ML20102B474

Effluent & Waste Disposal Semiannual Rept,Jan-June 1982

ML20102B474
Person / Time
Site:	Prairie Island
Issue date:	06/30/1982
From:	NORTHERN STATES POWER CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
NUDOCS 8503040002
Download: ML20102B474 (9)

Text

_ _ . .

, e

} PINGP #158, Rev. 4 EFFLUENT AND WASTE DISPOSAL GE:4I-ANNUAL REPORI Januarv THROUGH June 1982 SUPPLEMENTAL INFORMATION Facility - Prairie Island Nuclear Generating Plant Licensee - Northern States Power Company License Nos. - DPR-42 & DPR-60

1. Regulatory Limits Action is required if the rate of release of radioactive e.aterials, when averaged over a three-month period, is such that these quantities, if continued at the same release rate for a year, vould 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:

Qi 1 1300 m /see MPCg

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

01 1 67 m /sec i i

c. Liquid Effluents:

1. Annual total quantity of radioactive material in liquid vaste, excluding tritium and dissolved gases,' of 5 Ci per unit.

2. Annual average concentration of radioactive material in liquid vaste, prior to dilution in the Mississ,gppi River, excluding tritium and dissolved gases, of 2 I 10 pCi/ml.

3. Annual average concentration of tritium in liquy waste, prior to dilution in the Mississippi River, of 5 X 10 uC1/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, Coluc:n 1

~~

8503040002 820630 gDR ADOCK 05000282 /

PDR y pl dl

• ! PINGP 138

. -  ! Rav, 4

. 2. Maximum Permissible Concentrations

b. Iodine and particulates with nalf-lives greater than 8 days in gaseous releases:

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

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 Geli Nuclide Geli

c. Particulates in gaseous Total Geli.

releases: Nuclide Geli

d. Liquid Effluents: Total Gross Beta Gamma Nuclide Geli BATCH RELEASES

a. Liquid QTR 1 QTR 2 Number of Batch Releases 1.80E01 I A Arn1 Total Time Period for a Batch Release (hr) 2.53E01 1.23E02 3 Maximum Time for a Batch Release (hr) 2.00E00 2.42E00 Average Time for a Batch Release (hr) 1.41E00 1.47E00 Minimum Time for a Batch Release (hr) 1.17E00 1.17E00 Ave Mississippi flow during Quarter (CFS) 1.15E04 4.51E04 i

b. Gaseous QTR 1 QTR 2 Number of Batch Releases 0.00E00 3.00E00 Total Time Period for Batch Releases (hr) 0.00E00 3.88E01 Maximum Time for a Batch Release (hr) 0.00E00 2.59E01 Average Time for a Batch Release (hr) 0.00E00 1.29E01 Minimum Time for a Batch Release (hr) 0.00E00 1 4.67E00 2-

/

Yg

j i PINCP 158 ABNORMAL RELEASES Rsv. 4

a. Liquid QTR 1 QTR 2

Number of Releases 0.00E00 0.00E00 Total Activity Released (C1) 0.00F00 0.00E00 Total Tritium Released (Ci) 0.00F00 0.00E00

b. Gaseous QTR 1 QTR 2 Number of Releases 0.00E00 0.00E00 Total Activity Releases (C1) 0.00E00 0.00F00 0.00F00 1 0.00E00 O

4 3-

, ) PINGP 158

. TABLE 1A Rav. 4 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT.

GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES UNIT EST 0 QTR l_ QTR 2_

A. Fission and Activation Gases Total Release Ci 8.07E01 1.36E02 2 25% i Averase Release Rate uCi/see 1.03E01 1.73E01 l E.

Short Lived Particulate ( t1 /2 II d*78) 0.00E00 0.00E00 Total Releasa Ci 2 25%

Averate Release Rate uCi/sec 0.00E00 0.00E00 C. Tritium Total Release Ci 9.03E00 1.56E01 2 25%

Averate Release Rate uCi/see 1.15E00 1.98E00 Tetal A & B & C UCi/see 1.14E01 1.93E01 2 25%

% of Design Objective  % 4.16E00 1 7.04E00 D. . Iodines Total 1131 C1 4.26E-05 1.58E-04 2 25%

Average Release Rate uCi/sec 5.42E-06 2.01E-05 E. Long Lived Particulates ( t 1/2> 8 days)

Total Release Ci 0.00E00 0.00E00 t Averate Release Rate VCi/sec 0.00E00 0.00E00 Tetal D & E uCi/sec 5.42E-06 2.01E-05  ! 25%

% of Desian Objective  % 7.10E-02 2.63E-01 F. Gross Alpha frotal Release ici 1 0.00E00 1 0.00E00 l 2 25% l 8

,---9 , ,--w-, e,,-->--s- - - - - - - - - - , , - - - ,a ,---._,.-a,,,-.,m,. .wn-e-,--,-e --w, ,,--n----w, , - , , ~--,,-- -----n- , , - - . - = .

i PINCP 158 Rav. 4 TA3LE 1B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS f

C0h7IhTOUS MODE BATCH MODE NUCLIDE UNIT QTR _1, , QTR L QTR 1 QTR L

1. Fission and Act".vation Gases Kr85- Ci 3.09E-02

, Kr85a C1 1.84E00 Kr87 Ci 7.83E-01 Kr88 C1 1.09E00 Xel33 Ci 8.03E01 1.27E02 2.58E-01 Xe135 Ci 3.89E-01 4.70E00 9.59E-02 X11356 Ci 2.18E-01 Xe138' Ci 8.70E-02 Xe131m Ci Ar41 Ci 8.39E-02 Xe133m Ci 6.96E-01 Intal Ci 8.07E01 1.36E02 0.00E00 3.82E-01

2. Iodines i I131 Ci 4.26E-05 1.58E-04 1133 C1 2.20E-04 1135 Ci

Total Ci 4.26E-05 3.78E-04 0.00E00 0.00E00 C0hTINUOUS HODE BATCH .TDE _

NUCLIDE UNIT QTR _,1, QTR_Z, QTR ,,,1,,, QTR 1,,

4

3. Particulates Sr89 Ci I j Sr90 Ci Cs134 Ci Cs137 Ci B*-La140 Ci -

CoS8 C1 Co60 C1 Cd109 . Ci Shl24 Ci i EA2.6. Ci C oS 7 C1 Ca144 Ci 1 Zr-Nb95 Ci Rh 88 C1

~ ~ >

f PINGP 158 Rsv. 4 TABLE IB EFTLUDIT AND WASTE DISPOSAL SDfIANNUAL REPORT CASE 005 EFFLUEhTS

3. Particulates Sr85 Ci  :

Mn54 C1 Cc138 Ci .

Y88 Ci TOTAL Ci 0.00E00 0.00E00 0.00E00 0.00E00 I

1 4

O l

l

.l

. . .' j i

, i l PINCP 158 Rav. 4 TABLE 2A EFFLUENT AND WASTE DISPOAL SEMIANNUAL REPORT LIQUID EFFLUENTS - SIDDfATION OF ALL RELEASES UNIT 0 QTR 1 QTR 1 A. Fission and Activation Products "

, Total Release W/0 H-3, Rad Gas, Alpha Ci 4.57E-05 1.42E-04 2 25% i Average Diluted Concentration pCi/ml 1 78t-11 1.54r-11 i

% of T. S. Annual Curie Design Objective  % 4.57E-04 1.42E-03 l B. Tritium Total Releast Ci 9.24E01 1.98E02 2 25%

Average Diluted Concentration uCi/mi 1.60r-07 2.14K-07

% of T. S. Annual Design Obiective Conc  % 7.20F00 4.2RK00 C. Dissolved and, Entrained Gases ,

3 Total Release' Ci 6.31E-03 6.54E-02 2 25%

Average Diluted Concentration uCi/nl 2.46E-11 7.07E-11 D. Gross Alpha Total Release ICi 1 0.00E00 l 8.75E-08l 2 25% ;

E. Volume of Waste (Prior to Dilution) l liters l 4.77E07 l 8.37E07 l t 25% l F. Volume of Dilution Water l liters l 2.57E11 l 9.25E11 l t 25%

e

U PINGP 199

, I Rav. i TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID EFFLUENTS - SUE!ATION OF ALL RELEASES Continuous Mode Batch Mode NUCLIDE UNIT' QTR J QTR 1 QTR _2_ QTR h l

Sr89 Ci Sr90 Ci Col 34 C1 Col 37 Ci Il31 Ci CoS8 C1 1.77E-05 Cc60 Ci o.zes-vo En59 Ci Zn65 Ci Mn54 Ci Cr51 Ci Z r-Nb95 Ci Mo99 Ci B,-lal40 Ci Ag110m Ci Nn24 Ci W187 Ci Sbl24 - Ci Sr85 Ci Cal 36 Ci Zr-Nb9 7 - C1 Cd109 Ci Rb 88 Ci l

t Total Ci 0.00E00 1.77E-05 0.00EUU d.zsE-ue I Continuous Mode Batch Mode NUCLIDE UNIT QTR I QTR 2 QTR _1_ QTR2 _

Xal33 Ci '

6.2dE-03 '

o.**E-vz l Xel33m Ci 4.99E-J4 l

X113Ln ci 4.44E-u4 Xe135 Ci . 1.61E-03 9.aot-v3 Kr85m Ci Kr85 Ci l Kr88 Ci X al35m C1 1.aot-03 Total C1 0.00E00 0.00E00 o.J1E-UJ o.34c-v4 9-9-82 i

l I

l t

e 4 , ,

< t,

'. I

,  ; PINGP 158

. Rav. 4 ,

TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January through June 1982 Solid Waste and Irradiatted Fuel Shipments A. Solid waste shipped offsite for burial or disposal (not irradiated fuel)

1. Type of Waste Unit 6 Month Est. Total Period Error %

a. Spent Resins ftJ 320

+ 15%

Ci 320.8

b. Dry compressible vaste, contaminated ft3 2533.3 + 15%

equipment, evaporator, bottoes, etc. Ci 9.1

c. Irradiated components, control rods, ft3 None etc. Ci

d. Other (describe) fd None

2. Estimate of major nuclide composition (by type of vaste).

a. cosa 2.1 % l  ! 10%

Co60 l 79 ; t 10%

Cal 37 14.2 % t 10%

calla 3.7% 10%

Mn54 1.0% 10%

CoS8 t 10% l

b. 0.6 %

Co60 86.8 % 10%

Cal 37 8.8 % 2 10%

Cal 34 2.3 % t 10%

Mn54 1. 5 % t 10%

c.

I l

d.

v.

• l l 3. Solid Waste Disposition l Nu=ber of Ship =ents Mode of Transportation Destination 5 Truck U.S. Ecology Richland, WA 2 Truck Chem Nuclear, Barnwell, SC B. Irradiated Fuel Shipments (disposition) i l

mn .

r Northem States Power Company 414 Nicollet Mall Minneapons. Minnesota 55401 Teleonone (612) 330 5500 August 27, 1982 Regional Administrator, Region III U S Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 PRAIRIE ISLAND NUCLEAR GENERA 11NG PLANT Docket No. 50-282 License No. DPR-42 50-306 DPR-60 Effluent and Waste Disposal Semiannual Report for January 1, 1982 through June 30, 1982 In accordance with the Prairie Island Technical Specifications, Appendix A to Operating License DPR-22, we are submitting one copy of the Effluent and Waste Disposal Semiannual Report covering the first half of 1982.

Mws David Musolf Manager of Nuclear Support Services DMM/bd cc: Document Control Desk, USNRC (1)

G Charnoff MPCA Attn: J W Ferman NRC Resident Inspector g, .__w*

Cortifici "? M

[ji

"- ~

-