ML20135A601

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


Text

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PINGP 158, Rzv. 6 ~

Page 1 of 8 ' -

, Retention: Lifetime EFFLUENT SEMI-ANNUAL REPORT 4 JAN-1985 THROUGH JUN-1985 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:

4 Noble Gases < 500 mres/ Year Total Body

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

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PINGP 158, Rev. 6 P ga 2 cf 8 -

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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 l 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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. 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 I I l l NUCLIDE l UNIT l QTR_L. l QTR_2_ l QTR_L I

QTR_2_ - l l l l l l I l 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 I I I I NUCLIDE l UNIT l QTR 1 l QTR_2, l QTR_1_ l QTR_.2. l I I I I 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 l

  • 5.00E-07 1.57E-06 l l Total Ci 5.00E-07 0.00E00 1.03E-05 0.nnynn l
  • Particulate activity (C1) from attachment Ill

4 -

FINGY 133, M;V. O .

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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)

Concentration ll 1.44E-06 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 --

4; PINCP 158, Rev. 6 i

.- Page 7 of 8 I

TABLE 2A

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

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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 l l 1 l NUCLIDE l UNIT l QTR 1 l QTR 9 l QTR i l QTR2 l l l l l l l l 27.0 INDIVIDUAL LIQUID EFFLUENT l Sr89 Ci l l Sr90 Ci ~

l l Cs134 Ci 2.84E-05 6.10E-07 l 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 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 l l Total Ci 1.71E-04 0.00E00 4.29E-03 1.84E-03 l

ATTACHMENT 1 .

g ADDITIONAL NUCLIDES

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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

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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 l Sb-125 3.75E-04 l 4.61E-04 l 1.90E-04 l g ________l____l____________g____________;__________

l Ci l 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____ ___________l l__Js:U____i. 9 _g____________l____________l____________g 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

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A PINGP 753, Rev. 1 l

V Retention:

Page 1 of 5 Lifetime 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.

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PINGP 753, Rev. 1

  • Retention: Lifetime

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Page 2 of 5

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, PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 1-1-85/7-1-85 1

NORTHERN STATES POWER License No. DPR-42 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

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B

  • Fe55 23.8 1
  • N163 J16.0 Co58 ~18.1 Co60 _13.7 Cs137 12.3 Cal 34 9.5

__NB95 1.7 Mn54 1.6 Zr95 1.1 1

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, * = Inferred - Not Measured on Site

- PINGP 753, Rev. 1 Retention: Lifetime p Page 3 of 5 q U 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

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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 l
  • Ni63 16.9 I Cal 37 14.9 Cal 34 12.4 i Co58 6.1 I Agl10 3.2 Mn54 2.2 i

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  • = 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

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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 85-17 85-20 178 80 170 0.905 0.315 0.793 D

A A

L L

A C

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

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