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 41 <

_ 1300 m /sec MPC g

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

Qi <

_ 67 m /sec 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.

3. Annua 1' average concentration of tritium in liqug waste, prior to dilution in the Mississippi River, of 5 X 10 pC1/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 4009090 M4,

' T n; -

, ' 's

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

a. ' Fission and' activation gases Total Geli -

in gaseous releases: Nuclide Geli

b. Iodines' in gaseous releases Total Gell 4

Nuclide Geli 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

s l l

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 1.69E-04 Xe133m C1 2.42E-02 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-Total- Ci _

2.18E-04 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 UNIT TOTAL 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~ l l

)

w

w .,

s -TABLE 2A' 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 -

S r90' Ci I l~

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 0 j ~~

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

p ,

a.- None  %

i  % +

t i  %  !'

l  !

! i

- b. Co-60' +68.1  % i do-58 ,10.8' %  !

Cs-137- f3.9 : I

Mn-54' '

! 6.2 %

Cs-134 l1.2-g l Zr-95 l 5.1-1

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

2 Nb 95

--a1 4.7 % .,

l . . - .

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 ..