ML19210E984
| ML19210E984 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/21/1979 |
| From: | Branagan E, Congel F, Pasciak W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19210E923 | List: |
| References | |
| NUREG-0598, NUREG-0598-DRFT, NUREG-598, NUREG-598-DRFT, NUDOCS 7912130353 | |
| Download: ML19210E984 (78) | |
Text
i, ENCLOSURE 2 NUREG-0598 Release of Radionuclides into the Susquehanna River from Three Mile Island Nuclear Station during the Period of 3/28/79 - 5/11/79 Data and Analysis Walt Pasciak Frank J. Congel Edward F. Branagan, Jr.
Radiological Assessment Branch Division of Site Safety and Environmental Analysis Office of Nuclear Reactor Regulation 1546 160
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- 353 791o1.90
Foreword O(March 28, 1979, a series of events occurred at Three Mile Island Unit 2, w5ich resulted in the release of approximately 600,000 of gallons contaminate,d water onto the containment floor.
Part of this liquid was discharged into the Susquehanna River over the period of March 28 through May 11.
This document presents data for these discharges, and analyses of their, consequences.
At no time did the releases endanger the health and safety of the public, nor did they result in significant environmental impact.
This document was assembled by members of the Radiological Assessment Branch staff. The analyses in the main body of it document were done by Walt Pasciak, and technical and editorial review was done by Frank J. Congel an'd Edward F. 9ranagan, Jr.
1546 161 Me me O
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Table of Contents Subiect Page 1.
Introduction..........................................................
I 2.
Ef fluent release paths and activity released.........
1 3.
Concentrations of radionuclides in water..............................
4 4.
Estimation of doses via consumption of fishes.........................
6 5.
Estimation of doses via consumption of drinking water.................
8 6.
Doses to fishes frca accumulation of radionuclides...................
9
- 7. Summary....................................................".r..........
10 8.
References.............................................................
10 A.
Appendix A:
O n s i te m e as u r eme n t s...................................... A-1 B.
Appendix B:
Discharge measurements................................... B-2
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Licensee's calculations...................................
C-1 C.
Appendix C:
1546 162 9
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List of Tables and Figures No.
Description Page Tables:
J-1.
Summary of radionuclides released to the Susquehanna River.......... 3 2.
Time-Space average concentration of nuclides in river water.........
5 3.
Estimated concentration of nuclides in fish flesh...................
6 4.
Estimated equivalent dose per fish meal............................. 7 5.
Estimated equil avent dose f rom drinking water....................... 8 6.
Estimated dose to fishes............................................
9 A-1 Concentrations of I-131 released from the IWTS flow path............. A-2 A-2 Concentrations of I-131 rel eased f rom the IWFS flow path............. A-3 A-3 Concentrations of various nuclides released from the WECST flow path.A-9 A-4 Dil ution factors for discharge permits............................... A-19 A-5 Concentration of I-131 from WECST A & B flow paths................... A-22 A-6 Concentration of I-131 from cil flow paths........................... A-26 B-1 I-131 grab sampl es at di scharge.................................... 8-2 B-2 I-131 grab samples at East dike
......................................B-10
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Figures:
1 Flow paths by which radionuclides were released into the river.......
2 A-1 Concentrations of H-3 prior to each discharge......................... A-37 A-2 Concentration of Co-58 prior to each discharge........................ A-38 A-3 Concentration of Co-60 prio_r to each di scharge........................ A-39 A-4 Concentration of Cs-134 & Cs-137 prior to each discharge.............. A-40 IS46 163 e
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1.
Introduction The purpose of this document is to present data on radionuclide releases made to Susquehanna River as a result of the incident at Three Mile Island Nuclear
~
Station during the period of 3/28/79 through acproximately 5/11/79, and to evaluate the health and environmental consequences of those releases.
The main body of this document presents methods used to determine the maximum doses that an individual would receive as a result of ingestion of drinking water and fish flesh, and also a method for determining maximum doses that could be received by the fish biota.
The calculated doses were well below the current criteria for public health, and protection of the environment.
Appendix A contains measurements made at the site prior to dilution with plant
~
and river flow and form the basis for calculating concentrations 'in the environ-cent and the resulting doses.
Appendix B contains data of measurements of concentrations at the-discharge and downstream of the discharge, and serve to provide backup evidence for the calculational method.
Most of the data of Appendicies A and B were infromally provided by Metropolitan Edicen Co., and their consultant, Porter-Gertz Consultants, Inc.
What wasen't supplied by these sources was based on calculations described in the text.
Appendix C contains dose calculations made by the license, and is presented for reference (1).
The results of their analysis are roughly comparable to the ones presented here and lead to the same conclusions regarding public health and protection of the environment.
1546 164 2.
Effluent release oaths and activity released Figure 1 depicts the liquid release flow paths by which radioactive materials were released into the Susquehanna River.
It also lists the total volumetric
' release, the aNra'ge volume per release, and average volume released per day.
for each flow path.
Table 1 lists the total activity of each nuclide released over the period.
Thelicensee'sdatainAppendixAshowthat!exceptfor t
Iodine-133, the entire spectrum of nuclides were released through the waste eNaporator condensate storage tanks (WECST) flow path.
Iodine _133,however1
~
was released from all flow paths except the Sec. Neut, path.
Table 1 also lists the expected activity that would be released annuall'y under normal operation according to the Final Environmental Statement (FES) for TMI, Unit 2 (1976).
As can be seen from comparison of the anticipated normal releases to the actual ones, for many nuclides the actual releases that occurred during the incident were much smaller than (or similar to) the findings of the FES, it can be concluded that these nuclide releases had no signi.ficant health or
\\
environmental effects.
The calculations which follow support.'this conclusion.
Table 1 Summary of Radionuclides Released to the Susquehanna and releases anticipated in FES Ratio of Activity Activity FES Anticipated Released to Radionuclide Released (Ci)
Annual Release (Ci)
FES Annual Release H-3 12.4 1000.
.01 Cr-51
.00079
.0088
.09 Mn-54
.00041
.00003 1.37 Co-58
,024
.095
.25 Co-60
.0075
.013
.58 Zr-95
.00005
.00072
.69 Nb-95
.00018
.0008
.23 2
Ag-110m
.0012 I-131
.239 2.7
.09 I-132
.00034
.052
.01 I-133
.00015
.20
.00 Xe-133
.012 3000. (air)
.00 Cs-134
.0025
.54
.00 Cs-136
.00092
.15
.00 Cs-137
.0062
.41
.02 La-140
.0048
.0032 1.50 Ba-140
.0042
.0030 1.40 1546 165
i h
Figure 1 j
Liquid Release Flow Paths e s o.. i
- 1,044,039 gal. f Total Releaso
- 1G2,026 gal.
]
Total lleleaso Avg. Per fielease -
5,748 gal.
40,155 gal, i52,202 gal.
5) f vg. Per Helease,
l
{
Avti. Per Day 3,600 gal.
Avg. Per Day j }
y s
Sec. Neut.*
WECST Tank A, B Unit 1 Unit 1 RML-G Station V
V RIVER m
^
Discliarge g
4 I
RML-7 IWTS IWFS k
LTI
- (
s 4
Ch Sumps Sumps Ch Unit 1,2 Unit 1,2 Ch j Total Release
- 4,584 700 gal.
, Total Release
- 7G7,840 gal.
l I
I 241,300 gal.
Avg. Per liclease - 47,990 gal.
[ Avg.Per Release 17,063 gul. (
Avg. Per Day 101,882 gal.
Avg. Per Day t
s s
- The sourco of water into the Secondary Neutralizing Tank is from the regeneration of tlio Illinois Water Treatment System demineralizer. Although samples aro taken for isotopic t nalysis tiiero has been no eviilonce of radioactivo contamination of this system, tlierefono,it is listeil to givo an idea of the volume T
of water passing tlirough this system.
3.
Concentration of radionuclides in water At least 17 isotopes were released from the WECST tanks in measurable concentra-tMons as indicated by Table 1.
Most of these were released in such low corcen-trations and at such infrequent intervals that their effect is considered unimportant in comparison.
The isotopes of most concern were H-3, Co-58, Co-60, Cs-134, and Cs-137.
Figures A-1 through A-4 of Appendix A depict the concentration of each isotope and relate it to the discharge permit number.
The discharge permit number can be equated to the period over which the discharge occurred by means of Tabel A-4.
As can be seen from Table A-4, successive numbers correspond to successive days, hence the figures display the release over time.
In addition to the isotopes described above, I-131 was also released from the WECST tanks as well as from the IWFS and IWTS flow paths.
The I-131 that was released is handled separately from those nuclides above because it was released from the three sources.
The concentration of the isotopes, H-3, Co-58, Co-60, Co-134 and Cs-137, in the river water is determined by the figures and by Table A-4.
These concentra-tion estimates are made by selecting a concentration value from each figure that is larger than the average value, and dividing that value by 10% of the dilution factor of Table A-4.
A detailed discussion of river flows with which the dilution factors were determined is contained in Reference (3).
Ten percent is used to be conservative and to not take credit for full river mixing.
Table 2 lists the estimates of the concentration in river water determined by this method.
The results in this table are used to calculate the dose to humans from consumption of drinking water and from consumption of fish flesh, as well as dose to fishes.
1546 167
-5 Table 2 Nuclide Concentration H-3 6.2 x 10*I pCi/1 f
Co-58 6.7 x 10'I pCi/1 Co-60 1.2 x 10'I pCi/1
-I I-131 6.2 x 10 pCf/1
-2 Cs-134 3.1 x 10 pCi/1
-2 Cs-137 9.3 x 10 pCi/1 The above value for I-131 was determined from the data in Table A-6, which lists the I-131 releases between 3/28/79 and 5/11/79 from all, known sources.
Included in Table A-6 is the time peried over which each releas~e was made, the release concentration which takes into consideration plant dilution flow but not river dilution flow, the activity released for each period, and the cumulative activity released.
The highest release concentration over the entire period was 2.8 x 10*4 pCi/1.
This value is conservative in comparison to the data of
~
~ ~
Table B-1 by over an order of magnitude.
The average release rates from the IWTS, IWFS, WECST, and Sec. Neut. flow paths was about 48,000 gal / day.
The average flew in the river over this period was about 34,000 cfs.
If the discharge flow were fully mixed with the river flow the discharge concentration 5
would be diluted by a factor 4.5 x 10.
As was done for the other nuclides in Table 2, for this calculation 10% dilution is assumed for conservatism, hence the average river water concentration of I-131 is 6.2 x 10'I pCf/1, which appears in the above table.
1546 168
i 6-4.
Estimation of doses via consumotion of fishes The dose from the fish consumption pathway is determined as follows.
The concentration of the nuclide n fish flesh is determined by multiplication of the concentration in water times the bioaccumulation factor.
This approach for determining the concentration in fish flesh is conservative as it assumes that the concentration in the flesh has come to equilibrium with the concentration in the water.
The time period necessary to reach equilibrium can be long, and with intermittent releases such as occurred at TMI it is doubtful that equilibrium would be reached even if the releases went on indefinitely.
Multiplying these concentrations listed in Table 2 by the appropriate bicaccumulation factors of Reg. Guide 1.109 (2) for freshwater fish results in the follgwing concentrations of radionuclides in fishes.
Table 3
"~
Nuclides Fish Concentrations H-3 56 pC1/kg Co-53 33 pCi/kg Co-60 6 pCi/kg I-131 9 pCi/kg Cs-134 62 pCi/kg Cs-137 182 pCi/kg 1546 169
Next, it was assumed that an individual could eat 0.25 kg of fish flesh at a meal, and no credit was taken for the decay of the nuclides in catching and preparing ' t.e fish.
This resulted in an estimated total body dose equivalent an adult individual would get from a meal of fish, based on dose factors in Reg. Guide 1.109, to be as follows.
Table 4 Nuclides Dose oer fish dinner
-6 H-3 1.5 x 10 mrem
-5 Co-58 1.4 x 10 mrem
-6 Co 7.1 x 10 mnem
-6 I-131 8.0 x 10 mrem" -
-3 Cs-134 1.9 x 10 mrem Cs-137 3.3 x 10-3,7,g
-3 Total 5.2 x 10 mrem
~~~
Even if this amount of fish were eaten by a single individual twice daily for three months the dose would still be less than one millirem.
On this basis, we conclude that no significant doses or health effects occurred as a result of fish consumption.
Because of the unrealistic conservatism built into this calculation, and because the result is so insignificant, calculations are presented only for whole body dose, and not for other body organs.
It is not anticipated that significant dosas would occur for the other organs.
1546 170
'5.
Estimation of Doses via Consumotion of Drinkina Water Estimation of the dose by consumption of drinking water is made by multiplication of the consumption of water, by the concentration of nuclides in the water, by the ingestion dose factor. This calculation is based on a sixty day period -
pth a consumption rate of one liter per day.
The concentrations given in Table 2 and the dose ingestion factors of Reg. Guide 1.109 result in the following estimated doses.
Table 5 Nuclides Dese (60 day)
~~
-4 H-3 3.9 x 10 mren
~
Co-58 6.7 x 10 mrem
-5 Co-60 3.4 x 10 mrem
~4 I-131 1.3 x 10 mrem
-4 Cs-134 2.2 x 10 mem
-3 Total 1.3 x 10 mrem Actually the dose would be expected to be significantly smaller than this because the nearest location at which drinking water is drawn from the river is 4.1 miles downstream and more than 10% dilution would be expected, and secondly the releases were intermittent and during most of the time no releases ~
were being made at all, or the actual concentrations being released were smaller than those used for this calculation.
1546 171
....m-.
On the basis of this number we conclude that there were no health effects of any significance as'sociated with this pathway.
e Doses to fishes from accumulation of radionuclides 6.
The dose equivalent a fish would receive can be calculated from the data of This is done here by making the conservative assumption that all the Table 3.
decay energy from radioactive disintegration of nuclides accumulated within a fish is absorbed in the tissues of the fish.
Multiplication of each value of Table 3, by its appropriate decay energy, times 60 days, times the appropriate unit conversion fctors results in Table 5, the dose to fishes.
Table 6 mrad /60 days Nuclide 0.003 H-3 0.230 Co-58 0.046
~ ~ ~ ~
Co-60 0.027 I-131 3.90 Cs-134 0.650 Cs-137 Total 4.9* mrem /60 days
- The mrad units are equivalent to mrem units in this instance as for this spectrum the principal forms of decay are $ particles, indicating a quality factor of 1.
1546 1712
10 -
This value is below the 10 CFR Part 50 Appendix I criteria for humans of 5 mrem total body,15 mrem skin, thus we conclude that these releases will not have a significant effect on the fish populations.
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7.
~ Summary n
-3 mrem due to The above calculations resulted in a total body dose of 5.2 x 10
-3 mrea due to drinking water consumption excessive fish consumption,1.3 x 10 In spite over sixty days, and a dose to fishes of 4.9 mrem over sixty days.
of the fact that these results are based on unrealistically conservative assumptions, they are small enough that they indicate that the health and safety of the public was not endangered, nor was there signif.icant environ-mental impact.
8.
References Porter, S.
W., Jr., Memorandum to J. Collins on " Data and Flowpaths for 1.
TMI Liquid Release Presentations of 5/16/79 and 5/21/79" dated May 15, 1979.
U.S. Nuclear Regulatory Commission Regulatory Guide 1.109, " Calculation 2.
of Annual Doses to Man from Routine Releases of Reactor Efflue Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,"
October 1979.
1546 173 e
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Hickey, Clarence, Jr., Robert B. Samworth, "The Non-Radiological Consequences 3.
A to the Aquatic Biota and Fisheries of the Susquehana River from the 1979
^
Accident at Three Mile Island Nuclear Station", Draft August,1979.
?ReportNUREG-0596,OfficeofNuclearReactorRegulation,U.S.'~ Nuc hRegulatory Commission, Washington, DC.
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Accendix A This appendix contains data regarding releases of radionuclides to the Susquehanna Riier during the period 3/28/79 through 5/10/79.
For the most part, it consists e
of activity and concentration prior to dilution with plant flow or river flow.
The first three tables, A-1, A-2, and A-3, list the activity and concentration of isotopes released from the IWTS,.IWFS, and WECST flow paths, respectively.
Note that only I-131 was released from the first two of these flow paths.
Table Table A-4 gives dilution factors for the releases listed in Table A-3.
A-5 gives further detail for the releases from the WECST flow path, and the last table, Table A-6, lists the I-131 releases from all three flow paths, Figures A-1, A-2, A-3, and A-4 depict the concentration of consecutively.
radionuclides released in highest concentrations over time from the WECST Figure A-1 is for H-3, A-2 for Co-58, A-3 for Co-60, and A-4 for tanks.
Cs-134 and Cs-137.
4 de 154L6 175 4
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m Table A-1 This table lists the concentrations of I-131 released frcm the It gives the period over which the Industrial Waste Treatment System.
discharge was made along with the total activity, gallons discharged, Also the calculated discharge the dilution factor, and discharge rate.
concentration is given.
1546 176 O
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IIIDUSTRIAL WASTE TREATMENT SYSTEM (IWTS)
(All data refers to I-131)
~
(pC1/cc)
Totat.ii Calc. Conc.
pCf Rate at Discharge _
Discharge (pCi'/hr)
(pC1/cc)
Gallons Discharged Avg l I
Start
- Stop, Avg. I-131
-7 6,469 1290.
1.58 x 10 400 6.33 x 10-5 27,000 3/28 3/28 2
0400 0900 7.5 x 10-10 7.5 g,
400 6,600 3/29, 3/29
<MOA 1315 1410 (Use 3 x 10~7)
-10 37 8.
3 7.5 x 10 400 15,000 3/29 3/29
<MDA 1610 1815 (Use 3 x 10~7)
-10 jg3 12.
4 6.74 x 10 445 134,700 >
3/30 3/30
<MDA 0300 1600 (Use 3 x 10~7)
-7 15,279 1910.
1.2 x 10 456
-5 69,600 3/30 3/30 5.8 x 10 1600 2400 2.5 x 10 92,112 3860.
-7 529
-4 187,200 3/31 3/31 1.3 x 10 (130 gpm avg.
0010 2400 disch. rate) 1.49 x 10 54,678 2280.
-7 561 8.36 x 10-5 172,800 4/1 4/1 (120 9pm avg.
0001 2400 disch, rate) 483 1.08 x 10 27,854 1510.
~7
-5 141,250 4/2 4/2 5.21 x 10 (125 gpm avg.
~
1850 disch. rate)
[
0001 1.86 x 10-7 400.1 -
578.
113 m
2.1 x 10-5 6,040 4/6 4/6 N
0310 0400 N
1 I
I I
i l
}
IWIS (Continued)
(pci/cc)
Total Release Calc. Conc.
'hC1 " '
Rate Start Sg Avg. 1-131_
Gallons Discharged Avg. OF at Discharge Discharge IpCi/hr)
(pCl/cc)
-8
-5 244 7.92 x 10 16,668 414.
4/6 4/7 2.02 x 10 218,000 0615 2230
-8 4/10 4/13 4.2 x 10 390,510 200 2.1 x 10 6,208 06.
-6 0550 0535
-9 1,322 63.
-0 360 7.8 x 10 4/14.
4/15 2.8 x 10 124,710 0515 0215
-9 21'.5 11.
s 4/17 4/17 1.2 x 10 4,730 126 9.5 x 10
-6 1415 1610
-9 524.6 37.
i 4/18 4/18 1.1 x 10 126,000 172 6.4 x 10
\\
-6 1000 2400
-0 2910.88 38,
-6 150 3.5 x 10 4/19 4/23 1.05 x 10 510,680 2400 0450
-9 261.67 7,
-7 150 2.5 x 10 4/25 4/27
.3.13 x 10 220,000 2123 1113
-9 688.8 8.
-7 190 1.9 x 10 4/27 4/30 2.4 x 10 756,000 1200 2400 Used average dilution Used average of IWTS I-131 concentrations from 3/28 to 4/2.
~1 No isotopic analysis available.
-7 g
factor of 400.
in the order *of 3 x 10 AlthoughanalysisshowedlessthanMDA,MDA'sdurin9thattimeperiodwererunnin9 3
2,3,4 for a conservative estimate.
Used 3 x 10 N
CD 1
i R
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Table A-2 This table lists the concentrations of I-131 released frem the Industrial Waste Filtering System.
It gives the period over which the discharge was made along with the total activity, gallons discharged, the dilution factor, and discharge rate.
Also the calculated discharge concentration is given.
1546 179 e
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IllDtibTRIAL WASTE FillERIllG SYSTEM (IWFS)
(All data refers to 1-131)
(pC1/cc)
Total.
4 D'istharge (pCi/cc)
Calc. Conc.
pCi Rate Start Stop Avg. 1-131 Gallons Discharged Avg. DF at Discharge Discharge fiCi/hr)
~I 3/30 3/30
<5.6 x 10
~
135.8 30.
64,050 467 1.2 x 10 1200 1630
-62 3/31 3/31 2.5 x 10 3
-0 25,500 100 2.5 x 10 241.3 85.
0140 0430
-62 4/1 4/l 2.5 x 10 3
-8 36,600 100 2.5 x 10 346.3 85.
0130 0534
~
x
-62 4/1 4/1 2.5 x 10 3
-8 41,850 100 2.5 x 10 396.
101.
i 1521 1915 N
-62 4/2 4/2 2.5 x 10 3
-0 41,700 100 2.5 x 10 394.6 67.
0515 1110
-6
-8 4/6 4/7 3.4 x 10 72,340 67 5.1 x 10 930.9 98.
1930 0450
-7
~9 4/10 4/10 3.8 x 10 56,040 67 5.7 x 10 80.6 11.
0645 1410
-6
~0 4/13 4/14 7.9 x 10 65,430 163 4.8 x 10 1,956.
144.
1140 0117 Cn
-9 A
4/16 4/16 4.3 x 10~
63,010 37'1, '-
1.2 x 10 102.6
,13.,...
1135 1915
~7 4
-8 4/20 4/20 5.25 x 10 3.86 x 10 150 3.1 x 10 77.
13.
CD 1535 2125 4/23 4/24 4.2 x 10~
6.'77 x 104
~0 150 3.1 x 10 108.
13.
1910 0310
-8 4
-8 4/27 4/28
\\
3.8 x 10 5.45 x 10 150 3.1 x 10 7.9 0.8 1400 0015
IWFS
~
(pCi/cc)
Total Discharge Calc. Conc.
pCi rate (pCi/cc)
Start Stop Avg. 1-131 Gallons Discharged Avg. OF at Discharge Discharge 'hidf/llrl
~Il 5/1 5/2 3.1 x 10 27,670 400 7.75 x 10 3.25 0.6
~0 2119 0300
-8 6.75 x 10'II 4.28 0.8 5/4 5/4 3.1 x 10 36,430 459 0800 1320 5/7 5/8 9.3 x 10 50,360 1000 2.63 x 10~0(2)
.0177 0.0
~II 1000 1200 5/10 5/10 2.85 x 10 26,060 708 3.3G x 10-8(2) 2.81 0.6
~0 0755 1230
-10 5/14 5/14 3 x 10 80,000 150 1.29 x 10 9.16 2.2
\\
~0
\\
0940 2345
~II 5/18 5/18 1.4 x 10 54,310 150 6.6 x 10 2.89 0.3
~0 0845 1740 (1) Estimated based on previous data b
(2) Actual conc based on a sample taken at RML 7 (plant discharge)
A Ch O
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J Table A-3 This table lists the concentrations of various nuclides released from the WECST tank for each discharge pemit.
It gives the total activity released under each discharge pemit along with the concentration in the tank prior to release.
1546 182 em
/
i d
LIOUID WECST RELEASES Total Discharge Concentration Activity Pediit (uCi/cc)
(Ci)
Number Radionuclide 45-79-L H
3.2E -2 0.547 3
51 1.65E -2 3.5E -4 Cr 54 6.244E -6 1.37E -4 Mn 58 5.757E -5 1.22E -3 Co 60 4.ll2E -5 8.74E -4 Co 134 1.654E -5 3.,52E -4 Cs I37 2.096E -5 4.44E -4 Cs 95 2.28E -6 4.83E -5 Zr 95 6.699E -6 1.42E -4 Nb 110m 1.87E -6 3.97E -5 Ag 46-79-L Co SE -6 1.4E -4 58
~-
60 SE -7 1.4E -5 Co 134 SE -7 1.4E -5 Cs 137 1E -7 2.8E -6 Cs 131 SE -6 1.4E -4 I
133 SE -6 1.4E -4 I
47-79-L H
3.48E -2 0.547 3
60 1.75E -5 1.9E -4 Co 137 1.62E -5 4.52E -4 Cs 1546 183
/
d LIOUIbWECSTRELEASES(Cont.)
Di harge Total Pennit Concentration Activity Nuinber Radionuclide (uCi/cc)
(Ci) 58 48-79-L Co 5.37E -5 1.47E -3 60Co 1.5E -5 4.1E -4 131 I 3.7E -5 1.01E -3 133 Xe 7.92E -5 (2.08E -3)"
58 49-79-L Co 1.6E -6 4.51E -5 60Co 1.14E -5 3.22E -4 131 I 4.2E -5 1.18E.-3 133 Xe 3.43E -5 (7.09E -4)*
137 50-79-L Cs 2.06E -5 5.77E -4 131 I 1.81E -5 5.07E -4 133 Xe 2.04E -5 (5.03E -4)*
3
- ~
51-79-L Co 6.38E -6 1.799E -4
~
137 5.98E -6' l.686E -4 Cs 131 I 4.57E -6 1.289E -4 133 Xe 1.983E -5 (5.6E-4)*
52-79-L Cancelled 3
53-79-L H
6.6E -3 0.086 60 Co 9.88E -6 2.79E -4 1546 184
/
d LIOUID WECST RELEASES (Cont.I Total-Disc rge Concentration Activity Permit (uCi/cc)
(Ci)
Number Radionuclide 131 7.08E -6 1.997E -4 I
133 2.33E -5 (3.01E -4)*
Xe 54-79-L H
0.2329 5.66 3
60 5.97E -5 1.67E -3 Co 134 1.186E -5 3.32E -4 Cs 137 4.31E -6
- 1. 21 E -4 Cs 133 7.46E -5 (1.83E-3)*
Xe 95 1.415E -6 3.959E -5 Nb 55-79-L Cancelled 0.0125 0.31 8 56-79-L H
58 8.5E -6 1.3E -4 Co 60 1.7E -5 2.6E -4 Co 137 6.7E -6 1.0E -4 Cs 131 4E -6 6E -5 I
57-79-L H
0.0295 0.785 3
58 6.75E -5 1.9E -3 Co 60 1.018E -5 2.87E -4 Co 131 5.6E -5 1.59E -3 I
"All analysis cata in parenthesis is questionable because of solubility of xenon, which is a noble gas, in water.
1546 185
/
LIOUID WECST RELEASES (Cont.)
Total Disch5rge Concentration Activity Perd t Number Radionuclide (uCi/cc)
(Ci) 57-79-L La 3.198E -5 9.02E -4 140 (con'd)
Xe 1.598E -4 (4.51E -3)*
133 132 1.22E -4 3.44E -3 I
II 2.71E -5 7.63E -4 Ag 58-70-L H
0.027 0.674 3
- 8 3.01E -4 8.55E -3 5
Co 134 1.2E -5 3.41E -4 Cs 137 2.98E -5 8.46E -4 Cs 131 7.44E -5 2.ll2E -3 I
133 7.04E -5 (1.999E -3)*
Xe
'59-79-L H
2.28E -2 1.44E -?
3 Co 5.lE -5 5.92E -5 58 60 2.lE -6 5.92E -5 Co 134 1.3E -6 3.67E -5 Cs 137 8.7E -6 2.45E d Cs 131 1.2E -5 3.38E -4 I
140 1.3E -6 3.67E -5 8a 140 5.0E -6 1.41E -4 La
- ine analysis ca:a in parenthesis is questionable because of solubility of xenon, which is a noble gas, in water.
1546 186
J LIOUID WECST RELEASES (Cont.)
Total Discharge Concentration Activity Permit (uCi/cc)
(Ci)
' Number
' Radionuclide 3
0.0265 0.306 60-79-L H
8 2.07E -4 3.26E -3 Co 60 1.40E -5 2.20E -4 Co 137 1.lE -5 1.73E -4 Cs 131 5.47E -5 8.62E -4 I
1O 1.56E -5 2.46E -4 La I
2.86E -5 4.5E
.4 Ag 3
2.17E -2 0.585 61 L H
58 7.98E -5 2.23E -3 Co 137 1.26E -5 3.52E -4 Cs 131 5.46E -5 1.52E -3 I
~~~
62-79-L H
1.6E -2 0.393 54 9.8E -6 2.74E -4 Mm 58 7.lE -5 1.99E -3 Co 60 7.8E -5 2.EE -3 Co 134 1.2E -5 3.36E -4 Cs 137 5.3E -5 9.24E -4 Cs 131 4.3E -5 1.20E -3 I
140 1.6E -5 4.48E -4 Ba 1546 187
'1 j
LIOUID WECST RELEASES (Cont.)
Total Discharge Concentration Activity Per5it Number Radionuclide (uCi/cc)
(Ci) i 3
63-79-L H
9.03E -3 0.175 131 1.91E -6 4.37E -5 I
64-79-L H
1.27E -2 0.285 3
137 5.3E -5 1.43E -3 Cs I3I 5.5E -5 1.48E -3 I
3 65-79-L H
1.11E -2 0.248 131 2.1E -5 5.92E -4 I
3 66-79-L H
1.17E -2 0.282 58 1.8E -4 4.95E -4 Co 60 4.9E -6 1.35E -4 Co 134 4.4E -6 1.21E -4 Cs 136 9.8E -6 2.70E -4 Cs 137 1.3E -5 3.56E -4 Cs 131 1.7E -5 4.68E -4 I
140 4.2E -6 1.15E -4 8a 67-79-L H
2.54E -3 6.3E -2 3
Cs 3.8E -6 1.06E -4 131 3.01E -6 8.43E -5 I
8.87E -3 2.18E -1 68-79-L H
5B 9.06E -6 2.54E -4 Co 1546 188
/
,J LIOUID WECST RELEASES (Cont.)_
Total Dischaige Concentration Activity Permft (uCi/cc)
(Ci)
Number Radionuclide 134 3.55E -6 9.94E -5 Cs 68-79-L 131 2.31E -5 6.47E -4 I
(cont.)
140 2.94E -5 8.23E -4 La 3
1.44E -2 3.61E -1 H
69-79-L 137 8.7E -6 2.44E -4 Cs 131 2.24E -5 6.27E -4 I
3.78$-4 140 1.35E -5 Ba 136 2.47E -5 6.29E -4 Cs 3
1.39E -2 3.43E -1 g.
70-79-L 9I 1.86E -5 5.21E -4 sr 134 2.0E -6 5.6E -5 Cs I37 9.4E -6 2.63E -4 Cs 131 2.22E -5
- 6. 21 E -4 I
140 1.27E -5 3.56E -4 Ba 3.959E -5 1.11E -3 Co 71 L 131 3.07E -5 8.59E -4 I
140 9.822E -5 2.75E -3 La 3
9.79E -3 2.46E -1 H
72-79-L 51 1.5E -5 4.29E -4 Cr 1546 189
i
.J LIOUID WECST RELEASES (Cont.)
Dishharge Total Pehnit Concentration Activity NuEber Radionuclide (uCi/cc)
(Ci) 58 72-79-L Co 2.3E -5 6.58E -4 60 (cont.)
Co 1.0E -6 2.86E -5 134 Cs 1.0E -6 2.86E -5 136Cs 2.2E -5 6.29E -4 137 Cs 7.2E -6 2.06E -4 131 I 1.7E -5 4.86E -4 140 Ba 7.2E -5 2.06E -4 133 I SE -7 1.43E -5 3
73-79-L H
1.03E -2 l.55E -1 134Cs 9.6E -7 1.776E -5 136 Cs 1.2E -6 2.22E -5 131
~
I 2.8E -5 5.18E -4 140 Ba 4.1E -5 7.58E -4 74-79-L H
7.52E -3 1.55E -1 58Co 3.2E -5 7.75E -4 134Cs SE -6
- 1. 21 E -4 137 Cs 1.6E -5 3.87E -4 131 2.4E -5 5.81E -4 I
140 BE -5 1.94E -3 Ba 1546 190
.2 LIOUID WECST RELEASES (Cont.)
Total Di charge Farmit Concentration Activity ifumber Radionuclide (uCi/cc)
(Ci) 3 75-79-L H
5.48E -3 5.48E -2 54 1.03 -6 9.46E -6 f4n 58 1.4E -5 1.39E -4 Co 60 9.4E -6 9.36E -5 Co 134 1.7E -6 1.69E -5 Cs 137 5.4E -6 5.87E -5 Cs 131 1.2E -5 1.19E -4 I
140 8.5E -6 8.46E -4 La
^^
1546 191
_9 e
4+
A
~'
./.
6 w-Hble A-4 This table lists the time period for each discharge permit pertaining to WSCST releases, along with the approximate river flow In addition, the volume released for each pemit for the time period.
The average dilution is listed with the appropriate dilution factor.
6 factor over the period was 3.2x10.
1546 192
~
/
1
.. ~ '
Dilution Factors Discnarge Permit Date and Time Approx River Gal.
Dilution""*
Number On Off AT(hr) Flow (CFS)-
Released Factor 45-79-L 3/28/79 3/29/79 0320 1230 43.16 104,000 5748**
1.8E+7 ~
46-59-L 3/31/79 3/31/79 0240 0710 4.5 62,000 5748 1.1E+6 m
47-79-L 4/1/79 4/1/79 0720 1504 7.73 55,000 5748 1.7E+6 48-79-L 4/5/79 4/6/79 1813 0750 13.61 124,000 5748 6.8E+6 49-79-L 4/7/79 4/8/79 1745 0150 8.08 68,000*
5748 2.2E+5 50-79-L 4/9/79 4/9/79 0155 0945 7.83 56,000 5748 1.7E+6 51-79-L 4/10/79 4/10/79 1125 1900 7.58 57,400*
5748 1.7E+6 52-79-L 53-79-L 4/12/79 4/12/79 0055 1230 11.75 87,800 5748 4.1E+6 54-79-L 4/13/79 4/14/79 0535 0440 23.05 87,800 5748 8.1E+6 55-79-L 56-79-L 4/13/79 4/13/79 0048 0449 4.01 87,800 5748 1.4E+6 57-79-L 4/15/79 4/15/79 0545 2015 14.50 76,000*
5748 4.4E+6 58-79-L 4/17/79 4/18/79 1345 1048 21.05 68,000 5748 5.7E+6 59-79-L 4/19/79 4/19/79 0135 2005 18.66
~62,500 5748 4.7E+6 60-79-L 4/20/79 4/21/79 1830 0255 8.41 55,700 5748 1.9E+6 61-79-L 4/23/79 4/24/79 0500 0230 21.50 38,600+
5748 3.3E+6 62-79-L 4/24/79 4/25/79 0950 0630 20.66 34,800 5748 2.8E+6 63-79-L 4/25/79 4/26/79 1742 1300 19.30 32,000 5748 2.5E+6 64-79-L 4/26/79 4/27/79 2130 1515 17.75 34,000 5748 2.4E+6 65-79-L 4/27/79 4/28/79 2115 1515 18.00 32,700 5748 2.4E+6 66-79-L 4/30/79 5/11/79 1810 1123 17.21 37,500 5748 2.6E+6 I546 193
/
j Discharge Permit Date and Time Approx River Gal.
Dilution Number On Off AT Flow (CF5)-
Released Factor 67-79-L 5/1/79 5/2/79
~
1.4E+6 1800 0420 10.30 41,100 6570-68 L 5/2/79
.5/2/79 1700 2318 6.30 39,300 6510 8.8E+5" 69279-L 5/4/79 5/5/79 0900 0415 19.25 32,100 6620 2.1E+6 70-79-L 5/5/79 5/6/73 0940 000f 14.41 31,500 6510 1.6E+6 71-79-L 5/6/79 5/7/79 1715 1130 18.25 32,300 6521 2.0E+6 72-79-L 5/7/79 5/8/79 1422 1310 22.80 30,700 6638 2.4E+6 73-79-L 5/9/79 5/9/79 0020 1140 11.33 28,800 3970 1.9E+6 74-79-L 5/10/79 5/11/79 1925 0750 12.41 26,500 5463 1.4E+6 75-79-L 5/14/79 5/14/79 1925 2255 3.50 22,800 5748 3.2E+5
' Values determined at 7 AM daily.
+These values are for mean daily flow
- Estimated values
- Values of 5748 gal represent a value calculated based on the average of several releases
^** Determined by dividing Gal. Released by product of AT and Approx. River Flow, and correcting for units.
1546 l94
/
.J Table A-5 This table lists data for I-131 releases between 3/28/79 and 5/ld/79 from the WECST A & B flow paths.
The table gives the discharge permit number, the daIe anE time the release occurred, the volume I-131, I-133 concentrations, I-131, I-133, Co-58, Co-60 activity, flow rate, and the counts per flow rate.
1546 195 O
e 4
e 6-W
L,1 QUID WECST RELEASES 131 133 58 C
Flow Rate MDCT Discharge Permit Date & Time Volume I
I 131 60 llumber On Off (Gal) pCi/cc pCi/cc I (pCi)
Co (pCi)
(GPH)
KGPH 45-79-L 3/28/79 3/29/79 4.5E+3 tione lione tione 1623 8.23 52 TT59 WECST-B 0320 1230 46-79.L 3/31/79 3/31/79 7.3E+3 SE-6 SE-6 140 140 27.0 67.2 7
WECST-A 0240 0710 47-79-L 4/01/79 4/01/79 6.19E+3 Hone tione flone 0
27.0 Ave.
4 65.9.
M9 WECST-B 0720 1504 48-79-L 4/05/79 4/06/79 6.9E+3 3.7E-5 lione 1010 1470 9.3 Ave.
lil
\\ 43.6 WECST-A 1813 0750
\\
49-79-L 4/07/79 4/08/79 5.44E+3 4.2E-5 tione 1180 45 20.3 22 TE2 WECST-B 1745 0150 50-79-L 4/09/79 '4/09/79 6.5E+3 1.81x10-5 tione 443 27.0 34.2 WECST-B 0155 0945 SI-79-L 4/10/79 4/10/79 4.llE+3 4.6E-6 tione 129 180 27.0 34.2
~6 WECST-A 1125 1900 52-79-L Cancelled Ln 53-79-L 4/12/79 4/12/79 3.41E+3 7.08E-6 tione 200 0
27.0 34.2 27D A WECSI-B 0055 1230 ch 11.0 34.2 54-79-L 4/13/79 4/14/79 6.46E+3 lione tione lione 1670 0
] WECST-A 0535 0440 os Cancelled 55-79-L 56-79-L 4/13/79
-1/13/79 2.84E*3 4t-6 tione 60 130 25.7 34.2 260 8
WECST-B 0048 0449 1900 9.72 54 57-79-L 4/15/79 4/15/79 7.1E*3 5.64E-5 lione 1590
~ 267 WECST-A 0545 2015
i yll10WECSIREIEASES 58 131 133 C0 Flow Rate HDCT Permit Date & Time Volume I
I 131 60 On Off _
_ (Gal)
_pci/cc
_ pCi/cc I (pCi)
Co (pCl)
(GPH)
KGPH Discharge lloinber 2112 8543 6.2 34.2 58-79-L 4/17/79 4/18/79 6.57E<3 7.44E-5 tione lione WECST-A 1345 1048 59-79-L 4/19/79 4/19/79 6.52E+3 1.2E-5 tione 338 1440 13.2 34.2 7
WECSI-B 0135 2005 60-79-L 4/20/79 4/12/79 3.04E+3 5.47E-5 tione 862 3260 6.39 52 226 WECST-A 1830 0255 61-79-L 4/23/79 4/24/79 7.1E+3 5.46E-5 tione 1520 2230 9.7 58 lione WECST-A 0500 0230 62-79-L 4/24/79 4/25/79 6.E49+3 4.3E-5 tione 1200 1990 6.09 46 YT8D WECST-8 0950 0630 63-79-L 4//2579 4/26/79 5.11E+3 1.91E-6 tione 43.7 0
13.13 54 0
WECSI-A 1742 1300 9.48 38 64-79-L 4/26/79 4/27/79 5,875 5.5E-5 flone 1480
_00 WECSI-B 2130 1515 592 0
11.72 38 65-79-L 4/27/79 4/18/79 5,875 2.6E-5
. flone 0
WECSI-A 2115 1515 66-79-L 4/30/79 5/01/79 6.345 1.7E-5 lione 468 495 9.81 38 M
1810 1123
] WECST-B
-6
$ 67-79-L 6/01/79 5/02/79 6570 3.01E tione 84.3 0
12.22 38 0
WECSI-B 1800 0420 5
68-79-L 5/02/79 5/02/79 6510 2.31E tione 647 254 20 38
-5
'l N
WECST-A 1700 2318 69-79-L 5/04/79 5/05/79 6620 2.24E' tione 627 0
22 30 D
WECSI-B 0900 0415 i
TM 0G 8
0 0
2 8
i i,
CP HK 3
5 5
5 3
e a) 3 3
5 RH 7
1 i
P 3
(
0 9
9 5
9 wG 1
1 t
~
~
)
ru l
6 p
00 00 8-00 5
e C
7 n
566T 7o 1
1
(
i 1
l 1
C oC 8 0 5 6
)
i C
9 6
8 1
8 p
1
(
2 5
8 1
6 8
4 5
5 I
1 3
1 SE S
A E
4 L
ER c
7 e
e 1 c/
e e
'E n
n TS 3
i n
n C
3 C
o o
5 o
o l
l f
f l
i f
E 1
p l
W D
I UQ I
L 5
5 c
5 5
5 I c E
E
/
2 7
E E
E 0
7 8
4 2
i 1
1 p 2 3
1 F
2 3
C 2
e) ml 8
0 3
ua 0
1 2
3 7
6 o(
5 5
6 9
4 l G 1
V 6
6 6
3 5
9 9
9 9
9
\\
7 7
7 7
7 f
/5
/0
/0
/0
/5 ef 60 73 81 94 15 mO 00 01 03 01 17
/0
/1
/1
/1
/0 T
5 5
5 5
5 i
e 9
9 9
9 9
t 7
7 7
7 7
6 bC
%C h
D a
/0
/5
/0
/0
/5 Dn 54 61 73 92 02 O
09 07 09 00 19
/0
/1
/1
/0
/1 5
5 5
5 5
e r
hie 9T 9T 9T 9T 9I at r cmb 7S 7 S 7S 7S 7S srm
- C C
- C
- C
- C i eu 0E 1E 2E 3E 4E DPl 7W 7W 7W 7W 7W l
/
J Table A-6
[
This table lists data for I-131 releases between 3/28/79 and 5/11/19.
The l
data list releases from all, sources.
The first two columns give the start and f
stodhtimeanddateforeachrelease.
The third column is the release source; 6
the fourth column is the concentration at the station discharge based on dilution with plant flow; the fif th column is the concentrat',on at the discharge location based on a gram sample; the sixth column is the activity released over the discharge period; and the last column is the cumulative activity released starting from 3/28/79 at 4:00 a.m.
b l99 W
9
/
i e
LIOUID EFFLUENT RELEASES (Tfl data refers to I-131) j(uCi/cc) 2 (uCi/cc)
~
Concentration Concentration Cumulative
~
at Station Discharge at Station Discharge pCi pCi Start Stoo Tank (Dilution Calc. )
(Grab Samoles)
Discharced Discharced 5
3/28 3/28 IWTS 1.6x10~7 4x10~9 6469 6,469.
0400 0900 at 1100 hrs.
3 3/28 3/28 WECST-B None None 6,469.
0320 0655 3/29 3/29 WECST-B None None 6,469.
0015 1215 7.5x10-10 5.4x10-10(7) 7.5 6476.
3/29 3/29 IWTS 1315 1410 at 1700 hrs.
3/29 3/29 IWTS
- 7. 5x10-10 l7.0 6493.
1610 1815 None#
6493.
3/30 3/30 SEC. NEUT.
None 0020 0753 1.2x10~9 135.86 6629.
3/30 3/30 IWFS 1200 1630 6.7x10-10 153 6782 3/30 3/20 ISTS 0300 1600 3/30 3/30 SEC. NEUT.
None None 6782 2020 2253 2.5x10-8 241.3 7023.
3/31 3/31 IWFS 0140 0430
- 5. 8x10-8 6,981 14C04.
3/30 3/30 IWTS 1600 2400 2.7x10-7 92,112 106116.
3/31 3/31 IWIS 0001 2400 3/31 3/31 WECST-A 3.0x10~9 140 106256.
0240 0710
~
1546 200
[
J LIOUID EFFLUENT RELEASES (All cata refers to I-131)
(pCi/cc) 2(pC1/cc)
) Concentration Concentration Cumulative at Station Discharge at Station Dischar9e pCi.
pCi Start Stoo Tank (Dilution Calc. )
(Grab Samoles)
Discharced Discharced 3/31 4/1 SEC. NEUT.
None Ncne 106256.
2230 1030 4/1 4/1 WECST-8 None Ncne 106256.
0650 1504 1.49x10-7 6.2x10-8(7) 54678 160934.
4/1 4/1 IWTS 0001 2400 2020 hrs.
4/1 4/1 IWFS 2.5x10-8 346.3 1612E0.
0130 0534 A/l 4/1 IWFS
- 2. 5x10-8
~ 396 161676.
1521 1915 4/2 4/2 IWTS 1.08x10-7 1.5x10-8(7) 27854 189530.
0001 1850 1130 hrs.
4/2 4/2 SEC. NEUT.
None Ncne 189530.
1650 1850 2.5x10-8 394.6 189925.
4/2 4/2 IWFS 0515 1110 7.3x10-10(7)
Ncne 189925.
4/3 4/3 SEC. NEUT.
None 1540 hrs.
1025 1915 2x10-10(7) 4/4 1x10-8 1815 hrs 1010 190935.
4/5 4/6 WECST-A 1.0x10-io 1813 0750 4/5 at 1305 hrs. *(7)
None 190935.
4/5 4/6 SEC. NEUT.
None 1800 0003 1.9x10-7 480.1 191415.
4/6 4/6 -
IWTS 0310 0400 1546 201
/
.,J
^
LIOUID EFFLUENT RELEASES (A1.1 data refers to I-131)
E j (pCi/cc) 2 (pCi/cc)
Concentration Concentration Cumulative at Station Discharge at Station Discharge uCi pC1 Start Stoo Tank
- (Dilution Calc. )
(Grab Samolesi Discharced Discharced 4/6 4/7 IWTS 7.9x10-8 5.9x10-9(7) 16668 208053.
0615 2230 4/6 at 1640 hrs.
5.1x10-8 930.9 209014.
4/6 4/7 IWFS 1930 0450
<6x10-0 None 209014.
4/7 4/7 SEC. NEUT.
None 6.3x10-9(7) 0355 1430 4/7 at 1045 hrs.
<4x10-8 1180 21019a.5 4/7 4/8 WECST-B
<3x10-10(7) 1745 0150 4/8 at 1100 hrs.
<4x10-8 None 210194.5 4/9 SEC. NEUT.
None 0945
<4x10-8 443 210637.5 4/9 4/9 WECST-B 0155 0945
<2x10-10(7) 4/9 at 1910 hrs.
5.7x10-9
<6.5x10-8 80.6 210718.1
/10 4/10 IWFS 4.2x10-9(7) 0645 1410 4/10 at 1710 hrs.
<6.5x10-8 129.0 210847.1 4/10 4/10 WECST-A 1125 1900
<l.1x10-8 None 210847.1 4/11 SEC. NEUT.
None 1.4x10-9(7) 1600 4/11 at 1620 hrs.
<3. 9x10-9 ( 7) 200.0 211047.1' 4/12 4/12 WECST-B 1.5x10-0055 1230 4/12 at 2000 hrs.
<3.6x10-9 None 211047.1 4/13 WECST-A None 2005 1546 202
LIQUID EFFLUENT RELEASES (All cata refers to 1-131)
~
j(uCi/cc) 2 (uCi/cc)
Concentration Concentration Cumulative at Station Discharge at Station Discharge pCi pCi Start Stoo Tank (Dilution Calc.)
(Grab Samoles)
Discharced Discharged
<3x10-9 None 211047.1 4/13 SEC. NEUT.
None 1150
<5.1x10-8 60.0 211107.1 4/13 4/13 WECST-B 0048 0449 4/10 4/13 IWTS 2.1x10-8
<2.3x10-8 6,208 217315.1 0550 0535 4/13 4/14 IWFS
- 4. 8x10-8
<1.6x10-8
. 1,956 219271.1 1.2x10-9(7) 1140 0117 4/13 at 1230 hrs.
-8 4/13 4/14 WECST-A None
<5.1x10 None 219271.1 0535 0440 4/14 4/15 Ib7S 7.8x10-9
<2.2x10-8 1325 220596.1 1.9x10-9(7) 0515 0215 a '14 at 1530 hrs.
= 4/15 4/15 WECST-A
<3.6x10i-1590.0 222186.1 0545 2015 2.3x10 '
4/15 at 1550 hrs.
4/16 4/16 IWFS 1.2x10~9
<3.0x10-8 102.6 2222SS.7
<3x10-'O 1135 1915 4/16 at 1610 hrs.
4/17 4/17 IhTS 9.5x10-9 7.5x10-8 21.5 222310.2 7.8x10-9(7) 1415 1610 4/17 at 1810
-8 4/17 4/18 WECST-A 6.5x10 2112 224422.2 1345 1048 8
4/18 WECST-B 4.6x10-9 7.78x109(7) 23 224445.2 1945 4.8x10-1546 203
/
/
,J ID LIOUID EFFLUENT RELEASES (All data refers to I-131)
^
i
~
(pCi/cc) 2 (uCi/cc)
- Concentration Concentration Cumulative at Station Discharge at Station Discharge uCi uCi Start Stop Tank (Dilution Calc.)
(Grab Samoles)
Discharced ~Discharced
- 6. 4x10-9 5.1x10-8 4.5 224449.7 4/18 4/18 IWTS 4.8x10-9(7) 1000 2400 4/18 at 1930 3.5x10-8 3.5x10-8 2910.88 227360.58 4/19 4/23 IWTS 2400 2450
-8 3.7x 31 5 227675.58 3.65x10g0uCi/cc(7) 4/19 4/19 WECST-B 0135 2005 4/19 at 2150 hrs.
3.1x10-8 3.1 10-8 77 227752.58 3
4/20 4/20 IWFS 5.75x10 'uCi/cc(7) 1535 2125 4/20 at 2010 hrs.
1.39x10-8 862 228614.58 4/20 4/21 WECST-A 1.65x10-"uci/cc(7) 1830 0255 4/21 at 1535 hrs.
1520 230134.58 6.9x10-10 ffgj jfjj WECST-A 3.1x10-8 None 230134.58 4/23 SEC. NEUT.
None 4.2x10-9(7) 1856 TANKS 8
108 230242.58 3.1x10-0 3.1x1{0(7) 4/23 4/24 IWFS 2x10-1910 0310 1.7x10-8 1200 231442.58 3x10m0(7) 4/24 4/25 WFCST-B 0950 0630 2x10-8 None 231442.58 4/25 SEC. NEUT.
None 0755 TANKS 1.4x10 43.7 231486.28
-0 4/25 4/26 WECST-A 9.8x10 1742 1300
-9 2.5x10-9 261.67 231747.99 4/25 4/27 IWTS 2.5x10 2123 1113 1546 204
r LIQUID EFFLUENT RELEASES
~
(Xi,1 data refers to I-131)
-3 3 (pCi/cc) 2 (uCi/cc)
Cumulative Concentration Concentration at Station Discharge at Station Discharge uCf pCi Start Stoo Tank (Dilution Calc.)
(Grab Samoles)
Discharced ' Discharged _
1.4x10-8 1480 233227.55 4/25 4/27 WECST-B 1.5x10~9(7) 2130 1515 3.1 x10-8 3.1x10i' 7.9 233235.85 4/27 4/28 IWFS 1.1x10 '
0015 3.1x10-8 None 233235.85 4/28 SEC. NEUT.
None 1.1x10'9(7) 0425 TANKS 3.1x10-8 592 233327.85 4/23 WECST-A 1515
~
-8 4/29 SEC. NEUT.
None 3.1x10 None 233827.85 4.0x10-10(7) 0830 TANKS
-8 4/30 SEC. NEUT.
None 3.1x10 None 233527.85 1515 TANKS 1.9x10~9 3.1x10-8 688.8 234516.65 1.7x10'9(7) 4/27 4/30 IWTS 1200 2400 1960 236476.65
~ 4/30 5.1 WECST-A 1810 1123 196 236672.55 5/1 5/2 WECST-B 1800 0420 None 236672.65 U-1 SEC. NEUT.<3x10-7 5/1 5/2 1801 0620 None 236672.65
<3.1 x10'8 5/1 5/2 IWFS 2119 0300
- 2. 31 x10-5 182 236354.65 5/2 5/2 WECST-A 1700 2318
<3x10-7 None 236559.55 5/3 5/4 U-1 SEC. 2155 1434 NEUT. TANK 1546 205
/
LIOUID EFFLUENT RELEASES (A)1 cata refers to I-131)
~.
j (pCi/cc) 2 (UCi/cc)
Concentration Concentration Cumulative
~
at Station Discharge at Station Discharge uti uCi Start Stoo Tank (Dilution Calc.)
(Grab Samoles)
Discharced Discharced 5/4 5/4 IWFS
<3.1x10-8 0800 1320 5/4 5/5 WECST-B 2.24x10-5 194 237098.65 0900 0415 5/5 5/6 WECST-A
- 2. 22x10-5 182 237230.65 0945 0005 5/6 5/6 U-1 SEC.
<3x10-7 237230.65 0013 0950 NEUT.
-5 5/6 5/7 WECST-A 3.07x10 422 237652.65 1515 1130 5/7 5/7 U-l SEC.
<8x10-8 237652.65 0325 1040 NEUT.
- 9. 3x10-II_
.0177 237652.67 5/7 5/8 IWFS 1000 1200 5/7 5/8 AWECST 1.7x10-5 269 237921.67 1422 1305 2.8x10-5 131 238052.67 5/9 5/9 BWECST 0020 1140
-8 5/9 5/9 U-1 SEC.
None 2.35x10 None 238061.85 1135 1840 NEUT.
-9 2.65x10-8 205 238266.85 5/9 5/11 IWTS 1.56x10 1225 1010
<2.85x10-8 2.8 238269.65 5/10 5/10 IWFS 0755 1230 5/10 5/10 U-l SEC.
None Ncne 238259.55 30 2215 NEUT.
~
1546 20g
/
,J I
LIOUID EFFLUENT RELEASES (All data refers to I-131)
{
j (pCi/cc) 2 (pCi/cc) 1 Concentration Concentration Cumulative e
~
at Station Discharge at Station Discharge uCi uCi Start Stoo Tank (Dilution Calc. )
(Grab Samoles)
Discharced Discharced 383 238652.55 5/10 5/11 WECST-A 1925 0750
- 2. 65x10-8 None 238652.65 5/11 5/11 U-1 SEC.
None 05 2110 NEUT.
3.69x10-8 None 238652.65 5/12 5/13 U-1 SEC.
None 15 1000 NEUT.
3x10-8 3.1x10-8 9.16 238661.31 5/14 5/14 IWFS 0940' 2345
~
23878.81 3.1x10-8 120 5/14 5/14 WECST-B 25 2255 7.3x10-10 2.92x10-8 10.4 238792.21 5/15 5/15 IWTS 1105 1535 2.59x10-8 None 238729.21 5/15 5/15 U-1 SEC.
None 10 0855 NEUT.
2.09x10-10 3.64x10-8 79.81 238872.02 5/15 5/18 IWTS 0425 2130 1.69x10-8 None 238872.02 5/18 5/18 U-l SEC.
None 30 0725 NEUT.
1.4x10-8 2.89 238S74.91 5/18 5/18 IWFS 45 1740 1.2x10-8 None 238874.91 5/19 5/19 U-1 SEC.
None 30 0448 NEUT.
5/19 WECST-A 40 4x10-8 1546 207 5/9 5/9 U-1 SEC. 1135 1840 NEUT.
/
J LIOUID EFFLUENT RELEASES
~
(A1,1 data refers to I-131)
~
(pC1/cc) 2 (pCi/cc)
[
) Concentration Concentration Cumulative at Station Discharge at Station Discharge pCi pCi Start Stop Tank (Dilution Calc.)
(Grab Samoles)
DischarcedDischarced 2.3x10-7 205 238257.99 5/9 5/11 IWTS 1225 1010 2.85x10-8 5/10 5/10 IWFS 0755 1230 5.9x10-9 5/10 5/10 U-1 SEC. 1030 2215 NEUT.
2.4x10-5 383 238640.99 5/10 5/11 AWECST 1925 0750 NOTES Calculated based on average tank sample and known dilution factor (df) data Discharges 1.
during the period of time that the tank was being released.
for IWTS are averaged over a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period.
Calculated by averaging the station discharge (RML-7) grab samplesIf the number ap 2.
taken during the time the tank was being released.
in this column is a "less than" (<) number, all the numbers averaged were less than MDA numbers and the MDA's were Jsed for the purpose of averaging.
This calculation is conservative in that it overestimates the actual I-13 concentration at the station discharge.
(See Attachment 7 for RML-7 grab samples).
WECST Tank releases are controlled by procedure HP 1621 which limits the The HP 1621 per.ait takes the specific 3.
release concentration to 0.1 MPC.
activity of all the isotopes.in the tank, assumes a dilution factor from MDCT flow and calculates a release rate so that 0.1 MPC is not exca while discharging.
(See Attachments 4, 5 and 6).
The source of water into the Secondary Neutralizing Tank is from the The regeneration of the Illinois Water Treatment System demineralizers.
4.
1546 208
/
A-2
_J Illinois Water Treatment System produces demin water by taking pretreated')
,j river water form upstream of the station discharge and sending it through
}$
demineralizers.
The water from the regeneration of these d,emineralizers
- does to the Secondard Neutralizing Tank.
All isotopic samples on this,
- tank after 4/2/79 showed no detectable I-131 or I-133.
~Since the input to this tank is essentially river water from upstream of a.
the station discharge, it is~ reasonable to assume that form 3/28 at 0400 jh'c"i se -
to 4/2 at 1850, no I-131 was released from this tank.
5.
See Table A-1 for IWTS calculations / assumptions.
6.
See Table A-2 for IWFS calculations /assumptiens.
7.
Data from REMP performed by Porter-Gertz Consultants.
1546 209 O
.A
.J Figures A-1 thru A-4 These figures depict the concentration of H-3, Co-53, Co-60, Cs-134, and Cs-137 released from the WECST tanks for various discharge intervals. The horizontal axis gives the discharge permit number which is monotonically related to time.
Table A-4 relates the discharge permit numbers to the time periods.
e
- 1546 210 m
W
t 3H LIQUID WECST RELEASE CONCENTRATION 23 0(23) 7 4
i N6, e
x y
O p
3 e
<tf5 e
m a
z ES e
o e
o 2
E
<t m
e ay
- e e
a ge 1
e e
e q
e e
A I
I I
I I
I I
CN 0
45 50 60 G5 70 75 80 hJ DISCllARGE PERMIT NUMBER
\\
8 i
58 I
Co LIQUID WECST RELEASE CONCENTRATION i
l 4-o
- o 3
i e
2 9
E tcHu d$
2 O
z~S oo "i
i -
m tn er b
Oe O
m o
N e
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mIe a
a I
a 1
i g
N 45 50 55 60 65 70 75 80 DISClf ARGE PERMIT NUMBER r
\\
60Co LIQUID WECST RELEASE CONCENTRATION 4
a'-
g i
I O
G O
n 8
i'
<txF Ti za 4tL UU za 8
e
<t m
d 2
m 9
e O
Ln 4
o e
l l
T I
I 9
I I
45 50 55 60 GS 70 75 80 N
U DISCll ARGE PEllMIT NUMBEIl
\\
(03/!Od) 90L x NOl1V81N3DNOO 3SV3738
..O,, 50Lg L e
o 4
m e
o o
O I
l l
l 2
s 0
o O
H<
O g
}--
o 2
o w
O o
2 5
m
=
O O 05 ce E
f wh O
=
W4g 5
w w
w J O O
C we o
eC e=
5 C CO O
l-e O
e G*
U e
O a
ow S
O e
o Od2 O
8 O
O e
I l
I
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o.
A o
e o
o n
d (03/!O )
90L x NOl1V81N3DNCO ESV3138
..#,, s 3?EL 1546 214
Accendix 3 This appendix contains data on concentration levels of I-131, measured at the disch'arge and at the East dike for the period bf 6/5/79 through 5/19/79. Table B-1 centains the data for the discharge h
and Table B-2 for the East dike. As the East dike samples (S-2) are from the opposite side cf the island as the radwaste discharge they serve to indicate ambient levels.
1546 215 O
O e
s e
Table B-1 This table gives the time and dates for which grab samples for I-131 in discharge water were taken. Except for a few cases, the measured discharge concentration was less than 40. pCi/1, with
~
a mode of about 31. pCi/t.
These values are based on minimum detectable activity levels as almost all of the sample measurements resulted in null detection.
1546 216 e
a e
Grab Samoles at Station Discharce (All data refers to 1-131. "less than"
=
values indicate less than MDA)
Concentration (uCi/ccl Time _
Date n
<1x10j 0400
<4x10 4/7/79 0800
<4x10:8 1200
<4x10 1600
<4x10-8 2000
<4x10-8 2400
<4x10j~
0400
<4x10 4/8/79 0900
<4x10-8 1600
<4x10-8 2000
<4x10~0~
2400
<4x10j~
0400
<4x10 4/9/79 0800
<4x10-8 1200 1600
<1x10~7
<1x10-2000
<2. 4x10-8 2400
<2.4x10 0400
<1x10~9' 2.9x1 4/10/79 0800 1200
<3x10-8 1600
<2.9x10-8 2000
<3x10" 2400
<2. 9x10-8
~9 0400
<6.02x10 4/11/79 1000
<3.66x10~9 1200
<6.58x10:9 1600
<6. 28x10,9 2000
<3. 05x10 2400
~
<S.65x10, 0400
<3.05x10 a 4/12/79 0800
<3.05x10~9 1200
<3.05x10~8 2000
<5.12x10 2400 1546 217
Cata Time Concentration (uCi/cc) r 4/13f79 0400
<5.12x10 0800
<3.05x10 8 8
~-
1200
<3.05x10 9 1600
<3.05x10 9 2000
<5.12x10 8 2400
<5.12x10
<5.12x10-8 4/14/79 0400 0800
<3.05x10,-
1200
<3.05x10 -
<3.05x10-8 1600
-8 2000 -
<5.12x10-8 2400
<5.12x10
<5.12x10-$
/15/79 0400
<3.05x10 l 0800 1200
<3.05x101
<3.05x10 $
1600
<5.12x10-2000 2400
<5'.12x10"
<5.12x10-j 4/15/79 0400 0800
<3.05x10
<3.05x10-8 1200
<3.05x10-8 1600
-8
~ -
2000
<5.12x10
<7.08x10-8 4/17/79 0800 1200
<7.02x10,8
<7.48x10 1600
<5.12x10-8 2000
<7. 6x10-8 2400
<7.67x10-8 4/18/79 0400 0800
<4.58x10 8 1200
<5.19x10 7.78x10-8 1800
-8 2000
<3. 05x10-8 2400
<4.43x10
-8 0400
<3.05x10 4/1?/79
<4. 7 x10-0800 1200
<3.1x158
<4.43x10-8 1600 1546 218
Date Time Concentration (uCi/cc)
<3.1x10-8 4/1h79(cent.)
2000
<3.15x10-8 2400
<3.05x10-8 4/20/79 0400 0800
<3.05x10-
-8 1200
<3.1x10
<3.1 x10-8 1600
<3.1x10-8 2000
<3.05x10-8 2400
<3.05x10-8 4 / 21/ 7 9 0400 0800
<3.05x10 8 1200
<3.05x10 8 1600
<3.05x10 8 2000 2.93x10-
<3.05x10-8 2400
<3.05x10-8 4/22/79 0400 0800
<3.05x10 8 1200
<3.05x10 8 1600
<3.05x10 8 2000
<3.53x10
' <3.1x10-8 2400
<3.1x10-8 4/ 22/7 9 0400 0800
<3.1 x10
<3.1x10-8 1200
<3.1x10-8 1600
<3.1 x10-8 2000
<3.1x10-8 2400
<3.1x10-8 4/24/79 0400 8
0800
<3.05x107 1200
- 1. 9x10-
<4.6x10-8 1600
<l.5x10-9 2000
<l.5x10-9 2400
<4.6x10-8 4/25/79 0400 0800
<3.1x10-
<3.1x10-8 1200
<3.1 x10-8 1600
<3.1 x10-8 2000
<3.1x10-8 2400 1546 219
Concentration (uCf/cc)_
Time Date
<3.1x10j" 0400 4/25/79
<3.1 x10 0800
<3.1x10-8 1200
<3.1 x10-8 e
r 1600
<3.1 x10-8 2000
<3.1x10-8 2400
<3.1 x10-8 0400 4/27/ 79
<3.05x10-8 0800
<3.05x10-8 1200
-8
' <3.1x10 1600
<3.1x10-8 2000
<5.65x10-8 2400
<3.1x10. 8 0400 4/28/79
<3.05x10-8 0800
<3.05x10-3 1200
<3.1x10 jost Sample 1600 2000
-8
<3.1x10 2400
<3.1 x10-8 0400 0800
<1.5xig-
- /29/79
<3x10 1200
<3.1 x10-8 1600
-8
<3.1 x10 2000
<3.1x10-8 2400
<3.1 x10-8
-g 0400 4/30/79
<3.05x10 0800
<3.1 x10-8 1200
<3.1 x10-8 1600
<3.1 x10-8 2000
<3.1 x10-8 2400
<3.1E -8 0001 5/1/79
<3.1E -8 0400
<3.lE -8 0800
<3.lE -8 1200
<3.1E -8 1600
<3.1E -8 2000 l546 220
Date Time Concentration (uci/cc)
~
5/2/h9 0001
<3.lE -8 0400
<3.1E -8 0800
<3.lE -8 1200
<3.1E -8 1600
<3.lE -8 2000
<3.1E -8 5/3/79 0001
<3.lE -8 0400
<3.lE -8 0800
<3.1E -8 1200
<3.1E -8 1600
<3.1E -8 2000
<3.1E -8 5/4/79 0001
<3.1E -8 0400
<3.1E -8 0800
<3.1E -8 1200
<3.lE -8 5/5/79 0001
<2'.9E -8 0400
<6.4E -8, 0800
<4E -8 1200
<3E -8 1600
<3.3E -8 2000
<3.1E -8
<3.1E -8 5/6/79 0001 0400
<3.1E -8 0800
<3.1E -8 1200
<3.1E -8 1600
<3.1E -8 2000
<3.1E -8 5/7/79 0001
<3.lE -8 0400
<3.1E -8 0800
<3.1E -8 1200
<3.1E -8 1600
<2.3E -8 2000
<2.9E -8 1546 221
~
Concentration (uci/cc)_
' Time _
Date_
~
<2.93E -8 0800
<2.38E -8 5/8/79 -
1200
<l.3E -8 1600
<5.2E -9 2000
<l.5E -8 0001
<l.7E -8 5/9/79 0400
<3E -8 0800
<2.6c -8 1200
<2.5E -8 1600
<2.82E -8 2000
<1.6E -8 0001
<l.6E -8 5/10/79 0400
<3.71E -8 0800
<3E 1200
<3.4E 1600
<3E -8 2000
<3.1E -8 0001
<2.8E -8 5/11/79 0400
<3.3E -8 0800
<3.6E -8 1200
<l.37E -8 1600
<l.37E -8 2000
<l.38E -8 0001
<2.96E -8 5/12/79 0400
<3.2E -8 0800
<l.8E -11 1200
<l.4E -8 1600
<3.5E -8 2000
<3.0E -8 0058
<9.78E -8 5/13/79 1200
<2.8E -8 0358
<3.2E -8 1600
<3.2E -8 2000
<3.4E -8 0015
<3.lE -8 5/14/79 1020
<3.lE -8 0800
<2.9E -8 1230
<3.2E -8 1607
<2.9E -8 2004 1546 222
Cate Time Concentration (uci/cc) 5/15/7 9 0005
<2.6E -8 0400
<3.2E -8 0800
<2.8E -8 1210
<3.3E -8 1600
<2.6E -8 2000
<3.0E -8 5/15/7 9 0001
<2.9E -8 0400
<3E -8 0800
<2.8E -8 1200
<3.3E -8 1600
<l.3E -8 2000
<l.9E -8 5/17/79 0005
<3.8E -8 0402
<l.9E -8.
1215
<2.0E -8 1600
<l.8E -8 2000
<3.07E -8 5/11/79 0003
<l.3E -8 0800
<2.19E -8 0900
<2.59E -8 1600
<l.15E -8 2000
<l.25E -8 5/15/79 0300
<l.20E -8 0400
<1.28E -8 0805
<1.2E -8 1546 223 e
2 -
g.
- 1 lW ~2]'
.2..
' ~ ~ -
Table B-2 T,his table summarizes measurements of I-131 in plant discharge water along the bst dike for the period of 4/5/79 through 5/18/79.
For a considerable number of measurements, the levels of I-131 were below the minimum detectable activity level.
1546 224 O
e 4
e w
4 e
O
[
e m
/
East Dike Discharce Analysis SAMPLE IDENTIFICATION DATE & TIME CONCENTRATION FRACTION RUMBER SAMPLED (uCi/ml) of (MPCT W dBW156 4/05/79
< 3E -7 (MDA)**
< l.0
- (ED) 1355 OBW 155 4/05/79
< 3E -7
< l.0 (Ed Discharge) 1555 OBW 222 4/06/79
< 7.4E -8
< 0.25 (ED) 1700 OBW 223 4/06/79
< 7.4E -8
< 0.25 (ED) 1700 OBW 224 4/06/79 4.4E -8 0.15 (ED) 1700 035 256 4/07/79 1.8E -7
~
0.6 (ED) 1200 05W 259 4/07/79
- 1. 2E -7
- O.4 (ED) 1200 OBW 324 4/08/79 4E -8
< 0.133 (ED) 0630_
OBW 330 4/08/79 4E -8
< 0.133 (ED) 1830 OBW 352 4/09/79 3E -7
< l.0 (ED) 1700 0070 4/10/79
< 3.0E -8
< 0.1 (ED) 0552 389 4/10/79
< 3.05E -9
< 0.01 (ED) 1400 OBW 390 4/10/79
< 3. 0E -8
< 0.1 (ED) 1640 OBW 426 4/11/79
< 3.23E -9
< 0.01 (ED) 0615
- East Oike (ED)
- Minimum Oetectacle Activity 1546 225
. 1-2 East Dike Discharce Analysis SAMPLE IDENTIFICATION DATE & TIME CONCENTRATION FRACTION HUMBER SAMPLED (uCi/ml) of (MPC) W
~
0157 4/11/79 6.5SE -8 0.22
- (ED) 1.700
- 0177
.4/12/79
< 3.05E -9
< 0.01 (Ed) 0500 0228 4/12/79
< 8.85E -9
< 0.03 (ED) 1700 276 4/13/79
< 4.5S5 -9
< 0.015 (ED) 0500 0326 4/13/79
< 3.05E -8
< 0.1 (ED) 1705 0372 4/14/79
< 3.05E -9
< 0. 01 (ED) 0500 0457 4/14/79
< 5.12E -7
< 0.17 (ED) 1700 0494 4/15/79
< 3.05E -8'
< 0. 01 (ED) 0500 0601 4/15/79 7.93E -8 O.25 (ED) 1700
~
0664 4/16/79
< 4.58E -8
< 0.15 (ED) 0500 0762 4/16/79
< 5.12E -8
< 0.171 (ED) 1700 0829 4/17/79 SAMPLE LOST (ED) 0500 0929 4/17/79 1.51E -7 0.5 (ED) 1700 0972 4/18/79 1.85E -9 0.62 (ED) 0500 1094 4/18/79 2E -7 0.67 (ED) 1700 1546 226
/
East Dike Discharce Analysis.
4 FRACTION CONCENTRATION of (MPC) 'd SAMPLE DATE & TIME (pCi/ml)
IDENTIFICATION SAMPLED _
NUMBER
,=
0.67 2.01E -7 4/18/79 3120 2130 (ED) 0.65 1.98E -7 h148 4/19n9 0500 (Ed) 0.5 1.5E -7 4/19n9 1160 1700 (ED VALVE LEAK 0FF) 0.49 1.48E -9 4/19/79 1255 1700 (ED) 0.5 1.5E -7 4/19/79 1267 1400 (ED) 0.47 1.42E -7 4/19n9 1268 1400 (ED VALVE LEAK 0FF) 0.244 7.32E -8 4/19n9 1308 1820 (ED nISCHARGE) 0.55 1.68E -7 4/1999 1311 1940 (EAST DIKE CHANNEL RUN OFF) 0.46 1.39E -7 4/21M9 1439 0500 (ED)
< 0.15
< 4.58E -8 4/21/79 1531 1700 (ED) 0.47 1.4E -7 4/22/79 1574 0500 (ED)
SAMPLE LOST 4/22/79 1688 1700 (ED) 0.37 1.12E -7 4/22n9 1744 1820 (ED VALVE LEAK OFF)
< 0.15
< 4.58E -8 4/? R9 1746 1825 (ED) 1546 227
/
,e-
,/
East Dike Discharce Analysis SAMPLE IDENTIFICATION DATE & TIME CONCENTRATION FRACTION NUMBER SAMPLED (uCi/ml) of (MPC) W 1729 4/23/79 1.0E -7 l
0.33
- (ED) 0500 4/i3/79
< 3.1E -8
< 0.10
[
- 1854 (Ed) 1700 1880 4/24/79
< 4.6E -8
< 0.15 (ED) 0556 1989 4/24/79
< 3.1E -8
< 0.10 (ED CHANNEL RUN OFF) 2036 4/25/79
< 3.1E -8
< 0.1 (ED) 0500 2153 4/25/79
< 4.6E -8
< 0.17 (ED) 1700 2223 4/26/79 1.25E -7 0.42 (ED) 0547 2313 4/26/79
< 4.6E -8 '
< 0.15 (ED) 1700 2339 4/27/79
< 4.58E -8
< 0.15 (ED) 0500-2466 4/27/79 1.2E -7 0.4 (ED)
'1700 2544 4/28/79
< 4.68E -8
< 0.16 (ED) 0500 2641 4/28/79
< 4.6E -8
< 0.15 (ED) 1700 2687 4/29/79
< 3.1E -8
< 0.1 (ED) 0500 2777 4/29/79 6E -8 0.2 (ED) 1700 2838 4/30/79
< 3. 05E -8
< 0..-
(ED) 0500 '
1546 228
. ~. -
j
. East Dike Discharce Analysis SAMPLE IDENTIFICATION DATE & TIME CONCENTRATION FRACTION NUMBER SAMPLED (uCi/ml) of (MPC) W 2936 4/30/79
< 4.6E - 8
?
< 0.15 (ED) 1700
< 3.1E - 8
< 0.10 3002 5/01/79 (ED) 0515 3088 5/01/79 7.02E - 8 0.234 (ED) 1530 3148 5/02/79 8.0E - 8 0.267 (ED) 0555 3241 5/02/79
< 3.05E - 8
< 0.10 (ED) 1700 3292 5/03/79 7.3E - 8 0.243 (ED) 0630 3412 5/03/79 9.6E - 8 O.32 (ED) 1645 3545 5/04/79
< 3.05E - 3
< 0.10 (ED) 1700 3611 5/05/79
< 4.E - 8
< 0.13 (ED) 0500 3696 5/05779 7.3E - 8 0.24
' ~
(ED) 1656 4036 5/06/79
< MDL 4E - 8
< 0.13 (ED) 0500 4113 5/06/79
< MD L 3.1 E - 8
< 0.1 (ED) 1700 4168 5/07/79 8E-8 0.27 (ED) 0500 4251 5/07/79
< 3.3E - 8
< 0.11 (ED) 1700 4311 5/08/79
< MDL 2.96E - 8
< 0.09 (ED) 0500 1546 229
/
East Dike Discharce Analysis SAMPLE IDENTIFICATION DATE & TIME CONCENTRATION FRACTION NUMBER SAMPLED (uCi/ml) of (MPC) W 4192 5/08/79
< MDL 2.0E - 8
<t0.06 (ED) 1700-4465 5/09/79
< MDL 3.2E - 8
< 0.11 (ED) 0500 4526 5/09/79
< MDL 3. 21 E - 8
< 0.11 (ED) 1700 4585 5/10/79
< 5.3E - 8
< 0.18 (ED) 0500 4654 5/10/79
< 2.4E - 8
< 0.08 (ED) 1700 4727 5/11/79
< MOL 3.5E - 8
< 0.12 (ED) 0500 4809 5/11/79
< MOL 3.4E - 8
< 0.11 (ED) 1700 4835 5/12/79
< 2.4 E-11
< 0.00008 (ED) 0500 4885 5/12/79
< 3.05 E-8
< 0.1 (ED) 1600 4919 5/13/79
< 3.05 E-8
< 0.10
' ~
(ED) 0500 5000 5/13/79
< 3 E-8
< 0.1 (ED) 1700 5049 5/14/79
< 1.2 E-8
< 0.04 (ED) 0500 5138 5/14/79 5.5 E-8 0.18 (ED) 1700 5196 5/15/79 SAMPLE LOST (ED) 0500 5275 5/15/79
< 3.3E-8
< 0.11 (ED) 1700 1546 230
/
J Accendix C This appendix contains the licensee's analysis of the data for this period.
It is presented for reference. Table I is a comparis'en of doses to i
imaximum individual for drinking water, fish consumption, and b'oating activity, 8
- Table II gives data on effluent releases for the period, Table III depicts the liquid release flow paths, Table IV summarizes the radienuclides that were released, Table V summarizes the H-3 concentrations at the Columbia water treatment plant, and Table VI discusses gross gamma measurements.
Many of the data presented here are redundant with earlier portions of this document, and are presented here only to keep the licensee's analysis intact.
0 15'46 23l we me k
/
5/15/79 ;i t
l TAllt.E I C0tlPARIS0 tis OF DOSES TO tlAXIttilti INDIVIDilAll DRINKING TREATED SilSf}UEIIANNA RIVER WATER DOUllSTREAlf 0F 7tfI the people drinking water downstream of TtlI received the same dose as people drinking wStSf'u'pstream of,
j tiote that Hil.
tiote that the 1979 dose did not change significantly from the 1978 dose.
Columbia (1) (2)
(4)
Intake Actual 3/28 to 5/11 (3)
Forty-Five t
(5)
Environmental Upstream Control mrem Calculated from Day Sample Dose from Actual Release Data Fraction of 45 day Downstream Dose lleasurements in the Downstream Dose Allowable mrem (6)
Critical 3/28 to 5/11 Environment 3/28 to 5/11 Tecimical Naturel l'a thway thicl ide_
Organ 1979 1978 1979 1979 Specification Doso Backgroundi
\\
l mrem 1rinking I
mrem Ja ter Thyroid (0.04
( 0.05
( 0.04 f.0. 011 0.6 mre'm
'none i'
I
)tinking 3
Whole 0.002 0.002 l
0.002 0.00003 0'~6'mr em
.00,04
- l' i
g
.Jater Body
\\
i e'
E "U
I Thyroid
/,,0.02 4 0.02 4 0.02 0.004 0.6 mrem none Inting 3
Whole 0.00005 0.00005 0.00004 0.00004
'~0'.'6 mrem
.00001 j
fish 11 llody loating Whole 40.0000003 40.000002 4 0.000001 0.0000003 0.6 mrem none 1
f I
I Body 10TES TO TABLE I All data extrapolated to 5/11 f rom actual environmental monitoring r'esults available throughM/3.
Dose to maximum individual.
] '.
All results less than minimum detectable activities are averaged as if the minimum detectable activity were present.
A Realistic model using Reg. Guide 1.109 for ingestion dose factors and fish concentration factors.
m L.
The Tech Spec allowable annual dose to the poptil.ation per site from 1,1 quids (exclusive of noble gases) is 5 mrem /yr.
N i.
J4 M
.. _3
- i. Based"on 730 liters ll 0/yr, 21 Kgr. fish /yr; a backgroun(1 11 of~250 pCi/ liter.
2 The resultant dose from all other radionucliden dischnrged uere a factor of 100 less than I, except for 11.
/
_/
M LE II TMI EFFLUENT WATER RELEASE FOR THE PERIODS 3,/28/7 9-5/11/79 vs. 3/28/78-5/11/78 Total Volume 131 3
for Units 1 & 2 Total I
H Total-Curies Released Activity Activity Activity excluding Year (ft)
(Ci)
(Ci)
(Ci) 3u & 131,.
1978 1.55E +9 16.0
< MD A
- 15.9 0.1 1979 3.86E +9 12.7 U.239 12.4 0.06**
- Minimum Detectable Activity Due primarily to refueling of Unit 1 1546 233
l l
5/15/79
~
'I'Mll.E III Three Mile Island
{. -' /,
n,....,
Lilluid Release Flow Paths Flow Path E a Evaporator Flow path Pa. State Seconilary Normal l
h Epicore 1 Plow path nu Water sr Heutralizer Radwaste
/
c Epicore 2 Flow path Quality Tank Systems 4
d New System Flow path Radiation Monitor j
Units 1 & 2 A& il and Unita 1&2 Sampler-l
't.
l b,
i Tiquid Radiation m
C f
Monitor #6*
?
Zooling (Station
_l
[@'
n I' owe r Discharge
' >, _ (_
r
___ _ _,_A LJ
{O s
0 Slowdown A
i A
\\,
e Y
r Industrial Liquid Industrial Waste Filter Radiation N
Waste Treatment System Monitor jiN A
- 7 System A
A
.C.
j
m Unit 1, 2
Unit 1, 2
A
,A
(
Ch Station r-Security Y N
l Fence y,
Flow path F Flowpath G n-sodium iodide crystal, a single channel analyze)
- Liquid radiation monitors consist of a shielded Monitor 36, a strip chart recorder in each control room and alarms in both control rooms.
automatically closes the discharge valve when it alarms.
7 v
e
>1
\\
Tf.
t
a
- m-TA3LE IV J
SU).SARY OF RADIONUCLIDES N
RELEASED TO THE SUSOUEHANNA RIVER 3/28/-5/11/78' 3/28/-5/11/79 Activity Activity Radionuclide (Ci)
(C1) 3 17 12 H
Cr 2E -3 7E -4 51
~
1 54 1E -3 4E -4 g
58 7E -2 2E -2 Co 60 1E -3 7E -3 Co 95._95 :
4E -3 2E -4 g
2 110 4E -3 1E -3 Ag 131 13 _4 0.2 7
132 O
3E
-4 e
I 133 O
1E -4 I
133 2E -2 1.2E -2 Xe 134 2E -2 2E -3' Cs.
136
- 1E -4 9E -4 Cs e.. - -
137 1E -2 6E -3 Cs 4E -5 9E.13 140Sa 140La Total (less H3 +1's) 1.32E -1 5.92 E-2 1546 235
~
e e
O e
e o
e e e e
e*
O a
-N N4
- 6 '
e m eem :
m en w em p
+e ee F Me e
e me m=
e m o see se em he e
/
/
/
_J TABLE V SU10fARY OF 3H CONCENTRATION AT COLI.MBIA WATER TREATMENT PLANT 2/21 - 6/1[74 Ave 230t 170 pCi/1 6/5 - 12/31/74 Ave 3031 200 pCi/l 1/75 - 6/75 Ave 2391 246 pC1/1 7/75 - 12/75 Ave 3001 270 pC1/1 1/76 - 12/76 Ave 1691 100 pCi/1 1/77 - 12/77 Ave 1961 44 pC1/1 e
1/78 - 12/78
. Ave 2971 240 pCi/1 General Ave 248 9
1546 236 e
e e
Y me e e
m-O e
eo e Oee e e
e e W
m o me e e en es e eem 8M
- M M *
- emD
~
/
j 5/15/79 TABLE VI h
CRO$S CMDfA MEASURDENTS
=
Except for s=all quantities of naturally occurring Potassium -40 and Radiu= -226, no ga==a e=itting radionuclides were =easured in the Susquehanna River during the period 3/28/79 through 5/11/79.
The control station measurements made upstream from TMI were 40K ed 226,, _
g greater than the downstream measure =ents for the o
1546 237 e
~
4 g
i s
?
.f.-
e+
=,
~
1..
,,,.. -.-.......... -.....