Text

Effluent Semiannual Rept for Jan-June 1985
	ML20135A601
Person / Time
Site:	Prairie Island
Issue date:	06/30/1985
From:	; NORTHERN STATES POWER CO.
To:	;
Shared Package
ML20135A592	List: ML20135A590; ML20135A601;
References
	NUDOCS 8509100214
	Download: ML20135A601 (14)
	v • d • e

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PINGP 158, Rzv. 6

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Page 1 of 8 Retention: Lifetime EFFLUENT SEMI-ANNUAL REPORT JAN-1985 THROUGH JUN-1985 4

SUPPLEMENTAL INFORMATION Facility - Prairie Island Nuclear Generatina Plant Licensee - Northern States Power Company License Nos. - DPR-42 & DPR-60 A.

Reaulatory Limits 1.-

Liquid Effluents:

a.

The dose or dose commitment to an individual from radio-active materials in liquid effluents released from the site shall be limited:

for the Quarter 3.0 aren Total Body 10.0 aren Any Organ for the Year 6.0 aren Total Body 20.0 mren Any Organ 2.

Gaseour Effluents:

a.

The dose rate due to radioactive materials released in gaseous effluents from the site shall be limited to:

Noble Gases

< 500 mres/ Year Total Body 4

i 3000 meem/ Year Skin I-131, H-3, LLP 51500 arem/ Year Any Organ i

b.

The dose due to radioactive gaseous effluents shall be limited to:

Noble Gases 5 10 mrad /Qtr Gamma

< 20 mrad /Qtr Beta

< 20 mrad / Year Gamma j 40 mead / Year Beta I-131, H-3, LLP

$ 15 mres/Qtr 5 30 mrem / Year O

8509100214 850030 PDR ADOCK O y2 l

_R.

PINGP 158, Rev. 6 P ga 2 cf 8 l'

~

B.

Maximum Permissible Concentrations 1.-

Fission and activation gases in gaseous releases:

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

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

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

Liquid Effluents,for radionuclides other than dissolved or i

entrained gases:

1 10 CFR 20, Appendix B, Table 2, Column 2 4.

Liquid Effluent dissolved and entrained gases:

i 2.0E-04 pei/ml Total Activity C.

Average Energy Not applicable to Prairie Island Regulatory Limits.

O D.

Measurements and Approximations of Total Radioactivity 1.

Fission and activation gases Total Geli in gaseous releases:

Nuclide Geli 2.

Iodines in gaseous releases Total Geli Nuclide Geli 3.

Particulates in gaseous Total Geli releases:

Nuclide Geli 4.

Liquid Effluents:

Total Geli Nuclide Geli 1.0 BATCH RELEASES (Liquid)

QTR QTR 1.1 Number of Batch Releases l 7.00R01 4.40E01 l

1.2 Tdtal Time Period for a Batch Release l

l (hr.)

l 1.14E02 6.83E01 l

'1.3 Maximum Time for a Batch Release (br) l 2.91Eco 2.87Fnn I

i 1.4-Average Time for a Batch Release (br) l 1.61Foo 1.ssvnn l

1.5 Minimum Time for a Batch Release (hr) l 1.17Eco _

t.17Fnn l

1.6 Ave Mississippi flow during Quarter (CFS)l 1.86x104 3.97E04 l

4

- -.... - ~,.

FINGP 158, N:v. 6 P;Es 3 of 8 T()

2.0. BATCH RELEASES (Gaseous)

\\

QTR 1 QTR 2 2.1 Number of Batch Releases l8.00E00 1.00E00 l

2.2 Total Time Period for a Batch Release (hr) l 1.45E02 4.64E-01 l

2.3 Maximum Tim'e for a Batch Release (br) l3.68E01 4.64E-01 l

2.4 Average Time for a-Batch Release (br) l1.81E01 4.64E-01 l

2.5 Minimum Time for a Batch Release (hr) l8.43E-02 4.64E-01 l

3.0 ABNORMAL RELEASES (Liquid)

QTR 1 QTR 2 3.1 Number of Batch Releases l0.00E00 0.00E00 l

3.2 Total Activity Release (Ci) 1 0.00E00 0.00E00 l

3.3 Total Tritium Release (Ci).

l 0.00E00 0.00E00 l

4.0. ABNORMAL RELEASES (Gaseous)

J QTR 1 QTR 2 4.1 Number of Batch Releases l 1.00E00 0.00E00 l

4.2 Total Activity Release (Ci) l 2.50E-02 0.00EQQ___l O

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h i

O

navr iss, nev. o PJfa 4 cf 8 TABLE 1A EFFLUENT SEMIANNUAL REPORT GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES l

l l

l I

l UNIT l

QTR 1 l

QTR g lEST TOTAL!

I I

I I ERROR % l 5.0 FISSION AND ACTIVATION GASES 5.1 Total Release (Ci) l1.2sEn1 4.67Fnn 7.snwni l

5.2 Average Release Rate (pCi/sec) I 1_sorno

s. oar-ni 5.3 Gamma Dose (arad) l 7.85E-03 1.17v-n1 1

5.4 Beta Dose (arad) l 2. 25E-02 6.32E-03 l

5.5 % of Gamma T.S. Limit (%)

l 7.85E-02 1.37E-02 l

5.6 % of Beta T.S. Limit (%)

l 1.13E-01 3.16E-02 l

1 6.0 IODINES 6.1 Total I-131 (Ci) l 3.43E-03 1.80E-06 2.50E01 l

Ox 6.2 Average Release Rate (pCi/sec) l 4.36E-04 2.29E-07 7.0 PARTICULATES 7.1 Total Release (Ci) l~1.08E-05 0.00E00 2.50E01 l

7.2 Average Release Rate (pCi/sec) l 1.37E-06 0.00E00 t

8.0 TRITIUM 8.1 Total Release (Ci) l 1.17E01 1.47Foi 7.snvnt l

8.2 Average Release Rate (pCi/sec) l 1.49E00 1.87Fon 9.0 TOTAL IODINE PARTICULATES AND l

l l

l TRITIUM (pCi/sec) l 1.49E00 1 1.87E00 12.50E01 l

10.0 DOSE (arem) l 2.24E-01 l 2.67E-02 l

11.0 % OF T.S. LIMIT

(%)

l 1.49E00 l 1.7RF-n1 l

4 12.0 GROSS ALPHA 12.1 Total Release, (CL) l 0.00E00 l9.82F-n7 l 2.50E01 l

FinGP 153, Nev. @

Pcge 5 ef 8 TABLE IC EFFLUENT SEMIANNUAL REPORT GASEOUS EFFLUENTS GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE I

I I

I l

l NUCLIDE l UNIT l

QTR_L.

l QTR_2_

l QTR_L I

QTR_2_ -

l l

l I

13.0 INDIVIDUAL FISSION AND ACTIVATION GASES l Kr85 Ci 1.i?vnn l

l Kr85a Ci R 04v-oa l

l Kr87 Ci

?.o6r na l

l Kr88 Ci 1.32E-03 l

l Xe133 Ci 9.91E00 3.55E00 2.54E00 l

l Xe135 Ci 1.15E-02 l

l Xe135m Ci 1.60E-04 l

l Xe138 Ci l

l Xe131m Ci l

l Ar41 Ci 4.49E-03 l

l Xe133m Ci l

l I

I I

l Total Ci 9 olvnn a.67pnn 7.q6Fnn n_nnynn l

14.0 I0 DINES (Ci) l 1131 Ci 3.43E-03 1.80E-06 l

l I133 Ci 5.24E-05 l

l I135 Ci l

l Total Ci 3.48E-03 1.80E-06 n.nnynn n.nnynn l

CONTINUOUS MODE BATCH MODE I

I I

I NUCLIDE l UNIT l

QTR 1 l

QTR_2, l

QTR_1_

l QTR_.2.

l I

I I

15.0 PARTICULATES (Ci) l Sr89 Ci l

l Sr90 Ci l

l Cs134 C1 1.28E-06 l

l Cs137 Ci 1.38E-06 l

l Ba-La140 Ci l

l CoS8 Ci 4.80E-06 l

l Co60 Ci 1.27E-06 l

5.00E-07 1.57E-06 l

l l Total Ci 5.00E-07 0.00E00 1.03E-05 0.nnynn l

Particulate activity (C1) from attachment Ill

FINGY 133, M;V. O

)

4 P:ge 6-ef 8 j

i TABLE 2A i

EFFLUENT SEMIANNUAL REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES UNIT l

QTR 3 l

QTR_2--

l l

l lE R%l 16.0 VOLUME OF WASTE (Prior to Dilution) l Liters 1 6.43E07 l 5.39E07 l?.snFni l

17.0 VOLUME OF DILUTION Water'(liters) l Liters l 1.03E11 l 8.14E10 12.50E01 l

18.0 FISSION AND ACTIVATION PRODUCTS 18.1 Total Release W/0 H-3, (C1) l l

l l

Rad Gas, Alpha l6.20E-03 2.19E-03 2.50E01 l

18.2 Average Diluted (pCi/ml) l Concentration l 6.02E-11 l 2.69E-11 l

19.0 TRITIUM i

19.1 Total Release (Ci) l 1.48E02 '

1.79E02 2.50E01 l

19.2 Average Diluted (pCi/al) l 1.44E-06 Concentration l

l 2.20E-06 l

20.0 DISSOLVED AND ENTRAINED GASES 20.1 Total Release (Ci) l 4.46E-03 1.84E-03 2.50E01 l

20.2 Average Diluted (pCi/ml) l Concentration l 4.33E-11 l 2.26E-11 l

21.0 GROSS ALPHA 21.1 Total Release (Ci) l0.00E00 l 0.00E00 12.50E01 l

.1 22.0 TOTAL TRITIUM, FISSION AND ACTIVATION PRODUCTS (pCi/al) l 1.44E-06 l 2.20E-06 12.50E01 l

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,.-,----,,,,m

PINCP 158, Rev. 6 4;

i Page 7 of 8 I

TABLE 2A EFFLUENT SEMIANNUAL REPORT LIQUID EFFLUENTS - SUMMATION OF-ALL RELEASES i

UNIT l

QTR 1 I

QTR 2 I

i l

l ERR R % I 4

23.0 TOTAL BODY DOSE (area) l 1 air _n3 l A_ur_nA l

24.0 CRITICAL ORGAN DOSE (arem) l 1.62E-03 4.50E-04 l

(organ) l tiver 1.iver l

s 25.0 % TOTAL BODY T.S. LIMIT (%)

l 4.03E-02 l 1.45E-02 l

26.0 % OF CRITICAL ORGAN

(%)

l l

l T.S. Limit l 1.62E-02 l 4.50E-03 l

4 4

e i

i

l i

O i

t I

PINGP 158, Rev. 6 Page 8 of 8 TABLE 2A EFFLUENT SEMIANNUAL RPEORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES

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CONTINUOUS N0DE BATCH MODE I

l l

l 1

l NUCLIDE l UNIT l

QTR 1 l

QTR 9 l

QTR i l

QTR2 l

l l

l 27.0 INDIVIDUAL LIQUID EFFLUENT l Sr89 Ci l

l l Sr90 Ci

~

2.84E-05 6.10E-07 l

l Cs134 Ci l Cs137 Ci 1.90E-04 2.50E-05 l

l I131 Ci l

l CoS8 Ci 8.62E-04 1.59E-04 1_72E-n't 1.6%F-OA l

l Cc60 Ci 4.48E-04 3.51E-04 3.29E-04 l

p l Fe59 Ci l

Zn65 Ci l

Q l Mn54 l

Ci 8.34E-05 6.76E-06 l

l Cr51 Ci l

l Zr-Nb95 Ci 4.07E-05 l

l Mo99 Ci l

l Ba-La140 Ci l

l Ci 3.75E-04 0.00E00 2.07E-03 1.53E-03 l

l l

l Total Ci 1.88E-03 1.59E-04 4.32E-03 2.03E-03 l

Individual Liquid Effluent Activity from Attachment #1 CONTINUOUS MODE BATCH MODE l

l l

l 1

l NUCLIDE I UNIT l

QTR 1 l

QTR 2 l

QTR 1 l

QTR 2 l

l l

I I

l I

I 28.0 DISSOLVED AND ENTRAINED GASES l Xe133 Ci 1.71E-04 3.30E-03 1.84E-03 l

l Xe133m Ci l

l Xe131m Ci l

q l Xe135 Ci 2.99E-05 3.18E-06 l

jl Kr85m Ci l

l Kr85 Ci 9.64E-04 l

l-Kr88 Ci l

l l

l Total Ci 1.71E-04 0.00E00 4.29E-03 1.84E-03 l

ATTACHMENT 1 ADDITIONAL NUCLIDES g

\\

GASEOUS EFTLUENTS CONTINU0US MODE BATCH MODE NUCLIDE UNIT QTR 1 QTR 2 QTR 1 QTR 2 l_________l____l____________g____________l____________l____________l i Ga-72 l Ci l l

l 8.06E-07 l

l h

-l_________l____l____________l____________l____________l____________l l Mn-54 l Ci-l l

l 7.61E-07 l

l l_________l____l____________g____________l____________l____________l l Se-75 i Ci l 5.00E-07 l

l l

l l_ g ____i g_li____________l____________l____________l____________;

____________l____________l____________l____________l l_________g____

I Subtotall Ci l 5.00E-07 l

0.00E00 l

1.57E-06 l

0.00E00 l

l_________i____l____________;____________l____________l____________l LIQUID EFTLUENTS ~

CONTINUOUS MODE BATCH MODE NUCLIDE. UNIT QTR 1 QTR 2 QTR 1 QTR 2

~

i_________g____l____________l____________l____________l____________i l Ag-ilon l Ci l l

l 9.03E-05 l

8.62E-04 l

l_________l____l____________l____________l____________l____________l l Cs-136 l Ci l l

l l

5.17E-05 l

g_________g____l____________l____________;____________i____________l l Ga-72 l Ci l l

l 8.83E-05 l

l l_________l____l____________;____________l____________l____________i l fB-97 l Ci l l

l 7.10E-07 l

l

_________g____i____________l____________l____________l____________l l Sb-124 l C1 l l

l 1.43E-03 l

1.20E-04 l

l_________l____l____________l____________l____________ ____________l g ________l____l____________g____________;__________

l Sb-125 l Ci l 3.75E-04 l

l 4.61E-04 l

1.90E-04 l

l Sc-47 i Ci l l

l 1.50E-06 l

l i_________i____i____________l____________l____________l____________l l Sr-92 l Ci l l

l l

2.66E-04 l

l_________l____l____________l____________l____________l____________l l Zr-97 l Ci-l l

l l

3.66E-05 l

l__Js:U____i. 9 _g____________l____________l____________g___________l

_______l____

g_

l____________l____________l____________l____ _______l

, Subtotall Ci l 3.75E-04 l

0.00E00

_l 2.07E-03 l

1.53E-03 l

_________l____l____________l____________l____________l____________l i

r

A PINGP 753, Rev. 1 V Retention:

Lifetime l

Page 1 of 5 i

PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period:

1-1-85/7-1-85 NORTHERN STATES POWER License No. DPR-42 l

SOLID RADIOACTIVE WASTE DISP.OSAL SEMI-ANNUAL REPORT Table I:

Solid Waste and Irradiated Fuel Shipments A.

Solid Waste Total Volumes and Measured Curie Quantities:

1.

Type of Waste:

Container Units Total Volumes A.

Resins Ft3 818 170/3 @ 76 Ci 388.254 1 @ 8C B.

Dry Compacted Ft3 2577 7.5 x

Ci 2.106 C.

Non Compacted Ft3 1862 98 Ci

.1 D.

Wst. Concentrates Ft3 493 7.5 i

ci 8.796 l.

1 i

i 1

l lO l

l l

w

.o,

PINGP 753, Rev. 1 Retention:

Lifetime Page 2 of 5

('~)

^

V PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 1-1-85/7-1-85 NORTHERN STATES POWER License No. DPR-42 1

4 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT Table I:

Solid Waste and Irradiated Fuel Shipments (Continued) 2.

Measured Major Nuclide Composition by Type of Waste:

{

TYPE (From Page 1)

Nuclide Percent i

l A

Co6o 60

. N 163.___

26.2 l

Cs137 5.1 Co58 4.1 Cal 34 3.0 4

()

.r-f

~

l B

Fe55 23.8

~-

N163 J16.0 1

Co58

~18.1 Co60

_13.7 Cs137 12.3 Cal 34 9.5

__NB95 1.7 Mn54 1.6 Zr95 1.1 1

i

(~

(.

= Inferred - Not Measured on Site

PINGP 753, Rev. 1 Retention:

Lifetime p

Page 3 of 5 U

q PRAIEIE ISLAND NUCLEAR GENERATING PLANT Period: 1-1-85/7-1-85 NORTHERN STATES POWER License No. DPR-42 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPOR.T

~

Table I:

Solid. Waste and Irradiated Fuel Shipments (Continued) i 2.

Measured Major Nuclide Composition by Type of Waste i

(Continuation):

i TYPE (From Page 1)

Nuclide Percent i

i C

Fe55 41.2 Ni63 22.9 Co60 11.4 Co58 8.2 Zr95 3.4 i

NB95 5.4 Mn54 1.7 Agl10 1.2 Cr51 1.2 i

1 t

D Fe55 25.0 i

Co60 19.2 I

l Ni63 16.9 Cal 37 14.9 Cal 34 12.4 i

Co58 6.1 I

Agl10 3.2 Mn54 2.2 i

d i

/

I j b

= Inferred --Not Measured on Site a

PINGP 753, Rev. 1 Retention:

Lifetime Page 4 of 5 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Perm 1-1-85/7-1-85 i

NORTHERN STATES POWER Lie

<..se No. DPR-42 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT Table 1:- Solid Waste and Irradiated Fuel Shipments (Continued)

)

3.

Solid Waste Disposition:

i i

Number of Shipments Mode Destination j

9 Truck Richland 1

3 Truck Barnwell l

i I

i B.

Irradiated Fuel Shipments:

Number of Shipments Mode Destination None l

1 i

e i

4 9

l

PINGP 753, Rev. 1 Retention:

Lifetime Page 5 of 5 v

PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 1-1-85/7-1-85 NORTHERN STATES POWER License No. DPR-42 SOLID RADIOACTIVE WASTE DISPOSAL SEMI-ANNUAL REPORT Table I:

Solid Waste and Irradiated Fuel Shipments (Continued)

C.

Shipping Container and Solidification Method:

No.

Volume Activity Type of Container Solidify (Ft3)

(Ci)

Waste Code Code 85-01 1078 0.069 C

L 85-12 630 0.448 B

L 85-12 98 0.002 C

L 85-14 76 126.563 A

B 85-13 76 128.545 A

B 85-15 420 0.701 B

L 85-15 210 0.701 D

L C

85-15 98 0.001 C

L 85-17 270 0.098 B

L 85-17 196 0.020 C

L O

85-17 178 0.905 D

L C

85-17 80 0.315 A

L 85-20 170 0.793 A

A B'P2F 196 0.006 C

L 85-21 893 0.632 B

L 85-22 105 7.190 D

L C

85-23 170 9.750 A

A 85-24 170 0.188 A

L 85-24 196 0.002 C

L 85-24 364 0.227 B

L 85-19 76 122.100 A

B CONTAINER CODES:

L = LSA A = Type'A B = Type B Q = Large Quantity SOLIDIFICATION CODES:

C = Cement TYPES OF WASTE:

A = Resins B = Dry Compacted O

C = Non-Compacted f)

D = Wst. Conc.

S = Spent Fuel

ML20135A601

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