ML20024F205

Effluent & Waste Disposal Semiannual Rept Jan-June 1983

ML20024F205
Person / Time
Site:	Prairie Island
Issue date:	06/30/1983
From:	Musolf D NORTHERN STATES POWER CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
NUDOCS 8309090045
Download: ML20024F205 (9)

Text

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PINGP 158, Rev. 5 Page 1 of 8 Retention: Lifetime EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT I

January THROUGH 3,in, t on l

SUPPLEMENTAL INFORMATION Facility - Prairie Island Nuclear Generating Plant Licensee - Northern States Power Company License Nos. - DPR-42 & DPR-60 1.

Regulatory Limits a.

Liquid Effluents:

1.

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

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

Gaseous' Effluents:

=

1.

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

Noble Gases 1 500 mren/ Year Total Body 1 3000 mrem /Yesr Skin I-131, H-3, LLP 1 1500 arem/ Year Any Organ 2.

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

Noble Goes 1 10 mead /Qtr Gamma i 20 mead /Qtr Beta i 20 mead / Year Gamma 5 40 mead / Year Beta I-131, H-3, LLP

$ 15 mrem /Qtr 1 30 mres/ Year 8309090045 830829 PDR ADOCK 05000282 fg6 R

PDR I I

PINGP 158, Rav. 5 Paga 2 of 8 2.

Maximum Permissible Concentrations a.

Fission and activation gases in gaseous releases:

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 c.

Liquid Effluents for radion6clides other than dissolved or entrained gases:

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

Liquid Effluent dissolved and entrained gases:

2.0E-04 pei/ml Total Activity 3.0 Averste Energy Not applicable to Prairie Island Regulatory Limits.

4.0 Measurements and Approximations of Total Radioactivity a.

Fissiod and activation gases Total Geli 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.

Geli Nuclide Geli BATCH RELEASES a.

Liquid QTR 1 QTR 2 Number of Batch Releases l

6.50E01 5.80E01 l

Total Time Period for a Batch Release (br) l 9.66E01 8.63E01 l

Maximum Time for a Batch Release (br) l 2.30E00 2.00E00 l

Average Time for a Batch Release (hr) l 1.50E00 l 1.50E00 l

Minimum Time for a Batch Release (br) l 1.10E00 l 9.00E-01 l Ave Mississippi flow during Quarter (CFS) l 2.82E04 1 3.90E04 l

PINGP 158, R:v. 5 Pega 3 of 8 b.

Gaseous QTR 1 QTR 2 Number of Batch Releases 1 1_nornn

.I ? norno' l Total Time Period for a Batch Release (br) 11_17Foi i 1_narni l

Haximum Time for a Batch Release (hr) l6_anrno l R_nnrnn l

Average Time for a Batch Release (br) l 1_90rno i s_Anrnn l

Minimum Time for a Batch Release (br) l 2 anron i 9 anrnn l

ABNORMAL RELEASES a.

Liquid QTR 1 QTR 2 Number of Batch Releases 1

0.OOFOO l O_OOFOO l

Total Activity Release (Ci) l 0.OOEOO O_OOFOO l

Total Tritium Release (Ci) 1 0 OOFOO h O_OOFOO l

2 b.

Gaseous QTR _1 __ __

QTR Number of Batch Releases l

o,oogoo l

v. vu t.vu Tctal Activity Release (Ci) l 0.00E00 l 0.00E00 l

i e

PINGP 158, RIv. 5 Paga 4 of 8 TABLE 1A EFFLUENT'AND WASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES

'EST TOTAL UNIT l

QTR 1 QTp 2 l

l l

l l

l A.

Fission and Activation Gases l Total Release Ci l

4.4sF01 l

1_1orn9 l !2.50E0I-l l Average Release Rate pCi/sec l

1. 26 E01 1

1.42E01 l

l Gamma Dose arad 3.67E-02 8.38E-02 l

l Beta Dose arad 1.35E-01 2.30E-01 l

l % of Gamma T.S. Limit l

l 3.67E-01 8.38E-01 l

.l % of Beta T.S. Limit l

l

6. 75 E-01 1.15E00 l

B.

Iodines l Total 1131 Ci l

Z. 34 E-04 l

5.16E-03 lt2.50E01 l l__A*:erage Release Rate

' pCi/sec l 2.98E-05 l

6.56E-04 l

C.

Particulates l Total Release lCi l

3. 46 E-07 l

1.13E-07 l12.50E01 l l Average Release Rate i pCi/sec l 4.40E-U5 l

1.44E-05 l

D.

Tritium l Total Release lCi l

1.81E01 l

1.88E01 lt2.50E01 l l Average Release Rate l pCi/sec l 2.30E00 l

,2.39E00 l

l Total B & C & D l pCi/sec l 1.81E01 l

1.88E01 l!2.50E01 l l Dose l mrem l

5.11E-02 l

4.19E-01 l

l % of T.S. Limit l

1 3.41E-01 l

2.79E00 l

E.

Gross Alpha l Total Release lCi l

0.00E00 l

0.00E00 lt2.50E01 l

PINGP 158, Rrv. 5 Pega 5 ef 8 TABLE IC EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT CASEOUS EFFLUENTS CROUND LEVEL RELEASES CONTINUOUS MODE BATCH N0DE l

l l

l l

l l NUCLIDE l UNIT l

QTR1 l

QTR1 l

QTR 1 l

QTR2 l

l l

l l

l l

l 1.

Fission and Activation Gases l Kr85 Ci 9.77E01 l

7.04E-01 l

l 7.33E-01 l l Kr85m Ci l

l I

l l Kr87 Ci l

l l

l l Kr88 Ci l

l l

l Xe133 Ci 2.2/EUU 5.90EUl l

l Z.33EU1 l

l Xe135

'Ci 3.43E-01 4./ZEUU l

6.06E-01 l

l Xe135m l Ci l

l l Xe138 I Ci l

l l

l Xe131m Ci l

a u r_nq l

l l

l Ar41 Ci l

l l

l Xe133m F Ci I

9 tav_ns l

1 97p_n1 l

l 1

I l

l l

l I

l l

l l

l l

l l

l Total I Ci 9.93EU1 l

9.44EU1 l

U.UUEE l

4. 3 U t,U1

_l 2.

Iodines l 1131 l Ci l

2.34E-04 l

5.16E-03 l

l 3.4 7E-06 l l __

l Ci l

2.10E-04 l

7.22E-04 l

l 5.36E-07 l

I133 l 1135 l Ci l

I l

l l Total l Ci I

4.44E-04 5.88E-03 1

0.00r.09 I

4. 01E-06 l CONTINUOUS MODE BATCH MODE I

l l

l l

l l

l NUCLIDE l UNIT l

QTR 1 l

QTR 2 l

QTR 1 l

QTR 2 l

l l

l l

l l

l 3.

Particulates l

l Sr89 I Ci 3 9ar_ny l Sr90 l Ci l' AW_no l

l Cs134 l Ci l

l l

l l Cs137 I Ci l

l l

l l Ba-La140 l Ci l

l l

l,CoS8 l Ci

? 1?r_n7 1 inr_n?

I l

l l Co60 1 Ci l

l l

l 1

1 I

I l

l l

l Total I Ci l

3.46E-07 1.13E-07 1

0.00E00 l

0.00ECO l

s^

PINGP 158, Rzv. 5 Page 6 of 8 TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID EFFLUENTS - SUMMATION OF ALL REL~2SES l UNIT l

QTR 1 l

QTR 2 lE l

l l

l l

A.

Fission and Activation Products l Total Release W/0 H-3, I l

ci 2.10 E-04

2. 39 E-03 l !2.50E01 I l Rad Gas, Alpha l

l g

l Average Diluted i

6.05E-14 5.24E-13 l Concentration l pCi/ml I

B.

Tritium l Total Release Ci l 1.12E02 1.66E02

!2.50E01 l

• '8'

• d

pCi/ml 3.23E-08 3.64E-08 l Total A & B l pCi/ml l 3.23E-08 l

3.64E-08 l

l Total Body Dose' l mrem l 2.39E-04 l

4.36E-04 l

l Critical Organ Dose l mrem l 4.80E-04 l

1.57E-03 l

l l Organ l GI l

THYROID l

l % Total Body T.S. Limit l l 7.93E-03 l

1.45E-02 l

l % of Critical Organ l

l l

l g

l T.S. Limit l

l 4.80E-03 l

1.57E-02 l

C.

Dissolved and Entrained Gases l Total Release l Ci l 3'HE-0) l

/.23E-02 ltZ.50 E01 l l Average Diluted lE'"

l 1.50E-14 l

l l

l 1.59E-ll l

l Concentration l

D.

Gross Alpha l Total Release l Ci l O 00'00 l u.uur.vu ltz.3ucul l E.

Volume of Waste (Prior to Dilution) l Liters 1 3.22E07 l 2.71E07

62. 50 E01 l F.

Volume of Dilution Water l Liters l 3.47E12 l 4.56E12 h2.50E01 l

6' PINGP 158, Rsv. 5 Page 7 of 8 TABLE 2A h ~

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

l' l

l l

l 1

l NUCLIDE l

UNIT l

QTR 1 l

QTR 2 l

QTR1 l

QTR 2 l

l l

l l

l l

l l Sr89 l Ci l

i 1

l l Sr90 Ci l

l l Cs134 Ci 8.10E-06 l

l Cal 37 Ci 8.88E-06 l

l 1131 Ci 1.58E-04 1 1.86E-03 l

,l'CoS8 Ci 5.95E-05 1.08E-05 2.62E-04 l

.l Co60 Ci 4.94E-06 1.78E-04 4.05E-06 l

l Fe59 Ci I

l l Za65 Ci l

l l Mn54 Ci l

l Cr51 Ci l

l Zr-Nb95 Ci l

1.58E-05 l

l l Mo99 Ci l

l l Ba-La140 l Ci ll 11 l

l

-l Tc-99m I Ci 11 l

l _,Ce-141 Ci l

l I-133 =

Ci l

2.57E-05 l

l Total Ici I

4.94E-06 l 2.18E-04 l 2.05E-04 1 2.17E-03 l

CONTINUOUS MODE BATCH MODE l

l l

l l

l l

l NUCLIDE l UNIT l

QTR 1 l

QTR 2 l

QTR 1 l

QTR 2 l

l l

l l

l l

l

.l.Xe133 l Ci l

l 2.89E-05 l

7.llE-02 l

.l Xel33m l Ci l

-l 1

3.76E-04 l

-l Xel31m l Ci l

ll l 1.70E-05 5.43E-04 l

l Xel35 l Ci l

l 5.96E-06 1

2.80E-04 l

l Kr85m l Ci l

l l Kr85 l Ci l

l l Kr88 l Ci l

l l

1 l

l I

l l

1 l

l l-1 l

l l

l l

l Total I Ci 1 0.00E00 1

0.00E00 l 5.tqE-Os l 7.23E-02 l

___.__.___d_..________._

'i~

PINGP'158, Rzv. 5 Pega 8 of 8 TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SOLID RADIOACTIVE WASTE SEMI-ANNUAL REPORT JAN 1981_ THROUGH 3rm ions Volume 1

i Percent Container (FT3)

Curie Quantity Radionuclides Abundance Type Quantity CEMENTED 1.11E 03 1.31E01 Co 60 9.16E01 DOT 7A 1.34E02 WASTE Cs 134 9.90E-01 TYPE A Cs 137 6.39E-00 55 GAL Mn 54 1.02E00 AND 83 GAL DRUM COMPACTED 2.37E03 2.29E00 Ag110M 3.77E00 DOT 7A 3.22E02 TRASH Cs 137 4.24E00 TYPE J Co 58 2.94E00 55 GAL Mn 54 1.10E00 DRUM Co 60 8.79E01 DEWATERED 3.30E02 4.53E00 Co 60 9.72E01 3.00E00 RESIN Mn 54 1.01E00 Cs 137 1.80E00 STEEL LINER NON-COMPACTED 2.14E03 3.20E-01 Sb 124 7.51E-01 WOOD 2.20E01 TRASH Ag 110M 3.47E00 AND Cs 137 3.00E00 METAL Nb 95 8.35E-01 BOXES Co 58 3.49E01 Mn 54 2.16E00 Co 60 5.49E01 Tetal Volume s agA3 FT3 Tc*al Curie Content 7.ngmi Curies 1Curie Quantity and Radionuclides are measured not estimated

/

Dfn G Northem States Power Company 414 Nicollct Mall Minneapoks. Minnesota 55401 Telephone (612) 330-5500 August 29, 1983 D/RA i 6

.i l

A //i; 4 j

6.L. I i

A Regional Administrator 4

-ib[.x..

k i

~

Region III j

U S Nuclear Regulatory Commission C:

l l

i 799 Roosevelt Road ka j

t Glen Ellyn, IL 60137 7C~l t.2illiX6d PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket No. 50-282 License No. DPR-42 50-306 DPR-60 Effluent and Waste Disposal Semiannual Report for January 1. 1983 through June 30, 1983 In accordance with the Prairie Island Technical Specifications, Appendbc A to Operating Licenses DPR-42 and DPR-60, we are submitting one copy of the Effluent and Waste Disposal Semiannual Report covering the first half of 1983.

b Nu David Musolf Manager - Nuclear Support rvices D!Bf/bd cc: Document Control Desk, USNRC (1)

Project Manager, USNRC Resident Inspector, USNRC G Charnoff MPCA Attn: J W Ferman g

j Attachment i

e S

/

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