ML20087C999

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Effluent & Waste Disposal Semiannual Rept,Jul-Dec 1983
ML20087C999
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 12/31/1983
From:
NORTHERN STATES POWER CO.
To:
Shared Package
ML20087C965 List:
References
NUDOCS 8403130258
Download: ML20087C999 (9)
v • d • e


Text

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'XNGF 158, Bew. 5 Fage 1 cf 8 Botenties: Lifetime EFFLUENT AIS HASTE DISPOSAL SENI-AIDIUAL REPORT July aggggge December of 1983 8WP131 ENTAL INFCSIIATIT Facility - Er_airie Island Nuclear Cemetatina Plant Lh*M,= ph -

License Nos. - DPR-42 & DPR-60 1.

Reamisterr Limits s.

Liquid Effluents:-

1.

The dose sea 4mse camattamat, to sa individual fres radio-actiw meterials la 11(id(~gi,fl,uests released from the site shall be limited:

for the Quarter 3.0 area Total Body 10.0 aren Aav orges

~

for the Year 6.0 area Total Body 20.0 aren Amy Orgaa h.

Geseems Eff1ments:

1.

The dose rate due to radioactive materials released la saseous affluents free the site shall be limited to:

Eeble esses f500 ares /TearTotalBody S 3000 arem/ Year Skia I-131,3-3, LLP_

i 1500 area / Year Any Orgaa 2.

The dose due to radteactive gaseous effluents shall be 1 W ted tot

.Neble, Gases i 10 mrad /Qtr Games i 20 mrad /Qtr Beta

< 20 stad/ Year Gasons 1 40 mrad / Year Bete l

I-131, 5-3, LLP i 15 ares /Qtr S 30 ares / Year L

l 8403130258 840301 PDR ADOCK 05000282 R

PM

-w--.-,w

. -. --. -,..-.--...--,..--- =.--

mw.--

y.,,w---.,--,-.-,-w,--,w.

-,,..,-,---+.w,m-,w----------w,--w.m--,----

i, t

PINGP 158, Rev. 5 P ge 2 cf 8 2.

Maximus Permissible Concentrations Fission and activation gases in gaseous releases:

a.

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

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

10 CFR 20, Appendix B, Table 2, Column I Liquid Effluents for radionuclides other than dissolved or c.

entrained gases:

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

Liquid Effluent dissolved and entrained gases:

2.0E-Da pei/ml Total Activity o

3.0 Ave ~t e Energy Not applicable to Prairie Island Regulatory Limits.

4.0 Measurements 'and Approximations of Total Radioactivity Fission *and activation gases Total Geli a.

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 Gelf Nuclide Geli BATCH RELEASES a.

Liquid QTR 3 QTR 4 Number of Batch Releases l 6.00E01 6.30E01 l

Total Time Period for a Batch Release (hr) l 8.47E01 1.08[02 l

Haximum Time for a Batch Release (hr) l 1.67EoD 4.17E00 i

' Average Time for a Batch Release (hr) l 1.41E00 1.71E00 l

Minimum Time for a Batch Release (br) l 1.00E00 1.17E00 l

Ave Mississippi flow during Quarter (CFS) l 2.19E04 l

1.76E04 l

PINGP 158, Rev. 5 P ge 3 ef 8 b.

Gaseous QTR 3 QTR 4 Nember of Batch Releases l 5.00E00 l 4.00EOO l

Total Time Period for a Batch Release (br) l 4.95E01 l 1.09E02 l

Maximum Time for a Batch Release (hr) '

l 3.llE01

'I 8.08EOI l

Average Time for a Batch Release (br) l 9.90E00 2.73EOI l

Minimum Time for a Batch Relesse (hr) l 4.20E-02 l.08E-01 l

ABNORMAL RELEASES a.

Liquid QTR 3 QTR 4 Number of Batch Releases l 0.000E00 1 0.00E00 l

Total Activity Release (Ci) i 0.00EOO 0.00F,00 l

Total Tritium Release (Ci) l 0.00E00 0.00EOO l

b.

Gaseous QTR 3 QTR 4 Number of Batch Releases l 0.00E00 0.00E00 l

Total Activity Release,(Ci) l 0.00E00 0.00EOO l

4 l

e i

i

PINGP 158, Rev. 5 P;3e 4 cf 8 TABLE 1A i

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REFORT GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES UNIT l

QTR 3 l

QTR 4 lE I

I I

I l

A.

Fission and Activatien Gases l Total Release Ci l 3.84E01 1.93E01 l!2.50E01 l l Average Release Rate pCi/sec 4.88E00 2.45E00 l

l_Gasuna Dose

. _ arad 1.39E-02 6.77E-03 l

l Beta' Dose erad 5.00E-02 2.46E-02 l

! % of Gamma T.S. Limit.

1 1.39E-01 6.77E-02

~l l 1 of Beta T.S. Limit 1

2.50E-01 1

1.23E-01 l

B. ' Iodines l Total I131 Ci 7.76E-03 7.85E-04 lt2.50E01 l l Averase Release Rate pCi/sec 9.87E-04 9.98E-05 l

C.

Particulates l Total Release lCi 8.02E-06 2.26E-05 2.50E01 l l Averste Release Rate l pCi/see 1.02E-06 2.87E-06 D.

Tritium l Total Release lCi 1.78 E01 1.45E01 l 2.50E01 l l Averste Release Rate l pCi/sec 2.26E00 1.84E00 l

l Total B & C & D pCi/sec 0 2.26 EGO l

1.84E00 2.50E01 l l Dose eres 5.58E-01 8.01E-02 l % of T.S. Limit 3.72E00 5.34E-01 l

E.

Gross Alpha l Total Release lCi l 0.00E00 1

0.00E00 lt2.50E01 l l

l

PINGP 158, Rev. 5 P:8e 5 cf 8 TABLE IC EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS GROUND LEVEL RELEASES 1

CCNTINUOUS MODE BATCH MODE l

l l

l l

1 l

l NUCLIDE l UNIT l

QTR 3 I

QTR 4 l

QTR 3 l

QTR 4 l

l l

l l

l I

l 1.

Fission and Activation Gases l Er85 Ci 5.57E00 l

2.41E00 l

l Er85s Ci

-1 l

l Er87 i Ci L

l l Er88 Ci 11 l

l l<Xe133 Ci 3.15E01 1.67E01 1.07E-01 1.57E-01 l

l Xe135 Ci 8.27E-01 l

l_Xe135m Ci L

9.50E-03 l

l Xe138 Ci l

l Xe131a Ci 3.90E-01 6.89E-03 l

l Ar41 Ci 2.69E-03 l

l Xe133m Ci 4.13E-03 l

l 1

l 1

1 l

l 1

l l

l l Total Ci l

3.83E01

[

1.91E01 l

1.07E-01 1.69E-01 l

2.

Iodines l I131 Ci I

7.10E-03 1

6.72E-04 l

4.88E-06 I 7.53E-06 l

l 1133 Ci I

6,52E-04 1

1.05E-04 3.31E-07 l

l I135 Ci l

l l

l Total Ci I

7.75E-03 l

7.77E-04 l

5.21E-06 1

7.53E-06 l

CONTINUOUS MODE BATCH MODE l

l 1

l l

l l

l NUCLIDE l

UNIT l

QTR 3 l

QTR 4 l

QTR 3 l

QTR 4 l

I I

I I

I I

l 3.

Particulates i Sr89 I Ci l

l 3.56E-08 l

l l

l Sr90 i Ci l

l l

l l

l Cs134 i Ci l

l l

l l

l Cs137 l Ci l

l l

l l

l Ba-La140 i Ci l

l li l

l l CoS8 l Ci l

7.99E-07 l

2.26E-05 l

l Co60-l Ci I

7.22E-06 l

l l

l l' Total l

l Ci l

8.02E-06 1

2.26E-05 11 0.00E00 0.00E00 l

- - -.. ~. ~. ~ - - ~. ". ~. ~ ^ - ~ - ~

PINCP 158, Rev. 5 Pzge 6 cf 8 TABLE 2A EFFLUENT AND WASTE DISPOSAL SEM1 ANNUAL REPORT LlQUID EFFLUENTS - SUMMATION OF ALL RELEASES I

l l

l fg l

_3

@4 A.

Fission and Activation Products l Total Release W/O H-3, l Ci I

i l Rad Gas. Alpha l

7.87E-03 l

1.34E-02 1

2.50E01l

'(r t

-4 sci /al e

l 5.70E-13 9.44E-13 B.

Tritium l Total Release l Ci l

1.47E02 9.47E01 l !2.50E01l l Average Diluted l E '!"

l j

l Concentration l

l 1.06E-08 l

6.67E-09 l

l Total A & B pCi/ml 1.06E-08 P

6.67E-09 l

l Total Body Dose aren 9.04E-04 l

1.60E-03 l

l Critical Oraan Dose eres 1.37E-03 2.07E-03 l

l Organ LIVER l

LIVER l

l % Total Body T.S. Limit.

l 3.01E-02

[

5.33E-02 l

l % of Criti, cal Organ l

l l

l I

l T.S. Limit l

l 1.37E-02 l

2.07E-02 l

C.

Dissolved and Entrained Gases l Total Release l Ci l

9.69E-03 l

4.38E-03 l!2.50E01 l l Average Diluted l pCi/ml l

l l

l Concentration I

l 7.02E-13 l

3.08E-13 l

D.

Gross Alpha l Total Release l Ci l

0.00E00 l

0.00E00 l!2.50E01 l E.~

Volume of Was.te 4

(Prior to Dilution) l__ Liters i

3.66E07 l

3.06E07 l!2.50E01 l F.

Velume of Dilution Water l Liters l

1.38E13 l

1.42E13 l!2.50E01 l

u-..

e

..----..._......u.w..=

z..

=..

I FINGP 158 Rev. 5 F ge 7 af 8 1

TABLE 2A l

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL RPEORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES CONTINUOUS MODE BATCH MODE

'l -

l l

I I

I I

.l NUCLIBE l UNIT l

QTR 3.

l QTR 4 l

QTR 3 l

QTR 4 l

l.

I I

I I

I

._I l Sr89 C1

~

1.30E-04 l

l Sr90 Ci l

l Cs134 Ci 8.28E-05 4.78E-06 9.71E-05 l

l Cs137 Ci 7.69E-05 1.04E-05 9.22E-05 l

l 1131 Ci 4.18E-QA.

1.20E-03

3. ole,04 3.97E-05 l

l CoS8 Ci 8.33E 06 3.46E-05 5.92E-04 3.05E-03 l

l cme Ci 2.47E-05 1.30E-04 7.51E-04 l

l Fe59 Ci l

l Za65 Ci l

l Mn54 Ci

c 1.61E-05 l

!?

l Cr51 Ci l

l Zr-Nb95 Ci l

) Mo99 Ci l

l Ba-La140 Ci I

lFrom Adda=Aum Ci 2.14E-04 0.00E00 5.87E-03 8.20E-03 l

1-I I Total Ci 8.25E-04 1.23E-03 7.04E-03 1.22E-02 l

CONTINUOUS HQDE BATCH MODE l

l l

l l

l l

f.NUCLIDE.

l UNIT l

QTR 3 l

QTR 4 l

QTR 3 l

QTR 4 l

l l

I I

l l

l l Ie133 Ci 7.59E-05 3.52E-03 8.30E-03 l

7.64E-04 i

'I Ie133m Ci 3.04E-05 l

l Xe131a ci 1.28E-03 l

l Ie135 Ci 8.48E-05 1.67E-06 1.66E-05 l

.I Ir85m Ci l

l Kr85 i

ci l

l 1,Kr88 i 'Ci i

l l

l B

i i

l I

I I

1-I l

I l

l I Total l Ci I

7.59E-05 3.60E-03 l

9.61E-03 1

7.81E-04 l

I l

l

- PINGP 158, Rev. 5 P 32 8 cf 8 TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SOLID RADIOACTIVE WASTE SEMI-ANNUAL REPORT July '83 THROUGH December '83 V luise Percent Container (FT3)

Curie Quantity Radionuclides Abundance Type Quantity CEMENTED 502.5 10.93 C060 70 DOT 7A 67 WASTE C058 22 Type A CS137 1

55-Cal CS134 1

Drum MN54 1

COMPACTED 1005 1.67 Cu60 65 DOT 7A 134 TRASH C058 20 Type A CS134 4

55-Cal CS137 7

Drum MN54 4

DEWATERED 572 159.24 C060 70 Type B 5

kESIN C058 2

USA /6601/B CS134 4

HIC-121 Ft3(2)

CS137 23 Type B MN54 1

USA /6754/B HIC-80 Ft3(2)

HN-100 Series 2 Metal liner 170 Ft3(1)

M-CWAN 391.2 0.112 C060 70 TRASH.

Metal Box 4

l C058 22 (STC)

CS137 1

97.8 Ft3 CS134 1

MN54 1

SHIPMENTS 9

5-RICHLAND 4-BARNWELL TItal Volume 2470.7 FT8 lo Total Curie Content 171.95 Curies l

l

F r-TABLE 2A ADDENDUM EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES I CONTINU0tlS RELEASES I BATCH RELEASES I

l___________l_________l__________l__________l__________g__________l 1 NUCLIDE I

UNIT I

OTR 3 1

QTR 4 I

QTR 3 i

OTR 4 I

. g._____..

__g_________g__________g__________g__________l__________l l___________g

________l_________

g__________l__________l__________l l

As110m i

Ci l

i I 6.22E-04 1 3.41E-04 1 g __________g._

___l__________l_______

__g__________l__________l 1

Fe55 i

Ci l

i I 2 8BE-03 I I

l-----------l---------l----------l----------l----------l----------I I

I133 I

Ci i 1.34E-04 I i 5.75E-06 I i

- g__________

g........

g

_________g__________g__________l__________l l

Na24 i

Ci I 7.97E-05 I I

I I

g___________g_________l__________l__________l__________l__________g i

Sb124 i

Ci l

l I 2.33E-03 1 5.34E-03 I g.

_________g.________g._________g__________l__________g__________g i

Sb125 i

Ci i

l 1

I 2.45E-03 I g

__________l_________l__________l__________g___

______l..________l l

Sc47 I

Ci l

I i 1.28E-05 1 7 95E-06 i g___________g___..____g._________l__________l_________

g__________l l

Tc99m i

Ci l

I i

1 5.80E-05 l l.

___._____g.________l____

..___g....._____l__________g._________l 1

Zr97 i

Ci i

l i 1.70E-05 1 6.30E-06 i g__________.g_________g__________l_________

__________l__________g i

._________l_________l__________l_____

__________g__________l l SUB TOTAL I Ci i 2.14E-04 1 0.00E00 1 5.87E-03 1 8.20E-03 l l_ _________g.. ______l.._______

g__________g__________l__________l 9

e e

6

- -. -. *

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