ML19242D264
| ML19242D264 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 06/30/1979 |
| From: | NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML19242D258 | List: |
| References | |
| NUDOCS 7908140765 | |
| Download: ML19242D264 (9) | |
Text
.s EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT January 1,1979 THROUGH June 30, 1979 Supplemental Information Facility - Prairie Island Nuclear Generating Plant Licensee - Northern States Power Conpany License Nos. - DPR-42 DPR-60 1.
Regulatory Limits Action is required if the rate of release of radioactive materials, when averaged over a three-mont'n period, is such that these quantities, if continued at the same release rate for a year, would exceed twic,e the design objectives. Design objectives are:
a.
Fission and activation gases (and all other radioactive isotopes except halogen and particulace isotopes with half-lives greater than 8 days) in gaseous releases:
O i 1 1300 m /sec MPC i
b.
Iodines and particulates with half-lives greater than 8 days in gaseous releases:
O i 1 67 m /sec MPC 1
c.
Liquid Effl~:ents:
1.
Annual total quantity of radioactive materials in liquid waste, exclusing tritium and dissolved gases, of 5 Ci per unit.
2.
Annual average concentration of radioactive materials in liquid waste, prior to dilution in the Mississippi River, excluding tritium and dissolved gases, of 2 x 10-8 uCi/ml.
Annual average concentration of tritium in li prior to dilution in the Mississippi River, of 5 x 10 guid waste, 3.
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:
10CFR20, Appendix B, Table 2, Column 1 v
T 90814074d.
2.
Maximum Permissible Concentrations b.
Iodine and particulates with half-lives greater than 8 days in gaseous releases:
10 CFR 20, Appendix B Table 2, Column 1 c.
Liquid Effluents:
10 CFR 20, Appendix B, Table 2, Column 2 3.
Averare Energy Not applicable to Prairie Island Regulatory Limits.
4.
Measurements and Approximations of Total Radioactivity a.
Iission and activation gaces Total Geli in gescous releases:
Nuclide Geli b.
Iodines in gaseous releases Total Geli Nuclide Geli c.
Particulates in gaceous 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 3.3E01
! 7.0E01 Total Time Period for a Batch Release (hr) 4.66E01 12J2E02 Maximum Time for a Batch Release (hr) 2.50E00 3.47E00 Average Time for a Batch Relcase (hr) 1.41E00 1.60E00 Minimum Time for a Batch Release (hr) 7.50E-01 1.00E00 Ave Mississippi flow during Quarter (CFS) 9.33E03 5.27E04 b.
Gaseous QTR 1 QTR 2 Number of Batch Releases 0
3.00E00 Total Time Period for Batch Releases (hr)
Maximum Time for a Batch Release (hr) 0 6.72E01 0
3.12E01 Average Time for a Batch Release (hr) 0 2.24E01 Minimum Time for a Batch Release (hr) 0 1.33E01 1 -
)
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e t
ABNORMAL RELEASES a.
Liquid QTR 1
QTR 2 Number of Releases 1
Total Activity Released (C1) 0 0
.s' 0
0 Total Tritium Released (Ci) 0 0
b.
Gaseous QTR 1
QTR 2 s
Number of Releases 0
1.0E00 Total Activity Releases (Ci) 0 3.93E00 P
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yg 4
TABLE LA EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES UNIT (TR 1 QTR 2 RR R A.
Fission and Activation Cases rotal Release Ci 5.1]Uf01 4.14E02 t 50%
Asorage aclease Rate pCi/sec 6.54ECC 5.27E01 i
B.
Short Lived Particulates (t1/2 < 8 days)
Total Release C1
- 3. 4 7E-05 50%
Average Relcace Rate pCi/sec 4.42E-06 C.
Tritium Total Release C1 2.53E01 6.54E01 50%
Average Release Rate pCijsec 3.77E00 8.41E00 Total A 6 B & C pCi/sec 9.76E00 6.10E01
% of Design objective 3.89E00 2.43E01 D.
Iodines Total 1131 Ci 6.30E-05 3.27E-03 50%
Average Release Rate pCi/sec 8.02E-06 4.20E-04 E.
Long Li';ed Particulates (t1/2
>8 days)
Total Release C1 2.91E-06 1.32E-05 1 50%
Average Release Rate pCi/sec 3.70E-07 1.68E-06 Total D 6 E pC1/sec 8.39E-06_
4.22E-04
% of Design Objective 1.18E-01 6.27E00 F.
Gross Alpha frotal Release Ci 8.50E-09 l
1.19E-08 100%
Note:
" " indicates that relesses were below lower limit of detection (LLD) values.
Mcximum allowed values of LLD are given in the Technical Specifications..>:./
TABLE IB EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT CASEOUS EFFLUENTS CONTINUOUS MODE BATCH MODE SULLIDE UNIT QTR 1 QTR l QTR 1 QTR g__
1.
Fission and Activation Gases fEr85 C1
'O l
Fr85m Ci 7.41E-01 0
Er87 Ci 1.96E00 0
Kr88 Ci O
Xe133 C1 4.07E01 3.86E02 0
2.07E01 Xe135 Ci 5.62E00 6.68E00 0
2.15E-01 Xe1356 C1 0
Xc138 C1 0
Xe131m C1 0
Ar41 C1 2.41E00 0
2.01E-01 Xe133m C1 5.06E-01 0
7.03E-02 Total Ci 5.14E01 3.93E02 0
2.12E01 2.
Iodines 1131 Ci 6.30E-05 3.27E-03 0
I133 Ci 1.43E-04 0
1135 C1 0
Total Ci 6.30E-05 3.41E-03 0
CONTINUOUS MODE BATCH MODE NUCLIDE UNIT QTR 1 QTR _2_
3.
Particulates Sr89' C1 0
Sr90 Ci 0
Cs134 Ci 0
Cs137 Ci 0
Ba-Lp
",0 -
C1 0
CoS8 C1 2.06E-06 1.52E-06 0
Co60 Ci 8.42E-07 0
Cd109 Ci 0
Sb124 C1 0
Na24 C1 0
C oS 7 C1 0
Cel44 C1 1.06E-05 0
Zr-h195' Ci 0
Rb8E Ci 0
M t.3.47E-05 s. -
me
~
TABLE IB EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS 3.
Part1 ilates O
pf!1 C1 0
fitM4 C1
.o Es_L.18 Ci 0
- 8. 70E- 07 YS3 C1 Ce139 C1 2.12E-07 0
1 -
.c
.)
I /
TABLE 2A EFFLUENT AND WASTE DISP 0AL SEMIANNUAL REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES UNIT QTR 1 QTR 2 p7 A.
Fission and Activation Products Total Release W/011-3, Rad Gas, AlpM.
C1 1.32E-04 7.74E-04 1 50%
Ave _rfre Diluted Concentration pC1/ml 9.71E-13 6.97E-13 ot T.
S. Annual Curic Design Obj e_c_t_ive 1.328-03 7.74E-03 B.
Tritium Total Releast-
~
Ci 6.78E01 2.42E02 25%
Averane Diluted Concentration pCi/mi
- 4. 9TE-07 2.18E-07
. of T. S. Annual Desig Objective Co n e_ _
9.98ETO 4.36E00 C.
Dissolved and Entrained Cases Total Relyase C1 1.53E-02 9.81E-02 150f Average D_iluted Concentration pCi/ml 1.13E-10 8.84E-11 D.
Cross Alpha Total Releast
~
Ci l
l 3.60E-08 150%
E.
Volume of Waste (Prior to Dilution) l lifers 4.03E07 l 4.31E07 125%
l F.
Volume of Dilution Water llitus l 1.36 Ell l 1.11E12 50%
l 7-7 ;Un J L.
TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Continuous Mode Batch Mode NUCLIDE UNIT QTR l QTR 2_
QTR l__
QTR 2_
l Sr89 C1 l
Sr90 Ci Cs134 Ci 3.80E-06 Cs137 C1 5.60E-06 1131 Ci 6.05E-04 CoS8 C1 5.79E-05 2.84E-05 Co60 C1 2.62E-05 1.56E-05 1.59E-05 Fe59 C1 Zn65 Ci Mn54 Ci Cr51 C1 Z r-Nb 95 C1 Mo99 C1 Ba-la140 C1 Ag110m C1 Na24 C1 W187' C1 Sb124 Ci 1.63E-06 Sr85 C1 Cs136 C1 Zr-ht97 Ci Cd109 Ci Rb88 C1 Cn57 C1 5.20E-06 Total Ci 2.62E-05 1
8.45E-05 6.55E-04 Continuous Mode Batch Mode NUCLIDE UNIT QTR __1_
QTR __2_
QTR l QTR L Xe133 C1 1.52E-02 9.75E-02 Xe133m Ci 5.32E-05 2.95F-04 Xe131m C1 Xe135 Ci 7.09E-05 2.57E-04 Kr85m Ci Kr85 C1 Kr88 C1
,;4 "3
s TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Jan. 1. 1979 through June 30. 1979 Solid Waste and Irradiatted Fuel Shipments A.
'~ o l i. waste abipped offs;te for b arial or disposal (not irradiated fuel) 1.
Type of Waste Unit 6 Month Est. Total Period Error %
~
Spent Renins ftJ 80
.i.
+ 257.
C1 19.8 b.
inry compressible waste, contaminated ft3 558.6
- 257.
c'li: 1 pme n t, evaporator, bottoms, etc.
Ci 1.2 e.
I rratt ia ted components, contiol rods, f t,3 NONE etc.
C.
d.
Other (describe)
Ih NONE 2.
Estimate of major nuclide composition (by type of waetc).
a.
CO-60 41.9 CO-58 20.4 CS-137 23.5 CS-134 9.4 2
b.
CS-137 35.4 CS-134 24.2 Sh-124 23.4 CO-60 8.7 2
c.
NONE
'I '
I NONE L
3.
Solid Waste Disposition Number of Shipments Mode of Transportction Destination 1
Truck Barnwell S.C.
1 Truck Richland Wash.
B.
Irradiatet! Fuel Shipmeats (dispos ttion) 'll