ORP-TAD-77-2
AN ANALYSIS OF LOW-LEVEL SOLID
RADIOACTIVE WASTE FROM
LWRs THROUGH 1975
NOVEMBER 1977
U.S. ENVIRONMENTAL PROTECTION AGENCY
OFFICE OF RADIATION PROGRAMS
WASHINGTON, D.C. 20460
-------
AN ANALYSIS OF LOW-LEVEL SOLID RADIOACTIVE
WASTES FROM LWRs THROUGH 1975
by
J. W. Phillips
Gary A. Gaul
Office of Radiation Programs
U. S. Environmental Protection Agency
401 M Street, S.W.
Washington, D. C. 20460
-------
PREFACE
The Office of Radiation Programs (ORP) of the Environmental Protection
Agency carries out a national program designed to evaluate public health
impact from ionizing and nonionizing radiation, and to promote develop-
ment of controls necessary to protect the public health and the environ-
ment. This report provides the technical information necessary for ORP
to evaluate the environmental aspects concerning the transportation and
disposal of low-level radioactive solid wastes generated by light-water-
cooled nuclear power plants. Furthermore, ORPs current estimates of the
quantity and radionuclide composition of low-level radioactive wastes
which will shipped offsite for burial from a 1000 MWe LWR operating at
80 % capacity are presented. This information is also being used by ORP
in the development of environmental radiation protection criteria and
generally applicable environmental standards for low-level radioactive
waste managment practices.
David S. Smith
Director
Technology Assessment Division (AW-459)
-------
TABLE OF CONTENTS
Page
Abstract
Introduction 2
Purpose 2
Source of Data 3
BWR Volume 4
BWR Activity 4
PWR Volume 4
PWR Activity 5
Summary 5
Major Radionuclides Found in Solid Radioactive Waste 6
Conclusion 7
ii
-------
List of Tables
Table 1
Table 2
Table 3
Table 4
Table 5
Table 6
Table 7
Table 8
Table 9
Table 10
Table 11
Table 12
Table 13
Table 14
Table 15
Tables 16-a
thru 16-e
Tables 17-a
thru 17-h
Page
Comparison of Previous Studies 8
BWR Annual Volume and Activity Shipped 9
& Prorated to 3400 MWt and 80% Capacity
PWR Annual Volume and Activity Shipped -13
& Prorated to 3400 MWt and 80% Capacity
BWR Actual Volume Shipped per Unit - m3/yr 18
BWR Annual Volume Shipped per Unit - m3/yr 19
Prorated to 3400 MWt and 80 % PCF ;
BWR Actual Activity Shipped per Unit - Ci/yr '• 20
BWR Annual Activity Shipped per Unit - Ci/yr 21
Prorated to 3400 MWfc and 80% PCF
PWR Actual Volume Shipped per Unit - m3/yr 22
PWR Annual Volume Shipped per Unit - m3/yr 23
Prorated to 3400 MWt and 80% PCF
PWR Actual Activity Shipped per Unit - Ci/yr 24
PWR Annual Activity Shipped per Unit - Ci/yr 25
Prorated to 3400 MWt and 80% PCF
BWR - Average Values 26
PWR - Average Values 27
Minimum Value of the Correlation Coefficient, 28
r, to Show Significance at the 95% Probability
Level
Estimated Volumes and Activities of Solid Waste 29
from LWRs
PWR Category A for 1975
PWR Category A for 1976
30
35
iii
-------
List of Tables
Tables 18-a
thru 18-d
Tables 19-a
thru 19-g
Tables 20-a
thru 20-b
Tables 21-a
thru 21-e
Tables 22-a
thru 22-f
Tables 23-a
thru 23-b
Tables 24-a
thru 24-d
Tables 25-a
thru 25-e
Table 26
Table 27
Table 28
Table 29
Table 30
PWR Category B for 1975
PWR Category B for 1976
BWR Category A for 1974
BWR Category A for 1975
BWR Category A for 1976
BWR Category B for 1974
BWR Category B for 1975
BWR Category B for 1976
Categories A & B -^ Pressurized Water Reactors
Categories A & B - Boiling Water Reactors
Relative Composition of Low-Level Solid
Waste from LWRs
Composition of Solid Waste by Nuclide - NRG
Composition of Solid Waste by Nuclide - Dames
& Moore
Page
43
47
54
56
61
67
69
73
78
80
83
84
85
iv
-------
List of Figures
Page
Figure 1 Annual Volume of Waste Shipped vs. Number 86
of Years of Operation- BWR (Linear)
Figure 2 Annual Volume of Waste Shipped vs. Number 87
of Years of Operation- BWR (Exponential)
Figure 3 Annual Volume of Waste Shipped vs. Number 88
of Years of Operation- BWR (Power)
Figure 4 Annual Activity of Waste Shipped vs. Number 89
of Years of Operation- BWR (Linear)
Figure 5 Annual Activity of Waste Shipped vs. Number 90
of Years of Operation- BWR (Exponential)
Figure 6 Annual Activity of Waste Shipped vs. Number 91
of Years of Operation- BWR (Power)
Figure 7 Annual Volume of Waste Shipped vs. Number 92
of Years of Operation- PWR (Linear)
Figure 8 Annual Volume of Waste Shipped vs. Number 93
of Years of Operation- PWR (Exponential)
Figure 9 Annual Volume of Waste Shipped vs. Number 94
of Years of Operation- PWR (Power)
Figure 10 Annual Activity of Waste Shipped vs. Number 95
of Years of Operation- PWR (Linear)
Figure 11 Annual Activity of Waste Shipped vs. Number 96
of Years of Operation- PWR (Exponential)
Figure 12 Annual Activity of Waste Shipped vs. Number 97
of Years of Operation- PWR (Power)
-------
AN ANALYSIS OF LOU-LEVEL SOLID RADIOACTIVE HASTES FROM
LWRs THROUGH 1975
by
J. W. Phillips
Gary A. Gaul
Office of Radiation Programs
,S. Environmental Protection Agency
4(11 M Street, S.'J.
Washington, n.C.
Abstract
A 1975 study by the U.S. Environmental Protection Agency (EPA)
which considered operating data from light-water-cooled nuclear power
plants through 1974 resulted in projected volumes of waste
considerably greater than that which was being used at the time !\y tho
Atomic Energy Commission (now the Nuclear Regulatory Commission) in
environmental impact statements. A current study by the Nuclear
Regulatory Commission (NRC) resulted in estimated volumes of waste
which are in relative agreement with the 1°!75 EPA study. Another
recent study by the Atomic Industrial Forum (AIF) concluded that tho
volume of waste from an LWR will continue to increase over the first
ten years of life and then level off at a value approximately twice
that calculated by the NRC or the EPA.
In consideration of the wide disparity of data bases and.
conflicting conclusions, this study will update the previous EPA study
in an attempt to substantiate either the NRC study or the AIF study.
In addition, this study will also provide a break down of projected
annual volumes by type of waste, i.e., demineralizer resins and filter
sludge, evaporator bottoms, and contaminated trash, and also identify
the relative composition of the wastes by major nuclides. These
latter results will be compared with similar results from the NRC
study and a recent study prepared by Dames ?< Moore for the New York
State Energy Research and Development Authority.
-------
Introduction
This report is the result of a study conducted by the Office of
Radiation Programs of the United States Environmental Protection
Agency (EPA). This study investigated the volume and radioactivity of
solid wastes being shipped for burial from light-water-cooled nuclear
power plants (LWRs), and the relative composition of these wastes with
respect to major radionuclides.
The results of this study will be used by the EPA in (1) its
review of the environmental impact in nuclear power plants, (2) for
improvement in predictive models, and (3) to provide additional data
for use in EPA's program to develop environmental radiation protection
criteria for radioactive waste management and environmental standards
for low-level radioactive waste disposal.
Purpose
In an attempt to stabilize the current controversy over the
question of the quantity of solid waste, and activity, the average
reference LWR produces in a year the EPA undertook an independent
study to analyze available information from nuclear power plant
operating reports. An EPA study reported in 1975 (Ma-75) looked at
the average quantities of waste reported as being shipped for burial
and concluded that the average annual volume for a BWR was 35,000
cubic feet (990m3) and for a PWR 21,000 cubic feet (595m3). A study
by the NRC (Be-77) reported in January of 1977 also concluded that the
average annual volume of waste from a BWR was 35,000 cubic feet
(990m3) but for a PWR was only 15,500 cubic feet (440m3). A more
comprehensive study by NUS (Mu-76) for the Atomic Industrial Forum has
reported estimates for BWRs of 55,000 cubic feet per year (1560m3/yr)
and for PWRs a volume of 40,000 cubic feet per year (1130m3/yr).
These values are summarized in Table 1 along with estimates of the
radioactivity contained within these wastes by the NRC.
Instead of trying to pinpoint a specific value to typify an
average annual waste volume for both BWRs and PWRs, we decided to
evaluate the data in two ways. First we assumed that the reported
volumes were strictly a function of plant housekeeping activities and
radwaste management activities and independent of plant size, i.e.,
the reported values would be typical of plants of all sizes. Second,
we assumed that the reported data were primarily a function of plant
size and power generation. In actuality we feel that the true case is
somewhere between these two cases and that the results of our analysis
would then define a lower and an upper boundary about the true
conditions.
In order to simplify the study we considered only those plants
which have been operating more than one year and have an electrical
-------
rating of more than AGO MWe. We did not include the first year if the
plant operated for less than 6 months of that year. If the first year
of operation was between six and eleven months the data was prorated
to a full year. Plants with units of different size were also
excluded if one of the units was less than 500 MWe. The actual
annual data were then prorated to a 3400 MWt reference plant with an
80 percent plant capacity factor (PCF) using the actual gross thermal
power generated during the year. The actual and prorated data for
BWRs is given in Table 2, and for PWRs in Table 3. Hence further the
actual data will be referred to as the lower limit and the data
prorated to 3400 MWt and 80% PCF will be referred to as the upper
limit. These data were then tabulated in terms of. the number of years
of operation, and averages calculated for each year of operation. See
Tables 4 through 11. This procedure resulted in four sets of average
values, each with an upper and lower limit, to be analyzed for
significant statistical correlation with respect to the number of
years of operation. These values are summarized in Table 12 for BWRs
and Table 13 for PWRs. The upper and lower limits for each data set
were then plotted on linear, semi-log and full log paper, a simple
regression analysis performed with the resultant equation of best fit
calculated along with the correlation coefficient. The equations and
their correlation coefficients are also shown in Tables 12 and 13
Table 14 below shows the minimum value of r, the correlation
coefficient, required to show significant correlation between the
dependent and independent variables (CR69).
The analysis performed using the method of least squares shows a
trend toward increased volumes of waste and increased activity, as the
plants operate longer and longer. Of course, as with every rule there
is an exception. In this case the exception is the upper limit of the
volume of waste from PWRs. Each of the four sets of data will be
discussed separately to evaluate the significance of the data. It
should be pointed out ahead of time that while in some cases the
correlation coefficients are much higher than needed to show
significant correlation they do not necessarily tell the whole story.
Obviously we do not expect volumes and activities to continue to
increase at their previous rate. For one thing, there is a finite
limit to the rate at which solid waste handling systems can process
these wastes not to mention the financial burden which utilities are
willing to accept. Therefore, our conclusions are based as much on
intuitive practicality as on the analytical results of the analysis.
Source of Data
The data used in this report were taken directly from the semi-
annual or annual operating reports or the radioactive effluent reports
published by the utility responsible for the operation of the plant.
-------
BWR Volume
Volumes of waste from BWRs is based on the average values shown in
Tables 4 and 5. Each analysis, linear, exponential and power, shown
in Figures 1, 2 and 3, respectively, resulted in correlation
coefficients well above the minimum value to establish significant
correlation. The average values analyzed, the equations of best fit
and the correlation coefficients are shown in Table 12. What this
analytical analysis fails to fully recognize is the apparent leveling
off in the last three years of the data for the lower limit. While
these most recent years are by no means conclusive, based on currently
available information, the average annual volume of waste from these
plants should run between 1000 to 2000 cubic meters. This is in basic
agreement with the NUS estimate of 55,000ft3/yr (1560m3/yr), and
slightly higher than previously estimated by the EPA or NRC.
BWR Activity
The activity of the waste from BWRs is based on the average values
shown in Tables 6 and 7. The analysis performed on these data linear,
exponential and power, as shown in Figures 4, 5 and 6, respectively,
has also shown significant correlation to the number of years of
operation. The average values analyzed, the equations of best fit and
the correlation coefficients are also shown in Table 12. In the first
five years of operation there has been a tremendous increase in the
radioactivity associated with the solid wastes shipped from'BWRs. As
with the volume of waste, the analyses again fails to fully recognize
the apparent leveling off over the last three years. In lieu of
including data for 1976, which is not yet fully available, we feel
that a reasonable approximation to use at this time is a range of 3000
to 7000 Ci/yr. Therefore, the NRC estimate of 4100 Ci/yr may be low
but is definitely within an acceptable range.
PWR Volume
The volumes of waste from PWRs is based on the averages shown in
Tables 8 and 9. The analytical analyses of these data; linear,
exponential and power as shown in Figures 7, 8 and 9, respectively,
did not result in any significant correlation with respect to the
number of years of operation. The average values analyzed, the
equations of best fit and the correlation coefficients are shown in
Table 13. By visual inspection of Figures 7,8 and 9, it appears that
volumes of 200 to 500 cubic meters could be expected. These estimates
are slightly lower than the NRC estimate of 15,500ft3/yr (440m3/yr)
and significantly lower than the NUS estimate of 40,000ft3/yr
(1130m /yr).
-------
PWR Activity
The activity of the waste from PWRs is based on the average values
shown in Tables 10 and 11. While the correlation coefficients
obtained in these analyses are decidedly better than for the volume of
waste from PWRs, they generally fail to meet the minimum requirement
to show significant correlation. The results of linear, exponential
and power analyses of these data are shown in Figures 10, 11, and 12,
respectively. The average values, equations of best fit and
correlation coefficients are shown in Table 13. Furthermore, the same
problem arises here as with the BWR data; the data from the most
recent years falls below that which is predicted by the analytical
analysis, or in other words appears to be leveling off. Again, by
visual inspection of the data we estimate annual activities of solid
waste to average between 500 to 1500 curies as compared to the NRC
estimate of 1900 curies.
Summary
Table 15 summarizes the results of this analysis and compares
those results to the previous EPA study, the NRC study and the NUS
study.
-------
Major Radionuclides Found in Solid Radioactive Waste
Prompted by the NRC study mentioned previously and as part of the
review of a study by Dames and Moore (Da-76) we expanded our
investigation into solid radioactive waste from LWRs to cover the
subject of the major contributing radionuclides in this waste. The
plants used in the analysis in the first half of this report have only
reported the volume and activity of their solid waste by type of waste
for the last few years. In addition, this part of the study was not
limited to plant greater than 500 MWe, but used all available data.
Therefore, the values presented here on the volume and gross activity
can not in any .way be compared to the previously reported results.
The two types of waste investigated are defined in Regulatory Guide
1.21 as Category A, filter sludges, spent resins, evaporator bottoms,
etc.; and Category B, dry compressible waste, contaminated equipment,
etc. Data was compiled from operating reports in which the solid
waste data has been reported according to Reg. Guide 1.21. Available
data covers the years 1974, 1975 and 1976. Not all reports for 1976
are available but we used what we had. The data used in this
analysis, on a plant by plant year by year basis is detailed in Tables
16 through 25. Weighted averages were calculated for each of the
three years, for Category A and B, for both PWRs and BWRs, see Tables
26 and 27. The cumulative averages, or combined averages of the most
predominant isotopes, are shown in Table 28.
Table 28 shows the average percent by nuclide for the two
categories of waste for PWRs and BWRs. Also shown is the percent of
the total PWR waste, by volume and activity, which was found to be
Category A and Category B, and the total BWR waste, by volume and
activity, which was found to be of each category. For both types of
plants filter sludges, spent resins and evaporator bottoms, constitute
approximately 55% of the total waste volume and more than 95% of the
activity whereas compressible waste and contaminated equipment
constitute approximately 45% of the total waste and less than 5% of
the total activity.
The results reported by NRC did not include the isotopic
composition of dry compressible wastes but compared the composition of
filter sludge and spent resin vs. evaporator bottoms. Their results
are repeated here only as a comparison to the results of our study.
See Table 29. It should be noted here that the source of the NRC data
were the plant operating reports for Nine Mile Point Unit 1, 1974 and
1975, for the BWR data and H. B. Robinson, January to June 1975, for
the PWR data.
The Dames and Moore report does not draw any conclusions as to the
average composition of wastes from typical plants but it does report
the composition of samples taken at four plants in New York State in
1976. The plants were, Nine Mile Point, FitzPatrick, Indian Point,
and Ginna. The results of their analysis of these samples for Nine
-------
Mile Point and Ginna are reproduced here in Table 30, for comparison
to our analysis of the data.
Whether these percentages change during the life of the plant we
do not know. Additional studies in this area will be performed from
time to time and our results published.
Conclusions
The analyses we have performed are by no means conclusive. The
estimates we have presented are in basic agreement with other studies
and we hope add some stabilizing influence to the confusing question
of how much waste at what level of activity. Obviously, we have
admitted in our analysis that even though in some cases significant
correlation does exist between the quantities investigated and the
number of years of operation there are just not enough years of
experience to draw definite conclusions. EPA will continue to monitor
the data from operating reactors and report its findings on
appropriate occasions.
-------
Comparison of Previous Studies
EPA-1975 NUS-1976 NRC-1977
Volume (m3/yr)
BWR 990 1560 990
PWR 595 1130 440
Activity (Curies/yr)
BWR N.C. N.C. 4100
PWR N.C. N.C. 1900
N.C. - Not Calculated
Table 1
8
-------
Plant - BWRs
Browns Ferry
Brunswick
Cooper
Dresden 2 & 3
All Units
Duane Arnold
FitzPatrick
Hatch
Millstone
yr
741
75
74
75
70
71
72
7311
741"
7514
74
75
74
75
74
75
70
71
72
73
74
75
Actual Quantities
Shipped
m3
261
411
379
290
Ci
70.9
6.96
17.2
266.
3724 (Ki-74) 9.4^
558 (Ki-74) 49.2
1000
2200
119
134
2190 (Nu-77)5Q50
5850
321
262
013
510
12813
583
O13 0
7340
61.4
79.0
O13
132.
8.313
271.
Ci-74) o13
208 (Ki-74) 95.5
261
351
838
1780
432.
2370.
257
2580
Power Generation
Actual
MWDt
6 . 08+5
2.33+5
2.87+5
2.31+5
1.20+4
4 . 63+5
1 . 05+6
1.28+6
9.65+5
6.40+5
1.87+5
3.09+5
0
2.84+5
1.01+4
4.07+5
1.20+4
4 . 63+5
4 . 04+5
2.48+5
4 . 65+5
5 . 02+5
Prorated
to 3400 MWt
and 80 % PCF
1.63
3.552
3.17
4.30
1+
4.285
1.895
2.326
3.096
4.656
4.432
3.21
O13
3.50
32. 87
2.44
20. 78
2.14
2.46
4.00
2.13
1.98
Quantities Shipped
prorated to 3400 MWt
and 80 % PCF
m3
372
1460
1200
1250
1190
945
Ci
101
25
55
1140
105
112
Excluded
due to one
unit < SOOMWe
1420
841
13
1780
13
1420
13
445
642
1400
1780
3520
270
254
13
462
13
660
13
204
1060
9480
547
5110
BWR Annual Volume and Activity Shipped & Prorated to 3400 MWt and 80 % Capacity
Table 2
-------
Plant - BWRs
Monticello
Nine Mile Point
Oyster Creek
Peach Bottom
yr
70
71
72
73
74
75
69
70
71
72
73
74
75
69
70
71
72
73
74
75
73
74
75
Actual Quantities
Shipped
m3
013(Ki-
Ci
-74) O13
309 (Ki-74) 17.6
178
211
268
380
88.2
393
2480
5430
O13 (Ki-74) O13
87 (Ki-74) 3.7
366 (Ki-74) 201
427 . 265
545
452
489
0
218
292
435
832
1210
990
30. I13
397
582
1010
1930
3260
0
3.0
5.0
1300
2890
1570
2810
0.313
58.0
217
Power Generation
Actual
MWDt
O9
1.79+5
4.54+5
4.12+5
3.45+5
3.70+5
1.23+4
2.60+5
4.14+5
4.17+5
4.57+5
4.26+5
4 . 03+5
4.89+4
4.42+5
4.87+5
5.41+5
4 . 53+5
4 . 64+5
4 . 09+5
0
5.11+5
1.39+6
Prorated
to 3400 MWfc
and 80 % PCF
5.55
2.19
2.41
2.88
2.68
26. 97
3.82
2.40
2.38
2.17
2.33
2.46
13.310
2.25
2.04
1.83
2.19
2.14
2.43
_9
2.75
Quantities Shipped
prorated to 3400 MWfc
and 80 % PCF
m3
13
1710
390
509
772
1020
13
332
878
1020
1180
1050
1200
0
490
596
796
1820
2590
2400
13
773
1.43 j 416
Ci
13
98
193
947
7140
14600
13
14
482
631
2190
4500
8020
0
7
10
2380
6330
3360
6830
13
113
165
BWR Annual Volume and Activity Shipped & Prorated to 3400 MWt and 80 % Capacity
Table 2 (continued)
-------
Plant - BWRs
Pilgrim
Quad Cities
Vermont Yankee
yr
72
73
74
75
71
72
73
74
75
72
73
74
75
Actual Quantities
Shipped
m
67.5
210
406
456
60 (Ki-
1070
1010
831
1400
126
186
198
308
Ci
19.
567
1460
3800
-74) 1
9
294
735
2410
18
24
108
225
Power Generation
Actual
MWDt
1.11+5
5.22+5
2.50+5
3.38+5
4. 12+1 9
5.21+5
1.18+6
1.09+6
9 . 64+5
6.16+4
2.53+5
3.42+5
4 . 69+5
Prorated
to 3400 MWt
and 80 % PCF
5.2211
1.90
3.97
2.94
1.9112
1.685
1.825
2.065
13. 42
3.92
2.90
2.12
Quantities Shipped
prorated to 3400 MWfc
and 80 % PCF
m
352
399
1610
1340
13
1170
848
756
1440
1690
729
574
653
Ci
99
1080
5796
11200
13
9.6
247
670
2480
241
94
313
477
5
6
7
8
9
Due to the fire in 1975 data for this year was not considered
Based on 10 months, 80 % PCF at 3400 MWt
Based on 11 months, 80 % PCF at 3400 MWt
Dresden 2 took 2% years to become commercial, and since power generated in 1970 was small, data
for 1970 was not considered to be typical and therefore not used
Based on two units at 3400MWt and 80 % PCF
Based on three units at 3400 MWt and 80 % PCF
Based on 4 months, 80 % PCF at 3400 MWt
Based on 3 months, 80 % PCF at 3400 MWt
Low power testing - not taken as the first year
BWR Annual Volume and Activity Shipped & Prorated to 3400 MWfc and 80 % Capacity
Table 2 (continued)
-------
10 Based on 8 months, 80 % PCF, at 3400 MWt
11 Based on 7 months, 80 % PCF, at 3400 MWt
12 Neither unit achieved commercial operation until 1972 therefore 1972 was taken as equivalent
to one 3400 MWt unit at 80 % PCF
13 Data for a given year was not condidered as the first year if the unit operated less than
six months of the year
1^ Not used due to the complexity involved in evaluating three units with one unit < 500 MWe
BWR Annual Volume and Activity Shipped & Prorated to 3400 MWt and 80 % Capacity
Table 2 (continued)
-------
Plant - PWRs
Arkansas One
Calvert Cliffs
Cook
Fort Calhoun
Ginna
Haddam Neck
yr
74
75
74
75
75
73
74
75
69
70
71
72
73
74
75
67
68
69
70
71
72
73
74
75
Actual Quantities
Shipped
3
m
0.
0.
0.
0.
172
45.4
323
537
0.
51.4
701
366
198
275
458
0.
11.7
83.3
58.6
104
188
159
204
624
Ci
0.
0.
0.
0.
.537
.02
10.
56.1
0.
5
47
1410
599
614
138
0.
.1
51
316
274
4770
571
942
1320
Power Generation
Actual
MWDt
8.29+4
6.42+5
1.60+0
5.84+5
6 . 08+5
8 . 54+4
3.16+5
2.80+5
6.41+3
2.85+5
3.54+5
3.21+5
4.48+5
2.80+5
4.04+5
7.Q7+4
3.96+5
4.81+5
4.75+5
5.59+5
5.74+5
2.91+5
5.90+5
5.58+5
Prorated
to 3400 MWt
and 80 % PCF
4.99 :
1.55
6.2+4 2
1.70
1.63
4.84 l
3.14
3.55
25.8 3
3.48
2.81
3.09
2.21
3.55
2.46
7.02 k
2.51
2.06
2.09
1.78
1.73
3.41 '
1.68
1.78
Quantities Shipped
prorated to 3400 MWt
and 80 % PCF
3
m
20
0.
20
0.
280
20
1010
1910
20
177
1970
1130
438
976
1130
0.
29
172
122
185
325
542
342
1110
Ci
20
0.
20
0.
1
20
31
199
20
17
132
4360
1320
2180
339
0.
•3
105
660
488
8250
1950
1580
2350
P¥R Annual Volume and Activity Shipped & Prorated to 3400 MWt and 80 % Capacity
Table 3
-------
Plant - PWRs
Indian Point
Kewaunee
Maine Yankee
Millstone
Oconee
Palisades
Point Beach
yr
72
73
74
75
74
75
72
73
74
75
75
73
74
75
71
72
73
74
75
70
71
72
73
Actual Quantities
Shipped
m3
191
411
445
622
0.
15.9
0.
67.0
159
231
0.
263
571
1420
0.
9.63
63.0
234
801
0.
76.4
194
295
Ci
157
208
61.9
2000
0.
2.12
0.
3.24
530
1480
0.
23.3
219
1680
0.
1.85
28.6
26.6
210
0.
4.0
214
1830
Power Generation
Actual
MWDt
1.12+5
6.13+4
2.44+5
6.85+5
2.75+5
4.51+5
6.00+4
4.51+5
4.81+5
6.12+5
2 . 66+4
3.11+5
7.07+5
1.95+6
3.33+1
2.46+5
3.25+5
1 . 65+4
3.71+5
2 . 63+4
4.17+5
4.15+5
7 . 68+5
Prorated
to 3400 MWt
and 80 % PCF
5
5
5
5
3.226
2.20
4.142
2.20
2.06
1.62
9.332
2.937
3.748
1.539
19,879. 10
4.04
3.06
5.02
2.67
6.29 3
3.9712
4.78^
2.5913
Quantities Shipped
prorated to 3400 MWt
and 80 % PCF
m3
_
_ .
-
0.
35.0
20
147
328
374
20
841
916
724
0.
39
193
1170
2140
20
303
554
383
Ci
_
_
-
0.
5.0
20
7.0
1090
2400
20
74
351
857
0.
7.0
88
134
561
20
16
612
237Q
PWR Annual Volume and Activity Shipped & Prorated to 3400 MWt and 80 % Capacity
Table 3 (continued)
-------
Plant - PWRs
Point Beach (con't)
Prairie Island
Rancho Seco
Robinson
San Onofre
yr
74
75
73
74
75
74
75
70
71
72
73
74
75
67
68
69
70
71
72
73
74
75
Actual Quantities
Shipped
m3
132
408
0.
136
150
0.
.011
0.
24.2
70.6
292
353
356
0.
10.8
40.0
41.3
22.9
107
113
68.3
79.6
Ci
2120
8230
0.
76.1
34.7
0.
.115
0.
NR
4.85
96.7
197
1340
0.
2.0
8.0
11.0
2.0
7.97
381
230
26.0
Power Generation
Actual
MWDt
8.48+5
8.72+5
5.33+3
2.19+5
9.38+5
3 . 94+4
5.50+4
2 . 65+3
3.27+5
6.47+5
5 . 08+5
6.48+5
5 . 66+5
4 . 93+4
1 . 69+5
3.29+5
3.83+5
4.15+5
3.56+5
2.93+5
4 . 06+5
4.17+5
Prorated
to 3400 MWt
and 80 % PCF
2.3413
2.2813
15.5 1*
4.5315
2.1213
8.4016
18.1
125. 16
3.04
1.53
1.95
1.53
1.75
11.7 17
5.88
3.02
2.59
2.39
2.79
3.39
2.45
2.38
Quantities Shipped
prorated to 3400 MWt
and 80 % PCF
m3
154
465
20
616
159
20
.02
20
74
108
569
540
623
0.
63.5
121
107
54.7
299
383
167
189
Ci
2480
9400
20
344
36.7
20
2.0
20
NR
7.0
189
301
2340
0.
11.8
24.2
28.5
4.78
22.2
1290
564
61.9
PWR Annual Volume and Activity Shipped & Prorated to 3400 MWt and 80 % Capacity
Table 3 (continued)
-------
Plant - PWRs
Surry
Three Mile Island
Turkey Point
Zion
yr
72
73
74
75
74
75
72
73
74
75
73
74
75
Actual Quantities
Shipped
m3
160
365
1250
9210
200
458
0.
233
449
889
416
1620
1580
Ci
1.9-4
1.59
50.6
2640
6.06
258
0.
3.98
44.7
104
.159
4.65
15.4
Power Generation
Actual
MWDt
5.33+4
9.46+5
4.60+5
1.21+6
3.26+5
7.34+5
1.74+4
6.43+5
1 . 06+6
1.16+6
1.14+5
7 . 03+5
1.37+6
Prorated
to 3400 MWt
and 80 % PCF
9.32k
1.9218
4.3213
1.6413
1.781?
1.35
16.9 2
2.4519
1.87!3
1.7113
5.0815
2.8213
1.4513
Quantities Shipped
prorated to 3400 MWt
and 80 % PCF
m3
2980
382
2700
21
356
618
20
360
419
759
3170
2280
1150
Ci
.004
1.7
109
21
10.8
348
20
6.1
41.7
88.9
1.0
6.5
11.2
1
2
3
k
5
6
7
Based on 5 months, 80 % PCF and 3400 MWt
Based on 3 months, 80 % PCF and 3400 MWt
Based on 2 months, 80 % PCF and 3400 MWt
Based on 6 months, 80 % PCF and 3400 MWt
Data not used due to complexity of evaluating units of different size which report combined data
Based on 10 months, 80 % PCF and 3400 MWt
Based on 11 months of operation at 3400 MWt and 80 % PCF (9 months of Unit 1 and 2 months of Unit 2
compared to single unit 3400 MWt power plant due to minimal operation of unit 2)
PWR Annual Volume and Activity Shipped & Prorated to 3400 MWt and 80 % Capacity
Table 3 (continued)
-------
8 Based on 2 years 4 months of operation compared to three 3400 MWt units at 80 % capacity
9 Compared to three 3400 MWt units at 80 % capacity
10 Based on 8 months, 80 % PCF at 3400 MWt
11 Based on 1 months operation at 3400 MWt and 80 % PCF; plant shutdown Jan - Sept and Nov - Dec
12 Based on 1 year 8 months of operation compared to two 3400 MWt units at 80 % capacity
13 Compared to two 3400 MWt units at 80 % capacity
ltf Based on 1 month, 80 % PCF at 3400 MWt
15 Based on 1 year operation of one 3400 MWt unit at 80 % PCF
16 Based on 4 months, 80 % PCF at 3400 MWt
17 Based on 7 months, 80 % PCF at 3400 MWt
18 Based on 1 year 10 months of operation compared to two 3400 MWt units at 80 % capacity
19 Based on 1 year 7 months of operation compared to two 3400 MWt units at 80 % capacity
20 Data for this year was not considered as the first year since the unit operated less than one year
21 Data for Surry in 1975 was not used. Plant personnel indicated the unusally large volume and
actrivity shipped from the site was the result of some form of operational problem but refused
to discuss details with us.
PWR Annual Volume and Activity Shipped & Prorated tO 3400 MWt and 80 % Capacity
Table 3 (continued)
-------
Plant - BWRs
Browns Ferry
Brunswick
Cooper
Dresden
Duane Arnold
FitzPatrick
Hatch
Millstone
Monticello
Nine Mile Point
Oyster Creek
Peach Bottom
Pilgrim
Quad Cities
Vermont Yankee
Average m3/yr
1 st*
228
493
413
279
385
510
583
208
309
87
0
281
115
611
151
310
2 nd
290
500
262
261
178
366
218
291
210
505
186
297
3 rd
351
211
427
292
406
415
198
328
Year of Operation
4 th 5 th 6 th 7 th 8 th
838 1780
268 380
545 452 489
435 832 1210 990
456
700
308
507 861 850 990
First year prorated to full year based on the actual number of months of operation
BWR Actual Volume Shipped per Unit - m3/yr
Table 4
-------
Plant - BWRs
Browns Ferry
Brunswick
Cooper
Dresden
Duane Arnold
FitzPatrick
Hatch
Millstone
Monticello
Nine Mile Point
Oyster Creek
Peach Bottom
Pilgrim
Quad Cities
Vermont Yankee
Average m3/yr
1 st
372
1460
1200
1190
1420
1780
1420
445
1710
332
0
773
352
1170
1690
1020
2 nd
1250
945
841
642
390
878
490
416
399
848
729
711
3 rd
1400
509
1020
596
1610
756
574
923
Year of Operation
4 th 5 th 6 th 7 th 8 th
1780 3520
772 1020
1180 1050 1200
796 1820 2590 2400
1340
1440
653
1140 1850 1900 2400
BWR Annual Volume Shipped per Unit - m3/yr
Prorated to 3400 MWt and 80 % PCF
Table 5
-------
Plant - BWR.S
i ...
j
Browns Ferry
Brunswick
Cooper
Dresden
Duane Arnold
FitzPatrick
Hatch
1 st*
62
8
19
25
74
132
271
Millstone 95
Monticello
Nine Mile Point
Oyster Creek
Peach Bottom
Pilgrim
Quad Cities
Vermont Yankee
18
4
0
41
32
5
22
Average Ci/yr 54
2 nd
226
60
79
432
88
201
3
108
567
147
24
176
3 rd
2370
393
265
5
1460
368
108
710
Year of Operation
4 th 5 th 6 th 7 th 8 th
257 2580
2480 5430
1010 1930 3260
1300 2890 1570 2810
3800
1210
225
1470 3210 2420 2810
First year prorated to full year based on the actual number of months of operation
BWR Actual Activity Shipped per Unit - Ci/yr
Table 6
-------
ro
Plant - BWRs
Browns Ferry
Brunswick
Coo
Dresden
Duane Arnold
FitzPatrick
Hatch
Millstone
Monticello
Nine Mile Point
Oyster Creek
Peach Bottom
Pilgrim
Quad Cities
Vermont Yankee
Average Ci/yr
1 st
101
25
55
105
270
462
660
204
98
14
0
113
99
10
241
164
2 nd
1140
112
254
1060
193
482
7
165
1080
247
94
439
3 rd
9480
947
631
10
5800
670
313
2550
Year of Operation
4 th 5 th 6 th 7 th 8 th
547 5110
7140 14600
2190 4500 8020
2380 6330 3360 6830
11200
2480
477
3770 7630 5690 6830
BWR Annual Activity Shipped per Unit - Ci/yr
Prorated to 3400 MWt and 80 % PCF
Table 7
-------
KJ
Plant - PWRs
Arkansas One
Calvert Cliffs
Cook
Fort Calhoun
Ginna
Haddam Neck
Kewaunee
Maine Yankee
Oconee
Palisades
Point Baech
Prairie Island
Rancho Seco
Robinson
San Onofre
Surry
Three Mile Island
Turkey Point
Zion
Average m3/yr
1 st*
0
0
172
323
51.4
0
0
67
287
0
76
136
0.01
24.2
0
320
480
147
624
142
2 nd
537
701
11.7
15.9
159
245
9.6
116
75
70.6
10.8
199
458
224
810
243
3 rd
366
83.3
231
473
63
148
292
40
625
444
790
323
Year of Operation
4 th 5 th 6 th 7 th 8 th
198 275 458
58.6 104 188 159 204
234 801
66 204
353 356
41.3 22.9 107 113 68
158 294 251 136 136
9 th
624
80
352
First year prorated to full year based on the actual number of months of operation
PWR Actual Volume Shipped per Unit - m3/yr
Table 8
-------
NJ
OJ
Plant - PWRs
Arkansas One
Calvert Cliffs
Cook
Fort Calhoun
Ginna
Haddam Neck
Kewaunee
Maine Yankee
Oconee
Palisades
Point Beach
Prairie Island
Rancho Seco
Robinson
San Onbfre
Surry
Three Mile Island
Turkey Point
Zion
Average mVyr
1 st
0
0
280
1010
177
0
0
147
841
0
303
616
0.2
74
0
2980
356
360
3170
543
2 nd
1910
1970
29
35
328
916
39
554
159
108
63.5
382
618
419
2280
654
Year of Operation
3 rd 4 th 5 th 6 th 7 th
1130 438 976 1130
172 122 185 325 542
374
724
193 1170 2140
383 154 465
569 540 623
121 107 54.7 299 383
2700
759
1150
752 421 740 585 462
8 th 9 th
342 1110
167 189
254 650
PWR Annual Volume Shipped per Unit - m3/yr
Prorated to 3400 MWt and 80 % PCF
Table 9
-------
Plant - PWRs
Arkansas One
Calvert Cliffs
Cook
Fort Calhoun
Ginna
Haddtam Neck
Kewaunee
Maine Yankee
Oconee
Palisades
Point Beach
Prairie Island
Rancho Seco
Robinson
San Onofre
Surry
Three Mile Island
Turkey Point
Zion
Average Ci/yr
*
1 st
0
0
0.5
10
5
0
0
3.2
25.3
0
4
76.1
0.1
NR
0
.0004
10.4
2.5
0.2
7.6
2 nd
56.1
47
0.1
2.1
530
93.8
1.8
128
17.3
4.8
2
0.87
258
22.3
2.3
77.8
3 rd
1410
51
1480
560
28.6
915
96.7
8
25.3
52
7.7
421
Year of Operation
4 th 5 th 6 th
599 614 138
316 274 4770
26.6 210
1060 4120
197 1340
11 2 8
368 1090 1640
7 th 8 th 9 th
571 942 1320
38.1 230 26
304 586 623
First year prorated to full year based on the actual number of months of operation
PWR Actual Activity Shipped per Unit - Ci/yr
Table 10
-------
Plant - PWRs
Arkansas One
Calvert Cliffs 0
Cook
Fort Calhoun
Ginna
Haddam Neck
Kewaunee
Maine Yankee
Oconee
Palisades
Point Beach
Prairie Island
Rancho Seco
Robinson
San Onofre
Surry
Three Mile Island
Turkey Point
Zion
Average Ci/yr
1 st
0
0
1
31
17
0
0
7
74
0
16
344
2
NR
0
0.004
10.8
6.1
1
28.3
2 nd
199
132
0.3
5
1090
351
7
612
36.7
7
11.8
1.7
348
41.7
6.5
190
Year of Operation
3 rd 4 th 5 th 6 th 7 th 8 th 9 th
4360 1320 2180 339
105 660 488 8250 1950 1580 2350
2400
857
88 134 561
2370 2480 9400
189 301 2340
24.2 28.5 4.8 22.2 1290 .564 61.9
109
88.9
11.2
964 820 2500 2870 1620 1070 1210
PWR Annual Activity Shipped per Unit - Ci/yr
Prorated to 3400 MWt and 80 % PCF
Table 11
-------
BWR - Average Values
Years of Annual Volume - m3
Operation Lower Limit Upper Limit
1 310
2 297
3 328
4 507
5 861
6 850
7 990
1020
711
923
1140
1850
1900
2400
Annual Activity - i
Lower Limit Upper L
54
176
710
1470
3210
2420
2810
164
439
2550
3770
7630
5690
6830
Type of
Regression
Analysis
Linear
Exponential
Power
Annual Volume - m3
Lower Limit Upper Limit
y=131t+67 y=266t+357
r=.9436 r=.9155
y=207e'233t y=618e-187t
r=.9464 r=.9019
y=230f681 y=702f509
r=.8768 r=.7799
Annual Activity - Ci
Lower Limit Upper Limii
y=545t-629
r=.9148
y=56e.
r=.9171
y=53t2-23
r=.9764
y=1270t-1220
r=.9190
y=178e-622t
r=.8997
y=164t2-n
r=.9677
Table 12
26
-------
PWR - Average Values
Years of Annual Volume - m3
Operation Lower Limit Upper Limit.
1 142
2 243
3 323
4 158
5 294
6 251
7 136
8 136
9 ' 352
543
654
752
421
740
585
462
254
650
Annual Avtivity - Ci
Lower Limit Upper Lim
7.6
77.8
421
368
1090
1640
304
586
623
28.3
190
964
820
2500
2870
1620
1070
1210
Type of
Regression
Analysis
Linear
Exponential
Power
Annual Volume - m3
Lower Limit Upper Limit
y=3.82t+207 y=-19.8t+661
r=.1219 r=-.3347
y=202e-0098t y=676e~'Olf61t
r=.0683 r=-.3678
y=187f°811f y=658t--llt28
r=.1492 r=-.2997
Annual Activity - Ci
Lower Limit Upper Limit
y=83.7t+150 y=179t+358
r=.4459 r=.5143
y=113e-375t
r=.7062
r=.4506
y=19.1t1-93 y=59.8t1-765
r=.5592 r=.8735
Table 13
27
-------
Minimum Value of the Correlation Coefficient, r, to
Show Significance at the 95% Probability Level
Significance Level
Degrees of Fredom a =.05
1 .9877
2 .9000
3 .8050
4 .7290
5 .6690
6 .6210
7 .5820
8 .5490
9 .5210
10 .4970
Table 14
28
-------
Estimated Volumes and Activities of
Solid Waste from LWRs
EPA-1977 NRC-1977 NUS-1976 EPA-1975
Volume (m^/yr) ; :
BWR 1000-2000 990 1560 990
PWR 200-500 440 1130 595
Activity (Curies/yr)
BWR 3000-7000 4100
PWR 500-1500 1900
Table 15
29
-------
CATEGORY A
ISOTOPE
Co-57
Co-58
Co-60
Cs-134
Cs-137
Fe-59
1-131
Mn-54
Nb-95
Nb-97
Sb-124
Sb-125
Other
TOTAL
AM NECK
JAN
CURIES
195.
25.
220.
YEAR 1975 VOLUME: JA
JU
ACTIVITY
- JUN JUL
PERCENT CURIES
88.7 109.
11.3 926.
I-
100. 1089.
N - JUN H.4 m3
L - DEC 7.6 m3
- DEC
PERCENT
10.
85.
I-
100.
Table 16-a
30
-------
CATEGORY A
PLANT INDIAN POINT YEAR 1975 VOLUME: JAN - JUN m3
JUL - DEC 321. m3
JAN
ISOTOPE CURIES
Co-57
Co-58
Co-60
Cs-134
Cs-137
Fe-59
1-131
Mn-54
Nb-95
Nb-97
Sb-124
Sb-125
Other
TOTAL
ACTIVITY
- JUN JUL
PERCENT CURIES
279.7
48.
359.1
545.6
27.1
1260.
- DEC
PERCENT
22.2
3.81
28.5
43.3
2.15
99.96
Table 16-b
31
-------
CATEGORY A
PLANT MAINE YANKEE YEAR 1975 VOLUME: JAN, - JUN 119,. 6 ' m3
JUL - DEC 25.9 m3
JAN
ISOTOPE CURIES
Co-57
Co -58 273.4
Co-60 95.7
Cs-134 382-8
Cs-137 615'2
Fe-59
1-131
Mn-54
Nb-95
Nb-97
Sb-124
Sb-125
Other
TOTAL 1367.
ACTIVITY
- JUN JUL
PERCENT ' -.CURIES
20. 20.2
7. 7.
28. 28.2
45. 45.4
100. 100.8
- DEC
PERCENT
20.
7.
28.
45.
100.
Table 16-c
32
-------
CATEGORY A
PLANT: RANCHO SECO
YEAR 1975 VOLUME: JAN - JUN
JUL - DEC
Q.Q11
ACTIVITY
ISOTOPE '
JAN - JUN
CURIES PERCENT
JUL - DEC
CURIES ' PERCENT
Co-57
Co-58 -1
Co-60 -01
Cs-134
Cs-137
•
Fe-59
1-131
Mn-54 .005
Nb-95
Nb-97
Sb-124
Sb-125
Other
TOTAL • ! ! 5
85.
10.
5.
100.
Table 16-d
33
-------
PLANT ROBINSON
CATEGORY A
YEAR 1975 VOLUME: JAN - JUN
m
JUL - DEC 119. i
JAN
ISOTOPE CURIES
Co-57
Co-58
Co-60
Cs-134
Cs-137
Fe-59
1-131
Mn-54
Nb-95
Nb-97
Sb-124
Sb-125
Other
TOTAL 322.*
ACTIVITY
- JUN JUL
PERCENT CURIES
.06
10.36
10.37
6.73
9.2
.05
1.17
.04
.97
.52
.36
39.8
- DEC
PERCENT
.2
26.
26.1
16.9
23.1
.1
2.9
.1
2.4
1.3
.9
100.
No isotopic analysis given
Table 16-e
34
-------
CATEGORY A
PLANT FORT CALHOUN
ISOTOPE
Co-57
Co-58
Co-60
Cs-134
Cs-137
Fe-59
1-131
Mn-54
Nb-95
Nb-97
Sb-124
Sb-125
Other
TOTAL
YEAR 1976 VOLUME: JAN - JUN
JUL - DEC
ACTIVITY
168
235 m3
JAN - JUN JUL - DEC
CURIES PERCENT CURIES PERCENT
10.1
2.1
4.6
.9
17.8
57 7.3
12. 20.2
26. 25.3
5. 3.4
100. 56.2
13
36.
45.
6.
100.
Table 17-a
35
-------
CATEGORY A
PLANT HADDAM NECK
YEAR 1976 VOLUME: JAN - JUN
JUL - DEC
70.82
ACTIVITY
ISOTOPE
JAN - JUN
CURIES PERCENT
JUL - DEC
CURIES PERCENT
Co-57
Co-58 60.2
Co-60 481.6
Cs-134
Cs-137 30.1
Fe-59
1-131
Mn-54 30.1
Nb-95
Nb-97
Sb-124
Sb-125
Other
TOTAL 602.
10.
80.
5.
5.
100.
Table 17-b
36
-------
CATEGORY A
PLANT INDIAN POINT
YEAR 1976 VOLUME: JAN - JUN
JUL - DEC
280. m3
"",3
m-
ACTIVITY
ISOTOPE
JAN - JUN
CURIES PERCENT
JUL - DEC
CURIES PERCENT
Co-57
Co-58
Co-60
Cs-134 89.9
Cs-137 144.5
Fe-59
1-131
Mn-54
Nb-95
Nb-97
Sb-124
Sb-125
Other* 161.6
TOTAL 396.
22.7
36.5
40.8
100.
* Mn-54, Co-58, Co-60
Table 17-c
37
-------
CATEGORY A
PLANT KEWAUNEE YEAR 1976 VOLUME: JAN - JUN 3.39m3
JUL - DEC m3
JAN
ISOTOPE CURIES
Co-57
Co-58 -025
Co-60
Cs-134
Cs-137
Fe-59
1-131
Mn-54
Nb-95
Nb-97
Sb-124
Sb-125
Other .01
TOTAL .035
ACTIVITY
- JUN JUL
PERCENT CURIES
65.7
34.3
100.
- DEC
PERCENT
Table 17-d
38
-------
CATEGORY A
PLANT MAINE YANKEE
YEAR 1976 VOLUME: JAN - JUN
JUL - DEC
58.
m-
ACTIVITY
ISOTOPE
JAN - JUN
CURIES PERCENT
JUL - DEC
CURIES PERCENT
Co-57
Co-58 44.7
Co-60 89.1
Cs-134 139.2
Cs-r37 223.7
Fe-59
1-131
Mn-54
Nb-95
Nb-97
Sb-124
Sb-125
Other
TOTAL 497.
9.
18.
28.
45.
100.
Table 17-e
39
-------
CATEGORY A
PLANT MILLSTONE 2 YEAR 1976 VOLUME: JAN - JUN 201. m3
JUL - DEC 78.9m3
JAN
ISOTOPE CURIES
Co-57
Co-58 -13
Co-60 '01
Cs-134 -01
Cs-137 -13
Fe-59
1-131 -62
Mn-54 -02
Nb-95
Nb-97
Sb-124
Sb-125
Other
TOTAL • 92
ACTIVITY
- JUN JUL
PERCENT CURIES
14. .76
.9 .03
1 . .02
14. .02
.02
68. -02
2. -03
100. .89
- DEC
PERCENT
85.
3.
2.5
2.
2..
2.5
3.
100.
Table 17-f
40
-------
CATEGORY A
PLANT PRAIRIE ISLAND
YEAR 1976 VOLUME: JAN - JUN
JUL - DEC
79.3 m3
n,3
ACTIVITY
ISOTOPE
JAN - JUN
CURIES PERCENT
JUL - DEC
CURIES PERCENT
Co-57
Co-58 22.4
Co-60 7-7
Cs-134
Cs-137
Fe-59
1-131
Mn-54 3 . 2
Nb-95
Nb-97
Sb-124
Sb-125
Other 1-8
TOTAL 35-
64.
22.
9.
5.
100.
Table 17-g
41
-------
CATEGORY A
PLANT ROBINSON YEAR 1976 VOLUME: JAN - JUN 71. m3
JUL - DEC m3
JAN
ISOTOPE CURIES
Co-57 -04
Co-58 6.84
Co-60 7-2
Cs-134 322
Cs-137 6>1
Fe-59
1-131 -04
Mn-54 -62
Nb-95
Nb-97
Sb-124 -24
Sb-125 *17
Other
TOTAL 24.46
ACTIVITY
- JUN JUL
PERCENT CURIES
.2
28.
29.4
13.1
25.
.2
2.5
1.
.7
100.
- DEC
PERCENT
Table 17-h
42
-------
CATEGORY B
PLANT HADDAM NECK YEAR 1975 VOLUME: JAN - JUN 429. m3
JUL - DEC 176.4 m3
JAN
ISOTOPE CURIES
Co-57
Co-58 2.3
Co-60 2.3
Cs-134
Cs-137
Fe-59
1-131
Mn-54
Nb-95
Nb-97
Sb-124
Sb-125
Other
TOTAL 4 . 6
ACTIVITY
- JUN JUL
PERCENT CURIES
50. 1.
50. 9.
I-
100. 11.0
- DEC
PERCENT
9.1
81.8
!••'
100.
Table 18-a
43
-------
CATEGORY B
PLANT INDIAN POINT YEAR 1975 VOLUME: JAN - JUN m3
JUL - DEC 21.2 m3
JAN
ISOTOPE CURIES
Co-57
Co-58
Co-60
Cs-134
Cs-137
Fe-59
1-131
Mn-54
Nb-95
Nb-97
Sb-124
Sb-125
Other
TOTAL
ACTIVITY
- JUN JUL
PERCENT CURIES
.8
.1
1.
1.5
.1
3.52
- DEC
PERCENT
22.2
3.81
28.5
2.15
2.15
99.6
Table 18-b
44
-------
CATEGORY B
ISOTOPE
Co-57
Co-58
Co-60
Cs-134
Cs-137
Fe-59
1-131
Mn-54
Nb-95
Nb-97
Sb-124
Sb-125
Other
TOTAL
: YANKEE
JAN
CURIES
1.8
.6
2.5
4.1
9.0
YEAR 1975 VOLUME: JA
JU
ACTIVITY
- JUN JUL
PERCENT CURIES
20. 5.6
7. 1.0
28. 2.1
45. 5.6
100. 14.3
N - JUN 71. m3
L - DEC 14.1 m3
- DEC
PERCENT
39.2
7.0
14.7
39.2
100.
Table 18-c
45
-------
CATEGORY B
PLANT ROBINSON YEAR 1Q75 VOLUME: JAN - JUN 52. m3
JUL - DEC 101. m3
JAN
ISOTOPE CURIES
Co-57 .05
Co-58 11-0
Co-60
Cs-134
Cs-137
Fe-59
1-131
Mn-54 3 . 0
Nb-95 .06
Nb-97 ®
Sb-124
Sb-125
Other 11.2
TOTAL 25.3
ACTIVITY
- JUN JUL
PERCENT CURIES
.21 .6
43.4 12.8
8.5
11.9 3.5
.22 .1
.3
44.3 .8
100. 26.6
- DEC
PERCENT
2.35
48.3
31.9
13.2
.253
1.13
2.87
100.
Table 18-d
46
-------
CATEGORY B
ISOTOPE
Co-57
Co-58
Co-60
Cs-134
Cs-137
Fe-59
1-131
Mn-54
Nb-95
Nb-97
Sb-124
Sb-125
Other
TOTAL
1 CALHOUN
JAN
CURIES
6.
1.3
2.8
.5
10.6
YEAR 1976 VOLUME: JAI
JIT
ACTIVITY
- JUN JUL
PERCENT CURIES
57. 1.7
12. 4.8
26. 5.9
5. .8
100. 13.2
N - JUN 67.5
L - DEC 101.1 i
- DEC
PERCENT
13.
36.
45.
6.
100.
Table 19-a
47
-------
CATEGORY B
PLANT HADDAM NECK YEAR 1976 VOLUME: JAN - JUN. 407 .;3 m3
JUL - 'DEC m3
JAN'
ISOTOPE ;CURIES
Co-57
Co-58 .1
Co-60 -8
Cs-134
Cs-I37 -05
Fe-59
1-131
Mn-54 • 05
Nb-95
Nb-97
Sb-124
Sb-125
Other
TOTAL 1 . 0
ACTIVITY
- JUN JUL
PERCENT CURIES
10.
80.
5.
5.
100.
- DEC
. PERCENT ,;
Table 19-b
48
-------
CATEGORY B
PLANT
INDIAN POINT
YEAR 1976 VOLUME: JAN - JUN
JUL - DEC
106. m3
ACTIVITY
ISOTOPE
Co-57
Co-58
Co-60
Cs-134
Cs-137
Fe-59
1-131
Mn-54
Nb-95
Nb-97
Sb-124
Sb-125
*
Other
TOTAL
JAN - JUN
CURIES PERCENT
8.5
13.7
15.3
37.5
JUL - DEC
CURIES PERCENT
22.7
36.5
40.8
100.
Includes Mn-54, Co-58 and Co-60
Table 19-c
49
-------
CATEGORY B
PLANT KEWAUNEE YEAR 1976 VOLUME: JAN - JUN 27.8 m3
JUL - DEC m3
JAN
ISOTOPE CURIES
Co-57
Co-58 4.94
Co-60
Cs-134
Cs-137
Fe-59
1-131
Mn-54
Nb-95
Nb-97
Sb-124
Sb-125
Other 2.58
TOTAL 7.52
ACTIVITY
- JUN - ' ,, JUL
PERCENT , ... CURIES
65.7
34.3
100.
- DEC
PERCENT
Table 19-d
50
-------
CATEGORY B
PLANT MAINE YANKEE YEAR 1976 VOLUME: JAN - JUN 34.2 m3
JUL - DEC m3
JAN
ISOTOPE CURIES
Co-57
Co-58 .5
Co-60 1.1
Cs-134 -5
Cs-137. 1-4
Fe-59
1-131
Mn-54
Nb-95
Nb-97
Sb-124
Sb-125
Other
TOTAL 3 . 5
ACTIVITY
- JUN JUL
PERCENT CURIES
15.
30.
15.
40.
100.
- DEC
PERCENT
Table 19-e
51
-------
CATEGORY B
PLANT PRAIRIE ISLAND
YEAR 1Q76 VOLUME: JAN - JUN
JUL - DEC
69.4
ACTIVITY
ISOTOPE
JAN - JUN
CURIES PERCENT
JUL - DEC
CURIES PERCENT
Co-57
Co-58 3.6
Co-60 1.3
Cs-134
Cs-137
Fe-59
1-131
Mn-54 . 5
Nb-95
Nb-97
Sb-124
Sb-125
Other .3
TOTAL 5 . 7
64.
22.
9.
5.
100.
Table 19-f
52
-------
CATEGORY B
PLANT
ROBINSON
YEAR 1976 VOLUME: JAN - JUN
JUL - DEC
64.1
m
ACTIVITY
ISOTOPE
JAN - JUN
CURIES PERCENT
JUL - DEC
CURIES PERCENT
Co-57
Co-58 .3
Co-60 15.
Cs-134
Cs-137 5.
Fe-59
1-131
Mn-54 .5
Nb-95 -6
Nb-97 -5
Sb-124
Sb-125
Other 2.5
TOTAL 24 . 4
1.4
61.3
20.6
2.2
2.5
2.0
10.
100.
Table 19-g
53
-------
CATEGORY A
PLANT COOPER YEAR 1974 VOLUME: JAN - JUN »1Q7. 1
JUL - DEC 265. '
JAN
ISOTOPE CURIES
BaLa-140
Ce-141
Co-58 .85
Co-60 .06
Cr-51 2.58
Cs-134
Cs-137
Fe-59
1-131
Mn-54
Na-24
Nb-95
Ni-95
Sb-124
Sr-89
Sr-90
W-187
Zn-65
Other
TOTAL 3 . 5
ACTIVITY
- JUN JUL
PERCENT CURIES
24.4 4.4
1.6 .3
73.8 9.0
100. 13.7
- DEC
PERCENT
32.1
2.2
65.7
100.
Table 20- a
54
-------
CATEGORY A
PLANT HATCH
ISOTOPE
BaLa-140
Ce-141
Co-58
Co-60
Cr-51
Cs-134
Cs-137
Fe-59
1-131
Mn-54
Na-24
Nb-95
Ni-95
Sb-124
Sr-89
Sr-90
W-187
Zn-65
Other
TOTAL
YEAR 1974 VOLUME: JAN - JUN
JUL - DEC
115.
m
ACTIVITY
JAN - JUN
CURIES PERCENT
JUL - DEC
CURIES PERCENT
1.2
6.2
.9
8.3
14
75.
11.
100.
Table 20-b
55
-------
CATEGORY A
PLANT BRUNSWICK YEAR 1975 VOLUME: JAN - JUN 45. m3
JUL - DEC m3
JAN
ISOTOPE CURIES
BaLa-140
Ce-141 .39
Co-58 .74
Co-60 .04
Cr-51 .95
Cs-134
Cs-137
Fe-59 .03
1-131
Mn-54 .02
Na-24
Nb-95
Ni-95 <.Q1
Sb-124
Sr-89
Sr-90
W-187
Zn-65
Other .26
TOTAL 2.43
ACTIVITY
- JUN JUL
PERCENT CURIES
15.9
30.6
1.55
39.1
1.27
.67
.022
10.89
100.
Table 21-a
- DEC
PERCENT
56
-------
CATEGORY A
PLANT COOPER YEAR 1975 VOLUME: JAN - JUN qfi fi m3
JUL - DEC 121. m3
JAN -
ACTIVITY
- JUN JUL
- DEC
ISOTOPE CURIES PERCENT CURIES PERCENT
BaLa-140
Ce-141
Co-58 20.6
Co-60 13.
Cr-51 42.6
Cs-134
Cs-137
Fe-59
1-131
Mn-54
Na-24
Nb-95 3.4
Ni-95
Sb-124
Sr-89
Sr-90
W-187
Zn-65
Other .1
TOTAL 79.7
25.9 37.8
16.3 39.8
53.4 65.3
1.5
27.3
4.24
.16 14.3
100. 186.
20.3
21.4
35.1
.8
14.7
7.7
100.
Table 21-b
57
-------
CATEGORY A
PLANT HATCH YEAR 1975 VOLUME: JAN - JUN 204
JUL - DEC 188.
JAN
ISOTOPE CURIES
BaLa-140
Ce-141
Co-58 22.1
Co-60
Cr-51 28.4
Cs-134
Cs-137
Fe-59
1-131
Mn-54
Na-24
Nb-95
Ni-95
Sb-124
Sr-89
Sr-90
W-187
Zn— 65 g q
Other o g
TOTAL 63 . 2
ACTIVITY
- JUN JUL
PERCENT CURIES
35. 64.2
45. 82.8
14- 55.9
6- 4.1
10°- 207.
Table 21-c
- DEC
PERCENT
31.
40.
27.
2.
100.
58
-------
CATEGORY A
PLANT HUMBOLDT BAY
YEAR 1975 VOLUME: JAN - DEC 37.3 m3
ACTIVITY
ISOTOPE
BaLa-140
Ce-141
Co-58
Co-60
Cr-51
Cs-134
Cs-137
Fe-59
1-131
Mn-54
Na-24
Nb-95
Ni-95
Sb-124
Sr-89
Sr-90
W-187
Zn-65
Other
TOTAL
1975
CURIES PERCENT
.4
.6
1.2
.3
.4
2.9
15.
20.
40.
10.
15.
100.
CURIES PERCENT
Table 21-d
59
-------
CATEGORY A
PLANT VERMONT YANKEE YEAR 1975 VOLUME: JAN - JUN 92.
JUL - DEC 56.1 i
JAN •
ISOTOPE CURIES
BaLa-140
Ce-141
Co-58
Co-60 1.5
Cr-51 .9
Cs-134
Cs-137 .8
Fe-59
1-131
Mn-54
Na-24
Nb-95
Ni-95
Sb-124
Sr-89
Sr-90
W-187
Zn-65 1.3
Other . 9
TOTAL 5.4
ACTIVITY
- JUN JUL
PERCENT CURIES
28.7 3.8
16.6 2.2
14.1 1.8
24.1 3.2
16.5 2.2
100. 13.1
- DEC
PERCENT
28.7
16.6
14.1
24.1
16.5
100.
Table 21-e
60
nr
-------
CATEGORY A
PLANT COOPER YEAR 1975 VOLUME: JAN - JUN 157. m3
JUL - DEC 70.5 m3
JAN
ISOTOPE CURIES
BaLa-140
Ce-141
Co-58 33.5
Co-60 54.4
Cr-51 73.8
Cs-134 5.34
Cs-137 10.4
Fe-59 2.5
1-131 24.1
Mn-54 39\5
Na-24
Nb-95
Ni-95
Sb-124
Sr-89
Sr-90
W-187
Zn-65
Other 14.5
TOTAL 258.
ACTIVITY
- JUN JUL
PERCENT CURIES
13. 6.03
21.1 12.8
28.6 22.5
2.1 1.0
4.0 1.9
1.0 .4
9.3 .4
15.3 lT.7
5.6 4.4
100. 61.2
- DEC
PERCENT
9.8
20.9
36.8
1.7
3.2
.65
.65
19.1
7.2
100.
Table 22-a
61
-------
CATEGORY A
PLANT HATCH YEAR 1976 VOLUME: JAN - JUN 167. i
JUL - DEC 149. i
JAN
ISOTOPE CURIES
BaLa-140
Ce-141
Co-58* (17-9
44'7
Co-60 '26.8
Cr-51 57.7
Cs-134
Cs-137 * Estimate
and 60%
Fe-59
1-131
Mn-54
Na-24
Nb-95
Ni-95
Sb-124
Sr-89
Sr-90
W-187
Zn-65 38.8
Other 2.9
TOTAL 144 .
ACTIVITY
- JUN JUL
-PERCENT CURIES
(12) 12.6
31-
(19) 69.5
40.
based on 40% Co-58
Co-60
27- 50.2
2- 10.4
100. 143.
- DEC
PERCENT
8.8
48.7
35.2
7.3
100
Table 22-b
62
-------
CATEGORY A
PLANT HUMBOLDT BAY
ISOTOPE
BaLa-140
Ce-141
Co-58
Co-60
Cr-51
Cs-134
Cs-J.37
Fe-59
1-131
Mn-54
Na-24
Nb-95
Ni-95
Sb-124
Sr-89
Sr-90
W-187
Zn-65
Other
TOTAL
YEAR 1976 VOLUME: JAN - JUN
JUL - DEC
0.85 nr
ACTIVITY
JAN - JUN
CURIES PERCENT
.02
,03
,05
,01
.02
,137
JUL - DEC
CURIES PERCENT
15.
20.
40.
10.
15.
100.
Table 22-c
63
-------
CATEGORY A
PLANT MILLSTONE 1 YEAR 1976 VOLUME: JAN - JUN 207. m°
JUL - DEC 352. m3
JAN -
ISOTOPE CURIES
BaLa-140
Ce-141
Co-58
Co-60 428.
Cr-51
Cs-134 97.4
Cs-137 179.8
Fe-59
1-131
Mn-54 273.9
Na-24
Nb-95
Ni-95
Sb-124
Sr-89
Sr-90
W-187
Zn-65
Other 91.
TOTAL 1070.
ACTIVITY
- JUN JUL
PERCENT CURIES
40. 230.6
9.1 69.2
16.8 154.1
25.6 103.5
8.5 44.5
100. 602.
Table 22-d
- DEC
PERCENT
38.3
11.5
25.6
17.2
7.4
100.
64
-------
CATEGORY A
PLANT NINE MILE POINT
YEAR 1Q76 VOLUME: JAN - JUN
JUL - DEC
190.1
n
ISOTOPE
BaLa-140
Ce-141
Co-58
Co-60
Cr-51
Cs-134
Cs-137
Fe-59
1-131
Mn-54
Na-24
Nb-95
Ni-95
Sb-124
Sr-89
Sr-90
W-187
Zn-65
Other
TOTAL
JAN - JUN
CURIES PERCENT
ACTIVITY
294.8
348.4
629.8
4.3
41.5
2.4
11.1
7.6
1340.
22.
26.
47.
.32
3.1
.18
.83
.57
100.
JUL - DEC
CURIES PERCENT
Table 22-e
65
-------
CATEGORY A
PLANT VERMONT YANKEE YEAR 1976 VOLUME: JAN - JUN 44.
JUL - DEC i
JAN
ISOTOPE CURIES
BaLa-140
Ce-141
Co-58
Co-60 3.4
Cr-51 2.0
Cs-134
Cs-137 2.0
Fe-59
1-131
Mn-54
Na-24
Nb-95
Ni-95
Sb-124
Sr-89
Sr-90
W-187
Zn-65 2.9
Other 1.7
TOTAL 11.9
ACTIVITY
- JUN JUL
PERCENT CURIES
28.7
16.6
16.6
24.1
14.1
100.1
- DEC
PERCENT
Table 22-f
66
-------
CATEGORY B
PLANT COOPER
ISOTOPE
BaLa-140
Ce-141
Co-58
Co-60
Cr-51
Cs-134
Cs-137
Fe-59
1-131
Mn-54
Na-24
Nb-95
Ni-95
Sb-124
Sr-89
Sr-90
W-187
Zn-65
Other
TOTAL
YEAR 1974 VOLUME: JAN - JUN i .7R m;
JUL - DEC 3.55 m;
ACTIVITY
JAN
Cl/RIES
JUN
PERCENT
JUL
CURIES
DEC
PERCENT
3.8E-6
2.6
25.7
25.7
7.62E-5
31.8
8.22
49.9
Table 23-a
67
-------
CATEGORY B
PLANT
HATCH
ISOTOPE
BaLa-140
Ce-141
Co-58
Co-60
Cr-51
Cs-134
Cs-137
Fe-59
1-131
Mn-54
Na-24
Nb-95
Ni-95
Sb-124
Sr-89
Sr-90
W-187
Zn-65
Other
TOTAL
YEAR 1974 VOLUME: JAN - JUN
JUL - DEC
12.8
m
ACTIVITY
JAN - JUN
CURIES PERCENT
JUL - DEC
CURIES PERCENT
.0042
.0225
.003
.03
14
75.
11.
100.
Table 23-b
68
-------
CATEGORY B
PLANT COOPER
ISOTOPE
BaLa-140
Ce-141
Co-58
Co-60
Cr-51
Cs-134
Cs-137
Fe-59
1-131
Mn-54
Na-24
Nb-95
Ni-95
Sb-124
Sr-89
Sr-90
W-187
Zn-65
Other
TOTAL
YEAR 1975 VOLUME: JAN - JUN
JUL - DEC
ACTIVITY
. 7
m
JAN - JUN JUL - DEC
CURIES PERCENT CURIES PERCENT
.06
.02
.15
.02
<.01
.247
24.2 .1
7.25 .05
61.6 .22
6.76
.19 .03
100. .401
25.7
11.5
54.9
7.9
100.
Table 24-a
69
-------
CATEGORY B
PLANT HATCH YEAR 1975 VOLUME: JAN - JUN 91.1
JUL - DEC 94.4 i
JAN •
ISOTOPE CURIES
BaLa-140
Ce-141
Co-58 .074
Co-60
Cr-51 .095
Cs-134
Cs-137
Fe-59
1-131
Mn-54
Na-24
Nb-95
Ni-95
Sb-124
Sr-89
Sr-90
W-187
Zn-95 .0296
Other .013
TOTAL .211
ACTIVITY
- JUN JUL
PERCENT CURIES
35. .27
45. .35
14- .238
6. .018
100. .884
- DEC
PERCENT
31.
40.
27.
2.
100.
Table 24-b
70
-------
CATEFORY B
PLANT
HUMBOLDT BAY
ISOTOPE
BaLa-140
Ce-141
Co-58
Co-60
Cr-51
Cs-134
Cs-137
Fe-59
1-131
Mn-54
Na-24
Nb-95
Ni-95
Sb-124
Sr-89
Sr-90
W-187
Zn-65
Other
TOTAL
YEAR 1975 VOLUME: JAN - JUN
JUL - DEC
89.3
ACTIVITY
JAN - JUN
CURIES PERCENT
12.1
4.
12.1
6.
40.2
JUL - DEC
CURIES PERCENT
30.
10.
15.
30.
15.
100.
Table 24-c
71
-------
CATEGORY B
PLANT VERMONT YANKEE YEAR 1975 VOLUME: JAN - JUN 21.4
JUL - DEC 139.
JAN -
ISOTOPE CURIES
BaLa-140
Ce-141
Co-58
Co-60 .3
Cr-51 .2
Cs-134
Cs-137 .2
Fe-59
1-131
Mn-54
Na-24
Nb-95
Ni-95
Sb-124
Sr-89
Sr-90
W-187
Zn-65 .3
Other .2
TOTAL 1 . 2
ACTIVITY
- JUN JUL
PERCENT CURIES
28.7 .8
16.6 .5
14.1 .4
24.1 .7
16.5 .5
100. 2.9
- DEC
PERCENT
28.7
16.6
14.1
24.1
16.5
10Q.
Table 24-d
72
-------
CATEGORY B
PLANT COOPER YEAR 1976 VOLUME: JAN - JUN 31.4
JUL - DEC 42.5
JAN -
ISOTOPE CURIES
BaLa-140
Ce-141
Co-58 .03
Co-60 -02
Cr-51 .06
Cs-134
Cs-137
Fe-59
1-131
Mn-54 .01
Na-24
Nb-95
Ni-95
Sb-124
Sr-89
Sr-90
W-187
Zn-65
Other -01
TOTAL -!32
ACTIVITY
- JUN JUL
PERCENT 'CURIES
22.6 .15
15.1 .24
45.3 .32
.02
.05
.01
.10
7.55 .17
9.45 .06
100. 1.12
- DEC
PERCENT
13.
21.1
28.6
2.07
4.02
.95
9.35
15.3
5.61
100.
Table 25-a
73
-------
CATEGORY B
PLANT HATCH
YEAR 1976 VOLUME: JAN - JUN
JUL - DEC
61.6
m-
33.5
ACTIVITY
ISOTOPE
BaLa-140
Ce-141
Co-58*
Co-60*
Cr-51
Cs-134
Cs-137
Fe-59
1-131
Mn-54
Na-24
Nb-95
Ni-95
'Sb-124
Sr-89
Sr-90
W-187
Zn-65
Other
TOTAL
JAN - JUN
CURIES PERCENT
JUL - DEC
CURIES PERCENT
14
22
.364
.47
Estimate
and 60%
.318
.023
1.17
31.
40.
12,
19,
.0383
.455
based on 40% Co-58
Co-60
27,
2.
.329
.111
100.
.933
4.1
48.7
35.2
12.
100.
Table 25-b
74
-------
CATEGORY B
PLANT HUMBOLDT BAY
ISOTOPE
BaLa-140
Ce-141
Co-58
Co-60
Cr-51
Cs=134
Cs=137
Fe-59
1-131
Mn-54
Na-24
Nb-95
Ni-95
Sb~124
Sr-89
Sr-90
W-187
Zn-65
Other
TOTAL
YEAR _I2ZJL_ VOLUME: JAN - JUN ____4JLJL__m'
JUL - DEC m':
ACTIVITY
JAN - JUN
CURIES PERCENT
.85
.28
,42
.85
,42
2.82
JUL
CURIES
DEC
PERCENT
30,
10,
15.
30.
15.
100.
Table 25»c
75
-------
CATEGORY B
PLANT MILLSTONE 1 YEAR 1976 VOLUME: JAN - JUN 291.
JUL - DEC 478.
JAN
ISOTOPE CURIES
BaLa-140
Ce-141
Co-58
Co-60 13.5
Cr-51
Cs-134
Cs-137 1.7
Fe-59
1-131
Mn-54 2.4
Na-24
Nb-95
Ni-95
Sb-124
Sr-89
Sr-90
W-187
Zn-65
Other 1.1
TOTAL 18.8
ACTIVITY
- JUN JUL
PERCENT CURIES
72. 4.19
9. .52
13. .76
6. .35
100. 5.82
- DEC
PERCENT
72.
9.
13.
6.
100.
Table 25-d
76
-------
CATEGORY B
PLANT VERMONT YANKEE
YEAR 1976 VOLUME: JAN - JUN
JUL - DEC
32,
ra-
ISOTOPE
BaLa-140
Ce-141
Co-58
Co-60
Cr-51
Cs-134
Cs-137
Fe-59
1-131
Mn-54
Na-24
Nb-95
Ni-95
Sb-124
Sr-89
Sr-90
W-187
Zn-65
Other
TOTAL
ACTIVITY
JAN - JUN
CURIES PERCENT
JUL - DEC
CURIES PERCENT
.53
.30
.30
.44
.26
1.83
28.7
16.6
16.5
24.1
14.1
100.
Table 25-e
77
-------
CATEGORY A
PLANT PRESSURIZED WATER REACTORS VOLUME: 1975 604.5 m3
ACTIVITY
1976 1245.4 m3
1975 1976
ISOTOPE CURIES PERCENT CURIES PERCENT
Co-57 '°6
Co-58 887'56
Co-60 1112.08
Cs-134 776.63*
Cs-137 1215. *
Fe-59
1-131 .05
Mn-54 28.275
Nb-95 -04
Nb-97 -97
Sb-124 -52
Sb-125
Other .36
TOTAL 4075.
<.01 -04
21.8 152.5
27.3 585.64
19.6 254.44
30.6 434.45
.02
<-01 .68
•7 33.97
<.01
<.01
<.01 .24
<.01 167.75
100. 1630.04
<.01
9.4
35.9
15.6
26.6
<.01
<.01
2.1
<.01
<.01
10.3
>99.9
Includes 54 curies reported as combined. 22 curies were assumed
to be Cs-134 and 32 curies as Cs-137.
Table 26-a
78
-------
CATEGORY B
PLANT PRESSURIZED WATER REACTORS VOLUME: 1975 812.7
ACTIVITY
1976 877.4
1975 1976
ISOTOPE CURIES PERCENT CURIES PERCENT
Co-57 .6
Co-58 24.3
Co-60 21.5
Cs-134 6.1
Cs-137 11.7
Fe-59
1-131
Mn-54 3.6
Nb-95 .1
Nb-97
Sb-124
Sb-125 .3
Other .8
TOTAL 69.
.9
35.2 17.1
31.2 18.2
8.8 15.1
17.0 28.9
5.2 1.1
.1 .6
.5
.4
1.2 22.0
100. 103.5
16.5
17.6
14.6
27.9
1.1
.6
.5
21.2
100.
Table 26-b
79
-------
CATEGORY A
PLANT BOILING WATER REACTORS VOLUME: 1974 487. m 3
1975 840. m3
ACTIVITY
1974 1975
ISOTOPE CURIES PERCENT CURIES PERCENT
BaLa-140
Ce-141
Co-58 6.4
Co-60 .4
Cr-51 17.8
Cs-134
Cs-137
Fe-59
1-131
Mn-54
Na-24
Nb-95
Ni-95
Sb-124
Sr-89
Sr-90
W-187
Zn-65
Other .9
TOTAL 25.5
.4
25. 145.5
2. 58.5
70. 223.4
.6
3.8
1.5
27.6
3.4
trace <.001
69.4
3. 26.0
100. 560.
.07
26.0
10.4
39.9
.1
.7
.3
4.9
.6
<.01
12.4
4.9
99.97
Table 27-a
80
-------
CATEGORY A
PLANT BOILING WATER REACTORS
ACTIVITY
1976
ISOTOPE CURIES PERCENT
BaLa-140
Ce-141
Co-58 57.4
Co-60 1063.4
Cr-51 225.5
Cs-134 521.4
Cs-137 978.0
Fe-59 2.9
1-131 28.8
Mn-54 470.1
Na-24
Nb-95
Ni-95
Sb-124
Sr-89 2.4
Sr-90 11.1
W-187
Zn-65 91.9
Other 177.0
TOTAL 3630.
1.6
29.3
6.2
14.4
26.9
.08
.8
13.0
<.01
.3
2.5
4.9
99.99
Table 27-b
81
VOLUME 1976
1337
m-
-------
CATEGORY B
PLANT BOILING WATER REACTORS VOLUME: 1975 507. m3
1976 1015. m3
ACTIVITY
1975 1976
ISOTOPE CURIES PERCENT CURIES PERCENT
BaLa-140
Ce-141
Co-58 .5
Co-60 13.3
Cr-51 1.5
Cs-134 4.0
Cs-137 6.6
Fe-59
1-131
Mn-54 12.1
Na-24
Nb-95 .02
Ni-95
Sb-124
Sr-89
Sr-90
Zn-65 1.0
Zn-95 .27
Other 6.73
TOTAL 46.0
1.1 .36
28.9 19.6
3.3 1.6
8.7 .3
14.3 3.0
.01
.1
26.3 4.2
.04
2.2 1.09
.6
14.6 2.33
100. 32.6
1.1
60.1
4.9
.9
9.2
.03
.3
12.9
3.3
7.2
99.93
Table 27-c
82
-------
Relative Composition of Low-Level Solid
Waste from LWRs
Ci/plant-yr (%)
m3/plant-yr
% by nuclide
Co-58
Co-60
Cs-134
Cs-137
Mn-54
Other
Category A
(filter sludge, resin
and evap. bott.)
PWR BWR
670 (96) 400 (98)
275 (54) 250 (57)
Category B
(dry compress.,
contain, equip.)
PWR BWR
26 (4) 10 (2)
230 (46) 190 (43)
18
30
18
30
1
3
5
27
12
23
12
21
26
20
11
20
4
19
1
42
5
12
21
19
Table 28
83
-------
Composition of Solid Waste by Nuclide - NRC
Nuclide % Filter Sludge/Spent Resin Evaporator Bottoms
BWR1 PWR2 BWR3 PWR2
Co-58 - 1 22
Co-60 40 39 15 17
Cs-134 8 18 28 20
Cs-137 30 25 49 18
Mn-54 22 3 26
1-131 - - 19
1 Nine Mile Point Unit 1, January - December 1974
2 H. B. Robinson Unit 2, January - June 1975
3 Nine Mile Point Unitl, January - June 1975
Table 29
84
-------
Composition of Solid Waste by Nuclide - Dames & Moore
Nuclide %
Filter Sludge
BWR PWR
Spent Resin
BWR PWR
Evaporator Bottoms
BWR PWR
Co-58
Co-60
Cs-134
Cs-137
Fe-55
-
12
6
9
61
1
17
1
1
63
-
15
7
73
1
1
5
30
53
3
-
11
20
27
34
10
6
11
30
1
Table 30
85
-------
CO
0
T3
01
n,
a
0)
4-1
CO
O
01
3000
2000
1000
tlr
iiiik
ii
^Prorated Data
Actual Data
1L
3 5 7
Years of Operation
Annual Volume of Waste Shipped vs. Number of Years of Operation
Boiling Water Reactors
Figure 1
86
-------
5xl03
a
i
0)
P.
ex
•H
ca
a)
a)
&
iH
o
n)
I
103
102
50
4 6
Years of Operation
10
Annual Volume of Waste Shipped vs. Number of Years of Operation
Boiling Water Reactors
Figure 2
87
-------
CO
a
0)
a,
CO
«J
o
cu
10"
103 ,
102
10
Prorated Data
Actual Data
2 4 6 8 10
Years of Operation
Annual Volume of Waste Shipped vs. Number of Years of Operation
Boiling Water Reactors
Figure 3
88
-------
O
(1)
O.
O.
•H
,C
CO
rt
4-1
•H
rt
s
10000
8000
6000
4000
tH^J
IT;:
200D
iirt+rtt
ffi
-ii
ffi
nt:
Ftt
Prorated Data
I
Actual Data-
rr
ffi
13579
Years of Operation
Annual Activity of Waste Shipped vs. Number of Years of Operation
Boiling Water Reactors
Figure 4
89
-------
5xl(T
10"
£
•H
U
1
"8
a
a
•H
,0
Crt
0)
4-1
CO
£ 103
4-1
O
>>
4J
•H
£
4-J
O
-------
2 4 6 8 10
Years of Operation
Annual Activity of Waste Shipped vs. Number of Years of Operation
Boiling Water Reactors
Figure 6
91
-------
1200
CO
a
r
T)
Cu
•rl
O
0)
cd
E
1000 ::
800
600
400
200
3 5
Years of Operation
Annual Volume of Waste Shipped vs. Number/of Years of Operation
Pressurized Water Reactors
Figure 7
92
-------
5xl03
a
i
-a
01
o.
co
0)
w
cd
0)
6
g
103
102 =
50
4 6
Years of Operation
Annual Volume of Waste Shipped vs. Number of Years of Operation
Pressurized Water Reactors
Figure 8
'93
-------
0
I
CO
I
e
cd
§
c
2 4 6
Years of Operation
8 10
Annual Volume of Waste Shipped vs. Number of Years of- Operation
Pressurized Water Reactors
Figure 9
94
-------
QJ
D.
a
CO
I
o
^
-------
5xlOc
U
I
0)
a,
a
CO
cfl
13
o
^
4-1
•H
3
4-1
O
n)
I
103
10
Prorated Data:
Actual Data
4 6
Years of Operation
10
Annual Activity of Waste Shipped vs. Number of Years of Operation
Pressurized Water Reactors
Figure 11
96
-------
0)
cx
a
•H
,c
4-1
CO
14-1
o
4-1
•H
>
rt
I
10'
10
t m
~:l-
tr-
Prorated Data
Actual Data
g 4 6 8 10
Years of Operation
Annual Activity of Waste Shipped vs. Number of Years of Operation
Pressurized Water Reactors
Figure 12
97
-------
References
Be-77 Bell M. J., 1977, "Sources of Reactor Wastes, Their Characteri-
zation and Amounts", Radwaste Management Workshop, sponsered by
ORNL.
Cr-69 CRC Handbook of Tables for Probability and Statistics, Second
Edition 1969, pg 390, (Edition by Beyer, W.) published by The
Chemical Rubber Co.
Da-76 Dames & Moore, 1976, "Preliminary Draft - Final Report Study to
Characterize Low-Level Radioactive Wastes Generated by Light
Water Reactors", prepared for the New York State ERDA.
Ma-75 Mann B. J., Goldberg S. M., Hendricks W. D., 1975, "Low-Level
Solid Radioactive Waste in the Nuclear Fuel Cycle", in Trans.
Am. Nuc. Soc., Winter Meeting.
Mu-76 Mullarkey T. B., Jentz T. L., Connelly J. M., Kane J. P., 1976,
"A Survey and Evaluation of Handling and Disposing of Solid Low-
Level Nuclear Fuel Cycle Wastes", AIF/NESP-008ES.
98
------- |