous z

releases:

p t

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

Liquid. Effluents:

10 CFR 20 Appendix B,' Table 2, Column 2 3.

.-Average Energy Not applicable to Prairie Island Regulatory Limits.

4.

Measurements and Approximations of Total Radioactivity

' Fission and' activation gases Total Geli a.

in gaseous releases:

Nuclide Geli b.

Iodines' in gaseous releases Total Gell Nuclide Geli 4

j '

c.

Particulates in gaseous Total Geli releases:

Nuclide Geli

'd.-

_ Liquid' Effluents:

Total Gross Beta Gamma j

Nuclide Geli j

BATCH RELEASES a..

Liquid' QTR 1 QTR 2 Number of Batch Releases 6.40E01 4.40E01

' Total. Time Period 'for a Batch Release (hr) 1.03E02 6.62E01 Maximum Time for a Batch Release (hr) 4.20E00 2.30E00 Average Time for a Batch Release (hr) 1.61E00 1.50E00 Minimum Time. for a Batch-Release.(hr) 8.00E-01 1.00E00

' Ave Mississippi flow during Quarter (CFS) 8.36E03 1 2.08E04 b.

. Gaseous QTR l'

QTR ' Number of Batch Releases 1.00E01 3.00E00-

-Total Tine Period for Batch Releases (hr) 1.62E02 3.32E01 Maximum Time for:a Batch Release (hr) "

5.39E01 2.34E01

~

_ Average' Time for a Batch Release (hr) 1.62E01-1.11E01 Minimum Time for a: Batch Release (hr) 1.20E00 1.80E00 v

9

=

L y

,j i

1 m

...w

[. 's.

ABNORMAL' RELEASES a.

' Liquid QTR 1

QTR 2 Number of Releases 0.00E00 O.00E00

-Total Activity Released (C1) 0.00E00 i-0.00E00 Total Tritium Released (C1) 0.00E00 1 0.00E00

~b.:

[ Gaseous.

OTR 1 QTR 2 Number of Releases-0.00E00 l1.00E00

~ Total; Activity Releases (C1) 0.00E00 i1.59E-01

?

1 i

l s '

u

.~

l cr i

)7 TABLE'lA'

. EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS -'SUFJfATION OF ALL RELEASES UNIT QTR L QTR L ERR R A.

Fission and Activation Cases Total Release Ci l

1.24E02 3.69E01 1 50%

Average Release Rate pCi/seei 1.35E01 4.69E00 B.

Short Lived Particulate (t1/2 < 8 days)

Total Release ci 7.65E-04 1

4.03E-01 I. 50%

Averare Release Rate-UCi/sec 9.73E-05 1

5.13E-04 i

'C..

Tritium Total Re'1 ease Ci 3.19E01 1.33E01

2. 50%

Average Release Rate pCi/sec 4.06E00 1.69E00 i

Total A & B & C-pCi/sec 1.99E01 6.38E00 2 of Design Objective 5.26E00 1.69E00 i-D.

Iodines i

'! Total 1131 Ci 2.19E-04 4.32E-05 2; 50%

lAverage Release Rate UCi/sec 2.79E-05 5.50E-06 i

E.

Long-Lived Particulates (t1/2 > 8 days)

Total Release Ci 5.78E-05 0.00F00 d; 50%

Average Release Rate pCi/sec 7.35E 0,6 0.00E00 Total D & E-UCi/sec 3.53E-05 5.50E-06

% of Design Objective 5.271:-01 8.21E-02 F.

Gross Alpha.

' lTo tal - Re lease (Ci l'

4.97E-09

'l 1.99E-08 l d; 100%

l P

L !

L.

y, " '

TABLE 13.

~ EFFLUENT AND WASTE DISPOSAL-SEMIANNUAL REPORT GASEOUS EFFLUENTS CONTINUOUS MODE BATCH MODE NUCLIDE-UNIT;

.QTRj(,

QTRjL, QTRJ, QTR 2_, i 1.

Fission and Activation Gases Kr85-Ci t

4.71E-01 2.18E-01 Kr85m-C1

-7.76E-01 i

3.45E-04 Kr87-Ci 1.82E00 1

3.40E-04 Kr88 Ci 1.35E-04 Xe133' Ci 9.98E01 3.61E01 5.99E00 3.21E-01 Xe135-C1 4.72E00 6.13E-02 2.50E-01 Xe135'm Ci Xe138' C1 Xe131m C1-1.54E-03 Ar41 Ci 1.01E01 1.51E-02 4.49E-02 Xe133m C1 2.42E-02 1.69E-04 Total C1 1.1/EUZ 3.61E01 6.56E00 8.36E-01

' 2.

Iodines Il31 C1 2.18E-04 4.32E-05 6.77E-07 4.91E-08 1133 C1 2.03E-08 1135 Ci-2.18E-04 Total-Ci 4.32E-05 6.97E-07 4.91E-08 CONTINUOUS MODE BATCH MODE NUCLIDE.

-UNIT QTR L QTR L QTR J QTR J 3.

Particulates Sr89

'Ci Sr90-Ci-

_.^

Cs134 Ci-Cs137-

~Ci i

' ~~~'

Ea-Lal40 Ci-l CoS8 C1 3.63E-05 1 ~ ~ ' ~~~

i Co60' Ci

2.15E-05

[ "'

[,

Cd109 -

Ci s

~~

Sbl24 Ci Na24

'Ci Co57-Ci'-

Cel44 Ci Zr-Nb 9 5 '

-Ci i

Rb86-l Ci-7. 6 5 E-4 '+

i 4.03E-03 T.

+

f TABLE 13 EFFLUENT AND WASTE DISPOSAL SD1IANNUAL REPORT.

CASE 00S EFFLUENTS.

^ 3.

Particulates-Sr85 C1 i

I Mn54 C1 Cs138 Ci Y88-C1 2_RQF-OR 7

Zr-97 C1 1.65E-07 TOTAL ~'

Ci 5.80E-05 0.00F00 1

7.65v-04

&_017 n1

)

2-4 4

c

-s-

w TABLE.2A EFFLUENT AND WASTE DISP 0AL SEMIINNUAL REPORT LIQUID EFFLUENTS - SUh7ATION OF ALL RELEASES TOTAL UNIT QTR 1 QTR 1 ERROR L A.

Fission and Activation Products-To tal Release W/0 H-3, Rad Gas, Alpha Ci 1.67E-03 1.73E-03

+ 5.0E01 Averane = Diluted Concentration pCi/ml 7.70E-12 3.90E-12

% of T. S. Annual Curie Design Objective 1.67E-02 1.73E-02 1

B.: Tritium Total Release Ci 1.02E02 1.60E02

+ 2.5E01 Average Diluted Concentration pCi/ml 4.70E-07 3.60E-07 3 of T. S. Annual Design Objective Conc c%

9.40E00 7.20E00 C.

Dissolved and Entrained Gases

Total Release Ci 5.24E-03 l 3.24E-02

+ 5.0E01-Ave rage Diluted Concentration uC1/ml 2.41E-11 l 7.30E-ll D.

Gross Alph-s trotal Release (Ci i

1.22E-05 I 3.70E-09 f + 5.0E01' E..Volme of Waste (Prior to Dilution) l liters i 4.79E07 1 3.91E07

!~+ 2.5E01 F.

Volume of Dilution Water l liters i 2.17E11 1 4.44 Ell i +5.0E01

-7~

)

--we w

w

-TABLE 2A' s

EFFLUENT-AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID' EFFLUENTS --SUMMATION OF.ALL RELEASES

? Continuous Mode Batch Mode-.

NUCLIDE1 UNIT QTR L.

QTR l QTR 1 QTR Sr89 Ci I

I l~

S r90' Ci I

Cal 34 C1 -

I-Cs137 C1 R.Rav-06 1

Il31 Ci s.osv-as l'

CoS8 C1 1.33E-04 9.09E-05 8.60E-04 I

3.45E-04 Co60 C1 2.30E-04 I

-2.30E-04 1.79E-04 i

6.20E-04 Fe59 Ci i

Zn65-Ci i

I Mn54-Ci-2.22E-05 1

1.26E-04 1.07E-05 i

Cr51 Ci l

i I

l Zr-Nb95-Ci i

1.56E-05 i

9.42E-06 i

Mo99 Ci i-I j

Ba-la140 Ci-I Ag110m Ci i

i 2.98E-05 Na24 Ci t

I W187

~Ci i

i Sbl24-Ci 1

i Sr85' Ci i-Cal 36 C1 Zr-Nb97 Ci CdlC9 C1 i

Rb88

~Ci l

I To tal -'

C1 3.85E 4.56E 1.12E-03 1.00E-03 l'

Continuous Mode Batch Mode i

NUCLIDE

. UNIT

'QTR l_.

QTR 2_.

.ylk 1 QTF 2_j e

Xt133 Ci

.I 5.24E-03 3.22E-02 l-Xs133m Ci 1.34E-04 Xal31m -

Ci i

Xs135 C1' 9.03E !

Kr85m-Ci l

Kr85 Ci Kr88 C1 i

Kr87

.Ci 4.69E-06

.I,

k

rn.

- y.y

-p n

t 1

4 -

TABLE.3 EFFLUENT AND WASTE DISPOSAL SEMIA!DIUAL REPORT-1-l-80 through-6-30-80

..-Solid. Waste and Irradiatted Fuel Shipments d

. A.. ' Solid waste shipped'offsite for burial or disposal (not irradiated fuel) 1.- Type-of: Waste Unit

'6 Month Est. Total !

Period Error %

u-a.

Spent Resinsy feJ 0.

(

Ci 0-i b.

. Dry compressible. waste... contaminated ft3 12951.8' equipment, evaporator, bottoms, etc.

Ci 23.7

-+-25%

c.

=Ir:-adiated components, control rods, fc3 0

etc.

Ci 0

d.

Other (describe) lfh l j

~~

0 2.

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

p a.-

None i

+

i t

l i

- b.

Co-60'

+68.1 i

do-58

,10.8' %

Cs-137-f3.9 :

I Mn-54'

! 6.2 %

l1.2-g l

Cs-134

%.. I..- - -. --- -

l 5.1-1 Zr-95 L

2 Nb 95 1 4.7 %

l

--a I

L.

I

.i 3..

Solid-Waste Disposition

.Nu'mber of Shipments Mode of Transportation Destination 15'

_ Truck-Richland, WA

-B.

Irradiated ' Fuel-Shipments (disposition)

.9.-

1 i

2

..