ML20010F072
| ML20010F072 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 08/28/1981 |
| From: | NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20010F070 | List: |
| References | |
| NUDOCS 8109090335 | |
| Download: ML20010F072 (9) | |
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j > IFFLUENT AND WASTE DlS?CdAL SEMI-ANNUAL F220RT l
Jan 1, 1981 TrIROUGH Jeme 30, 1981.
b Y r
SUPPLE.'GNTAL INFOIf.ATION r
i Facility - Prairie Island Nuclear Generating Plant i
Licensee - Nor:hern States Power Co pany License li:s. - DPR-42 & OPR-60 1.
Regulatorv timits Ac:1cn is required if :he rate of release of radioac:ive ma:erials, when averaged over a three-conth period, is such tha: these quanti:1es, if continued at the same release rate for a year, would exceed twice :he design objectives. Design objec:ives are:
a.
Fission and activation gases (and all other radioac:ive isotopes except halogen and particulate isotopes wi:h half-lives greater than 3 days) in gaseous releases:
3 l
01 1
1200 m /sec 2C 1
i b.
Iodines and par:1cula:es with hali-lives greater :han 3 days in gaseous releases:
01 1
67 c /sec q.WC c.
Liquid Effluents:
1.
Annual total quanti:y of radioactiva =aterial' in liquid waste, excluding triciu= and dissolved gases, of 5 Ci per uni:.
l-2.
Annual average concentrstion of radioactive material in liquid waste, prior to dilution in the Missisgppi River, excluding tritius and dissolved gases, of 2 X 10 C1/=1.
3.
Annual average concentration of critius in liquid waste, prior to dilution in the Mississippi River, of ~5 X 10~ uCi/=1.
2.
Ma:<icum Permissible Concentrations a.
Fission and activation gases (and all other radioac:ive isotopes excep:
j-halogen and particulace. isotopes with half-lives greater than i days) l I
in gaseous releases:
10 CFR 20, Appendix 3, Table 2, Column 1 l
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8109090335 810828 PDR ADOCK 05000282
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PINCP 158 Rev. 4 2.
Maximum Permissible Concentration:;
b.
lodine and particulates with fulf-lives greater than 8 days in gaseous releases:
10 CFR 20, Appendix B, Table 2, Coluan 1 c.
Liquid Effluents:
10 CFR 20, Appendix B, Table 2, Column 2 3.
A_verane Energy Net applicable to Prairie Island Regulatory Limits.
4.
Measurements and Anproximations of Total Radioactivity a.
Fission and activatica gases Total Geli in gaseous releases:
Nuclide Goli b.
Iodines in gaseous releases Total GeJ1 Nuclide Gell c.
Particulates in gaseous Total Celi releases:
Nuclide Geli O
d.
Liquid Effluents:
Total Gross Beta Gamma Nuclide Cell BATCll RELEASES a.
Liquid QTR 1 QTR 2 Number of Batch Releanos Total Tina Period for a Batch Release (hr) 50-33 71.1 49.8 Maximum Time for a Batch Release (hr) 1.87 1.87 Average Time for a Betch Release (hr) 1.42 1.51 Minimum Tina for a Batch Release (hr) 1.05
- 1. l'e Ave Fussiss ppi flow during Quarter (CFS) 7.19 E 03 2.05 E 04 i
b.
Gascous QTR 1 QTR 2 Number of i ttch Releases 1
0
_]
Total Time /criod for Batch Releases (hr) 17.3 0
Maximum Time for a Batch Release (hr) 17.3 0
_ _j Average Time for a Batch Release (hr) 17.3 0
Minimum Time for a Batch Release (hr) 17,3 l
0 P
l' INCL
- 158 AI; NORMAL RELEA!iES RdV. 4 a.
Liquid QTR1 OTR 2
^~
Number of Releases 0
0 l
Total Activity Released (C1) 0 0
i Total Tritium Released (C1) 0 O_
l b.
Gascous OTR 1
,, QTR 2 Nuc.ber of Release 3
_.n 0
.)
Total Activity Reicases (C1) o o
0 0
O l
l l
m
g PINCP 158 TABLE lA ROV-4 EFFLUENT AND WASTE DI; MAL SEM1 ANNUAL REPORT CASEOUS EFFLUENTS - SUMfATION OF ALL RELEASES EST TOTAL UNIT QTR L QTR 2-ERRO2%]
A.
Fission and Activation Cases Total Release C1 2.61F-02 1_1Ar-n7
? 50%
Average Release Rate pCi/ cec 3.32E-03 1.45E-08 B.
Short Lived Particulate (t1/2 < 8 days)
Total Release Ci 0
6.82E-05
! SQ%
Average Releace Rate-pC1/sec 0
8.68E-06 C.
Tritium Total Release
!Ci 11.5 21.7 25%
Average Release Rate' lpCi/sec 1.72 3.02 O
l Total A 6 B 6 C pCi/sec 1.72 3.02 i% of Design Objective 6.62E-01 1.18 D.
Iodines Total 1131 di 2.62E-05 1.29E-06
! 50%
Average Release Rate LCi/sec 3.33E-06 1.64E-07 E.
Long Lived Particulates (t /2 > 8 days) 1 l
Total Release Ci 1.84E-05 0
50%
Average Release Rate pCi/sec 9.97E-06 0
Total D 6 E pC1/see 1.33E-05 1.64E-07
% of Design Objective 1.97E-01 5.02E-01 F.
Cross Alpha l Total Release lCi l
6.19E-08 1
1737E-8~
l t100"___[]
(
b.
g-.
PINGP 158 i
Rev. 4 TABLE IB EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT p
GASEOUS
-FLUENT 5 CONTINUOUS MODE BATCl! MODE NUCLIDE UNIT QTR 1 QTR 1 QTR 1 Q'P. _2_
l 1.
Fission and Activation Gases lKr85-l Ci 9.70E-09 Kr85m Ci Kr87 Ci 2.29E-08 Kr83 Ci
_7 L3 3
- C1 3 34E-08 2.61E-02 1
Xe135_
Ci 4.80E-08 Xe135n ci Xel38' Ci Xe131m Ci Ar41 C1
~
Xel33m Ci I
i I
n lotal Ci 1.14E-07 2.61E-02 l
2.
Iodines 1131 C1 2.62E-05 1.29E-06 I133 Ci 6.82E-05 I135 Ci Total Ci c.62F-05 6.95E-05 CONTINUOUS MODE liATCll MODE NUCLIDE UNIT QTR _1_
Particulates Sr89 Ci
~'
Sr90
_C_s 134,
C1 C1 Cs137 Ci Ba-La140 Ci CoS8 C1 4.20E-05 Co60 Ci 3.99E-06
_Qd109 -
Ci Eb_124 C1 l21 Ci
( @oS7 Ci Cel44 Ci 1.82E-06 _
Zr-Nb95 Ci e
Pb86 Ci l
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I'.
PINGP 158 Rev. 4 TAL. m IB EFFLUENT AND WA.iTE DISPOSAL SD!IANNUAL REPORT CASE 0US EFFLUENTS 3.
Particulates Sr85 Ci
, Fin 3 4 -
Ci
(.138 Ci Y88_
Ci An110M Ci 3.06E-05 b
I i
O 1
6-
?.
PIM P 158 Rev.
4 TAL 2A EFFLUENT AND WASTE DI:
aL SEMIANNUAL REPORT LIQUID EFFLUENTS - SUPJ!ATION OF ALL RELIASES r orAf' UNIT QTR L QTR,L
}...
A.
Fission and Activation Products Total Releagi W/0 H-3, Rad Gas, Alpha Ci s.06E-0/i 1.h E-04 1 1
- 557, Average Diluted Concentration pC1/mi 3.54E-12 4.99E-13 1
% of T. S. Annual Curic Design Objective 5.06E-03_l 1.93E-03 i
2 B.
Tritium Total Release ci 1.50E 02 1.21E 02 25%
l Average Diluted Concentration yC1/ml 1.05E-06 3.13E-07 I
% of T. S. Annual Design Objecti_ve Conc 2.10E 01 }
6.26E 00 C.
Dicsolved and Entrained Gases Total Rele n;e Ci 1.20E-02 1.56E-03
! 50%
Average D11utca Concentration pCI'/n1 8.39E-11 4.03E-12 D.
Gross Alpha Tota 1 ReIcase lCi l
2.24E-07 i S.60E-08__l 1 50% __j E.
Volume of Waste (Prior to Dilution)
[.J i t e rn l 3T23h'd7 l 3.355 67 [ l y%~] j i
'~~1.43E 11l 3787E i1 T {50f ] l F.
Volume of Dilution Water
,ters i
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7 PINGi 158 Rev. 4 TABLE 2A EFFLUENT AND WASTE DI SAL SEMIANNUAL REPORT f
LIQUID EFFLUENTS - SL:.IION OF ALL RELEASES Continuous Mode Batch Mode NUCLIDE UNIT QTR 1 QTR 2_
QTR _i_
QTR 2 l
Sr89 Cf l
Sr90 Ci i
i Cn134~
C1 Cal 37 Ci I_l_31 Ci CoS8 Ci
&_non-nv 2.73E-05 J.66E-04 5.25E-06 Co60 C1 1.54E-05 8.94E-05 Fe59 Ci Zn65 Ci
_?t:5 4 C1 Cr51 Ci Zr-Nb95 Ci Mo99 Ci Ba-lal40 Ci All10m Ci Na24 Ci illB2 Ci SlL 24 -
Ci 2.56E-05 1
Sr85 C1 Csl36 Ci Zr-Nb97 C1 1.13E-05 Cd109 Ci i
Rb88 C1 l
l Total C1 1.sgr-Os 2.78E-05 2.92E-04 5.25E-06
~
Continuous Mede Batch Mode I
NUCLIDE UNIT QTR l QTR L QTR L QTR L i
_Xcl33 Ci 1.16E-02 5.55E.01 Xel33m Ci 9.10E-05 Xel31m Ci Xel35 Ci 3.18FcQ4
- 1. 34 E-0_5 Kr85m Ci Kr85 Ci Kr88 Ci Total Ci 1.20E-02 1.56E-03 j
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PINCP 158 o e e-Rev. 4 TABI 3
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT l-1-81 through 6-30-81 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 332 Ci 42 1 50%
b.
Dry compressible waste, contaminated ft3 4067 equipment, evaporator, bottoms, etc.
C1 4.5 t 507.
c.
Irradiated components, control rods, ft3 etc.
Ci Nonc d.
Other (describe) f[.f None 2.
Estimate of rujor nuclide composition (by type of waste).
a.
Co-58 2.4 %
O CO-60 79.6 %
CS-134 3.0 %
CS-137 11.5 %
MN-54 3.5 %
b.
CO-58 7.4 %
CO-60 64_s %
CS-134 2.0 4 CS-137 19.5 %
FEsc 6.6 %
c.
None d.
None 3.
Solid Waste Disposition Number of Shipments Mode of Transportatie.
Destination 9
Truck US Ecology Richland, WA B.
Irradiated Fuel Shipments (disposition)
None.
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