PWR Source Term Generation and Evaluation Rev 00B, ICN 00

000-00C-MGR0-00100-000-00B

May 2004

1. PURPOSE 
This calculation is a revision of a previous calculation (BSC 2003 [DIRS 162471]) that bears the 
same title and has the Document Identifier 000-00C-MGR0-00100-000-00A. The purpose of 
this calculation is to revise the burnup value of the maximum pressurized water reactor (PWR) 
spent nuclear fuel (SNF) assembly to be consistent with Licensing Position-009 (Williams 2003, 
Attachment, p. 1 [DIRS 166132]). No new computer runs were performed for this revision. The 
source terms for the maximum PWR assembly were taken from the results of computer runs 
performed for the previous revision - BSC 2003 [DIRS 162471]. 
The scope of work includes the following: 
 Generate PWR SNF assembly source terms as a function of initial enrichment, burnup, 
and cooling time using an appropriate and defensible methodology. 
 Provide the average and maximum PWR fuel assembly specifications. 
 Calculate crud source term deposited on the surfaces of the assembly. 
This calculation establishes PWR SNF assembly source terms. The results of this calculation are 
intended for use in evaluation of shielding requirement or other follow-on analysis. They may 
also be used as input for Preclosure Safety Analysis and Total System Performance Assessment 
analyses. 
The results are provided on a per-assembly basis for the representative PWR fuel assembly used 
in this calculation. Limitation on the use of the results for other fuel assembly types should be 
evaluated on a case-by-case basis. 
The source terms of the representative PWR SNF assembly are generated for the first one million 
years after the SNF is discharged from the reactors. These source terms provide data 
characterizing the neutron and gamma spectra in particles per second, the decay heat in watts, 
and radionuclide inventories in curies. Conservative source terms are generated for a wide range 
of burnups and enrichments (see Tables 8 and 12) that are representative of the waste stream, 
stainless steel (SS) clad, and South Texas PWR assemblies. The source term due to the 
activation of corrosion products deposited on the surfaces of the assembly from the coolant is 
also calculated. 
The results of this calculation support many areas of the Monitored Geologic Repository (MGR), 
which include thermal evaluation, radiation dose determination, radiological safety analyses, 
surface and subsurface facility designs, preclosure safety analysis, and total system performance 
assessment. Therefore, it is subject to the requirements of the Quality Assurance Requirements 
and Description (DOE 2004 [DIRS 168669]). This includes MGR items classified as Safety 
Category, for example, the Commercial Waste Package (BSC 2003, p. A-3 [DIRS 165179]). 
Development, performance, and documentation of this calculation conform to the administrative 
procedure AP-3.12Q, Design Calculation and Analyses [DIRS 168413].

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
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2. METHOD 
The method used to evaluate the radioactive nuclides inventory and source terms at a specific 
time involves the simulation of the burnup and decay of fuel assemblies. For the previous 
revision of this calculation, the SAS2H/ORIGEN-S sequence of SCALE 4.3 computer code 
system was used to calculate the source terms for the selected fuel assemblies as function of 
assembly average burnup and cooling time. No new calculations were performed with 
SCALE 4.3 for this revision. Uncertainties and limitations in the computed source terms by the 
SAS2H/ORIGEN-S sequence are discussed in the SAS2H manual (CRWMS M&O 2000, 
Section S2.3 [DIRS 153872]) and in the NUREG/CR-5625 report (Hermann et al. 1994, 
Section 6.6.2 [DIRS 154045]). 
For each time-dependent fuel composition, SAS2H performs 1D neutron transport analysis of the 
reactor fuel assembly using a two-part procedure with two separate lattice-models. Basically, the 
model represents the fuel by an infinite lattice of fuel pins (path-A model) and the cell-weighted 
cross sections produced with the path-A model are then applied to the fuel region of a larger 
unit-cell model (path B) used to represent a fuel assembly. The concept of using cell-weighted 
data in the 1D transport analysis of the path-B model is an approximate method for including the 
2D assembly effects. The path-B model is used by SAS2H to calculate an "assembly-averaged" 
fuel-region flux spectrum that includes the effects of the path-A model and other components in 
the assembly (e.g., guide tubes, burnable poison rods, etc.). The cross sections derived from a 
transport analysis at each time step are used in a point-depletion computation via ORIGEN-S that 
produces the burnup-dependent fuel composition to be used in the next spectrum calculation. 
This sequence is repeated over many cycles over the power history). 
Geometrically, SAS2H models the actual assembly by defining an equivalent cylindrical 
representation. Besides the geometric simplification, other approximations within SAS2H are: 
 Axial uniformity, 
 Densities within the fuel pin are considered uniform with space, 
 A constant temperature is applied in each zone of the unit cell, 
 A single fuel-pin unit-cell type is assumed for the entire assembly (i.e., all fuel pins are 
assumed to have the same enrichment), and 
 Fuel loading is proportional to the fuel length. 
The resulting source terms are extracted from the SAS2H output to create data files for future 
analyses. 
Electronic management of information generated from this calculation is controlled in 
accordance with AP-3.13Q, Design Control, [DIRS 167460]. The computer input and output 
files generated from this calculation are stored on four compact disks (CDs), and submitted as an 
attachment to this document (Attachment X).

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Title: PWR Source Term Generation and Evaluation 
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3. ASSUMPTIONS 
3.1 It is assumed that various PWR assembly types can be approximated by a single assembly 
and the source terms generated will not be greatly affected by using this common 
geometry. This assumption results in the path A and B representations in SAS2H for unit 
cells of the South Texas and SS assemblies being identical to those of the 
Babcock & Wilcox (B&W) Mark B assembly used to represent the waste stream cases. 
Different initial heavy metal loadings (IHMLs) are accounted for by adjusting the fuel 
length, which is calculated from the IHML and the fuel density. 
Rationale: A sensitivity study (BSC 2004, Section 6.4 [DIRS 167058]) determined that the 
selection of a particular assembly is not sensitive to the resulting source terms. 
Usage: This assumption is used in the entire calculation. 
3.2 It is assumed that the neutron activation factors for the assembly hardware regions (bottom 
end-fitting, plenum, and top end-fitting) are 1.5 time of the values recommended by the 
U.S. Nuclear Regulatory Commission (NRC) and provided in Luksic 1989, Table S.1 
[DIRS 120506]. 
Rationale: This assumption provides 50% conservative margin for the neutron-activated 
sources in the hardware regions. 
Usage: This assumption is used in Section 5.3. 
3.3 It is assumed that the fuel rod length is 153.68 in. or 390.3472 cm (DOE 1988, p. 2A-33 
[DIRS 100979]) and that the plenum region height is the difference between the fuel rod 
length and the fuel stack height (30.1752 cm = 390.3472 cm  360.172 cm). 
Rationale: Fuel rod data are proprietary information and. DOE 1988 [DIRS 100979] is the 
best available technical information. 
Usage: This assumption is used in Section 5. 
3.4 The hardware parts and materials of the B&W Mark B PWR assembly described in 
DOE 1988, p. 2A-32 and p. 2A-34 [DIRS 100979] are assumed. 
Rationale: Fuel assembly data are proprietary information and the information in 
DOE 1988 [DIRS 100979] is the best available. 
Usage: This assumption is used in Section 5.3. 
3.5 It is assumed that the South Texas assembly will generate the bounding crud source term 
and that the physical characteristics of the South Texas assembly can be obtained from 
DOE 1988, p. 2A-361 and p. 2A-363 [DIRS 100979]. 
Rationale: Again, DOE 1988 [DIRS 100979] is the best available technical information on 
PWR fuel. The crud source is proportional to the surface area that is exposed to coolant; 
since the South Texas fuel assembly has larger surface area than the B&W Mark B 
assembly, it will generate a more conservative (higher) crud source that will serve as the 
bounding crud source for the representative PWR assembly. 
Usage: This assumption is used in Section 5.3.

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
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4. USE OF COMPUTER SOFTWARE AND MODELS 
4.1 SOFTWARE APPROVED FOR QA WORK 
The SAS2H/ORIGEN-S sequence of SCALE Version 4.3, modular code system (CRWMS 
M&O 1997, [DIRS 154059]) was used to perform source terms (decay thermal power, gamma 
spectrum, neutron spectrum) and radionuclide inventory calculations. The software 
specifications are as follows: 
 Program Name: SCALE 
 Version/Revision Number: 4.3 (Addendum) HP 9000 Version 
 CSCI Number: 30011 V4.3 (Addendum) (CRWMS M&O 1997 [DIRS 154059]) 
 Computer Type: Hewlett Packard 9000 Series 
 Status/Operating System: qualified1/HP-UX 10.20 
 Computer Processing Unit Names and Civilian Radioactive Waste Management System 
(CRWMS) Management and Operating (M&O) Contractor Tag Number: Bloom, 
CRWMS-M&O Tag 700887. 
The SAS2H/ORIGEN-S sequence of SCALE Version 4.3 software was: (a) appropriate for 
source term calculations, (b) used only within the range of validation as documented in CRWMS 
M&O 1997. Software Qualification Report for THE SCALE Modular Code System Version 4.3. 
[DIRS 106016], and (c) obtained from Software Configuration Management in accordance with 
the appropriate procedure. 
The *.cut files, which consist of the input echoes and the final ORIGEN-S outputs, are listed in 
Attachment VIII and their electronic versions are stored in Attachment X. The *.cut files are 
sufficient to independently repeat the calculation. 
4.2 EXEMPT SOFTWARE 
4.2.1 Excel 
 Title: EXCEL 
 Version/Revision Number: Microsoft Excel 2000 SR-1 
 This software is installed on a personal computers running Microsoft Windows 2000 with 
CPU Number 501661. 
Standard functions of Microsoft Excel for Windows, Version 2000 SR-1, are used in this 
calculation to display results graphically or in tabular form and to perform simple calculations as 
documented in Section 5 of this calculation. The user-defined formulas, inputs, and results are 
documented in sufficient detail in Section 5 to allow an independent repetition of the various 
computations without recourse to the originator. Microsoft Excel is an exempt software product 
1 The modular code system SCALE Version 4.3 results were produced in prior revisions of this calculation. This 
software version has since been retired.

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Title: PWR Source Term Generation and Evaluation 
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according to the procedure LP-SI.11Q-BSC, Software Management, Section 2.1.6 
[DIRS 168412]. The Excel files are stored on CDs (Attachment X) and documented in 
Attachment VIII. 
4.2.2 UNIX Script Files 
 Titles: cut-script, neutrons, gammas, curies, watts 
 Version/Revision Number: All are version 00 
 Computer Type: Hewlett Packard 9000 Series 
The UNIX script files are listed in Table 1. The cut-script file executes SAS2H and generates 
a *.cut file from the SAS2H output file. The other four files perform simple editorial tasks that 
extract lines of information from a single *.cut file. They are executed by typing the command 
awk f (script file) (input *.cut file name) > (output file name). These files are intended for 
use only with the SAS2H/ORIGEN-S output files for the waste stream, SS clad, and South Texas 
assemblies stored in Attachment X. The output of the script files has been verified by visual 
inspection. The specific task of each script file is noted in Table 1. The script files are listed in 
Attachment V. This software is considered exempt from the requirements of LP-SI.11Q-BSC, 
Software Management, Section 2.1.2 [DIRS 168412]. 
Table 1. UNIX Script Files 
File Name Function 
neutrons Extracts the total (alpha-n plus spontaneous fission) neutron source table from a *.cut file 
gammas Extracts the gamma source from the light element, actinide, and fission product contributions from a 
*.cut file 
watts Extracts the total thermal output from the light element, actinide, and fission product contributions 
from a *.cut file 
curies Extracts the tables of nuclide curies from a *.cut file for the light element, actinide, and fission 
product contributions 
cut-script Generates *.cut file from each SAS2H output file

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5. CALCULATION 
5.1 REVISION HISTORY 
The purpose of this revision is to update the burnup value for the maximum PWR SNF assembly 
to 80 GWd/MTU in conformance with the Licensing Position-009 (Williams 2003, Attachment, 
p. 1 [DIRS 166132]). At the same time, based on the conclusion of BSC 2004 [DIRS 167058], 
the rationale of the Assumption 3.1 was modified since a sensitivity study (BSC 2004, 
Section 6.4 [DIRS 167058]) determined that the selection of a particular assembly is not 
sensitive to the resulting source terms. Also, an Acronyms and Abbreviation section and 
Attachment XI were added. 
Several calculations have been performed to provide PWR SNF source terms for shielding 
calculations. CRWMS M&O 1997 [DIRS 136439] was the first in a series of calculations to 
provide source terms, but was limited to a South Texas assembly and a handful of burnups and 
enrichments that represented the anticipated average and maximum waste stream assemblies. In 
addition, the source terms represented only the first twenty-five years after discharge from the 
reactor. CRWMS M&O 1998 [DIRS 124815] built on this calculation to extend the source terms 
to 30,000 years. CRWMS M&O 1999 [DIRS 105912] extends the calculation done in CRWMS 
M&O 1998 [DIRS 124815] to include a wide range of burnups and enrichments, and the 
inclusion of a crud source. The sources were also provided out to 1 million years after discharge. 
CRWMS M&O 1999 [DIRS 136429] provides a complete set of conservative source terms for 
the SS clad, South Texas, and PWR assemblies in the expected waste stream. BSC 2003 
[DIRS 162471] expands the source terms database of the representative PWR SNF in CRWMS 
M&O 1999 [DIRS 136429] to include burnups of 80 and 85 GWd/MTHM. 
The following modifications are included in this revision: 
 Figure 3, Table 14, Attachment VII and IX were updated to include the values calculated 
in the last revision (BSC 2003 [DIRS 162471]) for the PWR SNF assembly maximum 
burnup of 80 GWd/MTU. The cooling times selected to present the curies inventories 
correspond with those used in SAS2H calculations. 
 The description of the design methodology was expanded in Section 2. 
 Acronyms and Abbreviations section was added. 
 Sections 1, 3, 5.1, 5.5, and 6 were modified. 
 Attachment VIII was modified to reflect the current content of the CDs. 
Since this revision retains all the results of BSC 2003 [DIRS 162471], the methodology and 
calculation method of the last revision and this revision are the same. The fuel densities for the 
PWR assemblies are kept constant, and the lengths of the assemblies are varied to reflect the 
heavy metal loading in the SAS2H calculations (see Section 5.4.2). 
5.2 SELECTION OF CONSERVATIVE PARAMETERS 
The inputs for this calculation are specifically chosen to lead to conservative source terms. This 
section discusses the main inputs and the reasons they are used. It covers several different

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Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page 11 of 33 
parameters. The first of these is the geometry for the South Texas, waste stream, and SS clad 
assemblies. 
In this calculation, the geometry used to model the assemblies in SAS2H corresponds to a typical 
B&W Mark B PWR fuel assembly. The Mark B has a high IHML and a large amount of 
assembly hardware, supporting more fission product generation and hardware activation. 
Therefore, this assembly provides a conservative basis for the PWR waste stream. While a real 
Mark B assembly has an IHML of 464 kg, this is increased to 475 kg for the waste stream and 
the SS clad assemblies to provide slightly higher source intensities. The South Texas assembly 
calculations use a 550 kg IHML. 
As mentioned in Section 5.1, additional heavy metal mass is accounted for by increasing the fuel 
length, rather than the fuel density. A longer active fuel length and a lower density rather than a 
shorter fuel length and a higher density decrease the fuel self-shielding. This results in a higher 
flux and consequently higher source intensities. In this calculation the higher IHML of the waste 
stream, SS clad, and South Texas assemblies is accounted for by the fuel length rather than the 
fuel density (see Section 5.4.2). 
The fuel density also affects the source from the hardware regions of the assembly. The 
irradiation of the assembly hardware is calculated by inputting the desired amount of light 
element material into the fuel region in SAS2H. When the sources are calculated, only the light 
elements are included. For the South Texas assembly, since the same power is generated by a 
longer fuel rod than by the shorter Mark B, the result is a lower power density. This lower flux 
per unit height for the South Texas assembly provides a lower source for the hardware regions. 
For this reason, the South Texas assemblies use the hardware files for the waste stream (the SS 
assemblies also use waste stream files for the bottom and top assembly regions). In addition, 
since these hardware sources are calculated by irradiating the material in the fuel region, scaling 
factors (SF) are used to account for the lower flux seen in the non-fuel regions of the reactor. 
The SFs for the neutron flux, provided in Luksic 1989, Table S.1 [DIRS 120506], have an 
uncertainty of  50%. To generate conservative source terms for the non-fuel regions of the 
PWR assembly, the scaling factors used in this calculation represent 150% of those listed in 
Luksic 1989 [DIRS 120506]. 
Consideration has also been given to the material definitions. The compositions of Zircaloy-4 
(ASTM B 811-90 1991 [DIRS 131753]), Stainless Steel 304, Stainless Steel 304L (ASME 2001 
[DIRS 158115]), Stainless Steel 302 (ASTM A 240/A 240M-97a 1997 [DIRS 102769]), 
Inconel-718 (Inco Alloys International 1988 [DIRS 130835]), and Stainless Steel CF3M 
(ASM 1980 [DIRS 104317]) are representative of materials used in the manufacture of nuclear 
fuel assemblies. These compositions use the maximum amounts of cobalt given by the 
references and a 0.08 wt% cobalt impurity (Ludwig and Renier, p. 45 [DIRS 146398]) for the 
stainless steels. While none is indicated in ASME 2001 [DIRS 158115] and ASTM A 240/A 
240M-97a 1997 [DIRS 102769], it is a common practice to include a cobalt impurity in stainless 
steels (due to nickel previously alloyed with cobalt). The balance of the remaining elements are 
representative of the material compositions for each material, but are biased towards the 
maximum amount of Sn, Ni, and Nb. Impurities are also included in the fuel itself, and are given 
in Table 4.

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Not all the activation sources can be calculated with SAS2H. The source due to corrosion 
material that accumulates on the surfaces of the assembly from the flow of coolant (crud) is also 
calculated. A bounding crud source term is based on the South Texas assembly. This 
representation of the South Texas does not use Mark B dimensions. The South Texas has a 
greater surface area exposed to coolant, and the crud source is strongly dependent on the 
available surface area. This dependence comes from the source being calculated with a 
radioisotope activity density (Ci/cm2). Two estimates for radioisotope densities are used, from 
two sources (NRC 2000 [DIRS 149756] and Jones 1992 [DIRS 146405]). This calculation is 
discussed in detail in Section 5.3.2. 
The enrichments calculated range from 0.711 wt% (natural) to 5.5 wt% (the complete list is 
shown in Section 5.4.2). This is done to cover the wide range seen in the waste stream and avoid 
the need to extrapolate for information on assemblies currently being developed. Also, the 
number of time steps has been increased to 180, in order to provide more detailed information, 
particularly for the first 100 years the fuel is out of the reactors. 
5.3 INPUT 
5.3.1 Input for SAS2H Source Calculations 
The general assembly description for a B&W Mark B PWR fuel assembly is provided in Table 2. 
Table 3 presents the PWR assembly hardware components and flux SF used to determine the 
masses of the light elements that are entered in SAS2H data Block 10. 
The concentrations of element impurities in fresh light water reactor fuel, in parts of element per 
million parts of heavy metal (ppm), are listed in Table 4. These values are provided by Ludwig 
and Renier [DIRS 146398] and reflect measured concentrations instead of the maximum 
allowable concentrations given in purity specifications. 
Table 5 provides the chemical compositions of the hardware materials used. Ranges are 
provided for some of the elements, and the values used in this calculation are provided.

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
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Table 2. B&W Mark B PWR Fuel Assembly Description and Operating Parameters 
Assembly Parameter Value Units Metric Units Reference 
Average core exit moderator temperature 612 F 595.4 K 
Average core moderator pressure 2200 Psia - - 
Maximum beginning of cycle boron 
concentration - - 1050 ppm 
Core thermal power - - 2568 MW 
Pellet average temperature (K) 1200 F 922 K 
Fuel cladding to moderator temperature 
differential 50-75 F 28-42 K 
Average core moderator temperature rise 59.4 F 33 K 
Framatome Cogema 1999, 
p 3 [DIRS 146419] 
In association with 
BSC 2003, p. 2 
[DIRS 165684] 
Number of guide tubes 16 /assembly NA NA 
Number of instrument tubes 1 /assembly NA NA 
Clad/tube material Zircaloy-4a NA NA NA 
Number of assemblies 177 In core NA NA 
Total number of fuel rods 208 /assembly NA NA 
Number of rods on a lattice side 15 /side NA NA 
Fuel pellet outer diameter (OD) 0.3686 inches 0.93624 cm 
Fuel stack height 141.8 inches 360.172 cm 
Fuel clad OD 0.430 inches 1.0922 cm 
Clad thickness 0.0265 inches 0.06731 cm 
Fuel rod pitch 0.568 inches 1.44272 cm 
Guide tube OD 0.530 inches 1.3462 cm 
Guide tube ID 0.498 inches 1.26492 cm 
Fuel clad inner diameter (ID) 0.377 inches 0.95758 cm 
Table 2-2 
Fuel pellet fraction of theoretical density - - 0.95 NA Table 2-9 
Mass of U - - 463.63 kg Table 3-1 
Fuel assembly envelope 8.536 inches 21.6814 cm 
Punatar 2001b 
[DIRS 155635] 
p. 2-3 
Fuel rod length 153.68 inches 390.3472 cm 
Plenum region height - - 30.1752 cm 
Assumption 3.3 
Specific volume of steam at 2200 psi, 580F 0.02275 ft3/lbm - - 
Specific volume of steam at 2200 psi, 590F 0.02235 ft3/lbm - - 
ASME 1993, p. 281 
[DIRS 108050] 
NOTE: a Stainless steel clad calculations use SS-304 as the clad material. 
b The sources of the fuel assembly physical data in Punatar 2001 [DIRS 155635] are from [DIRS 154999], 
[DIRS 155000], [DIRS 155001], and [DIRS 155002].

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Table 3. Assembly Hardware and Flux Scaling Factors 
Region Flux Scaling Factorsa Part Nameb kg/Assemblyb Materialb 
Top nozzle 7.48 Stainless Steel CF3M 
Spring retainer 0.91 Stainless Steel CF3M 
Hold down spring 1.8 Inconel-718 
Upper end plug 0.06 Stainless Steel 304 
Top end fitting 0.15 
Upper nuts 0.51 Stainless Steel 304L 
Bottom nozzle 8.16 Stainless Steel CF3M 
Spacer-bottom 1.3 Inconel-718 Bottom end fitting 0.30 
Lower nuts 0.15 Stainless Steel 304c 
Guide tubes 8.0 Zircaloy-4d 
Instrument tube 0.64 Zircaloy-4 
Spacers-incore 4.9 Inconel-718 
Grid supports 0.64 Zircaloy-4 
Spacer-plenum 1.04 Inconel-718 
Fuel/Plenum fuel region - 1.00 
plenum region - 0.30 
Plenum spring 0.042e Stainless Steel 302e 
NOTE: a Assumption 3.2. 
b Assumption 3.4. 
c Zircaloy-4 was used instead of SS 304, but the effect on 60Co activated source is negligible because of the 
much larger cobalt content in the bottom nozzle and bottom spacer. 
d Stainless steel clad calculations use SS-304 as the clad material. 
e Pounds per assembly, Assumption 3.4. 
Table 4. Non-actinide Composition of UO2 
Element Concentration 
(ppm) Element Concentration 
(ppm) Element Concentration 
(ppm) 
Li 1.0 Mn 1.7 V 3.0 
B 1.0 Fe 18.0 Cr 4.0 
C 89.4 Co 1.0 Bi 0.4 
N 25.0 Ni 24.0 Pb 1.0 
F 10.7 Cu 1.0 Ti 1.0 
Na 15.0 Zn 40.3 Ca 2.0 
Mg 2.0 Mo 10.0 W 2.0 
Al 16.7 Ag 0.1 Cl 5.3 
Si 12.1 Cd 25.0 Sn 4.0 
P 35.0 In 2.0 - - 
Source: Ludwig and Renier, Table 5.4 [DIRS 146398].

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Table 5. Chemical Composition for Hardware Materials 
Element Wt% Range Value Used 
Chemical Composition for Stainless Steel 304La 
C 0.03 (max) 0.03 
Mn 2.00 (max) 2.00 
Si 0.75 (max) 0.75 
Cr 18.00-20.00 19.00 
Ni 8.00-12.00 11.92 
Co - 0.08 
P 0.045 (max) 0.045 
S 0.03 (max) 0.03 
N 0.1 (max) 0.1 
Fe Balance 66.045 
Chemical Composition for Stainless Steel 304a 
C 0.08 (max) 0.08 
Mn 2.00 (max) 2.00 
Si 1.00 (max) 0.75 
Cr 18.00-20.00 19.00 
Ni 8.00-10.50 10.42 
Co - 0.08 
P 0.045 (max) 0.045 
S 0.03 (max) 0.03 
N 0.1 (max) 0.1 
Fe Balance 67.495 
Chemical Composition for Stainless Steel 302e 
C 0.15 0.15 
Mn 2.00 2.00 
Si 0.75 0.75 
Cr 17.00-19.00 18.00 
Ni 8.00-10.00 9.92 
Co - 0.08 
P 0.045 0.045 
S 0.03 0.03 
N 0.10 (max) 0.1 
Fe Balance 68.925 
Chemical Composition for Stainless Steel CF3Mb 
C 0.03 (max) 0.03 
Mn 1.50 (max) 1.50 
Si 2.00 (max) 2.00 
Cr 17.00-21.00 19.00 
Ni 8.00-12.00 11.92 
Co - 0.08 
Mo 2.00-3.00 2.50 
Fe Balance 62.97

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Title: PWR Source Term Generation and Evaluation 
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Table 5. Chemical Composition for Hardware Materials (Continued) 
Element Wt% Range Value Used 
Chemical Composition for Inconel-718c 
Ni 50.00-55.00 54.00 
Cr 17.00-21.00 19.00 
Fe Balance 14.934 
Nb/Ta 4.75-5.50 5.5 
Mo 2.80-3.30 3.05 
Ti 0.65-1.15 0.90 
Al 0.20-0.80 0.50 
Co 1.00 (max) 1.00 
Mn 0.35 (max) 0.35 
Si 0.35 (max) 0.35 
Cu 0.30 (max) 0.30 
C 0.08 (max) 0.08 
S 0.015 (max) 0.015 
P 0.015 (max) 0.015 
B 0.006 (max) 0.006 
Chemical Composition for Zircaloy-4d 
O 0.09-0.16 0.12 
Cr 0.07-0.13 0.10 
Fe+Cr 0.28-0.37 0.20 (Fe) 
Sn 1.20-1.70 1.70 
Zr Balance 97.88 
NOTE: a ASME 2001, SEC II A SA-240, Table 1 [DIRS 158115]. 
b ASM 1980, p. 95 [DIRS 104317]. 
c Inco Alloys International 1988, p. 11 [DIRS 130835]. 
d ASTM B 811-90 1991, Table 2 [DIRS 131753]. 
e ASTM A 240/A 240M-97a 1997, Table 1 [DIRS 102769]. 
5.3.2 Input for Crud Calculations 
In addition to the source terms for an assembly based on the irradiated assembly, it is also 
necessary to estimate the radiation source due to the activated corrosion products from the 
coolant deposited on the surfaces of the assembly (crud). These surfaces include all the areas of 
the assembly exposed to the flow of coolant. A bounding estimate of the PWR assembly surface 
area is based on a South Texas assembly (Assumption 3.5), which has a longer length, 264 fuel 
rods, and 25 guide or instrumentation tubes. The fuel rods for this assembly have a 0.374-inch 
(0.95-cm) outer diameter (OD) and a length of 176.642 inches (448.67 cm) (DOE 1988, 
p. 2A-363 [DIRS 100979]). Both the inner and outer surface areas of the guide and instrument 
tubes are included in the estimation of the surface area of the assembly. The tube OD is taken to 
be the pitch of the fuel pins for a conservative estimate and is 0.496 inches (1.2598 cm) 
(DOE 1988, p. 2A-361 [DIRS 100979]). The cladding thickness is used to determine the inside 
diameter and surface area and is 0.0225 inches (0.05715 cm) (DOE 1988, p. 2A-363 
[DIRS 100979]). The overall assembly length is 199 inches (505.46 cm) (DOE 1988, p. 2A-361 
[DIRS 100979]). In addition to the calculation of a bounding crud source based on the South 
Texas assembly parameters, a source for a regular B&W Mark B assembly is also calculated.

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A radionuclide activity density (Ci/cm2) is required to calculate the crud source. Two estimates 
for the radionuclide activity density are used in this calculation. The first estimate for the 
activity density is provided by the NRC NUREG-1567 (NRC 2000, Table 9.2 [DIRS 149756]), 
and has a value 140 Ci/cm2, which is entirely due to 60Co. The second estimate of crud activity 
density is provided by Jones 1992 [DIRS 146405]. This estimate has activities for eight 
radionuclides and is included in this calculation for information purposes only. The data from 
NRC 2000 [DIRS 149756] and Jones 1992 [DIRS 146405] are summarized in Table 6. 
Although the data in Jones 1992 [DIRS 146405] contain activities from multiple radioactive 
isotopes, it is recommended that the NRC value be used for crud activity. The reason is that the 
60Co activity from NRC is nearly three times the 60Co activity from Jones 1992 [DIRS 146405]. 
Emitting two very energetic photons and some beta particles, 60Co is the most dominant isotope 
for crud. Since other radionuclides in Table 6 either have shorter half-lives or emit much lower 
intensity radiation, they become insignificant by the time the SNF arrives the potential 
repository. 
Table 6. Radionuclide Activity Densities Used in Crud Source Calculation 
Radionuclide Activity Density (Ci/cm2) 
at Discharge Half Lifea Reference 
60C0 1.40x10-4 5.27 years NRC 2000, Table 9.2 [DIRS 149756] 
51Cr 1.89x10-4 27.70 days 
54Mn 7.40x10-5 312.10 days 
55Fe 5.90x10-3 2.73 years 
58Co 4.03x10-4 70.88 days 
59Fe 7.60x10-5 44.51 days 
60Co 5.10x10-5 5.27 years 
63Ni 2.00x10-6 100.00 years 
95Zr 1.90x10-5 64.02 days 
Jones 1992, Table 1 [DIRS 146405] 
NOTE: a Parrington et.al. 1996, pp. 24-28 [DIRS 103896]. 
5.4 SAS2H INPUT PARAMETER CALCULATION 
This section describes the calculation of the required input for SAS2H. The SAS2H sequence 
calculates source terms for the four axial regions: bottom end fitting, active fuel, plenum, and top 
end fitting. Every calculation requires the input of assembly parameters, burnup history, decay 
time steps, the pin cell description (path A), and the larger unit cell description for the whole 
assembly (path B). The path A input is presented in Section 5.4.1. Section 5.4.2 describes the 
calculation of uranium isotopic composition, density, and length for the active fuel region. The 
calculation of the path B representation is provided in Section 5.4.3. Section 5.4.4 provides the 
masses of the light elements used in SAS2H source calculation of the activation products. 
Section 5.4.5 calculates the SAS2H input data for moderator temperature and density and boron 
concentration. Fuel burnup and decay calculations are provided in Section 5.4.6.

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5.4.1 Input for the Path A Calculation in SAS2H 
The first information in the SAS2H input files specifies the type of calculation and the cross 
section library to be used. The latticecell type of calculation and the 44groupndf5 cross 
section library are used. Because no dose calculation is performed in this calculation, the 
parameters for the shipping cask skipcellwt and skipshipdata are specified. SAS2H then 
uses this information to generate an infinite lattice of unit pin cells and calculate cell-weighted 
cross sections. These cross sections are then applied to the assembly described by the path B 
representation. 
Figure 1 presents the path A unit pin cell representation for SAS2H and Table 7 presents the 
input parameters for cell calculations. 
fuel pin 
fuel cell moderator 
cladding 
Figure 1. Unit Pin Cell Representation for Path A 
Table 7. SAS2H Input for the Path A Calculation 
Variable Name Value Used 
Lattice type Square pitch 
Pitch 1.44272 cm 
Fuel OD 0.93624 cm 
Mfuel 1 
Mmod 3 
Clad OD 1.0922 cm 
Mclad 2 
Clad ID 0.95758 cm 
Mgap 0

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5.4.2 Fuel Uranium Isotopic Composition, Density, and Calculated Length 
The isotopic composition of uranium for commercially available enriched uranium is determined 
by the given initial 235U enrichment and the following formulae (Bowman et.al. 1995, p. 20 
[DIRS 123796]): 
batch fuel associated the of enrichment U U wt _ _ _ _ _ 
235 235 % = 
0837 . 1 235 234 ) % ( * 007731 . 0 % U wt U wt = 
) % ( * 0046 . 0 % 235 236 U wt U wt = 
) % % % ( 100 % 236 235 234 238 U wt U wt U wt U wt + + - = 
The values for initial uranium isotope composition, presented in Table 8, are calculated in 
Attachment I. 
Table 8. Initial Uranium Isotope Compositiona 
*.cut Files 
E Code 
235U (wt%) 236U (wt%) 234U (wt%) 238U (wt%) 
E12 0.711 0.00327 0.00534 99.28039 
E11 1.0 0.00460 0.00773 98.98767 
E10 1.5 0.00690 0.01200 98.48110 
E9 2.0 0.00920 0.01639 97.97441 
E8 2.5 0.01150 0.02087 97.46763 
E7 3.0 0.01380 0.02543 96.96077 
E6 3.5 0.01610 0.03005 96.45385 
E5 4.0 0.01840 0.03473 95.94687 
E4 4.2 0.01932 0.03661 95.74407 
E3 4.5 0.02070 0.03946 95.43984 
E2 5.0 0.02300 0.04423 94.93277 
E1 5.5 0.02530 0.04904 94.42566 
NOTE: a Only enrichment 1.5 wt% through 4.0 wt% are used for the SS clad calculations. 
A smeared fuel density is used in SAS2H. This is a common approach because fuel pellets 
expand and fill the gap during and after reactor operation. The smeared density is calculated 
from the following equation: 
( ) . .. 
. 
. .. 
. 
. = . 2 
2 
l theoretica smeared diameter inside clad 
diameter pellet * * density l theoretica %

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With a UO2 density of 10.96 g/cm3 (ORNL 1997, p. M8.2.3 [DIRS 135808]) and the pellet and 
clad inside diameters from Table 2, the smeared fuel density is: 
3 2
2 
3 953 . 9 
95758 . 0 
93624 . 0 * ) 96 . 10 ( * ) 95 . 0 ( 
cm
g 
cm
g 
smeared = . .. 
. 
. .. 
. 
= . 
A smeared fuel density of 9.96 g/cm3 is used in SAS2H. With the initial heavy metal loadings of 
464 kg, 475 kg, and 550 kg respectively for the waste stream assembly, the SS clad assembly, 
and the South Texas assembly, the active fuel lengths of 369.699 cm, 378.463 cm, and 
438.221 cm are obtained (see Attachment I). 
5.4.3 Input for the Path B Calculation 
The larger representation of the assembly used in the path B calculation by SAS2H is shown in 
Figure 2. Four regions are used in describing this larger unit cell. The four regions are 
concentric rings, similar to the unit pin cell representation in path A. The inner region is the 
moderator inside the guide tube, which is surrounded by the guide tube itself (region 2). The 
third region is the moderator in the guide tube cell surrounding the outside of the guide tube. 
The last region represents the homogenized fuel, cladding, and moderator of the assembly. 
Figure 2. Larger Unit Cell Representation for Path B 
The first radius, r1, corresponds to the inner radius of the guide tube (1.26492/2 = 0.63246 cm). 
The second radius, r2, corresponds to the outer radius of the guide tube (1.3462/2 = 0.6731 cm). 
The third radius, r3, corresponds to an area equivalent to rod pitch squared. Thus, 
cm 814 . 0 44272 . 1 pitch r 
2 2 
3 = 
p 
= 
p 
= 
r3-outside of guide tube 
cell moderator 
r4-outside of homogenized fuel 
and moderator region 
r2-outside of guide tube 
r1-inside of guide tube

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The fourth radius is calculated to preserve the guide tube-to-fuel volume ratio. The material for 
the fourth region is defined as mixture 500, which is the homogenized fuel, cladding and 
moderator determined from the path A calculation by SAS2H. Thus, the fourth radius is 
determined by taking a ratio of the number of available positions for fuel pins in the assembly to 
the number of positions used by the guide tubes and instrumentation tubes. This ratio is set equal 
to the ratio of the areas of the intended fuel region and the moderator (i.e., the guide tube pin 
cell). This allocates the number of fuel pins equally to each guide tube, and then sets the total 
volume of the assembly cell to be equal to the volume of the number of pin cells per guide tube. 
The instrument tube is taken to be equivalent to a guide tube for the path B calculation. This 
approach preserves the guide tube to fuel ratio and provides a unit cell that is representative of a 
core average composition. Therefore, the r4 radius is derived according to the following 
equations: 
r1 through r4 are shown in Table 9 with the mixtures used in each radius. Table 10 lists the rest 
of the input for the fuel assembly required by SAS2H. 
Table 9. Dimensions of the Larger Unit Cell for Path B 
Variable Name Value Used Comment 
Mixes 3 Material No. for the moderator 
Radius 0.63246 cm, region 1 
Mixes 2 Material No. for the Zircaloy-4 
Radius 0.67310 cm, region 2 
Mixes 3 Material No. for the moderator 
Radius 0.814 cm, region 3 
Mixes 500 Special material No. for fuel in the larger unit cell 
Radius 2.961 cm, region 4 
cm 961 . 2 
17
15 * 15 * 814 . 0 * 
: Yielding 
* as written be can which , 
2 2 
3 4 
2
3 
2
4 2
3
2
4 
2
3
2
4 
= = = 
= = = 
N
N r 
N
N r r r r
r r
N
N 
tubes guide 
positions 
tubes guide 
positions 
tubes guide 
positions
r 
p
p

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Table 10. Input for Fuel Assembly in SAS2H Calculations 
Variable Name Value Used 
Npin/assm 208 pins per assembly 
Fuelngth 360.172a 
Ncycles 1 cycle 
Nlib/cycb See Table 12 
Lightel 33 
Printlevel 5 
Inplevel 2 
Numholes 17 
Numinstr 1 
Mxtube 2 
Ortube 0.6731 cm 
Srtube 0.63246 cm 
Asmpitch 21.6814 cm 
Numztotal 4 
Mxrepeats 1 
Mixmod 3 
Facmesh 1.0 
NOTE: a See Section 5.4.2 for the calculation of the fuel lengths to account for the 
different IHMLs. 
b Number of libraries made per cycle. 
5.4.4 Light Element Mass Calculations 
The masses of the light elements for each axial fuel region are calculated in Attachment III and 
are reported in Table 11. The light element masses are determined by multiplying the weight of 
the hardware by the wt%s of the elements that make up the hardware and then adjusting by 
scaling factors to account for hardware's location in the reactor. For the active fuel region, the 
impurities in the fuel are also included. SAS2H is then used to simulate the irradiation of the 
fuel and the light elements and to decay the radiation source.

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Table 11. Light Element Masses per Assembly (kg) 
Region: Top 
(SF: 0.15) 
Bottom 
(SF: 0.30) 
Fuel 
(SF: 1) 
Plenum 
(SF: 0.30) 
Element Waste Stream Waste Stream Waste Stream South Texas Steel Clad Waste Stream Steel Clad 
Ag - - 0.0000 0.0001 0.0000 - - 
Al 0.0014 0.0020 0.0324 0.0337 0.0324 0.0016 0.0016 
B 0.0000 0.0000 0.0008 0.0008 0.0008 0.0000 0.0000 
Bi - - 0.0002 0.0002 0.0002 - - 
C 0.0006 0.0010 0.0464 0.0531 0.1567 0.0003 0.0030 
Ca - - 0.0010 0.0011 0.0010 - - 
Cd - - 0.0119 0.0138 0.0119 - - 
Cl - - 0.0025 0.0029 0.0025 - - 
Co 0.0038 0.0059 0.0495 0.0496 0.1598 0.0031 0.0059 
Cr 0.3067 0.5393 1.0480 1.0764 27.1279 0.0632 0.7187 
Cu 0.0008 0.0012 0.0152 0.0153 0.0152 0.0009 0.0009 
F - - 0.0051 0.0059 0.0051 - - 
Fe 0.8894 1.5998 0.9706 1.0282 93.7937 0.0563 2.3893 
In - - 0.0010 0.0011 0.0010 - - 
Li - - 0.0005 0.0006 0.0005 - - 
Mg - - 0.0010 0.0011 0.0010 - - 
Mn 0.0215 0.0381 0.0180 0.0181 2.7753 0.0012 0.0705 
Mo 0.0397 0.0731 0.1542 0.1550 0.1542 0.0095 0.0095 
N 0.0001 0.0000 0.0119 0.0138 0.1497 0.0000 0.0035 
Na - - 0.0071 0.0083 0.0071 - - 
Nb 0.0149 0.0215 0.2695 0.2695 0.2695 0.0172 0.0172 
Ni 0.3059 0.5024 2.6574 2.6592 17.0229 0.1690 0.5301 
O 0.0000 0.0001 64.9109 75.1719 64.7735 0.0035 0.0000 
P 0.0001 0.0001 0.0173 0.0200 0.0794 0.0000 0.0061 
Pb - - 0.0005 0.0006 0.0005 - - 
S 0.0001 0.0001 0.0007 0.0007 0.0421 0.0000 0.0011 
Si 0.0268 0.0503 0.0229 0.0238 1.0569 0.0011 0.0271 
Sn 0.0000 0.0008 1.9589 2.4374 0.0128 0.0489 0.0000 
Ti 0.0024 0.0035 0.0446 0.0447 0.0446 0.0028 0.0028 
V - - 0.0014 0.0017 0.0014 - - 
W - - 0.0010 0.0011 0.0010 - - 
Zn - - 0.0191 0.0222 0.0191 - - 
Zr 0.0000 0.0440 112.6799 140.2127 0.6264 2.8164 0.0000

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5.4.5 Assembly Operating Parameters 
To specify the reactor moderator condition used in the pin cell calculations, the moderator 
temperature and density and the boron concentration are required. 
The moderator temperature is determined from the average core exit temperature, 612F, and the 
average moderator temperature rise across the core, 59.4F, (see Table 2) as follows: 
K F F F 9 . 578 3 . 582 
2
4 . 59 612 .  = .. 
. 
.. 
.  
-  
The density of the moderator for this temperature is then determined from steam tables by linear 
interpolation. Using the values corresponding to steam temperatures of 580F and 590F at a 
steam pressure of 2200 psia, (see Table 2) the specific volume is: 
( ) 
lbm 
ft 022446 . 0 4 . 582 590 * 
580 590 
02235 . 0 02275 . 0 02275 . 0 
3 
= - .. 
. 
.. 
. 
-
- 
- 
Converting this to density yields: 
3 3 3 cm
g 7136 . 0 
ft 
lbm 551 . 44 
lbm 
ft 022446 . 0 
1 = = 
If more than one library per cycle is required in SAS2H calculations, the boron concentration is 
automatically changed during the passes of a cycle and is assumed to vary linearly from 1.9 to 
0.1 times its average (input) density during the time interval of the cycle (ORNL 1997, 
p. S2.2.10 [DIRS 135808]). Therefore, the required input average boron concentration is 
calculated by dividing the beginning of cycle value provided in Table 2 by 1.9, 
e.g., 1050 ppm/1.9 = 552.6 ppm. 
5.4.6 Power History Input 
Also required by SAS2H is the operational history of the assembly in the reactor. 
Table 12 presents the values required in Block 9 of SAS2H describing the assembly's power 
history. Since the histories can be very complicated, this calculation uses the simple approach of 
one cycle and new libraries at least every 100 days. The assemblies are irradiated at a power of 
14.5085 MW (2568 MWt/ 177 assemblies in a core). These parameters are calculated in 
Attachment II. 
5.4.7 ORIGEN-S Input 
The inputs for ORIGEN-S are the decay time steps shown in Table 13. Other inputs for 
ORIGEN-S are the specification of information tables to be printed, and how the gamma sources 
are generated. The gamma spectra can be calculated from the light elements, fission products 
and actinides of an assembly, or just from the light elements. For the hardware regions, only the 
light elements are used to generate the gamma source. In this calculation, the tables of curies 
and watts for each isotope are printed, as are the neutron and gamma spectra.

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Table 12. SAS2H Input Data for Assembly Depletion/Decay ParametersX 
*.cut Files 
B Code 
Final Burnup 
(GWd/MTU) 
Effective 
Full Power Days 
U Mass 
(kg /assembly) 
Number of Libraries 
per Cycle 
B1 0.001 0.03274 475 1 
B1 0.001 0.03791 550 1 
B2 0.01 0.3274 475 1 
B2 0.01 0.3791 550 1 
B3 0.1 3.274 475 1 
B3 0.1 3.791 550 1 
B4 1 32.739 475 1 
B4 1 37.909 550 1 
B5 10 327.39 475 4 
B5 10 379.09 550 4 
B6 20 654.79 475 7 
B6 20 758.18 550 8 
B7 30 982.18 475 10 
B7 30 1137.26 550 12 
B8 40 1309.58 475 14 
B8 40 1516.35 550 16 
B9 48.086 1574.31 475 16 
B9 48.086 1822.88 550 19 
B10 50 1636.97 475 17 
B10 50 1895.44 550 19 
B11 60 1964.37 475 20 
B11 60 2274.53 550 23 
B12 70 2291.76 475 23 
B12 70 2653.62 550 27 
B13 75 2455.46 475 25 
B13 75 2843.16 550 29 
B14 80 2619.15 475 27 
B15 85 2782.85 475 28

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Table 13. Time Steps Used for Decay Calculation 
Decay time steps (years) 
1 2 3 4 5 6 7 8 9 10 
11 12 13 14 15 16 17 18 19 20 
21 22 23 24 25 26 27 28 29 30 
31 32 33 34 35 36 37 38 39 40 
41 42 43 44 45 46 47 48 49 50 
51 52 53 54 55 56 57 58 59 60 
61 62 63 64 65 66 67 68 69 70 
71 72 73 74 75 76 77 78 79 80 
81 82 83 84 85 86 87 88 89 90 
91 92 93 94 95 96 97 98 99 100 
110 120 130 140 150 160 170 180 190 200 
250 300 350 400 450 500 550 600 650 700 
750 800 850 900 950 1000 1500 2000 2500 3000 
3500 4000 4500 5000 5500 6000 6500 7000 7500 8000 
8500 9000 9500 1.0x104 1.5x104 2.0x104 2.5x104 3.0x104 3.5x104 4.0x104 
4.5x104 5.0x104 5.5x104 6.0x104 6.5x104 7.0x104 7.5x104 8.0x104 8.5x104 9.0x104 
9.5x104 1.0x105 1.5x105 2.0x105 2.5x105 3.0x105 3.5x105 4.0x105 4.5x105 5.0x105 
5.5x105 6.0x105 6.5x105 7.0x105 7.5x105 8.0x105 8.5x105 9.0x105 9.505 1.0x106 
5.5 RADIONUCLIDE INVENTORIES FOR PERFORMANCE ASSESSMENT 
Several separate SAS2H/ORIGEN-S cases are provided in this calculation to determine average 
and maximum radionuclide inventories for specific years. The average and maximum PWR 
assemblies are derived from the results of CRWMS M&O 2000 [DIRS 138239] and listed 
below. The characteristics of the average PWR assembly are estimated based on the average 
PWR assembly of Case A with full inventory (83,800 MTU) in CRWMS M&O 2000, Table 5 
[DIRS 138239]. For this case, the characteristics of the average PWR assembly are 3.75wt%, 
41.70 GWd/MTU, and 25.3 years old with an initial uranium loading of 434 kg. A comparison 
study, based on the data base in DOE 1992, Appendix 1C [DIRS 102812], indicates that per 
initial MTU loading the average PWR assembly selected in this calculation is more conservative 
than any average PWR assembly for the scenarios in CRWMS M&O 2000, Table 5 
[DIRS 138239] (See Attachment IV). The characteristics of the maximum PWR assembly are 
also derived from CRWMS M&O 2000, Attachment III, preblend files [DIRS 138239]. From 
these files the following maximum PWR SNF characteristics are noted: initial uranium loading 
of 477 kg, burnup of 69 GWd/MTU, initial uranium enrichment of 5.0 wt%, and cooling time of 
5 years. It should be noted that there is no single assembly in the waste stream with these 
combined characteristics. Rather, these are the maximum characteristics of each parameter in 
the entire waste stream. Compared to these SNF characteristics, the maximum PWR assembly 
selected here is more conservative because the effect of the higher burnup (80 GWd/MTU versus 
69 GWd/MTU) exceed that of the two kilogram (475 versus 477 kg) difference in the initial 
uranium loading.

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To provide margin for conservatism and sufficiently cover future projected commercial high 
burnup fuel, the maximum burnup of 69 GWd/MTU based on the Waste Packages and Source 
Terms for the Commercial 1999 Design Basis Waste Streams (CRWMS M&O 2000, 
Attachment III, preblend files [DIRS 138239]) was increased to 80 GWd/MTU as the bounding 
burnup value. This selection is consistent with the value used in Licensing Position-009, Waste 
Stream Parameters (Williams 2003, Attachment, p. 1 [DIRS 166132]). The characteristics of 
the average and maximum PWR SNF assemblies used in this calculation are: 
 Average PWR assembly: 4.0%, 48 GWd/MTU, 25 years cooling time 
 Maximum PWR assembly: 5.0%, 80 GWd/MTU, 5 years cooling time 
The radionuclide inventories (curies) for both average and maximum PWR assemblies are 
provided in Attachment IX for different cooling times. 
5.6 CRUD SOURCE TERM 
The activity of the crud on the surface of the PWR assemblies at time zero is determined by 
multiplying the calculated assembly surface area by the 60Co or other corrosion product activity 
per unit area of surface. A time dependent crud activity is derived using the following equation: 
where t is the radionuclide half-life and t is the decay time in years. 
A bounding estimate of the PWR assembly surface area is 449,003 cm2, based on a South Texas 
assembly. This value and the crud source term are calculated in Attachment VI. 
2 / 1 t 
2 ln t 
e ) 0 ( N ) t ( N 
- 
=

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6. RESULTS 
The section presents the results of this calculation. The outputs of this calculation are reasonable 
compared to the inputs, and the results are suitable for the intended use. The uncertainties are 
taken into account by consistently using the most conservative approach; the calculations, 
therefore, yield a conservatively bounding set of results. 
6.1 EFFECTS OF FUEL IMPURITIES 
The effects of impurities in the fuel are examined using a waste stream assembly with a 4.2 wt% 
235U initial enrichment. Negligible differences in radiation spectra and thermal powers have 
been observed. However, the results for 36Cl and 14C are summarized in this section. Attention 
is given to 36Cl and 14C (with half-lives of 3.01x105 and 5715 years (Parrington et.al. 1996, p. 19 
and p. 22 [DIRS 103896]), respectively) because of their very high solubility-limits in aqueous 
concentrations (CRWMS M&O 1995, p. 6-7 [DIRS 100198]). 36Cl and 14C activities at 
discharge as function of burnup are presented in Table 14. Two mass concentrations for the 
chlorine impurity have been used in these calculations: 5.3 ppm (a measured concentration from 
Ludwig and Renier, Table 5.4 [DIRS 146398]) and 10 ppm. 
Figure 3 presents a plot of 36Cl and 14C activity per ppm versus burnup. This conclusion can be 
used to estimate the resulting radioactivity from activation of a certain chlorine impurity 
concentration. 
Table 14. 36Cl and 14C Activities for the Waste Stream Assembly 
with 4.2 wt% 235U Enrichment at Time of Discharge 
36Cl Activity 
(Ci/assembly) 
36Cl Activity 
(Ci/assembly)/Initial 
Impurity (ppm) Burnup 
(GWd/MTU) 
5.3 ppm 10 ppm 5.3 ppm 10 ppm 
14C Activity 
(Ci/assembly) 
14C Activity 
(Ci/assembly)/ 
Initial Impurity 
(ppm) 
1 1.24x10-4 2.35x10-4 2.34x10-5 2.35x10-5 5.67x10-3 6.34x10-5 
10 1.24x10-3 2.33x10-3 2.34x10-4 2.33x10-4 5.69x10-2 6.36x10-4 
20 2.51x10-3 4.74x10-3 4.74x10-4 4.74x10-4 1.17x10-1 1.31x10-3 
30 3.87x10-3 7.32x10-3 7.30x10-4 7.32x10-4 1.87x10-1 2.09x10-3 
40 5.32x10-3 1.01x10-2 1.00x10-3 1.01x10-3 2.54x10-1 2.84x10-3 
50 6.89x10-3 1.31x10-2 1.30x10-3 1.31x10-3 3.33x10-1 3.72x10-3 
60 8.55x10-3 1.62x10-2 1.61x10-3 1.62x10-3 4.20x10-1 4.70x10-3 
70 1.03x10-2 1.95x10-2 1.94x10-3 1.95x10-3 5.13x10-1 5.74x10-3 
75 1.11x10-2 2.12x10-2 2.09x10-3 2.12x10-3 5.62x10-1 6.29x10-3 
80 1.19x10-2 - 2.25x10-3 - 6.11x10-1 6.83x10-3

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1.E-05 
1.E-04 
1.E-03 
1.E-02 
0 10 20 30 40 50 60 70 80 90 
Burnup (GWd/MTU) 
Activity per Unit Impurity (Ci/ppm) 
chlorine 36 (5.3 ppm) 
chlorine 36 (10 ppm) 
carbon 14 
Figure 3. 36Cl and 14C Activity per Unit Impurity at Discharge as a Function of Burnup 
for a Waste Stream Assembly with 4.2 wt% 235U Enrichment 
6.2 WASTE STREAM, SS CLAD, AND SOUTH TEXAS SOURCE TERMS 
Due to large amount of information generated by this calculation, the results are provided as 
electronic files on four CDs (Attachment X). However, a summary of the results are presented 
also in Section 6 and Attachments IV, VI, VII, and IX. 
Attachment XI presents information to be used in License Application  Safety Analysis Report, 
Section 1.5.1. 
6.3 STUDY LIMITATIONS 
Data evaluated in this calculation are the assembly average source terms and it will be left to the 
subsequent analysis to account for any axial distribution of the radionuclide inventories and 
consequently radiation and heat source terms. 
6.4 CONCLUSIONS 
The objectives of this calculation are to generate PWR SNF assembly source terms that bound 
selected groupings of PWR assemblies, with regard to assembly burnup and cooling time. 
Bounding PWR SNF assembly source terms to be used for evaluation of shielding requirements 
or other follow-on analysis have been calculated in this study. The results of this calculation 
may also be used as input for Preclosure Safety Analysis and Total System Performance 
Assessment analyses.

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page 30 of 33 
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Term Generation and Evaluation. 000-00C-MGR0-00100-000-00A. Las Vegas, Nevada: 
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CRWMS M&O 1997. PWR Assembly Source Terms for Waste Package Design. BBA000000- 
01717-0200-00023 REV 00. Las Vegas, Nevada: CRWMS M&O. ACC: 
MOL.19970708.0431. [DIRS 136439] 
CRWMS M&O 1997. Software Code: SCALE. V4.3. HP. 30011 V4.3. [DIRS 154059] 
CRWMS M&O 1997. Software Qualification Report for THE SCALE Modular Code System 
Version 4.3. CSCI: 30011 V4.3. DI: 30011-2002, Rev. 01. Las Vegas, Nevada: CRWMS 
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Waste Packages. BBAC00000-01717-0210-00001 REV 00. Las Vegas, Nevada: CRWMS 
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CRWMS M&O 1999. PWR Source Term Generation and Evaluation. BBAC00000-01717- 
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MOL.20010822.0085; MOL.20010822.0086; MOL.20010822.0087. [DIRS 153872] 
CRWMS M&O 2000. Waste Packages and Source Terms for the Commercial 1999 Design 
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DOE (U.S. Department of Energy) 1992. Characteristics of Potential Repository Wastes. 
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Other Radioactive Wastes Which May Require Long-Term Isolation. DOE/RW-0184. 
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DOE (U.S. Department of Energy) 2004. Quality Assurance Requirements and Description. 
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Radioactive Waste Management. ACC: DOC.20040331.0004. [DIRS 168669] 
Framatome Cogema Fuels. 1999. Operational Data - B&W NSS. 51-5004349-01. Lynchburg, 
Virginia: Framatome Cogema Fuels. ACC: MOL.19990610.0201. [DIRS 146419]

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Hermann, O.W.; Parks, C.V.; and Renier, J.P. 1994. Technical Support for a Proposed Decay 
Heat Guide Using SAS2H/ORIGEN-S Data. NUREG/CR-5625. Washington, D.C.: U.S. 
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International. TIC: 239397. [DIRS 130835] 
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California: Robert H. Jones, P.E., Consultant. ACC: HQX.19920825.0007. [DIRS 146405] 
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of Energy, Office of Civilian Radioactive Waste Management. ACC: DOC.20040225.0007. 
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Models for the ORIGEN2 Computer Code. ORNL/TM-11018. Oak Ridge, Tennessee: Oak 
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Northwest Laboratory. ACC: NNA.19890926.0124. [DIRS 120506] 
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05/22/2001. [DIRS 155001] 
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[DIRS 155002] 
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Storage Facilities. NUREG-1567. Washington, D.C.: U.S. Nuclear Regulatory Commission. 
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Performing Standardized Computer Analyses for Licensing Evaluation. NUREG/CR-0200, Rev. 
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Isotopes, Chart of the Nuclides. 15th Edition. San Jose, California: General Electric Company 
and KAPL, Inc. TIC: 233705. [DIRS 103896] 
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Stream Parameters." Letter from N.H. Williams (BSC) to J.D. Ziegler (DOE/ORD), November 
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Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page 33 of 33 
8. ATTACHMENTS 
The ten attachments for this calculation are listed in Table 15. Attachments I to IX are included 
with this document. Attachment X consists of four compact discs, which content is listed in 
Attachment VIII. Two new worksheets PWR.bou.2.curies and PWR.bou.3.curies were 
added to the spreadsheet ATTACH_IX.XLS to include the new burnup value (80 GWd/MTU) 
for the maximum PWR assembly. 
Table 15. Attachments 
Description Attachment Number No. of Pages 
Fuel density and composition calculations I 1 
Burn history calculations II 2 
Light element mass calculations III 12 
Comparison of source terms per MTU of 4 average PWR SNF assemblies IV 1 
Listing of UNIX script files V 1 
Calculation of crud source VI 4 
36Cl and 14C calculations VII 1 
List of *.cut files on compact discs VIII 22 
Radionuclide inventories for Performance Assessment (all nuclides included) IX 10 
Electronic copies versions of *.cut files X 4 CDs 
Evolution in Time of Thermal Power and Total Radioactivity XI 1

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page I-1 of I-1 
Attachment I 
Determination of fuel compositions and burn histories 
Initial Heavy Metal 
Mass # of pins in assembly Pin length pellet outer radius 
464 208 360.172 0.46812 
475 
550 
KG UO2/Assembly densities (g/cc) cross sect. area (cm^2) volume needed (cm^3) density (g/cc) new fuel length (cm) 
527.27 10.22 143.1949164 52939.03 9.96 369.699 
539.77 10.47 54194.05 378.463 
625 12.12 62751.00 438.221 
Burn histories 
Burnup,GWd/MTU 
days for 464 assembly 
to achieve burnup 
Required 
libraries/cycle for 100 
day cycles 
days for 475 assembly 
to achieve burnup 
Required 
libraries/cycle for 100 
day cycles 
days for 550 assembly 
to achieve burnup 
Required 
libraries/cycle for 100 
day cycles 
0.001 0.03 0.0003 0.0327 0.0003 0.0379 0.0004 
0.01 0.32 0.0032 0.3274 0.0033 0.3791 0.0038 
0.1 3.20 0.0320 3.2739 0.0327 3.7909 0.0379 
1 31.98 0.3198 32.7394 0.3274 37.9088 0.3791 
10 319.81 3.1981 327.39 3.3 379.09 3.8 
20 639.63 6.4 654.79 6.5 758.18 7.6 
30 959.44 9.6 982.18 9.8 1137.26 11.4 
40 1279.25 12.8 1309.58 13.1 1516.35 15.2 
50 1599.06 16.0 1636.97 16.4 1895.44 19.0 
60 1918.88 19.2 1964.37 19.6 2274.53 22.7 
70 2238.69 22.4 2291.76 22.9 2653.62 26.5 
75 2398.59 24.0 2455.46 24.6 2843.16 28.4 
80 2558.50 25.6 2619.15 26.2 3032.70 30.3 
85 2718.41 27.2 2782.85 27.8 3222.25 32.2 
235 Enrichment 236 enrichment 234 enrichment 238 
0.711 0.00327 0.00534 99.28039 
1 0.00460 0.00773 98.98767 
1.5 0.00690 0.01200 98.48110 
2 0.00920 0.01639 97.97441 
2.5 0.01150 0.02087 97.46763 
3 0.01380 0.02543 96.96077 
3.5 0.01610 0.03005 96.45385 
4 0.01840 0.03473 95.94687 
4.2 0.01932 0.03661 95.74407 
4.5 0.02070 0.03946 95.43984 
5 0.02300 0.04423 94.93277 
5.5 0.02530 0.04904 94.42566 

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page II-1 of II-2 
Attachment II 
PWR Source Term Generation and Evaluation 
Final Burnup 
(GWd/MTU) 
Effective Full Power 
Days MW /assembly kg /assembly 
Number of libraries 
for 1 library every 
100 days 
#days covered by 
last library Nlib/cycle required 
0.001 0.03274 14.5085 475 0 0.03274 1 
0.001 0.03791 14.5085 550 0 0.03791 1 
0.01 0.3274 14.5085 475 0 0.32739 1 
0.01 0.3791 14.5085 550 0 0.37909 1 
0.1 3.274 14.5085 475 0 3.27394 1 
0.1 3.791 14.5085 550 0 3.79088 1 
1 32.739 14.5085 475 0 32.73943 1 
1 37.909 14.5085 550 0 37.90881 1 
10 319.81 14.5085 464 3 19.8 4 
10 327.39 14.5085 475 3 27.4 4 
10 379.09 14.5085 550 3 79.1 4 
20 639.63 14.5085 464 6 39.6 7 
20 654.79 14.5085 475 6 54.8 7 
20 758.18 14.5085 550 7 58.2 8 
30 959.44 14.5085 464 9 59.4 10 
30 982.18 14.5085 475 9 82.2 10 
30 1137.26 14.5085 550 11 37.3 12

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page II-2 of II-2 
Attachment II 
Final Burnup 
(GWd/MTU) 
Effective Full 
Power Days MW /assembly kg /assembly 
Number of 
libraries for 1 
library every 100 
days 
#days covered by 
last library Nlib/cycle required 
40 1279.25 14.5085 464 12 79.3 13 
40 1309.58 14.5085 475 13 9.6 14 
40 1516.35 14.5085 550 15 16.4 16 
48.086 1537.85 14.5085 464 15 37.9 16 
48.086 1574.31 14.5085 475 15 74.3 16 
48.086 1822.88 14.5085 550 18 22.9 19 
50 1599.06 14.5085 464 15 99.1 16 
50 1636.97 14.5085 475 16 37.0 17 
50 1895.44 14.5085 550 18 95.4 19 
60 1918.88 14.5085 464 19 18.9 20 
60 1964.37 14.5085 475 19 64.4 20 
60 2274.53 14.5085 550 22 74.5 23 
70 2238.69 14.5085 464 22 38.7 23 
70 2291.76 14.5085 475 22 91.8 23 
70 2653.62 14.5085 550 26 53.6 27 
75 2398.59 14.5085 464 23 98.6 24 
75 2455.46 14.5085 475 24 55.5 25 
75 2843.16 14.5085 550 28 43.2 29 
80 2558.50 14.5085 464 25 58.5 26 
80 2619.15 14.5085 475 26 19.2 27 
80 3032.70 14.5085 550 30 32.7 31 
85 2718.41 14.5085 464 27 18.4 28 
85 2782.85 14.5085 475 27 82.9 28 
85 3222.25 14.5085 550 32 22.2 33

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page III-1 of III-12 
Attachment III - Worksheet "Data" 
Babcock and Wilcox Mark B fuel assembly Hardware 
Region Part Name kg/assembly Material 
top nozzle 7.48 SS CF3M ***Mass of oxygen to be added to fuel region light elements to acount for the oxygen in the fuel: 
spring retainer 0.91 SS CF3M KG U KG UO2 KG O 
Top hold down spring 1.8 Inconel-718 475 539.77 64.77 
upper end plug 0.06 SS 304 550 625 75.00 
upper nuts 0.51 SS 304L (KG U)/0.88 (KG UO2)- (KG U) 
bottom nozzle 8.16 SS CF3M 
Bottom bottom spacer 1.3 Inconel-718 
lower nuts 0.15 Zircaloy-4 
Fuel/plenum guide tubes 8 Zircaloy-4 
Fuel/plenum instrument tube 0.64 Zircaloy-4 *** Cladding mass is calculated on next worksheet 
Fuel/plenum incore spacers 4.9 Zircaloy-4 Inconel 718 used in calculation since many have this material for spacers 
Fuel grid supports 0.64 Zircaloy-4 
plenum plenum spacers 1.04 Inconel-718 
plenum springs 0.019 SS 302 
0.042 (lbs) 
RAW MATERIAL DATA: Updated 8/17 
Material: SS 304 SS304L Zircaloy-4 Inconel-718 SS CF3M ss302 
Element Range Used Range Used Range Used Element Range Used Element Range Used Element Range Used 
c 0.08 (max) 0.08 0.03 (max) 0.03 0 0 ni+co 50-55 54 c 0.03 0.03 c 0.15 0.15 
mn 2 (max) 2 2 (max) 2 0 0 cr 17-21 19 mn 1.5 1.5 mn 2 2 
p 0.045 (max) 0.045 0.045 (max) 0.045 0 0 fe bal 14.934 si 2 2 p 0.045 0.045 
s 0.03 (max) 0.03 0.03 (max) 0.03 0 0 co (max) 1 1 cr 17-21 19 s 0.03 0.03 
si 1.0 (max) 0.75 0.75 (max) 0.75 0 0 mo 2.8-3.3 3.05 ni 8.-12 11.92 si 0.75 0.75 
cr 18-20 19 18-20 19 0.07-0.13 0.1 w 0 0 mo 2.-3 2.5 cr 17-19 18 
ni 8-10.5 10.42 8.0-12.0 11.92 0 0 nb+ta 4.75-5.5 5.5 fe balance 62.97 ni 8.-10 9.92 
n 0.1 (max) 0.1 0.1 0.1 0 0 ti .65-1.15 0.9 99.92 mo 0 0 
fe Balance 67.495 Balance 66.045 0.18-0.24 0.2 al .2-.8 0.5 co 0.08 n 0.1 0.1 
o 0 0 0 0 0.09-0.16 0.12 c 0.08 0.08 cu 0 0 
sn 0 0 0 0 1.2-1.7 1.7 mn 0.35 0.35 fe balance 68.925 
zr 0 0 0 0 Balance 97.88 si 0.35 0.35 99.92 
99.92 99.92 100 b 0.006 0.006 
co - 0.08 - 0.08 cu 0.3 0.3 co 0.08 
Material: SS 304 SS304L Zircaloy-4 p 0.015 0.015 
s 0.015 0.015 
100 
REORGANIZED DATA BY ELEMENT: 
Material: SS 304 SS304L Zircaloy-4 Inconel-718 SS CF3M ss302 ***Here the assumption of a 0.08wt% Cobalt impurity in the steels. 
Element 
al 0 0 0 0.5 0 0 
b 0 0 0 0.006 0 0 
c 0.08 0.03 0 0.08 0.03 0.15 
co 0.08 0.08 0 1 0.08 0.08 
cr 19 19 0.1 19 19 18 
cu 0 0 0 0.3 0 0 
fe 67.495 66.045 0.2 14.934 62.97 68.925 
mn 2 2 0 0.35 1.5 2 
mo 0 0 0 3.05 2.5 0 
n 0.1 0.1 0 0 0 0.1 
nb+ta 0 0 0 5.5 0 0 
ni 10.42 11.92 0 54 11.92 9.92 
o 0 0 0.12 0 0 0 
p 0.045 0.045 0 0.015 0 0.045 
s 0.03 0.03 0 0.015 0 0.03 
si 0.75 0.75 0 0.35 2 0.75 
sn 0 0 1.7 0 0 0 
ti 0 0 0 0.9 0 0 
zr 0 0 97.88 0 0 0 
100 100 100 100 100 100

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page III-2 of III-12 
Attachment III  Worksheet impurities.test.cases 
PWR U mass (g) 475000 PWR mass (kg) 539.7727273 
PWR assembly volume (cc) 54194.05 
PWR 
Impurities atomic mass (g) ppm/U mass (kg) at dens 
Li 6.941 1 0.000475 7.6043E-07 
B 10.811 1 0.000475 4.8822E-07 
C 12.0107 89.4 0.042465 3.9287E-05 
N 14.00674 25 0.011875 9.4208E-06 
F 18.9984032 10.7 0.0050825 2.9727E-06 
Na 22.98977 15 0.007125 3.4438E-06 
Mg 24.305 2 0.00095 4.3433E-07 
Al 26.981538 16.7 0.0079325 3.2669E-06 
Si 28.0855 12.1 0.0057475 2.2740E-06 
P 30.973761 35 0.016625 5.9643E-06 
Cl 35.4527 5.3 0.0025175 7.8906E-07 
Ca 40.078 2 0.00095 2.6339E-07 
Ti 47.867 1 0.000475 1.1027E-07 
V 50.9415 3 0.001425 3.1084E-07 
Cr 51.9961 4 0.0019 4.0604E-07 
Mn 54.938049 1.7 0.0008075 1.6333E-07 
Fe 55.845 18 0.00855 1.7013E-06 
Co 58.9332 1 0.000475 8.9562E-08 
Ni 58.6934 24 0.0114 2.1583E-06 
Cu 63.546 1 0.000475 8.3060E-08 VF 
Zn 65.39 40.3 0.0191425 3.2529E-06 0.000035464 
Mo 95.94 10 0.00475 5.5015E-07 
Ag 107.8682 0.1 0.0000475 4.8932E-09 
Cd 112.411 25 0.011875 1.1739E-06 
In 114.818 2 0.00095 9.1940E-08 
Sn 118.71 4 0.0019 1.7785E-07 
W 183.84 2 0.00095 5.7421E-08 
Pb 207.2 1 0.000475 2.5474E-08 
Bi 208.98038 0.4 0.00019 1.0103E-08 
Total 0.1680075 
mass (g) at. Dens. 
cl 10 4.75 1.48879E-06

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page III-3 of III-12 
Attachment III - Worksheet impurities.test.cases 
Light Elements (PWR) 
From hardware Add impurities Zn mass (g) 19.1425 
element mass (kg) mass (kg) at mass (g) wt fr at dens 
al 0.0245 0.0324 Zn-64 63.929146 0.4751 1.5808E-06 
b 0.0003 0.0008 Zn-66 65.926036 0.28126 9.0748E-07 
c 0.0039 0.0464 Zn-67 66.927131 0.04196 1.3336E-07 
co 0.0490 0.0495 Zn-68 67.924847 0.19527 6.1150E-07 
cr 1.0461 1.0480 Zn-70 69.925325 0.00642 1.9529E-08 
cu 0.0147 0.0152 1.00001 3.2527E-06 
fe 0.9819 0.9904 Ag mass (g) 0.0475 
mn 0.0172 0.0180 at mass (g) wt fr 
mo 0.1495 0.1542 Ag-107 106.90509 0.51377 2.5366E-09 
n 0.0000 0.0119 Ag-109 108.904756 0.48623 2.3566E-09 
nb 0.2511 0.2511 1 4.8932E-09 
ni 2.6460 2.6574 In mass (g) 0.95 
o 0.1381 64.9081 at mass (g) wt fr 
p 0.0000 0.0166 In-113 112.904062 0.04228 3.9531E-09 
s 0.0000 0.0000 In-115 114.903879 0.95772 8.7987E-08 
si 0.0172 0.0229 1 9.1940E-08 
sn 1.6117 1.6136 Sn mass (g) 1.9 
ti 0.0441 0.0446 at mass (g) wt fr 
zr 113.0252 113.0252 Sn-112 111.90482 0.00914 1.7244E-09 
li 0.000475 Sn-114 113.902782 0.00624 1.1566E-09 
f 0.0050825 Sn-115 114.903347 0.00348 6.3942E-10 
na 0.007125 Sn-116 115.901745 0.14186 2.5841E-08 
mg 0.00095 Sn-117 116.902955 0.07563 1.3659E-08 
cl 0.0025175 Sn-118 117.901608 0.24055 4.3075E-08 
ca 0.00095 Sn-119 118.903311 0.08594 1.5260E-08 
v 0.001425 Sn-120 119.902198 0.32917 5.7961E-08 
zn 0.0191425 Sn-122 121.903441 0.04755 8.2353E-09 
ag 0.0000475 Sn-124 123.905274 0.06043 1.0297E-08 
cd 0.011875 0.99999 1.7785E-07 
in 0.00095 
w 0.00095 B mass (g) 0.475 
pb 0.000475 at mass (g) wt fr 
bi 0.00019 b-10 10.0129371 0.18431 9.71561E-08 
b-11 11.0093055 0.81569 3.91064E-07 
4.8822E-07 
Li mass (g) 0.475 
at mass (g) wt fr 
li-6 6.015122 0.065 5.70363E-08 
li-7 7.016004 0.935 7.03404E-07 
7.6044E-07

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page III-4 of III-12 
Attachment III - Worksheet South.Texas.impurities 
South Texas impurities and number densities 539.7727273 
PWR U mass (g) 550000 PWR mass (kg) 625 
PWR assembly volume (cc) 62751.00402 
PWR 
Impurities atomic mass (g) ppm/U mass (kg) at dens 
Li 6.941 1 0.00055 7.6043E-07 
B 10.811 1 0.00055 4.8822E-07 
C 12.0107 89.4 0.04917 3.9287E-05 
N 14.00674 25 0.01375 9.4208E-06 
F 18.9984032 10.7 0.005885 2.9727E-06 
Na 22.98977 15 0.00825 3.4438E-06 
Mg 24.305 2 0.0011 4.3433E-07 
Al 26.981538 16.7 0.009185 3.2669E-06 
Si 28.0855 12.1 0.006655 2.2740E-06 
P 30.973761 35 0.01925 5.9643E-06 
Cl 35.4527 5.3 0.002915 7.8906E-07 
Ca 40.078 2 0.0011 2.6339E-07 
Ti 47.867 1 0.00055 1.1027E-07 
V 50.9415 3 0.00165 3.1084E-07 
Cr 51.9961 4 0.0022 4.0604E-07 
Mn 54.938049 1.7 0.000935 1.6333E-07 
Fe 55.845 18 0.0099 1.7013E-06 VF 
Co 58.9332 1 0.00055 8.9562E-08 0.000035464 
Ni 58.6934 24 0.0132 2.1583E-06 
Cu 63.546 1 0.00055 8.3061E-08 
Zn 65.39 40.3 0.022165 3.2529E-06 
Mo 95.94 10 0.0055 5.5015E-07 
Ag 107.8682 0.1 0.000055 4.8932E-09 
Cd 112.411 25 0.01375 1.1739E-06 
In 114.818 2 0.0011 9.1940E-08 
Sn 118.71 4 0.0022 1.7785E-07 
W 183.84 2 0.0011 5.7421E-08 
Pb 207.2 1 0.00055 2.5474E-08 
Bi 208.98038 0.4 0.00022 1.0103E-08 
Total 0.194535 
mass (g) at. Dens. 
cl 10 5.5 1.72386E-06

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page III-5 of III-12 
Attachment III - Worksheet South.Texas.impurities 
Light Elements (PWR) 
From hardware Add impurities Zn mass (g) 22.165 
element mass (kg) mass (kg) at mass (g) wt fr at dens 
al 0.0245 0.0337 Zn-64 63.929146 0.4751 1.5808E-06 
b 0.0003 0.0008 Zn-66 65.926036 0.28126 9.0748E-07 
c 0.0039 0.0531 Zn-67 66.927131 0.04196 1.3336E-07 
co 0.0490 0.0496 Zn-68 67.924847 0.19527 6.1150E-07 
cr 1.0461 1.0483 Zn-70 69.925325 0.00642 1.9529E-08 
cu 0.0147 0.0153 1.00001 3.2527E-06 
fe 0.9819 0.9918 Ag mass (g) 0.055 
mn 0.0172 0.0181 at mass (g) wt fr 
mo 0.1495 0.1550 Ag-107 106.90509 0.51377 2.5366E-09 
n 0.0000 0.0138 Ag-109 108.904756 0.48623 2.3566E-09 
nb 0.2511 0.2511 1 4.8932E-09 
ni 2.6460 2.6592 In mass (g) 1.1 
o 0.1381 64.9081 at mass (g) wt fr 
p 0.0000 0.0193 In-113 112.904062 0.04228 3.9531E-09 
s 0.0000 0.0000 In-115 114.903879 0.95772 8.7987E-08 
si 0.0172 0.0238 1 9.1940E-08 
sn 1.6117 1.6139 Sn mass (g) 2.2 
ti 0.0441 0.0447 at mass (g) wt fr 
zr 113.0252 113.0252 Sn-112 111.90482 0.00914 1.7244E-09 
li 0.000475 Sn-114 113.902782 0.00624 1.1566E-09 
f 0.005885 Sn-115 114.903347 0.00348 6.3942E-10 
na 0.00825 Sn-116 115.901745 0.14186 2.5841E-08 
mg 0.0011 Sn-117 116.902955 0.07563 1.3659E-08 
cl 0.002915 Sn-118 117.901608 0.24055 4.3075E-08 
ca 0.0011 Sn-119 118.903311 0.08594 1.5260E-08 
v 0.00165 Sn-120 119.902198 0.32917 5.7961E-08 
zn 0.022165 Sn-122 121.903441 0.04755 8.2353E-09 
ag 0.000055 Sn-124 123.905274 0.06043 1.0297E-08 
cd 0.01375 0.99999 1.7785E-07 
in 0.0011 
w 0.0011 B mass (g) 0.55 
pb 0.00055 at mass (g) wt fr 
bi 0.00022 b-10 10.0129371 0.18431 9.7156E-08 
b-11 11.0093055 0.81569 3.9106E-07 
4.8822E-07 
Li mass (g) 0.55 
at mass (g) wt fr 
li-6 6.015122 0.065 5.7036E-08 
li-7 7.016004 0.935 7.034E-07 
7.6044E-07

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page III-6 of III-12 
Attachment III - Worksheet impurities 
For volumes and weights, see Attachment I 
PWR U mass (g) 475000 PWR mass (kg) 539.7727273 
South Texas U mass (g) 550000 South Texas mass (kg) 625 
PWR assembly volume (cc) 54194.05 
South Texas assembly volume (cc) 62751 
PWR South Texas 
Impurities 
atomic mass 
(g) ppm/U mass (kg) at dens mass (kg) at dens 
Li 6.941 1 0.000475 7.6043E-07 0.00055 7.6043E-07 
B 10.811 1 0.000475 4.8822E-07 0.00055 4.8822E-07 
C 12.0107 89.4 0.042465 3.9287E-05 0.04917 3.9287E-05 
N 14.00674 25 0.011875 9.4208E-06 0.01375 9.4208E-06 
F 18.9984032 10.7 0.005083 2.9727E-06 0.005885 2.9727E-06 
Na 22.98977 15 0.007125 3.4438E-06 0.00825 3.4438E-06 
Mg 24.305 2 0.00095 4.3433E-07 0.0011 4.3433E-07 
Al 26.981538 16.7 0.007933 3.2669E-06 0.009185 3.2669E-06 
Si 28.0855 12.1 0.005748 2.2740E-06 0.006655 2.2740E-06 
P 30.973761 35 0.016625 5.9643E-06 0.01925 5.9643E-06 
Cl 35.4527 5.3 0.002518 7.8906E-07 0.002915 7.8906E-07 
Ca 40.078 2 0.00095 2.6339E-07 0.0011 2.6339E-07 
Ti 47.867 1 0.000475 1.1027E-07 0.00055 1.1027E-07 
V 50.9415 3 0.001425 3.1084E-07 0.00165 3.1084E-07 
Cr 51.9961 4 0.0019 4.0604E-07 0.0022 4.0604E-07 
Mn 54.938049 1.7 0.000808 1.6333E-07 0.000935 1.6333E-07 
Fe 55.845 18 0.00855 1.7013E-06 0.0099 1.7013E-06 VF 
Co 58.9332 1 0.000475 8.9562E-08 0.00055 8.9562E-08 3.5464E-05 
Ni 58.6934 24 0.0114 2.1583E-06 0.0132 2.1583E-06 
Cu 63.546 1 0.000475 8.3060E-08 0.00055 8.3061E-08 
Zn 65.39 40.3 0.019143 3.2529E-06 0.022165 3.2529E-06 
Mo 95.94 10 0.00475 5.5015E-07 0.0055 5.5015E-07 
Ag 107.8682 0.1 4.75E-05 4.8932E-09 0.000055 4.8932E-09 
Cd 112.411 25 0.011875 1.1739E-06 0.01375 1.1739E-06 
In 114.818 2 0.00095 9.1940E-08 0.0011 9.1940E-08 
Sn 118.71 4 0.0019 1.7785E-07 0.0022 1.7785E-07 
W 183.84 2 0.00095 5.7421E-08 0.0011 5.7421E-08 
Pb 207.2 1 0.000475 2.5474E-08 0.00055 2.5474E-08 
Bi 208.98038 0.4 0.00019 1.0103E-08 0.00022 1.0103E-08 
Total 0.168008 0.194535

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page III-7 of III-12 
Attachment III - Worksheet tables 
element Waste Stream Composition (kg/assembly) 
fuel impurities fuel oxygen Total bottom plenum top 
Ag 4.75E-05 0.000048 
Al 0.0245 0.007933 0.032433 0.0020 0.0016 0.0014 
B 0.00029 0.000475 0.000769 0.0000 0.0000 0.0000 
Bi 0.00019 0.000190 
C 0.00392 0.042465 0.046385 0.0010 0.0003 0.0006 
Ca 0.00095 0.000950 
Cd 0.011875 0.011875 
Cl 0.002518 0.002518 
Co 0.04900 0.000475 0.049475 0.0059 0.0031 0.0038 
Cr 1.04612 0.0019 1.048020 0.5393 0.0632 0.3067 
Cu 0.01470 0.000475 0.015175 0.0012 0.0009 0.0008 
F 0.005083 0.005083 
Fe 0.96200 0.00855 0.970550 1.5998 0.0563 0.8894 
In 0.00095 0.000950 
Li 0.000475 0.000475 
Mg 0.00095 0.000950 
Mn 0.01715 0.000808 0.017958 0.0381 0.0012 0.0215 
Mo 0.14945 0.00475 0.154200 0.0731 0.0095 0.0397 
N 0.00000 0.011875 0.011875 0.0000 0.0000 0.0001 
Na 0.007125 0.007125 
Nb 0.26950 0.269500 0.0215 0.0172 0.0149 
Ni 2.64600 0.0114 2.657400 0.5024 0.1690 0.3059 
O 0.13814 64.77273 64.910872 0.0001 0.0035 0.0000 
P 0.00070 0.016625 0.017325 0.0001 0.0000 0.0001 
Pb 0.000475 0.000475 
S 0.00070 0 0.0001 0.0000 0.0001 
Si 0.01715 0.005748 0.022898 0.0503 0.0011 0.0268 
Sn 1.95705 0.0019 1.958947 0.0008 0.0489 0.0000 
Ti 0.04410 0.000475 0.044575 0.0035 0.0028 0.0024 
V 0.001425 0.001425 
W 0.00095 0.000950 
Zn 0.019143 0.019143 
Zr 112.67989 112.679885 0.0440 2.8164 0.0000

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page III-8 of III-12 
Attachment III - Worksheet tables 
element South Texas Composition (kg/assembly) Steel Clad Composition (kg/assembly) 
fuel fuel oxygen impurities Total fuel 
hardware 
fuel 
oxygen impurities Total plenum 
Ag 0.000055 0.00006 4.75E-05 4.75E-05 
Al 0.0245 0.009185 0.03369 0.0245 0.00793 0.03243 0.00156 
B 0.0003 0.00055 0.00084 0.00029 0.00048 0.00077 0.00002 
Bi 0.00022 0.00022 0.00019 0.00019 
C 0.0039 0.04917 0.05309 0.11421 0.04247 0.15668 0.00303 
Ca 0.0011 0.00110 0.00095 0.00095 
Cd 0.01375 0.01375 0.01188 0.01188 
Cl 0.002915 0.00292 0.00252 0.00252 
Co 0.0490 0.00055 0.04955 0.15929 0.00048 0.15977 0.00590 
Cr 1.0742 0.0022 1.07645 27.12602 0.00190 27.1279 0.71868 
Cu 0.0147 0.00055 0.01525 0.01470 0.00048 0.01518 0.00094 
F 0.005885 0.00589 0.00508 0.00508 
Fe 1.0183 0.0099 1.02820 93.78510 0.00855 93.7937 2.38930 
In 0.0011 0.00110 0.00095 0.00095 
Li 0.00055 0.00055 0.00048 0.00048 
Mg 0.0011 0.00110 0.00095 0.00095 
Mn 0.0172 0.000935 0.01809 2.77445 0.00081 2.77526 0.07051 
Mo 0.1495 0.0055 0.15495 0.14945 0.00475 0.1542 0.00952 
N 0.0000 0.01375 0.01375 0.13787 0.01188 0.14974 0.00347 
Na 0.00825 0.00825 0.00713 0.00713 
Nb 0.2695 0.26950 0.26950 0.2695 0.01720 
Ni 2.6460 0.0132 2.65920 17.01150 0.01140 17.0229 0.53010 
O 0.1719 75.00000 75.17190 0.00077 64.77273 64.7735 0.00000 
P 0.0007 0.01925 0.01995 0.06280 0.01663 0.07943 0.00610 
Pb 0.00055 0.00055 0.00048 0.00048 
S 0.0007 0 0.04210 0.0421 0.00110 
Si 0.0172 0.006655 0.02381 1.05114 0.00575 1.05689 0.02712 
Sn 2.4352 0.0022 2.43744 0.01088 0.00190 0.01278 0.00000 
Ti 0.0441 0.00055 0.04465 0.04410 0.00048 0.04458 0.00281 
V 0.00165 0.00165 0.00143 0.00143 
W 0.0011 0.00110 0.00095 0.00095 
Zn 0.022165 0.02217 0.01914 0.01914 
Zr 140.2127 140.21265 0.62643 0.62643 0.00000

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page III-9 of III-12 
Attachment III - Worksheet Steel clad 
cladding volume (cm3) 17596.28 Guide tube mass (kg) 9.634146 
cladding mass (g) 139010.6 Instrument tube mass (kg) 0.770732 Materials and 
cladding mass 
updated 8/16 fuel: 92% plenum 8% Oxygen from fuel not included in these tables. 
See final worksheet 'tables' 
Region Fuel Plenum 
guide 
tubes 
instrument 
tube 
incore 
spacers cladding grid 
supports 
guide 
tubes 
instrument 
tube cladding spacers springs 
8.889393 0.711151 4.9 128.2646 0.64 0.744753 0.05958 10.74601 1.04 0.019 
SS 304 SS304 Inconel- 
718 SS304 Zircaloy-4 SS 304 SS 304 SS 304 Inconel- 
718 SS 302 
al 0 0 0.5 0 0 0 0 0 0.5 0 
b 0 0 0.006 0 0 0 0 0 0.006 0 
c 0.08 0.08 0.08 0.08 0 0.08 0.08 0.08 0.08 0.15 
co 0.08 0.08 1 0.08 0 0.08 0.08 0.08 1 0.08 
cr 19 19 19 19 0.1 19 19 19 19 18 
cu 0 0 0.3 0 0 0 0 0 0.3 0 
fe 67.495 67.495 14.934 67.495 0.2 67.495 67.495 67.495 14.934 68.925 
mn 2 2 0.35 2 0 2 2 2 0.35 2 
mo 0 0 3.05 0 0 0 0 0 3.05 0 
n 0.1 0.1 0 0.1 0 0.1 0.1 0.1 0 0.1 
nb+ta 0 0 5.5 0 0 0 0 0 5.5 0 
ni 10.42 10.42 54 10.42 0 10.42 10.42 10.42 54 9.92 
o 0 0 0 0 0.12 0 0 0 0 0 
p 0.045 0.045 0.015 0.045 0 0.045 0.045 0.045 0.015 0.045 
s 0.03 0.03 0.015 0.03 0 0.03 0.03 0.03 0.015 0.03 
si 0.75 0.75 0.35 0.75 0 0.75 0.75 0.75 0.35 0.75 
sn 0 0 0 0 1.7 0 0 0 0 0 
ti 0 0 0.9 0 0 0 0 0 0.9 0 
zr 0 0 0 0 97.88 0 0 0 0 0 
Fuel Plenum 
guide 
tubes 
instrument 
tube 
incore 
spacers cladding grid 
supports 
guide 
tubes 
instrument 
tube cladding spacers springs Element 
Mass 
Calculations 8.889393 0.711151 4.9 128.2646 0.64 0.744753 0.05958 10.74601 1.04 0.019 
SS 304 SS 304 Inconel- 
718 SS 304 Zircaloy-4 TOTALS SS 304 SS 304 SS 304 Inconel- 
718 SS 302 TOTALS 
al 0.0000 0.0000 0.0245 0.0000 0.0000 0.0245 0.0000 0.0000 0.0000 0.0016 0.0000 0.0016 
b 0.0000 0.0000 0.0003 0.0000 0.0000 0.0003 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 
c 0.0071 0.0006 0.0039 0.1026 0.0000 0.1142 0.0002 0.0000 0.0026 0.0002 0.0000 0.0030 
co 0.0071 0.0006 0.0490 0.1026 0.0000 0.1593 0.0002 0.0000 0.0026 0.0031 0.0000 0.0059 
cr 1.6890 0.1351 0.9310 24.3703 0.0006 27.1260 0.0425 0.0034 0.6125 0.0593 0.0010 0.7187 
cu 0.0000 0.0000 0.0147 0.0000 0.0000 0.0147 0.0000 0.0000 0.0000 0.0009 0.0000 0.0009 
fe 5.9999 0.4800 0.7318 86.5722 0.0013 93.7851 0.1508 0.0121 2.1759 0.0466 0.0039 2.3893 
mn 0.1778 0.0142 0.0172 2.5653 0.0000 2.7745 0.0045 0.0004 0.0645 0.0011 0.0001 0.0705 
mo 0.0000 0.0000 0.1495 0.0000 0.0000 0.1495 0.0000 0.0000 0.0000 0.0095 0.0000 0.0095 
n 0.0089 0.0007 0.0000 0.1283 0.0000 0.1379 0.0002 0.0000 0.0032 0.0000 0.0000 0.0035 
nb+ta 0.0000 0.0000 0.2695 0.0000 0.0000 0.2695 0.0000 0.0000 0.0000 0.0172 0.0000 0.0172 
ni 0.9263 0.0741 2.6460 13.3652 0.0000 17.0115 0.0233 0.0019 0.3359 0.1685 0.0006 0.5301 
o 0.0000 0.0000 0.0000 0.0000 0.0008 0.0008 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 
p 0.0040 0.0003 0.0007 0.0577 0.0000 0.0628 0.0001 0.0000 0.0015 0.0000 0.0000 0.0016 
s 0.0027 0.0002 0.0007 0.0385 0.0000 0.0421 0.0001 0.0000 0.0010 0.0000 0.0000 0.0011 
si 0.0667 0.0053 0.0172 0.9620 0.0000 1.0511 0.0017 0.0001 0.0242 0.0011 0.0000 0.0271 
sn 0.0000 0.0000 0.0000 0.0000 0.0109 0.0109 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 
ti 0.0000 0.0000 0.0441 0.0000 0.0000 0.0441 0.0000 0.0000 0.0000 0.0028 0.0000 0.0028 
zr 0.0000 0.0000 0.0000 0.0000 0.6264 0.6264 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 
TOTALS 8.889 0.711 4.900 128.265 0.640 143.405 0.223 0.018 3.224 0.312 0.006 3.783 
kg*SCALING 
FACTOR 8.889 0.711 4.900 128.265 0.640 0.223 0.018 3.224 0.312 0.006 

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page III-10 of III-12 
Attachment III - Worksheet South Texas 
fuel plus plenum length 478.8452 Fractions in fuel and plenum 
cladding volume (CM^3) 21585.65305 fuel: 94% plenum 6% 
cladding mass (g) 141601.88 
****Oxygen from fuel not included 
in these tables. See final 
worksheet 'tables' South Texas/Mark B 1.22671674 
Part Name guide tubes instrument 
tube incore spacers cladding grid supports 
kg/assembly 9.195305715 0.73562446 4.9 132.6786137 0.64 
Material Zircaloy-4 Zircaloy-4 Inconel-718 Zircaloy-4 Zircaloy-4 
al 0 0 0.5 0 0 
b 0 0 0.006 0 0 
c 0 0 0.08 0 0 
co 0 0 1 0 0 
Wt % of the 
constituent 
isotopes 
cr 0.1 0.1 19 0.1 0.1 
cu 0 0 0.3 0 0 
fe 0.2 0.2 14.934 0.2 0.2 
mn 0 0 0.35 0 0 
mo 0 0 3.05 0 0 
n 0 0 0 0 0 
nb+ta 0 0 5.5 0 0 
ni 0 0 54 0 0 
o 0.12 0.12 0 0.12 0.12 
p 0 0 0.015 0 0 
s 0 0 0.015 0 0 
si 0 0 0.35 0 0 
sn 1.7 1.7 0 1.7 1.7 
ti 0 0 0.9 0 0 
zr 97.88 97.88 0 97.88 97.88 
Region 
Part Name guide tubes instrument 
tube incore spacers cladding grid supports 
Element 
Mass 
Calculations kg/assembly 9.195305715 0.73562446 4.9 132.6786137 0.64 
Material Zircaloy-4 Inconel-718 Inconel-718 Zircaloy-4 Zircaloy-4 TOTALS 
al 0.0000 0.0000 0.0245 0.0000 0.0000 0.0245 
b 0.0000 0.0000 0.0003 0.0000 0.0000 0.0003 
c 0.0000 0.0000 0.0039 0.0000 0.0000 0.0039 
co 0.0000 0.0000 0.0490 0.0000 0.0000 0.0490 
cr 0.0092 0.0007 0.9310 0.1327 0.0006 1.0742 
cu 0.0000 0.0000 0.0147 0.0000 0.0000 0.0147 
fe 0.0184 0.0015 0.7318 0.2654 0.0013 1.0183 
mn 0.0000 0.0000 0.0172 0.0000 0.0000 0.0172 
mo 0.0000 0.0000 0.1495 0.0000 0.0000 0.1495 
n 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 
nb+ta 0.0000 0.0000 0.2695 0.0000 0.0000 0.2695 
ni 0.0000 0.0000 2.6460 0.0000 0.0000 2.6460 
o 0.0110 0.0009 0.0000 0.1592 0.0008 0.1719 
p 0.0000 0.0000 0.0007 0.0000 0.0000 0.0007 
s 0.0000 0.0000 0.0007 0.0000 0.0000 0.0007 
si 0.0000 0.0000 0.0172 0.0000 0.0000 0.0172 
sn 0.1563 0.0125 0.0000 2.2555 0.0109 2.4352 
ti 0.0000 0.0000 0.0441 0.0000 0.0000 0.0441 
zr 9.0004 0.7200 0.0000 129.8658 0.6264 140.2127 
TOTALS 9.195 0.736 4.900 132.679 0.640 148.150 
kg*SCALING FACTOR 9.195 0.736 4.900 0.638 0.640 16.109

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page III-11 of III-12 
Attachment III - Worksheet Waste Stream 
Materials and cladding 
mass updated 8/16 ****Oxygen from fuel not included in these tables. See final worksheet 'tables' 
Region Top Bottom 
Part Name top nozzle spring 
retainer 
hold down 
spring 
upper end 
plug upper nuts bottom 
nozzle 
bottom 
spacer lower nuts 
kg/assembly 7.48 0.91 1.8 0.06 0.51 8.16 1.3 0.15 
Material SS CF3M SS CF3M Inconel-718 SS 304 SS 304L SS CF3M 
Inconel- 
718 Zircaloy-4 
al 0 0 0.5 0 0 0 0.5 0 
b 0 0 0.006 0 0 0 0.006 0 
c 0.03 0.03 0.08 0.08 0.03 0.03 0.08 0 
co 0.08 0.08 1 0.08 0.08 0.08 1 0 
cr 19 19 19 19 19 19 19 0.1 
cu 0 0 0.3 0 0 0 0.3 0 
fe 62.97 62.97 14.934 67.495 66.045 62.97 14.934 0.2 
mn 1.5 1.5 0.35 2 2 1.5 0.35 0 
mo 2.5 2.5 3.05 0 0 2.5 3.05 0 
n 0 0 0 0.1 0.1 0 0 0 
nb+ta 0 0 5.5 0 0 0 5.5 0 
ni 11.92 11.92 54 10.42 11.92 11.92 54 0 
o 0 0 0 0 0 0 0 0.12 
p 0 0 0.015 0.045 0.045 0 0.015 0 
s 0 0 0.015 0.03 0.03 0 0.015 0 
si 2 2 0.35 0.75 0.75 2 0.35 0 
sn 0 0 0 0 0 0 0 1.7 
ti 0 0 0.9 0 0 0 0.9 0 
Wt % of the 
constituent 
isotopes 
zr 0 0 0 0 0 0 0 97.88 
Region Top Bottom 
Element 
Mass 
Calculations 
Part Name top 
nozzle 
spring 
retainer 
hold 
down 
spring 
upper 
end plug 
upper 
nuts 
bottom 
nozzle 
bottom 
spacer 
lower 
nuts 
kg/assembly 7.48 0.91 1.8 0.06 0.51 8.16 1.3 0.15 
Material SS CF3M SS CF3M 
Inconel- 
718 SS 304 SS 304L TOTALS SS CF3M 
Inconel- 
718 
Zircaloy- 
4 TOTALS 
al 0.0000 0.0000 0.0014 0.0000 0.0000 0.0014 0.0000 0.0020 0.0000 0.0020 
b 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 
c 0.0003 0.0000 0.0002 0.0000 0.0000 0.0006 0.0007 0.0003 0.0000 0.0010 
co 0.0009 0.0001 0.0027 0.0000 0.0001 0.0038 0.0020 0.0039 0.0000 0.0059 
cr 0.2132 0.0259 0.0513 0.0017 0.0145 0.3067 0.4651 0.0741 0.0000 0.5393 
cu 0.0000 0.0000 0.0008 0.0000 0.0000 0.0008 0.0000 0.0012 0.0000 0.0012 
fe 0.7065 0.0860 0.0403 0.0061 0.0505 0.8894 1.5415 0.0582 0.0001 1.5998 
mn 0.0168 0.0020 0.0009 0.0002 0.0015 0.0215 0.0367 0.0014 0.0000 0.0381 
mo 0.0281 0.0034 0.0082 0.0000 0.0000 0.0397 0.0612 0.0119 0.0000 0.0731 
n 0.0000 0.0000 0.0000 0.0000 0.0001 0.0001 0.0000 0.0000 0.0000 0.0000 
nb+ta 0.0000 0.0000 0.0149 0.0000 0.0000 0.0149 0.0000 0.0215 0.0000 0.0215 
ni 0.1337 0.0163 0.1458 0.0009 0.0091 0.3059 0.2918 0.2106 0.0000 0.5024 
o 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0001 0.0001 
p 0.0000 0.0000 0.0000 0.0000 0.0000 0.0001 0.0000 0.0001 0.0000 0.0001 
s 0.0000 0.0000 0.0000 0.0000 0.0000 0.0001 0.0000 0.0001 0.0000 0.0001 
si 0.0224 0.0027 0.0009 0.0001 0.0006 0.0268 0.0490 0.0014 0.0000 0.0503 
sn 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0008 0.0008 
ti 0.0000 0.0000 0.0024 0.0000 0.0000 0.0024 0.0000 0.0035 0.0000 0.0035 
zr 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0440 0.0440 
TOTALS 1.122 0.137 0.270 0.009 0.077 1.614 2.448 0.390 0.045 2.883 
kg*SCALING FACTOR 1.122 0.137 0.270 0.009 0.077 1.614 2.448 0.390 0.045 2.883

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page III-12 of III-12 
Attachment III - Worksheet Waste Stream 
cladding volume (CM^3) 17596.28 
cladding mass (g) 115431.61 
Fractions in fuel and plenum fuel: 92% plenum 8% 
Region FUEL PLENUM 
guide tubes instrument 
tube 
incore 
spacers cladding grid 
supports guide tubes instrument 
tube cladding spacers springs 
7.381572 0.590526 4.9 106.50834 0.64 0.618428 0.049474 8.923266 1.04 0.019 
Zircaloy-4 Zircaloy-4 Inconel-718 Zircaloy-4 Zircaloy-4 Zircaloy-4 Zircaloy-4 Zircaloy-4 Inconel-718 SS 302 
0 0 0.5 0 0 0 0 0 0.5 0 
0 0 0.006 0 0 0 0 0 0.006 0 
0 0 0.08 0 0 0 0 0 0.08 0.15 
0 0 1 0 0 0 0 0 1 0.08 
0.1 0.1 19 0.1 0.1 0.1 0.1 0.1 19 18 
0 0 0.3 0 0 0 0 0 0.3 0 
0.2 0.2 14.934 0.2 0.2 0.2 0.2 0.2 14.934 68.925 
0 0 0.35 0 0 0 0 0 0.35 2 
0 0 3.05 0 0 0 0 0 3.05 0 
0 0 0 0 0 0 0 0 0 0.1 
0 0 5.5 0 0 0 0 0 5.5 0 
0 0 54 0 0 0 0 0 54 9.92 
0.12 0.12 0 0.12 0.12 0.12 0.12 0.12 0 0 
0 0 0.015 0 0 0 0 0 0.015 0.045 
0 0 0.015 0 0 0 0 0 0.015 0.03 
0 0 0.35 0 0 0 0 0 0.35 0.75 
1.7 1.7 0 1.7 1.7 1.7 1.7 1.7 0 0 
0 0 0.9 0 0 0 0 0 0.9 0 
Wt % of the 
constituent 
isotopes 
97.88 97.88 0 97.88 97.88 97.88 97.88 97.88 0 0 
FUEL PLENUM 
Element Mass 
Calculations 
guide 
tubes 
instrumen 
t tube 
incore 
spacers cladding grid 
supports 
guide 
tubes 
instrumen 
t tube cladding spacers springs 
7.381572 0.590526 4.9 106.50834 0.64 0.618428 0.049474 8.923266 1.04 0.019 
Zircaloy-4 Zircaloy-4 Inconel- 
718 Zircaloy-4 Zircaloy-4 TOTALS Zircaloy-4 Zircaloy-4 Zircaloy-4 Inconel- 
718 SS 302 TOTALS 
0.0000 0.0000 0.0245 0.0000 0.0000 0.0245 0.0000 0.0000 0.0000 0.0016 0.0000 0.0016 
0.0000 0.0000 0.0003 0.0000 0.0000 0.0003 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 
0.0000 0.0000 0.0039 0.0000 0.0000 0.0039 0.0000 0.0000 0.0000 0.0002 0.0000 0.0003 
0.0000 0.0000 0.0490 0.0000 0.0000 0.0490 0.0000 0.0000 0.0000 0.0031 0.0000 0.0031 
0.0074 0.0006 0.9310 0.1065 0.0006 1.0461 0.0002 0.0000 0.0027 0.0593 0.0010 0.0632 
0.0000 0.0000 0.0147 0.0000 0.0000 0.0147 0.0000 0.0000 0.0000 0.0009 0.0000 0.0009 
0.0148 0.0012 0.7318 0.2130 0.0013 0.9620 0.0004 0.0000 0.0054 0.0466 0.0039 0.0563 
0.0000 0.0000 0.0172 0.0000 0.0000 0.0172 0.0000 0.0000 0.0000 0.0011 0.0001 0.0012 
0.0000 0.0000 0.1495 0.0000 0.0000 0.1495 0.0000 0.0000 0.0000 0.0095 0.0000 0.0095 
0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 
0.0000 0.0000 0.2695 0.0000 0.0000 0.2695 0.0000 0.0000 0.0000 0.0172 0.0000 0.0172 
0.0000 0.0000 2.6460 0.0000 0.0000 2.6460 0.0000 0.0000 0.0000 0.1685 0.0006 0.1690 
0.0089 0.0007 0.0000 0.1278 0.0008 0.1381 0.0002 0.0000 0.0032 0.0000 0.0000 0.0035 
0.0000 0.0000 0.0007 0.0000 0.0000 0.0007 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 
0.0000 0.0000 0.0007 0.0000 0.0000 0.0007 0.0000 0.0000 0.0000 0.0000 0.0000 0.0000 
0.0000 0.0000 0.0172 0.0000 0.0000 0.0172 0.0000 0.0000 0.0000 0.0011 0.0000 0.0011 
0.1255 0.0100 0.0000 1.8106 0.0109 1.9570 0.0032 0.0003 0.0455 0.0000 0.0000 0.0489 
0.0000 0.0000 0.0441 0.0000 0.0000 0.0441 0.0000 0.0000 0.0000 0.0028 0.0000 0.0028 
7.2251 0.5780 0.0000 104.2504 0.6264 112.6799 0.1816 0.0145 2.6202 0.0000 0.0000 2.8164 
TOTALS 7.382 0.591 4.900 106.508 0.640 120.020 0.186 0.015 2.677 0.312 0.006 3.195 
kg*SCALING 
FACTOR 7.382 0.591 4.900 0.512 0.640 14.024 0.186 0.015 2.677 0.312 0.006 3.195

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page IV-1 of IV-1 
Attachment IV 
Comparison of Source Terms per MTU of 4 Average PWR SNF Assemblies 
4%-48GWd-25y 3.75%-41.2GWD-23y 3.75%-41.7GWd-25y 3.82%-42.6GWd-22y 
(475 MTU/Assembly) (432 MTU/Assembly) (434 MTU/Assembly) (432 MTU/Assembly) 
Curies 
Activation Products 9.6490E+02 9.7950E+02 8.6260E+02 1.0830E+03 
Actinides and daughters 6.3270E+04 6.2700E+04 5.8460E+04 6.6380E+04 
Fission products 2.7740E+05 2.5350E+05 2.4360E+05 2.6820E+05 
Total 3.4180E+05 3.1720E+05 3.0290E+05 3.3580E+05 
Watts 
Activation Products 6.4270E+00 7.4370E+00 5.8040E+00 8.6610E+00 
Actinides and daughters 4.6310E+02 3.6000E+02 3.6600E+02 3.8180E+02 
Fission products 7.9390E+02 7.2600E+02 6.9640E+02 7.6900E+02 
Total 1.2650E+03 1.0940E+03 1.0690E+03 1.1590E+03 
Grams 
Activation Products 4.4030E+05 4.4030E+05 4.4030E+05 4.4030E+05 
Actinides and daughters 9.5050E+05 9.5740E+05 9.5690E+05 9.5590E+05 
Fission products 4.9330E+04 4.2400E+04 4.2870E+04 4.3830E+04 
Total 1.4400E+06 1.4400E+06 1.4400E+06 1.4400E+06 
Neutrons/s 
Alpha,n 1.3490E+07 1.0420E+07 1.0580E+07 1.1070E+07 
Sponteneous fission 4.2280E+08 2.7610E+08 2.6950E+08 3.1690E+08 
Total neutrons 4.3650E+08 2.8650E+08 2.8030E+08 3.2810E+08 
Photons/s 
Total intensity 6.7570E+15 6.1720E+15 5.9220E+15 6.5400E+15

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page V-1 of V-1 
Attachment V - Listing of UNIX Script Files 
cut-script 
batch43 INPUTFILE 
csplit -f cut INPUTFILE.output "/module origens is finished/"\ 
"/halt feature/" 
cat cut00 cut02 > INPUTFILE.cut 
rm cut0* INPUTFILE.output 
curies 
BEGIN {intable=0 && insas=0 } 
/halt feature/ {insas=1} 
/nuclide radioactivity/{if (insas) print $0; intable=1} 
/initial/ {if (insas && intable) print $0} 
/charge/ {if (insas && intable) print $0} 
/E/ {if (insas && intable) print $0} 
/total/ {intable=0} 
gammas 
BEGIN {insas=0 && intable=0} 
/halt feature/{insas=1} 
/gamma source spectrum/ {if (insas) intable=1; print $0} 
/ to / {if (insas && intable) print $0} 
/totals/ {intable=0} 
neutrons 
BEGIN { intable=0} 
/alpha-n plus/ {intable=1; print $0} 
/yr/{if (intable) print $0} 
/E/ {if (intable) print $0} 
/ gamma sources determined / {intable=0} 
watts 
BEGIN {intable=0 && insas=0 } 
/halt feature/ {insas=1} 
/nuclide thermal power, watts/{if (insas) print $0; intable=1} 
/charge/ {if (insas && intable) print $0} 
/initial/ {if (insas && intable) print $0} 
/E/ {if (insas && intable) print $0} 
/total/ {intable=0}

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page VI-1 of VI-4 
Attachment VI - Calculation of Crud Source 
South Texas information taken from 2A-361-2A-363 
PWR assembly parameters to maximize surface area Mark B South Texas 
Rod OD, cm 1.0922 0.95 
Instrument tube OD 1.3462 1.25984 
# of Rods 208 264 
Rod Length 390.347 448.67 
All dimensions in cm! 
# Guide and instrument tubes 17 25 
Assembly Length 420.688 505.46 
Instr. tube outside area+ inside area 3380.439626 3819.621782 
PWR Assembly Surf. Area, cm^2 336057.9243 449002.7692 
(Rod surface +instrument tubes inside and outside surfaces) 
Crud activities per unit area 
Co-60 1.40E-04 Ci/cm^2 
NRC recommended value: 1.40E-04 Ci/cm^2 
From Jones report, Table 1, 
p. 7 
Cr 51 1.89E-04 Ci/cm^2 
Mn 54 7.40E-05 Ci/cm^2 
Fe 55 5.90E-03 Ci/cm^2 
Co 58 4.03E-04 Ci/cm^2 
Fe 59 7.60E-05 Ci/cm^2 
Co 60 5.10E-05 Ci/cm^2 
Ni 63 2.00E-06 Ci/cm^2 
Zn 65 0.00E+00 Ci/cm^2 
Zr 95 1.90E-05 Ci/cm^2 
Half Life information 
Cr 51 27.70 days 0.0758 years 
Mn 54 312.10 days 0.8545 years 
Fe 55 2.73 years 2.73 years 
Co 58 70.88 days 0.1941 years 
Fe 59 44.51 days 0.1219 years 
Co 60 5.27 years 5.27 years 
Ni 63 100.00 years 100.00 years 
Zn 65 243.80 days 0.6675 years 
Zr 95 64.02 days 0.1753 years

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page VI-2 of VI-4 
Attachment VI - Calculation of Crud Source 
Fuel Age, years 
since reactor 
discharge 
Crud (Ci) for regular 
assembly, using NRC 
Co 60 values 
For South Texas 
Assembly, using NRC 
Co 60 values 
0 47.05 62.86 
5 24.38 32.57 
6 21.37 28.56 
7 18.74 25.04 
8 16.43 21.95 
9 14.41 19.25 
10 12.63 16.88 
11 11.07 14.80 
15 6.54 8.74 
20 3.39 4.53 
25 1.76 2.35 
30 0.91 1.22 
35 0.47 0.63 
40 0.24 0.33 
45 0.13 0.17 
50 0.07 0.09 
55 0.03 0.05 
60 0.02 0.02 
65 0.01 0.01 
70 0.00 0.01 
75 0.00 0.00 
80 0.00 0.00 
85 0.00 0.00 
90 0.00 0.00 
95 0.00 0.00 
100 0.00 0.00 
200 0.00 0.00 
300 0.00 0.00

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page VI-3 of VI-4 
Attachment VI - Calculation of Crud Source 
Crud (Ci) for regular assembly, using Jones values Fuel Age, years since 
reactor discharge Cr 51 Mn 54 Fe 55 Co 58 Fe 59 Co 60 Ni 63 Zn 65 Zr 95 
0 63.51 24.87 1983.41 135.43 25.54 17.14 0.67 0.00 6.39 
5 0.00 0.43 557.28 0.00 0.00 8.88 0.65 0.00 0.00 
6 0.00 0.19 432.32 0.00 0.00 7.79 0.64 0.00 0.00 
7 0.00 0.09 335.38 0.00 0.00 6.83 0.64 0.00 0.00 
8 0.00 0.04 260.18 0.00 0.00 5.99 0.64 0.00 0.00 
9 0.00 0.02 201.84 0.00 0.00 5.25 0.63 0.00 0.00 
10 0.00 0.01 156.58 0.00 0.00 4.60 0.63 0.00 0.00 
11 0.00 0.00 121.47 0.00 0.00 4.03 0.62 0.00 0.00 
15 0.00 0.00 43.99 0.00 0.00 2.38 0.61 0.00 0.00 
20 0.00 0.00 12.36 0.00 0.00 1.24 0.59 0.00 0.00 
25 0.00 0.00 3.47 0.00 0.00 0.64 0.57 0.00 0.00 
30 0.00 0.00 0.98 0.00 0.00 0.33 0.55 0.00 0.00 
35 0.00 0.00 0.27 0.00 0.00 0.17 0.53 0.00 0.00 
40 0.00 0.00 0.08 0.00 0.00 0.09 0.51 0.00 0.00 
45 0.00 0.00 0.02 0.00 0.00 0.05 0.49 0.00 0.00 
50 0.00 0.00 0.01 0.00 0.00 0.02 0.48 0.00 0.00 
55 0.00 0.00 0.00 0.00 0.00 0.01 0.46 0.00 0.00 
60 0.00 0.00 0.00 0.00 0.00 0.01 0.44 0.00 0.00 
65 0.00 0.00 0.00 0.00 0.00 0.00 0.43 0.00 0.00 
70 0.00 0.00 0.00 0.00 0.00 0.00 0.41 0.00 0.00 
75 0.00 0.00 0.00 0.00 0.00 0.00 0.40 0.00 0.00 
80 0.00 0.00 0.00 0.00 0.00 0.00 0.39 0.00 0.00 
85 0.00 0.00 0.00 0.00 0.00 0.00 0.37 0.00 0.00 
90 0.00 0.00 0.00 0.00 0.00 0.00 0.36 0.00 0.00 
95 0.00 0.00 0.00 0.00 0.00 0.00 0.35 0.00 0.00 
100 0.00 0.00 0.00 0.00 0.00 0.00 0.34 0.00 0.00 
200 0.00 0.00 0.00 0.00 0.00 0.00 0.17 0.00 0.00 
300 0.00 0.00 0.00 0.00 0.00 0.00 0.08 0.00 0.00

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page VI-4 of VI-4 
Attachment VI - Calculation of Crud Source 
Crud (Ci) for South Texas assembly, using Jones values Fuel Age, years since 
reactor discharge Cr 51 Mn 54 Fe 55 Co 58 Fe 59 Co 60 Ni 63 Zn 65 Zr 95 
0 84.86 33.23 2650.01 180.95 34.12 22.90 0.90 0.00 8.53 
5 0.00 0.58 744.58 0.00 0.00 11.86 0.87 0.00 0.00 
6 0.00 0.26 577.62 0.00 0.00 10.40 0.86 0.00 0.00 
7 0.00 0.11 448.10 0.00 0.00 9.12 0.86 0.00 0.00 
8 0.00 0.05 347.62 0.00 0.00 8.00 0.85 0.00 0.00 
9 0.00 0.02 269.68 0.00 0.00 7.01 0.84 0.00 0.00 
10 0.00 0.01 209.21 0.00 0.00 6.15 0.84 0.00 0.00 
11 0.00 0.00 162.30 0.00 0.00 5.39 0.83 0.00 0.00 
15 0.00 0.00 58.78 0.00 0.00 3.19 0.81 0.00 0.00 
20 0.00 0.00 16.52 0.00 0.00 1.65 0.78 0.00 0.00 
25 0.00 0.00 4.64 0.00 0.00 0.86 0.76 0.00 0.00 
30 0.00 0.00 1.30 0.00 0.00 0.44 0.73 0.00 0.00 
35 0.00 0.00 0.37 0.00 0.00 0.23 0.70 0.00 0.00 
40 0.00 0.00 0.10 0.00 0.00 0.12 0.68 0.00 0.00 
45 0.00 0.00 0.03 0.00 0.00 0.06 0.66 0.00 0.00 
50 0.00 0.00 0.01 0.00 0.00 0.03 0.63 0.00 0.00 
55 0.00 0.00 0.00 0.00 0.00 0.02 0.61 0.00 0.00 
60 0.00 0.00 0.00 0.00 0.00 0.01 0.59 0.00 0.00 
65 0.00 0.00 0.00 0.00 0.00 0.00 0.57 0.00 0.00 
70 0.00 0.00 0.00 0.00 0.00 0.00 0.55 0.00 0.00 
75 0.00 0.00 0.00 0.00 0.00 0.00 0.53 0.00 0.00 
80 0.00 0.00 0.00 0.00 0.00 0.00 0.52 0.00 0.00 
85 0.00 0.00 0.00 0.00 0.00 0.00 0.50 0.00 0.00 
90 0.00 0.00 0.00 0.00 0.00 0.00 0.48 0.00 0.00 
95 0.00 0.00 0.00 0.00 0.00 0.00 0.46 0.00 0.00 
100 0.00 0.00 0.00 0.00 0.00 0.00 0.45 0.00 0.00 
200 0.00 0.00 0.00 0.00 0.00 0.00 0.22 0.00 0.00 
300 0.00 0.00 0.00 0.00 0.00 0.00 0.11 0.00 0.00

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page VII-1 of VII-1 
Attachment VII - 36Cl and 14C calculations 
PWR 
curies per ppm 
Burnup 
(GWd/MTU) CL36 (5.3ppm) Cl36(10ppm) 
Ratio of 10 ppm to 
5.3 ppm values for 
Cl36 
Cl36 5.3 ppm 
value/5.3 
Cl36 10 ppm 
value/10 
Ratio of 10 ppm to 
5.3 ppm values for 
Cl36 for curies per 
ppm 
1 1.24E-04 2.35E-04 8.952E-01 2.34E-05 2.35E-05 1.0044E+00 
10 1.23E-03 2.33E-03 8.943E-01 2.32E-04 2.33E-04 1.0040E+00 
20 2.51E-03 4.74E-03 8.884E-01 4.74E-04 4.74E-04 1.0009E+00 
30 3.87E-03 7.32E-03 8.915E-01 7.30E-04 7.32E-04 1.0025E+00 
40 5.32E-03 1.01E-02 8.985E-01 1.00E-03 1.01E-03 1.0062E+00 
50 6.89E-03 1.31E-02 9.013E-01 1.30E-03 1.31E-03 1.0077E+00 
60 8.55E-03 1.62E-02 8.947E-01 1.61E-03 1.62E-03 1.0042E+00 
70 1.03E-02 1.95E-02 8.932E-01 1.94E-03 1.95E-03 1.0034E+00 
75 1.11E-02 2.12E-02 9.099E-01 2.09E-03 2.12E-03 1.0123E+00 
80 1.19E-02 2.25E-03 
1.886792453 
Burnup 
(GWd/MTU) C-14 (Ci/assembly) 
1 5.67E-03 6.34E-05 
10 5.69E-02 6.36E-04 
20 1.17E-01 1.31E-03 
30 1.87E-01 2.09E-03 
40 2.54E-01 2.84E-03 
50 3.33E-01 3.72E-03 
60 4.20E-01 4.70E-03 
70 5.13E-01 5.74E-03 
75 5.62E-01 6.29E-03 
80 6.11E-01 6.83E-03 
1.E-05 
1.E-04 
1.E-03 
1.E-02 
0 10 20 30 40 50 60 70 80 90 
Burnup (GWd/MTU) 
Activity per Unit Impurity (Ci/ppm) 
chlorine 36 (5.3 ppm) 
chlorine 36 (10 ppm) 
carbon 14

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page VIII-1 of VIII-22 
Attachment VIII - List of Files on Compact Disks 
This attachment lists the files stored on Attachment X (four CDs). 
These files include: 
*.cut files - these files are the sections of the SAS2H/ORIGEN-S output files that contain the 
input echoes and the final ORIGEN-S output. Other intermediate calculations and information 
generated by SAS2H and included in the output files have been removed. In the *.cut file 
names, the E, R, and B codes explanations are listed in Table VIII-1. The files listed as 
"PWR.max.2.cut, PWR.ave.2.cut, PWR.max.3.cut, and PWR.min.3.cut are used to 
generate radionuclide inventories for specific years (see Section 5.5). The *.2.cut files 
generate the information for cooling times up to 10000 years. The *.3.cut files generate the 
information for cooling times over 10000 years. The files listed as pwr_imp_BU#.cut and 
pwr_cl2_BU#.cut are the SAS2H/ORIGEN-S output files used to demonstrate the effect of 
fuel impurities on the source terms. The BU# indicates the burnup for that particular 
calculation, and follows the same convention as the rest of the files. 
Table VIII-1. *.cut files Codification 
*.cut Files 
E Code 
Enrichment 
(% 235U) 
*.cut Files 
R Code 
Light Elements 
Source Term Region 
*.cut Files 
B Code 
Burnup 
(MWd/MTU) 
E1 5.5 R1 assembly fuel B1 0.001 
E2 5.0 R2 bottom end fitting B2 0.01 
E3 4.5 R3 plenum B3 0.1 
E4 4.2 R4 top end fitting B4 1. 
E5 4.0 - - B5 10. 
E6 3.5 - - B6 20. 
E7 3.0 - - B7 30. 
E8 2.5 - - B8 40. 
E9 2.0 - - B9 48.086 
E10 1.5 - - B10 50. 
E11 1.0 - - B11 60. 
E12 0.711 - - B12 70. 
- - - - B13 75. 
- - - - B14 80. 
- - - - B15 85. 
UNIX script-files  these files are used to generate *.cut files from SAS2H/ORIGEN-S output 
files and to extract different parameters of interest from the *.cut files. They are described in 
Table 1. 
Microsoft EXCEL spreadsheets  these files were used to calculate and display different 
parameters, presented in the Attachments I, II, III, IV, VI, VII, and IX, in a tabular and/or 
graphical form. 
Microsoft WORD file  This file presents the UNIX script-files (Attachment V).

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page VIII-2 of VIII-22 
Attachment VIII - List of Files on Disk 1 
Volume in drive D is PWR ST G&E 1 
Volume Serial Number is 5F87-42C7 
Directory of D:\ 
05/17/2004 10:17a <DIR> Attachments 
05/04/2004 11:26a <DIR> Oldcutfiles 
05/04/2004 11:26a <DIR> South Texas 
05/04/2004 11:23a <DIR> Steel Clad 
05/04/2004 11:22a <DIR> UNIX-script files 
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04/15/2004 12:18p 20,992 ATTACH_VII.XLS 
05/17/2004 10:17a 482,816 ATTACH_XI.XLS 
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04/15/2004 11:06a 15,872 ATTACH_IV.XLS 
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11/03/1999 09:44a 205,038 pwr_imp_BU4.cut 
11/03/1999 09:44a 253,669 pwr_imp_BU8.cut 
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Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page VIII-3 of VIII-22 
Attachment VIII - List of Files on Disk 1 (Continued) 
Directory of D:\South Texas 
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10/12/1999 09:23a 2,931,169 South.Texas.E11.R1.B10.cut 
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Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page VIII-4 of VIII-22 
Attachment VIII - List of Files on Disk 1 (Continued) 
10/12/1999 09:39a 2,737,183 South.Texas.E5.R1.B5.cut 
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10/12/1999 09:20a 2,809,763 South.Texas.E1.R1.B6.cut 
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10/12/1999 09:35a 2,949,311 South.Texas.E4.R1.B11.cut 
10/12/1999 09:47a 2,966,133 South.Texas.E8.R1.B11.cut 
10/12/1999 09:44a 2,952,287 South.Texas.E7.R1.B11.cut 
10/12/1999 09:32a 2,944,829 South.Texas.E3.R1.B11.cut 
10/12/1999 09:41a 2,951,112 South.Texas.E6.R1.B11.cut

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page VIII-5 of VIII-22 
Attachment VIII - List of Files on Disk 1 (Continued) 
10/12/1999 09:29a 2,941,979 South.Texas.E2.R1.B11.cut 
10/12/1999 09:38a 2,952,298 South.Texas.E5.R1.B11.cut 
10/12/1999 09:49a 2,966,512 South.Texas.E9.R1.B11.cut 
10/12/1999 09:36a 2,972,768 South.Texas.E4.R1.B12.cut 
10/12/1999 09:47a 2,986,779 South.Texas.E8.R1.B12.cut 
10/12/1999 09:44a 2,985,386 South.Texas.E7.R1.B12.cut 
10/12/1999 09:33a 2,968,501 South.Texas.E3.R1.B12.cut 
10/12/1999 09:41a 2,982,734 South.Texas.E6.R1.B12.cut 
10/12/1999 09:29a 2,968,654 South.Texas.E2.R1.B12.cut 
10/12/1999 09:38a 2,981,238 South.Texas.E5.R1.B12.cut 
10/12/1999 09:49a 2,987,240 South.Texas.E9.R1.B12.cut 
10/12/1999 09:36a 2,987,227 South.Texas.E4.R1.B13.cut 
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10/12/1999 09:45a 2,994,401 South.Texas.E7.R1.B13.cut 
10/12/1999 09:33a 2,985,229 South.Texas.E3.R1.B13.cut 
10/12/1999 09:41a 2,992,591 South.Texas.E6.R1.B13.cut 
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10/12/1999 09:50a 2,991,886 South.Texas.E9.R1.B13.cut 
10/12/1999 09:19a 2,976,930 South.Texas.E1.R1.B13.cut 
10/12/1999 09:21a 2,165,921 South.Texas.E10.R1.B1.cut 
10/12/1999 09:22a 2,754,276 South.Texas.E10.R1.B5.cut 
10/12/1999 09:23a 2,921,082 South.Texas.E10.R1.B9.cut 
10/12/1999 09:26a 2,158,110 South.Texas.E12.R1.B1.cut 
10/12/1999 09:27a 2,777,351 South.Texas.E12.R1.B5.cut 
10/12/1999 09:28a 2,923,102 South.Texas.E12.R1.B9.cut 
10/12/1999 09:21a 2,254,801 South.Texas.E10.R1.B2.cut 
10/12/1999 09:22a 2,827,347 South.Texas.E10.R1.B6.cut 
10/12/1999 09:27a 2,252,746 South.Texas.E12.R1.B2.cut 
10/12/1999 09:27a 2,829,772 South.Texas.E12.R1.B6.cut 
10/12/1999 09:22a 2,389,011 South.Texas.E10.R1.B3.cut 
10/12/1999 09:23a 2,859,957 South.Texas.E10.R1.B7.cut 
10/12/1999 09:27a 2,386,065 South.Texas.E12.R1.B3.cut 
10/12/1999 09:28a 2,860,860 South.Texas.E12.R1.B7.cut 
10/12/1999 09:22a 2,533,525 South.Texas.E10.R1.B4.cut 
10/12/1999 09:23a 2,895,781 South.Texas.E10.R1.B8.cut 
10/12/1999 09:27a 2,541,011 South.Texas.E12.R1.B4.cut 
10/12/1999 09:28a 2,895,708 South.Texas.E12.R1.B8.cut 
10/12/1999 08:17a 2,177,594 South.Texas.E1.R1.B1.cut 
10/12/1999 09:18a 2,915,271 South.Texas.E1.R1.B10.cut 
10/12/1999 09:18a 2,935,609 South.Texas.E1.R1.B11.cut 
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156 File(s) 425,043,049 bytes 
Directory of D:\Steel Clad 
05/04/2004 11:23a <DIR> . 
05/04/2004 11:23a <DIR> .. 
10/12/1999 09:56a 2,782,317 Steel.Clad.E11.R1.B6.cut 
10/12/1999 09:56a 2,821,068 Steel.Clad.E11.R1.B7.cut 
10/12/1999 09:56a 2,512,360 Steel.Clad.E11.R1.B4.cut 
10/12/1999 09:56a 2,724,285 Steel.Clad.E11.R1.B5.cut 
10/12/1999 09:54a 2,786,542 Steel.Clad.E10.R1.B6.cut 
10/12/1999 09:54a 2,817,115 Steel.Clad.E10.R1.B7.cut 
10/12/1999 09:53a 2,511,160 Steel.Clad.E10.R1.B4.cut 
10/12/1999 09:54a 2,708,185 Steel.Clad.E10.R1.B5.cut 
10/12/1999 09:57a 2,546,881 Steel.Clad.E11.R3.B6.cut 
10/12/1999 09:57a 2,578,229 Steel.Clad.E11.R3.B7.cut 
10/12/1999 09:57a 2,299,511 Steel.Clad.E11.R3.B4.cut

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page VIII-6 of VIII-22 
Attachment VIII - List of Files on Disk 1 (Continued) 
10/12/1999 09:57a 2,494,067 Steel.Clad.E11.R3.B5.cut 
10/12/1999 09:55a 2,543,340 Steel.Clad.E10.R3.B6.cut 
10/12/1999 09:55a 2,575,144 Steel.Clad.E10.R3.B7.cut 
10/12/1999 09:54a 2,298,950 Steel.Clad.E10.R3.B4.cut 
10/12/1999 09:55a 2,482,806 Steel.Clad.E10.R3.B5.cut 
10/12/1999 09:56a 2,857,583 Steel.Clad.E11.R1.B8.cut 
10/12/1999 09:54a 2,852,001 Steel.Clad.E10.R1.B8.cut 
10/12/1999 09:57a 2,605,337 Steel.Clad.E11.R3.B8.cut 
10/12/1999 09:55a 2,604,253 Steel.Clad.E10.R3.B8.cut 
10/12/1999 10:10a 2,699,294 Steel.Clad.E7.R1.B5.cut 
10/12/1999 10:14a 2,706,668 Steel.Clad.E9.R1.B5.cut 
10/12/1999 10:00a 2,770,507 Steel.Clad.E3.R1.B6.cut 
10/12/1999 10:05a 2,777,769 Steel.Clad.E5.R1.B6.cut 
10/12/1999 10:10a 2,780,927 Steel.Clad.E7.R1.B6.cut 
10/12/1999 10:15a 2,783,163 Steel.Clad.E9.R1.B6.cut 
10/12/1999 10:01a 2,816,024 Steel.Clad.E3.R1.B7.cut 
10/12/1999 10:05a 2,814,975 Steel.Clad.E5.R1.B7.cut 
10/12/1999 10:10a 2,812,901 Steel.Clad.E7.R1.B7.cut 
10/12/1999 09:52a 2,855,179 Steel.Clad.E1.R1.B8.cut 
10/12/1999 10:15a 2,820,032 Steel.Clad.E9.R1.B7.cut 
10/12/1999 10:00a 2,494,750 Steel.Clad.E3.R1.B4.cut 
10/12/1999 10:01a 2,853,614 Steel.Clad.E3.R1.B8.cut 
10/12/1999 10:04a 2,491,140 Steel.Clad.E5.R1.B4.cut 
10/12/1999 10:06a 2,850,059 Steel.Clad.E5.R1.B8.cut 
10/12/1999 10:10a 2,499,772 Steel.Clad.E7.R1.B4.cut 
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10/12/1999 10:00a 2,697,357 Steel.Clad.E3.R1.B5.cut 
10/12/1999 10:05a 2,698,354 Steel.Clad.E5.R1.B5.cut 
10/12/1999 10:11a 2,471,198 Steel.Clad.E7.R3.B5.cut 
10/12/1999 09:53a 2,532,504 Steel.Clad.E1.R3.B6.cut 
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10/12/1999 10:06a 2,285,068 Steel.Clad.E5.R3.B4.cut 
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10/12/1999 10:11a 2,288,720 Steel.Clad.E7.R3.B4.cut 
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10/12/1999 09:53a 2,468,820 Steel.Clad.E1.R3.B5.cut 
10/12/1999 10:15a 2,297,335 Steel.Clad.E9.R3.B4.cut 
10/12/1999 10:17a 2,600,424 Steel.Clad.E9.R3.B8.cut 
10/12/1999 10:01a 2,468,879 Steel.Clad.E3.R3.B5.cut 
10/12/1999 10:06a 2,469,752 Steel.Clad.E5.R3.B5.cut 
10/12/1999 10:12a 2,702,613 Steel.Clad.E8.R1.B5.cut 
10/12/1999 09:58a 2,765,408 Steel.Clad.E2.R1.B6.cut 
10/12/1999 10:03a 2,772,984 Steel.Clad.E4.R1.B6.cut 
10/12/1999 10:08a 2,777,854 Steel.Clad.E6.R1.B6.cut

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page VIII-7 of VIII-22 
Attachment VIII - List of Files on Disk 1 (Continued) 
10/12/1999 10:12a 2,782,306 Steel.Clad.E8.R1.B6.cut 
10/12/1999 09:58a 2,810,058 Steel.Clad.E2.R1.B7.cut 
10/12/1999 10:03a 2,816,663 Steel.Clad.E4.R1.B7.cut 
10/12/1999 10:08a 2,815,490 Steel.Clad.E6.R1.B7.cut 
10/12/1999 10:13a 2,816,363 Steel.Clad.E8.R1.B7.cut 
10/12/1999 09:58a 2,493,876 Steel.Clad.E2.R1.B4.cut 
10/12/1999 09:58a 2,852,681 Steel.Clad.E2.R1.B8.cut 
10/12/1999 10:02a 2,493,633 Steel.Clad.E4.R1.B4.cut 
10/12/1999 10:03a 2,850,029 Steel.Clad.E4.R1.B8.cut 
10/12/1999 10:08a 2,496,875 Steel.Clad.E6.R1.B4.cut 
10/12/1999 10:08a 2,848,333 Steel.Clad.E6.R1.B8.cut 
10/12/1999 10:12a 2,500,306 Steel.Clad.E8.R1.B4.cut 
10/12/1999 10:13a 2,852,939 Steel.Clad.E8.R1.B8.cut 
10/12/1999 09:58a 2,699,293 Steel.Clad.E2.R1.B5.cut 
10/12/1999 10:02a 2,698,850 Steel.Clad.E4.R1.B5.cut 
10/12/1999 10:08a 2,700,978 Steel.Clad.E6.R1.B5.cut 
10/12/1999 10:13a 2,472,647 Steel.Clad.E8.R3.B5.cut 
10/12/1999 09:59a 2,536,008 Steel.Clad.E2.R3.B6.cut 
10/12/1999 10:04a 2,537,920 Steel.Clad.E4.R3.B6.cut 
10/12/1999 10:09a 2,542,264 Steel.Clad.E6.R3.B6.cut 
10/12/1999 10:13a 2,546,086 Steel.Clad.E8.R3.B6.cut 
10/12/1999 09:59a 2,571,438 Steel.Clad.E2.R3.B7.cut 
10/12/1999 10:04a 2,576,427 Steel.Clad.E4.R3.B7.cut 
10/12/1999 10:09a 2,574,500 Steel.Clad.E6.R3.B7.cut 
10/12/1999 10:14a 2,576,923 Steel.Clad.E8.R3.B7.cut 
10/12/1999 09:59a 2,288,298 Steel.Clad.E2.R3.B4.cut 
10/12/1999 10:00a 2,608,519 Steel.Clad.E2.R3.B8.cut 
10/12/1999 10:03a 2,287,685 Steel.Clad.E4.R3.B4.cut 
10/12/1999 10:04a 2,609,864 Steel.Clad.E4.R3.B8.cut 
10/12/1999 10:09a 2,284,955 Steel.Clad.E6.R3.B4.cut 
10/12/1999 10:09a 2,608,262 Steel.Clad.E6.R3.B8.cut 
10/12/1999 10:13a 2,290,742 Steel.Clad.E8.R3.B4.cut 
10/12/1999 10:14a 2,606,967 Steel.Clad.E8.R3.B8.cut 
10/12/1999 09:59a 2,469,203 Steel.Clad.E2.R3.B5.cut 
10/12/1999 10:03a 2,469,999 Steel.Clad.E4.R3.B5.cut 
10/12/1999 10:09a 2,471,880 Steel.Clad.E6.R3.B5.cut 
10/12/1999 09:51a 2,494,355 Steel.Clad.E1.R1.B4.cut 
10/12/1999 09:52a 2,698,260 Steel.Clad.E1.R1.B5.cut 
10/12/1999 09:52a 2,764,210 Steel.Clad.E1.R1.B6.cut 
10/12/1999 09:52a 2,812,099 Steel.Clad.E1.R1.B7.cut 
110 File(s) 287,487,993 bytes 
Directory of D:\UNIX-script files 
05/04/2004 11:22a <DIR> . 
05/04/2004 11:22a <DIR> .. 
10/12/1999 12:45p 261 curies 
02/27/2003 08:37a 177 cut-script 
10/12/1999 12:45p 177 gammas 
10/12/1999 12:45p 158 neutrons 
10/12/1999 12:47p 268 watts 
5 File(s) 1,041 bytes 
Total Files Listed: 
302 File(s) 718,893,946 bytes 
15 Dir(s) 0 bytes free

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page VIII-8 of VIII-22 
Attachment VIII - List of Files on Disk 2 
Volume in drive D is PWR ST G&E 
Volume Serial Number is 2154-7748 
Directory of D:\ 
04/20/2004 11:49a <DIR> Waste Stream 1 
0 File(s) 0 bytes 
Directory of D:\Waste Stream 1 
04/20/2004 11:49a <DIR> . 
04/20/2004 11:49a <DIR> .. 
10/12/1999 10:44a 2,672,362 Waste.Stream.E11.R2.B10.cut 
02/21/2003 10:03a 2,727,688 Waste.Stream.E11.R2.B14.cut 
10/12/1999 10:32a 2,672,723 Waste.Stream.E10.R2.B10.cut 
02/21/2003 10:01a 2,725,235 Waste.Stream.E10.R2.B14.cut 
10/12/1999 10:56a 2,673,941 Waste.Stream.E12.R2.B10.cut 
02/21/2003 10:04a 2,726,251 Waste.Stream.E12.R2.B14.cut 
10/12/1999 10:47a 2,667,944 Waste.Stream.E11.R3.B10.cut 
02/21/2003 10:03a 2,730,244 Waste.Stream.E11.R3.B14.cut 
10/12/1999 10:35a 2,668,171 Waste.Stream.E10.R3.B10.cut 
02/21/2003 10:01a 2,727,657 Waste.Stream.E10.R3.B14.cut 
10/12/1999 10:59a 2,671,765 Waste.Stream.E12.R3.B10.cut 
02/21/2003 10:04a 2,728,673 Waste.Stream.E12.R3.B14.cut 
10/12/1999 10:50a 2,618,552 Waste.Stream.E11.R4.B10.cut 
02/21/2003 10:03a 2,676,120 Waste.Stream.E11.R4.B14.cut 
10/12/1999 10:38a 2,619,037 Waste.Stream.E10.R4.B10.cut 
02/21/2003 10:01a 2,674,039 Waste.Stream.E10.R4.B14.cut 
10/12/1999 11:02a 2,622,373 Waste.Stream.E12.R4.B10.cut 
02/21/2003 10:04a 2,674,549 Waste.Stream.E12.R4.B14.cut 
10/12/1999 10:41a 2,927,839 Waste.Stream.E11.R1.B11.cut 
02/21/2003 10:02a 2,966,957 Waste.Stream.E11.R1.B15.cut 
10/12/1999 10:29a 2,927,543 Waste.Stream.E10.R1.B11.cut 
02/21/2003 10:00a 2,966,456 Waste.Stream.E10.R1.B15.cut 
10/12/1999 10:21a 2,210,392 Waste.Stream.E1.R2.B3.cut 
10/12/1999 10:24a 2,195,502 Waste.Stream.E1.R3.B3.cut 
10/12/1999 10:27a 2,156,972 Waste.Stream.E1.R4.B3.cut 
10/12/1999 10:22a 2,615,464 Waste.Stream.E1.R2.B7.cut 
10/12/1999 10:25a 2,614,106 Waste.Stream.E1.R3.B7.cut 
10/12/1999 10:28a 2,569,124 Waste.Stream.E1.R4.B7.cut 
10/12/1999 10:53a 2,927,141 Waste.Stream.E12.R1.B11.cut 
02/21/2003 10:04a 2,963,837 Waste.Stream.E12.R1.B15.cut 
10/12/1999 10:44a 2,699,067 Waste.Stream.E11.R2.B11.cut 
02/21/2003 10:03a 2,730,561 Waste.Stream.E11.R2.B15.cut 
10/12/1999 10:32a 2,701,013 Waste.Stream.E10.R2.B11.cut 
02/21/2003 10:01a 2,732,426 Waste.Stream.E10.R2.B15.cut 
10/12/1999 10:56a 2,698,199 Waste.Stream.E12.R2.B11.cut 
02/21/2003 10:04a 2,729,187 Waste.Stream.E12.R2.B15.cut 
10/12/1999 09:47a 2,697,129 Waste.Stream.E11.R3.B11.cut 
02/21/2003 10:03a 2,732,983 Waste.Stream.E11.R3.B15.cut 
10/12/1999 10:35a 2,698,703 Waste.Stream.E10.R3.B11.cut 
02/21/2003 10:01a 2,734,848 Waste.Stream.E10.R3.B15.cut 
10/12/1999 10:59a 2,698,503 Waste.Stream.E12.R3.B11.cut 
02/21/2003 10:04a 2,731,609 Waste.Stream.E12.R3.B15.cut 
10/12/1999 10:50a 2,647,499 Waste.Stream.E11.R4.B11.cut 
02/21/2003 10:03a 2,678,859 Waste.Stream.E11.R4.B15.cut 
10/12/1999 10:38a 2,649,569 Waste.Stream.E10.R4.B11.cut 
02/21/2003 10:01a 2,680,848 Waste.Stream.E10.R4.B15.cut 
10/12/1999 11:02a 2,648,997 Waste.Stream.E12.R4.B11.cut

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page VIII-9 of VIII-22 
Attachment VIII - List of Files on Disk 2 (Continued) 
02/21/2003 10:04a 2,677,609 Waste.Stream.E12.R4.B15.cut 
10/12/1999 10:41a 2,938,848 Waste.Stream.E11.R1.B12.cut 
10/12/1999 10:29a 2,942,160 Waste.Stream.E10.R1.B12.cut 
10/12/1999 10:21a 2,325,962 Waste.Stream.E1.R2.B4.cut 
10/12/1999 10:24a 2,327,292 Waste.Stream.E1.R3.B4.cut 
10/12/1999 10:27a 2,286,676 Waste.Stream.E1.R4.B4.cut 
10/12/1999 10:22a 2,650,067 Waste.Stream.E1.R2.B8.cut 
10/12/1999 10:25a 2,647,345 Waste.Stream.E1.R3.B8.cut 
10/12/1999 10:28a 2,596,887 Waste.Stream.E1.R4.B8.cut 
10/12/1999 10:54a 2,939,975 Waste.Stream.E12.R1.B12.cut 
10/12/1999 10:45a 2,710,830 Waste.Stream.E11.R2.B12.cut 
10/12/1999 10:32a 2,712,644 Waste.Stream.E10.R2.B12.cut 
10/12/1999 10:57a 2,709,323 Waste.Stream.E12.R2.B12.cut 
10/12/1999 10:48a 2,709,512 Waste.Stream.E11.R3.B12.cut 
10/12/1999 10:35a 2,713,072 Waste.Stream.E10.R3.B12.cut 
10/12/1999 10:59a 2,709,503 Waste.Stream.E12.R3.B12.cut 
10/12/1999 10:51a 2,659,510 Waste.Stream.E11.R4.B12.cut 
10/12/1999 10:38a 2,663,070 Waste.Stream.E10.R4.B12.cut 
10/12/1999 11:02a 2,658,003 Waste.Stream.E12.R4.B12.cut 
10/12/1999 10:42a 2,951,704 Waste.Stream.E11.R1.B13.cut 
10/12/1999 10:29a 2,952,395 Waste.Stream.E10.R1.B13.cut 
10/12/1999 10:20a 2,033,682 Waste.Stream.E1.R2.B1.cut 
10/12/1999 10:23a 2,022,398 Waste.Stream.E1.R3.B1.cut 
10/12/1999 10:26a 1,986,718 Waste.Stream.E1.R4.B1.cut 
10/12/1999 10:22a 2,510,288 Waste.Stream.E1.R2.B5.cut 
10/12/1999 10:25a 2,505,418 Waste.Stream.E1.R3.B5.cut 
10/12/1999 10:27a 2,470,228 Waste.Stream.E1.R4.B5.cut 
10/12/1999 10:23a 2,660,542 Waste.Stream.E1.R2.B9.cut 
10/12/1999 10:26a 2,660,816 Waste.Stream.E1.R3.B9.cut 
10/12/1999 10:28a 2,612,104 Waste.Stream.E1.R4.B9.cut 
10/12/1999 10:54a 2,949,586 Waste.Stream.E12.R1.B13.cut 
10/12/1999 10:45a 2,718,686 Waste.Stream.E11.R2.B13.cut 
10/12/1999 10:32a 2,720,007 Waste.Stream.E10.R2.B13.cut 
10/12/1999 10:57a 2,716,816 Waste.Stream.E12.R2.B13.cut 
10/12/1999 10:48a 2,718,866 Waste.Stream.E11.R3.B13.cut 
10/12/1999 10:35a 2,718,937 Waste.Stream.E10.R3.B13.cut 
10/12/1999 11:00a 2,719,362 Waste.Stream.E12.R3.B13.cut 
10/12/1999 10:51a 2,667,366 Waste.Stream.E11.R4.B13.cut 
10/12/1999 10:38a 2,668,811 Waste.Stream.E10.R4.B13.cut 
10/12/1999 11:03a 2,665,496 Waste.Stream.E12.R4.B13.cut 
10/12/1999 10:41a 2,896,144 Waste.Stream.E11.R1.B10.cut 
02/21/2003 10:01a 2,959,610 Waste.Stream.E11.R1.B14.cut 
10/12/1999 10:28a 2,896,009 Waste.Stream.E10.R1.B10.cut 
02/21/2003 10:00a 2,958,253 Waste.Stream.E10.R1.B14.cut 
10/12/1999 10:21a 2,096,750 Waste.Stream.E1.R2.B2.cut 
10/12/1999 10:24a 2,087,832 Waste.Stream.E1.R3.B2.cut 
10/12/1999 10:27a 2,050,890 Waste.Stream.E1.R4.B2.cut 
10/12/1999 10:22a 2,574,106 Waste.Stream.E1.R2.B6.cut 
10/12/1999 10:25a 2,572,604 Waste.Stream.E1.R3.B6.cut 
10/12/1999 10:28a 2,530,410 Waste.Stream.E1.R4.B6.cut 
10/12/1999 10:53a 2,897,971 Waste.Stream.E12.R1.B10.cut 
02/21/2003 10:04a 2,960,033 Waste.Stream.E12.R1.B14.cut 
10/12/1999 10:57a 2,206,154 Waste.Stream.E12.R2.B3.cut 
10/12/1999 10:32a 2,087,907 Waste.Stream.E10.R2.B2.cut 
10/12/1999 10:57a 2,080,954 Waste.Stream.E12.R2.B2.cut 
10/12/1999 10:33a 2,213,316 Waste.Stream.E10.R2.B3.cut 
10/12/1999 10:56a 2,014,074 Waste.Stream.E12.R2.B1.cut 
10/12/1999 10:31a 2,022,505 Waste.Stream.E10.R2.B1.cut

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page VIII-10 of VIII-22 
Attachment VIII - List of Files on Disk 2 (Continued) 
10/12/1999 10:45a 2,086,669 Waste.Stream.E11.R2.B2.cut 
10/12/1999 10:45a 2,211,617 Waste.Stream.E11.R2.B3.cut 
10/12/1999 10:44a 2,020,769 Waste.Stream.E11.R2.B1.cut 
10/12/1999 11:00a 2,200,986 Waste.Stream.E12.R3.B3.cut 
10/12/1999 10:36a 2,079,381 Waste.Stream.E10.R3.B2.cut 
10/12/1999 11:00a 2,072,820 Waste.Stream.E12.R3.B2.cut 
10/12/1999 10:36a 2,201,526 Waste.Stream.E10.R3.B3.cut 
10/12/1999 10:59a 2,004,650 Waste.Stream.E12.R3.B1.cut 
10/12/1999 10:34a 2,008,493 Waste.Stream.E10.R3.B1.cut 
10/12/1999 10:48a 2,078,535 Waste.Stream.E11.R3.B2.cut 
10/12/1999 10:48a 2,202,689 Waste.Stream.E11.R3.B3.cut 
10/12/1999 10:47a 2,005,765 Waste.Stream.E11.R3.B1.cut 
10/12/1999 11:03a 2,165,382 Waste.Stream.E12.R4.B3.cut 
10/12/1999 10:39a 2,041,913 Waste.Stream.E10.R4.B2.cut 
10/12/1999 11:03a 2,033,224 Waste.Stream.E12.R4.B2.cut 
10/12/1999 10:39a 2,162,320 Waste.Stream.E10.R4.B3.cut 
10/12/1999 11:02a 1,967,234 Waste.Stream.E12.R4.B1.cut 
10/12/1999 10:37a 1,975,665 Waste.Stream.E10.R4.B1.cut 
10/12/1999 10:51a 2,038,805 Waste.Stream.E11.R4.B2.cut 
10/12/1999 10:51a 2,169,521 Waste.Stream.E11.R4.B3.cut 
10/12/1999 10:50a 1,974,301 Waste.Stream.E11.R4.B1.cut 
10/12/1999 10:26a 2,630,797 Waste.Stream.E1.R4.B11.cut 
10/12/1999 10:20a 2,672,150 Waste.Stream.E1.R2.B10.cut 
10/12/1999 10:23a 2,668,426 Waste.Stream.E1.R3.B10.cut 
10/12/1999 10:26a 2,619,466 Waste.Stream.E1.R4.B10.cut 
10/12/1999 10:20a 2,683,853 Waste.Stream.E1.R2.B11.cut 
10/12/1999 10:23a 2,683,011 Waste.Stream.E1.R3.B11.cut 
10/12/1999 10:54a 2,369,702 Waste.Stream.E12.R1.B3.cut 
10/12/1999 10:29a 2,242,511 Waste.Stream.E10.R1.B2.cut 
10/12/1999 10:54a 2,239,729 Waste.Stream.E12.R1.B2.cut 
10/12/1999 10:29a 2,375,128 Waste.Stream.E10.R1.B3.cut 
10/12/1999 10:53a 2,148,686 Waste.Stream.E12.R1.B1.cut 
10/12/1999 10:28a 2,155,009 Waste.Stream.E10.R1.B1.cut 
10/12/1999 10:42a 2,244,135 Waste.Stream.E11.R1.B2.cut 
10/12/1999 10:42a 2,374,287 Waste.Stream.E11.R1.B3.cut 
10/12/1999 10:41a 2,154,885 Waste.Stream.E11.R1.B1.cut 
10/12/1999 10:58a 2,618,022 Waste.Stream.E12.R2.B7.cut 
10/12/1999 10:33a 2,583,981 Waste.Stream.E10.R2.B6.cut 
10/12/1999 10:58a 2,585,801 Waste.Stream.E12.R2.B6.cut 
10/12/1999 10:33a 2,612,294 Waste.Stream.E10.R2.B7.cut 
10/12/1999 10:58a 2,536,272 Waste.Stream.E12.R2.B5.cut 
10/12/1999 10:33a 2,333,159 Waste.Stream.E10.R2.B4.cut 
10/12/1999 10:58a 2,345,297 Waste.Stream.E12.R2.B4.cut 
10/12/1999 10:33a 2,518,820 Waste.Stream.E10.R2.B5.cut 
10/12/1999 10:46a 2,585,869 Waste.Stream.E11.R2.B6.cut 
10/12/1999 10:46a 2,617,985 Waste.Stream.E11.R2.B7.cut 
10/12/1999 10:45a 2,336,911 Waste.Stream.E11.R2.B4.cut 
10/12/1999 10:46a 2,529,863 Waste.Stream.E11.R2.B5.cut 
10/12/1999 11:01a 2,617,190 Waste.Stream.E12.R3.B7.cut 
10/12/1999 10:36a 2,583,263 Waste.Stream.E10.R3.B6.cut 
10/12/1999 11:01a 2,587,945 Waste.Stream.E12.R3.B6.cut 
10/12/1999 10:37a 2,610,336 Waste.Stream.E10.R3.B7.cut 
10/12/1999 11:01a 2,534,532 Waste.Stream.E12.R3.B5.cut 
10/12/1999 10:36a 2,334,653 Waste.Stream.E10.R3.B4.cut 
10/12/1999 11:00a 2,343,691 Waste.Stream.E12.R3.B4.cut 
10/12/1999 10:36a 2,513,722 Waste.Stream.E10.R3.B5.cut 
10/12/1999 10:49a 2,587,651 Waste.Stream.E11.R3.B6.cut 
10/12/1999 10:49a 2,616,389 Waste.Stream.E11.R3.B7.cut

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page VIII-11 of VIII-22 
Attachment VIII - List of Files on Disk 2 (Continued) 
10/12/1999 10:48a 2,339,159 Waste.Stream.E11.R3.B4.cut 
10/12/1999 10:49a 2,528,474 Waste.Stream.E11.R3.B5.cut 
10/12/1999 11:04a 2,567,198 Waste.Stream.E12.R4.B7.cut 
10/12/1999 10:40a 2,535,389 Waste.Stream.E10.R4.B6.cut 
10/12/1999 11:03a 2,537,601 Waste.Stream.E12.R4.B6.cut 
10/12/1999 10:40a 2,557,244 Waste.Stream.E10.R4.B7.cut 
10/12/1999 11:03a 2,489,828 Waste.Stream.E12.R4.B5.cut 
10/12/1999 10:39a 2,292,395 Waste.Stream.E10.R4.B4.cut 
10/12/1999 11:03a 2,296,805 Waste.Stream.E12.R4.B4.cut 
10/12/1999 10:39a 2,473,388 Waste.Stream.E10.R4.B5.cut 
10/12/1999 10:52a 2,537,163 Waste.Stream.E11.R4.B6.cut 
10/12/1999 10:52a 2,562,801 Waste.Stream.E11.R4.B7.cut 
10/12/1999 10:51a 2,292,283 Waste.Stream.E11.R4.B4.cut 
10/12/1999 10:52a 2,483,771 Waste.Stream.E11.R4.B5.cut 
02/21/2003 09:32a 2,692,754 Waste.Stream.E1.R4.B15.cut 
02/21/2003 09:31a 2,970,222 Waste.Stream.E1.R1.B15.cut 
02/21/2003 09:31a 2,732,909 Waste.Stream.E1.R2.B14.cut 
02/21/2003 09:32a 2,728,223 Waste.Stream.E1.R3.B14.cut 
02/21/2003 09:32a 2,681,093 Waste.Stream.E1.R4.B14.cut 
02/21/2003 09:31a 2,744,446 Waste.Stream.E1.R2.B15.cut 
02/21/2003 09:32a 2,744,244 Waste.Stream.E1.R3.B15.cut 
10/12/1999 10:26a 2,664,388 Waste.Stream.E1.R4.B13.cut 
10/12/1999 10:18a 2,941,608 Waste.Stream.E1.R1.B13.cut 
10/12/1999 10:21a 2,712,942 Waste.Stream.E1.R2.B12.cut 
10/12/1999 10:24a 2,707,864 Waste.Stream.E1.R3.B12.cut 
10/12/1999 10:26a 2,659,876 Waste.Stream.E1.R4.B12.cut 
02/21/2003 09:31a 2,954,087 Waste.Stream.E1.R1.B14.cut 
10/12/1999 10:21a 2,717,950 Waste.Stream.E1.R2.B13.cut 
10/12/1999 10:24a 2,713,140 Waste.Stream.E1.R3.B13.cut 
10/12/1999 10:55a 2,837,832 Waste.Stream.E12.R1.B7.cut 
10/12/1999 10:30a 2,794,671 Waste.Stream.E10.R1.B6.cut 
10/12/1999 10:55a 2,804,159 Waste.Stream.E12.R1.B6.cut 
10/12/1999 10:31a 2,830,968 Waste.Stream.E10.R1.B7.cut 
10/12/1999 10:55a 2,745,000 Waste.Stream.E12.R1.B5.cut 
10/12/1999 10:30a 2,515,615 Waste.Stream.E10.R1.B4.cut 
10/12/1999 10:54a 2,523,507 Waste.Stream.E12.R1.B4.cut 
10/12/1999 10:30a 2,719,618 Waste.Stream.E10.R1.B5.cut 
10/12/1999 10:43a 2,801,077 Waste.Stream.E11.R1.B6.cut 
10/12/1999 10:43a 2,837,041 Waste.Stream.E11.R1.B7.cut 
10/12/1999 10:42a 2,516,381 Waste.Stream.E11.R1.B4.cut 
10/12/1999 10:42a 2,735,903 Waste.Stream.E11.R1.B5.cut 
10/12/1999 10:58a 2,667,431 Waste.Stream.E12.R2.B9.cut 
10/12/1999 10:34a 2,642,893 Waste.Stream.E10.R2.B8.cut 
10/12/1999 10:58a 2,646,398 Waste.Stream.E12.R2.B8.cut 
10/12/1999 10:34a 2,665,243 Waste.Stream.E10.R2.B9.cut 
10/12/1999 10:46a 2,649,344 Waste.Stream.E11.R2.B8.cut 
10/12/1999 10:47a 2,665,392 Waste.Stream.E11.R2.B9.cut 
10/12/1999 11:02a 2,663,013 Waste.Stream.E12.R3.B9.cut 
10/12/1999 10:37a 2,640,067 Waste.Stream.E10.R3.B8.cut 
10/12/1999 11:01a 2,646,320 Waste.Stream.E12.R3.B8.cut 
10/12/1999 10:37a 2,662,799 Waste.Stream.E10.R3.B9.cut 
10/12/1999 10:49a 2,644,276 Waste.Stream.E11.R3.B8.cut 
10/12/1999 10:50a 2,660,726 Waste.Stream.E11.R3.B9.cut 
10/12/1999 11:04a 2,613,621 Waste.Stream.E12.R4.B9.cut 
10/12/1999 10:40a 2,593,939 Waste.Stream.E10.R4.B8.cut 
10/12/1999 11:04a 2,595,326 Waste.Stream.E12.R4.B8.cut 
10/12/1999 10:40a 2,611,805 Waste.Stream.E10.R4.B9.cut 
10/12/1999 10:52a 2,598,396 Waste.Stream.E11.R4.B8.cut

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page VIII-12 of VIII-22 
Attachment VIII - List of Files on Disk 2 (Continued) 
10/12/1999 10:53a 2,611,582 Waste.Stream.E11.R4.B9.cut 
10/12/1999 10:56a 2,891,213 Waste.Stream.E12.R1.B9.cut 
10/12/1999 10:31a 2,860,347 Waste.Stream.E10.R1.B8.cut 
10/12/1999 10:56a 2,868,608 Waste.Stream.E12.R1.B8.cut 
10/12/1999 10:31a 2,885,831 Waste.Stream.E10.R1.B9.cut 
10/12/1999 10:43a 2,870,934 Waste.Stream.E11.R1.B8.cut 
10/12/1999 10:44a 2,889,050 Waste.Stream.E11.R1.B9.cut 
10/12/1999 10:18a 2,373,785 Waste.Stream.E1.R1.B3.cut 
10/12/1999 10:19a 2,827,528 Waste.Stream.E1.R1.B7.cut 
10/12/1999 10:18a 2,498,066 Waste.Stream.E1.R1.B4.cut 
10/12/1999 10:19a 2,868,215 Waste.Stream.E1.R1.B8.cut 
10/12/1999 10:19a 2,706,428 Waste.Stream.E1.R1.B5.cut 
10/12/1999 10:20a 2,877,088 Waste.Stream.E1.R1.B9.cut 
10/12/1999 10:18a 2,246,240 Waste.Stream.E1.R1.B2.cut 
10/12/1999 10:19a 2,774,905 Waste.Stream.E1.R1.B6.cut 
10/12/1999 10:17a 2,166,186 Waste.Stream.E1.R1.B1.cut 
10/12/1999 10:17a 2,884,708 Waste.Stream.E1.R1.B10.cut 
10/12/1999 10:17a 2,899,303 Waste.Stream.E1.R1.B11.cut 
10/12/1999 10:17a 2,935,846 Waste.Stream.E1.R1.B12.cut 
240 File(s) 616,344,248 bytes 
Total Files Listed: 
240 File(s) 616,344,248 bytes 
3 Dir(s) 0 bytes free

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page VIII-13 of VIII-22 
Attachment VIII - List of Files on Disk 3 
Volume in drive D is PWR ST G&E 
Volume Serial Number is FF5B-4533 
Directory of D:\ 
04/20/2004 12:06p <DIR> Waste Stream 2 
0 File(s) 0 bytes 
Directory of D:\Waste Stream 2 
04/20/2004 12:06p <DIR> . 
04/20/2004 12:06p <DIR> .. 
10/12/1999 11:22a 2,093,522 Waste.Stream.E3.R2.B2.cut 
10/12/1999 11:25a 2,084,604 Waste.Stream.E3.R3.B2.cut 
10/12/1999 11:28a 2,047,662 Waste.Stream.E3.R4.B2.cut 
10/12/1999 11:23a 2,578,534 Waste.Stream.E3.R2.B6.cut 
10/12/1999 11:26a 2,577,032 Waste.Stream.E3.R3.B6.cut 
10/12/1999 11:29a 2,535,086 Waste.Stream.E3.R4.B6.cut 
10/12/1999 10:47a 2,089,658 Waste.Stream.E5.R2.B2.cut 
10/12/1999 10:50a 2,080,750 Waste.Stream.E5.R3.B2.cut 
10/12/1999 10:53a 2,043,798 Waste.Stream.E5.R4.B2.cut 
10/12/1999 10:48a 2,579,133 Waste.Stream.E5.R2.B6.cut 
10/12/1999 10:51a 2,577,507 Waste.Stream.E5.R3.B6.cut 
10/12/1999 10:54a 2,535,437 Waste.Stream.E5.R4.B6.cut 
10/12/1999 11:22a 2,208,810 Waste.Stream.E3.R2.B3.cut 
10/12/1999 11:25a 2,194,054 Waste.Stream.E3.R3.B3.cut 
10/12/1999 11:28a 2,155,142 Waste.Stream.E3.R4.B3.cut 
10/12/1999 11:23a 2,615,426 Waste.Stream.E3.R2.B7.cut 
10/12/1999 11:26a 2,614,450 Waste.Stream.E3.R3.B7.cut 
10/12/1999 11:29a 2,566,730 Waste.Stream.E3.R4.B7.cut 
10/12/1999 10:47a 2,205,701 Waste.Stream.E5.R2.B3.cut 
10/12/1999 10:50a 2,193,187 Waste.Stream.E5.R3.B3.cut 
10/12/1999 10:53a 2,152,167 Waste.Stream.E5.R4.B3.cut 
10/12/1999 10:48a 2,615,502 Waste.Stream.E5.R2.B7.cut 
10/12/1999 10:51a 2,614,402 Waste.Stream.E5.R3.B7.cut 
10/12/1999 10:54a 2,566,806 Waste.Stream.E5.R4.B7.cut 
10/12/1999 11:22a 2,323,496 Waste.Stream.E3.R2.B4.cut 
10/12/1999 11:25a 2,325,074 Waste.Stream.E3.R3.B4.cut 
10/12/1999 11:28a 2,284,086 Waste.Stream.E3.R4.B4.cut 
10/12/1999 11:23a 2,644,965 Waste.Stream.E3.R2.B8.cut 
10/12/1999 11:26a 2,644,733 Waste.Stream.E3.R3.B8.cut 
10/12/1999 11:29a 2,594,161 Waste.Stream.E3.R4.B8.cut 
10/12/1999 10:47a 2,323,628 Waste.Stream.E5.R2.B4.cut 
10/12/1999 10:51a 2,321,590 Waste.Stream.E5.R3.B4.cut 
10/12/1999 10:53a 2,280,354 Waste.Stream.E5.R4.B4.cut 
10/12/1999 10:49a 2,646,508 Waste.Stream.E5.R2.B8.cut 
10/12/1999 10:51a 2,646,906 Waste.Stream.E5.R3.B8.cut 
10/12/1999 10:55a 2,593,958 Waste.Stream.E5.R4.B8.cut 
10/12/1999 11:21a 2,031,326 Waste.Stream.E3.R2.B1.cut 
10/12/1999 11:24a 2,019,918 Waste.Stream.E3.R3.B1.cut 
10/12/1999 11:27a 1,984,362 Waste.Stream.E3.R4.B1.cut 
10/12/1999 11:22a 2,512,092 Waste.Stream.E3.R2.B5.cut 
10/12/1999 11:25a 2,504,856 Waste.Stream.E3.R3.B5.cut 
10/12/1999 11:29a 2,469,790 Waste.Stream.E3.R4.B5.cut 
10/12/1999 11:23a 2,666,260 Waste.Stream.E3.R2.B9.cut 
10/12/1999 11:26a 2,662,288 Waste.Stream.E3.R3.B9.cut 
10/12/1999 11:30a 2,613,204 Waste.Stream.E3.R4.B9.cut

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page VIII-14 of VIII-22 
Attachment VIII - List of Files on Disk 3 (Continued) 
10/12/1999 10:45a 2,027,359 Waste.Stream.E5.R2.B1.cut 
10/12/1999 10:49a 2,015,951 Waste.Stream.E5.R3.B1.cut 
10/12/1999 10:52a 1,982,379 Waste.Stream.E5.R4.B1.cut 
10/12/1999 10:48a 2,512,972 Waste.Stream.E5.R2.B5.cut 
10/12/1999 10:51a 2,507,596 Waste.Stream.E5.R3.B5.cut 
10/12/1999 10:54a 2,470,288 Waste.Stream.E5.R4.B5.cut 
10/12/1999 10:49a 2,663,102 Waste.Stream.E5.R2.B9.cut 
10/12/1999 10:52a 2,659,760 Waste.Stream.E5.R3.B9.cut 
10/12/1999 10:55a 2,610,542 Waste.Stream.E5.R4.B9.cut 
10/12/1999 11:14a 2,634,257 Waste.Stream.E2.R4.B11.cut 
10/12/1999 11:05a 2,905,223 Waste.Stream.E2.R1.B11.cut 
10/12/1999 11:08a 2,672,389 Waste.Stream.E2.R2.B10.cut 
10/12/1999 11:11a 2,668,541 Waste.Stream.E2.R3.B10.cut 
10/12/1999 11:14a 2,619,581 Waste.Stream.E2.R4.B10.cut 
10/12/1999 11:06a 2,936,479 Waste.Stream.E2.R1.B12.cut 
10/12/1999 11:09a 2,684,947 Waste.Stream.E2.R2.B11.cut 
10/12/1999 11:11a 2,684,105 Waste.Stream.E2.R3.B11.cut 
10/12/1999 11:05a 2,884,833 Waste.Stream.E2.R1.B10.cut 
10/12/1999 11:39a 2,641,780 Waste.Stream.E4.R4.B11.cut 
10/12/1999 11:30a 2,916,426 Waste.Stream.E4.R1.B11.cut 
10/12/1999 11:33a 2,665,578 Waste.Stream.E4.R2.B10.cut 
10/12/1999 11:36a 2,661,998 Waste.Stream.E4.R3.B10.cut 
10/12/1999 11:39a 2,612,646 Waste.Stream.E4.R4.B10.cut 
10/12/1999 11:31a 2,937,670 Waste.Stream.E4.R1.B12.cut 
10/12/1999 11:34a 2,692,728 Waste.Stream.E4.R2.B11.cut 
10/12/1999 11:36a 2,692,000 Waste.Stream.E4.R3.B11.cut 
10/12/1999 11:30a 2,880,646 Waste.Stream.E4.R1.B10.cut 
02/21/2003 09:37a 2,695,546 Waste.Stream.E2.R4.B15.cut 
02/21/2003 09:35a 2,971,888 Waste.Stream.E2.R1.B15.cut 
02/21/2003 09:36a 2,739,635 Waste.Stream.E2.R2.B14.cut 
02/21/2003 09:36a 2,734,825 Waste.Stream.E2.R3.B14.cut 
02/21/2003 09:37a 2,687,943 Waste.Stream.E2.R4.B14.cut 
02/21/2003 09:36a 2,744,872 Waste.Stream.E2.R2.B15.cut 
02/21/2003 09:37a 2,745,166 Waste.Stream.E2.R3.B15.cut 
10/12/1999 11:15a 2,671,260 Waste.Stream.E2.R4.B13.cut 
10/12/1999 11:06a 2,946,734 Waste.Stream.E2.R1.B13.cut 
10/12/1999 11:09a 2,713,317 Waste.Stream.E2.R2.B12.cut 
10/12/1999 11:11a 2,708,249 Waste.Stream.E2.R3.B12.cut 
10/12/1999 11:15a 2,659,879 Waste.Stream.E2.R4.B12.cut 
02/21/2003 09:35a 2,964,171 Waste.Stream.E2.R1.B14.cut 
10/12/1999 11:09a 2,725,318 Waste.Stream.E2.R2.B13.cut 
10/12/1999 11:12a 2,718,266 Waste.Stream.E2.R3.B13.cut 
02/21/2003 09:42a 2,697,920 Waste.Stream.E4.R4.B15.cut 
02/21/2003 09:41a 2,977,134 Waste.Stream.E4.R1.B15.cut 
02/21/2003 09:42a 2,741,642 Waste.Stream.E4.R2.B14.cut 
02/21/2003 09:42a 2,741,440 Waste.Stream.E4.R3.B14.cut 
02/21/2003 09:42a 2,692,192 Waste.Stream.E4.R4.B14.cut 
02/21/2003 09:42a 2,747,246 Waste.Stream.E4.R2.B15.cut 
02/21/2003 09:42a 2,747,416 Waste.Stream.E4.R3.B15.cut 
10/12/1999 11:40a 2,682,862 Waste.Stream.E4.R4.B13.cut 
10/12/1999 11:31a 2,959,090 Waste.Stream.E4.R1.B13.cut 
10/12/1999 11:34a 2,716,006 Waste.Stream.E4.R2.B12.cut 
10/12/1999 11:36a 2,708,954 Waste.Stream.E4.R3.B12.cut 
10/12/1999 11:40a 2,661,948 Waste.Stream.E4.R4.B12.cut 
02/21/2003 09:41a 2,968,906 Waste.Stream.E4.R1.B14.cut 
10/12/1999 11:34a 2,734,306 Waste.Stream.E4.R2.B13.cut 
10/12/1999 11:37a 2,731,862 Waste.Stream.E4.R3.B13.cut 
10/12/1999 11:31a 2,246,370 Waste.Stream.E4.R1.B2.cut

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page VIII-15 of VIII-22 
Attachment VIII - List of Files on Disk 3 (Continued) 
10/12/1999 11:32a 2,784,956 Waste.Stream.E4.R1.B6.cut 
10/12/1999 11:06a 2,372,432 Waste.Stream.E2.R1.B3.cut 
10/12/1999 11:07a 2,831,234 Waste.Stream.E2.R1.B7.cut 
10/12/1999 11:31a 2,374,591 Waste.Stream.E4.R1.B3.cut 
10/12/1999 11:32a 2,832,380 Waste.Stream.E4.R1.B7.cut 
10/12/1999 11:07a 2,494,583 Waste.Stream.E2.R1.B4.cut 
10/12/1999 11:08a 2,866,618 Waste.Stream.E2.R1.B8.cut 
10/12/1999 11:31a 2,498,222 Waste.Stream.E4.R1.B4.cut 
10/12/1999 11:33a 2,862,692 Waste.Stream.E4.R1.B8.cut 
10/12/1999 11:04a 2,163,086 Waste.Stream.E2.R1.B1.cut 
10/12/1999 11:07a 2,709,321 Waste.Stream.E2.R1.B5.cut 
10/12/1999 11:08a 2,877,537 Waste.Stream.E2.R1.B9.cut 
10/12/1999 11:30a 2,163,335 Waste.Stream.E4.R1.B1.cut 
10/12/1999 11:31a 2,708,645 Waste.Stream.E4.R1.B5.cut 
10/12/1999 11:33a 2,876,021 Waste.Stream.E4.R1.B9.cut 
10/12/1999 11:06a 2,244,256 Waste.Stream.E2.R1.B2.cut 
10/12/1999 11:07a 2,775,360 Waste.Stream.E2.R1.B6.cut 
10/12/1999 11:34a 2,092,892 Waste.Stream.E4.R2.B2.cut 
10/12/1999 11:37a 2,083,984 Waste.Stream.E4.R3.B2.cut 
10/12/1999 11:40a 2,047,032 Waste.Stream.E4.R4.B2.cut 
10/12/1999 11:35a 2,578,762 Waste.Stream.E4.R2.B6.cut 
10/12/1999 11:38a 2,577,012 Waste.Stream.E4.R3.B6.cut 
10/12/1999 11:41a 2,535,066 Waste.Stream.E4.R4.B6.cut 
10/12/1999 11:09a 2,207,540 Waste.Stream.E2.R2.B3.cut 
10/12/1999 11:12a 2,192,784 Waste.Stream.E2.R3.B3.cut 
10/12/1999 11:16a 2,153,872 Waste.Stream.E2.R4.B3.cut 
10/12/1999 11:10a 2,614,176 Waste.Stream.E2.R2.B7.cut 
10/12/1999 11:13a 2,612,808 Waste.Stream.E2.R3.B7.cut 
10/12/1999 11:17a 2,567,454 Waste.Stream.E2.R4.B7.cut 
10/12/1999 11:34a 2,208,945 Waste.Stream.E4.R2.B3.cut 
10/12/1999 11:37a 2,194,189 Waste.Stream.E4.R3.B3.cut 
10/12/1999 11:40a 2,155,411 Waste.Stream.E4.R4.B3.cut 
10/12/1999 11:35a 2,617,440 Waste.Stream.E4.R2.B7.cut 
10/12/1999 11:38a 2,616,340 Waste.Stream.E4.R3.B7.cut 
10/12/1999 11:41a 2,568,744 Waste.Stream.E4.R4.B7.cut 
10/12/1999 11:10a 2,322,107 Waste.Stream.E2.R2.B4.cut 
10/12/1999 11:12a 2,323,685 Waste.Stream.E2.R3.B4.cut 
10/12/1999 11:16a 2,282,697 Waste.Stream.E2.R4.B4.cut 
10/12/1999 11:10a 2,647,518 Waste.Stream.E2.R2.B8.cut 
10/12/1999 11:14a 2,647,286 Waste.Stream.E2.R3.B8.cut 
10/12/1999 11:17a 2,594,338 Waste.Stream.E2.R4.B8.cut 
10/12/1999 11:35a 2,324,496 Waste.Stream.E4.R2.B4.cut 
10/12/1999 11:37a 2,324,700 Waste.Stream.E4.R3.B4.cut 
10/12/1999 11:40a 2,283,588 Waste.Stream.E4.R4.B4.cut 
10/12/1999 11:35a 2,646,136 Waste.Stream.E4.R2.B8.cut 
10/12/1999 11:38a 2,646,658 Waste.Stream.E4.R3.B8.cut 
10/12/1999 11:41a 2,593,710 Waste.Stream.E4.R4.B8.cut 
10/12/1999 11:08a 2,030,334 Waste.Stream.E2.R2.B1.cut 
10/12/1999 11:11a 2,019,050 Waste.Stream.E2.R3.B1.cut 
10/12/1999 11:14a 1,983,370 Waste.Stream.E2.R4.B1.cut 
10/12/1999 11:10a 2,514,401 Waste.Stream.E2.R2.B5.cut 
10/12/1999 11:12a 2,507,165 Waste.Stream.E2.R3.B5.cut 
10/12/1999 11:16a 2,471,851 Waste.Stream.E2.R4.B5.cut 
10/12/1999 11:11a 2,666,849 Waste.Stream.E2.R2.B9.cut 
10/12/1999 11:14a 2,663,125 Waste.Stream.E2.R3.B9.cut 
10/12/1999 11:17a 2,614,165 Waste.Stream.E2.R4.B9.cut 
10/12/1999 11:33a 2,030,583 Waste.Stream.E4.R2.B1.cut 
10/12/1999 11:36a 2,019,175 Waste.Stream.E4.R3.B1.cut

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page VIII-16 of VIII-22 
Attachment VIII - List of Files on Disk 3 (Continued) 
10/12/1999 11:39a 1,983,495 Waste.Stream.E4.R4.B1.cut 
10/12/1999 11:35a 2,512,981 Waste.Stream.E4.R2.B5.cut 
10/12/1999 11:38a 2,507,729 Waste.Stream.E4.R3.B5.cut 
10/12/1999 11:41a 2,470,421 Waste.Stream.E4.R4.B5.cut 
10/12/1999 11:36a 2,661,841 Waste.Stream.E4.R2.B9.cut 
10/12/1999 11:38a 2,658,003 Waste.Stream.E4.R3.B9.cut 
10/12/1999 11:42a 2,609,033 Waste.Stream.E4.R4.B9.cut 
10/12/1999 11:09a 2,093,268 Waste.Stream.E2.R2.B2.cut 
10/12/1999 11:12a 2,084,350 Waste.Stream.E2.R3.B2.cut 
10/12/1999 11:15a 2,047,408 Waste.Stream.E2.R4.B2.cut 
10/12/1999 11:10a 2,573,724 Waste.Stream.E2.R2.B6.cut 
10/12/1999 11:13a 2,572,222 Waste.Stream.E2.R3.B6.cut 
10/12/1999 11:16a 2,530,028 Waste.Stream.E2.R4.B6.cut 
10/12/1999 11:27a 2,640,591 Waste.Stream.E3.R4.B11.cut 
10/12/1999 11:18a 2,914,731 Waste.Stream.E3.R1.B11.cut 
10/12/1999 11:21a 2,669,194 Waste.Stream.E3.R2.B10.cut 
10/12/1999 11:24a 2,665,604 Waste.Stream.E3.R3.B10.cut 
10/12/1999 11:27a 2,616,386 Waste.Stream.E3.R4.B10.cut 
10/12/1999 11:18a 2,937,469 Waste.Stream.E3.R1.B12.cut 
10/12/1999 11:21a 2,691,415 Waste.Stream.E3.R2.B11.cut 
10/12/1999 11:24a 2,690,439 Waste.Stream.E3.R3.B11.cut 
10/12/1999 11:18a 2,883,756 Waste.Stream.E3.R1.B10.cut 
10/12/1999 10:52a 2,641,779 Waste.Stream.E5.R4.B11.cut 
10/12/1999 11:42a 2,917,045 Waste.Stream.E5.R1.B11.cut 
02/26/2003 10:15a 2,666,625 Waste.Stream.E5.R2.B10.cut 
10/12/1999 10:49a 2,663,133 Waste.Stream.E5.R3.B10.cut 
10/12/1999 10:52a 2,613,905 Waste.Stream.E5.R4.B10.cut 
10/12/1999 11:43a 2,942,926 Waste.Stream.E5.R1.B12.cut 
10/12/1999 10:46a 2,694,969 Waste.Stream.E5.R2.B11.cut 
10/12/1999 10:49a 2,692,123 Waste.Stream.E5.R3.B11.cut 
10/12/1999 11:42a 2,883,661 Waste.Stream.E5.R1.B10.cut 
02/21/2003 09:40a 2,697,302 Waste.Stream.E3.R4.B15.cut 
02/21/2003 09:39a 2,974,398 Waste.Stream.E3.R1.B15.cut 
02/21/2003 09:40a 2,739,783 Waste.Stream.E3.R2.B14.cut 
02/21/2003 09:40a 2,739,705 Waste.Stream.E3.R3.B14.cut 
02/21/2003 09:40a 2,690,581 Waste.Stream.E3.R4.B14.cut 
02/21/2003 09:40a 2,746,628 Waste.Stream.E3.R2.B15.cut 
02/21/2003 09:40a 2,746,922 Waste.Stream.E3.R3.B15.cut 
10/12/1999 11:28a 2,681,741 Waste.Stream.E3.R4.B13.cut 
10/12/1999 11:19a 2,959,963 Waste.Stream.E3.R1.B13.cut 
10/12/1999 11:21a 2,715,929 Waste.Stream.E3.R2.B12.cut 
10/12/1999 11:24a 2,708,877 Waste.Stream.E3.R3.B12.cut 
10/12/1999 11:27a 2,661,747 Waste.Stream.E3.R4.B12.cut 
02/21/2003 09:39a 2,966,055 Waste.Stream.E3.R1.B14.cut 
10/12/1999 11:22a 2,735,551 Waste.Stream.E3.R2.B13.cut 
10/12/1999 11:25a 2,730,865 Waste.Stream.E3.R3.B13.cut 
02/21/2003 09:55a 2,697,161 Waste.Stream.E5.R4.B15.cut 
02/21/2003 09:43a 2,976,251 Waste.Stream.E5.R1.B15.cut 
02/21/2003 09:45a 2,741,393 Waste.Stream.E5.R2.B14.cut 
02/21/2003 09:55a 2,741,563 Waste.Stream.E5.R3.B14.cut 
02/21/2003 09:55a 2,691,943 Waste.Stream.E5.R4.B14.cut 
02/21/2003 09:55a 2,746,487 Waste.Stream.E5.R2.B15.cut 
02/21/2003 09:55a 2,746,657 Waste.Stream.E5.R3.B15.cut 
10/12/1999 10:53a 2,684,867 Waste.Stream.E5.R4.B13.cut 
10/12/1999 11:43a 2,959,969 Waste.Stream.E5.R1.B13.cut 
10/12/1999 10:47a 2,719,010 Waste.Stream.E5.R2.B12.cut 
10/12/1999 10:50a 2,711,958 Waste.Stream.E5.R3.B12.cut 
10/12/1999 10:53a 2,665,324 Waste.Stream.E5.R4.B12.cut

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page VIII-17 of VIII-22 
Attachment VIII - List of Files on Disk 3 (Continued) 
02/21/2003 09:43a 2,968,667 Waste.Stream.E5.R1.B14.cut 
10/12/1999 10:47a 2,734,069 Waste.Stream.E5.R2.B13.cut 
10/12/1999 10:50a 2,731,625 Waste.Stream.E5.R3.B13.cut 
10/12/1999 11:43a 2,243,260 Waste.Stream.E5.R1.B2.cut 
10/12/1999 11:44a 2,785,451 Waste.Stream.E5.R1.B6.cut 
10/12/1999 11:19a 2,374,456 Waste.Stream.E3.R1.B3.cut 
10/12/1999 11:20a 2,830,490 Waste.Stream.E3.R1.B7.cut 
10/12/1999 11:44a 2,371,471 Waste.Stream.E5.R1.B3.cut 
10/12/1999 11:45a 2,830,814 Waste.Stream.E5.R1.B7.cut 
10/12/1999 11:19a 2,496,220 Waste.Stream.E3.R1.B4.cut 
10/12/1999 11:20a 2,865,573 Waste.Stream.E3.R1.B8.cut 
10/12/1999 11:44a 2,497,478 Waste.Stream.E5.R1.B4.cut 
10/12/1999 11:45a 2,863,188 Waste.Stream.E5.R1.B8.cut 
10/12/1999 11:17a 2,164,078 Waste.Stream.E3.R1.B1.cut 
10/12/1999 11:19a 2,707,642 Waste.Stream.E3.R1.B5.cut 
10/12/1999 11:20a 2,878,704 Waste.Stream.E3.R1.B9.cut 
10/12/1999 11:42a 2,160,111 Waste.Stream.E5.R1.B1.cut 
10/12/1999 11:44a 2,708,770 Waste.Stream.E5.R1.B5.cut 
10/12/1999 11:45a 2,876,919 Waste.Stream.E5.R1.B9.cut 
10/12/1999 11:19a 2,244,758 Waste.Stream.E3.R1.B2.cut 
10/12/1999 11:20a 2,781,916 Waste.Stream.E3.R1.B6.cut 
240 File(s) 616,284,045 bytes 
Total Files Listed: 
240 File(s) 616,284,045 bytes 
3 Dir(s) 0 bytes free

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page VIII-18 of VIII-22 
Attachment VIII - List of Files on Disk 4 
Volume in drive D is PWR ST G&E 
Volume Serial Number is DF53-540C 
Directory of D:\ 
04/20/2004 12:20p <DIR> Waste Stream 3 
0 File(s) 0 bytes 
Directory of D:\Waste Stream 3 
04/20/2004 12:20p <DIR> . 
04/20/2004 12:20p <DIR> .. 
10/12/1999 12:11p 2,090,385 Waste.Stream.E7.R2.B2.cut 
10/12/1999 12:15p 2,080,495 Waste.Stream.E7.R3.B2.cut 
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10/12/1999 12:13p 2,583,704 Waste.Stream.E7.R2.B6.cut 
10/12/1999 12:16p 2,581,924 Waste.Stream.E7.R3.B6.cut 
10/12/1999 12:19p 2,539,482 Waste.Stream.E7.R4.B6.cut 
10/12/1999 12:37p 2,089,883 Waste.Stream.E9.R2.B2.cut 
10/12/1999 12:40p 2,081,233 Waste.Stream.E9.R3.B2.cut 
10/12/1999 12:43p 2,042,401 Waste.Stream.E9.R4.B2.cut 
10/12/1999 12:38p 2,579,551 Waste.Stream.E9.R2.B6.cut 
10/12/1999 12:41p 2,577,945 Waste.Stream.E9.R3.B6.cut 
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10/12/1999 12:12p 2,208,222 Waste.Stream.E7.R2.B3.cut 
10/12/1999 12:15p 2,192,940 Waste.Stream.E7.R3.B3.cut 
10/12/1999 12:18p 2,153,304 Waste.Stream.E7.R4.B3.cut 
10/12/1999 12:13p 2,612,440 Waste.Stream.E7.R2.B7.cut 
10/12/1999 12:16p 2,611,712 Waste.Stream.E7.R3.B7.cut 
10/12/1999 12:19p 2,561,502 Waste.Stream.E7.R4.B7.cut 
10/12/1999 12:37p 2,211,324 Waste.Stream.E9.R2.B3.cut 
10/12/1999 12:40p 2,200,040 Waste.Stream.E9.R3.B3.cut 
10/12/1999 12:43p 2,160,864 Waste.Stream.E9.R4.B3.cut 
10/12/1999 12:38p 2,615,870 Waste.Stream.E9.R2.B7.cut 
10/12/1999 12:41p 2,613,530 Waste.Stream.E9.R3.B7.cut 
10/12/1999 12:44p 2,560,572 Waste.Stream.E9.R4.B7.cut 
10/12/1999 12:12p 2,324,026 Waste.Stream.E7.R2.B4.cut 
10/12/1999 12:15p 2,322,360 Waste.Stream.E7.R3.B4.cut 
10/12/1999 12:18p 2,280,876 Waste.Stream.E7.R4.B4.cut 
10/12/1999 12:13p 2,648,094 Waste.Stream.E7.R2.B8.cut 
10/12/1999 12:16p 2,643,740 Waste.Stream.E7.R3.B8.cut 
10/12/1999 12:19p 2,592,910 Waste.Stream.E7.R4.B8.cut 
10/12/1999 12:37p 2,329,030 Waste.Stream.E9.R2.B4.cut 
10/12/1999 12:40p 2,330,142 Waste.Stream.E9.R3.B4.cut 
10/12/1999 12:43p 2,285,528 Waste.Stream.E9.R4.B4.cut 
10/12/1999 12:38p 2,639,469 Waste.Stream.E9.R2.B8.cut 
10/12/1999 12:41p 2,636,385 Waste.Stream.E9.R3.B8.cut 
10/12/1999 12:44p 2,586,527 Waste.Stream.E9.R4.B8.cut 
10/12/1999 12:10p 2,025,249 Waste.Stream.E7.R2.B1.cut 
10/12/1999 12:13p 2,013,345 Waste.Stream.E7.R3.B1.cut 
10/12/1999 12:17p 1,979,897 Waste.Stream.E7.R4.B1.cut 
10/12/1999 12:12p 2,512,410 Waste.Stream.E7.R2.B5.cut 
10/12/1999 12:16p 2,509,400 Waste.Stream.E7.R3.B5.cut 
10/12/1999 12:19p 2,469,602 Waste.Stream.E7.R4.B5.cut 
10/12/1999 12:13p 2,665,172 Waste.Stream.E7.R2.B9.cut 
10/12/1999 12:16p 2,661,954 Waste.Stream.E7.R3.B9.cut 
10/12/1999 12:20p 2,614,348 Waste.Stream.E7.R4.B9.cut 
10/12/1999 12:35p 2,025,233 Waste.Stream.E9.R2.B1.cut

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page VIII-19 of VIII-22 
Attachment VIII - List of Files on Disk 4 (Continued) 
10/12/1999 12:39p 2,011,345 Waste.Stream.E9.R3.B1.cut 
10/12/1999 12:42p 1,978,393 Waste.Stream.E9.R4.B1.cut 
10/12/1999 12:38p 2,515,070 Waste.Stream.E9.R2.B5.cut 
10/12/1999 12:41p 2,511,802 Waste.Stream.E9.R3.B5.cut 
10/12/1999 12:39p 2,672,119 Waste.Stream.E9.R2.B9.cut 
10/12/1999 12:41p 2,669,541 Waste.Stream.E9.R3.B9.cut 
10/12/1999 12:44p 2,620,923 Waste.Stream.E9.R4.B9.cut 
10/12/1999 12:05p 2,640,976 Waste.Stream.E6.R4.B11.cut 
10/12/1999 11:58a 2,668,099 Waste.Stream.E6.R2.B10.cut 
10/12/1999 12:01p 2,666,751 Waste.Stream.E6.R3.B10.cut 
10/12/1999 12:05p 2,615,033 Waste.Stream.E6.R4.B10.cut 
10/12/1999 11:59a 2,694,910 Waste.Stream.E6.R2.B11.cut 
10/12/1999 12:02p 2,689,832 Waste.Stream.E6.R3.B11.cut 
10/12/1999 12:30p 2,642,497 Waste.Stream.E8.R4.B11.cut 
10/12/1999 12:20p 2,920,213 Waste.Stream.E8.R1.B11.cut 
10/12/1999 12:23p 2,675,982 Waste.Stream.E8.R2.B10.cut 
10/12/1999 12:26p 2,675,264 Waste.Stream.E8.R3.B10.cut 
10/12/1999 12:30p 2,626,904 Waste.Stream.E8.R4.B10.cut 
10/12/1999 12:21p 2,955,099 Waste.Stream.E8.R1.B12.cut 
10/12/1999 12:24p 2,696,059 Waste.Stream.E8.R2.B11.cut 
10/12/1999 12:27p 2,691,383 Waste.Stream.E8.R3.B11.cut 
10/12/1999 12:20p 2,899,556 Waste.Stream.E8.R1.B10.cut 
02/21/2003 09:57a 2,696,084 Waste.Stream.E6.R4.B15.cut 
02/21/2003 09:56a 2,977,416 Waste.Stream.E6.R1.B15.cut 
02/21/2003 09:56a 2,742,166 Waste.Stream.E6.R2.B14.cut 
02/21/2003 09:56a 2,742,212 Waste.Stream.E6.R3.B14.cut 
02/21/2003 09:56a 2,692,840 Waste.Stream.E6.R4.B14.cut 
02/21/2003 09:56a 2,745,658 Waste.Stream.E6.R2.B15.cut 
02/21/2003 09:56a 2,745,828 Waste.Stream.E6.R3.B15.cut 
10/12/1999 12:05p 2,685,896 Waste.Stream.E6.R4.B13.cut 
10/12/1999 11:56a 2,962,238 Waste.Stream.E6.R1.B13.cut 
10/12/1999 11:59a 2,728,084 Waste.Stream.E6.R2.B12.cut 
10/12/1999 12:02p 2,725,640 Waste.Stream.E6.R3.B12.cut 
10/12/1999 12:05p 2,676,640 Waste.Stream.E6.R4.B12.cut 
02/21/2003 09:56a 2,971,930 Waste.Stream.E6.R1.B14.cut 
10/12/1999 11:59a 2,735,222 Waste.Stream.E6.R2.B13.cut 
10/12/1999 12:02p 2,735,020 Waste.Stream.E6.R3.B13.cut 
02/21/2003 09:59a 2,690,768 Waste.Stream.E8.R4.B15.cut 
02/21/2003 09:58a 2,974,848 Waste.Stream.E8.R1.B15.cut 
02/21/2003 09:58a 2,739,424 Waste.Stream.E8.R2.B14.cut 
02/21/2003 09:59a 2,739,728 Waste.Stream.E8.R3.B14.cut 
02/21/2003 09:59a 2,689,850 Waste.Stream.E8.R4.B14.cut 
02/21/2003 09:58a 2,740,218 Waste.Stream.E8.R2.B15.cut 
02/21/2003 09:59a 2,743,012 Waste.Stream.E8.R3.B15.cut 
10/12/1999 12:31p 2,686,491 Waste.Stream.E8.R4.B13.cut 
10/12/1999 12:21p 2,965,705 Waste.Stream.E8.R1.B13.cut 
10/12/1999 12:24p 2,728,197 Waste.Stream.E8.R2.B12.cut 
10/12/1999 12:27p 2,728,253 Waste.Stream.E8.R3.B12.cut 
10/12/1999 12:30p 2,678,871 Waste.Stream.E8.R4.B12.cut 
02/21/2003 09:58a 2,971,430 Waste.Stream.E8.R1.B14.cut 
10/12/1999 12:24p 2,735,817 Waste.Stream.E8.R2.B13.cut 
10/12/1999 12:27p 2,736,121 Waste.Stream.E8.R3.B13.cut 
10/12/1999 11:56a 2,244,100 Waste.Stream.E6.R1.B2.cut 
10/12/1999 11:57a 2,793,875 Waste.Stream.E6.R1.B6.cut 
10/12/1999 12:21p 2,243,491 Waste.Stream.E8.R1.B2.cut 
10/12/1999 12:22p 2,796,177 Waste.Stream.E8.R1.B6.cut 
10/12/1999 11:56a 2,371,110 Waste.Stream.E6.R1.B3.cut 
10/12/1999 11:57a 2,831,138 Waste.Stream.E6.R1.B7.cut

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page VIII-20 of VIII-22 
Attachment VIII - List of Files on Disk 4 (Continued) 
10/12/1999 12:21p 2,374,852 Waste.Stream.E8.R1.B3.cut 
10/12/1999 12:22p 2,826,542 Waste.Stream.E8.R1.B7.cut 
10/12/1999 11:57a 2,497,599 Waste.Stream.E6.R1.B4.cut 
10/12/1999 11:57a 2,861,462 Waste.Stream.E6.R1.B8.cut 
10/12/1999 12:22p 2,500,403 Waste.Stream.E8.R1.B4.cut 
10/12/1999 12:23p 2,864,173 Waste.Stream.E8.R1.B8.cut 
10/12/1999 11:55a 2,158,995 Waste.Stream.E6.R1.B1.cut 
10/12/1999 11:57a 2,709,395 Waste.Stream.E6.R1.B5.cut 
10/12/1999 11:58a 2,881,427 Waste.Stream.E6.R1.B9.cut 
10/12/1999 12:20p 2,155,893 Waste.Stream.E8.R1.B1.cut 
10/12/1999 12:22p 2,710,591 Waste.Stream.E8.R1.B5.cut 
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10/12/1999 11:59a 2,092,244 Waste.Stream.E6.R2.B2.cut 
10/12/1999 12:02p 2,081,982 Waste.Stream.E6.R3.B2.cut 
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10/12/1999 12:00p 2,584,889 Waste.Stream.E6.R2.B6.cut 
10/12/1999 12:03p 2,583,109 Waste.Stream.E6.R3.B6.cut 
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10/12/1999 12:24p 2,089,651 Waste.Stream.E8.R2.B2.cut 
10/12/1999 12:27p 2,079,379 Waste.Stream.E8.R3.B2.cut 
10/12/1999 12:31p 2,042,035 Waste.Stream.E8.R4.B2.cut 
10/12/1999 12:25p 2,583,731 Waste.Stream.E8.R2.B6.cut 
10/12/1999 12:28p 2,582,363 Waste.Stream.E8.R3.B6.cut 
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10/12/1999 12:03p 2,192,568 Waste.Stream.E6.R3.B3.cut 
10/12/1999 12:06p 2,152,808 Waste.Stream.E6.R4.B3.cut 
10/12/1999 12:00p 2,617,498 Waste.Stream.E6.R2.B7.cut 
10/12/1999 12:04p 2,614,404 Waste.Stream.E6.R3.B7.cut 
10/12/1999 12:06p 2,566,436 Waste.Stream.E6.R4.B7.cut 
10/12/1999 12:24p 2,210,828 Waste.Stream.E8.R2.B3.cut 
10/12/1999 12:28p 2,197,674 Waste.Stream.E8.R3.B3.cut 
10/12/1999 12:31p 2,157,606 Waste.Stream.E8.R4.B3.cut 
10/12/1999 12:25p 2,616,305 Waste.Stream.E8.R2.B7.cut 
10/12/1999 12:29p 2,611,589 Waste.Stream.E8.R3.B7.cut 
10/12/1999 12:32p 2,561,265 Waste.Stream.E8.R4.B7.cut 
10/12/1999 12:00p 2,323,759 Waste.Stream.E6.R2.B4.cut 
10/12/1999 12:03p 2,323,839 Waste.Stream.E6.R3.B4.cut 
10/12/1999 12:06p 2,281,735 Waste.Stream.E6.R4.B4.cut 
10/12/1999 12:01p 2,645,030 Waste.Stream.E6.R2.B8.cut 
10/12/1999 12:04p 2,645,180 Waste.Stream.E6.R3.B8.cut 
10/12/1999 12:07p 2,594,350 Waste.Stream.E6.R4.B8.cut 
10/12/1999 12:25p 2,325,809 Waste.Stream.E8.R2.B4.cut 
10/12/1999 12:28p 2,325,547 Waste.Stream.E8.R3.B4.cut 
10/12/1999 12:31p 2,282,555 Waste.Stream.E8.R4.B4.cut 
10/12/1999 12:26p 2,647,493 Waste.Stream.E8.R2.B8.cut 
10/12/1999 12:29p 2,643,789 Waste.Stream.E8.R3.B8.cut 
10/12/1999 12:32p 2,594,551 Waste.Stream.E8.R4.B8.cut 
10/12/1999 11:58a 2,026,491 Waste.Stream.E6.R2.B1.cut 
10/12/1999 12:01p 2,014,959 Waste.Stream.E6.R3.B1.cut 
10/12/1999 12:04p 1,981,263 Waste.Stream.E6.R4.B1.cut 
10/12/1999 12:00p 2,512,967 Waste.Stream.E6.R2.B5.cut 
10/12/1999 12:03p 2,509,957 Waste.Stream.E6.R3.B5.cut 
10/12/1999 12:06p 2,470,159 Waste.Stream.E6.R4.B5.cut 
10/12/1999 12:01p 2,664,737 Waste.Stream.E6.R2.B9.cut 
10/12/1999 12:04p 2,661,023 Waste.Stream.E6.R3.B9.cut 
10/12/1999 12:07p 2,611,547 Waste.Stream.E6.R4.B9.cut 
10/12/1999 12:23p 2,023,389 Waste.Stream.E8.R2.B1.cut

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page VIII-21 of VIII-22 
Attachment VIII - List of Files on Disk 4 (Continued) 
10/12/1999 12:26p 2,011,485 Waste.Stream.E8.R3.B1.cut 
10/12/1999 12:29p 1,978,161 Waste.Stream.E8.R4.B1.cut 
10/12/1999 12:25p 2,513,047 Waste.Stream.E8.R2.B5.cut 
10/12/1999 12:28p 2,510,161 Waste.Stream.E8.R3.B5.cut 
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10/12/1999 12:29p 2,670,414 Waste.Stream.E8.R3.B9.cut 
10/12/1999 12:32p 2,622,054 Waste.Stream.E8.R4.B9.cut 
10/12/1999 12:17p 2,641,378 Waste.Stream.E7.R4.B11.cut 
10/12/1999 12:08p 2,916,108 Waste.Stream.E7.R1.B11.cut 
10/12/1999 12:10p 2,673,547 Waste.Stream.E7.R2.B10.cut 
10/12/1999 12:14p 2,672,571 Waste.Stream.E7.R3.B10.cut 
10/12/1999 12:17p 2,622,599 Waste.Stream.E7.R4.B10.cut 
10/12/1999 12:08p 2,955,720 Waste.Stream.E7.R1.B12.cut 
10/12/1999 12:10p 2,694,940 Waste.Stream.E7.R2.B11.cut 
10/12/1999 12:14p 2,688,136 Waste.Stream.E7.R3.B11.cut 
10/12/1999 12:07p 2,893,555 Waste.Stream.E7.R1.B10.cut 
10/12/1999 12:42p 2,655,886 Waste.Stream.E9.R4.B11.cut 
10/12/1999 12:33p 2,931,742 Waste.Stream.E9.R1.B11.cut 
10/12/1999 12:36p 2,676,420 Waste.Stream.E9.R2.B10.cut 
10/12/1999 12:39p 2,673,842 Waste.Stream.E9.R3.B10.cut 
10/12/1999 12:42p 2,625,224 Waste.Stream.E9.R4.B10.cut 
10/12/1999 12:33p 2,949,791 Waste.Stream.E9.R1.B12.cut 
10/12/1999 12:36p 2,707,454 Waste.Stream.E9.R2.B11.cut 
10/12/1999 12:39p 2,705,020 Waste.Stream.E9.R3.B11.cut 
10/12/1999 12:33p 2,898,878 Waste.Stream.E9.R1.B10.cut 
02/21/2003 09:58a 2,695,645 Waste.Stream.E7.R4.B15.cut 
02/21/2003 09:57a 2,979,601 Waste.Stream.E7.R1.B15.cut 
02/21/2003 09:57a 2,741,606 Waste.Stream.E7.R2.B14.cut 
02/21/2003 09:57a 2,741,786 Waste.Stream.E7.R3.B14.cut 
02/21/2003 09:58a 2,692,032 Waste.Stream.E7.R4.B14.cut 
02/21/2003 09:57a 2,745,095 Waste.Stream.E7.R2.B15.cut 
02/21/2003 09:57a 2,745,523 Waste.Stream.E7.R3.B15.cut 
10/12/1999 12:18p 2,688,631 Waste.Stream.E7.R4.B13.cut 
10/12/1999 12:08p 2,967,597 Waste.Stream.E7.R1.B13.cut 
10/12/1999 12:11p 2,729,448 Waste.Stream.E7.R2.B12.cut 
10/12/1999 12:15p 2,727,262 Waste.Stream.E7.R3.B12.cut 
10/12/1999 12:17p 2,680,370 Waste.Stream.E7.R4.B12.cut 
02/21/2003 09:57a 2,971,246 Waste.Stream.E7.R1.B14.cut 
10/12/1999 12:11p 2,737,957 Waste.Stream.E7.R2.B13.cut 
10/12/1999 12:15p 2,738,261 Waste.Stream.E7.R3.B13.cut 
02/21/2003 10:00a 2,678,539 Waste.Stream.E9.R4.B15.cut 
02/21/2003 09:59a 2,963,135 Waste.Stream.E9.R1.B15.cut 
02/21/2003 09:59a 2,727,840 Waste.Stream.E9.R2.B14.cut 
02/21/2003 10:00a 2,727,018 Waste.Stream.E9.R3.B14.cut 
02/21/2003 10:00a 2,676,892 Waste.Stream.E9.R4.B14.cut 
02/21/2003 09:59a 2,729,983 Waste.Stream.E9.R2.B15.cut 
02/21/2003 10:00a 2,731,041 Waste.Stream.E9.R3.B15.cut 
10/12/1999 12:43p 2,673,672 Waste.Stream.E9.R4.B13.cut 
10/12/1999 12:33p 2,952,886 Waste.Stream.E9.R1.B13.cut 
10/12/1999 12:36p 2,719,407 Waste.Stream.E9.R2.B12.cut 
10/12/1999 12:39p 2,719,835 Waste.Stream.E9.R3.B12.cut 
10/12/1999 12:42p 2,670,081 Waste.Stream.E9.R4.B12.cut 
02/21/2003 09:59a 2,960,982 Waste.Stream.E9.R1.B14.cut 
10/12/1999 12:36p 2,723,370 Waste.Stream.E9.R2.B13.cut 
10/12/1999 12:40p 2,723,798 Waste.Stream.E9.R3.B13.cut 
10/12/1999 12:08p 2,242,241 Waste.Stream.E7.R1.B2.cut 
10/12/1999 12:09p 2,797,876 Waste.Stream.E7.R1.B6.cut

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page VIII-22 of VIII-22 
Attachment VIII - List of Files on Disk 4 (Continued) 
10/12/1999 12:34p 2,243,981 Waste.Stream.E9.R1.B2.cut 
10/12/1999 12:35p 2,792,141 Waste.Stream.E9.R1.B6.cut 
10/12/1999 12:08p 2,371,854 Waste.Stream.E7.R1.B3.cut 
10/12/1999 12:09p 2,827,349 Waste.Stream.E7.R1.B7.cut 
10/12/1999 12:34p 2,375,244 Waste.Stream.E9.R1.B3.cut 
10/12/1999 12:35p 2,828,672 Waste.Stream.E9.R1.B7.cut 
10/12/1999 12:09p 2,495,997 Waste.Stream.E7.R1.B4.cut 
10/12/1999 12:10p 2,862,026 Waste.Stream.E7.R1.B8.cut 
10/12/1999 12:34p 2,506,392 Waste.Stream.E9.R1.B4.cut 
10/12/1999 12:35p 2,856,045 Waste.Stream.E9.R1.B8.cut 
10/12/1999 12:07p 2,157,877 Waste.Stream.E7.R1.B1.cut 
10/12/1999 12:09p 2,709,706 Waste.Stream.E7.R1.B5.cut 
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Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page IX-1 of IX-10 
Attachment IX - Radionuclide Inventories for Performance Assessment 
The characteristics of the average and maximum PWR SNF assemblies are (see Section 5.5): 
 Average PWR assembly- 4% 235U, 48GWd/MTU, 25 years cooling time 
 Maximum PWR assembly- 5% 235U, 80GWd/MTU, 5 years cooling time 
For the maximum case, the combination of all the maximum parameters (maximum burnup, 
maximum 235U enrichment, and minimum cooling time  all independent of each other) were 
used in calculations.

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page IX-2 of IX-10 
Attachment IX 
Average PWR Assembly Radionuclide Inventories for Short Decay Times 
Age: 25 yr 125 yr 225 yr 325 yr 425 yr 525 yr 1025 yr 2025 yr 5025 yr 10025 yr 
Year: 2033 2133 2233 2333 2433 2533 3033 4033 7033 12033 
ac227 1.61E-05 4.00E-05 5.59E-05 7.14E-05 8.70E-05 1.03E-04 1.85E-04 3.41E-04 8.09E-04 1.59E-03 
ag108 3.85E-04 2.23E-04 1.29E-04 7.48E-05 4.34E-05 2.51E-05 1.64E-06 6.99E-09 5.41E-16 7.61E-28 
ag108m 4.42E-03 2.56E-03 1.48E-03 8.60E-04 4.98E-04 2.89E-04 1.88E-05 8.03E-08 6.22E-15 8.74E-27 
am241 1.98E+03 2.40E+03 2.05E+03 1.75E+03 1.49E+03 1.27E+03 5.69E+02 1.15E+02 1.15E+00 1.36E-01 
am242 6.36E+00 3.89E+00 2.38E+00 1.45E+00 8.90E-01 5.44E-01 4.66E-02 3.42E-04 1.34E-10 2.84E-21 
am242m 6.39E+00 3.91E+00 2.39E+00 1.46E+00 8.94E-01 5.47E-01 4.68E-02 3.43E-04 1.35E-10 2.86E-21 
am243 2.20E+01 2.18E+01 2.16E+01 2.14E+01 2.12E+01 2.10E+01 2.00E+01 1.82E+01 1.37E+01 8.57E+00 
ar 39 5.22E-05 4.04E-05 3.12E-05 2.41E-05 1.86E-05 1.44E-05 3.97E-06 3.02E-07 1.32E-10 3.36E-16 
ba137m 3.88E+04 3.85E+03 3.82E+02 3.79E+01 3.76E+00 3.73E-01 3.58E-06 3.30E-16 0.00E+00 0.00E+00 
bi211 1.61E-05 4.00E-05 5.59E-05 7.14E-05 8.70E-05 1.03E-04 1.85E-04 3.41E-04 8.09E-04 1.59E-03 
bi212 2.06E-02 7.81E-03 2.89E-03 1.07E-03 3.98E-04 1.48E-04 1.91E-06 8.94E-07 9.08E-07 9.37E-07 
c 14 3.32E-01 3.28E-01 3.24E-01 3.21E-01 3.17E-01 3.13E-01 2.95E-01 2.61E-01 1.82E-01 9.91E-02 
ca 41 9.25E-05 9.24E-05 9.24E-05 9.23E-05 9.22E-05 9.22E-05 9.19E-05 9.12E-05 8.94E-05 8.65E-05 
cd113m 7.66E+00 5.61E-02 4.12E-04 3.02E-06 2.21E-08 1.62E-10 3.43E-21 0.00E+00 0.00E+00 0.00E+00 
ce142 1.86E-05 1.86E-05 1.86E-05 1.86E-05 1.86E-05 1.86E-05 1.86E-05 1.86E-05 1.86E-05 1.86E-05 
ce144 1.18E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
cf249 7.72E-05 6.34E-05 5.20E-05 4.27E-05 3.50E-05 2.87E-05 1.07E-05 1.48E-06 3.92E-09 1.99E-13 
cf250 8.41E-05 4.20E-07 2.10E-09 1.06E-11 1.55E-13 1.03E-13 1.01E-13 9.67E-14 8.58E-14 7.03E-14 
cl 36 6.80E-03 6.80E-03 6.80E-03 6.80E-03 6.79E-03 6.79E-03 6.79E-03 6.77E-03 6.72E-03 6.65E-03 
cm242 5.26E+00 3.22E+00 1.97E+00 1.20E+00 7.36E-01 4.50E-01 3.85E-02 2.82E-04 1.12E-10 2.36E-21 
cm243 1.03E+01 9.01E-01 7.91E-02 6.95E-03 6.10E-04 5.36E-05 2.80E-10 7.66E-21 0.00E+00 0.00E+00 
cm244 1.36E+03 2.96E+01 6.42E-01 1.40E-02 3.03E-04 6.58E-06 3.18E-14 7.30E-31 0.00E+00 0.00E+00 
cm245 3.07E-01 3.04E-01 3.02E-01 2.99E-01 2.97E-01 2.94E-01 2.83E-01 2.60E-01 2.04E-01 1.36E-01 
cm246 1.04E-01 1.03E-01 1.01E-01 9.98E-02 9.83E-02 9.69E-02 9.01E-02 7.78E-02 5.01E-02 2.41E-02 
co 60 3.13E+02 6.06E-04 1.17E-09 2.27E-15 4.40E-21 8.52E-27 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
cs134 2.52E+01 6.33E-14 1.59E-28 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
cs135 3.50E-01 3.50E-01 3.50E-01 3.50E-01 3.50E-01 3.50E-01 3.50E-01 3.50E-01 3.49E-01 3.49E-01 
cs137 4.11E+04 4.08E+03 4.05E+02 4.01E+01 3.98E+00 3.95E-01 3.79E-06 3.49E-16 0.00E+00 0.00E+00 
eu150 2.07E-05 2.99E-06 4.31E-07 6.23E-08 8.98E-09 1.30E-09 8.11E-14 3.17E-22 0.00E+00 0.00E+00 
eu152 1.31E+00 7.23E-03 3.98E-05 2.20E-07 1.21E-09 6.67E-12 3.39E-23 0.00E+00 0.00E+00 0.00E+00 
eu154 6.71E+02 2.10E-01 6.57E-05 2.06E-08 6.44E-12 2.01E-15 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
eu155 5.15E+01 1.90E-05 7.04E-12 2.60E-18 9.61E-25 3.65E-31 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
fe 55 3.46E+00 3.25E-11 3.04E-22 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
h 3 1.14E+02 4.10E-01 1.48E-03 5.37E-06 1.94E-08 7.02E-11 4.35E-23 0.00E+00 0.00E+00 0.00E+00 
ho166m 5.38E-04 5.08E-04 4.79E-04 4.52E-04 4.27E-04 4.03E-04 3.02E-04 1.69E-04 2.99E-05 1.67E-06 
i129 2.19E-02 2.19E-02 2.19E-02 2.19E-02 2.19E-02 2.19E-02 2.19E-02 2.19E-02 2.19E-02 2.19E-02 
kr 85 1.13E+03 1.76E+00 2.74E-03 4.26E-06 6.63E-09 1.03E-11 9.36E-26 0.00E+00 0.00E+00 0.00E+00 
mo 93 4.14E-02 4.06E-02 3.98E-02 3.90E-02 3.83E-02 3.75E-02 3.40E-02 2.79E-02 1.54E-02 5.71E-03 
nb 91 1.96E-05 1.77E-05 1.60E-05 1.44E-05 1.30E-05 1.18E-05 7.06E-06 2.55E-06 1.20E-07 7.32E-10 
nb 93m 1.30E+01 1.09E+00 9.29E-01 9.27E-01 9.26E-01 9.25E-01 9.22E-01 9.16E-01 9.05E-01 8.95E-01 
nb 94 8.39E-01 8.36E-01 8.33E-01 8.30E-01 8.28E-01 8.25E-01 8.11E-01 7.84E-01 7.07E-01 5.96E-01 
ni 59 2.09E+00 2.09E+00 2.09E+00 2.08E+00 2.08E+00 2.08E+00 2.07E+00 2.05E+00 2.00E+00 1.90E+00 
ni 63 2.52E+02 1.26E+02 6.30E+01 3.15E+01 1.58E+01 7.89E+00 2.47E-01 2.43E-04 2.31E-13 2.12E-28 
np237 2.47E-01 3.26E-01 3.98E-01 4.60E-01 5.12E-01 5.57E-01 6.98E-01 7.90E-01 8.12E-01 8.11E-01 
np238 2.87E-02 1.76E-02 1.08E-02 6.58E-03 4.02E-03 2.46E-03 2.11E-04 1.54E-06 6.08E-13 1.29E-23 
np239 2.20E+01 2.18E+01 2.16E+01 2.14E+01 2.12E+01 2.10E+01 2.00E+01 1.82E+01 1.37E+01 8.57E+00 
pa231 2.97E-05 4.53E-05 6.08E-05 7.63E-05 9.18E-05 1.07E-04 1.85E-04 3.41E-04 8.09E-04 1.59E-03 
pa233 2.47E-01 3.26E-01 3.98E-01 4.60E-01 5.12E-01 5.57E-01 6.98E-01 7.90E-01 8.12E-01 8.11E-01 
pa234 1.92E-04 1.92E-04 1.92E-04 1.92E-04 1.92E-04 1.92E-04 1.92E-04 1.92E-04 1.92E-04 1.92E-04 
pa234m 1.48E-01 1.48E-01 1.48E-01 1.48E-01 1.48E-01 1.48E-01 1.48E-01 1.48E-01 1.48E-01 1.48E-01 
pb211 1.61E-05 4.00E-05 5.59E-05 7.14E-05 8.70E-05 1.03E-04 1.85E-04 3.41E-04 8.09E-04 1.59E-03 
pb212 2.06E-02 7.81E-03 2.89E-03 1.07E-03 3.98E-04 1.48E-04 1.91E-06 8.94E-07 9.08E-07 9.37E-07 
pd107 8.41E-02 8.41E-02 8.41E-02 8.41E-02 8.41E-02 8.41E-02 8.41E-02 8.41E-02 8.41E-02 8.40E-02 
pm145 1.07E-03 2.13E-05 4.24E-07 8.45E-09 1.68E-10 3.35E-12 1.05E-20 0.00E+00 0.00E+00 0.00E+00 
pm146 1.17E-01 4.22E-07 1.52E-12 5.45E-18 1.96E-23 7.03E-29 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
pm147 1.19E+02 3.99E-10 1.33E-21 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
po212 1.32E-02 5.00E-03 1.85E-03 6.87E-04 2.55E-04 9.47E-05 1.22E-06 5.73E-07 5.81E-07 6.00E-07

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page IX-3 of IX-10 
Attachment IX 
Average PWR Assembly Radionuclide Inventories for Short Decay Times 
Age: 25 yr 125 yr 225 yr 325 yr 425 yr 525 yr 1025 yr 2025 yr 5025 yr 10025 yr 
Year: 2033 2133 2233 2333 2433 2533 3033 4033 7033 12033 
po215 1.61E-05 4.00E-05 5.59E-05 7.14E-05 8.70E-05 1.03E-04 1.85E-04 3.41E-04 8.09E-04 1.59E-03 
po216 2.06E-02 7.81E-03 2.89E-03 1.07E-03 3.98E-04 1.48E-04 1.91E-06 8.94E-07 9.08E-07 9.37E-07 
pr144 1.18E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
pu236 1.01E-03 8.86E-07 8.85E-07 8.85E-07 8.84E-07 8.84E-07 8.81E-07 8.76E-07 8.60E-07 8.35E-07 
pu238 2.29E+03 1.04E+03 4.73E+02 2.16E+02 9.83E+01 4.49E+01 9.43E-01 6.33E-04 2.97E-10 6.27E-21 
pu239 1.77E+02 1.77E+02 1.77E+02 1.76E+02 1.76E+02 1.75E+02 1.73E+02 1.69E+02 1.56E+02 1.37E+02 
pu240 3.18E+02 3.18E+02 3.15E+02 3.12E+02 3.09E+02 3.05E+02 2.90E+02 2.61E+02 1.90E+02 1.12E+02 
pu241 2.46E+04 1.97E+02 1.87E+00 3.12E-01 2.97E-01 2.95E-01 2.83E-01 2.61E-01 2.04E-01 1.36E-01 
pu242 1.64E+00 1.64E+00 1.64E+00 1.64E+00 1.64E+00 1.64E+00 1.64E+00 1.63E+00 1.62E+00 1.61E+00 
ra223 1.61E-05 4.00E-05 5.59E-05 7.14E-05 8.70E-05 1.03E-04 1.85E-04 3.41E-04 8.09E-04 1.59E-03 
ra224 2.06E-02 7.81E-03 2.89E-03 1.07E-03 3.98E-04 1.48E-04 1.91E-06 8.94E-07 9.08E-07 9.37E-07 
rb 87 1.39E-05 1.39E-05 1.39E-05 1.39E-05 1.39E-05 1.39E-05 1.39E-05 1.39E-05 1.39E-05 1.39E-05 
rh102 3.04E-03 1.26E-13 5.26E-24 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
rh106 1.23E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
rn219 1.61E-05 4.00E-05 5.59E-05 7.14E-05 8.70E-05 1.03E-04 1.85E-04 3.41E-04 8.09E-04 1.59E-03 
rn220 2.06E-02 7.81E-03 2.89E-03 1.07E-03 3.98E-04 1.48E-04 1.91E-06 8.94E-07 9.08E-07 9.37E-07 
ru106 1.23E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
sb125 9.71E+00 9.11E-11 8.53E-22 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
sb126 5.39E-02 5.39E-02 5.38E-02 5.38E-02 5.38E-02 5.37E-02 5.35E-02 5.32E-02 5.21E-02 5.03E-02 
sb126m 3.85E-01 3.85E-01 3.85E-01 3.84E-01 3.84E-01 3.84E-01 3.82E-01 3.80E-01 3.72E-01 3.59E-01 
se 79 4.57E-02 4.57E-02 4.57E-02 4.57E-02 4.57E-02 4.56E-02 4.56E-02 4.55E-02 4.52E-02 4.47E-02 
sm151 2.11E+02 9.75E+01 4.51E+01 2.09E+01 9.67E+00 4.48E+00 9.52E-02 4.30E-05 3.96E-15 6.85E-32 
sn121 1.24E+00 3.51E-01 9.95E-02 2.82E-02 8.00E-03 2.27E-03 4.16E-06 1.40E-11 5.36E-28 0.00E+00 
sn121m 1.59E+00 4.52E-01 1.28E-01 3.64E-02 1.03E-02 2.92E-03 5.36E-06 1.81E-11 6.90E-28 0.00E+00 
sn126 3.85E-01 3.85E-01 3.85E-01 3.84E-01 3.84E-01 3.84E-01 3.82E-01 3.80E-01 3.72E-01 3.59E-01 
sr 90 2.72E+04 2.32E+03 1.97E+02 1.68E+01 1.43E+00 1.22E-01 5.48E-07 1.11E-17 0.00E+00 0.00E+00 
tc 99 8.98E+00 8.98E+00 8.98E+00 8.98E+00 8.97E+00 8.97E+00 8.96E+00 8.93E+00 8.84E+00 8.69E+00 
te125m 2.37E+00 2.23E-11 2.08E-22 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
th227 1.59E-05 3.95E-05 5.51E-05 7.05E-05 8.58E-05 1.01E-04 1.83E-04 3.36E-04 7.98E-04 1.57E-03 
th228 2.06E-02 7.81E-03 2.89E-03 1.07E-03 3.98E-04 1.48E-04 1.91E-06 8.94E-07 9.08E-07 9.37E-07 
th230 1.48E-04 1.00E-03 2.14E-03 3.40E-03 4.73E-03 6.08E-03 1.29E-02 2.64E-02 6.61E-02 1.29E-01 
th231 7.37E-03 7.38E-03 7.40E-03 7.42E-03 7.43E-03 7.45E-03 7.54E-03 7.71E-03 8.19E-03 8.91E-03 
th234 1.48E-01 1.48E-01 1.48E-01 1.48E-01 1.48E-01 1.48E-01 1.48E-01 1.48E-01 1.48E-01 1.48E-01 
tl207 1.61E-05 3.99E-05 5.57E-05 7.12E-05 8.67E-05 1.02E-04 1.85E-04 3.40E-04 8.07E-04 1.58E-03 
tl208 7.42E-03 2.81E-03 1.04E-03 3.85E-04 1.43E-04 5.32E-05 6.86E-07 3.21E-07 3.26E-07 3.37E-07 
u232 2.04E-02 7.59E-03 2.81E-03 1.04E-03 3.87E-04 1.44E-04 1.87E-06 8.76E-07 8.60E-07 8.35E-07 
u233 3.79E-05 1.62E-04 3.21E-04 5.08E-04 7.19E-04 9.52E-04 2.33E-03 5.61E-03 1.60E-02 3.32E-02 
u234 6.77E-01 1.12E+00 1.33E+00 1.42E+00 1.46E+00 1.48E+00 1.49E+00 1.49E+00 1.48E+00 1.46E+00 
u235 7.37E-03 7.38E-03 7.40E-03 7.42E-03 7.43E-03 7.45E-03 7.54E-03 7.71E-03 8.19E-03 8.91E-03 
u236 1.72E-01 1.73E-01 1.74E-01 1.74E-01 1.75E-01 1.76E-01 1.81E-01 1.89E-01 2.09E-01 2.30E-01 
u237 5.90E-01 4.71E-03 4.48E-05 7.46E-06 7.11E-06 7.05E-06 6.77E-06 6.24E-06 4.88E-06 3.25E-06 
u238 1.48E-01 1.48E-01 1.48E-01 1.48E-01 1.48E-01 1.48E-01 1.48E-01 1.48E-01 1.48E-01 1.48E-01 
y 90 2.72E+04 2.32E+03 1.97E+02 1.68E+01 1.43E+00 1.22E-01 5.48E-07 1.11E-17 0.00E+00 0.00E+00 
zr 93 8.94E-01 8.94E-01 8.94E-01 8.94E-01 8.94E-01 8.94E-01 8.94E-01 8.93E-01 8.92E-01 8.90E-01

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page IX-4 of IX-10 
Attachment IX 
Average PWR Assembly Radionuclide Inventories for Long Decay Times 
Decay Time 10025. yr 20025. yr 30025. yr 100025. yr 300025. yr 1000025 yr 
Year 12033 22033 32033 102033 302033 1002033 
ac225 1.17E-02 3.63E-02 6.53E-02 2.56E-01 5.66E-01 6.26E-01 
ac227 1.59E-03 3.10E-03 4.53E-03 1.09E-02 1.36E-02 1.37E-02 
am241 1.36E-01 6.01E-02 2.66E-02 8.81E-05 7.64E-12 0.00E+00 
am243 8.57E+00 3.35E+00 1.31E+00 1.81E-03 6.76E-07 6.56E-07 
at217 1.17E-02 3.63E-02 6.53E-02 2.56E-01 5.66E-01 6.26E-01 
bi210 1.02E-01 2.20E-01 3.24E-01 7.85E-01 8.53E-01 2.64E-01 
bi211 1.59E-03 3.10E-03 4.53E-03 1.09E-02 1.36E-02 1.37E-02 
bi213 1.17E-02 3.63E-02 6.53E-02 2.56E-01 5.66E-01 6.26E-01 
bi214 1.02E-01 2.20E-01 3.24E-01 7.85E-01 8.53E-01 2.64E-01 
c 14 9.91E-02 2.96E-02 8.82E-03 1.85E-06 5.72E-17 0.00E+00 
ca 41 8.65E-05 8.08E-05 7.56E-05 4.72E-05 1.23E-05 1.10E-07 
ce142 1.86E-05 1.86E-05 1.86E-05 1.86E-05 1.86E-05 1.86E-05 
cl 36 6.65E-03 6.49E-03 6.35E-03 5.40E-03 3.41E-03 6.80E-04 
cm245 1.36E-01 6.00E-02 2.65E-02 8.80E-05 7.24E-12 0.00E+00 
cm246 2.41E-02 5.57E-03 1.29E-03 4.52E-08 2.59E-18 2.01E-30 
cs135 3.49E-01 3.48E-01 3.47E-01 3.39E-01 3.20E-01 2.59E-01 
fr221 1.17E-02 3.63E-02 6.53E-02 2.56E-01 5.66E-01 6.26E-01 
fr223 2.19E-05 4.28E-05 6.25E-05 1.50E-04 1.88E-04 1.89E-04 
i129 2.19E-02 2.19E-02 2.19E-02 2.18E-02 2.17E-02 2.10E-02 
mo 93 5.71E-03 7.87E-04 1.09E-04 1.03E-10 6.32E-28 0.00E+00 
nb 93m 8.95E-01 8.87E-01 8.82E-01 8.55E-01 7.80E-01 5.69E-01 
nb 94 5.96E-01 4.24E-01 3.01E-01 2.76E-02 2.98E-05 1.24E-15 
ni 59 1.90E+00 1.74E+00 1.58E+00 8.29E-01 1.31E-01 2.02E-04 
np237 8.11E-01 8.09E-01 8.06E-01 7.88E-01 7.39E-01 5.89E-01 
np239 8.57E+00 3.35E+00 1.31E+00 1.81E-03 6.76E-07 6.56E-07 
pa231 1.59E-03 3.10E-03 4.53E-03 1.09E-02 1.36E-02 1.37E-02 
pa233 8.11E-01 8.09E-01 8.06E-01 7.88E-01 7.39E-01 5.89E-01 
pa234 1.92E-04 1.92E-04 1.92E-04 1.92E-04 1.92E-04 1.92E-04 
pa234m 1.48E-01 1.48E-01 1.48E-01 1.48E-01 1.48E-01 1.48E-01 
pb209 1.17E-02 3.63E-02 6.53E-02 2.56E-01 5.66E-01 6.26E-01 
pb210 1.02E-01 2.20E-01 3.24E-01 7.85E-01 8.53E-01 2.64E-01 
pb211 1.59E-03 3.10E-03 4.53E-03 1.09E-02 1.36E-02 1.37E-02

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page IX-5 of IX-10 
Attachment IX 
Average PWR Assembly Radionuclide Inventories for Long Decay Times 
Decay Time 10025. yr 20025. yr 30025. yr 100025. yr 300025. yr 1000025 yr 
Year 12033 22033 32033 102033 302033 1002033 
pb214 1.02E-01 2.20E-01 3.24E-01 7.85E-01 8.53E-01 2.64E-01 
pd107 8.40E-02 8.39E-02 8.38E-02 8.32E-02 8.15E-02 7.56E-02 
po210 1.02E-01 2.20E-01 3.24E-01 7.85E-01 8.53E-01 2.64E-01 
po213 1.15E-02 3.55E-02 6.39E-02 2.51E-01 5.54E-01 6.13E-01 
po214 1.02E-01 2.20E-01 3.24E-01 7.85E-01 8.53E-01 2.64E-01 
po215 1.59E-03 3.10E-03 4.53E-03 1.09E-02 1.36E-02 1.37E-02 
po218 1.02E-01 2.20E-01 3.24E-01 7.85E-01 8.53E-01 2.64E-01 
pu239 1.37E+02 1.04E+02 7.84E+01 1.06E+01 3.36E-02 6.56E-07 
pu240 1.12E+02 3.89E+01 1.35E+01 8.32E-03 7.17E-09 1.36E-08 
pu241 1.36E-01 6.01E-02 2.66E-02 8.81E-05 7.25E-12 0.00E+00 
pu242 1.61E+00 1.58E+00 1.55E+00 1.36E+00 9.40E-01 2.56E-01 
ra223 1.59E-03 3.10E-03 4.53E-03 1.09E-02 1.36E-02 1.37E-02 
ra225 1.17E-02 3.63E-02 6.53E-02 2.56E-01 5.66E-01 6.26E-01 
ra226 1.02E-01 2.20E-01 3.24E-01 7.85E-01 8.53E-01 2.64E-01 
rb 87 1.39E-05 1.39E-05 1.39E-05 1.39E-05 1.39E-05 1.39E-05 
rn219 1.59E-03 3.10E-03 4.53E-03 1.09E-02 1.36E-02 1.37E-02 
rn222 1.02E-01 2.20E-01 3.24E-01 7.85E-01 8.53E-01 2.64E-01 
sb126 5.03E-02 4.69E-02 4.38E-02 2.70E-02 6.74E-03 5.27E-05 
sb126m 3.59E-01 3.35E-01 3.13E-01 1.93E-01 4.81E-02 3.76E-04 
se 79 4.47E-02 4.38E-02 4.29E-02 3.70E-02 2.43E-02 5.59E-03 
sn126 3.59E-01 3.35E-01 3.13E-01 1.93E-01 4.81E-02 3.76E-04 
tc 99 8.69E+00 8.41E+00 8.14E+00 6.47E+00 3.35E+00 3.37E-01 
th227 1.56E-03 3.06E-03 4.47E-03 1.07E-02 1.34E-02 1.35E-02 
th229 1.17E-02 3.63E-02 6.53E-02 2.56E-01 5.66E-01 6.26E-01 
th230 1.30E-01 2.45E-01 3.47E-01 7.81E-01 8.50E-01 2.64E-01 
th231 8.91E-03 1.01E-02 1.10E-02 1.33E-02 1.37E-02 1.37E-02 
th234 1.48E-01 1.48E-01 1.48E-01 1.48E-01 1.48E-01 1.48E-01 
tl207 1.58E-03 3.10E-03 4.52E-03 1.09E-02 1.36E-02 1.36E-02 
tl209 2.46E-04 7.62E-04 1.37E-03 5.38E-03 1.19E-02 1.32E-02 
u233 3.47E-02 6.77E-02 9.93E-02 2.83E-01 5.60E-01 6.25E-01 
u234 1.46E+00 1.42E+00 1.39E+00 1.17E+00 7.27E-01 2.28E-01 
u235 8.91E-03 1.01E-02 1.10E-02 1.33E-02 1.37E-02 1.37E-02 
u236 2.30E-01 2.51E-01 2.58E-01 2.61E-01 2.60E-01 2.54E-01 
u238 1.48E-01 1.48E-01 1.48E-01 1.48E-01 1.48E-01 1.48E-01 
zr 93 0.8899 0.8865 0.8821 0.8552 0.7804 0.569

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page IX-6 of IX-10 
Attachment IX 
Maximum PWR Assembly Radionuclide Inventories for Short Decay Times 
Age: 5 yr 100 yr 200 yr 300 yr 400 yr 500 yr 1000 yr 2000 yr 5000 yr 10000 yr 
ac227 0.00E+00 4.48E-05 5.31E-05 6.00E-05 6.70E-05 7.39E-05 1.09E-04 1.83E-04 4.12E-04 8.26E-04 
ag108 1.38E-03 8.22E-04 4.76E-04 2.76E-04 1.60E-04 9.27E-05 6.05E-06 2.58E-08 0.00E+00 0.00E+00 
ag108m 1.59E-02 9.45E-03 5.48E-03 3.17E-03 1.84E-03 1.06E-03 6.95E-05 2.96E-07 0.00E+00 0.00E+00 
ag109m 3.31E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
ag110 4.65E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
ag110m 3.42E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
am241 8.79E+02 3.08E+03 2.65E+03 2.26E+03 1.92E+03 1.64E+03 7.37E+02 1.50E+02 2.45E+00 8.25E-01 
am242 1.01E+01 6.35E+00 3.89E+00 2.38E+00 1.45E+00 8.89E-01 7.61E-02 5.58E-04 0.00E+00 0.00E+00 
am242m 1.02E+01 6.38E+00 3.90E+00 2.39E+00 1.46E+00 8.93E-01 7.65E-02 5.60E-04 0.00E+00 0.00E+00 
am243 6.00E+01 5.95E+01 5.89E+01 5.84E+01 5.78E+01 5.73E+01 5.46E+01 4.97E+01 3.75E+01 2.34E+01 
ar 39 8.39E-05 6.57E-05 5.07E-05 3.92E-05 3.03E-05 2.34E-05 6.46E-06 4.91E-07 0.00E+00 0.00E+00 
ba133 2.30E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
ba137m 9.89E+04 1.10E+04 1.09E+03 1.08E+02 1.07E+01 1.07E+00 1.02E-05 9.43E-16 0.00E+00 0.00E+00 
bi211 0.00E+00 4.49E-05 5.32E-05 6.01E-05 6.70E-05 7.40E-05 1.09E-04 1.83E-04 4.12E-04 8.26E-04 
bi212 4.57E-02 3.00E-02 1.11E-02 4.11E-03 1.52E-03 5.66E-04 7.00E-06 3.04E-06 0.00E+00 0.00E+00 
bk249 2.56E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
c 14 5.35E-01 5.29E-01 5.22E-01 5.16E-01 5.10E-01 3.41E-03 4.73E-01 4.20E-01 2.92E-01 1.59E-01 
ca 41 1.49E-04 1.49E-04 1.49E-04 1.49E-04 1.49E-04 1.49E-04 1.48E-04 1.47E-04 1.44E-04 1.39E-04 
ca 45 1.15E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
cd109 3.31E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
cd113m 4.31E+01 4.04E-01 2.96E-03 2.17E-05 1.59E-07 1.02E-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
ce139 1.67E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
ce142 3.02E-05 3.02E-05 3.02E-05 3.02E-05 3.02E-05 3.02E-05 3.02E-05 3.02E-05 3.02E-05 3.02E-05 
ce144 5.80E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
cf249 3.90E-03 3.28E-03 2.69E-03 2.21E-03 1.81E-03 1.49E-03 5.54E-04 7.66E-05 0.00E+00 0.00E+00 
cf250 1.34E-02 8.70E-05 4.34E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
cf251 1.96E-04 1.82E-04 1.68E-04 1.56E-04 1.44E-04 1.34E-04 9.09E-05 4.20E-05 4.14E-06 0.00E+00 
cf252 2.55E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
cl 36 1.05E-02 1.05E-02 1.05E-02 1.05E-02 1.05E-02 1.05E-02 1.05E-02 1.05E-02 1.04E-02 1.03E-02 
cm242 3.56E+01 5.26E+00 3.21E+00 1.97E+00 1.20E+00 7.35E-01 6.30E-02 4.61E-04 0.00E+00 0.00E+00 
cm243 4.19E+01 4.16E+00 3.65E-01 3.21E-02 2.82E-03 2.48E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
cm244 1.40E+04 3.69E+02 8.02E+00 1.74E-01 3.78E-03 8.21E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
cm245 1.79E+00 1.78E+00 1.76E+00 1.75E+00 1.73E+00 1.72E+00 1.65E+00 1.52E+00 1.19E+00 7.92E-01 
cm246 1.21E+00 1.19E+00 1.17E+00 1.16E+00 1.14E+00 1.12E+00 1.04E+00 9.01E-01 5.80E-01 2.79E-01 
cm248 1.40E-04 1.40E-04 1.40E-04 1.40E-04 1.40E-04 1.40E-04 1.40E-04 1.39E-04 1.39E-04 1.37E-04 
co 58 7.70E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
co 60 5.99E+03 2.24E-02 4.33E-08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
cs134 4.05E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
cs135 6.34E-01 6.34E-01 6.34E-01 6.34E-01 6.34E-01 6.34E-01 6.34E-01 6.34E-01 6.33E-01 6.32E-01 
cs137 1.05E+05 1.17E+04 1.16E+03 1.15E+02 1.14E+01 1.13E+00 1.08E-05 9.98E-16 0.00E+00 0.00E+00 
eu150 7.54E-05 1.20E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
eu152 4.54E+00 3.24E-02 1.79E-04 9.85E-07 5.43E-09 2.99E-11 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
eu154 6.15E+03 2.88E+00 9.02E-04 2.82E-07 8.83E-11 2.77E-14 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
eu155 1.80E+03 1.39E-03 5.15E-10 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
fe 55 7.27E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
gd153 1.78E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
h 3 4.95E+02 2.37E+00 8.58E-03 3.10E-05 1.12E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
ho166m 3.43E-03 3.24E-03 3.06E-03 2.89E-03 2.73E-03 2.57E-03 1.93E-03 1.08E-03 1.91E-04 1.06E-05 
i129 3.60E-02 3.60E-02 3.60E-02 3.60E-02 3.60E-02 3.60E-02 3.60E-02 3.60E-02 3.60E-02 3.60E-02 
in113m 1.67E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
kr 85 5.79E+03 1.24E+01 1.93E-02 3.01E-05 4.68E-08 7.27E-11 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page IX-7 of IX-10 
Attachment IX 
Maximum PWR Assembly Radionuclide Inventories for Short Decay Times 
Age: 5 yr 100 yr 200 yr 300 yr 400 yr 500 yr 1000 yr 2000 yr 5000 yr 10000 yr 
mn 54 8.46E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
mo 93 7.22E-02 7.07E-02 6.94E-02 6.80E-02 6.66E-02 9.39E-03 5.93E-02 4.86E-02 2.68E-02 9.94E-03 
nb 91 2.93E-05 2.66E-05 2.40E-05 2.17E-05 1.96E-05 1.77E-05 1.06E-05 3.83E-06 0.00E+00 0.00E+00 
nb 93m 4.87E+01 2.26E+00 1.48E+00 1.46E+00 1.46E+00 7.74E-03 1.46E+00 1.44E+00 1.42E+00 1.41E+00 
nb 94 1.37E+00 1.37E+00 1.36E+00 1.35E+00 1.34E+00 6.21E-02 1.32E+00 1.27E+00 1.15E+00 9.71E-01 
nb 95 3.48E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
nb 95m 1.80E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
ni 59 2.96E+00 2.96E+00 2.95E+00 2.95E+00 2.94E+00 2.48E-01 2.93E+00 2.90E+00 2.82E+00 2.70E+00 
ni 63 4.52E+02 2.34E+02 1.17E+02 5.86E+01 2.93E+01 1.24E+00 4.60E-01 4.52E-04 0.00E+00 0.00E+00 
np235 1.73E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
np236 3.45E-05 3.45E-05 3.45E-05 3.45E-05 3.45E-05 3.44E-05 3.43E-05 3.41E-05 3.35E-05 3.25E-05 
np237 4.01E-01 4.86E-01 5.79E-01 6.58E-01 7.26E-01 7.83E-01 9.66E-01 1.08E+00 1.11E+00 1.11E+00 
np238 4.58E-02 2.87E-02 1.76E-02 1.07E-02 6.57E-03 4.02E-03 3.44E-04 2.52E-06 0.00E+00 0.00E+00 
np239 6.00E+01 5.95E+01 5.89E+01 5.84E+01 5.78E+01 5.73E+01 5.46E+01 4.97E+01 3.75E+01 2.34E+01 
pa231 4.18E-05 4.84E-05 5.53E-05 6.22E-05 6.91E-05 7.61E-05 1.11E-04 1.83E-04 4.11E-04 8.26E-04 
pa233 4.01E-01 4.86E-01 5.79E-01 6.58E-01 7.26E-01 7.83E-01 9.66E-01 1.08E+00 1.11E+00 1.11E+00 
pa234 1.85E-04 1.85E-04 1.85E-04 1.85E-04 1.85E-04 1.85E-04 1.85E-04 1.85E-04 1.85E-04 1.85E-04 
pa234m 1.42E-01 1.42E-01 1.42E-01 1.42E-01 1.42E-01 1.42E-01 1.42E-01 1.42E-01 1.42E-01 1.42E-01 
pb211 0.00E+00 4.49E-05 5.32E-05 6.01E-05 6.70E-05 7.40E-05 1.09E-04 1.83E-04 4.12E-04 8.26E-04 
pb212 4.57E-02 3.00E-02 1.11E-02 4.11E-03 1.52E-03 5.66E-04 7.00E-06 3.04E-06 0.00E+00 0.00E+00 
pd107 1.60E-01 1.60E-01 1.60E-01 1.60E-01 1.60E-01 1.60E-01 1.60E-01 1.60E-01 1.60E-01 1.60E-01 
pm145 5.12E-03 1.24E-04 2.48E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
pm146 2.64E+00 1.77E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
pm147 2.29E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
po212 2.93E-02 1.92E-02 7.10E-03 2.63E-03 9.76E-04 3.63E-04 4.49E-06 1.95E-06 0.00E+00 0.00E+00 
po215 0.00E+00 4.49E-05 5.32E-05 6.01E-05 6.70E-05 7.40E-05 1.09E-04 1.83E-04 4.12E-04 8.26E-04 
po216 4.57E-02 3.00E-02 1.11E-02 4.11E-03 1.52E-03 5.66E-04 7.00E-06 3.04E-06 0.00E+00 0.00E+00 
pr144 5.80E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
pr144m 8.12E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
pt193 8.74E-05 2.34E-05 5.85E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
pu236 3.46E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
pu238 6.80E+03 3.21E+03 1.46E+03 6.64E+02 3.02E+02 1.38E+02 2.77E+00 2.19E-03 0.00E+00 0.00E+00 
pu239 1.83E+02 1.83E+02 1.82E+02 1.82E+02 1.82E+02 1.81E+02 1.79E+02 1.76E+02 1.65E+02 1.47E+02 
pu240 4.01E+02 4.34E+02 4.30E+02 4.26E+02 4.22E+02 4.17E+02 3.96E+02 3.56E+02 2.59E+02 1.53E+02 
pu241 8.00E+04 8.14E+02 8.24E+00 1.80E+00 1.74E+00 1.72E+00 1.65E+00 1.52E+00 1.19E+00 7.94E-01 
pu242 3.34E+00 3.34E+00 3.34E+00 3.34E+00 3.34E+00 3.34E+00 3.33E+00 3.33E+00 3.32E+00 3.29E+00 
ra223 0.00E+00 4.49E-05 5.32E-05 6.01E-05 6.70E-05 7.40E-05 1.09E-04 1.83E-04 4.12E-04 8.26E-04 
ra224 4.57E-02 3.00E-02 1.11E-02 4.11E-03 1.52E-03 5.66E-04 7.00E-06 3.04E-06 0.00E+00 0.00E+00 
rb 87 2.13E-05 2.13E-05 2.13E-05 2.13E-05 2.13E-05 2.13E-05 2.13E-05 2.13E-05 2.13E-05 2.13E-05 
rh102 8.20E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
rh106 1.33E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
rn219 0.00E+00 4.49E-05 5.32E-05 6.01E-05 6.70E-05 7.40E-05 1.09E-04 1.83E-04 4.12E-04 8.26E-04 
rn220 4.57E-02 3.00E-02 1.11E-02 4.11E-03 1.52E-03 5.66E-04 7.00E-06 3.04E-06 0.00E+00 0.00E+00 
ru106 1.33E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
sb125 2.14E+03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
sb126 9.57E-02 9.56E-02 9.55E-02 9.55E-02 9.54E-02 9.53E-02 9.50E-02 9.44E-02 9.24E-02 8.93E-02 
sb126m 6.83E-01 6.83E-01 6.82E-01 6.82E-01 6.81E-01 6.81E-01 6.79E-01 6.74E-01 6.60E-01 6.38E-01 
se 79 7.35E-02 7.35E-02 7.35E-02 7.35E-02 7.35E-02 7.34E-02 7.34E-02 7.32E-02 7.28E-02 7.20E-02 
sm145 2.05E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
sm151 3.19E+02 1.54E+02 7.11E+01 3.29E+01 1.52E+01 7.05E+00 1.50E-01 6.77E-05 0.00E+00 0.00E+00 
sn113 1.67E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page IX-8 of IX-10 
Attachment IX 
Maximum PWR Assembly Radionuclide Inventories for Short Decay Times 
Age: 5 yr 100 yr 200 yr 300 yr 400 yr 500 yr 1000 yr 2000 yr 5000 yr 10000 yr 
sn119m 1.01E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
sn121 2.78E+00 8.39E-01 2.38E-01 6.75E-02 1.91E-02 3.34E-05 9.91E-06 3.33E-11 0.00E+00 0.00E+00 
sn121m 3.58E+00 1.08E+00 3.07E-01 8.70E-02 2.47E-02 4.30E-05 1.28E-05 4.30E-11 0.00E+00 0.00E+00 
sn123 2.53E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
sn126 6.83E-01 6.83E-01 6.82E-01 6.82E-01 6.81E-01 6.81E-01 6.79E-01 6.74E-01 6.60E-01 6.38E-01 
sr 90 6.52E+04 6.29E+03 5.36E+02 4.57E+01 3.89E+00 0.00E+00 1.49E-06 3.00E-17 0.00E+00 0.00E+00 
tb160 4.00E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
tc 98 1.57E-05 1.57E-05 1.57E-05 1.57E-05 1.57E-05 1.57E-05 1.57E-05 1.57E-05 1.57E-05 1.57E-05 
tc 99 1.34E+01 1.34E+01 1.34E+01 1.34E+01 1.34E+01 2.51E-04 1.33E+01 1.33E+01 1.32E+01 1.30E+01 
te123m 1.01E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
te125m 5.21E+02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
te127 6.27E-02 3.60E-02 3.60E-02 3.60E-02 3.60E-02 0.00E+00 3.60E-02 3.60E-02 3.60E-02 3.60E-02 
te127m 6.40E-02 6.34E-01 6.34E-01 6.34E-01 6.34E-01 0.00E+00 6.34E-01 6.34E-01 6.33E-01 6.32E-01 
th227 0.00E+00 4.43E-05 5.24E-05 5.92E-05 6.61E-05 7.29E-05 1.08E-04 1.81E-04 4.06E-04 8.15E-04 
th228 4.56E-02 2.99E-02 1.11E-02 4.11E-03 1.52E-03 5.66E-04 7.00E-06 3.04E-06 0.00E+00 0.00E+00 
th230 3.33E-05 1.12E-03 3.10E-03 5.48E-03 8.04E-03 1.07E-02 2.41E-02 5.08E-02 1.29E-01 2.53E-01 
th231 3.28E-03 3.30E-03 3.32E-03 3.34E-03 3.35E-03 3.37E-03 3.46E-03 3.64E-03 4.14E-03 4.91E-03 
th234 1.42E-01 1.42E-01 1.42E-01 1.42E-01 1.42E-01 1.42E-01 1.42E-01 1.42E-01 1.42E-01 1.42E-01 
tl207 0.00E+00 4.48E-05 5.30E-05 5.99E-05 6.68E-05 7.38E-05 1.09E-04 1.83E-04 4.11E-04 8.24E-04 
tl208 1.64E-02 1.08E-02 3.98E-03 1.48E-03 5.48E-04 2.04E-04 2.52E-06 1.09E-06 0.00E+00 0.00E+00 
tm171 4.96E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
u232 5.97E-02 2.91E-02 1.08E-02 4.00E-03 1.48E-03 5.51E-04 6.83E-06 3.01E-06 0.00E+00 0.00E+00 
u233 2.42E-05 2.25E-04 4.57E-04 7.27E-04 1.03E-03 1.36E-03 3.28E-03 7.79E-03 2.21E-02 4.56E-02 
u234 5.21E-01 1.80E+00 2.43E+00 2.71E+00 2.84E+00 2.90E+00 2.95E+00 2.94E+00 2.92E+00 2.88E+00 
u235 3.28E-03 3.30E-03 3.32E-03 3.34E-03 3.35E-03 3.37E-03 3.46E-03 3.64E-03 4.14E-03 4.91E-03 
u236 2.23E-01 2.24E-01 2.25E-01 2.27E-01 2.28E-01 2.29E-01 2.35E-01 2.46E-01 2.73E-01 3.03E-01 
u237 1.91E+00 1.95E-02 1.97E-04 4.31E-05 4.15E-05 4.12E-05 3.95E-05 3.64E-05 2.85E-05 1.90E-05 
u238 1.42E-01 1.42E-01 1.42E-01 1.42E-01 1.42E-01 1.42E-01 1.42E-01 1.42E-01 1.42E-01 1.42E-01 
y 90 6.53E+04 6.29E+03 5.36E+02 4.57E+01 3.89E+00 0.00E+00 1.49E-06 3.00E-17 0.00E+00 0.00E+00 
y 91 1.40E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
zn 65 4.64E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 
zr 93 1.41E+00 1.41E+00 1.41E+00 1.41E+00 1.41E+00 3.87E-03 1.41E+00 1.40E+00 1.40E+00 1.40E+00 
zr 95 1.53E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page IX-9 of IX-10 
Attachment IX 
Maximum PWR Assembly Radionuclide Inventories for Long Decay Times 
Age: 10000.0 yr 20000.0 yr 30000.0 yr 100000. yr 300000. yr 1000000 yr 
ac225 1.49E-02 4.82E-02 8.80E-02 3.51E-01 7.58E-01 8.63E-01 
ac227 8.26E-04 1.74E-03 2.69E-03 7.69E-03 1.01E-02 1.02E-02 
am241 8.25E-01 3.51E-01 1.55E-01 5.15E-04 4.24E-11 0.00E+00 
am243 2.34E+01 9.15E+00 3.57E+00 4.95E-03 1.21E-05 1.18E-05 
at217 1.49E-02 4.82E-02 8.80E-02 3.51E-01 7.58E-01 8.63E-01 
bi210 1.97E-01 4.30E-01 6.36E-01 1.51E+00 1.64E+00 3.89E-01 
bi211 8.26E-04 1.74E-03 2.69E-03 7.69E-03 1.01E-02 1.02E-02 
bi213 1.49E-02 4.82E-02 8.80E-02 3.51E-01 7.58E-01 8.63E-01 
bi214 1.97E-01 4.30E-01 6.36E-01 1.51E+00 1.64E+00 3.89E-01 
c 14 1.59E-01 4.75E-02 1.42E-02 0.00E+00 0.00E+00 0.00E+00 
ca 41 1.39E-04 1.30E-04 1.22E-04 7.60E-05 1.98E-05 0.00E+00 
ce142 3.02E-05 3.02E-05 3.02E-05 3.02E-05 3.02E-05 3.02E-05 
cl 36 1.03E-02 1.00E-02 9.80E-03 8.34E-03 5.26E-03 1.05E-03 
cm245 7.92E-01 3.51E-01 1.55E-01 5.14E-04 4.23E-11 0.00E+00 
cm246 2.79E-01 6.44E-02 1.49E-02 0.00E+00 0.00E+00 0.00E+00 
cm248 1.37E-04 1.34E-04 1.32E-04 1.14E-04 7.60E-05 1.82E-05 
cs135 6.32E-01 6.30E-01 6.28E-01 6.15E-01 5.79E-01 4.69E-01 
fr221 1.49E-02 4.82E-02 8.80E-02 3.51E-01 7.58E-01 8.63E-01 
fr223 0.00E+00 0.00E+00 0.00E+00 1.06E-04 1.40E-04 1.40E-04 
i129 3.60E-02 3.60E-02 3.60E-02 3.58E-02 3.55E-02 3.44E-02 
mo 93 9.94E-03 1.37E-03 1.89E-04 0.00E+00 0.00E+00 0.00E+00 
nb 93m 1.41E+00 1.39E+00 1.39E+00 1.34E+00 1.23E+00 8.93E-01 
nb 94 9.71E-01 6.91E-01 4.91E-01 4.50E-02 4.86E-05 0.00E+00 
ni 59 2.70E+00 2.46E+00 2.24E+00 1.17E+00 1.85E-01 2.86E-04 
np236 3.25E-05 3.06E-05 2.88E-05 1.89E-05 5.66E-06 0.00E+00 
np237 1.11E+00 1.11E+00 1.11E+00 1.09E+00 1.02E+00 8.11E-01 
np239 2.34E+01 9.15E+00 3.57E+00 4.95E-03 1.21E-05 1.18E-05 
pa231 8.26E-04 1.74E-03 2.69E-03 7.69E-03 1.01E-02 1.02E-02 
pa233 1.11E+00 1.11E+00 1.11E+00 1.09E+00 1.02E+00 8.11E-01 
pa234 1.85E-04 1.85E-04 1.85E-04 1.85E-04 1.85E-04 1.85E-04 
pa234m 1.42E-01 1.42E-01 1.42E-01 1.43E-01 1.43E-01 1.43E-01 
pb209 1.49E-02 4.82E-02 8.80E-02 3.51E-01 7.58E-01 8.63E-01 
pb210 1.97E-01 4.30E-01 6.36E-01 1.51E+00 1.64E+00 3.89E-01 
pb211 8.26E-04 1.74E-03 2.69E-03 7.69E-03 1.01E-02 1.02E-02 
pb214 1.97E-01 4.30E-01 6.36E-01 1.51E+00 1.64E+00 3.89E-01 
pd107 1.60E-01 1.59E-01 1.59E-01 1.58E-01 1.55E-01 1.44E-01 
po210 1.97E-01 4.30E-01 6.36E-01 1.51E+00 1.64E+00 3.89E-01 
po213 1.46E-02 4.72E-02 8.61E-02 3.44E-01 7.42E-01 8.45E-01 
po214 1.97E-01 4.30E-01 6.36E-01 1.51E+00 1.64E+00 3.89E-01 
po215 8.26E-04 1.74E-03 2.69E-03 7.69E-03 1.01E-02 1.02E-02 
po218 1.97E-01 4.30E-01 6.36E-01 1.51E+00 1.64E+00 3.90E-01 
pu239 1.47E+02 1.14E+02 8.68E+01 1.18E+01 3.76E-02 1.18E-05 
pu240 1.53E+02 5.32E+01 1.85E+01 1.14E-02 2.43E-07 0.00E+00 
pu241 7.94E-01 3.51E-01 1.55E-01 5.15E-04 4.24E-11 0.00E+00 
pu242 3.29E+00 3.23E+00 3.17E+00 2.79E+00 1.92E+00 5.25E-01

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page IX-10 of IX-10 
Attachment IX 
Maximum PWR Assembly Radionuclide Inventories for Long Decay Times 
Age: 10000.0 yr 20000.0 yr 30000.0 yr 100000. yr 300000. yr 1000000 yr 
ra223 8.26E-04 1.74E-03 2.69E-03 7.69E-03 1.01E-02 1.02E-02 
ra225 1.49E-02 4.82E-02 8.80E-02 3.51E-01 7.58E-01 8.63E-01 
ra226 1.97E-01 4.30E-01 6.36E-01 1.51E+00 1.64E+00 3.90E-01 
rb 87 2.13E-05 2.13E-05 2.13E-05 2.13E-05 2.13E-05 2.13E-05 
rn219 8.26E-04 1.74E-03 2.69E-03 7.69E-03 1.01E-02 1.02E-02 
rn222 1.97E-01 4.30E-01 6.36E-01 1.51E+00 1.64E+00 3.90E-01 
sb126 8.93E-02 8.33E-02 7.77E-02 4.78E-02 1.20E-02 9.34E-05 
sb126m 6.38E-01 5.95E-01 5.55E-01 3.42E-01 8.54E-02 6.67E-04 
se 79 7.20E-02 7.05E-02 6.90E-02 5.96E-02 3.91E-02 8.99E-03 
sn126 6.38E-01 5.95E-01 5.55E-01 3.42E-01 8.54E-02 6.67E-04 
tc 98 1.57E-05 1.57E-05 1.56E-05 1.55E-05 1.50E-05 1.33E-05 
tc 99 1.30E+01 1.25E+01 1.21E+01 9.64E+00 5.00E+00 5.02E-01 
th227 8.15E-04 1.71E-03 2.65E-03 7.58E-03 9.99E-03 1.00E-02 
th229 1.49E-02 4.82E-02 8.80E-02 3.51E-01 7.58E-01 8.63E-01 
th230 2.53E-01 4.81E-01 6.81E-01 1.53E+00 1.62E+00 3.84E-01 
th231 4.91E-03 6.19E-03 7.17E-03 9.78E-03 1.02E-02 1.02E-02 
th234 1.42E-01 1.42E-01 1.42E-01 1.43E-01 1.43E-01 1.43E-01 
tl207 8.24E-04 1.73E-03 2.68E-03 7.67E-03 1.01E-02 1.01E-02 
tl209 3.13E-04 1.01E-03 1.85E-03 7.37E-03 1.59E-02 1.81E-02 
u233 4.56E-02 9.11E-02 1.35E-01 3.88E-01 7.71E-01 8.61E-01 
u234 2.88E+00 2.80E+00 2.73E+00 2.26E+00 1.35E+00 3.10E-01 
u235 4.91E-03 6.19E-03 7.17E-03 9.78E-03 1.02E-02 1.02E-02 
u236 3.03E-01 3.31E-01 3.41E-01 3.45E-01 3.43E-01 3.36E-01 
u237 1.90E-05 8.39E-06 3.71E-06 0.00E+00 0.00E+00 0.00E+00 
u238 1.42E-01 1.42E-01 1.42E-01 1.43E-01 1.43E-01 1.43E-01 
zr 93 1.40E+00 1.39E+00 1.39E+00 1.34E+00 1.23E+00 8.93E-01

Environmental and Nuclear Engineering Design Calculation 
Title: PWR Source Term Generation and Evaluation 
Document Identifier: 000-00C-MGR0-00100-000-00B Page XI-1 of XI-1 
Attachment XI  Evolution in Time of Thermal Power and Total Radioactivity 
The following figures compare the evolution in time of the heat generated and total radioactivity 
of different fuel assemblies (data are presented in the Spreadsheet ATTACH_XI.XLS): 
1.E- 01 
1.E+00 
1.E+01 
1.E+02 
1.E+03 
1.E+04 
1.E+05 
1.E+06 
0.1 1 10 100 1000 10000 100000 1000000 
Cooling Time (years) 
Heat Output (Watts) 
BWR 40GWd/MTU BWR 75GWd/MTU PWR 48GWd/MTU PWR 80GWd/MTU 
Figure XI 1. Thermal Power after Discharge  PWR / BWR Comparison 
1.E+00 
1.E+01 
1.E+02 
1.E+03 
1.E+04 
1.E+05 
1.E+06 
1.E+07 
1.E+08
0.1 1 10 100 1000 10000 100000 1000000 
Cooling Time (years) 
Radioactivity (Curies) 
BWR 40GWd/MTU BWR 75GWd/MTU PWR 48GWd/MTU PWR 80GWd/MTU 
Figure XI 2. Radioactivity after Discharge  PWR / BWR Comparison