ML20041D555
| ML20041D555 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 02/26/1982 |
| From: | NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20041D531 | List: |
| References | |
| NUDOCS 8203050402 | |
| Download: ML20041D555 (9) | |
Text
.
PTNG? 4158, Res. 4 EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT July
,THROUCH December 1981],
SUPPLEMENTAL INFORMATION Facility - Prairk ' Islan! :hiclaar Cc.ui:1 ting Plant Licensee - Northc3n States Power Company License Nos. - DPR-4 & DPR-60' 1.
Regulatory Limits Action is required if the rate of relecta of radioactive. tar trials, when averaged cycr a three-month period, la mit.h that these no mities, if continued
+.t the same release rate for c. year, would er : '.dce the design ohjactives. Design objectives ar2:
r-a.
Fission and activation gases (and an other radioactu jsotopes except halogen and particulato icetc.jes with half-li,,,;reater than 3 drrr'; in gaseous releases:
9 3
Qi 1300 m /sec MPC1 b.
Iodines and particulates with ' half-lives greater than Ts days in 8aseous releases:
~
67 m /sec Qi c.-
Liquid Effluents:
1.
Annual total quantity of radioactivo imtcrial in. mid waste, excluding tritium and dissolved gases, of 5 Ci par. nit.
2.
Annual average concentration of radioactive materi n inl liquid waste, prior to dilution in the Mississippi River, neluding tritium and dissolved gases, of " X 10 'pci/ml.
3.
Annual average concentration of ::itium in liqu('.
,te, prior to dilution in the Mississippi River, of 5 X 10
'nl.
2.
Maximum Permissible Concentrations a.
Fission and activation gases (and all other radioact:.s _ :sotopes except-halogan and particulate isotopes with half-lives grearar than 8 days) in gaseous releases:
10 CFR 20, Appendix B, Tabla 2, Column 1
?f 2
8203050402 820226 ' '
4 PDR ADOCK 05000282 R
PINCP 158 Rev. 4 2.
Maximum Permissible Concentrations b.
Iodine and particulates with half-lives greater tnan 8 days in gaseous releases:
10 CFR 20, Appendix B. Table 2, Column 1 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 Celi in gaseous releases:
Nuclide Geli b.
Iodines in gaseous releases Total Celi 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 3
QTR 4 Number of Batch Releases 79 47 Total Time Period for a Batch Release (hr) 128.56 77.69 Maximum Time for a Batch Release (hr) 2.50 2.93 Average Time for a Batch Release (hr) 1.63 1.65 Minimum Time for a Batch Release (hr) 1.13 1.17 Ave Mississippi flow during Quarter (CFS) 1.72E04 1.53E04 b.
Gaseous QTR 3
QTR 4
Number of Batch Releases 1
2 Total Time Period for Batch Releases (hr) 8.00 2.94 Maximum Time for a Batch Release (hr) 8.00 1.82 Average Time for a Batch Release (hr) '
8.00 1.47 Minimum Time for a Batch Release (hr) 8.00 1.12 s
PINCP 158 Rev. 4 ABNORMAL RELEASES a.
Liquid QTR 3 QTR 4 Number of Releases 0
0 l
Total Activity Released (C1) 0 0
l Total Tritium Released (C1) 0 0
b.
Gaseous QTR 3 QTR 4 Number of Releases 0
1 1*
Total Activity Releases (C1) 0 l 2.79E01 Notes:
- - This release Eonsisted of two small leaks in the low level waste gas system. Approximately 2000 cubic feet over seven days was released before the leakage sources were found and isolated.
i 1
1.
+
PINGP 158 TABLE 1A Rev. 4 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT CASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES UNIT QTR j QTR L ERR R A.
Fission and Activation Cases Total Release Ci 9.55 3.69E01 I SOY Average Release Rate pCi/sec 1.21 4.70 B.
Short Lived Particulate (t1/2 < 8 days)
Total Release C1 2.87 3.43E-01
! 50%
Average Releace Race.
pCi/sec 3.66E-01 4.36E-02 C.
Tritium Total Release C1 1.78E01 1.85E01 1 25%
Average Release Rate pCi/sec 2.26 2.36 Total A & B & C pCi/see 3.84 7.10
% of Design Objective 3.52 6.51 D.
Iodines Total I131 Ci 4.69E-06 3.29E-04
! 50%
Average Release Rate pCi/sec 5.96E-07 4.19E-05 E.
Long Lived Partictlates (t1/2 > 8 days)
Total Release Ci 9.91E-06 0
I 50%
Average Release Rate pCi/sec 1.26E-06 0
Total D & E pCi/sec 1.86E-06 4.19E-05
% of Design Objective 1.52E-02 3.41E-01 F.
Gross Alpha l Total Release lCi l
6.99E-09 10 II 100%
l s.
PINCP 158 Rev. 4 TABLE IB EFFLUEUT AND WASTE DISPOSAL SEMIANNUAL REPORT GASEOUS EFFLUENTS CONTINUOUS MODE BATCH MODE NUCLIDE UNIT QTR _1 QTR 1 QTR L QTR 4__
1.
Fission and Activation Gases Kr85-Ci i
1.21E-01 Kr85m Ci 3.49E-01 i
Kr87 C1 2.81E-01 3.25E-01 Kr88 C1 1.48 3.99E-01 Xel33' C1 1.02 4.97 4.58E-02 2.78E01 Xe135 Ci 2.19 1.99 2.37E-06 9.51E-03 Xe135m Ci 4.70E-01 Xe138 C1 1.36 3.43E-01 Xe131m Ci Ar41 C1 3.02 l 1.50E-01 Xe133m C1 2.94E-02 1.40E-01 Total C1 1.66E01 8.88 1.96E-01 2.81E01 2.
Iodines I131 Ci 4.69E-06 I 3.29E-04 1133 Ci I 6.69E-04 1135 Ci Total Ci 4.69E-06 9.98E-04 CONTINUOUS MODE BATCH MODE NUCLIDE UNIT QTR 3 QTR 1 QTR _1 QTR 1 3.
Particulates Sr89 Ci l
Sr90 Ci Cs134 Ci l
Cs137 Ci Ba-La140 Ci j
Co58 C1 3.75E-10 co60 Ci I
9.91E-06 Cd109-Ci jib 124 Ci l
Na24 Ci CoS7 Ci Cel44 Ci Zr-Nb95 Ci i
Rb88 Ci 1.48 i
1 PINGP 158 Rev. 4 TABLE IB EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT CASEOUS EFFLUENTS e
I 3.
Particulates Sr85 Ci Mn54 Ci Cs138 C1 1.36 3.43E-01 Y88 C1 3.52E-02 j
l Total C1 2.88 3.4 3E-01 9.91E-06 0
i k
)
j i
i i
1 1
- e
-sy.
'o PINGP 158 Rev.
4 TABLE 2A EFFLUENT AND WASTE DISP 0AL SEMIANNUAL REPORT LIQUID EFFLUENTS - SIRDRTION OF ALL RELEASES UNIT QTR L QTR 4_
f0 g;
A.
Fission and Activation Products Total Release W/0 H-3, Rad Gas, Alpha Ci i
7.29E-03 1.13E-03 i 50%
i Average Diluted Concentration pCi/ml 1.98E-11 3.50E-12 i
% of T. S. Annual Curie Design Objective 7.29E-02 1.13E-02 l
B.
Tritium Total Release Ci 2.21E02 7.04E01 1 25%
Average Diluted Concentration pCi/ml 5.99E-07 2.18E-7
% of T. S. Annual Design Obiective Conc 1.20E01 4.36 C.
Dissolved and Entrained Cases Tecal Release Ci 1.47E-04 l 2.42E-04 1 50%
Average Diluted Concentration pCi/ml 3.98E-13 l 7.49E-13 D.
Gross Alpha Total Release lCi l
2.02E-06 l 7.52E-06 l 1 50%
l E.
Volume of Waste (Prior to Dilution) l liters l 4.93E07 1 4.95E07 i i 25%
F.
Volume of Dilution Water l liters i 3.69E11 l 3.23E11 11 50%
i
PINGD 158 Rev. 4 TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID EFFLUENTS - SU1MATION OF ALL RELEASES Continuous Mode Batch Mode NUCLIDE UNIT QTR _3_
QTR _4_
Sr90 Ci Cs134 Ci l
Csl37_
C1 1.78E-os l
l I131 Ci l
l CoS8 Ci 1.70E-03 l 1.08E-04 l 1.25E-03 5.84E-04 Co60 Ci 1.17E-03
.l.03E-04 Fe59 ci Zn65 Ci i
Mn54 Ci 5.31E-05 i
Cr51-Ci i
Zr-Nb95 Ci t
Mo99 Ci t
Ba-lal40 C1 2.82E-05 l
Agl10m Ci l
Na24 Ci i
W187 Ci i
Sbl24 -
Ci b.50E-04 Sr85 Ci l
Cal 36 Ci Zr-Nb97 C1 Cd109 I
ci i
Rb88 Ci Total Ci 1.80E-03 1.08E-04 3.07E-03 6.87E-04 i
Continuous Mode Eatch ibde NUCLIDE UNIT QTR J QTR _4__
QTR 3__
QTR 4_
Xe133 Ci l1.41E-04 l 2.42E-04 l
Xe133m Ci l
l Xe131m Ci 1
l l
Xe135 Ci l6.30E-06
(
l Kr85m Ci i
l Kr85 Ci Kr88 Ci l
l l
Total Ci l
0 1
0 1.47E-04 2.42E-04 PINGP 158 Rev. 4 TABLE 3 1
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REFORT July through December 1981 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 400 t 50%
Ci 1.6 b.
Dry compressible waste, contaminated ft3 2370.7 50%
equipment, evaporator, bottoms, etc.
Ci 8.2 c.
Irradiatcd components, control rods, ft3 NONE etc.
Ci d.
Other (describe) Spent Fuel Racks fbf 50%
0 2.
Estimate of major nuclide composition (by type of waste).
a.
CoS8 2
!I 25%
i 36 l
Co60 g
Mn54 l
2 %
Cs134 I 15 l
I Cs137 45 %
l b.
CoS8 I 15 %
35 %
l Co60 Csl37 f 25 %
Cs134 10 %
l Mn54 15 %
l c.
HONE I
l l 8.5 %
l
.d.
CoS8 C060 91.5 %
l
~3.
Solid Waste Disposition Number of Shipments hode of Transportation Destination 9
Truck U.S. Ecology, Richland, Washington B.
Irradiated Fuel Shipments (disposition)
NONE
,9,
_.