ML19332D039
| ML19332D039 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 06/30/1989 |
| From: | NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML19332B573 | List: |
| References | |
| NUDOCS 8911290328 | |
| Download: ML19332D039 (10) | |
Text
p:, ;pgf"~ ~
m q;
+
'i m
~
' 'NORTZERN: STATES'PONER' COMPANY
" lM
'MONTICELLO' NUCLEAR CENERATING; PLANT:
License;No.;DPR-22' Ih <
EFFLUENT'AND WASTE DISPOSAL SEMIANNUAL REPORT-I
(
' Period : Jan - Jun 1989 Supplemental-Information:
~
.K
. ~
Cili (Regulatory-Limits:
Quarterly levels requi' ring reporting to i
Nuclear Regulatory Commission l
m g
r i.Ak Noble: Gases *
- 5 mrad / quarter
- gamma [ radiation 110 mrad / quarter beta radiation r
.4;n3. Long Lived Iodines, Particulates,
- ~.5 TritiumD:
4
-7.5' mrem /quarterfdose to any organ.
C;cLiquid Effluents.:
t 0
7 l.5 mrem / quarter dose to'the total body.
5:0: mrem / quarter dose to any~ organ 2.: Maximum Permissible Concentrations
~
i
- A..~ Noble ~ Gases-:.
.10 CFR Part120, Appendix B,~ Table II, Column i l
~
4 fB.fLong1 Lived Iodiner,.Particulates, and' Tritium :-
210 CFR Part 20, Appendix B, Table II, Column 1 LC'.' Liquid Effluents 10 CFR;Part 20, Appendix B, Table II,. Column 2 2.0'E-4:uci/m1'for dissolved and entrained gases s;
- 3. Average-Energy 1
(Not. Applicable) e, c-
- ?V
\\
i e
L R
+
b u.-
9I
~
.POge
'2:
1.e a
EFFLUENT AND: WASTE DISPOSAL. SEMIANNUAL REPORT Period;: Jan - Jun 1989' i
..i.
Supplemental Information (continued)
' 4.; Measurements and Approximations of Total Radioactivty
[
A. Noble Gases :
Continuous gross activity monitors in Reactor Building Vent and Plant i
Stack exhaust streams.
Weekly isotopic analysis of steam jet
~
air ejector stream.
Monthly analysis of storage tank contents.
c B..; Iodines in Gaseous Effluent f
Continuous monitoring with charcoal cartridges in Reactor Building
-Vent and Plant Stack exhaust streams with weekly-analysis.
C.
Paritculates in Gaseous Effluent :
Continuous monitoring ~with particulate filters in Reactor Building Vent and Plant Stack exhaust streams with weekly analysis.
D.LTritium in Gaseous Effluent :-
Continous monitoring with silica gel cartridges in Reactor Building Vent and Plant Stack exhaust streams with weekly analysis.
E.
Liquid Effluents :
s 1
Tank sample analyzed prior to each planned release and continuous monitoring of gross activity during-planned release.
'5.
Batch Releases A.
Liquid :
- 1. Number of Batch Releases 0
2.. Total Time Period for Batch Releases NA min i
- 3. Maximum Time Period for a Batch Release NA min
- 4. Average Time Period for a Batch Release NA min
- 5. Minimum-Time Period for.a Batch Release NA min
- 6. Average River. Plow During Release NA cf/sec B.
Gaseous :
- 1. Number of Batch Releases 10
- 2. Total Time Period for Batch Releases 7355.0 min
- 3. Maximum Time Period'for a Batch Release 3293.0 min
- 4. Average Time Period for a Batch Release 735.5 min
- 5. Minimum Time Period for a Batch Release 26.0 min
p~
PageJ~3-s 4
ih;,
r 5,
s EFFLUENT'AND WASTE DISPOSAL: SEMIANNUAL REPORT Period :: Jan -1Jun -1989 g
'v.>....
Supplemental,Information (continued).
.6.
Abnormal; Releases-
- A.-Liquid
1= Number of Releases-O.
.2.
Total Activity Released NA Ci
-B.-(Gaseous :
-3.. Number of Releases 1
- 2. Total Activity Released 0.9 Ci E
i.
Y 4
)
i i
{f: -
m Pag 3 4~
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT I
~
Period:: Jan - Jun 1989 i
g L.
Table:1A-Gaseous Effluents - Summation of all Releases Units l 1st Qtr l 2nd Qtr Est. Total l
l-Error, (_
A.[ Fission & Activation gases
[
1.
Total Release Ci 1.44E+03 1.28E+03-5.00E+01 l 2.
Average Release Rate uci/sec 1.85E+02 1.63E+02 r
3.
Percent _ Tech Spec Qtrly Reporting Level i
Gamma Radiation 6.37E+00 5.42E+00-Beta Radiation i
3.86E+00 3.33E+00 B.' Iodines 1.
Total-I-131 Release Ci 1.80E-02 4.45E-02 5.00E+01 l 2.
Average I-131 Release Rate uci/sec 2.31E-03 5.67E-03 C.
Particulates 1.
Total Particulates Ci 3.85E-03 7.16E-03 5.00E+01 l-
- 2. Average Release Rate uci/sec 4.95E-04 9.llE-04 3.
Gross Alpha Radioactivity Ci 4.810-06 9.80E-06 Ef. Tritium 1.
Total Release Ci 2.65E+01 2.70E+01 5.00E+01 l
- 2. Average Release Rate uci/sec 3.41E+00 3.43E+00
'E.
Percent Qtrly Tech Spec Reporting Levels l
l l
'l. Iodines, Particulates, l
l 1 7.71E+01-l l
and Tritium I
l 2.34E+01 l.
Paga 5.
- a.
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jan - Jun 1989 Table'1B Gaseous Effluents - Elevated Releases l
l Continuous Mode l
Batch Mode j
Nuclides Released l Unit l 1st Qtr l 2nd Otr i ist Qtr l 2nd Qtr l
- 1. Fission Gases j
KR-85 Ci 4.17E+01 4.33E+01 0.00E+00 0.00E+00 l
KR-85M Ci 1.94E+00 1.65E+00 0.00E+00 0.00E+00 KR-87 Ci 9.56E+00 8.41E+00 0.00E+00 0.00E+00 KR-88 Ci 6.46E+00 5.55E+00 0.00E+00 0.00E+00 KR-89 Ci 1.84E+02 1.69E+02 0.00E+00 0.00E+00 KR-90 Ci 6.23E+00 5.76E+00 0.00E+00 0.00E+00 XE131M Ci 2.03E+00 1.91E+00 0.00E+00 0.00E+00 XE-133 Ci 4.44E+02 3.85E+02 4.87E-04 9.72E-03 1
XE133M C1 2.63E+00 3.58E+00 0.00E+00 0.00E+00 XE-135 Ci 1.01E+01 8.74E+00 4.45E-04 1.04E-02 XE135M Ci 1.41E+01 1.29E+01 0.00E+00 7.28E-04 i
XE-137 Ci 2.40E+02
-2.21E+02 0.00E+00 0.00E+00 g
XE-138 Ci 1.89E+02 1.74E+02 0.00E+00 0.00E+00 XE-139 Ci 1.85E+01 1.71E+01 0.00E+00 0.00E+00 Total for Period Ci 1.17E+03 1.06E+03 9.32E-04 2.08E-02 l
1 2.
Iodines j
i l
I-131 Ci 3.17E-03 7.91E-03 0.00E+00 7.31E-09 I-133 Ci 1.23E-02 1.63E-02 0.00E+00 0.00E+00 I-135 Ci 1.51E-02 1.16E-02 0.00E+00 0.00E+00 l
Total for Period Ci 3.06E-02 3.59E-02 0.00E+00 7.31E-09
- 3. Particulates
~
MN-54 Ci 6.01E-07 3.90E-06 0.00E+00 0.00E+00 CO-58 Ci 0.00E+00 8.15E-07 0.00E+00 0.00E+00 FE-59 Ci 0.00E+00 7.70E-07 0.00E+00 0.00E+00 CO-60 Ci 4.76E-06 1.82E-05 0.00E+00 0.00E+00 j
)
ZN-65 Ci 0.00E+00 1.25E-06 0.00E+00 0.00E+00 l l
l CS-137 Ci 1.13E-05 8.94E-06 0.00E+00 0.00E+00 i
BA-140 Ci 1.10E-03 5.83E-04 0.00E+00 0.00E+00 CE-141 Ci 0.00E+00 2.99E-07 0.00E+00 0.00E+00 i
CE-144 Ci 3.79E-07 0.00E+00 0.00E+00 0.00E+00 SR-89 Ci 5.40E-04 0.00E+00 0.00E+00 0.00E+00 l SR-90 Ci 2.50E-06 0.00E+00 0.00E+00 0.00E+00 Total for Period Ci 1.66E-03 6.17E-04 0.00E+00 0.00E+00 Anclysis of Sr-89 & 90 for the 2nd Qtr was not completed in time for this report, results will be included with the next semiannual report.
Page 6
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jan - Jun 1989 Table 1C Gaseous Effluents - Building Vent Releases l.
l Continuous Modo Batch Mode l Nuclides Released Unit l ist Qtr l 2nd Qtr 1st Qtr l 2nd Qtr
- 1. Fission Gases KR-85 Ci 1.23E-02 1.28E-02 0.00E+00 0.00E+00 KR-85M Ci 7.66E-01 5.80E-01 0.00E+00 0.00E+00 KR-87 Ci 3.81E+00 2.97E+00 0.00E+00 0.00E+00 KR-88 Ci 2.60E+00 1.95E+00 0.00E+00 0.00E+00 KR-89 Ci 7.23E+01 6.02E+01 0.00E+00 0.00E+00 KR-90 Ci 2.45E+00 2.05E+00 0.00E+00 0.00E+00 XE131M Ci 1.14E-03 1.04E-03 0.00E+00 0.00E+00 XE-133 Ci 5.88E-01 3.57E-01 0.00E+00 1.30E+00 XE133M C1 1.92E-02 1.59E-02 0.00E+00 0.00E+00 XE-135 Ci 3.99E+00 2.66E+00 0.00E+00 4.80E-01 XE135M Ci 5.56E+00 4.59E+00 0.00E+00 1.04E-04 XE-137 Ci 9.44E+01 7.84E+01 0.00E+00 0.00E+00 XE-138 Ci 7.40E+01 6.06E+01 0.00E+00 0.00E+00 XE-139 Ci 7.30E+00 6.09E+00 0.00E+00 0.00E+00 Total for Period Ci 2.68E+02 2.20E+02 l'.00E+00 1.78E+00 2.
Iodines I-131 Ci 1.48E-02 3.65E-02 0.00E+00 1.27E-04 I-133 Ci 1.40E-01 2.13E-01 0.00E+00 0.00E+00 I-135 Ci 1.93E-01 2.94E-01 0.00E+00 0.00E+00 Total for Period Ci 3.47E-01 5.43E-01 0.00E+00 1.27E-04
- 3. Particulates CR-51 Ci 3.89E-05 3.32E-04 0.00E+00 0.00E+00 l MN-54 Ci 2.23E-05 2.48E-05 0.00E+00 0.00E+00 j CO-58 Ci 2.82E-05 4.10E-05 0.00E+00 0.00E+00 CO-60 Ci 2.21E-04 2.51E-04 0.00E+00 0.00E+00 ZN-65 Ci 1.11E-04 1.13E-04 0.00E+00 0.00E+00 CS-134-Ci 0.00E+00 4.14E-06 0.00E+00 0.00E+00 CS-137 Ci 3.74E-06 2.00E-05 0.00E+00 0.00E+00 BA-140 Ci 1.52E-03 5.70E-03 0.00E+00 0.00E+00 l
CE-141 Ci 3.01E-05 5.53E-05 0.00E+00 0.00E+00 SR-89 Ci 2.17E-04 0.00E+00 0.00E+00 0.00E+00 SR-90 Ci 1.50E-06 0.00E+00 0.00E+00 0.00E+00 l 1
l l
-Total for Period Ci 2.19E-03 6.55E-03 0.00E+00 0.00E+00 l Analysis of Sr-89 & 90 for the 2nd Qtr was not completed in time for this report, results will be included with the next semiannual report.
l l
Page 7
7
+
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jan - Jun 1989
- v Table 2A Liquid Effluents - Summation of all Releases" l
Units
.lst Qtr
- 2nd Qtr Est. Total l
~ Error, %
.A.
Fission & Activation products 1.
Total Release (not including tritium, gases, alpha)
Ci 0.00E+00 0.00E+00 0.00E+00'
- 2. Avg Diluted Concentration uci/ml 0.00E+00 0.00E+00 B.< Tritium Jl 1.
Total Release Ci 0.00E+00 0.00E+00 0.00E+00 l l
2.
Avg Diluted Concentration uci/ml 0.00E+00 0.00E+00 C.
Dissolved and Entrained Gases 1.
Total Release Ci 0.00E+00 0.00E+00 0.00E+00 l 2.: Avg Diluted Concentration uci/ml 0.00E+00 0.00E+00 D.
Percent Qtrly Tech Spec Reporting Level i
1.
Whole Body Dose-0.00E+00 0.00E+00 l t
2.
Organ Dose 0.00E+00 0.00E+00 l E. Gross' Alpha Radioactivity l
1.
Total Release 1
Ci l 0.00E+00 l 0.00F.+00 l 0.00E+00-l lF. Volume of Waste Released l
Liters l 0.00E+00 l 0.00E+00 l 6".00E+00 l
'lF-.
Volume of Dilution Water Used l Liters l 0.00E+00 l 0.00E+00 l 0.00E+00 l 9
Table 2B Liquid Effluents
.l l
Continuous Mode l
Batch Mode l
.l'Nuclides Released Unit I ist'Otr l 2nd Otr i lst Qtr l 2nd Otr l
None Released This Period
g Pag 3 8-E EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT
- Period : Jan-- Jun 1989 Table 3 Solid Waste and Irradiated Fuel Ehipments
-- Ai Solid Waste Shipped Offsite for Burial or Disposal (not irradiated fuel) 1.. Type of Waste Units 6-month Est. Total Period-Error, %
- a. Spent resins, filter sludges, Cu. Meter 3.50E+01 evaporator bottoms, etc.
Ci-1.03E+02 5.00E+01 e
b.
Dry. compressible waste, Cu. Meter 1.70E+01 contaminated equipment, etc.
Ci 6.78E-01 5.00E+01 c.
Irradiated components, Cu. Meter 2.23E+00 control' rods, etc.
Ci 5.92E+04 5.00E+01-d.
Other (describe) 2.-Estimate of major nuclide Nuclide l
Percent composition (by type of waste)
A CR-51 9.75E-01 MN-54 1.48E+00 FE-55 2.94E+01 FE-59 l 5.55E+00 l
.l CO-60 2.70E+01 l-l ZN-65 3.24E+00 l l
SR-89 1.81E-01 l l
I-131 4.49E+00 l l
CS-134 l 2.57E+00 l l
CS-137 1.89E+01 l
l BA-140 1.93E+00 l
LA-140 l 7.01E-01 CE-141 3.29E-02 B
CR-51 1.77E+00 l
MN-54 l 2.83E+00 l
FE-55 l 3.81E+01 l
CO-60 l.2.93E+01 l l
ZN-65 l 3.04E+00 l l
I-131 l 1.85E+00 l l
CS-134 l 2.52E+00.l l
l CS-137 9.50E+00-l LA-140 1.11E+00 l C
CR-51 7.24E-01 l
_MN-54 l 3.15E+00 l FE-55 l 4.83E+01 l l
CO-60 l 4.43E+01 l
giir
[h g Pages 9'
v+-
-EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period =: Jan'- Jun~ 1989 sw Table 31fSolid Waste.and Irradiated Fuel Shipments
?
.;n
- 13. Solid waste disposal Number of Mode of Destination
' Shipments Transportation 8-Truck
. Chem-Nuc Inc., Barnwell, SC.
2 Truck US Ecolocy, Richland, WA.
A B.? Irradiated Fuel Shipments
- 1. Disposition
' Number of Mode.of Destination Shipments Transportation None This Period
...! L C '. 7 Shipping Container and Solidification Method No.-
. l Volume Activity.
Type of l Container Solidification M3 Ci Waste Code Code:
=89 5.83E+00 1.57E+01 A
A D
(
t89-01'
-7.'42E-01' 2.22E+04 [
C B.
89-05 7.42E-01_
1.99E+04 l C
B 89-06 5.83E+00' 1.39E+01 l A
l A'
D l
- 89-08.
7.42E-01;u 1.71E+04 l C
l B-89-09 5.83E+00 1.99E+01-l A
-l A
D
'89-12 5.83E+00 l 1.97E+01 l A
l A
D 189-13 5.83E+00 l 1.98E+01-l A
l A
l D
- 89-14
1.70E+01-l 6.78E-01 l B
l L
l 89 5". 8 3 E+ 0 0 - l 1.43E+01 l A
l A
l D
i
--ContainerLCodes :
Solidification Codes :
~L - LSA C'- Cement A.-EType A U - Urea Formaldehyde
.B - Type B D - Dewatering
~
LQ - Large-Quantity i
l'
Page 10-
/
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT Period : Jan - Jun 1989 i
N;tes ':
1, Release of individual' noble gas isotopes from the plant stack was datermined using an. isotopic analysis at the steam jet air ejector.
.X9-133, Xe-135, Xe-138, Kr-85m, Kr-87, and Kr-88 were measured and us0d to characterize the mode of gas release from the fuel.
Other r
significant noble gases were determined using known ratios, the measured
- total offgas holdup system delay time, and the known fraction of the offgas* stream released via the gland exhauster.
2.:.An isotopic' analysis for noble gases is normally not possible at th3 building vents.
Individual isotopes are generally below their lower limit-of detection (LLD).
Therefore, for reactor building. vent releases, tho noble gas isotopic mixture is assumed to be the same as the mixture
~
1 determined at the steam jet air ejector.
)
i i
-