ML033520008

CRC Depletion Calculations for the Rodded Assemblies in Batches 10 and 11 of Crystal River Unit 3

ML033520008
Person / Time
Site:	Crystal River, WM-00011
Issue date:	09/03/1997
From:	Benton H, Thomas D, Wright K US Dept of Energy, Office of Civilian Radioactive Waste Mgmt (OCRWM)
To:
References
-RFPFR BBA00000-01717-0200-00044 Rev 00
Download: ML033520008 (174)

Text

NOL.19971218.1080 Design Analysis Cover Sheet CRWMS/M&O L Compete l applicabe Ite IPage: I Of: 82

2. DESIGN ANALYSIS TITLE I CRC Depletion Calculations for dte Rodded Assemblies In Batches 10 and 11 of Crystal River Unit 3

3. DOCUMENT IDENTIFIER Elncluding Rev. No.1 4. TOTAL PAGES BBA00000-0l1717-020400044 REV 00 8t2 S. TOTAL ATTACHMENTS 6. ATTACHMENT NUMBERS - NO. OF PAGES IN EACH 10 This information Is provided in Section 9.

Printed Name Skbnatem Date

7. Originator P. L Jht ,

S. Checker . 7

9. Lead Design Engineer 7J A L

10. Department Manager 4 f A.

$A &arcwo. Y 4  !

'11. REMARKS Attachments V through X identified as REV 00 were moved to independent rcferences.

CAP- lEffeW 0U02/S'

• 0492 f~. 03110AW

Design Analysis Revision Record CRWMSIM&O L DESIGN ANALYSIS TIM I teIVJffD&*4p4P5C*hI.AWS.

IPage: 2 Of: 82 CRC Depletion Calculationis for dhe Rtodded Assemblies in Batrhes 10 and I11of Crysta Rime Unit 3 2.0OCD 1 ENWiTIM~ lrdu ngRaw. No BBAOOOOOO-01717-0200-ODD44 REV 00 4'. Revision No. S. Description of Ravislon 00o Initial suance Copy Iw StlrKMIN SA?*kVIgc,@1UIgI sv SWMU I:

Waste Package Development Design Analysis

Title:

CRC Dpletion Calculatins fr the Rodded Assmblies in Batches 10 and I Ioft CysWa River Unh 3 Document identifler BBAOOOOO.1717.020040044REVOO Page 3 of 82 Table of Contents him Enz

1. Purpose .................................................... S

2. Quality Assurance ........................................................... 5

3. Method ................ S

4. Design Inputs ............  ; 6 4.1 DesignParameters .. 6 4.1.1 Fuel Assembly Descriptions ............ 6 4.1.2 Burnable Poison Rod Assembly (BPRA) Description ............ 7 4.1.3 Control Rod Assembly (CRA) Description ............. 8 4.1.4 Axial Power Shaping Rod Assembly (APSRA) Description ......... ....

4.1.S System Pressure ................ 9 4.1.6 Fuel Assembly Insertion, Burnable Poison Loading, and Control Bank Insertion Histories .......................... 9 4.1.7 Fuel Assembly Insertion Position Histories ................................ 10 4.1.8 ReactorCycle History Data .......................................... 11 4.1.9 Boron LetdownData ............................................... 13 4.1.10 Bumup, Fuel Temperature, and Moderator Specific Volume Data ......... . 15 4.1.11 Insertion History Data for CRA's and APSRA's .......... ............... 24 4.2 Criteria .............. .......... ............................ 26 4.3 Assumptions ........................ ............................ 26 4.4 Codes and Standards . ........................ 27

5. References ............. 27

6. Use of Computer Software ............................. 28 6.1 Software Approved for QA Work ...............................28 6.2 Software Routines ............................. 29

7. Design Analysis ............ 31.

7.1 Assembly Depletion Calculation Procedure ..................................... 31 7.2 Path B Unit Cell Model Development ............. ............................ 32 7.3 Cycle Irradiation History Layouts for the Depletion of the Rodded Assemblies in Batch 10 of Crystal River Unit3 .................................................... 44 7.4 The Commercial Reactor Assembly Follow Taskmaster (CRAFT) Code & Usage ....... 53 7.5 Input & Output Filename Descriptions for CRAFT and SAS2H 56 56.............

7.6 Rodded Assembly Depletion Calculations for Fuel Batch 10 of Crystal River Unit 3 ..... 57 7.7 Isotopic Results ......................................................... so

8. Conclusions ....... 81

Waste Package Development Design Analysis Unit 3 Ttle: CRCDpletion Calculations for the Rodded Assemblies in Batches 10 and 11 OfiCrystal River Document Ientifier BBAOOOO-01717.0200-00044 REV 00 Pagem of82

81

9. Atachmnents ..........

Waste Package Devolopment Design Analysis

Title:

CRC Depletion Calculations for the Rodded Assemblies inBatches 10 and 11 of Cystal iver Unit 3 Document Identlfler. BBA00000017170200W00044 REV 00 Page 5 of 82

1. Purpose The purpose of this design analysis is to document the SAS2H depletion calculations of certain rodded fuel assemblies firom batches 10 and 11 of the Crystal River Unit 3 pressurized water reactor (PWR) that are required for Commercial Reactor Critical (CRC) evaluations to support development of the disposal criticality methodology. A rodded assembly is one that contains a control rod assembly (CRA) or an axial power shaping rod assembly (APSRA) for some period of time during its Irradiation history. The objective of this analysis is to provide SAS2H calculated isotopic compositions of depleted fuel and depleted burnable poison for each fuel assembly to be used in subsequent CRC reactivity calculations containing the fuel assemblies. It should be noted that there are currently no rodded assembly depletion calculations for fuel batch 11 documented in this analysis. If future CRC evaluations of Crystal River Unit 3 require depletion calculations for rodded assemblies from batch 1, those depletion calculations will be added to this analysis in a revision.

2. Quality Assurance The Quality Assurance (QA) program applies to this analysis. The work reported in this document is part of the criticality disposal methodology development that will eventually support the License Application Design phase. This activity, when appropriately confirned, can impact the proper functioning of the Mined Geologic Disposal System (MGDS) waste package; the waste package has been identified as an MGDS Q-List item important to safety and waste isolation (pp. 4, 15, Ref. 5.6).

The waste package is on the Q-List by direct inclusion by the Deparanent of Energy (DOE), without conducting a QAP-2-3 evaluation. As determined by an evaluation performed in accordance with QAP-2-0, Conduct ofActivities, the work performed for this analysis is subject to Quality Assurance Requirements and Description(QARD; Ref 5.2) requirements. As specified in NLP-3-1 8, "Documentation of QA Controls on Drawings, Specifications, Design Analyses, and Technical Documents', the development of this analysis is subject to QA controls. The Waste Package Development Department (WPDD) responsible manager has selected the applicable procedural controls for this activity commensurate with the work control activity evaluation entitled "Perform Criticality, Thermal, Structural, arid Shielding Analyses" (Ref. 5.1).

The work reported in this document is part of the CRC neutronic analyses to support the development of the disposal criticality methodology. All design parameters utilized in this analysis are from a qualified source (Ref. 5.3) which was developed under a U. S. Nuclear Regulatory Commission approved QA program. Therefore, all design parameters utilized in this analysis are qualified.

3. Method The method for obtaining fuel and burnable poison isotopic compositions at specific points during each assembly's irradiation history is based upon the use of the SAS2H control module of the SCALE 4.3 modular code system (Ref. 5.4). The effective full-power day (EFPD) times during reactor operation that correspond to a CRC evaluation are called 'statepoints". An assembly depletion calculation between two CRC statepoints is called a "statepoint calculation". The depleted fuel and depleted burnable poison compositions may be used in subsequent CRC reactivity calculations. The SAS2H

Waste Package Development ___ Design Analysis

Title:

CRC Depletion Calculations for the Rodded Assemblies In Batches 10 uad 11 of Cystal River Unit 3 Document Idenutifr. BBAOOOOOO.01717.0200.00 44 REV 00 Pabe 6 oft82 input decks are automatically developed by the CRAFT program which is a software routine documented in Sections 7.4 and 7.5 and Attachment I of reference S. 1. The SAS2H input decks and depletion models are developed using actual assembly specifications, actual assembly irradiation histories, and actual CRA and APSRA insertion histories. The isotopic results obtained from the SAS2H depletion calculations are reviewed and analyzed to identify any anomalous results which may propagate to subsequent CRC reactivity calculations and ultimately impact the development of the disposal criticality methodology.

4. Design Inputs The design inputs documented in this analysis describe the design specifications and irradiation histories for certain rodded fuel assemblies in fuel batch 10 of the Crystal River Unit 3 PWR. There are currently no rodded assembly depletion calculations required for fuel batch I1. All of the design inputs listed in this analysis are obtained from reference 5.3, which is a reference summarizing the necessary input parameters.

4.1 Design Parameters 4.1.1 Fuel Assembly Descriptions Table 4. .1 -l contains a description of the rodded fuel assemblies corresponding to fuel batch 10 of Crystal River Unit 3. All fuel assemblies within a given fuel batch have the same characteristics as identified in Table 4.1.1-1.

Table 4.1.1-1 Fuel Assembly Descriptions for Batch 10 of Crystal River Unit 3 Fuel Batch Identifier Parameter 10 Assembly Type' Mark-B4Z Weight Percent U-235 3.94 kg of U per Assembly 463.63 Fuel Height (cm) 360.172 Fuel Pellet OD' (cm) 0.936244 Fuel Rod Clad OD (cm) 1.0922 Fuel Rod Clad IDV (cm) 0.95758 Spacer Grid Material Zircaloy Volume Fraction of Spacer Grid in Moderator 0.008165257

Waste Package Development Design Analysis

Title:

CRC Depletion Calculations for the Rodded Assemblies in Batches 10 and 11 of Coysal RIVer Unit 3 Document Identifier BBAOOOOOO.01717-00-00044 REV 00 Page 7 of 82 Fuel Batch Identifier Parameter Guide Tube Material Zircaloy.

Guide Tube OD (cm) 1.3462 Guide Tube ID (cm) 1.26492 Instrument Tube Material Zircaloy Instrument Tube OD (cm) 1.38193 Instrument Tube ID (cm) 1.12014 Array Size 1SxIS Number of Fuel Rods 208 Number of Guide Tubes 16 Number of Instr. Tubes 1l Pin Pitch (cm) 1.44272 Assembly Pitch (cm) 21.81098

'OD - Outer Diameter 2ID - Inner Diameter 4.1.2 Burnable Poison Rod Assembly (BPRA) Description Table 4.1.2-1 contains a description of the burnable poison rod assembly utilized in the various fuel assemblies from fuel batch 10 of Crystal River Unit 3. The rods of the BPRA are inserted into the guide tubes of the fiul assembly during irradiation to produce a lower thermal flux which ultimately allows for longer fuel assembly burnup and better core power distributions.

Table 4.1.2-1 BPRA Descriptions for Use In Batch 10 of Crystal River Unit 3 Parameter Value Burnable Poison (BP) Material A]2 0,-B4C BP Density Wcc) 3.7 BP Pellet OD (cm) 0.8636 Burnable Poison Rod (BPR) Cladding Material Zircaloy BPR Cladding OD (cm)

• 1.0922

Waste Package Development Design Analysis

Title:

CRC Depition Calculations fbr the Rodded Asmblies inBatches 10 and 11 ofCYsa River Unit 3 Document Identifier. BBA00000001717.0200-0044 REV to Page 8 of 82 Parameter  ! Value BPR Cladding ID (cm) 0.9144 Number of BPRts in a BPRA 16-4.1.3 Control Rod Assembly (CRA) Description Table 4.1.3-1 contains a description of the control rod assembly utilized in the various fuel assemblies from fuel batch 10 of Crystal River Unit 3. The rods of the CRA are inserted into the guide tubes of the fuel assembly during irradiation to produce a local thermal flux depression which provides a mechanism for controlling the core power distribution (both radially and axially). Operating with CRAs inserted may also allow for extended fuel assembly burnup.

Table 4.1.3-1 CRA Descriptions for Use in Batch 10 of S~stal River Unit 3 Parameter Value Control Rod Neutron Absorbing Material Ag-In-Cd with a 79.8, 15.0, and 5.0 weight percent by mass composition, respectively Ag-In-Cd Density (g/cc) 10.17 Absorber Pellet OD (cm) 0.99568 Control Rod (CR) Cladding Material Stainless Steel 304 (SS304)

CR Cladding OD (cm) 1.11760 CR Cladding ID (cm) 1.01092 Number of CR's in a CRA 16 4.1.4 Axial Power Shaping Rod Assembly (APSRA) Description Tables 4.1.4-1 contains a description of the axial power shaping rod assemblies utilized in the various fuel assemblies fiom fuel batch 10 of Crystal River Unit 3. The rods of the APSRA are inserted into the guide tubes of the fuel assembly during irradiation to produce a local thernal flux depression which provides a mechanism for controlling the core power distribution (both radially and axially). Operating with APSRAs inserted allows for a more uniform axial burnup which results in longer average fuel assembly burnups. There are two tMes of APSRAs (black and g ) utilized in Crystal River Unit 3.

The black APSRAs utilize Ag-In-Cd as the neutron absorbing material. The grey APSRAs utilize Inconel as the neutron absorbing material. As the names indicate, the black APSRAs have a larger macroscopic neutron absorption cross-ection than the grey APSRAs. Assembly H12 from batch 10 is the only assembly depletion docwnenled in this analysis that contained an APSRA. This assembly contained a grey APSRA during Cycle-9.

Waste Package Development Design Analysis

Title:

CRC Depletion Calculations for the Rodded Assemblies InBatches 10 and II of Coysag River Unit 3 Document Identfler: BBAOOOODO.01717-020040044 REV -OPage 9 of 82 Table 4.1A1 Grey APSRA Description for Use In Batch 10 ofCryst RiverUnit 3 Parameter I Value APSRA Neutron Absorbing Material Inconel Inconel Density (glcc) 83 Absorber Pellet OD (cm) 0.95250 Axial Power Shaping Rod (APSR) Cladding Stainless Steel 304 (SS304)

Material APSR Cladding OD (cm) 1.11760 APSR Cladding ID (cm) 0.98044 Number of APSR's in an APSRA 16 4.1.5 System Pressure Crystal River Unit 3 is a pressurized water reactor that operates at a constant pressure of 2200 psia (pounds per square inch absolute).

4.1.6 Fuel Assembly Insertion, Burnable Poison Loading, and Control Bank Insertion Histories The actual irradiation histories of the fuel assemblies in batch 10 must be used to perform the various assembly depletion calculations relevant to the CRC analyses. Table 4.1.6-1 contains the assembly insertion, burnable poison (BP) loading, and control bank insertion histories for the rodded assemblies in fuel batch 10 which arF required for the CRC analyses of Crystal River Unit 3.

Waste Package Development Design Analysis

Title:

CRC Depletion Calculations for he Rodded Assemblies in Batches 10 and 11 of Qystal River Unit 3 Document identifier. BBAOOOOOo.01717.020000044 REV 00 Page 10 of 82 Table 4.1.6-1 Crystal River Unit 3, Batch 10, Rodded Fuel Assembly Insertiont BP Loading, and Control Bank Insertion Histories Assembly Assembly Location in Cycle Number/Bateb 8 9 Comments H04 1 10 2.0 CR6 CR6 not inserted H12 /10 2.0 CR8Grey APSRA H23 / 10 2.0 CR6 CR6 not Inserted H27a / 10 X CR7 The "X" indicates that the assembly is present in the cycle Indicated.

The "H" designation in the assembly number indicates that Cycle48 Is the assembly Initial insertion cycle.

The numeric inputs Indicate that assembly contained a BPRA in that cycle. These values Indicate the wt% of BgC in the A1,0 3-BC absorber.

CR6 refers to control bank 6.

CR7 refers to control bank 7.

CR8 refers to control bank 8 which In an APSRA bank.

"CR6 not Inserted" means that control rod bank 6 was not inserted In the assembly during reactor operation at power. Therefore, there Is no control redinsertion history data for these assemblies.

4.1.7 Fuel Assembly Insertion Position Histories The positions of the various assemblies in the core must be known to correlate the burnup, fuel temperature, and moderator specific volume data with the appropriate assembly. The assembly position data is also used to document the depletion cases so that the isotopic results may be identified at a later time for a specific assembly in a particular position of the core. Table 4.1.7-1 contains the assembly position histories for the rodded assemblies in batch 10 of Crystal River Unit 3 which are relevant to the CRC analyses. The assembly position identifiers refer to locations in a one-eighth core symmetrical arrangement for Crystal River Unit 3 as shown in Figure 4.1.7-1. The integer values (1-29) shown in Figure 4.1.7-1 are used in the SAS2H depletion calculations to identify the various assembly locations.

Table 4.1.7-1 Assembly Position Histories for the Rodded Assemblies from Batch 10 of Crystal River Unit 3 Assembly Assembly Location in Cycle Number 8__ 9 H04 HI1 H14 H12 _ _ _ _K12 L12 H23 M12LIO H27a N13_ H12

Waste Package Development Design Analysis

Title:

CRC Depietion Calculations for ie Rodded Assemblies in Batches 10 and I1 of Cystal River Unit 3 Document Identifier: BBA00000O0417170200044 REV 00 Page 11 of 82 8 9 10 11 12 I3 14 15 H [1-2 13 1 516 I 7 W-K ~~~~1 l1 12 10 L 1i 118 19 20 1 M 22 23 24 25 N 26 27 28 0 29 Figure 4.1.7-1 One-Eighth Symmetry Core Layout for Crystal River Unit 3 4.1.8 Reactor Cycle History Data Table 4.1.8-1 contains a listing of the Crystal River Unit 3 reactor cycle history data that is relevant to the SAS2H depletion calculations documented in this analysis. The time durations other than the days of downtime and the total cycle effective full power days presented in Table 4.1.8-1 are calculated using the appropriate dates from Table 4.1.8-1 and the Lotus 1-2-3 WDATEDIFW function.

Table 4.1.8-1 Crystal River Unit 3 Reactor Cycle History Data Relevant to the Depletion Calculations for the Rodded Assemblies in Batch 10 Crystal River. Unit-3. Cycle-9 Summary 06/21/90: Cycle Start Date 10/09/90: 97.6 EFPD Shutdown Date (10/10/90, Ref. 5.3) 10/25I90 Restart Date After the 97.6 EFPD Shutdown 12/12/90' 139.8 EFPD Shutdown Date 12118190: Restart Date After the 139.8 EFPD Shutdown 10/14/91: 404.0 EFPD Shutdown Date (10/1 1/91, Ref. 5.3) 11/27/91: Restart Date After the 404.0 EFPD Shutdown (1 1/24/91, Ref 5.3) 12/02/91: 409.6 EFPD Shutdown Date (12/03/91, Ref. S.3) 12/07/91: Restart Date After the 409.6 EFPD Shutdown (12108/91, Ref 5.3) 03/27/92: 515.5 EFPD Shutdown Date 04/04/92: Restart Date After the 515.5 EFPD Shutdown 04/30/92: Cycle End Date 110: Cycle Length in Calendar Days to 97.6 EFPD Date 48: Cycle Length in Calendar Days from 97.6 EFPD Restart to 139.8 EFPD Date

Waste Package Development Design Analysis

Title:

CRC Depletion Calculations for die Rodded Assenblies in Batches 10 and 11 of Ciystal River Unit 3 Document Identfier. BBAOOOOOO.01717-0200044 REV oo Page 12 of 82 Table 4.1.8-1 Crystal River Unit 3 Reactor Cycle History Data Relevant to the Depletion Calculations for the Rodded Assemblies In Batch 10 300: Cycle Length in Calendar Days from 139.8 EFPD Restart to 404.0 EFPD Date 5: Cycle Length in Calendar Days from 404.0 EFPD Restart to 409.6 EFPD Date 111: Cycle Length in Calendar Days from 409.6 EFPD Restart to 515.5 EFPD Date 26: Cycle Length in Calendar Days from 515.5 EFPD Restart to EOC 679: Total Cycle Length (Calendar Days) 15.5 : Days of Downtime During Shutdown at 97.6 EFPD 6.2: Days of Downtime During Shutdown at 139.8 EFPD 44.4: Days of Downtime During Shutdown at 404.0 EFPD 4.9: Days of Downtime During Shutdown at 409.6 EFPD 7.6: Days of Downtime During Shutdown at 515.5 EFPD 535.9: Total Cycle Effective Full Power Days 75: Calendar Days of Downtime Between Cycle 8 and 9 Crystal River. Unit-3. Cycle-9 Summary 07/14/92: Cycle Start Date 12/29/92: 158.8 EFPD Shutdown Date 12/31/92 Restart Date After the 158.8 EFPD Shutdown 03/04/93: 219.0 EFPD Shutdown Date 04/26/93 : Restart Date After the 219.0 EFPD Shutdown 09/18/93 : 363.1 EFPD Shutdown Date (09119/93, Ref. 5.3)

O9/O/93: Restart Date After the 363.1 EFPD Shutdown 04/07/94 : Cycle End Date 168: Cycle Length in Calendar Days to 158.8 EFPD Date 63: Cycle Length in Calendar Days from 158.8 EFPD Restart to 219.0 EFPD Date 145: Cycle Length in Calendar Days from 219.0 EFPD Restart to 363.1 EFPD Date 199: Cycle Length in Calendar Days from 363.1 EFPD Restart to EOC 632: Total Cycle Length (Calendar Days )

2.146: Days of Downtime During Shutdown at 158.8 EFPD

Waste Package Development Design Analysis

Title:

CRC Depletion Calculations for the Rodded Assemblies InBatches 10 and 11 ofC River Uni 3

( Documentidentifier. BBA00000001717.0200.00044WREV* Page 13 of 82 Table 4.1.8-1 Crystal River Unit 3 Reactor Cycle History Data Relevant to the Depletion Calculations for the Rodded Assemblies In Batch 10 53.125: Days of Downtime During Shutdown at 219.0 EFPD 1.625: Days of Downtime During Shutdown at 363.1 EFPD 557.23 : Total Cycle Effective Full Power Days 55: Calendar Days of Downtime Between Cycle 9 and 10 A number of the dates presented in Table 4.1.8-1 do not correspond directly with the dates presented in reference 5.3. The date contained in reference 5.3, is presented in parentheses next to each inconsistency. Inconsistencies in the restart and shutdown date values do not affect the calculations due to the fact that the depletions are based upon EFPD durations rather tanm calendar day durations. The various calendar day time periods between statepoints as presented in Table 4.1.8-1 are used for documentation purposes only. The cycle starting and ending dates are the only dates presented in Table 4.1.8-1 which are involved in calculations that ar documented in this analysis. A cycle's starting and ending dates are used to'calculate calendar day decay durations for fuel assemblies which skip that particular cycle. The days of downtime between cycles are not calculated from the dates presented in Table 4.1.8-1. The days of downtime between cycles are obtained directly from reference 5.3 in units of hours that are converted to days for presentation in Table 4.1.8-1 and use in this analysis. Therefore, no calculations documented in this analysis are affected by the date inconsistencies between Table 4.1.8-1 and reference 5.3.

4.1.9 Boron Letdown Data The boron letdown data provided in the Core Operations Reports for Cycles 8 and 9 of Crystal River Unit 3 is used to determine the soluble boron concentration in the moderator at the mid-point of each irradiation step in the various SAS2H depletion calculations performed to deplete the rodded fuel assemblies of batches i 0 and 11. The boron concentrations at the irradiation sep midpoint effective full-power day (EFPD) times are determined by linear interpolation between the measured values listed in Tables 4.1.9-1 and 4.1.9-2. The boron letdown data tables presented in this section are obtained from reference 5.3, which is a summnary compilation ofdata pertinent to CRC analyses for Crystal River Unit 3.

Table 4.1.9-1 Boron Letdown Data for Cycle 8 of Crystal River Unit 3 Exposure (EFPD) Boron Concentration (ppm) 11.2 1 1537 52.4 1455 78 1411

Waste Package Development Design Analysis

Title:

CRC DCpleti;n CacujatIOns for the ROdded Assembles InBatches 10 and I I of Gya River Unit 3 Document Idontifler. BBAOOOOOO.1717D0200-00044 REV 00 Page 14 of 82 Table 4.1.9-1 Boren Letdown Data for Cycle 8 of Crystal River Unit 3 Exposure fEfFD) Boron Concentration (ppm')

111.4 1332 154.4 *1176 194.8 1103 234:6 999

. 271.5 887 338 701 390.7 522 445.7 394 474 311 513.1 216 The acronym "ppm" means parts per million by mass of moderator.

Table 4.1.9-2 Boron Letdown Data for Cycle 9 of Crystal River Unit 3 Exposure (EFPD) Boron Concentration fpm) 22.1 1608 61.5 1535 145.7 1329 192.8 1201 211.3 1157 262 994 303.7 869 345.7 750 397.9 577 432.5 473 452.4 412 495.4 283

Waste Packaae Development Design Analysis

Title:

CRC Depletion Calculations for the Rodded Asemblies in Batches Io and 11 of Cysa River Unit 3 Document Identifier. BBAOOOOOO-01717.02000044 REV 00 Page 15 of 82 Table 4.1.9-2 Boron Letdown Data for Cycle 9 of Crystal River Unit 3 Exposure (EFPD)Boron Concentration (ppm) 543.4 136 4.1.10 Burnup, Fuel Temperature, and Moderator SpecificVolume Data Burnup, fuel temperature, and moderator specific volume data are required for each node of each assembly in each SAS2H depletion calculation. A set of nodal bumup data at the beginning and end of each SAS2H depletion calculation is required. A set of nodal fuel temperature and moderator specific volume data representative of full-power operation during each depletion calculat on of interest is required. Tables 4.1.10-1 through 4.1.10-4 contain the burnup, fuel temperature, and moderator specific volume data necessary to perform all depletion calculations for each of the rodded fuel assemblies from batches 10 and 11 of Crystal River Unit 3. The assembly heights corresponding to the axial nodes presented in Tables 4.1.10-1 through 4.1.10-4 are as follow: the top node (node 1) is 17.78 cm, the bottom node (node I8) is 22.352 cm, all other nodes are 20.0025 cm. The top of node I begins at the top of the active fuel region- The burnup data is presented in units of gigawatt-days per metric ton of uranium (GWd/MTIJ). The fuel temperature data is presented in units of degrees Fahrenheit. The moderator specific volume data is presented in units of cubic feet per pound. The statepoint numbers shown in the tables identify the relative reactivity statepoint calculations that fuel and burnable poison isotopic data will be generated to support for the evaluation of that particular assembly. The EFPD statepoint and cycle number corresponding to each set of fuel temperature and moderator specific volume data are presented above their respective columns in the tables. Each set of fuel temperature and moderator specific volume data listed in the tables is applicable to the depletion calculation performed between the statepoint number identified above the particular data and the previous statepoint number.

Table 4.1.10-1 Burnup, Fuel Temperature, and Moderator Specific Volume Data for Assembly H04 of Crystal River Unit 3 Assembly Number H4 Statepolnt 22 (BOC Cycle 8) Statepolnt 23 (97.6 o 8) Statepolnt 24 (139.8 CYCl 8)

Node Burnwi Fuel Moderator BuruI Fuel Moderator eurnup Fuel Moderator No. (GWdPMTU) Temp. Pec. Vol. lGWdnATU) Tomp. Spec. Vol. IGWdMTU) Temp. Spec. Vol.

BOCCys

- 97. CyS 111ACy5 IIIACyI 139.5 Cy 111A CyS 11iACyU I-0.0 2.047 1200.9 0.0239 29 1200. 00235 2 0.0 2.-9-7 1415.7 00238 4.3 1415.7 0.023E 3 0.0 3,62 1542.4 0.0237 5.2 1542.4 0.0231 4 0.0 Data not uired. 3.95 i 1601.1 0.0235 .73 1601.1 0.023!

5 0.0 4.14-1 1625.7 0.0234 5.98 1625.7N 0.023 6 0.0 4.29 1635.6 0.0232 6.12 1635.5 0.023:

7 0.0 4.321 1638.9 0.0231 6.21d 1638.5 0.0231

_!6 0.0 4.36! 1640.0 0.0229 6.281 1640.0 0.0225 0.0 -- 4.404 '1639.9 0.0228 6.321 1639.0

• 0.022i

. 10 _____0.0 4.427 1639.1 0;022 6.356 1639.1 0.022C

Waste Package Development Design Analysis Tltle: CRC Deplefon aiCilations for ihe Rodd Asmblies ki Bawhes 10 a d1 of AC Rver tnt 3 Document Identifler: BBAOOQOOO01717-0200-0044 REV 00 Page 16 of 82 11 g- - 443 1637-.5 0.02251 6.371 1637.6 0.022 12 . - - 4.42 1634.6 0.0223 6.33i '1634.6 0.022' 13 - ,,4.38. 1628.9 0.022 6.3j4 1628.9 0.0222 14 0.0 4.29 1617.8 0.022 6.203 1617.B 0.02 Is 0.0 4.142 1596.6 0.021 6.wa 1596.. 0.021 16 0.0 3.882 1650.! 0 5.64 1550. 0.021E 17 0.0 3.42 1454.l 0.0217 4.99 1454.8 0.0217 1a 0.0 2.514 1242. 0.0216 3.65 1242.0 0.0216 Statepolit 25 (404.0 Cycle 8) Statepolt 26 (409.6 Cycle 8) Statepolnt 27(515.5 C 8acl Node Bum P Fuel Moderator Bumul Fuel Moderator BumuI Fuel Moderator No. IGWdIMTU Temp. Spec. Vol. (GWdIMTU Temp. Spec. Vol. (GWdITUTU Temp. Soec. Vol 404.0 Cyt 234.6 Cyl 2346 CyS 409.6 Cyl 234.6 Cyl 234.6 Cyl £155Cyg 470.7 470.7 Cyl 1 9.42 1202.2 0.0240 9.663 1202.2 0.0240 12.38 1162.6 0.024t 13.67 391.4 0.0239 13.875 1391.4 00239 17.87 1317.3 0.0238 3 16.148 1487.0 0.0238 16.38; 1487.0 0.0238 20.893 1358.E 0023 4 17.24 1520.3 0.0236 17.481 1520.: 0.0236 22.11 1355.6 0.023 5 7.71 1 152733 000234 22.57 1345.7 0.0234 6 17.931 1527. 0.0233 1.1j7 1527. 0.023 22.75! 1335.2 0.0232 7 18.0& 1524.9 0.0231 18.29 1524.91 0.023 22.858 1326.9 0.0231 8 j1E.14 1522.51 0.0230 1 .0230 22.93 1320.8 0.0229 9 18.221 1520.7 0.0228 18.47:2 150. 0.0228 23.01 ! 1316A 0.0228 10 18.30 1519. 0.0226 18.55 1519. 0.0226 23.101 1313.3 0.022 11 18.34 1519.4 0022 18.632 1519.4 0.022 23.20 1311.6 0.022!

12 18.44l 151S. 0.022 1869d '1519.7 0.0224 23.29 1311.8 0.0223 13 18.46 1519.J 0.0222 18B.711 1519. 0.02 23.35! 1314.6 0.0222 14 18.3821 1518.3 1518. 0.0221 23.331 1320.5 0.0221 15 18.10! 0021 31.1 1 .0219 23.11 1328.6 0.022 16 17.377 1490.1 00211 17.63: 1490. 01 2 0.0218 17 15.621 142.J 0.021 20.1j 1 0.02171 18 Ii1.4 1229.l 0.0211 I571 1229.1 00216 14.88§ 178 0.021E

- ~ -.

Sttepoint 28 (BOC 9ycle

) Statepolat 29(158.8 9) Statepoln t300219.0 ycle 9)

Iycle Node BumMun F Moderator umupI Fuel Moderator Bumuo Fuel Moderator No. (GwdrWM Temp. Spec. Y. (OWdJMTU Temp. Spec. Vol. (GWdVM Temp. Spec. Vol.

EOC Cy9 470.7 CyS 40.7 CyS 1583 Cy9 110.5 Cy9 110.5 Cy 219.0 Cy9 192.6 Cy9 192A Cy9 1 12.L 1162. 0.024 15.2 882.9 0.0230 16.135 895.1 0.0230 2 ig.694 1317.3 0.0238 2227 990.83 23.691 991.5 0.023 3 21. 1358.81 0.0237 26.12 1038.3 -0.02 27.80d 1026.4 0.022S 4 23.03t2 _ 135.6 0.0235 27.74: 1058.9 0.0228 29.521 1036.3 0.022 5 23.494 1 0.0234 28.39 1067.5 0.022 30.211 1038.2 0.022 6 23.67; 1335. 0.0232 28.680 1069.j 0.0226 30.501 1036.3 0.022

-7 23.76 1326.j 0.023 28.82 1063.1 0.0225 30.642 1032.8 0.022 23.83 1320. 0.0229 28.91 1066. 0.022 30.724 1028.J 0.

9 23.904 1316.4 0.0228 28.985 1062. 0.0223 30.796 1024.9 0.022

Waste Packagqe Development Design Analysis

Title:

CRC Depledion Calculations for the Rodded Assemblies in Batches 10 and I I of Crystal River Unit 3 DocumentIdentffer. BBAOOOOOO_1717_0200400 REV 00 Page 17 o 82 10 23.98 1313.3 00.226 29.051 1058.6 0.02221 30.85 ` 4 022 it1 24.063 J311.6l o.0225 29.d 104. o JOJ10.2 0.0222 12 24.1391 1311.8 00223 29.152. 1049.3 0.0221- 30j95 1 015.6 0.01 13 24.18 1314.6 0.0222 29 141 1043.8 0.022 3094 1013.2 0.

14 24.1A 1320.5 0.0221 29.028 1036.4 021 30.823 1010.3 0.021 15 23.934 1328.6 0.0220 28.652 1025.1 0.021e 30.42 1004. 0.021 16 ~23.18i 1331.7 0.0216 27.621 1o05. 0.0217 29.321 093.2 0.0217 17 21.071 12.5 0.0217 24.934 966. 0.0217 26.46 965.3 0.0217 is 15.45 1178 0.0216 17.918 856.- 0.0216_ 18.93 867.0 0.021 Statepolnt 31 (363.1 Cycle 9)

Node Bunup l Fuel Moderator No. IGWdJMTU) Temp. Spec. Vol.

363.1 Cyg 303.7 Cy9 303.7 Cy9 1 18.561 Q12.S 0.0230 2 _ 27.27. 993.7 0.0230 3 31.897 1016.! 0.0229 4 133.75 1021.7 0.0228 5 34.4671 1018. 0.0227 6 34.7401 10131 0.0226 7 34.6W 1007.6 0.0225 8 34.92 1002.8 0.0224 9 34.981 098.p 0.0223 1O 35.03 995.9 0.0222 11 35.097 993.7 0.0222 12 35.14 992.5 0.0221 13 35.161 992.4 0.022 14 35.05 93.1 0.021 15 34.660 993.0 0.021 16 33.49 986. _

17 32 .,..!§32 0.0213 18 21.561 881.01 0.0216 Table 4.1.10-2 Burnup, Fuel Temperature, and Moderator Specific Volume Data for Assembly H12 of Crystal River Unit 3

_Assembly Number H12 tatepolnt 22 (BOc Cycle 8) Statepoint 23 (97.6 8 lStatepolnt 24 (13928 Cycle 8)

Node Burnup Fuel Moderator Bumup Fuel Moderatorl Burnup Fuel Moderator No. (GWdJMT) Temp. Spec. Vol. IG(wdMTU) Temp. Spec. Vol. IGWdIMTUM Temp. spec. Vol.

=OC Cyt 17. CyS lIIlA Cyll lIA Cyg 139. CyS lII Cyl Il1A Cyt 1 O.0 - - 1.97 1184.9 0.0239 2.89 1184.d 0.023 2 0.0 2.901 1395.9 0.0238 4.24 1395.1 0.0238 3 0.0 - ___ _ 3.621 1621. 0.02361 6.12 1521.2 0.02 4 0.0 109ta not re uIred, 3.841 1578.1 0.02351 657 1578.1 0.023'

Waste Package Development ___b_ Design Analysis

Title:

CRC Depiction Calculations for the Rodded Assemblies InFBatches 10 and 11 of Crysai Rivce Unit 3 Document IdentUflier BBAOOOO.01717.0200-00044 REV 00 Page 18of 82 5 - 0 - - 4.020 1601.3 0.0233 5.81 1 1601.3 0.02

.0 - -4.128 1611 0.0232 595I 1611.4 0.02 7 0.0 -- 4.201 1616.1 0.0230 6.04' 1616.1 0.023 B 0.0 - 4.251 t67.1 0022 6.10' 1617 0.0 9 0.0 4.285 1617.61 0.022 6.150 1617. O.M7 10 -0.0 4.31C 1617.1 0.0226 6.182 1617.1 0.0226 11 4.3291 1616.2 0.0224 6.201 1616.2 0.0224 12 0.0 -. 344 1616.1 0.0223 6.23' 1616.1 0.022i 13 0.0 4.33-- 1615.7 0.0222 6.22 1615. 0.0222 14 0.0 4.256 1607.3 0.0220 6.1381 1607. 0.022 15i _0.0_ 4.106 I586.0 0.0211 5.9421 15B6. 0.0219 16 0.0 3.843 1539.2 0.0218 .5.8: 1539.J 0.0218 17 0.0 3.38 1443.- 0.0217 4.Q2d 1443. 0.0217 18 0.0 2.477 1232. 0.0216 3.60. 1232. 0.0216

- Statepolnt 25 (404.0 Cycle 8) Statepolnt 26 (409.6 Crcle 8) Statepolnt 27 (515.5 cle 8)

Node Bumuo Fuel Moderator Bumut Fuel Moderator Bumup I Fuel Moderator No. (GWdXATU) Temp. Spec. Vol. (GWd1UTU Temp. Spec. Vol. MGWdMTUM Temp. Spec. VoL 404.0 Cyt 234A CyS 234.6 Cyt 409A CV8 234A Cyt 234. Cyo S15.5 Cyt 470.7 Cyl 470.7 CyS 1 Jj.179 1190.S 0.0240 CM 1190.9 0.0240 12.102 1158.7 0.024 2 13.34' 1377.2 0.0239 13.544 1377.2 0023 17.50: 1315.S 0.023E 3 15.784 1472.0 0.0237 16.01! 1472.t 0.023 20481 1359.3 0.0237 4 I16.839 1504. 0.0238 17.075 1504. 0.0235 21.662 1355.6 0.0235 5 17.25 1511.1 0.0234 17.49 1511.1 0.0234 22.06 1343.3 0.0234 6 _17.457 1510.2 0.0232 17.69 1510. 0.0232 22.231 1332.S 0.0232 7 17.58t 1507.9 0.0231 17.82 1507.9 0.0231 22.332 1324.S 0.023 8 jj17.671 1505.7 0.022S 17.91 1505.7 0.0229 22.41 1318. 0.0229 9 j~17.75; 15.04. 0.0228 17.99 1504.t 0.0228 22.49 1314. 0.0228 10 1 17.0 1503.0 0.0226 18.078 1503.0 0.0226 22.591 1311.91 0.022 11 17.932 1503.2 0.022 0.0225 22.71 13105 0.022 12 18.06 1505.3 0.0223 18.31 105.31 0.0223 22.891 1311. 0.0223 13 18.171 1509. 0.0222 1.445 1509.0 0.tl22 23.081 1316.8 0.022 14 18.171_ 1509.2 0.0221 18.426 1509.2 0.0221 23.12d 1323. 0.0221 15 17.90A 1502.7 0.0219 18.161 1502.7 0.0211 22.923 1331.6 0.022t 16 17.18; 1481.7 0.0218 17.43 1481.7 0.0211 22.1631 1335.1 0.021 17_ 15. 7 15.67 1411. 0.0217 20.12 1316.1 0.0217 18 11.25! 1222. 0.0216 11.42 2 0.0216 14.725 1179. 0.0216

- - - a - - -I - - -

Statepolnt 28 (BOC Cycle 9) Statepoint 29 (158.8 Ccle 9) Statepolnt 30 (219.0 Cycle 9 Node Bumup - Fuel Moderator Burnup I Fuel Moderator Bumup [ Fuel Moderator No. (GWdUMTW Temp. Spec.Vol. (GWd)MJWij Temp. Spec. Vol. GOWdwm)j Temp. Spec. Vol.

BX Cy9 470.7 CyS 47T.Cyt 15A Cy9 I 110.5 Cy9 110. Cy9 219.0 Cy9I 192. Cyt I 192.8 Cy$

1 12.6 11587 0.0240 156901 989.5 0.0231 16.936 999.1 0.023 18.32! 1315.5 0.0238 22.96 1115.S 0.025 24.836 1114. 0.023A 3 I 21.4 1359.3 0.0237 26.981 1177.7 0.0234 29.167 1162.! 0.0233

Waste Package Development ____ Design Analysis

Title:

CRC Depledon Cakulations for dhe Rodded Assembles in Batches 10 and 11 of Cystal River Unit 3 Do;ument'tdentl1Ie~ BBAOOOO0O.01717-0200-00044 RV00 Page 19 of 82 4 22.5991 1355.6 0.0235 28.5931 120o0. 0.0232 30.898a 1177. 1 0.0232 S6 2301 1343. 7 0.0 2j041 11j27 -

0.21 -

_29 -

1181. 0.02311 6 23.16 1332. 1193.8 0.0230 . 158. 0.0229 7 23.25_ 1324.5 0.0230 29.4421 1iS93.4 0.0228 31.716 1155. 0.0228 8 23.331 1318.7 0.0229 28.54' 1101.2 0.0227 31.82 1151. 0.022 9 23.40! 13146 0.0228 296 1187.7 0.0226 31.90 1147. 0.0221 10 23.48 1311.8 0.0226 29.71 1183.8 0.0225 31.98 1144. 0.0225 11 23.91 1310.5 0.0225 29.814 1179.8 0.0224 32.0851 1141. 0.0224 12 _ 23.741 1311.8 0.0223 MO 1179.5 0.0223 32.3 1143. 0.0223 13 _23.9231 1316.8. 0.0222 _30.6281 1209.7 0.0221 32.S1451 1171.1 0.0221 14 23.9511 1323.4 0.0221 30.521 120.2 0.0220 32.9 1176. 0.0220 15 23.74 1331.6 _ 30.141 1192.4 0.021 32.66 1169. 0.021 16 22.89 1335.1 0.0218 29.04 1167.9 0.0218 31.38! _ 4. 0.0211 17 20.B8! 1316.1 0.0217 26.25 111 1.S 0.0217 28.371 1111. 0.021 18 15.303 1179.9 0.0216 18.871 983.2 0.0216 20.32 985.1 0.0219 IStatepoint 31 (363.1 Cycle 9)

Node Bumup Fuel- Moderator No. (GWdVMTUJ Temp. Spec. Vol.

363.1 Cys 303.7 Cy9 303.7 Cy9

_ 1010.7 0.023!

2 29A4& 1108.: 0.0234 3 34.455 1150.2 0.023i 4 36.374 1160.9 0.0232 5 36.620 1138. 0.0230 6 36.-84 1130.0 0.022i 7_ 36.986 1124.t 0.022E 8 37.07 111B.9 0.0221 9 37.15 1115. 0.0226 10 37.23 1112.1 0.0225 11 37.35 1110.4 0.0224 12 37.637 1jj2 0.0223 13 38.580 1139.j 0.0221 14 38.71 1148. 0.022 15 38.314 114.4 0.021i

16. 37.0351 1141 0.021E 17 33.594 1103.6 0.0217 18 23.99 990.0 0.0216

Waste Package Development Design Analysis TWtle: CRC Depleton Calculations for the Rodded Assemmbis in Batches 10 and 11 ofCuystai Rivr Unit 3 Document Identar. BBA00-01717-0200..000RE REV 0 0 Page 20 ofB2 Table 4.1.10-3 Burnup, Fuel Temperatures and Moderator Specific Volume Data for Assembly 123 of Crystal River Unit 3 I___________________ Assembly Number H23 lknqannint90 MUMl!B velaAl RI l;tfanaln US 107-t fCjel RAl 1qMtsimnnTn* 9L I4%S R fluelt Di Node Bumup Fuel Moderator Bumu=, Fuel Moderator hInmup I Fuel lModerator

.No. (GWdIMTU) Temp. Spec. Vol. (GWI~dUM Temp. Spec. Vol. (OnWdN=u Temp. Spec. Vol.

- SOC CYS 97.6X yy 1114Cyll 111ACyS 13.3CYl 111AC l1.4 Il Cyl I 0.0 1.960 1176.8 0.023 2.86 1176.1 0.0239 2 0.0 - 2.-1 1391.6 0_0238 4.24 1391. 0.0238 3 0.0 3.568 1520.8 0.023 5.17 1520. 0.0237 4 0.0 Data not rzulred. 3.920 1680.0 0.0235=5.651 1580 0.0235 5 0.0 - 4.11 1604.5 0.0234 5.91 1604.5 0.0234 6- 0.0 - 4.235 1615.1 0.0232 6.j0 1615.1 _0.023 7 0.0 4.31 1619.4 0.0230 6.17 1619 0.02 a 0.0 - 4.374 1620. 00229 6.24 1620. 0.0229 9- 0.0 4.41 1621.t 0.022, 6.29 1621. 0.0227 10 0.0 4.441 0.226 6.32 1620. 0.0226 11 0.0 4.467 161S9. 'n0225 6.3 1619. 0.0225 12 0.0 - 4.43 1621.1 00223 6.40 162J.1 0.0223 13 0.0 . 4.49 1622.6 0.0222 6.41 1622.6 0.0222 14 0.0 4A2 1616.4 0.02 6.3. 1616.4 0.0 15 0.0 4.27 1697.8 0.0219 6. 197A 0.0219 16 f-0.0 - 3.99- J52. 0.021Q 5.76' 1552.21 0.0218 17 0.0 3.491 1452.4 0.021 5.0 1452.4_ 0.021 18 0.0 2.521 1234.4 0.021 3.65 1234.4 0.0216 Statepoint. 25 (404.0 Cycle 8l) Statepolnt 26 (409.6 Cycle 8) Statepolnt 27 (516.6 Cyle 8)

Node Burur Fuel Moderator BuMuD Fuel Moderator BumupI Fuel Moderator Uo. (GldJMT Temp. Spec. Vol. (GWdNTU Temp. Spec. VoL (Owdwm) Temp. 6pec. VoL 404.0 C 234. O 234. Cyl 409. CyS 234.6 CY$ 23 Cyl S 1. Cyt I 47.7 Cyl 470.7 Cy$

I S.01 1180.1 0.023 Sj.147 11 . 0.0239 11.87 1148.S 0.023f 2 '13.191 1365. 0.0238 13.381 1365.5 0.0238 17.26 1303.S 0.0238 3 15.676 1459.! 002377 16.S0 1459.5 0.0237 20.291 1347.1 0.0236 4 H 7167 1491j . 0.0235 16.99 1491.3 0.0235 21.491 143.0 0.023.

5 17202j 1497.2 0.0234 17.438 1497.2 0.0234 21.911 13. 0.023 6 17.4151 1496.4 0.023 17.652 1496. 0.0232 22.10 1319.7 0.0232 7 17.643 1494.1 0.0231 17.78 1494.1 0.0231 22.2111 131.6 0.02 8 7 1491.8 0.0229 17.871 1491.t 0.0229 22.297 1305.8 0.022(

9 1. 189.S 0.0228 17.96 1489 0.0228 22.381 J301.7 0.022 10 1.81 1488. 0.0226 18.04. 1488.S 0.0226 22.47 1298.8 0.0226 11 17.1 1489.3 0.0225 18.165 14893 0.0225 22.60 1297.4 0.022 12 1807 1492.3 0.0223 16.3id 1492.3 0.0223 22.801 12gs.d_.2 13 18.24. 1497. 0.0222 18.48_ 14973 0.0222 23.038 1303.4 0.0222 14 18.25 1498.8 1 1.501 1498.8 00221 23.114j 1310. 0.022 15 18.01 1493.7 0.0219 18.268 1493.7 0.0219 22.94A 1318.8 0.022

Waste Package Development Design Analysis Tile: CRC Deplction Calculations for the Rodded Assemblies in Batches 10 and 1I ofCryal RiverUnk 3

. ocumentIdentfler BBAOOOOOO.0l7l7.0200-0044REVO0 - Page 21 of 82 16 17.2881 1472.6 0.0218 '17.538j 472.61 0.0218 2.21 q 1323.31 0.021 171 1.4891 144". n 217 16.7,` 1404.0 0.0217 20-1081 1305.!1 0.0217 18 11.211 12 14 . 9 0.0216 11.38 1214.9 0.0216 14.64a 1172 .: 0.021

- Statepolnt 28 (BOC Cycle 9) SatenLh 29 (158.8 ycle 9) Statepolnt 30 (219.0 I cle 9)

Node Burnup Fuel Moderator Bumup Fuel Moderator Burn Fuel Moderator No. (GWdMTU) Temp. Spec. Vol. (GWdMTW Temp. SPeC Vol. (OWdITV Temp. Spec. Vol.

=OC CylI 470.7 CyS 470.7 Cyt 15.8 Cy9 11O. Cy9 110.5Cyq 219.0 CY9 132. Cy 192 Cy 1 12.441 1148.5 0.0239 15-64 1015.8 0.0237 16.965 1025.d 0.023, 2 18.08d 1303.9 0.0238 22.930 1140.4 0.0236 24.88 1139.1 0.0236 3 21.197 1347.1 0.0236 26.94 1199.2 0.0234 29.21 1186.5 0.0234 4 22.42 1343.0 0.0235 28.63, 1226.3 0.0233 31.035 1204.11 0.0233

_5 22.846 1330.5 0.0233 29.30 1238.7 0.0232 31.75 1211. 0.023?

6 23.025 1319.7 0.0232 29.61 1242.8 0.0230 32.0 1211. 0.0231 7 23.13t 1311.6 0.0230 2978 1242.5 0.0229 32.26 1209. 0.022 8 23.20d 1305.8 0.0229 29.891 1239.8 0.0228 32.371 1205. 0.022 9 23.28. 1301.7 0.0227 29.97 1235.9 0.0226 32.4s 121. 0.022 10 23.3631 1298.8 0.0226 30.0 1231.2 0.0225 32.52 1197.4 0.02251 11 _23.476 1297.4 0.0226 30.14 1226.9 0.0224 32.611 1193. 0.022 12 23.65 1298.5 0.0223 30.29 1219.3 0.0223 32.765 1190. 0.022' 13 23.866 1303.4 0.0222 30.44 1210.8 0.0221 32.90d 1185. 0.0221 14 23.931 1310.3 0.0221 30.40: 1200.3 0.0220 32.85 1181. 0.022 156 23.754 1318.8 0.0220 30.041 1185.3 0.0219 32.463 1171. 0.021j

-16 23.012 1323.3 0.0218 28.Q81 1162.3 0.0218 31.32 1152. 0.021 17 20.865 13056. 0.0217 26.21' 1119.8 0.0217 28.34 1116. 0.021 18 15.207 1172.21 0.0216 18.83 990.2 0.0216 20.31 994. 0.021 Statepoint 31 (363.1 Cycle 9)

Node Bnumup Fuel Moderator No. (OwdmM Temp. Spec.VoL 353.1 CI9 203.? Cy 303.7 Cyl 1 20. 18 2 ~29730 11134.6 0.0236 3 34.7321 177.8 0.0234 4 36.782 1191.5 0.0233 5 37.56 1190.7 0.023 6 37.88' 1185.4 0.023C 7 38.050 1179.4 0.022F 8 38.145 1174.2 0.022E 9 38.218 1170.0 OE 1 38.294 1186.9 _0.02!2 11 38.399 1164.6 0.0224 12 38.156 _1163.0 0.0223 13 38.73 1162.3 0.0222 14 38.70! 1162.6 0.022C

Waste Package Development Design Analysis TiuTe: CRC Depletion Cilculjtions fordtCRodded Assemblies iBatches IC and I of Crystal RhrUan t3

• Document Identlifer. BBAOoooooa017l7.0200400044 pEV at Page 22 of 82 i5 38.304 1161.21 0.0219 16 37.04.1 1151.61 0.0218 17 33.64' 1113.8 0.021 18 24.06 999.8 0.0216 Table 4.1.104 Burnup, Fuel Temperature, and Moderator Specific Volume Data for Assembly 127i of Crystal River Unit 3 U

Assembly Number H27a U Caf~#f~q~nn 2 i2 NoluUn 1nC MY2l:it7 Uvula 0% IrfafanntIV 9A HIM0 A ESteptA A Node Burnup Fuel Moderator Gurnul Fuel Moderator Bumup I Fuel Moderator No. (GWd1MTUM Temp. Spe.Voal. (OWdTUM Temp. Spoc. VoL (GWd/UTUMI Temp. Spec. Vol.

BOCCy$ -7A Cyl IIIACyl IIIACVI 139.8CyS IIIACyl IIIACyt 1 0.0 -1.405 016.2 0.0234 2.0541 1016.2 0.0234 2 0.0 2.399 1252.6 0.0233 3747 1252.6 .0233 3 1 0.0 - I 301i 1369.3 0.0232 4.335 1369.3 0.0232 4 l 0.0 IDat not re ired. 3.3461 1420.0 0.0231 4.7771 420 _0 0.0231 5 I0.0 -- 3.530 1441.9 020 5.015 1441. 0.0230 6 o.ol 3.642 1451.1 0.0228 5.1is 1451.1 0.0228 7 0.0 - 3.713 1454.7 0.0227 .2401 1454. 0.0227 0.0 - 3.76 1455.8 0.0226 9 ~0.0 -. 794 1455.6 0.0225 5.337 1455 0.0225 10 0.0 3.814 144.6 0.0224 5.36 1454. 0.0224 11 0.0 3.82- 14533 0.0223 5.37 1453. 0.0223 122-0.0 3.817 1451.3 0.0221 5.37d 1451.: 0.0221 13 0.0 3.787 1447. 0.0220 5.33, 1447.1 0.0220 14 0.0 3.71- 1439.3 0.0219 5.25 1439.3 0.0219 15 _0.0 3.58- 1421.- 0.021 5.081 1421. 0.0218 16 0.0 3.-27 130.1 0.0217 4.741 1380.1 0.0217 17 0.0 - 2.Ui 1284.3 0.0216 4.041 1284.3 0.0216 18 0.0 1.694 1030.' 0.0216 2.45' 1030.7 0.0216 a

- - - ~ ~~ - ~ - ~~ - ~~~-- - -

- Statepolnt 25 (404.0 Cycle 8) StatePolnt 26 (409.6 Ccle 8) Statepolnt 27 (S15. cle 8 I INlode _Bumup Fuel Moderator Biumup Fuel Moderator Bumup Fuel lhoderator No. WMT oTmp. Spec. Vol. GOWdMTU) Temp. Spec. Vol. (GWdTU Temp. Spec. Vol.

404.0 CyS I24 CyS 214. Cyt 409.6 Cyl 234.6 Cy 234 Cy 615S Cyl 470.7 Cyl 470.7 Cyp

...L 6.591 1034.6 0.0233 6.691 1034.f 0.0233 C. 1044. 0.0233 2- 10.55 1227.6 . 0.0232 10.7121 127. 0.0232 13.771 0.0232 3 12.64 1303.4 0.0231 12.821 1303.4 0.0231 16. 1221. 0.0231 4 13.2 1326.2 0.0230 13.70 1326.2 0.023 17.221 1221. 0.0230 5 13.893 1329. 0.02219 1i0.0229 17.69 1212.4 o.o22q 6 14.071 1327.4 0.0228 ~14.2531 12.4 0.022 17.731 1203.4 0.022 7 14.16 1323.7 0.0227 14.345 1323.i 0.0227 17.81; 1t96.l 0.0227 8 14.22 1320.4 0.0226 14.4 1320.4 0,0226 17.6 1 . 0.0226 9_ 14.271 1317.9 0.0224 14.459 13179. 0.0224 17.91 - 1188.' 0.0224 10 14.32 1316.3 0.0223 14.505 1316.3 0.0223 17.96d 1185. 0.0223

Waste Package Development Design Analysis

Title:

CRC Depletion Calculations for the Rodded Assemblies in Batches 10and I I of CYst River Unit 3 Document Identifier. BBAOOOOOO-01 7 17-0200-00044 REVO00 Page 23 of 82 11 14.365 131J61 0.0222 14.S51 1315.6 0. 2 18. 1183.5 0.02

_12. 14.4071 1316.1 02 4 1316.1 00221 .1.082 11B3 0.0221 13 14.42 1317.j2 0.0220 _1.614 1317.2 0.022 18.13 11 54 0.022 14 14.38: 1317.1 0.0211j .14.,j 1317.8 0.021 18.12 11S 0. 0.022 15 14.184 1314.5 0.0218 14.37i 1314.5 0.0218 17.9 1 0.21 007.1 16 13.598 1297.8 0.021_ t3.78! 12C97.8 0.0217 17.3 1202.71 00.21 17 1200: 1239.2 0.021 12.17 1239.2 0.0217 15.54 1183. 0.021, 18 7.661 1040. 0.0216 7.782 1040.3 0.0218 10.14 1048. 0.021 Statepoint 28 (BOC Cdcle O) Statepolnt 29 (168.8 cb B) Statepolnt 30 (219.0 Ccle 9)

Node BuUD Fuel UModerator 1umuo Fuel Modertor Gumu Fuel Moderator Ho. (GWdIMTU) Temp. Spoc. Vol, IGWdMTU Semp. Spec. Vol. (GWdmTUI Temp. Spec. Vol.

BOC Cy1 470.7 Cy_ 47J7CyO I5IaCyJ 110Cy, t10.6 y 2191 CyI l82.CyS 19S CY9 1  ?.212 1044.3 0.023 12.05 1007.6 0.0238 13.29 1021. 0.023 2 _ 14.406 11i7.19 0.0232 1t.265 1186.3 0.0237 21.241 1178.2 0.023 3 i16.971 1221.61 0.0231 22.93. 1259.5 0.0231 25.27. 1242. .0.023 4 17.94, 1221.1 0.0230 24A4 1295.4 0.0234 26.051 1265.: 0.0234 5 1B.301 1212.4 0.0229 25.111 1311.9 0.0233 27.66 1271.7 0.0233 6 18.4sd 1203.4 0.0228 25.40 1318. 0.0231 27.081 1271.2 0.0231 7 18.511 1196.6 00227 25.5651 131j.7 0.0230 28.14 1268.3 0.023 8 18.56! 1191.6 0.0226 _2.660 1318B.4 0.0228 28.24 1264.7 0.0228

? 18.607 1188.1 0.0224 25.72 1315.8 0.0227 28.31: 1261.2 0.022 10 18.641 i185.! 0.0223 25.771 1312.4 0.0226 28.361 1258.: 0.0228 11 18.692 1183.9 0.0222 25.80l _308.2 0.0224 J840 1 12 18.738 1183.! 0.0221 25M 1305. 0.0223 28.43! 1254.4 0.022 13 18.77! 1185. 0.022 25.832 12Q9.t 0.022 28.438 1253.:2 0.0222 14 .76d. 1190.:2_ 0.0220 25.7' 1290.9 0.0221 28.32 1250.4 0.0221 15 18.611 1 17.6 0.0211 25.369 1274.7 00219 27.941 1243. 0.0219 16 18.01 1202.7l 0.0211 24.412 1246.6 0.021 26.89! 122s.d 0.021 17 16.t3 1183.2 0.021 21.854 1 1 027 241 s. 0.0217.

18 10.56 1048.4 0.0211 14.47 10628 0.0216 16. 1064.4 0.02161

- -. -I Statepolnt 31 (363.1 Cycle 9)

Node Burnuo Fuel Moderatorl No. (GWdlMTU) Temp. Spec. Val.

363.1 Cyg 303.7 Cy9 303.7 Cy2 1 16.44! 10441 0.0237 2 26.143 1171.1 0.0236 3 30.937 1214.3 00235 4 32.867 1225.4 0.0234 5 33.6 1222.8 0.0232 6 33. 1217.2 0.0231 7 34.11 1211.4 0.0229 8 34.2 1206. 0.0228 9 34.271 1202.0 0.0227

Waste Package Development Design Analysis

Title:

CRC IMPWe=o Calculatiors fo the Roded Assemblies inBatches I10 And I1I of cWaI River Unit 3 Document Identifter. BEAOOOOOO.01717-0200-00044 REV 0Do Page 24 of 82 10 34.32 1200.4 0.0226 11 34.392 1199.2 0.022 12 34.46: 1199.6 0.0223 13 34.60 1201.3 0.0222 14 34.43 1203.4. 0.0221 15 34.05 1203.3 0.0219 16 32.897 1196.0 0.0218 17 29.67' 1167.8 0.0217 18 20.034 1061.3 0.0216 4.1.11 Insertion History Data for CRA's and APSRA's The CRA and APSRA time of insertion in a particular axial position Ina fuel assembly is required data for performing appropriate depletion calculations for a rodded assembly. Hardening (locally increasing the average energy ofthe neutron population due to less local thernalization and increased local capture of neutrons at thermal energies) the neutron spectrum in a particular axial region of an assembly at a time during its irradiation history effects the isotopic composition of the depleted fuel. The CRC depletion calculations of rodded assemblies as performed in this analysis requires rod insertion time input in terms of EFPD's inserted for either a CRA or APSRA in each axial node of each fuel assembly for each statepoint depletion calculation of interest. Tables 4.1.11-1 through 4.1.11-2 present the CRA and APSRA insertion time data relevant to each assembly depletion calculation documented in this analysis. Assemblies H04 and H23 were located in a control bank 6 location during Cycle 9. During Cycle-9 operation, control bank 6 was 100% withdrawn from the core. Therefore, no control rod insertion data is needed or presented for assemblies H04 and H23 in this analysis. The assembly heights corresponding to the axial nodes presented in Tables 4.1.11-1 through 4.1.11-2 are as follow: the top node (node 1) is 17.78 cm, the bottom node (node 18) is 22.352 cm, all other nodes are 20.0025 cm.

The top of node I begins at the top of the active fuel region.

Table 4.1.11-1 Grey APSRA Insertion Time Data (EFPDs Inserted) for Assembly Number H12 Axial Node Cycle-9, 0.0 EFPD to Cycle-9, 158.8 EFPD to Cycle-9, 219.0 EFPD to (1-Top) Cycle-9, 158.8 EFPD Cycle-9, 219.0 EFPD Cycle-9, 363.1 EFPD I 0.00 0.00 . 0.00 2 0.00 0.00 0.00 3 0.00 0.00 0.00 4 0.00 0.00 0.00 5 0.00 0.00 0.O0 6 0.00 0.00 0.00 7 0.00 0.00 0.00 8 0.00 0.00 0.00

Waste Package Development Design Analysis Tiue: CRC Depletion Calculions for the Rodded Assemblies inBatches 10 and 11 of CrAl River Unit 3 Document Identiflor: BBA000000-017t4200-04 nREV 0O Page 25 of 82 9 34.52 2.57 12.56 10 158.80 60.20 144.10 11 158.80 60.20 144.10 12 153.66 60.20 144.1 13 2.29 9.45 16.20 14 0.00 0.00 0.00 150 0.00 0.00 16 0.00 0.00 0.00 17 0.00 0.00 0.00 18 0.00 0.00 0.00 Table 4.1.11-2 CRLA Insertion Time Data (EFPDs Inserted) for Assembly Number H27a Axial Node Cycle-9, 0.0 EFPD to Cycle-9, 158.8 EFPD to Cycle-9, 219.0 EFPD to (I=Top) Cycle-9, 158.8 EFPD Cycle-9, 219.0 EFPD Cycle-9, 363.1 EFPD 1 57.33 14.09 36.07 2 2.09 0.00 0.00 3 0.00 0.00 0.00 4 0.00 0.00 0.00 5 0.00 0.00 0.00 6 0.00 0.00 . 0.00 7 0.00 0.00 0.00 8 0.00 0.00 0.00 9 0.00 0.00 0.00 10 0.00 0.00 0.00 11 0.00 0.00 0.00 12 0.00 0.00 0.00 13 0.00 0.00 0.00 14 0.00 0.00 0.00

Waste Package Development Design Analysis

Title:

CRC Depletion Calculations for the Rodded Assemblies InBatches 10 and 11 ofCrystal River Unit 3 Document Identifier. BBA0000001717-0200-00044 REV 00 Page 26 of 82 15 0.00 0.00 0.00 16 0.00 0.00 0.00 17 0.00 0.00 0.00 18 0.00 0.00 0.00 4.2 Criteria The design of the waste package will depend on waste package configuration criticality analyses performed using an acceptable disposal criticality analysis methodology. Criteria that relate to the development and design of repository and engineered barrier components are derived from the applicable requirements and planning documents. The Engineered Barrier Design Requirements Document (EBDRD, Ref. 5.8) provides requirements for engineered barrier segment design. Tbe Repository Design Requirements Document (RDRD, Ref. 5.9) provides requirements for repository design. The Controlled Design Assumptions Document (Ref 5.10) provides guidance for requirements listed in the EBDRD and RDRD which have unqualified or unconfirmed data associated with the requirement.

This analysis supports the disposal criticality analysis methodology by providing input, in the form of fuel and burnable poison depletion results, to benchmark calculations which address the prediction of both spent fuel isotopic compositions and their associated reactivity. These benchmark calculations will contribute to the determination of bias values in the method of critical multiplication factor calculation that is implemented by the analytic tools to be used in the disposal criticality methodology. The requirements for utilizing the bias in the method of calculation ofthe critical multiplication factor for disposal configurations containing spent nuclear fuel are located in Section 3.2.2.5 of the RDRD and Section 3.2.2.6 of the EBDRD. This analysis does not satisfy these requirements, but the results from this analysis will be used as input to subsequent analyses which will satisfy these requirements.

4.3 Assumptions 4.3.1 The inherent approximation ofunifornmy distributed non-fuel lattice cells in the Path B unit cell models of the SAS2H calculations as described in Section 7.2 is considered acceptable within the fidelity of these calculations as documented in Section S2.2.3.1 of Volume 1, Rev. 5 in reference 5.4. The basis for this assumption is provided in the previously identified section of reference 5.4. This assumption is used throughout all depletion calculations documented in Section 7.

4.3.2 With the utilization of one cross-section update per irradiation time step, the maximum duration of any time step in any reactor cycle irradiation layout of this analysis should not exceed 80 days.

The basis for this assumption is that the 80 day irradiation time step limit assures that the isotopic concentrations of the system (primarily fuel and borated moderator) will not alter the neutron spectrum radically enough to cause a time step of the depletion calculation to be performed without the availability of cross-sections which have been properly weighted with an updated

Waste Package Development t____ Design Analysis

Title:

CRC Depletion Calculations for the Rodded Assemblies InBatches 10 Ad 11 oftCystl River Unit 3 Document Identfiter: BBA0OOOONO01717-0200.00044 REV 00 Page 27 of 82 neutron spectrum and spatial flux. This assumption is used throughout all depletion calculations documented in Section 7.

4.3.3 Distributing the spacer grid material uniformly in the moderator composition of the Path A and B models is acceptable. The basis for this assunption is that the limited reactivity worth of the spacer grid materials will have negligible impact on the neutron spectrum when placed homogeneously in axial regions of the assembly. This assumption is used throughout all depletion calculations documented in Section 7.

4.4 Codes and Standards Not applicable.

5. .References 5.1 Activity Evaluation: Perform Criticality, Thermal, Structural, and Shielding Analyses.

Document Identifier Number (DI#): BB0000000 01 717-2200-00025 REV 02, Civilian Radioactive Waite Management System (CRWMS) Management and Operating Contractor (M&O).

5.2 Quality Assurance Requirements and Description. DOE/RW-0333P REV 07, DOE (U.S.

Department of Energy).

5.3 Summary Report of CommercialReactorCriticalityDataforCrystalRiver Unit 3. DI#:

BOOOOOOOO-01 717-5705-00060 REV 00, CRWMS M&O.

5.4 SCALE 4.3: Modular Code Systemnfor Performing tandardizedComputer Analysesfor Licensing Evaluation.User's Manual Volumes 0 through 3, Oak Ridge National Laboratory, Document Number: CCC-545.

5.5 Software QualificationReportfor the SCALE Modular Code System Version 4.3. SCALE Version 4.3 Configuration Software Configuration Identifier (CSCI): 30011 V4.3, DI#: 30011-2002 REV 00, CRWMS M&O.

5.6 Q-List. YMPI90-S5Q, REV 04, YMP (Yucca Mountain Site Characterization Project).

5.7 This reference Is intentionally left blank 5.8 EngineeredBarrierDesign Requirements Document. YMPICM-0024, REV 0, ICN 1, DOE OCRWM.

5.9 Repository Design Requirements Document. YM/CM-0023, REV 0, ICN 1,DOE OCRWM.

Waste Package Development Design Analysis

Title:

CRC Depledon Calculations for the Rodded Assgulies InBatches 10 and 11 OrCrysa River Unit 3 Document Identfler. BBA0ooooo.01717.0200400044 REV 00 Page 28 of 82 5.10 ControlledDesignAssumptponsDocument. Dl#; BOOOOOO-017174600-O00 32 REV 04,IJCN 01, CRWMS M&O.

5.11 CRC Depletion Calculaflonsfor the Rodded Assemblies in Batches 1. 2. 3. and iXof Crystal River Unit 3. DI#: BBAOOOOOO-01 717-0200-00040 REV 00, CRWMS M&O.

5.12 CRC Depletion Calculationsforthe Non-Rodded Assemblies in Batches I. 2. and 3 of Crystal River Unit 3. DT#: BBAOOOOOO-01 717-0200-00032 REV 00, CRWMS M&O.

5.13 Interoffice Correspondence OC)Qfrom Hugh Benton to Greg Carlisle,Subject, Software Routines. July 29, 1997, IOC Number: LV.WP.DAT.07/97-164, CRWMS M&O.

5.14 Attachments for BBA0000 -01717-0200-00044 REV 00 - CRC Depletion Calculations for the Rodded Assemblies in Batches 10 and 11 of Crystal River Unit 3. Batch Number: MOY-970902-07.

5.15 CRC Depletion Calculations for the Rodded Assemblies in Batches 10 and 11 of Crystal River Unit 3 (DI#: BBAOOOOOO-01717-0200-00044 REV 00) - Attachments XIII and XIV - 2 Data Cartridges. Batch Number: MOY-970902-06.

6. Use of Computer Software 6.1 Software Approved for QA Work The SAS2H control module of the SCALE 4.3 modular code system (Ref. 5.4) was used in this analysis to perform fuel assembly depletion calculations required for CRC evaluations. The SCALE 4.3 code system is subject to the requirements of the QARD (Ref. 5.2). The SCALE 4.3 code system was obtained from the Software Configuration Management in accordance with appropriate procedures. The CSCI number for SCALE 4.3 is 30011 V4.3. The SAS2H calculations documented in this analysis were performed on Hewlett Packard (HP) 9000 series workstations. The SAS2H control module utilizes the BONAMI, NITAWL, XSDRNPM, COUPLE, and ORIGEN-S calculational modules to perform isotopic depletion calculations. A detailed description of the SAS2H control module is provided in Volume 1, Section S2 of reference 5.4. The SAS2H control module of the SCALE 4.3 code system is applicable to the engineering application within this analysis and is used within the range of verification and validation as documented in reference 5.5.

The Excel, Version 5.0, and Lotus 1-2-3, Version 4.0, spreadsheet packages are two of the computational support software packages utilized in this analysis. The user-defined formulas, inputs, and results for all calculations performed with these spreadsheet packages are documented, where applicable, throughout this analysis. The Nsed" line editor (Revision: 70.12) available in the "hibm" directory on the HP 9000 series workstations is utilized in the "sedexecute" script file which is called and executed by the CRAFT code. The usage of the 'sed" line editor is described in Section 6 of Attachment I of reference 5.11.

Waste Package Development Design Analysis

Title:

CRC Depletion C4aculations for the Rodded Assemblies in Batches 10 and I of Cyal River Unit 3 Document Identilfer. BBA0OOO.001717.0200-OO44 REV 00 Page 29 of 82 6.2 Software Routines A software routine entitled "Commercial Reactor Assembly Follow Taskmaster" (CRAFT) was written to automate the production of SAS2H input decks as required to support fuel assembly depletion calculations relevant to CRC evaluations. The CRAFT code does not generate data. All calculations performed by the CRAFT code are verified by visual inspection and/or hand calculations. The CRAFT code, Version 3.0, compiled on February 25, 1997, was utilized in this analysis to orchestrate the depletion calculations for the fuel assemblies. The CRAFT 3.0 source code ("CRAFT.f.V-3.compiled-on_02_2597") and executable file ("CRAFT3.O) exist in the directory

"/users/wright/CRAFT_V3" on the Waste Package Development Department (WPDD) HP 9000 series workstation designated "Opus". The CRAFT code is subject to the requirements of the QARD as defined by Section 1.2.1 Part C of Supplement I Rev. I of the QARD. Complete documentation of the CRAFT code, Version 3.0, including code description, user information, and documentation that the software provides correct results for a specified range of input parameters is included in Attachment I.of reference 5.11. The CRAFT Version 3.0 software routine will ultimately be documented as an addendun to the existing SCALE V4.3 baseline and assume the SCALE V4.3 baseline CSCI identifier number of30011 V4.3 (Ref. 5.13).

A software routine entitled "CRC DATA TABULIZER7 was written to automate the production of tables containing the isotopic results and other pertinent data for a set of 29 principal isotopes at each CRC statepoint for each assembly. The CRC DATA TABULIZER code does not generate data. All calculations performed by the CRC DATAJTABULIZER code are verified by visual inspection and/or hand calculations. The CRC DATA TABULIZER code, Version 2.0, compiled on March 20, 1997, was utilized to tabulate the principal isotope results for each fuel assembly at each CRC statepoint. The CRC DATA TABLJLIZER, Version 2.0, source code (CRC_DATATABULIZER-V2.f) and executable file (CRC-DATA TABULIZER V2.exe) exist in the directory

"/users/wright1CRC(DATAjABUL1ZER" on the WPDD HP 9000 series workstation designated "Opus". The CRCQDATA-TABUUZER code is subject to the requirements of the QARD as defined by Section 1.2.1 Part C of Supplement I Rev. I of the QARD. Complete documentation of the CRC DATA TABULIZER code including code description, user information, and documentation that the software provides correct results for a specified range of input parameters is presented in Attachment V of reference S.12. The CRCDATAjABULIZER Version 2.0 software routine will ultimately be documented as an addendum to the existing SCALE V4.3 baseline and assume the SCALE V4.3 baseline CSCI identifier number of 30011 V4.3 (Ref. 5.13).

A software routine entitled 'RLAYOUT" was written to automite the development of appropriate irradiation time step layouts for depletion calculations involving rod insertion histories in which rod movements must be followed. The RLAYOUT code does not generate data. All calculations performed by the RLAYOUT code are verified by visual inspection and/or hand calculations. The RLAYOUT code, compiled on February 4, 1997, was utilized to develop appropriate irradiation time step layouts for the statepoint depletion calculations having associated rod insertion histories. The RLAYOUT source code (RLAYOUT.f) and executable file (RLAYOUT.exe) exist in the directory lusers/wright/RLAYOUTF on the WPDD HP 9000 series workstation designated "Opus". The RLAYOUT code is subject to the requirements of the QARD as defined by Section L2.1 Part C of

Waste Package Development Design Analysis

Title:

CRC Depletion Calculations for te Rodded Assemblies in BatcIes 10 Sd II of Crystal Riv Unit 3 Document Identifier. BBAoooooooo17-0.200-00044 RiEv Page 30 of 82 Supplement I Rev. I of the QARD. Complete documentation of the RLAYOUT code including code description, user information, and documentation that the software provides correct results for a specified range of input parameters is presented in Attachment m of reference 5.1 1. The RLAYOUT software routine will ultimately be documented as an addendum to the existing SCALE V4.3 baseline and assume the SCALE V4.3 baseline CSCI identifier number of 30011 V4.3 (Ref S.13).

Waste Package Development Design Analysis

Title:

CRC Depletion Calculations for the Rodded ASSemnblies in atches I0 and II ofcrysWl River Unk 3 Document Identifier. BBA00000001717420M0O04 REV 00 Page 31 of 82

7. Design Analysis This design analysis documents the fuel assembly SAS2H depletion calculations for the rodded assemblies of fuel batch 10 which are required for the CRC evaluations of Crystal River Unit 3. There are currently no rodded assembly depletion calculations required for fuel batch 11 to support the CRC evaluations. Sections 7.1 through 7.5 describe how the parameters listed in Section 4.1 arm utilized to perform the appropriate SAS2H depletion calculations relevant to CRC evaluations. The CRAFT description and user information provided in Attachment I of reference 5.1 I is essential for understanding the SAS2H modeling techniques employed in this analysis. The Information in Attachment I (Ref. 5.1 1), the input parameters in Section 4.1, and the CRAFT input decks in Attachments I through IV work together to provide a complete description ofhow all of the SAS2H depletion calculations in this analysis were performed.

7.1 Assembly Depletion Calculation Procedure The calculational procedure for the fuel assembly SAS2H depletion calculations performed in this analysis is based on the utilization of the CRAFT Version 3.0 code. The CRAFT code is described generally in Sections 7.4 and 7.5. The complete detailed description of the CRAFT Version 3.0 code is provided in Attachment I of reference S.1 1. The procedure for performing a fuel assembly depletion calculation with CRAFT Version 3.0 consists of the following four steps:

I) Create a CRAFT input deck for the assembly depletion calculation.

2) Assure that the CRAFT executable file and the CRAFT input deck entitled wdatain" and the 'sedexecuteu executable file are in the same directory. The "sedexecute" executable file is a script file which is used in conjunction with the CRAFT code to create the consolidated output files described in Section 7.5.

3) Execute CRAFT.

4) Check and analyze the CRAFT generated SAS2H input decks and the SAS2H isotopic results.

The various CRAFT generated and consolidated SAS2H output files contain unique filenames which specify the following information:

I) reactor identifier,

2) one-eighth core symmetry assembly number in current reactor cycle,

3) axial node number,

4) reactor cycle number in which the SAS2H calculation begins,

5) EFPD statepoint at which the SAS2H calculation begins,

6) reactor cycle number in which the SAS2H calculation ends,

7) EFPD statepoint at which the SAS2H calculation ends.

A complete detailed description of the filename content and format is provided in Attachment I (Ref.

5.1 1). Specific isotopic results contained in the various consolidated output files generated by CRAFT may be retrieved using the output filename information.

Waste PackageDevelopment _____ Design Analysis

Title:

CRC Depletion Calculations for the Rodded Assemblies inBatches 10 and II of Caysta! River Unit 3 Page 32 of82 Document Identfler. BBA00000I17170200-00044 REV 00 7.2 Path B Unit Cell Model Development fuel The SAS2H control module uses ORIGEN-S to perform a point depletion calculation for the assembly or section of the fuel assembly described in the SAS2H input deck. The ORIGEN-S calculational module uses cell-weighted cross-sections based on one-dimensional (I-D) transport on two calculations performed by XSDRNPM. One-dimensional transport calculations are performed unit cell models, Path A and Path B, to calculate energy dependent spatial neutron flux distributions necessary to perform cross-section cell-weighting calculations.

rod. In the The Path A unit cell model is simply a unit cell of the fuel assembly lattice containing a fuel to Path A model, the fuel pellet, gap, and clad are modeled explicitly. The only modification required to a develop the Path A model is the conversion of the fuel assembly's square lattice unit cell perimeter cladding.

radial perimeter conserving moderator volume within the unit cell, exterior to the fuel rod This modification is performed automatically by the SAS2H control module. A lID transport spatial calculation is performed on the Path A unit cell model for each energy group, and the unit cell the fuel.

flux distributions for each energy group are used to calculate cell-weighted cross-sections for it is The Path B unit cell model is a larger unit cell representation than the Path A model; hence, represents all or part of sometimes referred to as the laiger unit cell model. The Path B unit cell model due to the fuel assembly. The Path B unit cell model attempts to account for spectral effects rods, or axial heterogeneities within the fuel assembly such as water gaps, burnable poison rods, control cells power shaping rods. Typically, fuel assemblies contain a number of similar non-fuel lattice The structure of the Path B unit cell dispersed somewhat uniformly throughout the assembly lattice.

most fuel assemblies model is based on a uniform distribution of these non-fuel lattice cells. In reality, uniformly distributed do not have uniformly distributed non-fuel lattice cells, but the approximation of in non-fuel lattice cells is considered acceptable within the fidelity of these calculations as documented Section S2.2.3.1 of Volume 1, Rev. S in reference 5.4.

performed The basic structure of the Path B unit cell model for the fuel assembly depletion calculations non-fuel lattice in this analysis includes an inner region composed of an explicit representation of the by cell. This inner region has essentially the same format as the Path A model with the fuel rod replaced assembly the non-fuel rod. A region representing the homogenization of the remainder of the fuel in A final region representing the moderator surrounds the inner region in the Path B unit cell model. The in the Path B unit cell model.

the assembly-to-assembly spacing surrounds the homogenized region by model is determined size of each radial region surrounding the inner region in the Path B unit cell from the conserving the fuel-to-moderator volume ratio in the system. The cell-weighted cross-sections transport Path A model are used with the fuel of the homogenized region during the Path B model group are then developed using the unit calculations. New cell-weighted cross-sections for each energy calculations. These cell-weighted cell spatial flux distribution results from the Path B model transport depleted cross-sections are used in point depletion calculations performed by ORIGEN-S to calculate description of fuel and depleted burnable poison, if present, isotopics in the fuel assembly. A detailed in Section the calculations used to produce time-dependent cross-sections by SAS2H is documented S2.2.4 of Volume 1,Rev. 5 in reference 5.4.

Waste Package Development Design Analysis

Title:

CRC Depletion Calculations for ts Rodded Assemblies InBatches 10 mad II of Crystal Rver Unit 3 Document Identifier. BBA00000001717-020000044 REV 00 Page S3 of 82 The Path B unit cell models for the various fiel assembly configurations must be developed manually and input to the SAS2H control module. The primary concern in the development of the Path B model for PWR assemblies is the conservation of the fuel-to-moderator volume ratio in the system. For the fuel assemblies in batch 10 of Crystal River Unit 3 a combination of the following sets of Path B models must be utilized:

Set 1) This set is composed of one Path B model representing the base fuel assembly configuration with sixteen water-filled guide tubes and one water-filled instrument tube.

This Path B model may only be employed in a statepoint depletion calculation which does not have any BPRA, CRA, or APSRA insertion history.

Set 2) This set is composed of three Path B models that are utilized i stagtepoint depletion calculations that have a BPRA insertion history. One of the Path B models in this set represents a fuel assembly axial region containing sixteen BPRs inserted into the guide tubes with one water-filled instrument tube. Another Path B model in this set represents a fuel assembly axial region containing sixteen non-absorbing BPRs inserted into the guide tubes with one water-filled instrument tube. The last Path B model in this set represents a fuel assembly axial region with the BPRA removed. Since a constant number of Path B model radial zones must be maintained during a given SAS2H calculation (i.e., a statepoint depletion calculation), if is necessary to define a Path B model equivalent to that previously described in Set 1, but with the same number of radial zones as those previously described in this set.

Set 3) This set is composed of two Path B models that are utilized in statepoint depletion calculations that have a CRA insertion history. One of the Path B models in this set represents a fuel assembly axial region containing sixteen CRs inserted into the guide tubes with one water-filled instrument tube. lThe other Path B model in this set represents a fuel assembly axial region with the CRA removed. Since a constant number of Path B model radial zones must be maintained during a given SAS2H calculation (i.e., a statepoint depletion calculation), it is necessary to define a Path B model equivalent to that previously described in Set 1,but with the same number of radial zones as the first Path B model described in this set.

Set 4) This set is composed of three Path B models that are utilized in statepoint depletion calculations that have a APSRA insertion history. One of the Path B models in this set represents a fuel assembly axial region containing sixteen APSRs (absorbing region present in the guide tubes) with one water-filled instrument tube. Another Path B model in this set represents a fuel assembly axial region containing sixteen APSRs (only the follow rod region present in the guide tubes) with one water-filled instrument tube. The last Path B model in this set represents a fuel assembly axial region with the APSRA removed. Since a constant number of Path B model radial zones must be maintained during a given SAS2H calculation (i.e., a statepoint depletion calculation), it is necessary to define a Path B model equivalent to that previously described in Set 1, but with the same number of radial zones as those previously described in this set.

Waste Package Development ____ Design Analysis Ttle: CRC Depletion Calculations for the Rodded Assemblies in Batches 10 and tl of Crystal River Unit 3 Document Identmler: BBA00000001717-02004044 REV OO Page 34 of B2 The Path B model development spreadsheets in Tables 7.2-1 through 7.24, present the input parameters required, the parameters calculated, references to equations used to calculate the parameters, and the final Path B unit cell model dimensions available for direct implementation into SAS2H input decks for the rodded assembly depletion analyses of batch 10. The spreadsheet presented in Table 7.2-1, calculates the dimensions of the Path B unit cell model for Set 1, as previously described. The spreadsheet presented in Table 7.2-2, calculates the dimensions of the Path B unit cell models for Set 2, as previously described. The spreadsheet presented in Table 7.2-3, calculates the dimensions of the Path B unit cell models for Set 3, as previously described. The spreadsheet presented in Table 7.2-4, calculates the dimensions of the Path B unit cell models for Set 4 with a grey APSRA, as previously described. Table 7.2-5, contains a listing of the equations referenced and utilized in each of the spreadsheets presented in Tables 7.2-1 and 7.2-4.

Table 7.2-1 Set I Path B Unit Cell Model Dimension Calculation Spreadsheet for the Rodded Assembly Axial Regions from Fuel Batch 10 of Crystal River Unit 3 SAS2U Path B Unit Cell Model Dimension Calculations for Ate Rodded Assemblv Axial Reglons In Fuel Batch 10 o Crystal River Unit 3 that Catitain 16 Water-Filled Guide Tubes and I Water-Filled Instrument Tube Input Parameters Number of unit cells inassembly: 225 Number of fuel rods inassembly: 208 Number ofguide tubes inassembly: 16 Rod pitch in assembly (cm): 1.44272 Fuel pellet diameter (cm): 0.936244 Fuel cladding outer diameter (cm): 1.0922 Guide tube outer diameter (cm): 1.3462 Guide tube inner diameter (cm): 126492 Instrument tube outer diameter (cm): 1.38193 Instrument tube Inner diameter (cm): 1.12014 Assembly pitch (cm): 21.81098 Fuel-to-Moderator Volume Ratio Calculation:

Identifier of Equation(s) Utilized: I (Table 7.2-S)

Fuel-to-Moderator Volume Ratio 0.529832 Moderator Unit Volume InCentral Unit Cell of Path B Model:

Identifier of Equation(s) Utilized: 2 (Table 72-5)

Waste Package Development Design Analysis

Title:

CRC Depetion Caluitions for the Rodded Assemblies inBatchcs 10 and II of Crystal UverUnit 3 Document Identlifie BBAOOOO001717-0200-0044 REV 00 Page 35 of 82 Table 7.2-1 Set I Path B Unit Cell Model Dimension Calculation Spreadsheet for the Rodded Assembly Axial Regions from Fuel Batch 10 of Crystal River Unit 3 Moderator Unit Volume In Central Unit Cell of Path B Model - 1.914755 Fuel Unit Volume in Fuel Rod Unit Cell:

Identifier of Equation(s) Utilized: 3 (Table 72-5)

Fuel Unit Volume in Fuel Rod Unit Cell - 0.658443 Moderator Unit Volume In Fuel Rod Unit Cell:

Identifier of Equation(s) Utilized: 4 (Table 72-5)

Modertor Unit Volume in Fuel Rod Unit Cell - 1.144S39 Number of Fuel Rod Unit Cells that must be Represented In the Homogenized Zone of the Path B Model:

Identifier of Equation(s) Utilized: 5 (Table 72-5)

Number of Fuel Rod Unit Cells that must be Represented in the Homogenized Zone oftthe Path B Model - 12.36742 Path B Unit Cell Model Dimensions:

Outer Radius Zone I (cm) Zone Description Inner 1 0.63246 Water filled gap 2 0.67310 Ouide tube 3 0.81397 Guide tube unit cell moderator 4 2.97599 Homogenized region Outer 5 2.99939 Moderator in the assenbly-w-assembly gap Notes: The Zone 4 outer radius Is calculated using Equation 6 (Table 72-5).

The Zone S outer iadius is calculated using Equation 7 (Table 7.2-5).

Waste Package Development Design Analysis r Assemblies Batches

Title:

CRC Depletion Calculations for the Rodded 1 o Cysta River Unit 3 Document Identifier EBAOOOOO01717-0200-00 Ev co REV00

- page 36 of 82 Table 7.2-2 Set 2 Path B Unit Cell Model's Dimension Calculation Spreadsheet for the Rodded Assembly Axial Regions from Fuel Batch 10 of Crystal River Unit 3 SAS2H Path B Unit rell Model Dimension Calecultlons for the Rodded Path B Models for Use In Assembly Ashl Reglons of Fuel Batch 10 of Carstal River Unit 3 that have a BPRA Insertion History Input Parameters Number of unit cells in assembly: 22S Number offuel rods in assembly: 208 Number of guide tubes hi assembly: 16 Number of BPR's in assembly: 16 Rod pitch in assembly (on): 1.44272 Fuel pellet diameter (cm): 0.936244 Fuel cladding outer diameter (cm): 1.0922 Gui&e tube outer diameter (cm): 1.3462 Guide tube inner diameter (cm): 1.26492 BPR cladding outer diameter (cm): 1.0922 BPR cladding inner diameter (cm): 0.9144 BP pellet diameter (cm): 0.8636 Instrument tube outer diameter (cm): 1.38193 Instrument tube Inner diameter (cm): 1.12014 Assembly pitch (cm): 21.81098 Fuel-to-Moderator Volume Ratio Calculation:

Identifier of Equation(s) Utilized: I (Table 7.2-5)

Fuel-o-Moderator Volume Ratio - O.560945 Moderator Unit Volume In Central Unit Cell of Path B Model:

Identifier of Equation(s) Utilized: 2 (Table 7.2-5)

Moderator Unit Volume in Central Unit Cell of Path B Model - 0.9778S2 Fuel Unit Volume In Fuel Rod Unit Cell:

Identifier of Equation(s) Utilized: 3 (Table 7.2-5)

Fuel Unit Volume In Fuel Rod Unit Cell - 0.688443

Waste Package Development Design Analysis

Title:

CRC Depletion Calculations for the Rodded Assemblies in Batches 10 and 11 of Crystal River Unit 3 4 Document Identifier. BBAOO0000-01717.0200-44 REV 00 Page 37 of 82 Table 72-2 Set 2 Path B Unit Cell Model's Dimension Calculation Spreadsheet for the Rodded Assembly Axial Regions from Fuel Batch 10 of Crystal River Unit 3 Moderator Unit Volume in Fuel Rod Unit Cell:

Identifier of Equation(s) Utilized: 4 (Table 7.2-5)

Moderator Unit Volume in Fue Rod Unit Cell- 1.144539 Number of Fuel Rod Unit Cells that must be Represented In the Homogenized Zone of the Path B Model:

Identifier of Equation(s) Utilized: S (Table 72-S)

Number of Fuel Rod Unit Cells that must be Reprcsented in the Homogenized Zone ofthe Path B Model I .81651 Path B Unit Cell Model Dimensions:

Outer Zone Descriptions Radius With Absorbing With Non.Absorbldig Zone U -

(Cm) BPRA lnserted SPRA Inserted Inner 0.43180 Absorbing BP Material Non-Absorbing BP Material 2 0.45720 Helium Gap Helium Gap 3 0.54610 BPR cladding BPR cladding 4 0.63246 Water Filled Gap Water Filled Gap S 0.67310 Guide tube . Guide tube 6 0.81397 Unit cell moderator Unit cell moderator 7 2.91402 Homogenized region Homogenized region Outer 8 2.93693 Moderator Outside Moderator Outside Assembly Assembly Notes: The Zone 7 outer radius is calculated using Equation 6 (Table 7.2-5).

The Zone 8 outer radius is calculated using Equation 7 (Table 72.5)

The Path B model that is used after the removal of the BPRA during a statepoint depletion calculation must use the same number of radial zones as the Path B model with the BPRA inserted. One difference between the Path B model with the BPRA removed and the Path B model with the BPRA inserted is that the materials in zones 1 through 3 are changed to water. Another difference is that the outer radius of zones 7 and 8 are adjusted to match the homogenized region and outer water region dimensions of the base Path B model (the Path B model with all empty guide tubes). Typically, a BPRA is not moved or removed during a reactor cycle. In this analysis there is no instance when a BPRA would need to be

Waste Package Development Design Analysis

Title:

CRC Depletion Calculations for the Rded Assemblies in Batches 10 VAd 11 of Crystal Rier Unit 3 Document Identifier. BBAOOOOOO-01717-020040044 REV oo Page 38 of 82 removed from an assembly axial node during a statepoint calculation. For this reason, the Path B model for the assembly node after removal of a BPRA during a statepoint calculation is not used in any of the assembly depletion calculations documented in this analysis.

Table 7.2-3 Set 3 Path B Unit Cell Model's Dimension Calculation Spreadsheet for the Rodded Assembly Axial Regions from Fuel Batch 10 of Crystal River Unit 3 Path B Models for Use In Assembly Axial Reglons of Fuel Batch 10 of Crstal RIver Unit 3 that hbae a CRA Insertion Wistorv Input Parameters Number of unit cells in assembly: 22S Number of fuel rods inassembly: 208 Number of guide tubes Inassembly: 16 Number of CR's inassembly: 16 Kod pitch in assembly (cm): IA4272 Fuel pellet diameter (cm): 0.936244 Fuel cladding outer diameter (cm): 1.0922 Guide tube outer diameter (cn): 13462 Guide tube Inner diameter (cm): 1.26492 CR cladding outer diameter (cn): 1.1176 CR cladding Inner diameter (cm): 1.01092 CR absorber material diameter (cm): 0.99568 Instrument tube outer diameter (cm): 1.38193 Instrument tube Inner diameter (cm): 1.12014 Assembly pitch (cm): 21.81098 Fuel-to-Moderator Volume Ratio Calculation:

Identifier of Equation(s) Utilieed: I (Table 7.2-5)

Fuel-to-Moderator Volume Ratio - 0S62499 Moderator Unit Volume In Central Unit Cell of Path B Model:

Identifier of Equation(s) Utilized: 2 (Table 72-S)

Moderator Unit Volume In Central Unit Cell of Path B Model - 0.933769 Fuel Unit Volume in Fuel Rod Unit Cell:

Identifier of Equation(s) Utilized: 3 (Table 7.2-S)

Waste Package Development Design Analysis

Title:

CRC Depletion Calculations for the Rodded Assemblies in Batches 10 and 11 of Crystal River Unit 3 Document Identlifer BBA000000o01717-200-00D4 REV 00 Pace 39 d 82 Table 7.2.3 Set 3 Path B Unit Cell Model's Dimension Calculation Spreadsheet for the Rodded Assembly Axial I Regions from Fuel Batch 1i of Crystal River Unit 3 Fuel Unit Volume in Fuel Rod Unit Cell - 0.688443 Moderator Unit Volume InFuel Rod Unit Cell:

Identifer of Equation(s) Utilized: 4 (Table 72-5)

Moderator Unit Volume in Fu Rod Unit CCel - 1.144539 Number of Fuel Rod Unit Cells that must be Represented Inthe Homogenized Zone of the Path B Model:

Identifier of Equation(s) Utilized: S(Table 72-5)

Number of Fuel Rod Unit Cells that must be Reprsetd in the Homogenized Zone ofthe Path B Model - 11.76595 Path B Unit Cell Model Dimensions:

Outer Radius With CRA Inserted With CRA Removed Zone 8 (cm) In Adia! Rerion from Axal Renion Inner I OA9784 CR Absorber Material Water 2 0.50546 Helium Gap Water 3 0.55880 CR cladding Water 4 0.63246 Water Water S 0.67310 Guide tube Guide tube 6 0.31397 Unit cell moderator Unit cell moderator 7 2.90826 Homogenized region Outer 8 2.93113 Moderator Outside Assembly 7 2.97599 - Homogenized region Outer 8 2.99939 - Moderator Outside

_ ~~~~~~~~~Assembl~y, Notes: The Zone 7 outer radius Iscalculated using Equation 6 (Table 72-5).

The Zone 8 outer radius is calculated using Equation 7 (Table 7.2-S).

The outer radius values for zones 7 and 8 with the control rod removed are calculated as shown in Table 7.2-1.

Waste Package Development Design Analysis

Title:

CRC Depletion Calculations for the Roded Assemblies in Batches 10 and II of CysUalverUnit 3 Documentidentifier. BBA000000-01717.0200.0044REVOO Page 40 of 82 Table 7.24 Set 4, with a Grey APSRA, Path B Unit Cell Model's Dimension Calculation Spreadsheet for the Rodded Assembly Axial Regions from Fuel Batch 10 of Crystal River Unit 3 Path R Models for Use In Assembl Axis Regions of Fuel Batch 10 Crystal Rlvcr UnIt 3 that have a Grev APSRA TIsertion History Input Parameters Number ofimit cells in assembly: 225 Number of fuel rods in assembly: 208 Number of guide tubes in assembly- 16 Number of APSR's in assemby: 16 Rod pitch in assembly (cm): 1.44272 Fuel pellet diameter (cm): 0.936244 Fuel cladding outer diameter (cm): 1.0922 Gulae tube outer diameter (cm): 1.3462 Guide tube Inner diameter (cm): 1.26492 APSR cladding outer diameter (cm): 1.1176 APSR cladding inner diameter (cm): 0.98044 APSR absorber material diameter (cm): 0.95250 Instrument tube outer diameter (cm): .38 193 Instrmient tube inner diameter (cm): 1.12014 Assembly pitch (cm): 21.81098 The APSR follow rod has the same dimensions as the APSR cladding and is filled with waer.

Fuel-to-Moderator Volume Ratlo Calculation:

Identifier of Equation(s) Utilized: I (Table 7.2-5)

Fuel4o-Moderator Volume Ratio for the cross-section of dhe assembly containing the absorbing region of the APSRA - 0.562499 Fuel-to-Moderator Volume Ratio for the cross-section of the assembly containing the follow rod region of the APSRA - 0.537017 Moderator Unit Volume InCentral Unit Cell of Path B Model:

Identifier of Equation(s) Utilized: 2 (Table 7.2-5)

Moderator Unit Volurme Inthe Central Unit Cell of the Path B Model for the Inserted APSR Absorber Region - 0.933769 Moderator Unit Volume in the Central Unit Cell ofthe Path B Model for die Inserted APSR Follow Rod - 1.688743

Waste Package Development Design Analysis

Title:

CRC Depletion Calculations for the Rodded Assemblies In Bathes Dand 11 ofCysa Riv Unit 3 Document Identifir. BBAOOOOOO-01717-020000044 REV _ _ Page 41 of 82 Table 7.24 Set 4, with a Grey APSRA, Path B Unit Cell Model's Dimension Calculation Spreadsheet for the Rodded Assembly Axial Regions from Fuel Batch 10 of Crystal River Unit 3 Fuel Unit Volume In Fuel Rod Unit Cell:

Itdentifier of Equation(s) Utilized: 3 (Table 72-5)

Fuel Unit Volume in Fuel Rod Unit Cell - 0.688443 Moderator Unit Volume in Feel Rod Unit Cell:

Identifier of Equation(s) Utilized: 4 (Table 72-5)

Moderator Unit Volume in Fuel Rod Unit Cell - 1.144539 Number of Fuel Rod Unit CellS that Must be Represented In the Homogenized Zone of the Path B Model:

Identifier of Equation(s) Utilized: 5 (Table 72-5)

Number of Fuel Rod Unit Cells that must be Represented in the Homogenized Zone ofthe Path B Model with the APSR Absorber Region Inserted- 11.76595 Number of Fuel Rod Unit Cells that must be Represented in tih Homogenized Zone of the Path B Model with the APSR Follow Rod Region Inserted - 12.28740 Path B Unit Cell Model Dimensions:

Outer Radius With APSRA Inserted With APSRA Removed With APSRA Follow Rod Zone # (CM) in Axial Reglon from AXIal Region Axial Region Inserted Inner 0.47625 APSR Absorber Material Water Water 2 0.49022 Heliun Gap Water Water 3 0.55880 APSR cladding Water APSR cladding 4 0.63246 Water Water Water 5 0.67310 Guide tube Guide tube Guide tube 0.81397 Unit cell moderator Unit cell moderator Unit cell moderator

-- K 7 2.90826 Homogenized region Outer 8 2.93113 Moderator Outside Assembly 7 2.97599 Homogenized region

Waste Package Development Design AnalysIs

Title:

CRC Depletion Calculations for the Rodded Assemblies in Batches 10 and 11 of Crystal River Unit 3 Document Idenftifir. BBAOOOO.017170200-00044 REV 00 Page 42 of 82 Table 7.2-4 Set 4, with a Grey APSRA, Path B Unit Cell Modeld' Dimension Calculation Spreadsheet for the Rodded Assembly Axial Regions from Fuel Batch 10 of Crystal River Unit 3 j Outer 3 2.99939 - Moderator Outside _

I Assembly 1 7 2.96707 - Homogenized region l Outer 8 2.99040 - - Moderator Outside

_ _ _ __r Assembly, Notes: -lhe Zone 7 outcr radius is calculated usmng Equation 6 (Table 7.2-5).

The Zone 8 oute r adius is calculated using Equation 7 (Table 7.2-5).

Thle outer radius values for zones 7 and 8 withi dwiAPSR rnod am calculated as shlown In Table 72-1.

Table 7.2-5 Equations Utilized In the Path B Model Dimension Carculatlon Spreadsheets Presented in Tables 7.2-1 and 7.2-4 (The equations in this table are derived.)

Equation 1 (Fuel-to-Moderator Volume Ratio in Actual Assembly):

F (Number of Fuel RodX(XFuel Pellet Diameter)2

- Ratio = 4 At ((Number of Fuel Rods)[Rod Pitch.2 -(Clad OD)2(.)J, 4

2 (Number of &npt GT's)[Rod Pitch -(GT OD9(I)+(GT JD)2( )]+

4 4 2

(Number of Rodded GT's)(Rod Pitch -(GT OD*(4!)+(GT ID)2( 4)-(Inserted Rod OD9(-)Y)+

4 4 4 (APSR Follow Rod ID)() .+[RodPitch2 -(iT OD)2( I)+ (lT ID)2( !.)])

4 4 4 where GT means guide tube, 1T means instrument tube, and ID means inner diameter, OD means outer diameter. This equation assumes that there is no instrument inserted in the instrument tube, and te instrument tube is filled with moderator. The APSR Follow Rod ID is only specified if the follow rod region of an APSRA is being represented in the Path B model.

Equation 2 (Central Unit Cell Moderator Volume):

CUCMV = Rod Pitch2-(GT ODA( . )+(GT IDA. )-(Inserted Rod ODA Q )

4 . 4 4

Waste Package Development Design Analysis

Title:

CRC Depletion Calculations for the Rodded Assemblies In Batches to and 11 of Cfyl Rir Unit 3 Document Identlfier. BBAOOOOOO-0171 7.2ooo44 REV 00 Page 43 of 82 Equation 3 (Fuel Volume in an Assembly Lattice Cell Containing a Fuel Rod):

FV. (Fuel Pellet OD?("4) 4 Equation 4 (Moderator Volume in an Assembly Lattice Cell Containing a Fuel Rod):

MV = Rod Pitch2 -(Fuel Clad OD)2(-r) 4 Base equation from which Equation 5 is derived:

F Raio2 X (cF)

M CUCMV+ x (MA¢)

where x is the number of assembly lattice cells containing fuel rods that must be represented in the Path B homogenized region.

Equation 5:

F (M RatioXCUCMV) x= M FV-(F RatioXMV)

M Base equations from which Equations 6 and 7 are derived:

Area of Any Annular Region in the Path B Model 7C (Outer Radius of Annular Region2 -Inner Radfus of Anmdar Region2)

Outer Radius of Annular Region =__Area of Annulr Region

• JR2 where IR means the inner radius of the annular region.

Equation 6:

Path B Model Homogenized Region Outer Radius = x (Rod Pitch9 2 Equation 7:

Waste Package Development __Design Analysis

Title:

CRC Depletion Calculations for the Rodded Assemblies in Batches 10 and II ofCrystal River Unit 3 Document Identifier: BBAOOO4OO1717-0200-00044 REV 00 Page d4 of 82 Assembly-to -Assembly Spacing Moderator Zone Outer Radius =

{ (x 1)

Number of Lattice Cells In Assembly

[Assembly Pitch2 -(Rod Ptch9(Number of Lattice Cells in AXssembJy)]( -X)+IR }° 7.3 Cycle Irradiation History Layouts for the Depletion of the Rodded Assemblies in Batch 10 of Crystal River Unit 3 The irradiation time step layouts for the statepoint depletion calculations performed with the SAS2H control module, as documented in this analysis, will vary depending on whether or not the analyzed assembly has a CRA or APSRA insertion history in the statepoint calculation of interest. This variation in irradiation time step layouts between statepoint calculations containing rod insertion histories occurs because the rod insertion histories vary between statepoint calculations for different assemblies. The rod insertion histories for an assembly must be modeled such that the appropriate axial nodes of the fuel assembly are depleted using the appropriate neutron flux and spectrum over the correct exposure duration. The presence of a CRA or APSRA will effect the isotopic inventory in a fuel assembly local axial region as a result of the hardened neutron spectrum. In general, a hardened neutron spectrum (a higher average energy for the neutron population) will be produced as a result of decreased neutron moderation and increased parasitic capture of thermal neutrons. A locally hardened neutron spectrum in a thermal reactor for a short period of time will result in a local decrease in reactivity due to the following:

I) a decrease in the thermal utilization factor (the ratio of thermal neutron absorptions in the fuel to total thermal neutron absorptions);

2) a decrease in the resonance escape probability (the fraction of fission neutrons that manage to slow down from fission to thermal energies without being absorbed).

The presence of a locally hardened neutron spectrum for longer periods of time will result in the build-up of Pu-239 through the parasitic capture of fast neutrons by U-238 with subsequent beta decay through Np-239. Due to the lower depletion of U-235 through fission and the increase production of Pu-239 through parasitic capture by U-238, the fissile content and hence reactivity of the fuel will be greater upon transition back to a thermal neutron spectrum rather than if the fuel had experienced a continuous thermal neutron spectrum. Therefore, the use of BPRAs, CRAs and APSRAs in reactor operation is not only for power regulation, but also for fuel assembly burnup extension. The isotopic inventory may be quite different between fuel with and without an absorbing rod assembly insertion history. These isotopic inventory differences must be accounted for in the CRC depletion calculations to allow for correct prediction of core lcff values in subsequent CRC reactivity evaluations.

In SAS2H, the duration of an irradiation interval may be separated into a number of time steps of variable length. Typically, an irradiation interval is a CRC statepoint depletion calculation interval, or the continuous irradiation time required to go from one CRC statepoint to another. To follow the CRA or APSRA insertion histories, detailed intra-cycle variable irradiation time steps are required. This is

Waste PackageDevelopment Design Analysis

Title:

CRC Depweion Calculations for the Rodded Assemblies In Batches 10 and I11ofCrsA River Unit 3 Document Identifier. BBAOOOOO-0 1717.020-00044 REVOO Page 45 of 92 due to the fact that the CRs and APSRs are only present in a given axial node of an assembly for a given period of exposure during a statepoint depletion calculation. A user specified number of cross-section library updates are performed during each time step of an irradiation interval. The boron letdown curve of the reactor cycle may also be followed by speci1fying, at each irradiation step, a fraction of the soluble boron concentration defined in the base moderator material specification. This boron concentration is applied uniformly over the irradiation time step. The boron concentration fraction at the mid-point of each irradiation time step is specified in the SAS2H depletion calculations of this analysis to appropriately follow boron letdown curves. Considering the cross-section update frequency, the boron letdown data, and the absorber rod assembly insertion histories, the following three primary requirements apply to determining an appropriate reactor cycle irradiation layout for a rodded assembly.

I) The duration of each time step should be specified such that a maximum of 80 days of irradiation is not exceeded between cross-section updates. The SAS21H calculations in this analysis utilize one cross-section update per irradiation step. Therefore, the maximum duration of any time step in any reactor cycle irradiation layout of this analysis should not exceed 80 days. Tle 80 day limit is an arbitrary limit based on engineering judgement. The 80 day irradiation time step limit should assure that the isotopic concentrations of the system (primarily fuel and borated moderator) will not alter the neutron spectrum radically enough to cause a time step of the depletion calculation to be performed without the availability of cross-sections Which have been properly weighted with an appropriate neutron spectrum and spatial flux.

2) Any radical perturbations in the boron letdown curve should be followed by defining irradiation time step durations such that the average boron concentration over each time step is representative of the actual boron letdown. Usually, the 80 day time step limit imposed for cross-section update frequency is adequate to properly follow a reactor cycle's boron letdown curve.

3) The duration of each time step should be specified such that the insertion of a CRA or APSRA, in a given assembly axial node may be modeled for the correct exposure time in terms of EFPD. A more detailed description of the meaning of this statement is warranted. In SAS2H there is an option to vary the Path B unit cell model between irradiation steps as long as the number of radial zones in the Path B models of a given SAS2H calculation (i.e., statepoint depletion calculation) remain the same. Therefore, an assembly axial node represented in a given SAS2H statepoint depletion calculation that has a CRA or APSRA insertion history for a specified period of exposure (that is a fraction of the exposure covered by the statepoint depletion calculation) may be modeled appropriately by changing the Path B model from one representing the insertion of a CRA or APSRA to one representing the removal of a CRA or APSRA at the appropriate time step (corresponding to the CRA or APSRA removal time).

All three of the requirements previously described must be correctly addressed in the SAS2H input decks developed for each axial node of an assembly in each statepoint depletion calculation. Assuring that the cross-section update frequency and the boron letdown curves are properly modeled is usually a by-product of developing the irradiation layouts for the statepoint depletion calculations containing

Waste Package Development Design Analysis

Title:

CRC Depletion Calculadons for the Rodded Assemblies in Batches 10 and 11 of Cystal Rver Uit 3 Document Identifler BBA0000O.o17170200.00044 REV 00 Page 46 of 82 either CRA orAPSRA insertion history. The irradiation time step layout for a given statepoint depletion calculation must be developed such that breakpoints exist between irradiation time steps that allow for the appropriate removal or insertion of a CRA or APSRA to obtain the correct integrated neutron spectrum exposure for each axial node of the assembly. It becomes obvious then that the complexity of the irradiation time step layout for a given statepoint calculation is proportional to the number of CRC axial nodes being modeled and the frequency of CRA or APSRA movement during the assembly depletion. The tine steps developed to model CRA or APSRA insertion histories are also designed to encompass the cross-section update and boron letdown requirements. A program entitled ORLAYOUT" was written to automate the development of appropriate irradiation time step layouts for the statepoint depletion calculations of an assembly containing either a CRA or APSRA insertion history. The RLAYOUT program is described in Attachment m of reference S.11.

The RLAYOUT program is only utilized to determine the irradiation tinle step layouts for the CRC statepoint depletion calculations that contain either a CRA or APSRA insertion history. A single assembly may have a combination of CRC statepoint calculations that either require or do not require the RLAYOUT developed irradiation time step layouts. For the CRC statepoint depletion calculations that do not require the consideration of CRA or APSRA insertion histories, the irradiation time step layouts are developed by considering the cross-section update frequency and the boron letdown data. Tables 7.3-1 and 7.3-2 contain the CRC statepoint depletion calculation time step layouts for each reactor cycle that is relevant to statepoint calculations documented in this analysis which do not have either a CRA or APSRA insertion history. The mid-step boron concentrations presented in Tables 7.3-1 and 7.3-2 are obtained by using linear interpolation within the data presented in Tables 4.1.9-1 and 4.1.9-2. A description of the linear interpolation procedures employed arc presented in the "UNITSCONVERSION" subroutine description section of the CRAFT code description in Attachment I of reference 5.11 .

The irradiation time step layouts developed with the RLAYOUT program for the assemblies documented in this analysis are presented in Tables 7.3-3 and 7.34. Tables 7.3-3 and 7.3-4 contain information required to prepare the irradiation layout portion and the CRA or APSRA insertion history portion of the CRAFTinput decks for assemblies containing either a CRA or APSRA insertion history.

The boron letdown data utilized by RLAYOUT in developing the irradiation layouts that are presented in Tables 7.3-3 and 7.3-4 is not exactly the same as that utilized in developing the irradiation history layouts for the non-rodded statepoint depletion calculations as presented in Tables 7.3-1 and 7.3-2. The boron letdown data provided to the RLAYOUT program is taken from the data presented in 4.1.9-1 and 4.1.9-2. However, some of the measured boron concentrations shown in Tables 4.1.9-1 and 4.1.9-2 were eliminated due to the fact that the particular boron concentration measurements in question were not made at nominal ful-power core operation conditions. The use of the entire set of boron letdown data from Tables 4.1.9-1 and 4.1.9-2 in the non-rodded statepoint depletion calculation layouts has no adverse effect on the depletion calculation results. The modified boron letdown data from Tables 4.1.9- .

I and 4.1.9-2 is presented in Tables 7.3-5 and 7.3-6. The acronym 'ppmb" in the following tables means part per million of natural boron by mass of moderator.

Waste Package Development Design Analysis Tltle: CRC Depletion Calculations for the Rodded Assemblies in Batches 10 and II of Crystal Rir Unit 3 DocumentIdentifier BBAOOoOoo.017174200-00044REVOO Page 47 of 82 Table 73-1 Crystal River Unit 3 Cycle-8 Irradiation listoiy Layout for Non-Rodded Assemblies Cycle-8 BOC to Stpt2 (97.6 EFPD) 2 Number of Irradiation Steps 48.8: Length of Each Irradiation Step (EFPD) e.tP%

M.tmhar MI;Steo

-- I- ---

nruymh MiLtADn FFPD 1510.73 24.40 2 1419.25 73.20 Stpt2 (97.6 EFPD) to Stpt3 (139.8 EFPD)

I :Number of Irradiation Steps

- 42.2: Length of Each Irradiation Step (EFPD)

Step Number Mid-Stpn nnmIb Mid-Step EFPD 1 1305.52 118.70 Stpt3 (139.5 EFPD) to Stpt4 (404.0 EFPD) 4 Number of Irradiation Steps 66.05: Length of Each Irradiation Step (EFPD)

Sted Number Mid-Star) comb Mid-Ste:) EFPD I 1142.75 172.83 2 985.95 238.88 3 793.58 304.93 4 588.91 370.98 Stpt4 (404.0 EFPD) to Stpt5 (409.6 EFPD)

I: Number of Irradiation Steps 5.6: Length of Each Irradiation Step (EFPD)

Stea Number Mid-Sten comb Mid-Step EFPD 484.53 408.80 I1 484.53 406.60

Waste Package Development Design Analysis TiMe: CRC Depletion Calculations for the Rodded Assemblies hI Batches 10 and II of Cuytal River Unit 3 Document Identifier. BBAOOOOOO-01 717-0200.00044 REV O0 Page 48 of 82 Stpt5 (409.6 EFPD) to Stpt6 (515.5 EFPD) 2 Number of Irradiation Steps 52.95 Length of Each Ilradiation Step (EFPD)

Stec Number Mid-Step ppmb Mid-Step EFPD 1 416.34 , 436.08 2 274.55 489.03 Stpt (515.5 EFPD) to EOC (535.9 EFPD) 1: Number of Irradiation Steps 20.4 Length of Each Irradiaton Step (EFPD)

Step Number Mid-Step ppmb Mid-Step EFPD 185.39 525.70 Table 7.3-2 Crystal River Unit 3 ycle-9 Irradiation History Layout for Non-Rodded Assemblies Cycle-9 BOC to Stpt2 (158.8 EFPD) 3 Number of Irradiation Steps 52.93 Lent of Each Irradiation Step (EFPD)

SteP Number Mid-Step ppmb Mid-Step EFPD 1 1599.85 26.47 2 1491.21 79A0 3 1361.78 132.33 Stpt2 (158.8 EFPD) to Stpt3 (219.0 EFPD) 1 : Number of Irradiation Steps 60.2: Length of Each Irradiatio Step (EFPD)

Stev Number Mid-Step Ppmb Mld-Step EFPD 1 1211.60 188.90 Stpt3 (219.0 EFPD) to Stpt4 (363.1 EFPD)

Waste Package Development Design Analysis

Title:

CRC Depletion Calculations for the Rodded Assemblies in Batches 10 and 1 of CoYSa River Unit 3 or Document Identifier. BBAODOOOO-01717.02 REV 00 Page 49 of 82 2: Number of Irradiation Steps 72.05 : Length of Each Irradiation Step (EFPD)

Sten NumbAr Wed-Atpon nmb WMid-Stan EFPD 1016.51 255.03 2 602.70 327.08 Stpt4 (363.1 EFPD) to EOC (557.23 EFPD) 3: Number of Irradiation Steps 64.71: Length of Each Irradiation Step (EFPD)

Stfn Niumber Mid-StAn nnmb Mid-StAn FFPD

- 584.95 395.46

-2 388.60 460.17 3 192.66 524.88 Table 7.3-3 Rodded Irrdiation Time Step Layout for Assembly Hi12 IRRADIATION LAYOUT FOR ASSEMBLY: H12 Cycle-09, .0 EFPD to Cycle-09, 158.8 EFPD Statepoint Calculation Step Exposure at Mid-Step Boron Irradiation Duration End of Step Concentration Step Number (EFPD) (EFPD) (ppm) 1 2.29 2.29 1646.8 2 32.23 34.52 1614.8 3 59.57 94.09 . 1528.1 4 59.57 153.66 1382.4 5 5.34 159.00 1300.1 Cycle-09, 158.8 EFFD to Cycle-09, 219.0 EFPD Statepoint Calculation Step Exposure at Mid-Step Boron Irradiation Duration End of Step Concentration Step Number (EFPD) (EFPD) (ppm) 1 2.57 2.57 1289.4 2 6.88 9.45 1276.5 3 50.55 60.00 1198.8 4 .20 60.20 1131.9 Cycle-09, 219.0 EFPD to Cycle-09, 363.1 EFPD Statepoint Calculation

• Step Exposure at Mid-Step Boron Irradiation Duration End of Step Concentration Step Number (EFPD) (EFPD) (ppm)

Waste Package Development Design Analysis

Title:

CRC Depiction Calculations for te Rodded Assemblies in Batches tO and II of Ctysal River Unit 3 Document Identftfer. BBAOOOOOO.01717.0200-0044 REV 00 Page 60 of 82 1 12.56 12.56 1111.4 2 3.64 16.20 1085.4 3 63.90 80.10 978.0 4 63.90 144.00 790.9 5 .10 144.10 691.8 NODAL ROD ASSEMBLY INSERTION LAYOUT FOR FUEL ASSEMBLY: 112 COLUMN A: Cycle-09, .0 EFPD to Cycle-09, 158.9 EFPD Statepoint Calculation COLUMN B: Cycle-09, 158.8 EFPD to Cycle-09, 219.0 EFPD Statepoint Calculation COLUMN C: Cycle-09, 219.0 EFPD to Cycle-09, 363.1 EFPD Statepoint Calculation X - Rod assembly inserted in corresponding node during the irradiation step 11 A 11 B 11 C NODE # 11l1213141511112131411112131415 1 11 I I I I 11 II I 11 I I I1 2 11 I I I I 11 I I I 11 I I I1 3 11 I I I I 11 II I 11 I I I1 4 11 I I I I 11 I I 11 I I .1 1 5 11 I I I I 11 II II I I I1 6 11 1 I 1 I tl I I I II I I I I 7 11 1 1 1 1 II I I I II I I I I 8 11I 11 1 1111 11 11.1 1I1I 9 IIXIXI I I IlXI I I 1IXI I I I 10 1IXIXIXIXIXIIXIXIXIXIIXIXIXIXIX 11 1lXIXIXIXIXIIXIXIXIXIlXIXIXIXIX 12 11XIX1 11X1X1XX11X1XIX1X 14 1 IX I I I II I I I II I I I I 15 11 I I I I I I I I 11.1 I I I 16 1I I I I I II I I I II I I 1 17 11 I I I I 11 I I 1 It I I I I 18 11 1 1 1 1 11 1 1 1 11 1 1 1 1 Table 7,3-4 Rodded Irradiation Time Step Layout for Assembly H27a IRRADIATION LAYOUT FOR ASSEMBLY: H27a Cycle-09, .0 EFPD to Cycle-09, 158.8 EFPD Statepoint Calculation Step Exposure at Mid-Step Boron Irradiation Duration End of Step Concentration Step Number (EFPD) (EFPD) (ppm) 1 2.09 2.09 1647.0 2 55.24 57.33 1593.9 3 50.74 108.07 1483.1 4 50.74 158.80 1359.0 Cycle-09, 159.8 EFPD to Cycle-09, 219.0 EFPD Statepoint Calculation Step Exposure at Mid-Step Boron Irradiation Duration End of Step Concentration Step Number (EFPD) (EFPD) (ppm)

_______________14.09_________14.09__________1274__________

1 14.09 14.09 1274.3

Waste Package Development Design Analysis TnUe: CRC Dpetion Clculaios fo the oddedAsmblies hi Batches 10 Ad 11 of ciyw River Unit 3 Document dentflflr BBAOOO .01717.0200-00044 REV 00 Pane 81 of 82 2 46.11 60.20 1193.5 Cycle-09, 219.0 EFPD to Cycle-09, 363.1 EFPD Statepoint Calculation Step Exposure at Mid-Step boron Irradiation Duration End of Step Concentration Step Number (EFPD) (EFPD) (ppm) 1 36.07 36.07 1074.3 2 54.02 90.09 933.8 3 54.02 144.10 777.2 NODAL ROD ASSEMBLY INSERTION LAYOUT FOR FUEL ASSEMBLY: H27a COLUMN A: Cycle-09, .0 EFPD to Cycle-09, 155.8 EFPD Statepoint Calculation COLUMN B: Cycle-09, 158.8 EFPD to Cycle-09, 219.0 EFPD Statepoint Calculation COLUMN C: Cycle-09, 219.0 EFPD to Cycle-09, 363.1 EFPD Statepoint Calculation X Rod assembly inserted in corresponding node during the irradiation step 11 A 11 B 11 C NODE 1 11121314111121111213 1 1IXIXI I IlXI IIXI 1 2 IIXI I I 11 I 11 I I 3 11 I I I 11 I II I I 4 11 1 I I i 1 II I I 5 IL I I I 11 I 11 I 1 6 11 I I 1 1I 11 I 1 7 11 1 1 I 1 I If I I 9 11 I I I 11 I 11 I I 10 11 I 1 I 11 I1 1 I I 11 11 I I I 11 I 11 I I 12 11 I I I II I II I I 13 II I I I II I II I I 14 . l I II 11 I 1 I 15 11 I I I H, I 11 I 1 16 11 I I I 17 I II I 1 17 11 I I I 11 I 11 II 18 11 I I I It I 11 I I Table 7.3-5 Boron Letdown Data Provided to RLAYOUT for Cycle 8 of Cryital River Unit 3 Exposure (EFPD) Boron Concentration (ppm) 11.2 1537 52.4 1455 78.0 .1411 111.4 1332 154.4 1176

Waste Package Development Design Analysis DesIgn Analysis

,- Waste

Title:

CMC Depletion _

Development Package Calculatios OO for the Rodded AL Asseblies RV0 in BatcheS I0 and I1I of Crysta River Uni 3 Document Identifler.' BB M4OO.1717.20044RV0 Page 62 of 82 Table 73-S Boron Letdown Data Provided to RLAYOUT for Cycle 8 of Crystal River Unit 3 Exposure (EFPD) [ Boron Concentration (ppm) 194.8 1103 234.6 999 271.5 887 338.0 701 390.7 522 445.7 394 474.0 311 513.1 216 Table 73-6 Boron Letdown Data Provided to RLAYOUT for Cyde 9 of Crystal River Unit 3 Exposure (EFPD) l Boron Concentration (Ppm) 22.1 1608 61.5 1535 145.7 1329 192.8 ~ 1201 211.3 1157

.____26 2.0 994 303.7 869 345.7 750 397.9 577 432.5 473 452.4 412 495A. 283 543.4 136 Some interesting behavior appears in the CRA nodal insertion history layouts presented in Tables 7.3-3 and 7.3-4. This interesting behavior refers to the axially staggered nodal CRA insertion locations in

Waste Package Development Design Analysis

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CRc Depletion Calcaons for the Rodded Assembles in Batches 10 andII of Crystal River Unh 3 2 Document ldentiller: BBA0000001717420000044 REV 0_ Page 83 of 82 some of the irradiation steps that are defined. At frst glance, the axial staggering of CRA nodal insertion locations in a given Irradiation time step does not make any sense. This is true from a physical perspective based on knowledge of actual CRA design and reactor operation. However, certain approximations are utilized in performing the CRC depletion calculations as documented in this analysis which result in this strange presentation of CRA insertion histories. The following discussion describes the modeling techniques utilized in the CRC depletion calculations of this analysis which contribute to this staggered CRA nodal insertion phenomena.

In the SAS2H CRC depletion calculations, the time dependency of the CRA and APSRA insertion histories are treated on an integral exposure basis rather than on a real-time irradiation history basis.-

This does not mean that the CRA and APSRA insertion history data utilized in the CRC depletion calculations of this analysis is not the actual insertion history data from the reactor. In fact, the CRA and APSRA insertion history diata for each axial node in each statepoint depletion calculation is based on the true CRA and APSRA movement data obtained during the actual reactor operation. The implementation of this true measured data in the SAS2H CRC depletion calculations is based on modeling CRA and APSRA insertion durations (measured in EFPD) in each axial node of the assembly at the beginning of each CRC statepoint calculation. An average nodal power is utilized in each SAS2H CRC statepoint depletion calculation for a given axial node. This average nodal power is calculated based on the average nodal burnup at the beginning and end of the statepoint depletion calculation. Therefore, EFPD durations in a SAS2H CRC statepoint depletion calculation are calculated based on this average nodal power that is being utilized in the statepoint depletion calculation. The CRA nodal insertion durations (measured in EFPDs of exposure) will need to be modeled in SAS2H based on the assembly average nodal power. Due to the fact that the assembly average nodal power may be less than the actual assembly nodal power during a given period of core operation, the SAS2H insertion time of a CRA in a given axial node may vary, relative to the other assembly axial nodes, depending on the average power that is being utilized in the SAS2H calculation and the nodal exposure (EFPD) required with CRA inserted. This results in the staggered CRA insertion phenomena that is present in some of the data presented in Tables 7.3-3 and 7.3-4.

7.4 The Commercial Reactor Assembly Follow Taskmaster (CRAFT) Code & Usage The Commercial Reactor Assembly Follow Taskm aster (CRAM) code directs the performance of assembly depletion and decay calculations relevant to CRC evaluations. The CRAFT code generates input decks for the SAS2H control module of the SCALE modular code system based on user-defined input which describes the fuel assembly's specifications and irradiation history. Appropriate isotopic concentrations relevant to both the CRC evaluations containing the fuel assembly and subsequent depletion and decay calculations of the fuel assembly are extracted and stored by CRAFT as it generates and executes SAS2H cases required to simulate the complete fuel assembly irradiation history.

The CRAFT code is developed with a high degree of flexibility that provides for the depletion and decay of fuel assemblies with widely varying features under either standard or non-standard core operating procedures. The following listing describes some of the capabilities and usage of the CRAFT code.

Waste Package Development Design Analysis

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CRC Depletion Clculations for the Rodded Assemblies InBatches 10 uld 11 of CNysWal River Unit 3 Document Identilfer. BBA00000017174200.0044 REV 00 Page 64 of 82 The CRAFT code generates and executes appropriate SAS2H cases required to perform a prescribed depletion and decay sequence for a fuel assembly. The depletion and decay sequence is orchestrated from the BOC statepoint calculation of the initial prescribed insertion cycle through the final statepoint calculation of the last prescribed insertion cycle. The CRAFT code extracts and saves fuel and burnable poison isotopics at each statepoint, including BOC statepoints, during the fuel assemblys depletion and decay sequence. A certain number of the generated isotopics in the depleted fuel composition obtained from a SAS2H calculation are not used in the initial charge composition to the next SAS2H calculation due to a lack of cross-section data in the specified cross-section library. The CRAFT code provides a listing of the fuel isotopics from the output of a SAS2H calculation which are not used in the initial charge to the next SAS2H calculation. The isotopics left out of the initial charge are fission products whose reactivity worth is small relative to the isotopics retained in the initial charge composition. The listing of excluded initial charge isotopics allows for a determination of the impact upon the reactivity worth of the initial fuel composition in the subsequent depletion calculation.

Any assembly design may be analyzed within the bounds of the SAS2H control module through the use of the CRAFT code. This includes both PWR and BWR fuel assemblies.

An axial blanket fuel modeling option is available in the CRAFT code. Any U0 2 enrichment may be specified for the axial blanket fuel. The axial blanket fuel may be defined to exist in any of the CRC axial nodes which are defined for the CRAFT calculation.

A spacer grid modeling technique is available with the CRAFT code. The modeling technique homogenizes the spacer grid material throughout the moderator of the fuel assembly by utilizing a user-defined spacer material and spacer material volume fraction in the moderator. The available spacer grid materials include the following- ZIRC-4 1 INCONEL, SS316, SS316S, SS304, SS304S. Any volume fraction of spacer material in the moderator may be specified (including zero).

The fuel cladding, BPR cladding, axial power shaping rod (APSR) cladding, or control rod (CR) cladding in the CRAFT calculation may be designated as any of the following materials- ZIRC-4, INCONEL, SS316, SS316S, SS304, SS304S.

The insertion of a BPR assembly during the irradiation of the fuel assembly may be modeled in the CRAFT calculation. Up to 10 unique BPR assembly designs may be specified for use during the depletion of a fuel assembly. Any type of BPR assembly design may be specified. The default BP material for use in CRAFT calculation is A] 20 3 -B4 C. Any arbitrary BP material may be specified for use in a BPR assembly design. A maximum of 10 unique BP materials may be specified. A maximum of 20 unique elements or isotopes may be specified in any given BP material. A BPR assembly may be inserted in any reactor cycle specified in the CRAFT calculation. Only one BPR assembly design may be specified per cycle. The position of the BPR assembly in the fuel assembly is specified by identifying the top and bottom axial nodes pf the BP material. The BPR assembly remains fixed during a given reactor cycle. TLe depletion of the BP material is tracked during the CRAFT calculation. The appropriate depleted BP material is utilized in statepoint calculations following the BOC to statepoint 2 calculation for a given

Waste Package Development Design Analysis

Title:

CRC Depletion Calculations for the Rodded Assemblies in Batches 10 and II of Cal River Unit 3 Document Identifler: BBAOOOOOo01717.0200-00044 RE 00 Page 55 of 82 reactor cycle. Depleted BP material isotopic concentrations are also retained for use in subsequent mid-cycle statepoint reactivity calculations which may be performed as part of the CRC evaluation process.

The insertion of a CR assembly during the irradiation of the fuel assembly may be modeled in the CRAFT calculation. Up to 10 unique CR assembly designs may be specified for use during the depletion of a fuel assembly. Any type of CR assembly design may be specified. Any arbitrary CR absorber material may be specified for use in a CR assembly design. A maximumn of 10 unique CR absorber materials may be specified. A maximum of 10 unique elements or isotopes may be specified in any given CR absorber material. A CR assembly may be inserted in any reactor cycle specified in the CRAFT calculation. Multiple CR assembly designs may be specified per cycle. The position of the CR assembly in the fuel assembly is specified by identifying the top and bottom axial nodes of sections of the fuel assembly which contain the CR absorber material. The CR assembly position may be changed between each irradiation step of a SAS2H calculation generated by CRAFT. The CR assembly design may also be changed between any two CRC statepoint depletion calculations in a given reactor cycle.

The insertion of an APSR assembly during the irradiation of the fuel assembly may be modeled in the CRAFT calculation. Up to 10 unique APSR assembly designs may be specified for use during the depletion of a fuel assembly. Any type of APSR assembly design may be specified.

Any arbitrary APSR absorber material may be specified for use in an APSR assembly design. A maximum of 10 unique APSR absorber materials may be specified. A maximum of 10 unique elements or isotopes may be specified in any given APSR absorber material. An APSR assembly may be inserted in any reactor cycle specified in the CRAFT calculation. Multiple APSR assembly designs may be specified per cycle. The position of the APSR assembly in the fuel assembly is specified by identifying the top and bottom axial nodes of the APSR absorber material. The APSR assembly position may be changed between each irradiation step of a SAS2H calculation generated by CRAFT. The APSR assembly design may also be changed between any statepoint calculations in a given reactor cycle. For any APSRA modeled, the APSR follow rods are modeled in the axial region above the absorbing region of the APSR. The APSR follow rod material may be specified as a cladding material in the CRAFT input deck.

& A fuel assembly may be inserted in a maximum of 10 reactor cycles during a CRAFT calculation.

A maximum of 20 statepoints (BOC is always considered a statepoint) may be specified in any given reactor cycle in a CRAFT calculation.

A maximum of 23 irradiation steps of variable duration may be specified in any given SAS2H statepoint calculation to be generated during a CRAFT calculation.

A maximum of 50 axial nodes may be.specified in the CRC nodal format for use in a CRAFT calculation. Each axial node may have a unique height.

The CRAFT code utilizes a user-defined input format for fuel temperature, moderator specific volume, and bumup data. The input data must be specified for each axial node in a user-defined

Waste Package Development Design Analysis TIe: CRC Depletion Calculations for the Rodded Assemblies in Batches 10 and 11 of Cryst Rier Unit 3 Document Identlfler: BBAOO0oo.oj7j7.02oo000044 REV 00 Page 66 of 82 nodal format of up to 50 nodes of arbitraMy height. The total assembly active fuel height for the input data descriptions may be different than that specified in the CRC nodal format. Depending on the users needs, the fuel temperature, moderator specific volume and burnup input data may be specified in a different nodal format each time an assembly set of this input data is provided.

Nominal fuel temperature input data representing full-power reactor operation must be provided in units of degrees Fahrenheit for each node in each statepoint calculation to be generated by the CRAFT calculation. Nominal moderator specific volume input data representing full-power reactor operation must be provided in units of cubic feet per pound for each node in each statepoint calculation to be generated by the CRAFT calculation. The nodal average burnup input data must be provided in units of GWd/MTU for each node at each statepoint including the BOC statepoint. All burnup input data that is specified must be cumulative from the initial insertion of the fuel assembly in the reactor.

A continuation CRAFT calculation for an assembly may be initiated from any statepoint in any reactor cycle if all of the nodal consolidated output files ("*.cut" files) from the statepoint calculation imnediately preceding the continuation calculation exist in the CRAFT execution directory.

Additional information on the CRAFT code is provided in the CRAFT user information in Attachment I of reference S.1 1. Instructions on how to develop CRAFT input decks and execute CRAFT calculations are also provided in Attachment I (Ref. S. 1). This attachment also discusses specific modeling procedures and details relevant to the SAS2H fuel assembly depletion calculations which are generated by CRAFT.

7.5 Input & Output Filename Descriptions for CRAFT and SAS211 The CRAFT code generates five types of files identified as either '*.input", ".output", "*.cut",

".msgs", or N*.notesu, where the n*" is the base file set identifier for the statepoint calculation of interest. The ".cut" and ".notes' files are the only files that must be retained for CkC evaluation and documentation purposes. All files are generated in the working directory in which the CRAFT calculation is performed.

All CRAFT generated filenarnes utilize the following format- "(Base File Set Identificr).{suffixj".

Where the suffix corresponds to one of the five file types previously mentioned, and the base file set identifier is a 25 character name containing essential information necessary to delineate one CRAFT generated SAS2H calculation from another.

The base file set identifier for a statepoint calculation contains the following information:

1) reactor identifier (three character);

2) one-eighth core symmetry assembly nimber in current reactor cycle (two digit);

3) axial node number (node I is always the top node) (two digit);

4) reactor cycle number in which the SAS2H calculation starts (two character);

5) EFPD statepoint at which the SAS2H calculation starts (three digit);

Waste Package Development Design Analysis

Title:

CRC Depletion Cakulations for the Rodded Assemblies in Batches 10 and 11 of Crlystl River Unit 3 Document Identfl{er. BBAo00oo0-01717.02o.00oo44 REV 00 Page 67 of 82

6) reactor cycle number in which the SAS2H calculation ends (two character);

7) EFPD statepoint at which the SAS2H calculation ends (three digit).

The format of the base file set identifer is as follows where the numbers identified as #{number) correspond to one of the seven items previously listed- #1 A #2 N #3 DC #4 T #5 AC #6 T #7. The letters contained in the base file set identifier are presented explicitly as shown in the previous format.

The base file set identifier does not contain any spaces.

The ".input" files contain a CRAFT generated SAS2H input deck. The ".output files contain a complete SAS2H calculation output file. The ".cut" files contain the corresponding SAS2H input deck followed by an output extraction, from the final ORIGEN-S pass of the SAS2H calculation, which contains data relevant to CRC evaluations. The "*.msgs' files contain the starndard run-time messages associated with the SAS2H calculation. The ".notes" files contain a listing of the isotopes and their concentration which were left behind in generating the initial charge fuel composition for a continuation SA92H calculation. The ".notes" files are only created for CRAFT generated SAS2H calculations which represent continuation depletion and decay calculations. The "*.cut' and "*.notes' files contain all of the information which is required to perform CRC evaluations or repeat calculations as necessary for quality assurance purposes. The remainder of the CRAFT generated files may be discarded once the

"*.cut" and ".notes" files have been produced correctly.

7.6 Rodded Assembly Depletion Calculations for Fuel Batch 10 of Crystal River Unit 3 Depletion calculations for 4 rodded fuel assemblies from fuel batch 10 of Crystal River Unit 3 are documented in this analysis. The depleted fuel and depleted burnable poison isotopics for these fuel assemblies must be calculated at a number of statepoints during several reactor cycles of Crystal River Unit 3 for use in subsequent CRC reactivity calculations. The assembly depletion calculations documented in this analysis are applicable to CRC statepoints in Cycles 8 and 9 of Crystal River Unit 3.

Table 7.6-1 identifies the CRC statepoint EFPD values in each of these cycles for which isotopic compositions are required.

Table 7.6-1 CRC Statepoint EFPD Values Relevant to Rodded Assembly Depletion Caculations for Fuel Batch 10 of Crystal River Unit 3 Crystal River Unit 3 Reactor e CRC Statepoint EFPD Values 8 (1BOC)

~~~~~~~~~0.0 8 *97.6 8 _ 139.8 8 404.0 8 409.6 8 .515.5

Waste Package Development Design Analysis

Title:

CRC Depletion Calculations for tie Rodded Assemblies in Batches 10 and I I ofCrsal River Unit 3

(* Document ldentlier: BBAOOMOOO017174200-0044 REV 00 Page 68 of 82 Crystal River Unit 3 Reactor Cgcle CRC Statepoint EFPD Values 9 0.0 (BOC) 9 . 158.8

.9 219.0 9 ._ 363.1 CRAFT input decks for each of the fuel assemblies identified in Tables 4.1.6-1 and 4.1.7-1 were developed and executed such that their depleted fuel and depleted burnable poison (if applicable) isotopic concentrations were retained at each of the CRC statepoints identified in Table 7.6-1 for which a particular assembly is inserted. The CRAFT input decks were developed in accordance with the instructions presented in Sections 5 and 7 of Attachment I of reference 5.1 1. SAS2H modeling features incorporated in the depletion calculations of this analysis are described in Attachment I (Ref. 5.1 1). The CRAFT input decks for the assembly depletions documented in this analysis are provided in Attachments I through IV, as documented in Section 9.

The SAS2H input decks generated for the various depletion calculations have similar structures depending on the characteristics of the fuel assembly axial node that is being depleted. The following listing presents the base SAS2H input deck descriptions.

Fuel assembly axial node containing empty guide tubes Fuel assembly axial node containing an absorbing BPRA inserted in the guide tubes Fuel assembly axial node (top node) containing a non-absorbing BPRA region inserted in the guide tubes Fuel assembly axial node containing a CRA insertion in the guide tubes (with or without CRA removal during the depletion calculation)

• Fuel assembly axial node containing an APSRA insertion in the guide tubes (with or without APSRA removal and/or APSRA follow rod region insertion during the depletion calculation)

All of the SAS2H input decks generated by CRAFT in this analysis will correspond to one of the afore-mentioned base SAS2H input decks depending on the assembly characteristics being modeled in the specific depletion calculation. The material compositions of the fuel, burnable absorber, and moderator are modified for each SAS2H case depending on the depleted material compositions at the beginning of the SAS2H case and the irradiation parameters for the SAS2H case as defined in the CRAFT input deck.

The material specifications for the fuel and burnable absorber have different formats in the SAS2H input decks depending on whether the depletion case represents the initial depletion calculation for the assembly axial node or a continuation depletion calculation for the axial node utilizing previously calculated fuel and burnable poison (if applicable) isotopics for the initial charge compositions.

Waste Package Development Dein Analysis

Title:

CRC Depletion Calculations for the Rodded Assemblies InBtches Dand 11 of Cystal River Unit 3

/ Document Identifier. BBAOOOOO0.01717-oo044REVo00 Page 59 of 82 The following ten example SAS2H input decks are presented to demonstrate the modeling techniques employed by CRAFT in generating appropriate SAS2H depletion cases for the fuel assembly depletion calculations relevant to this analysis. These example input decks are actual SAS2H input decks which were generated and executed during the depletion of fuel assemblies relevant to CRC evaluations (the assemblies from which these examples are obtained may not be documented in this analysis). Each section of the SAS2H input decks are modified as necessary to perform each depletion calculation according to the pertinent information provided in the CRAFT input deck.

SAS2H Depletion Input Deck Example 1: BOL Depletion Calculation for a B&W Fuel Assembly Axial Node Containing 208 Fuel Rods, 16 Empty Guide Tubes, and 1 Empty Instrument Tube

-sas2h parm-skipshipdata Crystal River, Unit 3 Assy-03, Node-05 (Cyc-lA, .0 to Cyc-lE, .0 EFPD) 44group latticecell fuel density based on mass of uranium per assembly S total pellet stack volume to account for fuel volume loss to pellet chamfers I

I material specification input uo2 1 den-10.121 1 1066.3 92234 .016 92235 1.930 92236 .009 92238 98.045 end kr-83 1 1-21 1066.3 end kr-85 1 1-21 1066.3 end sr-90 1 1-21 1066.3 end y-89 1 1-21 1066.3 end mo-95 1 1-21 1066.3 end zr-93 1 1-21 1066.3 end zr-94 1 1-21 1066.3 end zr-95 1 1-21 1066.3 end nb-94 1 1-21 1066.3 end tc-99 1 1-21 1066.3 end rh-103 1 1-21 1066.3 end rh-105 1 1-21 1066.3 end ru-101 1 1-21 1066.3 end ru-106 1 1-21 1066.3 end pd-105 1 1-21 1066.3 end pd-108 1 i-21 1066.3 end ag-109 1 1-21 1066.3 end sb-124 I 1-21 1066.3 end xe-131 1 1-21 1066.3 end xe-132 1 1-21 1066.3 end xe-135 1 1-21 1066.3 end xe-136 1 1-21 1066.3 end cs-134 I 1 1-21 1066.3 end Ics-135 1 1-21 1066.3 end Ics-137 1 1-21 1066.3 end Iba-136 1 1-21 1066.3 end la-139 1 1-21 1066.3 end Ize-144 1 1-21 1066.3 end Irid-143 1 1-21 1066.3 end Irnd-145 1 1-21 1066.3 end Ipm-147 1 1-21 1066.3 end Ipm-148 1 1-21 1066.3 end Ind-147 1 1-21 1066.3 end IIsm-147 1 1-21 1066.3 end Ism-149 1 1-21 1066.3 end

Waste Package Development Design Analysis

_. Tite: CRC Depletion Calculations for the Rodded Assemblies in Batches 10 and II ofCyszal Rver Unit 3 Document identMIer: BBAOOOOOO41717-0200-000444REv 00 Page 60 of62 sm-150 1 0 1-21 1066.3 end sm-151 1 0 1-21 1066.3 end sm-152 1 0 1-21 1066.3 end gd-155 1 0 1-21 1066.3 end eu-153 1 0 1-21 1066.3 end eu-154 1 0 1-21 1066.3 end eu-155 1. 0 1-21 1066.3 end arbm-zirc4 6.56 5 0 0 0 8016 0.12 24000 0.10 26000 0.20 50000 1.40 40000 98.18 2 1.0 640.0 end

• material composition of moderator within unit cell

• with smeared inconel spacer grids h2o 3 den-.7343 .99424 588.9 end arbm-bormod .7343 1 0 0 0 5000 100 3 .00092 589.9 end arbm-spacer .7343 5 0 0 0 14000 2.5 22000 2.5 24000 15.0 26000 7.0 28000 73.0 3 .00576 598.9 end he 5 end end comp base reactor lattice specification squarepitch 1.4422 .9398 1 3 1.0922 2 .9576 0 end more data szf-0.50 end I

assembly specification npin/assembly-208 fuelngth-20.003 ncycles-04 nlib/cyc-l lightel-O printlevel-05 inplevel-2 numztotal-05 mxrepeats-1 mixmod-3 facmesh-.50 end 3 .63246 2 .67310 3 .81397 500 2.97599 3 2.99939 assembly depletion/decay parameters I Cycle-lA, one-eighth core assembly number 03 power-1.0928 burn-67.20 down-.OOOOOE+00 bfrac-1.OOO end power-i.0928 burn-67.20 down-.OOOOOE+00 bfrac-.9470 end power-1.0928 burn-67.20 down-.OOOOOE+00 bfrac-.B016 end power-i.0928 burn-67.20 down-195.29 bfrac-.6603 end I

end of input end SAS2} Depletion Input Dcek Example 2: Continuation Depletion Calculation for a B&W Fuel Assembly Axial Node Containing 208 Fuel Rods, 16 Empty Guide Tubes, and 1 Empty Instrument Tube

-sas2h parm-skipshipdata Crystal River, Unit 3 Assy-03, Node-05 {Cyc-lB, .0 to Cyc-18, 142.2 EFPD) 44group latticecell fuel density based on mass of uranium per assembly & total pellet.stack volume to account for fuel volume loss to pellet chamfers material specification input I

arbm-fuel 10.1 183 0 0 0 8016 11.8

Waste Package Development Design Analysis

_. TiTWe: CRC Depletion Calculadons for the Rodded Assemblies in Batches 10 and 1 of Qysta River Unit 3 Document Identfier: BBAOOooo.01717-0200-0044 REV 00I Page 61 of 62 2004 .135E-05 90230 .373E-07 90232 .411E-08 91231 .568E-08 92233 .578E-07 92234 .112E-01 92235 .B87 92236 .147 92238 85.6 93237 .934E-02 94236 .466E-08 94238 .126E-02 94239 .356 94240 .907E-01 94241 .383E-01 94242 .650E-02 95241 .137E-02 95601 .578E-05 95243 .524E-03 96242 .289E-04 96243 .640E-06 96244 .507E-04 96245 .760E-06 96246 .400E-07 1003 .153E-05 3006 .876E-08 32072 .147E-06 32073 .448E-06 32074 .373E-06 33075 .363E-05 32076 . 111E-04 34076 .397E-07 34077 .255E-04 34078 .784E-04 34080 .428E-03 35081 .640E-03 34082 .103E-02 36082 .897E-05 36083 .151E-02 36084 .353E-02 36085 .763E-03 37085 .299E-02 36086 .602E-02 38086 .390E-OS 37087 .787E-02 38087 .249E-07 38088 .113E-01 38089 .249E-03 390E9 .149E-01 38090 .180E-01 39090 .469E-05 40090 .418E-03 39091 .541E-03 40091 .189E-01 40092 .205E-01 40093 .151E-01 40094 .240E-01 41094 .137E-07 40095 .948E-03 41095 .103E-02 42095 .228E-01 40096 .251E-01 42096 .221£-03 42097 .235E-01 42098 .252E-01 43099 .261E-01 44099 .952E-06 42100 .285E-01 44100 .122E-02 44101 .238E-01 44102 .224E-01 44103 .145E-03 45103 .176E-01 44104 .150E-01 46104 .215E-02 46105 .989E-02 44106. .448E-02 46106 .496E-02 46107 .544E-02 46108 .342E-02 47109 .248E-02 46110 . 1O1E-02 48110 .380E-03 48111 .527E-03 48112 .277E-03 48113 .548E-05 49113 .123E-06 48114 .311E-03 48601 .575E-07 49115 .664E-04 50115 .493E-05 48116 .142E-03 50116 .346E-04 50117 .129E-03 50118 .105E-03 50119 .112E-03 50120 .109E-03 51121 .115E-03 50122 .142E-03 52122 .282E-05 50123 .212E-05 51123 .133E-03 52123 .136E-07 50124 .239E-03 51124 .114E-06 52124 .22KE-05 51125 .234E-03 52125 .534E-04 50126 .531E-03 52126 .774E-05 52601 .337E-04 53127 .122E-02 52128 .264E-02 54128 .217E-04 52611 .359E-05 53129 .544E-02 54129 .424t-07 52130 . 1lOE-01 54130 .907E-04 54131 .160E-01 54132 .298E-01 55133 .383E-01 54134 .462E-01 55134 .147E-02 56134 .435E-03 55135 .654E-02 56135 .366E-06 54136 .736E-01 55136 .863E-09 56136 .227E-03 55137 .380E-01 56137 . 815E-03 56138 .394E-01 57139 .377E-01 5614Q .620E-07 57140 .938E-08 58140 .380E-01 58141 .928E-04 59141 .346E-01 55142 .349E-01 60142 . 192E-03 59143 .118E-06 60143 .304E-01 58144 .142E-01 60144 .217E-01 60145 .224E-01 60146 .197E-01 60147 .366E-08 61147. .887E-02 62147 .224E-02 60148 .112E-01 61148 .166E-07 61601 .241E-05 62148 .153E-02 62149 .273E-03 60150 .524E-02 62150 .859E-02 62151 .695E-03 63151 .334E-05 62152 . 459E-02 63152 .763E-06 64152 .555E-06 63153 .266E-02 62154 .989E-03 63154 .310E-03 64154 .198E-04 63155 .114E-03 64155 .986E-05 63156 .184E-07 64156 .989E-03 64157 .507E-05 64158' .373E-03 65159 .531E-04 64160 .235E-04 65160 .222E-06 66160 .229E-05 66161 .917E-05 66162 .699E-05 66163 .319E-05

Waste Package Development Design Analysis Te: CRC DePICtion Caculations for the Rodded AuSemblies In BatChe 1O mnd 1 Of Cystal River Unit 3 Document identer BBAoOOOOOO171742004O044 REVOO Pane 62 of 82 66164 .753E-06 67165 .804E-06 69166 .11OE-06 1 1.0 974.3 end arbm-zirc4 6.56 5 0 0 0 8016 0.12 24000 0.10 26000 0.20 50000 1.40 40000 98.18 2 1.0 640.0 end material composition of moderator within unit cell with smeared inconel spacer grids h2o 3 den-.7433 .99424 585.2 - end arbm-bormod .7433 1 0'0 0 5000 100 3 .00052 595.2 end arbm-spacer .7433 5 0 0 0 14000 2.5 22000 2.5 24000 15.0 26000 7.0 28000 73.0 3 .00576 585.2 end he 5 end end comp base reactor lattice specification squarepitch 1.44272 .9398 1 3 1.0922 2 .9576 0 end more data szf-0.50 end t

assembly specification npin/assembly-208 fuelngth-20.003 ncycles-02 nlib/cyc-1 lightel-0 printlevel-05 inplevel-2 numztotal-05 mxrepeats-l mixmod-3 facmesh-.50 end 3 .63246 2 .67310 3 .81397 500 2.97599 3 2.99939 assembly depletion/decay parameters Cycle-lB, one-eighth core assembly number 03 power-.92563 burn-71.10 down-.OOOOOEtOO bfrac-1.000 end power-.92563 burn-71.10 down-14.792 bfrac-.4938 end end of input I

end SAS2H Depletion Input Deck Example 3: BOL Depletion Calculation for a B&W Fuel Assembly Top Axial Node Containing 208 Fuel Rods, 16 Guide Tubes with BPR's Inserted, and I Empty Instrument Tube

-sas2h parm-skipshipdata Crystal River, Unit 3 Msay-02, Node-Ol (Cyc-lA, .0 to Cyc-lB, .0 EFPD) 44group latticecell I

fuel density based on mass of uranium per assembly S total pellet stack volume to account for fuel volume loss to pellet chamfers material specification input uo2 1 den-10. 121 1 820.6 92234 .021 92235 2.540 92236 .012 92238 97.427 end kr-8 '3 1 0 1-21 820.6 end kr-8 '5 1 0 1-21 820.6 end sr-9 1 0 1-21 820.6 end y-89 1 0 1-21 820.6 end mo-9 1 0 1-21 820.6 end zr-9 3 1 0 1-21 820.6 end zr-9 '4 2 0 1-21 820.6 end

Waste Package Development Design Analysis TMtle: CRC Depletion Calculations for de Rodded Assemblies in Batches 10 and II of Cystal River Unit3 f Document ldentifier. BEBOOOOOO01717-0200w0044 REV oo Page 63 of 82 zr-95 1 0 1-21 E20.6 end nb-94 1 0 1-21 820.6 end tc-99 1 0 1-21 820.6 end rh-103 1 0 1-21 820.6 end rh-lOS 1 0 1-21 820.6 end ru-101 0 1-21 820.6 end ru-106 0 1-21 820.6 end pd- 105 0 1-21 620.6 end 1 0 1-21 820.f end pd-108 I ag-109 0 1-21 E20.6 end 1 0 1-21 920.6 end sb-124 1 xe-131 0 1-21 820.6 end 1 0 1-21 820.6 end xe-132 1 xe-135 0 1-21 920.6 end 1 0 1-21 820.6 end xe-136 1 cs-134 0 1-21 820.6 end 1 0 1-21 820.6 end cs-135 1 cs-137 1 0 1-21 820.6 end ba- 136 0 1-21 820.6 end 1 0 1-21 820.6 end la- 39 1 0 ce-144 1 1-21 820.6 end nd-143 1 -0 0 1-21 820.6 end nd-145 1 0 21 820.6 end pm- 147 1 1-21 620.6 end pm-148 .1 0 1-21 820.6 end nd- 147 0 1-21 820.6 end sm-147 1 0 1-21 820.6 end sm-149 1 0 1-21 820.6 end sm-150 1 0 1-21 820.6 end sm-151 1 0 1-21 820.6 end sm-152 1 0 1-21 820.6 end gd-155 1 0 1-21 820.6 end eu-153 1 0 1-21 820.6 end eu-154 1 0 1-21 820.6 end eu-155 2 0 1-21 820.6 end arbm-zirc4 6.56 SCI 0 0 8016 0.12 24000 0.10 26000 0.20 50000 1.40 40000 98.18 2 1.0 640.0 end material composition of moderator within unit cell with smeared;inconel spacer grids h2o 3 den-.7198 .99424 594.5 end arbm-bormod .7198 1 0 0 0 5000 100 3 .00092 594.5 end arbm-spacer .7198 5 0 0 0 14000 2.5 22000 2.5 24000 15.0 26000 7.0 28000 73.0 3 .00576 594.5 end BPR above the BP absorber region al 6 den-3.700 .52 594.5 end o 6 den-3.700 .470 594.5 end he 5 end end comp base reactor lattic e specification squarepitch 1.44272 .9398 1 3 1.0922 2 .9576 0 end .

more data szf-0.50 end

assembly specification

Waste Package Development Design Analysis

Title:

CRC Depletion CalculatiOns for the Rodded Assemblies in Batches 10 and 11 oftCAa River Unit 3 Document Identifler: BBAOOOOO-01717.0200-00044 REV 00 Page 64 of 82 npin/assembly-20B fuelngth-17.780 ncycles-04 nlib/cyc-l lightel-O printlevel-05 inplevel-2 numztotal-08 mxrepeats-1 mixmod-3 facmesh-.50 end 6 .43180 5 .45720 2 .54610 3 .63246 2 .67310 3 .81397 500 2.91402 3 2.93693 I

assembly depletion/decay parameters I Cycle-lA, one-eighth core assembly number 02 power-.35463 burn-67.20 down-.OOOOOE+00 bfrac-l.000 end power-.35463 burn-67.20 down-.OOOOOE+00 bfrac-.9470 end power-.35463 burn-67.20 down-.OOOOOE+00 bfrac-.8016 end power-.35463 burn-67.20 down-195.29 bfrac-.6603 end U

end of input I

end SAS21 Depletion Input Deck Example 4: Continuation Depletion Calculation for a B&W Fuel Assembly Top Axial Node Containing 208 Fuel Rods, 16 Guide Tubes with BPR'u Inserted, and 1 Empty Instrument Tube

-sas2h parm-skipshipdata Crystal River, Unit 3 Assy-04, Node-Ol {Cyc-04, 228.1 to Cyc-04, 253.0 EFPD) 44group latticecell fuel density based on mass of uranium per assembly & total pellet stack volume to account for fuel volume loss to pellet chamfers I mater ial specification input arbm-fuel ' 10.2 192 0 0 0 8016 11.9 2004 .114E-OE 90230 .327E-07 92233 .309E-01 92234 .177E-01 92235 1.84 92236 .977E-02 92237 .305E-04 92238 85.4 93237 .311E-02 93238 .302E-07 94238 .184E-03 94239 .216 94240 .243E-0l 94241 .636E-02 94242 *337E-033 95241 .915E-04 95601 .946E-06 95243 .1031t-04 96242 .563E-05 96243 .334E-07 96244 .387E-Of 1003 .678E-06 3006 .406E-08 32072 .410E-01 32073 .142E-06 32074 .119E-06 33075 *174 E-0! 32076 .555E-05 34076 .747E-08 34077 *126E-04 34078 .354E-04 34080 .208E-03 35081 .311E-03 34082 .521E-03 36082 .185E-05 36083 .827E-033 36084 .177E-02 36085 .398E-03 37085 .157E-022 36086 .319E-02 37086 .747E-07 38086 .72GE-Of 37087 .417E-02 38087 .674E-08 38088 .597E-02 38089 .140E-02 39089 .670E-02 38090 .961E-02 39090 .250E-05 40090 .242E-03 39091 .20SE-022 40091 .816E-02 40092 .106E-01 40093 .766E-022 40094 .119E-0l 41094 .363E-08 40095 .277E-02 2 41095 .162E-02 42095 .781E-02 40096 .121E-01 42096 .659E-04 42097 .112E-01 42098 .11SE-01 42099 .346E-05 43099 .125E-01 44099 *320E-OE 42100 .131E-01 44100 .239E-03 44101 l109E-0l 1 44102 .973E-02 44103 .11SE-02 45103 .628E-02 44104 .54OE-02 46104 .440E-03 45105 .277E-01 46105 .353E-02 44106 .149E-02

Waste Package Development Design Analysis Ttl~e: CRC Depleion Calculations fortheRodddAssemblies i Batches 10 and 11 of I RiverUnt 3 Document identifier: BBAOOOOOO.017I7-020043000 REV 00 - Page 65 of 82 46106 793E-03 46107 .121 'E-02 46108 .770E-03 47109 .563E-03 46110 .231 SE-03 48110 .339E-04 47111 .160E-0S 48111 .125 'E-03 48112 .770E-04 48113 .429E-05 49113 .12' 3E-07 48114 .102E-03 48601 .275E-06 49115 .29S 9E-04 50115 .180E-05 48116 .536E-04 50116 .597E-05 50117 .429E-04 50118 .383E-04 501V9 .414 IE-04 50120 .410E-04 51121 .440E-04 50122 .52! 5E-04 52122 .394E-06 50123 .189E-05 51123 .50: 2E-04 50124 .877E-04 51124 .137E-06 52124 .24! SE-06 50125 .467E-06 51125 .854E-04 52125 .165 ;E-04 50126 .170E-03 51126 .317E-07 52126 .18! 5E-05 52601 .303E-04 53127 .410E-03 52128 .10, 7E-02 54128 .331E-05 52611 .506E-04 53129 .221LE-02 54129 .296E-08 52130 .490E-02 54130 .15!iE-04 53131 .862E-04 54131 .766E-02 52132 .73!5E-05 54132 .128E-01 54133 .709E-04 55133 .181 IE-Ol 54134 .217E-Ol 55134 .338E-03 56134 .4833E-04 55135 .800E-02 56135 .682E-07 54136 .286 'E-01 55136 .350E-05 56136 .758E-04 55137 .17!'E-01 56137 .39SE-03 56138 .1B8E-01 57139 .18( )E-01 56140 .460E-03 57140 .693E-04 58140 .18; 'E-0O 58141 .178E-02 59141 .149E-01 58142 .16E IE-O1 60142 .391E-04 58143 .498E-e7 59143 .505 9E-03 60143 .156E-01 58144 .869E-02 60144 .77(OE-02 60145 .112E-O1 60146 .911E-02 60147 .131LE-03 61147 .486E-02 62147 .119E-02 60148 .521 LE-02 61148 .207E-05 61601 .211E-04 62148 .421 LE-03 61149 .359E-06 62149 .183E-03 60150 .22! 5E-02 62150 .343E-02 61151 .123E-08 62151 .601 LE-03 63151 .170E-05 62152 .179E-02 63152 .22! 9E-05 64152 .124E-05 62153 .475E-07 63153 .804 IE-03 62154 .338E-03 63154 .586E-04 64154 .204 6E-05 63155 .490E-04 64155 .900E-06 63156 .11! 9E-04 64156 .222E-03 64157 .216E-05 64158 .821 7E-04 65159 .124E-04 64160 .529E-05 65160 .124IE-06 66160 .14SE-06 66161 .214E-05 66162 .10A IE-05 66163 .460E-06 66164 .137E-06 67165 .83! ME-07 68166 .115E-07 1 1. 0 872.8 end arbm-zirc4 6.56 5 0 Q 0 8016 0.12 2400C 0.10 26000 0.20 50000 1.40 40000 98.18 2 1.0 640.0 end material composition of moderator within unit cell I with smeared inconel spacer grids h2o 3 den-.7198 .99424 594.5 end arbm-bormod .7198 1 0 0 0 5000 100 3 .00022 594.5 end arbm-spacer .7198 5 0 0 0 14000 2.5 22000 2.5 24000 15.0 26000 7.0 28000 73.0 3 .00576 594.5 end BPR above the EP absorber region I

al 6 den-3.700 .52924 594.5 end 0 6 den-3.700 .47076 594.5 end he 5 end end comp base reactor lattice specification

Waste Package Development Design Analysis

Title:

CRC Depiction Catculatimo for de Rodded AsseMblies in Batches 10 and I oftoystal River Unit 3 Document Identflbr. BBA000000-1717-0200-00044 REV 00 Page 66 of 82 squarepitch 1.44272 .9390 1 3 1.0922 2 .9576 0 end more data szf-0.50 end assembly specification npin/assembly-208 fuelngth-17.780 ncycles-01 nlib/cyc-1 lightel-0 printlevel-05 inplevel-2 numztotal-08 mxrepeats-1 mixmod-3 facmesh-.50 end 6 .43180 5 .45720 2 .54610 3 .63246 2 .67310 3 .81397 500 2.91402 3 2.93693 assembly depletion/decay parameters P Cycle-04, one-eighth core assembly number 04 power-.45617 burn-24.90 down-24.000 bfrac-1.000 end I end of input end SAS2H Depletion Input Deck Example 5: BOL Depletion Calculation for a B&W Fuel Assembly Axial Node (Other than Top Node) Containing 208 Fuel Rods, 16 Guide Tubes with BPR's Inserted, and I Empty Instrument Tube

-sas2h parm-skipshipdata Crystal River, Unit 3 Assy-02, Node-02 (Cyc-lA, .0 to Cyc-lB, .0 EFPD) 44group latticecell fuel density based on mass of uranium per assembly & total pellet stack volume to account for fuel volume loss to pellet chamfers I

material specification input uo2 1 den-10.121 1 936.2 92234 .021 92235 2.540 92236 .012 92238 97.427 end kr-83 1 0 1-21 936.2 end kr-85 1 0 1-21 936.2 end sr-90 1 0 1-21 936.2 end y-89 1 0. 1-21 936.2 end mo-95 1 0; 1-21 936.2 end zr-93 1 0 1-21 936.2 end zr-94 1 0 1-21 936.2 end zr-95 1 0 1-21 936.2 end nb-94 1 0 1-21 936.2 end tc-99 1 0 1-21 936.2 end rh-103 1 0 1-21 936.2 end rh-105 1 0 1-21 936.2 end ru-101 1 0 1-21 936.2 end ru-106 1 0 1-21 936.2 end pd-105 1 0 1-21 936.2 end pd-108 1 0 1-21 936.2 end ag-109 1 0 1-21 936.2 end sb-124 1 0 1-21 936.2 end xe-131 1 .0 1-21 936.2 end xe-132 1 0 1-21 936.2 end xe-135 1 0 1-21 936.2 end xe-136 1 0 1-21 936.2 end cs-134 1 0 1-21 936.2 end cs-135 1 0 1-21 936.2 end cs-137 1 1-21 936.2 end

Waste Package Development Design Analysis T1e: CRC Depletion cacaions fr the Rbdded Asemblies in Batches 10 and I Iof Cstial River Unk 3 Document Identifer BBAOOOO-01717.020000044 REV 0. Pao& 67 of 82 ba-136 I 0 1-21 936.2 end la-139 1 0 1-21 936.2 end ce-144 1 0 1-21 936.2 end nd-143 1 0 1-21 936.2 end nd-145 1 0 1-21 936.2 end pm-147 1 0 1-21 936.2 end pm-14i 1 0 1-21 936.2 end nd-147 1 0 1-21 936.2 end sm-147 1 0 1-21 936.2 end sm-149 1 0 1-21 936.2 end sm-150 1 0 1-21 936.2 end sm-151 1 0 1-21 936.2 end sm-152 1 0 1-21 936.2 end gd-l55 1 0 1-21 936.2 end eu-153 1 0 1-21 936.2 end eu-154 1 0 1-21 936.2 end eu-155 1 0 1-21 936.2 end arbm-zirc4 6.56 5 0 0 0 8016 0.12 24000 0.10 26000 0.20 50000 1.40 40000 98.18 2 1.0 640.0 end I . material composition of moderator within unit cell I with smeared inconel spacer grids h2o 3 den-.7226 .99424 593.4 end arbm-bormod ..7226 1 0 0 0 5000 100 3 .00092 593.4 end arbm-spacer .7226 5 0 0 0 14000 2.5 22000 2.5 24000 15.0 26000 7.0 28000 73.0 3 .00576 593.4 ,nd f burnable absorber pellet specification r

b4c 4 den-3.700 .01340 593.4 end al 4 den-3.700 .52215 593.4 end 0 4 den-3.700 .46445 593.4 end he 5 end end comp base reactor latitice specification squarepitch 1.44272 .9399 1 3 l;0922 2 .9576 0 end more data szf-0.50 end assembly specification npin/assembly-208 fuelngth-20.003 ncycles-04 nlib/cyc-1 lightel-0 printlevel-05 inplevel-2 numztotal-08 mxrepeats-i mixmod-3 facmesh-.50 end 4 .43180 5 .45720 2 .54610 3 .63246 2 .67310 3 .81397 500 2.91402 3 2.93693 S

assembly depletion/decay parameters S

I Cycle-iA, one-eighth core assembly number 02 power-.63623 burn-67.20 down-.OOOOOE+00 bfrac-1.000 end power-.63623 burn-67.20 down-.OOOOOE+00 bfrac-..9470 end power-.63623 burn-67.20 down-.OOOOOE+00 bfrac-.8016 end power-.63623 burn-67.20 down-195.29 bfrac-.6603 end end of input end

Waste Package Development Design Analysis Tiut: CRC Depleion Caculation for the Rodded AssMblis in Batche 10 and I Iof Cyal RIT nit 3 Document Identfler BBA0 o1717-0200-044 REV _O - Page 68 of 82 SAS211 Depletion Input Deck Example 6: Continuation Depletion Calculation for a B&W Fuel Assembly Axial Node (Other than Top Node) Containing 208 Fuel Rods, 16 Guide Tubes with BPR's Inserted, and 1 Empty Instrument Tube

-sas2h parm-skipshipdata Srystal River, Unit 3 Assy-04, Node-05 (Cyc-04, 228.1 to Cyc-04, 253.0 EFPD) 44group latticecell fuel density based on mass of uranium per assembly S total pellet stack volume to account for fuel volume loss to pellet chamfers material specification input arbm-fuel 10.3 199 0 0 0 8016 11.8 2004 .129E-05 90230 .284E-07 90232 .273E-08 91231 .302E-08 92233 .657E-07 92234 .154E-01 92235 1.30 92236 .192 92237 .128E-03 92238 85.0 93237 .116E-01 93238 .275E-06 94236 .657E-08 94237 .299E-08 94238 .159E-02 94239. .388 94240 .873E-Ol 94241 .408E-01 94242 .593E-02 95241 .637E-03 95601 .995E-05 95243 .512E-03 96242 .118E-03 96243 .189E-65 96244 .533E-04 96245 .860E-06 96246 .401E-07 1003 .174E-05 3006 .833E-08 32072 .123E-06 32073 .506E-06 32074. .311E-06 33075 .425E-05 32076 .132E-04 34076 .472E-07 34077 .302E-04 34078 .904E-04 34080 .502E-03 35081 .752E-03 34082 .123E-02 36082 .105E-04 36083 .182E-02 36084 .421E-02 36085 .914E-03 37085 .361E-02 36086 .728E-02 37086 .452E-06 38086 .482E-05 37087 .951E-02 38087 .229E-07 38088 .136E-01 38089 .290E-02 39089 .154E-01 38090 .218E-01 39090 .566E-05 40090 .614E-03 39091 .442E-02 40091 .191E-Ol 40092 .246E-al 40093 .180E-01 40094 .28SE-Ol 41094 .116E-07 40095 .630E-02 41095 .371E-02 42095 .19O0-Ol 40096 .295E-01 42096 .421E-03 42097 .275K-01 42098 .293E-01 42099 .829E-05 43099 .302E-01 44099 .112K-05 42100 .330K-Ol 44100 .151E-02 44101 .274E-01 44102 .256E-01 44103 .322E-02 45103 .160E-01 44104 .162E-Ol 46104 .279E-02 45105 .914E-07 46105 .11E-01 44106 .560E-02 46106 .337E-02 46107 .539E-02 46108 .341E-02 47109 .242E-02 46110 .100E-02 48110 .381E-03 47111 .671E-05 48111 .523E-03 48112 .285E-03 48113 .634E-05 49113 .405E-07 48114 .332E-03 48601 .860E-06 49115 .715E-04 50115 .536E-05 48116 .155E-03 50116 .367E-04 50117 .137E-03 50118 .114E-03 50119 .121E-03 50120 .119E-03 51121 .125E-03 50122 .154E-03 52122 .312E-05 50123 .496E-05 51123 .143E-03 52123 .131E-07 50124 .260E-03 51124 .974E-06 52124 .170E-05 50125 .138E-05 51125 .259E-03. 52125 .509E-04 50126 .560E-03 51126 .134E-06 52126 .786E-05 52601 .934E-04 53127 .125E-02 52128 .295E-02 54128 .275E-04 52611 .138E-03 53129 .597E-02 54129 .644E-07 52130 .126E-01 54130 .991E-04 53131 .217E-03 54131 .180E-OI 52132 .182E-04

Waste Package Development Design Analysis TlUe: CRC Depletion Calculations for the Rodded Assemblies in Batches 10 and II of Crystal River Unit 3 Document Identifer: BBAOOO O0.01717.2_0_00044 REV_0 Page 69 of 82 54132 .344E-01 54133 *171E-03 55133 .442E-0l 54134 .539E-01 55134 .205E-02 56134 .313E-03 55135 .113E-01 56135 *l10E-05 54136 *813E-01 55136 .130E-04 56136 *290E-03 55137 .43SE-01 56137 .106E-02 56138 .462E-01 57130 *438E-01 56140 .108E-02 57140 *163E-03 58140 .44GE-01 58141 .418E-02 59141 .364E-01 58142 .411iE-Cl 60142 .245E-03 58143 .113E-06 59143 *21SE-02 60143 .347E-01 58144 .200E-01 60144 .221E-01 60145 .264E-01 60146 *231E-01 60147 *31OL-03 61147 .1O1E-01 62147 *264E-02 60148 .130E-01 61148 .900E-05 61601 .699E-04 62148 *203E-02 61149 .108E-05 62149 .300E-03 60150 .593E-02 62150 .957E-02 61151 .337E-08 62151 .680E-03 63151 .107E-05 62152 *496E-02 63152 .273E-05 64152 .246E-05 62153 .225E-06 63153 *297E702 62154 .106E-02 63154 .384 E-03 64154 *137E-04 63155 .133E-03 64155 .156E-05 63156 *624E-04 64156 .988E-03 64157 *512E-05 64158 .364E-03 65159 .526E-04 64160 *233E-04 65160 *126E-05 66160 .141E-05 66161 .887E-05 66162 *5G0E-05 66163 .317E-05 66164 .755E-06 67165 .627E-06 68166 .860E-07 1 1.0 1010:. end arbm-zirc4 6.56 5 0 0 0 8016 0.12 24000 0.10 26000 0.20 50000 1.40 40000 98.18 I 1.0 640.0 end material composition of moderator within unit cell I with smeared inconel spacer grids h2o 3 den-.7343 .99424 588.9 end arbm-bormod .7343 1 0 0 0 5000 100 3 .00022 588.9 end arbm-spacer .7343 5 0 0 0 14000 2.5 22000 2.5 24000 15.0 26000 7.0 28000 73.0 3 .00576 588.9 end burnable absorber pellet specification arbm-bp 3.699 5 0 0 0 5010 .225E-02 5011 .140 6012 .435E-01 13027 52.827 8016 46.987 4 1.0 588.9 end I

he 5 end end comp base reactor lattice specification squarepitch 1.44272 .9390 1 3 1.0922 2 .9576 0 end more data szf-0.50 end assembly specification I

npin/assembly-208 fuelngth-20.003 ncycles-01 nlib/cyc-1 lightel-0 printlevel-05 inplevel-2 numztotal-08 mxrepeats-l mixmod-3 facmesh-.50 end 4 .43180 5 .45720 2 .54610 3 .63246 2 .67310 3 .81397 500 2.91402 3 2.93693 assembly depletion/decay parameters

Waste Package Development Design Analysis

-. TitUe: CRc Dpledon Caculations for the Rodded Aswsbles i Batches 0 and ItI of rysT River Un 3 DocumentIenUtet BBAOOOx00oI717-020040044REVO - - Page 70 of 82 Cycle-04, one-eighth core assembly number 04 power-1.0347 burn-24.90 down-24.000 bfrac-l.000 end end of input end SAS2H Depletion Input Deck Example 7: BOL Depletion Calculation for a B&W Fuel Assembly Axial Node Containing 208 Fuel Rods, 16 Guide Tubes with a 16 Rod CRA Inserted for a Portion of the Depletion, and 1 Empty (Water-filled) Instrument Tube

-sas2h parm-skipshipdata Crystal River, Unit 3 Assy-07, Node-07 fCyc-lA, .0 to Cyc-lB, .0 EFPD) 44group latticecell fuel density based on mass of uranium per assembly a total pellet stack volume to account for fuel volume loss to pellet chamfers I

I material specification input uo2 1 den-10.121 1061.9 92234 .024 92235 2.830 92236 .013 92239 97.133 end kr-83 1 1-21 1061.9 end kr-85 1 1-21 1061.9 end sr-90 1 1-21 1061.9 end y-89 1 1-21 1061.9 end mo-95 1 1-21 1061.9 end zr-93 1 1-21 1061.9 end zr-94 I 1-21 1061.9 end zr-95 1 1-21 1061.9 end nb-94 1 1-21 1061.9 end tc-99 1 1-21 1061.9 end rh-103 1 1-21 1061.9 end.

rh-105 1 1-21 1061.9 end ru-201 1 1-21 1061.9 end ru-106 1 1-21 1061.9 end pd-105 1 1-21 1061.9 end pd-l08 I 1-21 1061.9 end ag-109 1 1-21 1061.9 end sb-124 1 L-21 1061.9 end xe-131 1 1-21 1061.9 end xe-132 1 1-21 1061.9 end xe-135 1 1-21 1061.9 end xe-136 1 1-21 1061.9 end cs-134 1 1-21 1061.9 end cs-135 1 1-21 1061.9 end cs-137 1 1-21 1061.9 end ba-136 2 1-21 1061.9 end la-139 1 1-21 1061.9 end ce-144 2 1-21 1061.9 end nd-143 1 1-21 1061.9 end nd-145 1 1-21 1061.9 end pm-147 I 1-21 1061.9 end pm-148 1 1-21 1061.9 end nd-147 1. 1-21 1061.9 end sm-147 2 1-21 1061.9 end sm-149 1 1-21 1061.9 end sm-150 .1 1-21 1061.9 end

Waste Package Development Design Analysis Tle: CRC Depledon Calctkations for he Rodded Assemblies in Bathe0andof Cyt ltnit3 Document Identflflb BBA00000041717402000044 REv 00 Pace 71 of 82 sm-151 ' 0 1-21 1061.9 end sm-152 1 0 1-21 1061.9 end gd-255 1 0 1-21 1061.9 end eu-153 1 0 1-21 1061.9 end eu-154 1 0 1-21 1061.9 end eu-155 1 0 1-21 1061.9 end arbm-zirc4 6.56 5 0 0 0 8016 0;12 24000 0.10 26000 0.20 50000 1.40 40000 98.18 2 1.0 640.0 end material composition of moderator within unit cell with smeared inconel spacer grids h2o 3 den-.7433 .99424 585.2 end arbm-bormod .7433 1 0 0 0 5000 100 3 .00090 585.2 end arbm-spacer .7433 5 0 0 0 14000 2.5 22000 2.5 24000 15.0 26000 7.0 28000 73.0 3 .00576 585.2 end

• control rod material specification arbm-ss304 7.92 4 0 0 0 24304 19.0 25055 2.0 26304 69.5 28304 9.5 6 1.0 640.0 end arbm-cr 10.17 4 0 0 0 47000 79.80000 49000 -15.00000 48000 5.00000 13027 .20000 7 1.0 585.1721 end he 5 end end comp base reactor lattice specification squarepitch 1.44272 .9398 1 3 1.0922 2 .9576 0 end more data szf-0.50 end assembly specification npin/assembly-208 fuelngth-20.003 ncycles-11 nlib/cyc-1 lightel-0 printlevel-05 inplevel-2 numztotal-08 mxrepeats-0 mixmod-3 facmesh-.50 end 7 .49784 5 .50546 6 .55880 3 .63246 2 .67310 3 .81397 500 2.38205 3 2.40078 7 .49784 5 .50546 6 .55880 3 .63246 2 .67310 3 .81397 500 2.38205 3 2.40078 7 .49784 5 .50546 6 .55880 3 .63246 2 .67310 3 .81397 500 2.38205 3 2.40078 3 .49784 3 .50546 3 .55880 3 .63246 2 .67310 3 .81397 500 2.97599 3 2.99939 3 .49784 3 .50546 3 .55880 3 .63246 2 .67310 3 .81397 500 2.97599 3 2.99939 3 .49784 3 .50546 3 .55880 3 .63246 2 .67310 3 .81397 500 2.97599 .3 2.99939 3 .49784 3 .50546 3 .55880 3 .63246 2 .67310 3 .81397 500 2.97599 3 2.99939 3 .49784 3 .50546 3 .55880 3 .63246 2 .67310 3 .81397 500 2.97599 3 2.99939 3 .49784 3 .50546 3 .55880 3 .63246. 2 .67310 3 .81397 500 2.97599 3 2.99939 3 .49784 3 .50546 3 .55880 3 .63246 2 .67310 3 .81397 500 2.97599 3 2.99939

Waste Package Development Design Analysis Ttle: CRC Depletion Calcuations for d, Roddcd Assemblies in Batches 10 and II of Crystl RiverUnit 3 D.Ocument Identlfikr-_BBAOOO41717.0200-00044 REV 00 Page 72 of 82 3 .49784 3 .50546 3 .55880 3 .63246 2 .67310 3 .E1397 500 2.97599 3 2.99939 assembly depletion/decay parameters I Cycle-lA, one-eighth core assembly number 07 power-i.0933 burn-2.500 down-.OOOOOE+00 bfrac-i.000 end power-1.0933 burn-6.500 down-.OOOOOE+00 bfrac-1.003 end power-1.0933 burn-i.000 down-.OOOOOE+00 bfrac-1.005 end power-1.0933 burn-l.000 down-. OOOOOE+00 bfrac-1.006 end power-1.0933 burn-l.000 down-.OOOOOE+00 bfrac-1.007 end power-i.0933 burn-.9700 down-.OOOOOE+00 bfrac-1.007 end power-1.0933 burn-1.040 down-.OOOOOE+00 bfrac-1.008 end power-1.0933 burn-63.70 down-.OOOOE+00 bfrac-1.030 end power-i.0933 burn-63.70 down-.OOOOOE+00 bfrac-.9481 end power-1.0933 burn-63.70 down-.OOOOOE+00 bfrac-.8072 end power-1.0933 burn-63.70 down-195.29 bfrac-.6578 end I end of input I

end SAS211 Depletion Input Deck Example 8: Continuation Depletion Calculation for a B&W Fuel Assembly Axial Node Containing 208 Fuel Rods, 16 Guide Tubes with a 16 Rod CRA Inserted for a Portion of the Depletion, and 1 Empty (Water-filled) Instrument Tube

-sas2h parm-skipshipdata Crystal River, Unit 3 Assy-07, Node-07 (Cyc-lB, .0 to Cyc-lB, 142.2 EFPD) 44group latticecell fuel density based on mass of uranium per assembly & total pellet stack volume to account for fuel volume loss to pellet chamfers material specification input I

arbm-fuel 10.1 193 0 0 0 8016 11.8 2004 .900E-06 90230 .585E-07 90232 .500E.-'08 91231 .825E-08 92233 .859E-07 92234 .175E-01 92235 1.55 92236 .179 92238 84.9 93237 .931E-02 94236 .407E-08 94238 .103E-02 94239 .349 94240 .698E-01 94241 .290E-01 94242 .356E-02 95241 .104E-02 95601 .428E-05 95243 .243E-03 96242 .169E-04 96243 .315E-06 96244 .197E-04 96245 .267E-06 96246 .102E-07 1003 .151E-05 3006 .982E-08 32072 i231E-06 32073 .431E-06 32074 .363E-06 33075 .370E-05 32076 .116E-04 34076 .349E-07 34077 .266E-04 34078 .784E-04 34080 .438E-03 35081 .657E-03 34082 .109E-02 36082 .750E-05 36083 .164E-02 36064 .370E-02 36085 .8ISE-03 37085 .321E-02 36086 .647E-02 38086 .356E-05 37087 .846E-02 38087 .226E-07 38088 .122E-01 38089 .27SE-03 39089 .161E-Ol 38090 .195E-01 39090 .507E-05 40090 .l48E-03 39091 .592E-03 40091 .203E-01 40092 .218E-01 40093 .159E-01 40094 .250E-01 41094 .118E-07 40095 .989E-03 41095 .107E-02 42095 .236E-01. 40096 .257E-0O 42096 .169E-03 42097 .240E-Ol 42098 .254E-0O

Waste Package Development Design Analysis Titie: CRC Depletion Calculations for the Rodded Assemblies In Batches 10 and II of C.)ml River Unit 3 Document 1dent~fler. BBA0O000101717-0200 0 V4_EV I page 73 of 82 43099 .26SE-01 44099 .962E-06 42100 .285E-0O 44100 .104E-02 44101 .237E-Ol 44102 .218E-01 44103 .132E-03 45103 .166E-Ol 44104 .134E-Ol 46104 .171E-02 46105 .863E-02 44106 .356E-02 46106 .373E-02 46107 .411E-02 46108 .254E-02 47109 .185E-02 46110 .757E-03 48110 .236E^03 48111 .404E-03 48112 .222E-03 48113  ;616E-05 49113 .105E-06 48114 .267E-03 48601 .496E-07 49115 .873E-04 50115 .442E-05 48116 . 129E-03 50116 .209E-05 50117 .111E-03 50118 .941E-04 50119 .100E-03 50120 .989E-04 51121 .104E-03 50122 .128E-03 52122 .227E-05 50123 .203E-05 51123 .122E-03 52123 .993E-OB 50124 .214E-03 51124 .917E-07 52124 .182E-OS 51125 .208E-03 52125 .476E-04 50126 .448E-03 52126 .599E-OS 52601 .294E-04 53127 .107E-02 52128 .249E-02 54128 .169E-04 52611 .335E-05 53129 .517E-02 54129 .274E-07 52130 .108E-Ol 54130 .678E-04 54131 .161E-01 54132 .291E-01 55133 .390E-Ol 54134 .469E-01 55134 .126E-02 56134 .373E-03 55135 .873E-02 56135 .269E-06 54136 .712E-Ol 55136 .794E-09 56136 .204E-03 55137 .380E-01 56137 .815E-03 56138 .401E-01 57139 .383E-01 56140 ..

633E-07 57140 .959E-08 58140 .367E-Ol 58141 .948E-04 59141 .353E-Ol 58142 .359E-Ol 60142 .153E-03 59143 .123E-06 60143. .326E-Ol 58144 .148E-01 60144 .214E-01 60145 .233E-Ol 60146 .199E-01 60147 .373E-08 61147 .938E-02 62147 .237E-02 60148 .113E-Ol 61148 .181E-07 61601 .264E-05 62148 .142E-02 62149 .307E-03 60150 .507E-02 62150 .832E-02 62151 .839E-03 63151 .421E-05 62152 .428E-02 63152 .989E-06 64152 .644E-06 63153 .232E-02 62154 .863E-03 63154 .255E-03 64154 .163E-04 63155 .979E-04 64155 .863E-05 63156 .136E-07 64156 .763E-03 64157 .448E-OS 64158 .280E-03 65159 .397E-04 64160 .174E-04 65160 .149E-06 66160 .155E-05 66161 .695E-05 66162 .421E-05 66163 .217E-OS 66164 .568E-06 67165 .490E-06 68166 .674E-07 1 1.0 8117.9 end arbm-zirc4 6.56 5 0 0 0 8016 0.12 24000 0.10 26000 0.20 50000 1.40 40000 98.18 2 1.0 640.0 end material composition of moderator within unit cell I with smeared inconel spacer grids h2o 3 den-.7588 .99424 578.4 end arbm-bormod .7589 1 0 0 0 5000 100 3 .00054 578.4 end arbm-spacer .7588 5 0 0 0 14000 2.5 22000 2.5 24000 15.0 26000 7.0 28000 73.0 3 .00576 578.4 end control rod material specification arbm-ss304 7.92 4 0 0 0 24304 19.0 25055 2.0 26304 69.5 28304 9.5 6 1.0 640.0 end arbm-cr 10.17 4 0 0 0 47000 - 79.80000 49000 15.00000 48000 5.00000 13027 .20000

Waste Package Development Design Analysis TIUe: CRC Depletion Calculadons for the RoddedAsemblies inBahes t and I Iof cysa Rier Unit 3 Document Identffer. BBA0OO00-0l717-0200PO0O44 REVo00 Page 74 Of 82 7 1.0 579.3998 end he S end end comp I

squarepitch 1.44272 .9398 1 3 1.0922 2 .9576. 0 end more data szf-0.50 end assembly specification npin/assembly-208 fueingth-20.003 noycles-10 nlib/cyc-l lightel-O printlevel-05 inplevel-2 numztotal-08 mxrepeats-0 mixnod-3 facmesh-.50 end 7 .49784 5 .50546 6 .55880 3 .63246 2 .67310 3 .81397 500 2.38205 3 2.40078 7 .49784 5 .50546 6 .55E80 3 .63246 2 .67310 3 .81397 500 2.38205 3 2.40078 7 .49784 5 .50546 6 .55880 3 .63246 2 .67310 3 .81397 500 2.38205 3 2.40078 7 .49784 5 .50546 6 .55880 3 .63246 2 .67310 3 .81397 500 2.38205 3 2.40078 7 .49784 5 .50546 6 .55880 3 .63246 2 .67310 3 .81397 500 2.36205. 3 2.40078 7 .49784 5 .50546 6 .55880 3 .63246 2 .67310 3 .81397 500 2.38205 3 2.40078 3 .49784 3 .50546 3 .55880 3 .63246 2 .67310 3 .81397 500 2.97599 3 2.99939 3 .49784 3 .50546 3 .55880 3 .63246 2 .67310 3 .81397 500 2.97599 3 2.99939 3 .49784 3 .50546 3 .55880 3 .63246 2 .67310 3 .81397 500 2.97599 3 2.99939 3 .49754 3 .50546 3 .55880 3 .63246 2 .67310 3 .81397 500 2.97599 3 2.99939 assembly depletion/decay parameters 9 Cycle-iB, one-eighth core assembly number 07 power-.59608 burn-4.460 down-.OOOOOE+00 bfrac-1.000 end power-.59608 burn-24.44 down-.OOOOOE+00 bfrac-1.050 end power-.59608 burn-42.89 down-.OOOOOE+00 bfrac-.8052 end power-.59608 burn-42.89 down-.OOOOOE+00 bfrac-.5791 end power-.59608 burn-9.320 down-.OOOOOE+00 bfrac-.5087 end power-.59608 burn-i.000O dow'n-.OOOOOE+00 bfrac-.5220 end power-.59608 burn-1.310 down-.OOOOOE+00 bfrac-.5240 end power-.59608 burn-7.900 down-.OOOOOE+00 bfrac-.5316 end power-.59608 burn-7.790 down-.OOOOOE+00 bfrac-.5262 end power-.59608 burn-.2000 down-14.792 bfrac-.5187 end end of input end

Waste Package Development Design Analysis

Title:

CRC Depletion Calculations for the Rodded Assemblies inBatches 10 and 11 of Crytal River Unit 3 Document Idenifitjer. BBA0oow0 717-020000M4 REV 00 Pane 75 o 82 SAS21H Depletion Input Deck Example 9: BOL Depletion Calculation for a B&W Fuel Assembly Axial Node Containing 208 Fuel Rods, 16 Guide Tubes with a 16 Rod APSRA Inserted for a Portion of the Depletion with a Subsequent APSRA Follow Rod Region Insertion with a Subsequent APSRA Removal, and I Empty (Water-filled) Instrument Tube

-sas2h parm-skipshipdata Crystal River,.Unit 3 Assy-18, Node-12 (Cyc-lA, .0 to Cyc-lB, .0 EFPD) 44group latticecell I fuel density based on mass of uranium per assembly I total pellet stack I volume to account for fuel volume loss to pellet chamfers material specification input uo2 1 den--10.121 I I1139.7 92234 .016 92235 1.930 92236 .009 92238 98.045 end kr-83 1 0 1-21 1139.7 end kr-85 1 0 1-21 1139.7 end sr'-90 1 0 1-21 1139.7 end y-89 1 0 1-21 1139.7 end mo-95 1 0 1-21 1139.7 end zr-93 1 0 1-21 1139.7 end zr-94 1 0 1-21 1139.7 end zr-95 1 0 1-21 1139.7 end nb-94 0 1-21 1139.7 end tc-99 0 1-21 1139.7 end rh-103 0 1-21 1139.7 end rh-105 0 1-21 1139.7 end ru-101 0 1-21 1139.7 end ru-106 1 0 1-21 1139.7 end pd-105 0 1-21 1139.7 end pd-108 1 0 1 1-21 1139.7 end 1 0 1139.7 end ag-109 1-21 1 0 1-21 1139.7 end sb-124 1 xe-131 0 1-21 1139.7 end 1 0 1-21 1139.7 end xe-132 1 xe-135 1 0 1-21 1139.7 end xe-136 1-21 1139.7 end cs -134 .1 1 0 o;- 1-21 1139.7 end 1 0 cs-135 11 1-21 1139.7 end cs-137 0 1-21 1139.7 end ba-136 1 0 1-21 1139.7 end la-139 1

1 0 1-21 1139.7 end 11 ce-144 1 0 1-21 1139.7 end nd-143 1 0 1-21 1139;7 end nd-145 .1 0 1-21 1139.7 end pm-147 I 0 1-21 1139.7 end pm-248 1 0 1-21' 1139.7 end nd-147 0i 1-21 1139.7 end sm-147 1 0 1-21 1139.7 end sm-149 1 0 1-21 1139.7 end sm-150 1 0 1-21 1139.7 end sm-151 1 0 1-21 1139.7 end sm-152 1 0 1-21 1139.7 end gd-155 1 0 1-21 1139.7 end eu-153 6.6 0 1-21 1139.7 end eu-154 0 1-21 1139.7 end eu-155 0 1-21 1139.7 end arbm-zirc4 0 0 8016 0.12 24000 0.10 26000 0.20 50000 1.40

Waste Package DevelOPment Design Analysis THle: CRC Depledon Calculations for thc Rodded Assemblies i Batches 10 and 11 of Crystal River Unit 3 IDocument Identefl~r BBA000000-0171742004004 REV 00 Page 76 of 82 40000 98.18 2 1.0 640.0 end material composition of moderator within unit cell 0 with smeared inconel spacer grids h2o 3 den-.7717 .99424 572.3 end arbm-bormod .7717 1 0 0 0 5000 100 3 .00090 572.3 end arbm-spacer .7717 5 0 0 0 14000 2.5 22000 2.5 24000 15.0 26000 7.0 28000 73.0 3 .00576 572.3 end APSR follow rod material specification arbm-ss304 7.92 4 0 0 0 24304 19.0 25055 2.0 26304 69.5 28304 9.5 6 1.0 640.0 end axial power shaping rod material specification arbm-ss304 7.92 4 0 0 0 24304 19.0 25055 2.0 26304 69.5 28304 9.5 6 1.0 640.0 end arbm-apsr 10.17 4 0 0 0 47000 79.80000 49000 15.00000 48000 5.00000 13027 - .20000 7 1.0 572.3109 end he 5 end end comp base reactor lattice specification squarepitch 1.44272 .9398 1 3 1.0922 2 .9576 0 end more data szf-0.50 end assembly specification npin/assembly-208 fuelngth-20.003 ncycles-12 nlib/cyc-1 lightel-0 printlevel-OS inplevel-2 numztotal-08 mxrepeats-0 mixmod-3 facmesh-.50 end 7 .49784 5 .50546 6 .55980 3 .63246 2 .67310

.81397 500 2.38205 3 2.40078

.49784 5 .50546 6 .55880 3 .63246 .67310

.81397 500 2.38205 3 2.40078

.49784 5 .50546 6 .55890 3 .63246 .67310

.81397 500 2.38205 .32.40078

.49784 S5 .50546 6 .55880 3 .63246 .67310

.81397 500 2.38205 3 2.40078

.49784 5 .50546 6 .55880 3 .63246 .67310

.81397 500 2.38205 3 2.40078

.49784 5 .50546 6 .55880 3 .63246 .67310

.61397 500 2.38205 3 2.40078

.49784 5 .50546 6 .55880 3 .63246 .67310

.01397 500 2.38205 3 2.40078

.49784 5 .50546 6 .55880 3 .63246 .67310

.81397 500 2.38205 3 2.40078

.49784 3 .50546 6 .55880 3 .63246 . 67310

.81397 500 2.38205 3 2.40078

.49784 3 .50546 6 .55880. 3 .63246 .67310

.81397 500 2.38205 3 2.40078

.49784 3 .50546 6 .55880 3 .63246 .67310

.81397 500 2.36205 3 2.40078

Waste Package Development Design Analysis

Title:

CRC Deplti Cculation for the Radded Assemblies In Batches 10 and IIof Crtw River Unit 3

- Document ldentler. BBADOOON 717.0200-000441RE 0 Page 77 of82 3 .497E4

• 3 .50546 3 .55880 3 .63246 2 .67310 3 .81397 !500 2.97599 3 2.99939 assemb ly depletion/decay parameters Cycle-lA, one-eighth core assembly number 19 poweer-.63853 burn-.7800 down-.OOOOOE+00 bfrac-l.000 end poweer-.63853 burn-1.420 down-.OOOOOE+00 bfrac-l.001 end poweer-.63853 burn-1.800 down-.0000E+00 bfrac-1.002 end poweer-.63853 burn-27.29 down-.OOOOOE+00 bfrac-1.011 end powecr-.63853 burn-45.42 down-.OOOOOE+00 bfrac-1.036 end powe.r-.63853 burn-45.42 down-.OOOOOE+00 bfrac-.9710 end powe-r-.63853 burn-58.01 down-.OOOOOE+00 bfrac-.8566 end powesr-.63853 burn-58.01 down-.00000E+00 bfrac-.7138 end poweer-.63853 burn-ll.91 down-.00000E+00 bfrac-.6388 end powe.r-.63053 burn-7.500 down-. OOOOOE+00 bfrac-.6591 end powe.r-.63853 burn-3.800 down-.OOOOOE+00 bfrac-.6174 end poweer-.63853 burn-7.440 down-195.29 bfrac-.5757 end I

end of input end SAS2Z1 Depletion Input Deck Example 10: Continuation Depletion Calculation for a B&W Fuel Assembly Axial Node Containing 208 Fuel Rods, 16 Guide Tubis with a 16 Rod APSRA Inserted for a Portion of the Depletion with a Subsequent APSRA Follow Rod Region Insertion with a Subsequent APSRA Removal, and I Empty (Water-filled) Instrument Tube

-sas2h parm-skipshipdata Crystal River, Unit 3 Assy-16, Node-ll (Cyc-lB, .0 to Cyc-lB, 142.2 EFPD) 44group latticecell fuel density based on mass of uranium per assembly &. total pellet stack volume to account for fuel volume loss to pellet chamfers material specification input arbm-fuel 10.1 .183 0 0 0 8016 11.9 2004 .902E-06 90230 .394E-07 90232 .360E-08 91231 .504E-08 92233 .518E-07 92234 .117E-01 92235 1.00 92236 .129 92238 85.7 93237 .710E-02 94236 .285E-08 94238 .819E-03 94239 .326 94240 .737E-O1 94241 .280E-Ol 94242 .391E-02 95241 .lOlE-02 95601 .404E-05 95243 .249E-03 96242 .175E-04 96243 .312E-06 96244 . 191E-04 96245 .233E-06 96246 .1OlE-07 1003 .125E-05 3006 .77BE-08 32072 118E-06 32073 .367E-06 32074 .304E-06 33075 .302E-05 32076 .922E-05 34076 .257E-07 34077 .214E-04 34078 .644E-04 34080 .353E-03 35081 .531E-03 34082 .864E-03 36082 .614E-05 36083 .129E-02 36084 .292E-02 36085 .641E-03 37085 .251E-02 36086 .507E-02 38086 .254E-05 37087 .662E-02 38087 .191E-07 38088 .950E-02 38089 .215E-03 39089 .125E-Ol 38090 .152E-Ol 39090 .394E-05 40090 .350E-03 39091 .463E-03 40091 .159E-Ol 40092 .172E-Ol 40093 .126E-01 40094 .200E-01 41094 .109E-07 40095- .795E-03

Waste Package Development Design Analysis

Title:

CRC Depleti Calculations fos &c uodded Assemblies in Batches 10 and 11 ofCrysal River Unit 3 Document Identiflber BBAOOOO0O.01717.0200-00044 REV 00 Page 78 of 82 41095 .864E-03 42095 .190E-01 40096 .208E-Ol 42096 .144E-03 42097 .195E-01 42098 .208E-01 43099 .218E-Ol 44099 .792E-06 42100 .234E-01 44100 .809E-03 44101 .196E-01 44102 .182E-01 44103 .115E-03 45103 .145E-01 44104 .119E-01 46104 .144E-02 46105 .799E-02 44106 .346E-02 46106 .367E-02 46107 .415E-02 46108 .260E-02 47109 .l91E-02 46110 .764j.-03 48110 .236E-03 48111 .401E-03 48112 .215E-03 48113 .500E-05 49113 .960E-07 48114 .245E-03 48601 .446E-07 49115 .785E-04 50115 .394E-05 48116 .114E-03 50116 .173E-05 50117 .102E-03 50118 .840E-04 50119 .895E-04 50120 .878E-Q4 51121 .926E-04 50122 .114E-03 52122 .179E-05 50123 .172E-05 51123 .107E-03 52123 .713E-08 50124 .191E-03 51124 .723E-07 52124 .145E-05 51125 .17E8-03 52125 .428E-04 50126 .418E-03 52126 .583E-05 52601 .267E-04 53127 .970E-03 52128 .214E-02 54128 .136E-04 52611 .289E-05 53129 .442E-02 54129 .217E-07 52130 .898E-02 54130 .610E-04 54131 .135E-01 54132 .241E-01 55133 .320E-0O 54134 .384E-01 55134 .980E-03 56134 .290E-03 55135 .638E-02 56135 .199E-06 54136 .596E-01 55136 .658E-09 56136 .177E-03 55137 .313E-01 56137 .668E-03 56138 .326E-01 57139 .311E-01 56140 .514E-07 57140 .778E-08 58140. .314E-01 58141 .771E-04 59141 .287E-01 58142 .290E-01 60142 .127E-03 59143 .101E-06 60143 .257E-01 58144 .119E-01 60144 .174E-01 60145 .18BE-01 60146 .161E-01 60147 .305E-08 61147 .771E-02 62147 .195E-02 60148 .926E-02 61148 .138E-07 61601 .201E-05 i2148 .112E-02 62149 .232E-03 60150 .425E-02 62150 .686E-02 62151 .631E-03 63151 .312E-05 62152 .377E-02 6315,2 .751E-06 64152 .490E-06 63153 .200E-02 62154 .778E-03 63154 .207E-03 64154 .133E-04 63155 .908E-04 64155 .792E-05 163156 .125E-07 64156 .713E-03 64157 .391E-05 64158 .274E-03 65159 .401E-04 64160 .178E-04 65160 .135S-06 66160 .142E-05 66161 .706E-05 i 66162 .449E-05 66163 .225E-os 66164 .542E-06 67165 .542E-06 68166 .703E-07 1 1.0 863.7 end arbm-zirc4 6.56 5 0 0 0 8016 0.12 24000 0.10 26000 0.20 50000 1.40 40000 98.118 2 1.0 640.CI end material composition of moderator within unit cell with smeared inconel spacer grids h2o 3 den-.7684 .99424 573.9 end arbm-bormod .7684 1 0 0 0 5000 100 3 .00054 573.9 end arbm-spacer .7684 5 0 0 0 14000 2.5 22000 2.5 24000 15.0 26000 7.0 28000 73.0 3 .00576 573.9 end I

I APSR follow rod material specification I

arbm-ss3D4 7.92 4 0 0 0 24304 19.0 25055 2.0 26304 69.5 28304 9.5 6 1.0 640.0 end I

I axial power shaping rod material specification 9

Waste Package Development Design Analysis TlUe: CRC Depletion Calculations for the Rodded Assemblies In Batches 10 and I I of Crystal River Unit 3

, Document Identifler. BBAOOOO00.01717.02000004.4 REV 00 Page 7oft82 arbm-ss304 7.92 4 0 0 0 24304 19.0 25055 2.0 26304 69.5 28304 9.5 6 1.0 640.0 end arbm-apsr 10.17 4 0 47000 79.60000 49000 15.00000 48000 5.00000 13027 .20000 7 1.0 573.8673 he 5 end end comp base reactor lattice specification squarepitch 1.44272 .9398 1 3 1.0922 2 .9576 0 end more data szf-0.50 end assembly specification npin/assembly-208 fuelngth-20.003 ncycles-06 nliblcyc-I lightel-0 printlevel-05 inplevel-2 numztotal-08 mxrepeats-0 mixmod-3 facmesh-.50 end 7 .49784 5 .50546 6 .55880 3 .63246 2 .67310 3 .81397 500 2.38205 3 2.40078 7 .49784 .5 .50546 6 .55980 3 .63246 2 .67310 3 .81397 500 2.38205 3 2.40078 7 .49784 5 .50546 6 .55880 3 .63246 2 .f7310 3 .81397 500 2.38205 3 2.40078 3 .49784 3 .50546 6 .55880 3 .63246 2 .67310 3 .81397 500 2.38205 3 2.40078 3 .49784 3 .50546 6 .55880 3 .63246 2 .67310 3 .81397 500 2.38205 3 2.40078 3 .49784 3 .50546 3 .55880 3 .63246 2 .67310 3 .81397 500 2.97599 3 2.99939 I assembly depletion/decay parameters I

I Cycle-lB, one-eighth core assembly number 18 power-.64570 burn-6.340 down-.OOOOOE+00 bfrac-1.000 end power-.64570 burn-10.50 down-.OOOOOE+00 bfrac-1.029 end power-.64570 burn-54.86 down-.OOOO'OE+00 bfrac-.8150 end power-.64570 burn-37.64 down-.OOOOOE+00 bfrac-.5974 end -

power-.'64570 burn-30.66 down-.OOOOOE+00 bfrac-.5207 end power-.64570 burn-2.200 down-14.792 bfrac-.5189 end end of input end Attachment IX (moved to reference S.15) contains the CRAFT generated consolidated SAS2H output files for the depletion calculations documented in this analysis as identified in the attachment listing of Section 9. The consolidated output files contain the following information:

• . time/date stamp for when the SAS2M depletion calculation was performed, DI echo of the SAS2H input deck generated by CRAFT,

WastePackage Development Design Analysis

Title:

CRC Depletion Calculations for the Rodded Assemblies InBatches 10 and II of Crysal River Unit 3 Document Identifier. BBA000000-01717-02o-00o44 REV 00 Page 80 of 82 the output extraction of information pertinent to CRC evaluations from the final ORJGEN-S calculation of the SAS2H depletion calculation.

7.7 Isotopic Results Isotopic results for the set of 29 principal isotopes identified in Tablc 7.7-lI.ar tabulated for each axial node of each fuel assembly at each CRC statepoint other than beginning of life (BOC of first reactor cycle of in which the assembly is inserted) statepoints. The program entitled "CRCDATATABUJLIZER.exe" as described in Section 6.1, and Attachment V of reference 5.12, was used to create the principal isotope result tables included in this analysis. Attachments V through VIII (moved to reference 5.14) contain the principal isotope tabulations for the assemblies documented in this analysis. The consolidated output files for the SAS2H depletion calculations contain Isotopic concentrations for all isotopes included in the ORIGEN-S cross-section library. The ORIGEN-S cross-section library contains a considerably larger number of isotopes than the 29 isotopes included in the principal isotope set. Isotopic concentrations may be extracted from the consolidated SAS2H output files for subsequent evaluation and/or use in CRC reactivity analyses.

Table 7.7-1 Principal Isotopes Mo-95 Tc-99 Ru-101 Rh-103 Ag-109 Nd-143 Nd-145 Sm-147 Sm-149 Sm-450 SM-151 SM-152 Eu-151 Eu-153 Gd-155 U-233 U-234 U-235 U-236 U-238 Np-237 Pu-238 Pu-239 Pu-240 Pu-241 Pu-242 Am-241 Am-242m Am-243 Between CRC statepoints in the depletion sequence for a fuel assembly axial region, a new SAS2H input deck must be created using the fuel isotopic results from the previous calculation as the initial charge.

Since the 44-group cross-section library utilized in the SAS2H depletion calculations of this analysis has a reduced isotopic inventory relative to the ORIGEN-S cross-section library, a number of isotopes present in the ORIGEN-S output cannot be transferred to the initial fuel charge of the subsequent SAS2H depletion calculation. The isotopic inventory in the ORIGEN-S output which cannot be propagated to the following SAS2H depletion calculation does not significantly affect integral reactivity or the energy dependent neutron spectrum as documented in Section 4.9.1 of Attachment I of reference 5.11. The non-propagated isotopic inventory is written to a file entitled "{depletion case identifier).notes" to allow for subsequent analysis of the impact of excluding these isotopics in the initial charge to the subsequent SAS2H depletion calculation. The "*.notes" files are contained in Attachment X (moved to reference 5.15) as documented in Section 9.

Waste Package Development Design Analysis

Title:

CRC Depletion Calulations for the Rodded Assemblies in Batches 10 and II of Caystal Rivr Unit 3 Document Identifier: BBAOOoooo.01717.020040044 REV 0o Page 81 of 82

8. Conclusions The SAS2H depletion calculations of the rodded fuel assemblies frxom batch 1O of the Crystal River Unit 3 PWR that are required for CRC evaluations to support development of the disposal criticality methodology are fully documented in this analysis. The isotopic compositions of depleted fuel and depleted burnable poison for the various assemblies documented in this analysis are available in the consolidated SAS2H output files of Attachment DC (moved to reference 5.15) for subsequent evaluation and/or use in CRC reactivity evaluations. The inputs for the depletion calculations are obtained from a qualified source (Ref. 5.3). The SAS2H modeling techniques employed in the depletion calculations within this analysis are dictated by the CRAFT Version 3.0 code which is fully documented in Attachment I of reference 5.1 1.

9. Attachments The attachments referenced throughout this design analysis are listed in Table 9-1. Attachment IX (moved to reference S.15) contains the consolidated SAS2H output files for the assembly depletion calculations documented in this analysis. Attachment X (moved to reference 5.15) contains the

.notes" files which arc generated during the CRAFT calculations for each assembly documented in this analysis. Attachments IX and X (moved to reference 5.15) are written in an ASCII format to an attachment tape. Detailed listings of the content of Attachments IX and X (moved to reference S.15) on the attachment tape are provided in a hard-copy format in their corresponding attachment locations. The listing of the tape content for Attachments IX and X contain the following information for each of the files that are written to the tape:

the directory and filename as taken from the HP workstation, the corresponding filename on the tape attachment, the number of text pages in the file on tape after the addition of page headers, the date that the file was created on the HP workstation,

• the size of the file on the HP workstation in bytes,

• the file type (ASCII or BINARY).

The tape for Attachments IX and X (moved to reference 5.15) contain text files only. This tape is written using the HP Colorado Trakker Model Ti000c External Parallel Port Backup System for personal computers.

Table 9-1 Attachment Listing Number of Generation Attachment N PagesDate Description I 18 08/06/97 CRAFT Input Deck for Fuel Assembly 1104 II 19 08106/97 CRAFT Input Deck for Fuel Assembly HI2 18 Im 08106/97 CRAFT Input Deck for Fuel Assembly 13

Waste Package Development Design Analysis

Title:

CRC Depletion Calculations for the Rodded Assemblies hi Batches 10 and 11 of Crystal Rivcr Unit 3 Document Identfier. BBAOOOOOO-017170200-00044 REV 00 Page 82 of 82

. Number of Generation Attachment Pages Date Description IV 18 08/06/97 CRAFT Input Deck for Fuel Assembly H27a V V 120 120 08/06/97 08/06/97 Principal

~~~~This Isotopewas attachment Results movedfortoAssembly reference H04 5.14.

VI 120 08/06/97 Principal Isotope Results for Assembly H12 This attachment was moved to reference 5.14.

VII 120 08/06/97 Principal Isotope Results for Assembly H23

____120_O_06_97 This attachment was moved to reference 5.14.

VII 120 08/06197 Principal Isotope Results for Assembly H27a This attachment was moved to reference 5.14.

Total Page Count for Tape Containing CRAFT Generated IX Hard-Copy 08/06197 Consolidated SAS2H Output Decks for Listing of Tape Assemblies H04, H12, H23. H27a Content - 10 and Total Page Count for CRAFr Generated "*.notes" files for X Hard-Copy 08/06/97 Assemblies H04, H12, H23, H27a Listing of Tape This attachment was moved to reference 5.15.

Content -9 9

Aug 06 11:27 1097 File Name: N041.dat E31O0Ooo.01717-0200 00044 IEV CO ATTACHNEWT I - Pae I

• sThis is not a plck-q pcu Crystal River, Unit I Reactor Identifier CR3 a Prefix Identifier for reactor 4"gro4w t11cale croseectian library 3.94 U-235 wtZ enrichent in U of Uc2 463630 :a rew, of U per ssasbly 208 a Kurber of fuel rods In assembly 1.44272 Pin-pitch in u sdbty (cm) 0.036U U

• Fuel pellet diameter Cen) 0.95758 t Fuel rod cladding ID (cm) 1.0922 M Fuel red cladding CD (cm) 360.172 sFuel stock height (Cm)

Y t No axial blanket fuel ZIRC-4 atpcer grid moterlal 0.008165257 a Vol. frec. of mod. displaced by grids ZIRC-4 I Fuel rod cladding material 640.0  : Avg. fuel rod cladding temp. (K)

H Ko cladding materials other than ZIRC-4 2200.0 System pressure (psi)

A Activate 3PMA tracking 1 i lufber of reactor cycles vith 1PRA 10 3

• of 1PM designs, # of non-Al2t394C BPs 3.7 2.0 0.5857 16 2 4 i Input Card IBC

• s1 of radial zones In USA Path I modal 4 0.43180 SPL4 Path I model (Input Card ISE) 5 0.45720 2 0.54610 3 0.63246 2 0.67310 3 0.81397 500 2.91402 3 2.93693 3 0.43180 Path nodel Klth BP roved (Irput Card 18F) 3 0.4720 3 0.54610 3 0.63246 2 0.67310 3 0.81397 500 2.91402 3 2.93693 6 0.43180 a BPRA Path £ model above absorber (Input Card 10) 5 0.45720 Z 0.54610 3 0.63246 2 0.67310 3 0.81397 500 2.91402 3 2.93693 AL203 6  : Rat. above absorber In UP&, tASN met. six. U 11 2 17 s1PI Insertion history (Input Card 1811) 5 :L6of radial zones In the standard Path I model 30.63244 s itandard Path C model (Irpat Card 20) 2 0.67310 3 0.81397 500 2.97599 3 2.99939 I s f of cross-section libraries per. rradsation step 5 isUS2H output print level 0.5 a Zone moh factor for XSMDRNP 10 SPECIAL I Ho special JtSORP control parameter specs.

2 s U of Insertion reactor cycles 8 a Insertion reactor cycle Identifier 6 s fof stpts in eycle 0 sStpt EFPD 0 s Length to stpt in calendar days O s Oowntime at stpt 97.6 s 4tpt EFPD 110.0 a Length to stpt in calendar days 15.5. s Dwntlie at stpt 139.8 s Stpt EFPD

Aug 06 11:2 1997 File Nam: N04f.dat *BRAMOo O.1717-0200-0004 RUV 00 ATTACNKEXT I -page !

173.5  : Length to StPt I n Calendar days 6.2 :so intie at stpt 404.0

• Ltpt EFPD 479.7  : Length to Stpt In Calendar days A4.'  : Downtine at stpt 409.6  : Stpt EfPD 29.1 I Length to *tpt In calendar days 4.9 I owntime at *tpt 515.5 u Stpt EFPO 6450  : Length to stpt in calendar days 7.6 s Downtim at *tpt 75.0 Daps of downtime at EOC 533.9 t Total cycl EFPD 679 s Total cycle length In calendar days 04  : Integer position of assutn y In cycle 09  : Insertion reactor cycle Identifier 4 s of stpts In cycle 0 :Stpt EFPD 0 :Length to stpt in calendar days O  : Downtim at stpt 158. :Stpt EFPD 168.0 Length to stpt In calendar days 2.146 s Dogntime at stpt 219.0 s Stpt EFPD 233.146 3 Length to stpt incalendar days 53.125 I Dountike at stpt 363.1 s Stpt EFPD 431.271 s Length to stpt In calendar days 1.625 s Downtime at stpt 55.0 s Cays of downtime at EOC 557.23 s Total cycle IFPD 632.0 :Total cycle tenoth In calendar days 07 s Integer position of assembly in cycle s rFlag for variable or constant irradiation step specs 1 s Relative Insertion cycle #

1 s Relative stpt # In insertion cycle 8.Z  : Irradiation step length in EFPC 2  :-4 of Irradiation steps to next stpt 1510.73  : ppb 1419.25 a pffb 2 Relative stpt # In intertion cycle 42.2 s Irradiation step length in EFPD 1 s

• of irradiation steps to next stpt 1305.52 s ppb 3 s Relative stpt f In insertion cycle 66.05 s Irradiation step tength in EFPO 4 I of irradiation steps to next stpt U

1142.75 s ppb 985.95 s pwb 793.58 s ppr 58.91 s ppb 4 s Relative xtpt I In Insertion cycle 5.6 s Irradistion step length in EFPD I s # of Irradiation steps to next stpt 484.53%Xpb 5 a Relative *tpt

• in Insertion cycle 52.95 a Irradiation step length in EFPD 2 a 6 of irradiation steps to next stpt 416.34 t ppb 274.5 sppb 6 Relative stpt #Iin Insertion cycle 20.4 t Irradiation step length In EFPD 1 t # of irradiation steps to next stpt 185.39 Am 2 Relative Insertion cycle I R

I Relative stpt I In Insertion cicle R

52.93 s Irradiation step length In EFPO 3 t i of irradiation steps to next stpt 1599.85 t ppb 1491.21 I ppb

0 ATTACHMENT I Page 3

&U 06 11:27 1997 File Name: WKI.dot gUIOOODO_7102 000044 UV 0 1361.7 s.n 2 s Rlative stpt # In Insertion cacle 60.2 s IradIatiUn Step l4gth In EFPD I # oft frradiationst tonext stpt 1211.60O psb 31 Re6ative stpt # in Insertion cycle 72.05 J Irradiation step tlenth in EFPD 2 s # of irradiation steps to next stpt 1016.51 s Wb

£02.70 :ppsb 4 s Relative stpt # In insertion cycle 6.71 :Irradiation step length In EFPD 3  : I of Irradiation steps to next stpt 584.95  : ppb 38.60 s 192.666 18 s *of axial nodes In CRC forumt 1 17.7800 s lode f node height (en) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 _

16 20.0025 17 20.0025 18 22.3520 No CIA INSERTION 1ISTORY Ho AP0RA INSERTION HISTORY la s

• of full top axial nodes CBOC-8 to Stpt2-8) 1 17.7800 s Node rnode height Cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0625 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 1200.9 1415.7 1542.4 1601.1 1625.7 1635.5 1638.9 1640.0 1639.9 1639.1 1637.5 1634.6 1628.9 1617.8

Aug 06 11I:27 197 Ff e maw: 104f .dat gBAOOODOo0171 7*02OO-00044 ay 00 ATTAMMENET I- Page £ f 1596.6 1550.5 1454.8 1242.0 is  : # of fuel top axisl nodes CStpt2-5 to Stpt3.B) 1 17.7300 lade #, node height (em) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 1200.9 1415.7 1542.4

.1601.1 1625.7 1635.5 1638.9 1640.0 1639.9 1639.1 1637.5 1634.6 1628.9 1617.8 1596.6 1550.5 1454.8 1242.0 18 fUof fuel teo axial nodes CStpt3-8 to Stpt4-8) 1 17.7300  : lode #, node height (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 1202.2 1391.4 1487.0 1520.3 1527.3 1527.1 1524.9 1522.5 1520.7 1519.7

Aug 06 11127' 1997 Ff to Name: u041.dhkt *3AcO0000-01717ZO200-W jy 00 ATTACNWIEi I Page 5 1519.4 1s19.7 1519.9 1518.3 1511.1 1490.1 1421.2 1229.6 18 t # of fuel tmp axial nodes CStptt4- to $tptS-)

i 17.7300 I Node F, node height acm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 B 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 1202.2 1391.4 1487.0 1520.3 1527.3 1527.1 1524.9 1522.5 1520.7 1519.7 1519.4 1519.7

¶519.9 1518.3 1511.1 1490.1 1421.2 1229.6 18  : # of fuel topm axist nodes CStpt54g to Stpt6-8) 1 17.7800  : Node U. node eight (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 1162.3 1317.3 1358.8 1355.6 1345.7 1335.2

Aug 06 11:27 1997 Ffle t ame: *041.dat *SAUMMOOO-01717-0200 -40044 REv 00 ATTACMEUT I - Page 6 1326.9 1320.4 1316.4 1313.3 1311.6 1311.8 1314.6 1320.5 1328.6 1331.7 1312.5 1178 18  : t of fuel teop axial nodes (Stpt6-8 to EOC-2) 1 17.7800 i lode f node height (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 1162.5

¶317.3 1358.8 1355.6 1345.7 1335.2 1326.9 1320.8 1316.4 1313.3 1311.6 1311.8 1314.6 1320.5 1328.6 1331.7 1312.5 1178 15 I # of fuel tap axial nodes (1OC-9 to Stpt2-9) 1 17.700 Node node height (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 t82.9 990.8

Atu 06 11:27 1997 Fit lame: K041S.dt £RAOoooo00 07174-2COD0 04 REV 00 ATTACOMM I - Pag 7 1038.3 1058.9 1067.5 1069.9 1069.1 1066.4 1062.7 1058.5 1054. 1 1049.3 1043.8 1036.4 1025.1 1005.8 966.6 856.7 18 a 4 of fuel tup axial nods (Stpt2-9 to St39) 1 17.7o8 a Node I node height (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 T 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 895.1 991.5 1026.4 1036.3 1038.2 1036.3 1032.8 1028.8 1024.9 1021.4 1018.2-1015.6 1013.2 1010.3 1004.9 993.2 965.3 867.0 18 X 4 of fuel tonp axlil nodes CStpt3-9 to Stpt4-9) 1 17.700  : node I, node height (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 .20.0025 16 20.0025

200 Am~ 06 JIM2 1997 Pile Nans: g01.&t *IAOOOO.01717O0 00044 a 00 ATTACOMEN I -Page £ 17 20.0025 r 18 912.9 22.3520 993.7 1016.5 1021.7 1018.7 1013.1 1007.6 1002.8 998.9 995.9 993.7 992.5 992.4 993.1 993.0 986.9 963.2 U8l.0

# of mod spec vot axisL nodes (SOC-l to stpt2-9) 1 17.7800  : Node I. nods height (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 0.0239 0.0238 0.0237 0.0235 0.0234 0.0232 0.0231 0.0229 0.0228 0.0226 0.0225 0.0223 0.0222 0.0220 0.0219 0.0218 0.0217 0.0216 18 z I of mod spec vol exist nodes CStpt2-8 to Stpt3-)

1 17.7800  : Node #, node height (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 a 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025

44 Aug 06 11:27 1997 fit* Name: RUI-dBt A~0 11:7 ~

197FleNme:OU EACC00000.017-7.ozoO000 1t UEV G0 ATTACIINe I - Page 9 13 20.0025 14 20.0025 1s 20.0025 16 20.0025 17 20.0025 18 22.3520 0.0239 0.0238 0.0237 0.0235 0.0234 0.0232 0.0231 0.0229 0.0228 0.0226 0.0225 0.0223 0.0222 0.0220 0.0219 0.0218 0.0217 0.0216 18  : # of mod spec vol axalt nodes CStpt3-8 to Utpt4-8)

I 17.7OO  : Node U, node height (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 Z0.0025 17 20.0025 18 22.3520 0.0240 0.0239 0.0238 0.0236 0.0234 0.0233 0.0231 0.0230 0.0228 0.0226 0.0225 0.0224 0.0222 0.0221 0.0219 0.0218 0.0217 0.0216 18  : of mod spec vtl axial nodes CStpt4-& to StptS t) 1 17.7500  : Node #, node height (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 a 20.0025

4 AM. 06 11:27 1997 File Kame: 1041.det *1A000000.01r17.0200.000 R!V 00 ATTArNMEN I Page 10 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 0.0240 0.0239 0.0238 0.0236 0.0234 0.0233 0.0231 0.0230 0.022O 0.0226 0.0225 0.0224 0.0222 0.0221 0.0219 0.0218 0.0217 0.0216 18 s a of mod pc vol exile nodes (Stpt5-8 to Stpt648) 1 17.7800  : Node I, node height tce)

Z Z0.0025 3 ZO.0025 4 zo.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 0.0240 0.0238 0.0237 0.0235 0.0234 0.0232 0.0231 0.0229 0.0225 0.0226 0.0225 0.02Z3 0O.0222 0.0221 0.0220 0.0218 0.0217 0.0216 18  : iof mod spec vol axial nodes (Stpt6-5 to EDC-8) 1 17.I00 i Node 9 node height (cm) 2 ZO.0025 3 20.0025 4 20.0025

Aug o6 11:27 1997 Ff La Name: 1104i.dat OBAD0000-01717-0200-.oOS REV 00 ATTACHMENT I - Pave II 5 20.0025 6 20.0025 7 20.0025 a 20.0025 9 20.0025 10 20.0025 I1 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 0.0240 0.0238 0.0237 0.0235 0.0234 0.0232 0.0231 0.0229 0.0228 0.0226 0.0225 0.0223 0.0222 0.0221 0.0220 0.0218 0.0217 0.0216 I8 s of. mod epee vol axIal nodes tBOC-9 to Stpt2-9) 1 17.7800 a Node #,node heioht (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 II 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 0.0230 0.0230 0.0229 0.0228 0.0227 0.0226 0.0225 0.0224 0.0223 0.0222 0.0222 0.0221 0.0220 0.0219 0.0218 0.0217 0.0217 0.0216 18  : of mod spec vol axial nodes (Stpt2-9 to Stpt3-9)

4 Aug 06 11:27 1997 Ff1i Kae: (041.dat gB1AOCOO-O1717.0200-.04 nV 00 ATTACNEXWT I - Page 12 1 17.7800  : Node #* node height (ClM) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 II 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 0.0230 0.0230 0.0229 0.0228 0.0227 0.0226 0.0225 0.0224 0.0223 0.0222 0.0222 0.0221 0.0220 0.0219 0.0218 0.0217 0.0217 0.0216 18 s ao mod spec vot axial nodies (Stpt3-9 to Stpt4-9) 1 17.7300 Maode#, node height (cm)

Z 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 1S 20.0025 16 Z0.0025 17 20.0025 18 22.3520 0.0230 0.0230 0.0229 0.0228 0.0227 0.0226 0.0225 0.0224 0.0223 0.0222 0.0222 0.0221 0.0220 0.0219 0.0218

0 20 0 00 4 4 Aug 06 11:27 1997 Pite Nam: NO41.dat *3A00DO-O T1T-7 - aEV 00 ATTACINENT I - Page 13 0.0218 0.0217 0.0216 18  : Uof brmp axial node (boC-8) 1 17.7800  : Node I node height (es) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 tI 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 18  : I of burnup axialt nodes CStpt2-)

1 17.7800 mode of node height (cm)

N 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 2.047 2.997 3.624 3.959 4.141 4.250 4.321 4.369 4.404 A.4P7 4.436

Aug 06.11!?1997 Pito Name: XIM1.dat BOA00000001717.0200-000" REV 00 ATTACOMENT I Pape 14 4.426 4.354 4.295 4.142 3.882 3.427 2.514 18 * # of burmup axis nodes (Stpt3-9) 1 17.7800 s Node if r.de ibeight.(cm) 2 Z0.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 T 20.0025 a 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 15 22.3520 2.990 4.37Z 5.270 S.7 5.986 6.128 6.219 6.281 6.325 6.356 6.371 6.363 6.314 6.203 6.003 5.645 4.995 3.6 18 a f of burni "tat nodes (Stpt4-5)

I 17m7800  : Mode f. node height (cm) 2 20.0025 3 20.0025 4 20.0025 S 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 9.421 13.671 16.14a 17.243 17.712 17.930 18.054

Aug 06 11,27 199? Ffte KWm: K041.dat hBA0o00000-81?IYVOO200-DW REV 00 ATTACIDEN I -Page ¶5 18.145 18.226 18.307 18.384 18.446

¶s.46 18.382 15.105 17.377 15.628 11.403 18  : ef.bunup axial nodes CStpt5-8) 1 17.7800  : Made I rade height (cm)

Z 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 9.563 13.875 16.382 17.487 17.958 18.176 18.299 18.390 18.472 18.553 18.632 18.696 18.717 18.638 18.363 17.633 15.866 11.578 1l  : # of bump axaial nodes CStpt6-8) 1 17.7I00 s Node f, node height (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 12.380 17.873 20.893

Aug 06 11:2? 1997 File Nuns: K041.dat 31A00000.0177.r02 00 0 0

- '. uv a ATIACMENT~ I -Page ¶6 22.111 22.572 22.759 22.858 22.937 23.019 23.108 23.204 23.297 23.359 23.336 23.117 22.377 20.316 14.882 1s  : # of burut4 axial nodes (C4-9) 1 17.7800  : Node w. node height (ce) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.002s 7 20.0025 8 20.0025 9 20.0025 10 20.0025

• 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 I8 22.3520 12.966 18.694 21.805 23.038 23.494 23.672 23.763 23.833 23.904 23.982 24.063 24.139 24.187 24.156 23.934 23.187 21.079 15.453 I8 t sof burmip exisl nodes (Stpt2-9) 1 17.7800 Node E. node height (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025

¶6 20.0025 17 20.0025

BSA00000-0j717.0200400 4 UV to ATTACINENT I Page 17 Aug 06 11:27 1997 File Namez N04i.dat l8 22.3520 15.200 22.257 26.127 27.743 28.398 28.680 28.822 28.912 28.985 29.050 29.110 29.152 29.148 29.028 25.652 27.620 24.934 17.918 18 1sof burmip axial nodes CStpt3-9) 1 17.7800 lode #, node height (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 a 20.0025 9 20.0025 10 20.002M 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 15 22.3520 16.135 23.691 27.808 29.521 30.211 30.501 30.642 30.728 30.796 30.858 30.914 30.455 30.949 30.823 30.424 29.328 26.465 18.932 18 I # of burmp axial nodes Stpt4-9) 1 17.7800 sode t, node height (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025

20 0 0 0 4 ATTACHMMET I a 16 Fe Aug 06 11:27 1997 Fitc Rane: H041.dat haAOOOOM o*01717- 0 4 aEV 00 14 20.0025 15 20.0025 16 20.0025 17 20.0025

¶8 22.352D-

¶8.561 27.279 31.897 33.756 34.467 34.740 34.858 34.925 34.981 35.038 35.097 35.149 35.161 35.056 34.660 33.490 30.290 21.561

Aug 06 11:50 1997 Flte Earm: Kt2i.dat nAAOOOOOO01717.0200-00044 REV 00 ATTACHMENT 11 page I N  : This ls not *piek-ip cue Crystal River# Unit 3 Reactor Identifier CR3 s Pr fix Identifier for reactor U"gror u Scale crois sectirn library 3.94 U-25 utS enrlehment in U of uo2 463630 s trm of U per gassbty 208 s Huiber of fuel rodi.In assembly 1.44272  : Pin-pitch In assembly (cm) 0.936244  : Fuel petlet dliOter (cm) 0.9575b  : Fuel rod cladding ID (cm) 1.0922

• Fuel rod cladding D (cm) 360.172  : Fuel stack height (cm)

N s No axial blanket fuel ZINC4  : Spacer grid material 0.003165257 S Vol. frac. of mod. displaced by grids ZIRC-4 s Fuel rod cladding material A40.0 S Avg. fuel rod cladding temp. (K)

Y s Cladding materials ether than ZIRC-4 1 s Unber of cladding materials needed other than ZIRC-4 a aSASZM material mixture number for clad eaterlal below SS304 :Cladding materale for CR's 2200.0 s System pressure (pst)

Y s Activate 8PRA tracking 1 s liNber of reactor cycles uith BPEA t0o c PRA designs, # of non-At20334C BP's of 3.7 2.0 0.557538 16 2

• Input Card 1JC 8 o f radial zones In SPRA Path I model 4 0.43180 U SPRA Path U model (Input Card 182) s 0.45720 2 0.54610 3 0.63246 2 0.67310 3 0.81397 500 2.91402 3 2.93693 3 0.43180 Path B model uith XPRA removed (Iniput Card 18F) 3 0.45720 3 0.54610 3 0.63246 2 0.6n310 3 O.81397 500 2.97599 3 2.99939 6 0.43184  : PRA Path I model above absorber (Input Card 18G) 5 0.45720 2 0.54610 3 0.63246 2 0.67310 3 0.81397 500 2.91402 3 2.93693 AL203 6 sMt. above obsorber In BPR $MM met six.

1 1 2 17  : PEA insertion history (Input Card 18M) 5  : f of radial zones in the standird Path 6 model 3 0.63246  : Standard Path U model (Input Card 20) 2 0.67310 3 0.81397 500 2.97599 3 2.9939 1  : I of cross-section llbraries per irradiation step 5 :SAS2H output print level 0.5 s Zone mash factor for XSDRUPR NO SPECIAL s No special KIORMPK control perometer specs.

2  :

• of insertion reactor cycles 08 s Insertion reactor cycle Identifier 6 s of stptsln cycle 0 sStpt EFPD 0 s Length to stpt in calendar days 0 :DoMt1me at stpt 97.6 tStpt EFPD

1 17 i

AUM 06 11:50 1997 Flle me: H12I.dat 3A00COOO TT 0200O0044 REV 00 ATACOENT 11 - Page 2 110.0 s Lenth to *tpt In calendar days 15.5 s Dontime at stpt 139.8 s 6tPt EFPO 173.5 sLength to ctpt fn calendar days 6.2 a Do0ntie at stpt 404.0 I Stpt EFPO 479.7  : Length to stpt in calendar days 44.4  : 0ojntiee at stpt 409.6 I Stpt EFPo 529.1 s Length to stpt In calendar days 4.9 a oint Ie at stpt 515.5  : gtpt EFPD 64S.0 s Length to stpt In calendar days 7.6 a Downtime at *tpt 75.0 :Days of downtim at EOC 535.9  : Total cycle EFPD 679  : Total cycle length In calendar days 12 a Integer position of mssewbly In cycle 09  : Insertion reactor cycle Identifier 4  :# of ctpts In cycle 0 :Stpt EFPD O  : Length to stpt In calendar days 0  : Dontime at stpt 158.8 s Stpt EFPC 168.0  : Length to stpt In calendar days 2.146 Downtime at stpt 219.0  : ttpt EFPt 233.46 Length to atpt In calendar days 53.125 s Downtime at ctpt 363.1  : ttpt EFPD 431.271  : Length to stpt in calendar days 1.625 s Downtime at ctpt 55.0 Days of downtime at EOC 55T.23  : Total cycle UPF 632.0 :aTotal cycle length In calendar days 18  : Integer position of asserbly In cycle Y s Flag for variable or constant IrradiatIon step specs I s Relative Insertion cycle 1  : Relative statepoint In Insertion cycle 2  : Nuber of steps in statepolnt calculation 48.8 1510.73  : Step length (EFPD), Kid-step ppmb 48.U 1419.25  : Step length tEFPO), Kid-step ppmb 2  : Relative statepoint In Insertion cycle I  : Umaber of at"ps In atatepoint calculation 42.2 1305.52 s Step length tEFPD), N-dstep ppmb 3 s Relative statepoint In Insertion cycle 4 Number of steps In statepoint calculation 66.05 1142.75 s Step length (ESPF), Kid-stop -

66.05 98595 s Step length CEFPD)* Kid-step pp;b 66.05 793.58  : Step length (EFPD) KNid-step ppmb 66.05 588.91  ; step length (ESfD) Kid-step ppb 4 s Relative statepoint In Insertion cycle I a ller of steps In statepoInt calculation 5.6 484.53 Step length (EFPo). Nid-step ppb 5 s Relative statepoint In Insertion cycle 2  : EUber of steps in atatepoint calculation 52.95 416.34 Step length (EFPD), Kid-step p-b 52.95 274.55 s Step length EFPD), Kid-step i 6 s Reative statepotnt in Insertion cycle 1 s Iuber of steps in atatepoint calculation 20.4 185.39 astep length (EFPD), Kid-step ppeb 2 sRelative Insertion cycle I s Relative atatepoint In Insertion cycle 5 sa mber ef steps in stateInt calculatIon 2.29 1646.8 s Step length EFPD), lid-step wib 32.23 1614.8  : Step length EFPD), Kid step ppb 59.57 1528.1  : Step length ESD), KId-step ppmb 59.57 138.4  : Step length (EF) sid-tep ppeb S.34 1300.1  : tep length (EP), Kid-step ppab 2 I Relative statepolnt Ininsertion cycle

Aug 06 11:50 1997 Fite Eamr: *121.dat O80000ooo01717-0200-0004 REV 00 ATTACUIE1T -* Page 3

lunber of stops In statepoint calculation 2.57 1289.4 2 51ttp lenth (EFPD), Kid-stop ppb 6.U0 1276.5  : SIlop length CEFPD). Kid-stop ppb 50.55 1196.8 :s1 top length (EtPDC. Kid-step ppmb

.20 1131.9 tep length (EFP0), kid-step ppmb 3  : Relative statepolnt In Insertion cycle 5 tnumber of steps In statepofnt calculatin 12.56 1111.4 tep length (EFPD): Nid-step ppab 3.64 1085.4  : Sitep length (EFPD) Kid-step ppob 63.90 978.0 tep length (EFPD). Kid-step FPb 63.90 790.9  : ,Si S1tep length (EFPD), Kid-step pprb

.10 691.8 :Sttep length (EFPD). KId-step FPth i Relative statepoint In Inertion cycle sIUutor of steps In statepoInt calculation 3

64.71 384.95 I:step length (IFPD), Kid-step ppob "J71 388.60 I step length (EFPD). Kid-step ppmb 64.71 192.66 I5Step length (EFPD). Kid-step ppb 18 IsI of axial nodes In CRC format 1 17.7100 II--node 1, node Mieght (cm)

Z 20.0025 3 Z0.0025 4 20.0025 5 Z.W0025 6 Z0.0025 7 20.0025 a 20.0025 -

9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 No CRA INSERTIOU KICTORI F RODDED 14 :Nuwber of Irradiation steps with APSUA Inserted 2 1 1 9 13 7 1 8 iIrput card 48 2 1 2 9 12 7T1 8  : IrAt card 483 2 1 3 10 12 7 1 8  : Iput card 483 2 1 4 10 12 7 18 slInut card 48 2 1 5 10 tl 7 1 8  : Irput card 4JB 2219 1371 a Irput card 488 2 2 2 10 13 7 1£ IsWt card 485 2 2 3 10 12 7 1 5 :Isput card 48U 2 2 4 10 12 7 1 8 Ispitt card 481 23 1 9 1371 A Irput card 4U8 23210 1371I sIWut card 4B8 23 310 1271I i Irpt card U8 2 3

• 10 12 7 1 8 sUwut card 483 2 3 S 10 12 7 1 £ sIrput card 488

luwber of different APSRA absorber noterial mixtures 7 S2 material abIture rurber for APS1 absorber 5 lumber of Isotopes or elo.nts In the APSRA absorber 14000 2.5 -SCALE Isotope 10, Isotope wtX Z2000 2.5 t SCALE isotope 10, Isotope WX 24000 15.0 aSCALE Isotope It, Isotope wtl 26000 7.0 SCALE Isotope ID, Isotope mt 28000 73.0 SCALE Isotope [D. Isotope vt%

1  : luber of APSRA dasigus 8.3 8 AAPSI absorber density, IPSR clad SAM mat. mix. mtber s lluber of radial zones InPath 8 model with APSUR insert4 7 0.47625 Path 8 modal APSRA Insarted (iptS Cord 48J) 5 0.49022 8 0.55880 3 0.63246 2 0.67310 3 0.81397

Aug 06 11s50 1997 Fifl lame: 3121.dst 1BADOU o0017-17.0200-0004 REV 00 ATTACKHM 11 - Page 4 50 2.90826 I 3 2.93113 3 0.47625 Path model VPW removed CurAut Card 48) 3 0.49022 3 0.55880 3 0.63246 2 0.67310 3 0.81397 500 2.97599 3 2.99939 3 0.47625 Path e model APM follow rod Cinput Card 48L) 3 0.49022 8 0:55880 3 0.63246 2 0.67310 3 0.81397 500 2.96707 3 2.99040 1I s 0 of fuel te axial nodes CBOC-8 to Stpt 2-9) 1 17.7800 Ilode if, node height (cm) 2 20.0023 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 18S4.9 1395.9 1521.2 1578.1 1601.3 1611.4 1616.1 1617.5 1617.6 1617.1 1616.2 1616.1 1615.7 1607.3 1586.0 1539.2 1443.6 1232.8 18 a f of-fuel tep axial nodes CStpt2-A to Stpt3-8) 1 17.7800 Node N I, node height Cm) 2 20.0025 3 20.0025 4 20.0025 S 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 It 20.0025 12 20.0025 13 20.0025 14 20.0025

Am 06 1160 1977 -File mm: mi2f.1clit AL~ 197Flerni:*21.I 3AD00000.01717-0200-00044 B061:5 REv 00 ATTACHMMEIIt - Page 5 15 20.0025 16 20.0025 17 20.0025 1t 22.3520 1184.9 1395.9 1521.2 1578.1 1601.3 1611.4 1616.1 1617.5 1617.6 1617.1 1616.2 1616.1 1615.7 1607.3 1586.0 1539.2 143.6 1232.8 18  : I of fuel temp axial rodes (Stpt3-I to Stpt4-O) 1 17.7800  : Nod #, node hergIht (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 B 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 1190.9 1377.2 1472.0 1504.8 1511.1 1510.2 1507.9 1505.7 1504.0 1503.0 1503.2 1505.3 1509.0 1509.2 1502.7 1481.7 1411.9 1222.4 18  : # of fuel tem aal nodes (Stpt4-8 to stptS-8) 1 17.7800  : Node #, node height (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 a 20.0025 9 20.0025 10 20.0025

Aug 06 11:50 1997 File NaMe: NIZI.dst RIA CDO-OO0177-02W00000S REV 0o ATTADC4ENT I I - Page 6 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 1190.9 1377.2 1472.0 1s04.8 1511.1 1510.2 1507.9 1505.T 1504.0 1503.0 1503.2 1505.3 1509.0 1509.2 1502.7 1481.7 1411.9 1222.4 18 U f of fuel tap exial nodes (Stpt5-I to gtpt6-8) 1 17.7800

• Nod I node height (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 a 20.0025 9 20.0025 10 20.0025

¶11 20.0025 12 20.0025 13 20.0025 14 20.0025

¶5 20.0025

¶6 20.0025 17 20.0025 1 22.3520 1158.7 1315.5 1359.3 1355.6 1343.3 1332.5 1324.5 1318.7 1314.6 1311.9 1310.5 1311.8 1316.8 1323.4 1331.6 1335.1 1316.1 1179.9 18 s # of fuel tow axial node (Stpt6-B to EOC-S)

I 17.7500 Node if node height (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025

AUg 06 11:50 1997 Fite NIam: 9I121.dat BL"00000-01717-8200-Ow" ILEV 00 ATTACNEIT 11 - Ps"e 7 7 20.0025 a 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 1158.7

'1315.5 1359.3 1355.6 1343.3 t332.5 1324.5 1318.7 1314.6 1311.9 1310.5 1311.8 1316.8 1323.4 1331.6 1335.1 1316.1 1179.9

of ftil tep axial nodes CXOC-9 to Stpt2-9) 1 17.7800 :lode #, node height (cm) a 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 15 22.3520 989.5 1115.9 1177.7 1200.9.

1192.7 1193.8 1193.4 1191.2 1137.7 1183.8 1179.8 1179.5 1209.7 1206.2 1192.4 1167.9 1119.9 9a3.2 18  : I of fuel temp axial nodes (Stpt-9 to Stpt3-9)

I 17.X00  : Node #. node height (cm) 2 20.0025

"06 11 gg0 ue Names MI.AMI 197 B3AO000000 7-017.200.o000. REV 00 ATTACOMMItIE - Page 3 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 tB 22.3520 999.8 1114.1 1162.5 1177.1 1161.5 1158.0 1155.0 1151.3 1147.7 11U.4 1141.9 1143.3 1171.3 1176.4 1169.4 1149.8 1111.9 985.9 1e s # of fuel tap axial nodes (Stpt3-9 to Stpt4:9) 1 17.78o0 g Node 6, node height (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 1010.7 1108.2 1150.2 1160.9 1138.5 1130.0 1124.0 1118.9 1115.0 1112.1 1110.4 1112.6 1139.0 1148.5 1149.4 1141.1 1103.6 a

Aug 06 11:50 1997 Aug61:5 Name:

197File mitf~at 33AD000.@1ITI-02O0044O REV 00 ATTACNMT 1I - Pag 9 990.0 18 # ef fod spec vaot xlis nodes (04C- to Stptl-S)

1. 17.780 s Node f, node height (et) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 a 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 2?.3520 0.0239 0.0238 0.0236 0.0235 0.0233 0.0232 0.0230 0.0229 0.0227 0.0226 0.0224 0.0223 0.0222 0.0220 O.0z2V 0.0218 0.0217 0.0216 18 s Uof mod spec vol axial nodes (Stpt2-8 to Stpt3-8)

¶ 17.7800 Node S. node height (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025

¶1 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025

¶7 20.0025 18 22.3520 0.0239 0.0238 0.0236 0.0235 0.0233 0.0232 0.0230 0.0229 0.0227 0.0226 0.0224 0.0223 0.0222

Aug 06 11:50 1997 File kams: K121.dat BAlR0000oc.I0717-0200-O000 IEV 00 ATTACINT 11 - Page 10 0.0220 0.0219 0.0218 0.0217 0.0216 18

• of mod spe vaol xil

1. x riqes (Stpt3- to gtpt4-8) 1 17.7800  : Node , rde height Cem) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 a 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 0.0240 0.0239 0.0237 0.0235 0.0234 0.0232 0.0231 0.0229 0.0228 0.0226 0.0225 0.0223 0.0222 0.0221 0.0219 0.0218 0.0217 0.0216 l8  : U of mod pc vot axial nodes (StptA-B to Stpt5-S) 1 17.7800 Uode f. rode height (en) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 I 9 20.0025 10 20.0025 17 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.002 17 20.0025 18 22.3520 0.0240 0.0239 0.0237 0.0235 0.0234 0.0232 0.0231 0.0229 0.0228

&Q06 11:50 1997 Fit. Name: U12f.dat SBACOODOOO01717-0200-00044 REV Oc ATTAWIEU 11 -page 11 0.0226 0.0225 0.0223 0.O222 0.0221 0.0219 0.0218 0.0217 0.0216 18 9 of meod Spec Vol axa'l nodes CstptS- to Stpt6-8) 1 17.7100  : Node J. node heloht (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 0.0240 0.0235 0.0237 0.0235 0.0234 0.0232 0.0230 0.0229 0.0228 0.0226 0.0225 0.0223 0.0222 0.0221 0.0220 0.0218 0.0217 0.0216 18 a 4 of maod qec vot axiat nodes CStpt6-3 to WC-B) 1 17.7800  : Node f, node height (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025

• 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 0.0240 0.0238 0.0237 0.0235 0.0234

AMg 06 11:50 1997 Ff~liaK,w: mi2f.dat *IA000o00.g1717.-0200-0004A REv 00 £iTTAtHIM4N It - Page 12 0.0232 f 0.0230 0.0229 0.0228 0.0224 0.0225 0.0223 0.0221 0.0221 0.0220 0.021B 0.0217 0.0216

of mod swc vol axial nodes tBC-9 to Stpt2-9) 1 17.7800 N Node U, node height (cm) 2 ZO.0025 3 20.0025 4 20.0025 S 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 Z0.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 1 22.3520 0.0236 0.0235 0.0234 0.0232 0.0231 0.0230 0.0228 0.0227 0.0226 0.0225 0.0224 0.0223 0.0221 0.0220 0.0219 0.0218 0.0217 0.0216 1I

• 9 of mod qe vot axial nodes (Stpt2-9 to Stpt3-9)

I 17.7800 *Node 9. node heIght (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 0.0235

Aug 06 II1-S0 1997 Ffle lawe H121.dt seACODOOOO017ll?020000044 1V 00 ATTACMENIT I I - Paae 13 0.0234 0.m233 0.0232 0.0231 0.0229 0.0228 0.0227 0.0226 0.0225 0.0224 0.0223 0.0221 0.0220 0.0219 0.0218 0.0217 0.0216 1a  : I of mod spc vot uial nodes CStpt3-9 to Stpt4-9) 1 17.7800 X mode U,node height Ca) 2 20.0025 3 20.0025 4 20.0025 S 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 0.0235 0.0234 0.0233 0.0232 0.0230 0.0229 0.0228 0.0227 0.0226 0.0225 0.0224 0.0223 0.0221 0.0220 0.0219 0.0218 0.0217 0.0216 la s I of burnup axt nodes Cb=C-)

1 17.7800 X Node #, node eUfght Cc.)

2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 Z0.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 .20.0025 15 20.0025

Amg 06 11:50 1997 Fite Wlum: N121.dat ggAOOooo-01717-0200-oco0. ItV 00 ATTACWNIE 11 Page 14 16 20.0025 17 20.0025 18 22.3520 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 18 2 I of bzrnp axial nodes (Stpt2-8) 1 17.78O I Node #, node height (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 1.978 2.905 3.521 3.846 4.020 4.128 4.201 4.251 4.285 4.310 4.329 4.344 4.331 4.256 4.106 3.843 3.384 2.477 18

• of burnmaxial nodes CStpt3-)

I 17.7800

• Node , node height (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 ZO.0025 7 20.0025 8; 20.0025 9 20.0025 10 20.0025 11 20.0025

0 Aug 06 11:50 IM Ff I* N", 1112i-dIt Aug06 tA0000-011f7-t~S 197Flegneu11.dt 20-0004 UiV 00 AT1AORMU 11 Page ¶5 12 20.0025 i 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 2.892 4.241 S.125 5.578 5.811 S.950 6.042 6.105 6.150 6.182 6.208 6.233 6.227 6.138 5.942 5.583 4.929 3.603 15  : of. burmp axial nodes (ttpt4-6) 1 17.7100  : Mode 0 roode height (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 Z0.0025 16 20.0025 17 20.0025 18 22.3520 9.179 13.343 15.784 16.839 17.256 17.457 17.580 17.671 17.752 17.835 17.932 18.067 18.197 18.171 17.909 17.182 15.437 11.255 18 s # of burnup axial nodes tStptd-I 1 17.7600 2 mode U.node height (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025

Aug 1150 1S97 File Nhe: N1ZI.dat *IAOMOOO .01717-0200 -0044 alv 00 ATTACNMET 11 - Page 16

._ 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 9.318 13.5"4 16.015 17.079 17.498 17.698 17.821 17.912 17.994 18.078 18.177 18.314 18.49 18.426 18.166 17.437 15.673 11.428 18  : # of bump axial nodes (Stpt6-S) 1 17.7800 :Node i, node heIght (cm) 2 Z0.0025 3 20.0025 4 20.0025 5 20.0025 6 Z0.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 12.102 17.502 20.4A8 21.662 22.064 22.231 22.332 22.414 22.497 22.591 22.713 22.891 23.086 23.126 22.923 22.183 20.122 14.729 18  : # of bawip axial nodes c1C-9) 1 17.7M00 Node C node height (cm) 2 ZO.0025 3 20.0025

Aug 06 11:50 1997 Ff1.e Ua: N121.j t BIOO17O.01717.0200-CO04 RV 00 ATTACNT 11

• Page 17 4 20.0025 5 20.0025 6 20.0025 7 20.0025 a 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 13 22.3520 12.688 18.325 21.406 22.599 23.001 23.163 23.257 23.331 23.405 23.486 23.591 23.749 23.923 23.951 23.744 22.997 z0.889 15.303 18 s .f humnW axiat gmneg (stpt2-9) 1 17.7800 z Node 9. node height (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520

¶5.690 22.967 26.981 28.593 29.024 29.283 29.442 29.549 29.634 29.714 29.814 30.022 30.528 30.528 30.141 29.047 26.253 18.878

Aug 06 11sS0 1997 Ffle uim: H12N.dat 3AC00 0.01717.0200-0 REV 00 fly ATTACWMI 11 X P&ae 18 18  :* of bauwv taal noe(tpt3-9) 1 17.7100 I Nod 9, nod hoight (en) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025

• 7 20.0025 a 20.0025 9 20.0025 10 20.0025 11 20.0025

-12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 16.936 24.636 29.167 30.898 31.292 31.554

.31.716 31.821 31.903 31.983 32.085 32.313 32.945 32.973 32.562 31.385 28.371 20.327 18  : # of bunW axfst rodes (stpt4-9) 1 17.7100 XNod I node height Ccm) 2 ZO.0025 3 Z0.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 a 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 20.119 29.464 34.455 36.374 36.620 36.845 36.986 37.077 37.153 37.234 37.351 37.637 38.580 38.713

2 VmOQ nATTACUIEM i- Page 19 tomums N1I.dat 66 1150 1997 Ffle 0ug *gAoOoO.O l?71 O-0200- 00 38.314 37.035 33.590 23.994

Aug 06 11:43 1997 File Name: N23I.dAt *BAOOOOo.01T17.0200-00044 NEl 00 ATTACOIRT III Page 1

• : This Is not *Pick-up case J Crystal Rliver, hlit3  : Reactor Identi fer CR3 s Prefis Identifier for reactor 4"growp Scale croMsasctIon library 3.94 :U-235 wtX enrichment In U of U02 463630 :Grams of U per assembly Z08 Nuiber of fuel rods In assembly 1.442 a Pin-pitch In asseubly (cm) 0.936244 :Fuel pellet disaeter (cm) 0.95753 :Fuel rod cladding ID (cm) 1.0922  : Fuel rod cladding 00 (cm) 360.172  : Fuel stack height (cm)

U :No axiat blanket fuel ZIRC-4 s Spacar grid material 0.008165257  : Vol. frac. of mod. displaced by grds ZIRC-4 s Fuel rod cladding material 640.0 s Avg. fuel rod cladding top. tO

• s No cladding materials other than ZIRC-4 2200.0 s System pressure (psi)

Y s Activate 8PRA tracking 1 s Hurber of reactor cycles with IPRA t0 # of BPRA designs, # of non-AM20384C UP's 3.7 2.0 0.5857538 16 2 4 s Isrut Card I&C E s osf radial :wnas in PPRA Path 9model 4 0.43180  : BPRA Path B model CIrpIt Card 1BE) s 0.45720 2 0.54610 3 0.63246 2 0.67310 3 0.81397 500 2.91402 3 2.93693 3 0.43180 - Path I model with 8PRA removed (lrlat CareI18F) 3 0.45720 3 0.54610 3 0.63246 2 0.67310 3 0.81397 500 2.91402 3 2.93693 6 0.43180 RPRA Path I model above absorber (input Cm ird ¶8G)

S o.4sno 2 0.54610 3 0.63246 2 0.67310 3 0.81397 500 2.91402 3 2.93693 AL203 6 t Hat. above absorber In SPR, SAt2N mat. mixx.if 11 2 17  : PPRA insertion history cInput Card 18m) 5  ; of radial zones in the standard Path F aodel 3 0.63246 sStandard Path I model (Irput Card 20) 2 0.67310 3 0.81397 500 2.97599 3 2.99939 1  : Iof cross-section libraries per Irraediat on step S SAS2N output print level 0.5  : Zone mesh factor for XSDR)WH NO SPECIAL t Uo special XSDRXNI control parometer specs 2 s # of Insertion reactor cycles 08 t Insertion reactor cycle Identifier 6  :# of tpts Incycle 0 h tpt EFPD 0 s Length to stpt in calendar days 0  : Downtime at *tpt 97.6 . Utpt EFP 110.0 tLength to stpt In calendar days 15.5 t Downtime at stpt 139.8 :Stpt EPPD

Aug 06 11:43 1997' File Name: K231.dht IMDOOM-OO.y01710Z000004 UV 80 ATTACIOIEIT III -Page 2 173.s Length to StPt In calendar days 6.2 I *omtime at stpt 404.0  : Stpt EFPD 479.7 1Lenth to stpt in calendar days 44*4 J Downtie at stpt 409.6 s Stpt EFPD 5Z9.1 s Length to MtPt In calendar days 4.9 s Dosntime at stpt 515.5 s Ctpt EFPD 645.0 Length to stpt'In calendar days 7.6 Sowntime at stpt 75.0 toays of downtit .at EOC 535.9 s Total cycle EFPo 679 i Total cycle length In calendar days Z3 s integer position of ASSIbly in cycle 09 Insertion reactor cycle identifier 4 s # of stpts In cycle O i tpt EFPD O  : Length to stpt In calendar days O s Dowatiue at stpt 15t.8 A Stpt EFPD 168.0 s Length to stpt In calendar days 2.146 s Downtime at stpt 219.0 s Stpt EFPD 233.146  : Length to stpt In calendar days 53.125 s Downtime at stpt 363.1 sttpt EFPD 431.271 s Length to stpt In calendar days 1.65U Dointime t stpt 55.0 I Days of dobhtoe at t C 557.23 s Total cycle EFPO 432.0 s Total cycle length In calendar days 16 s Integer position of assembly In cycle a s Flag for variable or constant irradiation step specs

Reloative Insertion cycle I 1 s Relative stpt 6 In Insertion cycle 48.8 s Irradiation step length in EFPO 2  :# of Irradiation steps to next stpt 1510.73 pab 1419.25 :ppb 2 s Relative stpt I In insertion cycle 42.2 s Irradiation step length In EFPO 1 s I of irradiation steps to next stpt 1305.52 s port 3 Relative stpt JIn Insertion cycle 66.05 Irradiation stop length In EFPD 4 s i of Irradiation steps to next stpt 1142.75 s ppmb 985.95 I ppnb 793.58 sppsb 588.91 :ppmb 4  : Retative stpt # In Insertion cycle 5.6 a Irradiation step length In EFPD I s I of Irradiation steps to next stpt 484.53 sppnb-5 s Relative stpt # In Insertion cycle 52.95 s Irradiation step length In [FPO 2 , s I of irradiation steps to next stpt 416.34 s ppb 274.55 sppab 6 Relative stpt f In Insertion cycle 20.4 s Irradiation step length In EFPO I ai of Irradiation step to next stpt 185.39 ppnb 2  : Rottive Insertion cycle U 1 s Relative stpt I in insertion cycle 52.93 a Irradiation step length in EFP 3 s i of Irradiation steps to next stpt 1599.85 :pprb 1491.21 s ppb

Aug 06 11z43 1997 Fit* Name: p2ni.dat BDAOOOOOO.Ol717.0200.00044 RE 00 ATTACW4EIL III- Page 3 1361.78 *ppmb 2  : Relative stpt f in ifsertion cycle 60.2 :Irradltion step length in EFPO I i i of Irradiation steps to next stpt 1Z11.6O  : ppeb 3 Relative stpt

• In Insertion cycle 72.05

• Irradiation step length In EFPO 2 :it of irradiation steps to next etpt 1016.51  : ppb 902.70  : ppnb

• s Reative rtpt f In Insertion cycle 64.71 t Irradiation stop length.In EFPD 3 s of irradiation steps to next stpt S4.95 ppb 318.60  : ppab 192.66 a ppnb 18 :I ofaxial odes In CRC format 1 17.7300 Node . rnde height (cm) 2 20.0025 3 20.0025 4 20.0025 S 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 N0 CRA INSERTION HISTORY NO APSRIA INSERTION HISTORY 1 *  : i of fuel tefp axisl nodem (SOC- to Stpt2-9) 1 17.7800  : Node I node height (cm) 2 20.0025 3 Z0.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 1t 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 1176.8 1391.6 1520.8 1580.0 1604.5 1615.1 1619.4 1620.8 1621.0 1620.3 1619.9 1621.1 1622.6 1616.4

AUW 06 11:43 1997 File Name: N231.dat g1A000000 17.O2W04004A REV 00 ATTACHMENT IIlI Page 4 1597.8 I 1552.2 1452.4 1234.4 18 3 1 of fuel ttP axial node (Stpt2-S to 5tpt3-8) 1 17.7800  : K Node rcdk helght (en) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 1176.8 1391.6 1520.8 1580.0 1604.5 1615.1 1619.4 1620.8 1621.0 1620.3 1619.9 1621.1 1622.6 1616.4 1597.8 1552.2 1452.4 1234.4 18 t sof fuel tep axial nodes tStpt3-8 to stpt4-E) 1 17.7800 :Node 1f node height (cs) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 1150.1 1365.5 1459.5 1491.3 1497.2 1496.4 1494.1 1491.8 1489.9 1488.9

Aug 06 ¶1:43 1997 File Kwe: KZSi.dat BUAOOO0oo.0¶717-0200-00044 UV 00 ATTACEUT III - page 5 1489.3 1492.3 1497.3

¶198.8 1493.7 1472.6

¶1404.0

• 1214.9 18  : # of fuel tonp axisl nodes cstpt4-8 to Stpt5-8) 1 17.7800  : Mode I, node height (cm)

Z 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 1180.1 1365.5 1459.5 1491.3 1497.2 1496.4 1494.1 1491.8 1489.9 1488.9 1489.3 1492.3 1497.3 1498.8

¶493.7 1472.6 1404.0 1214.9

¶8 # of fuel teup axial nodes CStpts-U to Stpt6-3)

U 1 17.7800  : mode #, node height Ccs) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 13 22.3520 1148.5 1303.9 1347.1 1343.0 1330.5 1319.7

AMg 06 11.43 1997 Fite pNew:

12 3.dat *uRA=00OO6 7 l7 'C2 O-00 REV 00 ATYACW4EU III - page 6 1311.6 1305.5 1301.7 1298.8 1297.4 1298.5 1303.4 1310.3 1318.8 1323.3 1305.5 W12.2 18  : I of fuel ten axial nodes (Stpt6-8 t EOC48) 1 17.7300 Node U, node %etght (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 a 20.0025 9 20.0D25 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 1148.5 1303.9 1347.1 1343.0 1330.5 1319.7 1311.6 1305.6 1301.7 1298.8 1297.4 1298.5 1303.4 1310.3 1318.8 1323.3 1305.5 1172.2 18  : U of fuel top axial fades (3OC-9 to Stpt2-9) 1 17.7800 t Node IT, node helgiht (ca) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 a 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 1015 8 I 1140.4

Aug 06 11:13 1997 File lame: H231.dat 1BAOOOOOO.-O¶TIT.02000001 UEV 00 ATTACWVET III - page 7 1199.2 r- 1226.3 1238.7 1242.8 1242.5 1239.8 1235.9 1231.2 1225.9 1219.3 1210.8 1200.3 1185.3 1162.3 1119.8 99.2 1s  : o fuel top axial nodes (Stpt2-9 to Stpt3-9) of 1 17.7800

• lode if, nod height (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 a 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 Z2.3520 1025.9 1139.8 1186.8 1204.1 1211.6 1211.9 1209.0 1205.2 1201.2 1197.4 1193.9 1190.4 1186.3 1181.3 1171.9 I 1152.2 1116.8 994.3

- 18 t I of fuel tap axial node. (Stpt3- to ttpt&-9) 1 17.7800  : Node t, node height (em) 2 20.0025 3 20.0025 4 20.0025 5 20e0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.05 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025

00 Au; 06 1143 1997 File Na&ne: N231.dat 91A000000.01717-02 -00044 UV Do ATTAIUET III - Page £ 17 20.0025 18 22.3520 1034.8 1134.6 1177.8 1191.5 1190.7 1185.4 1179.4 1174.2 1170.0 1166.9 1164.6 1163.0 1162.3 1162.6 1161.2 1151.6 1113.8 999.8 18  : ol e of od gpec vxtet nodes (BOC-8 to gtpt2-8) 1 17.7800  : Mode 6, node height (cm) 2 20.0025 3 Z0.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 0.0239 0.0238 0.0237 0.0235 0.0234 0.0232 0.0230 0.0229 0.0227 0.0226 0.0225 0.0223 0.0222 0.0220 0.0219 0.0218 0.0217 0.0216 18 i # f mod spec vot axslt nodes CStpt2-A to Stpt3-8) 1 17.7100 t node U, nod height'(c) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025

Aug 06 11:43 199 File Mrame.NM13.d~ *3A0D01000717.0200-0OM4 kWy 00 ATTACKMENT III - page 9 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 0.0239 0.0238 0.0237 0.0235 0.0234 0.0232 0.0230 0.0229 0.022 0.0226 0.0225 0.0223 0.0222 0.0220 0.0219 0.0215 0.0217 0.0216 18  : f of rod spec vol axial nodes (Stpt34 to Stpt4-8) 1 17.7800  : Mode f, node height (cm)

Z 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 e 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 0.0239 0.0238 0.0237 0.0235 0.0234 0.0232 0.0231 0.0229 0.0228 0.0226 0.0225 0.0223 0.0222 0.0221 0.0219 0.0218 0.0217 0.0216 1J  : # of mod spec vol axial nodes (Stpt448 to StptS4B) 1 17.7800  : Node #,node height (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 a 20.0025

Aug 06 11:43 1997 Flit ame: 231.dat BAM00000.01717-M -004004 RtV 0? ATTACIET IIl - Page 10 9 20.0025 t

¶0 20.0025 1 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 0.0239 0.0238 0.0237 0.0235 0.0234 0.0232 0.0231 0.0229 0.0228 0.0226 0.0225 0.0223 0.0222 0.0221 0.0219 0.0218 0.0217' 0.0216 18 s of mod spec vot axiat nodes tp5-l to StWt-8A) 1 17.7300  : Node t, node height (cm) 2 20.0025 3 20.0025 4 Z0.0025 5 20.0025 6 20.0025 7 20.0025 B 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 0.0239 0.0238 0.0236 0.0235 0.0233 0.0232 0.0230 0.0229 0.0227 0.0226 0.0225 0.0223 0.0222 0.0221 0.0220 0.0218 0.0217 0.0216 18 I U of mod spec vol axlal nodes CStpt6- to EOC-B) 1 17.7100 lode t node heighet (cm) 2 20.0025 3 20.0025 4 20.0025

Au 06 ¶1:3 1997 File aIw: N231.dat AO COOO0o.O¶7I7-0200-0044 REV 00 ATTACIIHT III Page 11 5 20.0025 6 20.0025 7 20.0025 a 20.0025 9 20.0025 10 20.0025 11 20.0025

• 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 Z2.35Z0 0.0239 0.0238 0.0236 0.0235 0.0233 0.0232 0.0230 0.0229 0.0227 0.0226 0.0225 0.0223 0.0222 0.0221 0.0220 0.0218 0.0217 0.0216 Is  :

• of mod spec vol axial rnods (BC-9 to Stpt2-)

1 17.7300 Node I* node iheght (em) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 1 22.3520 0.0237 0.0236 0.0234 0.0233 0.0232 0.0230 0.0229 0.0228 0.0226 0.0225 0.0224 O.O223 0.0221 0.0220 0.0219 0.0218 0.0217 0.0216 18 s # of mod spec vol axial nodes (StptZ-9 to Stpt3-9)

Aug 06 11:43 1997 File Nam: 210.dat ISAOMOOOO.017IT-02 00-80004 anV Go ATTACUMIIII -3 Papo 12 I 1 17.7500  : lode , rlode height (ae)

I 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 6 20.0025 9 20.0025

• 0 20.0025 12 20.0025 12 20.0025 13 20.0025

¶4 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 0.0237 0.0236 0.0234 0.0233 0.0232 0.0230 0.0229 0.0228 0.0226 0.0225 0.0224 0.0223 0.0221 0.0220 0.0219 0.0218 0.0217 0.0216 la t f of mod mpec vol axial nodes (Stpt3-9 to Stpt4i)

¶ 17.7800 Node #, node height (es)

Z 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 a 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 0.0237 0.0236 0.0234 0.0233 0.0232 0.0230 0.0229 0.0228 O.0Z26 0.0225 0.0224 0.0223 0.0222 0.0220 0.0219

Aug 66 11:43 1997 Fflto Ke: M31.dat SSCOOOM -GI717.0200.00044 ME60 ATTACwIEWT III Page 13 0.0216 0.0217 0.0216

of h uaalh nys (80-C) 1 17.780 3 d , noehe t ()d z 20.0025 3 20.0025 4 20.0025 S 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 18 I # of bown axial nodes (Stpt2-I) 1 17.7800 Node 1, nwo height (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 1.960 2.914 3.568 3.920 4.114 4.235 4.317 4.374 4.413 4.441 4.467

Aug 06 11:43 1997 File NUae: 10j.dst *BA000000-01717.0200.0044 REV °0 ATTACHWNT III - Page 14 4.493 4.491 4.424 4.274 3.994 3.491 2.521 10  :

• of bunmi axial nodes CStpt39) 1 17.7300 Mode 9, node height (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.00Z5 6 20.0025 7 20.0025 a 20.0025 9 20.00Z5 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 13 22.3520 2.860 4.242 5.171 5.659 5.914 6.069 6.172 6.241 6.290 6.327 6.363 6.402 6.412 6.336 6.14" 5.765 5.057 3.651 1l  : I of bu"* axial nodes (Stpt44) 1 17.7800 N 4, node height (cm)

Mode 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 a 20.0025 9 20.0025 10 . 20.0025 11 ZO.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 9.011 13.191 15.676 16.7r 17.202 17.415 17.548

Aug 06 11:U 1997 File Hawe: 1231.dat *DACOOOOO .lr,7170200-0044 REV 00 ATTAWIENT 1II Page 15 17.643 17.?24 17.80V 17.916 13.074 18.240 18.251 18.015 17.288 15.489 11.216

• f hurnup axial nodes CStpt5-B) 1 17.7300 Node #, node height (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 a 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025

.15 20.0025 16 20.0025 17 20.0025 18 22.3520 9.147 13.388 15.903 16.999 1r.438 17.652 17.783 lT.879 17.961 18.046 18.155 18.316 18.486 18.501 18.265 17.538 15.722 11.386 18 s ' of bueup axlel nodes IStpt6-8) 1 17.7100 N Mode t, node helght (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 a 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 1$ 22.3520 11.872 17.269 20.291

Aug 06 11:43 1997 fiLe Name: 231.dmt *BAO0OOOO-01717-0200.00044 00 MEV ATTACHMENT III - Page 16 21.495 21.918 22.100 22.211 22.297 22.380 22.474 22.605 22.W8 23.038 23.117 22.944 22.210 20.108 14.640 18 s # of bznup axisl nodes CIOC-9) 1 17.7500  :.lode I, node height (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 e 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 13 22.3520 12.448 18.080 21.197 22.422 22.846 23.025 23.130 23.209 23.282 23.363 23.476 23.657 23.866 23.931 23.754 23.012 20.865 15.207 I1  : .F of burm* axial nodes (StptZ-9) 1 17.7800  : lode #, node height (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 a 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025

Aug 06 11:4 1997 File Ewme: KZ.dAt BRAO O -01717.020.GO044 3EV 00 ATIACIIENT III f Page 17 18 22.3520 15.644 22.930 26.949 28.637 29.306 29.614 29.7J6 29.896 29.978 30.054 30.149 30.297 30.444 30.403 30.041 28.980 26.213 18.837 18 c # of burmip exist nodes (Stpt3-9) 1 17.7800 lMde U. node heiht Ccm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 Z0.0025 16 20.0025 17 20.0025 IB 22.3520 16.965 24.AB2 29.214 31.035 31.759 32.086 32.262 32.371 32.450 32.524 32.619 32.765 32.909 32.858 32.463 31.320 28.344 20.313 18  : # of burnup axial nodes (Stpt4-9) 1 17.7800 oda #, node height (en) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025

Aug 06 114 1997 File Name: 231.dat *BADOOOOC-01717-200-00044 REV 00 ATTAMNET III - POP 18 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 20.334 29.730 34.732 36.782 37.565 37.889 38.050 38.145 38.218 38.294 38.399 38.564 38.733 38.705 38.304 37.049 33.645 24.063

Auo 06 11:56 1997 Fite Name: 127al.dat gUA000OOOI117-02O00-000" UV 00 ATTAChMUqlT IV - Page 1 1 K s This is not a pick-tP case Crystal River , unit 3  : Reactor Identifier a Prefix Identifier for reactor

"~grow iScale cross-gection library 3.94 s U-Z35 t onrilhment Ir U of L102 s er of U per useubly 208 2 Nuber of fuel rods In iisrnbly 1.4un s PIn-pitch In ass " ly (cm) 0.9362U s Fuel pellet diameter (cm) 0.95758 I Fuel rod clading 10 Ce.)

1.0922 2 Fuel rod cladding O (cm) 360.172 s Fuel stack height cm)

U No axial blanket fuel ZIIC-4  : Spacer grid material 0.008163257 VVol. frac. of mod. displaced by grlds ZIRC-4 s Fuel rod cladding material 640.0 s Avg. fuel rod cladding temp. (I)

Cladding materials other than ZIRC-4 rV  : Iluier of cladding ateralsi needed other than ZIRC-4 sAS2H material mixture waber for clad material below 55304 t Cladding mteriat for Cl's S2200.0 System pressure (psl) s Activate EPRA tracking

IF of radial zones In the standard Path I model 3 0.632U s Standard Path S model (input Card 20) 2 0.67310 3 0.81397 500 2.97599 3 2.99939 s of cross-section libraries per Irradiation step 5 sAS2H output print level 0.5 s Zae ush factor for XSDRNPR No SPECIAL llo special XSDRNPK control parameter specs.

2 2 I of insertion reactor cycles 0 Insertion reactor cycle Identifier s of stpts in cycle 0 s *tpt EFPD 0 s Length to Otpt Incalendar days 0 s Downtime at stpt 97.6 s Stpt EFPD 110.0 s Length to stpt in calendar days 15.5 2 Downtime at stpt 139.5 s Stpt [FPO 173.5 s Length to stpt in cilendar days 6.2 r Dointim at stpt 404.0 Stpt t EFPD 479.7 s Length to *tpt in calendar days

".4 a DoseAtim at stpt 409.6 s Stpt EF0 529.1 a Length to stpt incalendar days 4.9 Downtime at stpt 515.5 2 Stpt EFRD 64S.0 s Length to stpt in calendar days 7.6 s Downtime at stpt 75.0 s Days of downtime at EDC M.9 s Total cycle EFPD

'79 s Total cycle length In calendar days 27 2 Integer position of aueslaby In cycle 09 s Insertion reactor cycle Identifier 4 s f of stpts In cycle

• Stpt EFFS a Length to stpt In calendar days s Dontime at stpt 155.5 t Stpt EWFD 168.0 s Length to stpt In calendar days 2.146 z Downtime at stpt 219.0  : Stpt EFWO s Length to stpt incalendar days 53.125 s Dointime at ctpt 363.1  : Stpt EFPD

@ - r Aug 06 11:56 1997 Ff1.

t ama: N27I.dat BUAOOOOOO-1717.0200O00o4A4 UV 00 ATTACNHEU IV - Page 2 431.271 Length to stpt in Calendar days 1.625 s Dontil at stpt 55A0 :aYs of downtima at fEX 557.23  : Total cycle EUD 632.0 a Total cycle length fn calendar days 05  : Integer position of assembly in cycle Y Ftla for variable or constant irradiation step specs I a tlative insertlon cycle 1 Relative statepoint In insertion cycle 2 i Iumber of steps In statepoInt calculation 45.U 1510.73  : Step length (EFPD), Kid-step ppmb 43.8 1419.25 TStep length CEFPD). id-ste P pb 2 a Relative statepoint In insertion cycle I :NIumber of steps in statepoint calculation 42.2 1305.52  : Step length EFPD0). Kid-step ppab 3  : Relative stastpoint in Insertion cycle 4 :Numb E er of steps in statepoint calculation 66.05 1142.75  : Step length (EFP0), Kid-step ppmb 66.05 985.95  : Step tength (EFP0), Kid-step ppob 66.05 793.5  : Step tength (EFPD). Kid-step prb 66.05 588.91  : Step length tEFPD), Kid-step pb 4 a Relative statepoint in irserticn cycle 1 s uater of steps In *tatepoint calculation 5.6 4J4.53  : Step length (EFPD). Kid-step pprb 5  : Reloative statepoint in insertion cycle 2 Nauber of steps In statepoint calculation 52.95 416.34  : Step ltength tEFP0), Kid-step ppb 52.95 274.55  : Step length (EFP0). Kid-step pprb 6  : Relative statepoint In insertion cycle I :Nuber of steps In statepoint calculation 20.4 185.39 s Step length (EFPD1) Kid-step ppub 2 . Reloative Insertion cycle I :Relative statepolnt In Insertion cycle 4  : Nluer of stept In statepoint calculation 2.09 1647.0 a Step length tEFPD), Kid-step pxb 55.24 1593.9  : Step length (EFP0). Kid-step pb 50.74 1433.1 s step length (EFPD). *id-step ppmb 50.74 1359.0 s Step length (EFP0). Nid-step ppb 2  : Reloative stetepolnt In Insertion cycle 2  : luber of steps In statepoint calculation 14.09 1274.3 s Step length (EFP0), Kid-step pmb 46.11 1193.5 s Step length (EFP0), Kid-step Wppb 3  : Relative statepoInt in insertion cycle 3 s luster of steps In astepoInt calculation 36.07 1074.3  : Step length (EF10), Kid-step ppb 54.02 933 a  : tep length (EFPD), Mid-step prb 54.02 777.2 s Step tlnth (EFP0). Kid-step ppab 4 s Relative statepoint In Insertion cycle 3  : Muber of steps In ctatepoint calculation 64.71 5K.95 tstep length (EFP10) Kid-step pplb 64.71 388.60  ; Step tength (EFP0). Mid-step ppib 64.71 192.66 Step length (EFP0), lid-step pFb U8 s fof xistl modes In tCC forest 1 17.7800  : Mode , node height (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025

7 2 Page 3 Aug 06 11:56 1997 Fl , Name: x27TA.dot tAOOOOO0171 -0 00-0004 REV 00 g ATTACWMKIV 18 22.3520 RODDED 4  : utber of irradiation steps with CaU Inserted 1 i Iuter of axial section wIth CRA inserted in step I 2 I 12 r I Irut card 47 1 5 Nlber of axial section with CIU Inserted in step 2 21 21 171  : Input ard47l 1 s Wier of axial section with CRA Inserted In step 3 22 11 1 7 I tIput card 47l 1  : nuber of axial section with CU Inserted In step 4 23 1 1 71 7lnput ard 47t 1 i Nllber of different CA absorber material mixtures 7 US211 material mixture sumter for CA absorber 4 i Hurber of Isotopes or elements In the CRA absorber 47000 79.8 i SCALE Isotope ID* Isotope wtS 49000 15.0 SCALE isotope ID. Isotope wtX 48000 5.0 t tCALE Isotope 10. Isotope wtX 13027 0.2  : SCALE isotope ID. Isotope wtX 1 wutber of CIA designs 10.17 a  : C absorber density, CR clad AS2N mat. mix. number a  : umber of radial zones In Path 3 model with CRA Inserted 7 0.497E4 s Path 8 model CUl inserted CirVpt Card 47J)

S 0.50546 8 0.55880 3 0.63246 2 0.67310

.3 0.81397 500 2.90826 3 2.93113 3 0.497E4 a Path I model CUA removed (Input Card 47K) 3 0.50546 3 0.55880 _

3 0.63246 2 0.67310 3 0.81397 500 2.97599 3 2.99939 NO APSRA INSERTIOU HISTORY 18 s # of fuel ta¢p axial nodes (5OC4 to Stpt2-8) 1 17.7B00 Hoda 6. nod height (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 1016.2 1252.6 1369.3 1420.0 1441.9 1451.1 1454.7 1455.8 1455.6 1454.6 1453.3 1451.3 1447.6

Aug 06 11S56 1997 Prle Name: 27I.dat *UAOMOOO01717-0200.OOrA REV 00 AITACJONT IV - Page 4 1439.3 1421.0 1380.1 1284.3 1030.7 18  : f of fuel to* axial nodes dStp?-a to Stpt3-8) 1 17.7800 lode #* node height (cm) 2 Z.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 1016.2 1252.6 1369.3 1420.0 1441.9 1451.1 1454.7 1455.8 1455.6 1454.6 1453.3 1451.3 147.6 1439.3 1421.0 1380.1 1284.3 1030.7 18 # of fuel teW axial nodes (Stpt3-I to Stpt4-8) 1 17.7800 sade *, node height (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 e 20.0025 9 20.0025 10 20.0025 11 20.0025 12 Z0.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 1034.6 1227.6 1303.4 1326.2 1329.9 1327.4 1323.7 1320.4 1317.9

Aug 06 11:56 1997 File "aes: N27a1.dat gADOoo-Do*17l 74 200

- §OO44 fEV 00 ATTACRMEIVT -Y Page 5 1316.3 1315.6 1316.1 1317.2 1317.8 1314.5 1297.8 1239.2 1040.3 18  : # of fuel top axil. nodes (Stpt4-8 to Stpt5-S) 1 17.7100  : Bode, node helight (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 1034.6 1227.6 1303.4 1326.2 1329.9 1327.4 1323.7 1320.4 1317.9 1316.3 1315.6 1316.1 1317.2 1317.8 1314.5 t297.8 1239.2 1040.3 18 i f of fuel tetq axial nodks (StptS 8 to Stpt6-8) 1 17.7300  : Node f, node height (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 1044.3 1179.9 1221.6 1221.5 1212.4

Amg 06 11:16 1997 Fite Name: N27al.dat Ba6aOo0~1717*OZOO00-C44Y ItE 0 ATTAEMUT IV

• Page 6 1203.4 1196.6 1191.6 1188.1 1185.5 1183.9 1183.5 1185.4 1190.2 1197.6 1202.7 1183.2 1048.4 18  : k of fuel tow axial nodes (Stpt6-8 to EOC-8) 1 17.7800 Node t, node height (es)

N 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 1044.3 1179.9 1221.6 1221.5 1212.4 1203.4 1196.6 1191.6 1188.1 1185.5 1183.9 1183.5 1185.4 1190.2 1197.6 1202.7 1183.2 1048.4 1 a I of fuel tet axial ros (*WC-9 to Stpt2-9) 1 17.7800 :Node f, node height (cm) 2 20.00ZS 3 20.00Z5 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 1007.6

4 Au0 11:56 1997 Fite Name: U2761.dat SIAOoo0O.1717-0 200-NO0 REV go ATTACRSENT IV -Page 7 1186.3 1259.5 1295.4 1311.9 1318.3 1319.7 1318.4 1315.8 1312.4 1308.9 1305.1 1299.9 1290.9 1274.7 1246.6 1198.1 1062.8 18  : # of fuel top axial nodes (Stpt2-9 to Stpt3-9) 1 17.7800 t.Uode I. node heilht (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 1021.4 1178.2 1242.0 1265.2 1271.7 1Z71.2 t268.3 1264.7 1261.2 1258.2 1255.9 1254.4 1253.2 1250.4 1243.3 1226.6 1186.6 1064.9 18 i I of fuel top extat nodes (Stpt3-9 to Stpt4-9) 1 17.7800 Node.# node Mkheit (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025

Aug 06 11:56 1997 Fite Name: 027st.dat UBAOOOOOO-01717-02000OO44 MEto ATTACUNEN IV. -page a 16 20.0025 17 20.0025 18 22.3520 1044.1

¶171.1 1214.3 1225.4 1222.8 1217.2 1211.4 1206.5 1202.9 1200.4 1199.2 1199.5 1201.3 1203.4 1203.3 1196.0 1167.8 1061.3 1a  : I of mod pec vol axial nodes (SCC-8 to Stpt2-8) 1 17.7800  : Mod I node helglt (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 13 20.0025 16 20.0025 17 20.0025 18 22.3520 0.0234 0.0233 0.0232 0.0231 0.0230 0.0228 0.0227 0.0226 0.0225 0.0224 0.0223 0.0221 0.0220 0.0219 0.0218 0.0217 0.0216 0.0216 18 t # of mod spec vl axal nodes (Stpt2- to Stpt3-8) 1 17.7800 s Node i, node height (cm)

Z 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025

Aug 06 JIM5 1997 Ffito lame: U27al-dat £u000000.O01717-020-00044 REV 00 ATTACUE:IT IV - Page 9 12 20.0025

r. 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 0.0234 0.0233 0.0232 0.0231 0.0230 0.0228 0.0227 0.0226 0.0225 0.0224 0.0223 0.0221 0.0220 0.0219 0.0218 0.0217 0.0216 0.0216 1l s 6 of mod spec vol axial nodes CStpt3-I to Stpt4U8) 1 17.7soo sllode #, node height (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 to 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 0.0233 0.0232 0.0231 0.0230 0.0229 0.0228 0.0227 0.0226 0.0224 0.0223 0.0222 0.0221 0.0220 0.0219 0.0218 0.0217 0.0217 0.0216 18 s # of mod cpec vol axial nodes (Stpt4-8 to Stpt5.-)

1 17.7500 s Node #U node height (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025

Aug 06 11:S6 1997 file amaw: NZT .dat 1BA000OM.O1717-020-0ON4 MIv 00 ATTACUWET IV - Page 10

• 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 0.0233 0.0232 0.0231 0.0230 0.0229 0.0228 0.0227 0.0226 0.0224 0.0223 0.0222 0.0221 0.0220 0.0219 0.0218 0.0217 0.0217 0.0216 i8  : 6 of mod spec vol axial noeks (Stptd- to Stpt6-8) 1 17.7800 :ode , node height (cm) 2 20.002i 3 20.0025 4 20.0025 5 Z0.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 Z0.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 0.0233 0.0232 I 0.0231 0.0230 0.0229 0.0225 0.0227 0.0226 0.0224 0.0223 0.0222 0.0221 0.0220 0.0220 0.0219 0.0218 0.0217 0.0216 18 * # of mod spec vol axIal nodes (Stpt6-I to EOC-S) 1 17.7800 z Mode f, node height (em) 2 20.0025 3 20.0025

Aug 06 11:56 1997 Fite Nanz 92701-dat 1A00000-o1717 40200400044 liv 00 ATACUCNT IV - 'Page 11 4 20.0025 I 5 20.0025 6 20.0025 7 20.0025 a 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 IT 20.0025 18 22.3520 0.0233 0.0232 0.0231 0.0230 0.0229 0.0228 0.0227 0.0226 0.0224 0.0223 0.0222 0.0221 0.0220 0.0220 0.0219 0.0213 0.0217 0.0216 18  :

• of mod spec vol axial nodes LOC-9 to StptZ-9)

I 17.7800  : Node U, node height Cc.)

2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 *20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 0.0238 0.0237 0.0236 0.0234 0.0233 0.0231 0.0230 0.0228 0.0227 0.0226 0.0224 0.0223 0.0222 0.0221 0.0219 0.0218 0.0217 0.0216

4 2 00 000 4 ATTAt1DEU IV -Page 12 Aug 06 11:56 1997' File Nam.e 1 271 1dat 31Aaaaa00.011l7 0 - UEV 00

.- 15  : # of Sd spe vot axiatl nodes (Stpt2-9 to ltpts-9) 1 17.7500 :de td (c) height 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 0.0238 0.0237 0.0235 0.0234 0.0233 0.0231 0.0230 0.0225 0.0227 0.0226 0.0224 0.0223 0.0222 0.0221 0.0219 0.0218 0.0217 0.0216 18  : j of nod spec vat axial nodes (Stpt3-9 to Stpt4-9) 1 17.7800 a lode I, node height (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 la 22.3520 0.0237 0.0236 0.0235 0.0234 0.0232 0.0231 0.0229 0.0225 0.0227 0.0226 0.0224 0.0223 0.0222 0.0221

AO06 11:56 1997 Ffile saft; K2701.dt *3A00 It~ 0

.01O717-020O-0OO44. ATTAIEN'T IV - Page 13 0.0219 0.0218 0.0217 0.0216 18 z I euwnP of axial nodes (W0C-6) 1 17.7800 Node #, node height (c) 2 20.0025 3 20.0025 4 2D.0025 5 20.0025 6 20.0025 T 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.O25 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 Is 22.3520 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 la  : # of burnup axta nodes (StptZ4S) 1 17.aoo  : Io nade height (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 1.405 2.399 3.013 3.346 3.530 3.642 3.713 3.762 3.794 3.814

Aug 06 11:56 1997 Fite Nuwi: II27aldat IRA000000.01717 4 20 0-00044 ftV 00 ATTAMWNET IV -page 14 3.82 3.817 3.787 3.717 3.582 3.327 2.814 1.694 18  : # of Wrnu axial nodes (Stpt3-s8) 1 17.7800 lode U, nod height (c) 2 Z0.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 2.054 3.474 4.335 4.777 5.015 5.153 5.240 5.298 5.337 5.362 5.374 5.370 5.337 5.255 5.086 4.749 4.044 2.453 16  : U of boufV axial nodes (Stpt4-8) 1 17.7800  : Node U node height (cm) 2 Z0.0025 3 Z0.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 6.590 10.558 12.64 13.524 13.899 14.070

Lug 06 11:.56 1997' File mane: himi-dlt UA000000.@171? 40200-CM04 is CO AtTACUNMM IV.-page 15 I 14.162 14.225 14.276

¶4.322 14.367 14.407 14.426 14.382 14.184 13.598 12.002 7.661

. of burq axial nodes Cttpt5-i) 1 17.7300 s Nock U*node height (cm) z ZO.0025 2 20.0025 4 20.0025 5 20.0025 6 20.0025 76 20.0025 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 6.691 10.712 12.821 13.707 14.083 14.253 14.345 14.408 14.459 14.505 14.551 14.593 14.614 14.572 14.376 13.789 12.178 7.782 18 s # of bunip axial nodes (Stpt6-8) 1

• 17.730 :Node node height (cm) 2 20.0025 3 20.0025 4 ZO.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 8.170 13.771

Aug 06 11:56 1997 File Me: H27kta.t huA000O Olyly-oz7-020000 tEV 06 ATTAcHM TV - Page 16 16.264 17.229 17.593 17.739 17.812 17.866 17.915 17.966 18.022 18.082 18.131 18.129 17.977 17.385 15.549 10.140 18 t of burqipaxist noeks (5OC-9) 1 17.7300 t Node U*node height ten) 2 Z0.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 a 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 Z2.3520 9.212 14.406 16.970 17.947 18.309 18.450 18.518 18.565 15.607 18.645 18.692 18.738 18.775 18.766 18.610 18.013 16.139 103.60 18  : I of bzrmip axial noesi Cstpt2-9) 1 17.7800 g lode I, node height (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 a 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.025 15 20.0025 16 20.0025

Amg 06 I1:%6 1997 Fite Name: Ni*61.dat BRA00000001717-0200-00044 kiv @0 ATTACUMEN IV - Page 17 17 20.0025

! 18 22.3520 12.054 19.265 22.933 24.458 25.110 25.408 25.565 25.660 25.724 25.771 25.809 25.831 25.832 25.722 25.369 24.412 21.854 4.473 18 5 Of Wbimp exisl nodes (Stpt3-9) 1 17T.700 :odel, node heglht (cm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 20.0025 12 20.0025 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 18 22.3520 13.297 21.246 25.274 26.951 27.664 27.985 28.149 28.246 28.312 28.361 28.403 28.439 28.438 28.324 27.941 26.895 24.114 16.054 18 i # of burmp axial nodes (Stpt4-9) 1 17.7800 :Mode # node height'tCm) 2 20.0025 3 20.0025 4 20.0025 5 20.0025 6 20.0025 7 20.0025 8 20.0025 9 20.0025 10 20.0025 11 .20.0025 12 20.0025

Aug 06 11:56 1997 FIle Name: N271i.dat BOMAOOO-01717.0200-00044 UEV 00 ATTAClMNT IV Page 18 13 20.0025 14 20.0025 15 20.0025 16 20.0025 17 20.0025 l8 22.3520 16.449 26.143 30.937 32.867 33.64 33.966 34.117 34.206 34.270 34.329 34.392 34.462 34.506 34.432 34.053 32.897 29.673 20.039

AM 06 13:30 J997 Fit* Name: ftgttltt Aug06 ~gst MEV 0 3~3197FleU~e IAOOO-D1717IMMa000 ATTlAtUMET IX Page I Coputer Tape Backup Number of File Date File Size File Type File Name File Nlae Print Pao"s (Output) (Byte$) (Foret) 104/CJ3aD0o1DCO8T000AC08T097.sut dl.Xfl 30 Aug 6 1997 141392 ASCII l04/CR3A04olDOc08§T97AC08T139.cut W R.XQ 31 Aul 6 1997 unT ASCII 304/CR3AC4UO1D CO8T139ACOST404.tut aI.Xf3 32 Aug 6 1997 148978 ASCII 14J/CW04NOlvCG8T404ACO8T409.eut 1.Xf4 32 Aug 6 1997 15338 ASCII 104JCR3AO4EO1DCOrT4O9ACcoTSI5.cut et.Xfs 33 Aug 6 1997 1554 ASCII N04/CR3AO4NOiDCO8TSiSAC09TOOO.cut *I.Xf6 2 Aug 6 1997 134334 ASCII 904ACR3A04902DCO8TOODAC8T097.cut I.Xt7 31 Aug 6 1997 144661 ASCII K04ICR3A04N02C08T097AC08T139.eut l

.Xfs 32 Aug 6 1997 150352 ASCII K04/CR3AO4U02DCDBT139AC8T4G4.cut *1.Xf9 33 Aug 6.1997 152650 ASCII 504/c33A04N02DC08T404AC08T409.cut sIX.flO 32 Aug 6 1W7 155170

• ASCII N04/1CA04N02DC08T409AC08tS15.eut *IX.fil 34 Au 6 197 15885t ASCII N04/0304N2DCO8t515ACO9TOW cut sIX.f12 29 Aug 6 1997 136997 ASCII 304/CR3A04NVDCO8TOOOACOWT97.cut aIX.fl3 31 Aug 6 1997 145491 ASCI I 04/CR3A4N53MC08T097AC0T139.cut aIX.f14 32 Aug 6 1997 151413 ASCII 1041/CAKN4I3DCOBr139AC08T404.Cut Xf1S 33 Aug 6 1997 153301 ASCII 041CR3A W03DCM8T404AC08T409.cut *IXfl6 33 Aug 6 1997 156914 ASCII b04/C13A04UO3CO8T409AC08T515.cut XIfl7 34 Aug 6 1997 159337 ASCII HK/C3AO4NO3DC08t515ACO9IOOO.cut SIX.f1 29 Aug 6 1997 137573 ASCIl MK0CRUA041040C08U0TAC08T097.cut AIX.f19 31 Aug 6 1997 143M4 ASCII NK/CR3A04l04DCOTO@97AC0T39.cut *IX.f20 32 Aug 6 1997 31579 ASCII KU/CIA04104C08T139ACOT4U.eut 5X.f21 33 Aug 6 1997 153965 ASCII K04/CR3A4040CO8T404ACOT409.cut *IX.f22 33 Aug 6 1997 136914 ASCII N04/CA3A4NUO4CCOST49ACOTIS.cut IX.M23 34 Aug 6 1997 159835 ASCII N04I/CR04M0UDCO8t5ISAC9TOOO.ut &lXf24 29 Aug 6 1997 137661 ASCII N04C3AUNOUDCOSTOOOACOTO9.cut *IX.t25 31 Aug 6 1997 146133 ASCII 004/CR3A04N050C08T097ACOtT139.cut a*X.f26 32 Aug 6 1997 151662 ASCII 04/CR3A04X050C08T132AC08T404.cut IX.fZ7 33 Aug 6 1997 154214 ASCII N04/C33A0KU050C08T404ACOT409.ut SIX.f28 33 Aug 6 1997 156914 ASCII K04/CR3AUO4N5DC8T409ACO8TSIS.Cut aIX.f29 34 Aug 6 1997 159835 ASCII KO4/CR3AD4NO5DCO8T5SACO9TOOO.cut aX.f3O 29 . Aug 6 1997 137661 ASCII HKO4C3AUONCCOSTOOOACOSTO97.ut aIX.31 31 Aug 6 1997 14626 ASCII HN/3AU10460COMT097AC08T139.cut IX.f32 32 Aug 6 1997 151745 ASCII N04/CR11 M060COST139AC08T4.cut lX.f33 33 Aug 6 1997 154214 ASCII HN4/C3AU06DCOaT404ACO8T409.cut IX.f34 33 Aug 6 1997 156997 ASCII 10/CR3A041060DCOT409ACOT515.cut IX.f35 34 Aug 6 1997 159835 ASCII N041CA04511060C08TS15AC09tOOO.cut aX.f36 29 Aug 6 1997 13757J ASCII NU/cUI3A04N07bC08TOOAC08T097.cut SIX.f37 31 Aug 6 1997 146299 ASCII H04/Cl3A04K07oCOsT097ACosT139.eut IX.f38 32 Aug 6 1997 151745 ASCII K04/C33AKO4070COtT139AC08T40.cut IX.f39 33 Aug 6 1997 154214 ASCII K04/C53A04N0CO0T404AC98T409.Cut sIX.f40 33 Aug 6 1997 156997 ASCII (04/03A04U070C08T409AC8T515.9ut aIX.f41 34 Aug 6 1997 159752 ASCII H04/CR3AO4NOZDCO8TSI5AC09TOOO.Cut aIX.f42 29 Aug 6 1997 137578 ASCII H04 1 CO8TOODACO8T097.cut IXt43 31 Aug 6 1997 146382 ASCII 104/C3A0NO08CO3T097AC08TI39.cut *IX.f44 32 Aug 6 1997 151745 ASCII 04IC33A04K08DC08T139ACD8T404.cut *IX.f4S 33 Aug 6 1997 154214 ASCII HNOCA0U084 C08T404ACO8t409.cut aIX.46 33 Aug 6 1997 156997 ASCII WX/CR3AO4N080CT409Ac08T5.cut GIX.f47 34 Aug 6 1997 159752 ASCII K04ICR3AO4NG8DCOTSi5ACO9TOOO.*ut SXIfU4 29 Aug 6 1997 137378 ASCII H04f3A4UN9CO8T800ACO8T097.cut IX.49 31 Aug 6 1997 14382 ASCII UO/C33A0409C8T097ACO8T139.cut axX.f50 32 Aug 6 1997 15345 ASCII N04/CIA4U 09DCW8T139AC08T404.ut aIX.f5l 33 Aug 6 197 154297 ASCII H104M/3A04N OCT40UAC8T409.cut a*X.f52 33 Aug 6 1997 156997 ASCII N04/C53A04NO9DC08T409AC08TS15.eut aX.f53 34 Aug 6 1997 15972 ASCII 104/C33A4OU C08T515ACOW0 0.cut sIX.f54 29 Aug 6 1997 13745 ASCII 10VCRU4NIODCOTOOSAMCUTN.cut a*X.f55 31 Aug 6 1997 14382 ASCII U04/CR3AUNODC08T097AC08T139.cut .*S1f6 32 Aug 6 997 152345 ASCII 1041C3A04N100C08T139AC08T.cut EIX.ff7 33 Aug 6 199 154297 ASCII N04/Ck3A041100C08T404AC08T409.cut a2X.f38 33 Aug 6 1M7 15697 ASCII U04/C53A04NlODC08T409AC08T515.cut aId 59 34 Aug 6 1997 159752 ASCII NU4/C03AOUNICDCOOTSISAC9TOOO.cut IX.f60 29 Aug 6 1997 137495 ASCII 104/CR3A4xIlDC1OTOOOAC8TO97.cut aIX.f6t 31 Au 6 1997 146382 ASCII U04/C3A04111tC08T097ACT139.cut *IX.t62 32 Aug 6 1997 153343 ASCII K04/C3AQ04N110COT139ACO0T404.cut .IX.63 33 Aug 6 1997 15427 ASCII H04/C23A04Ul10C08T404AC08T409.cut aIX.f64 33 Aug 6 1997 156997 ASCII O4ICR3A41IDCO8T49ACOBTSIS.cut aIXf65 34 Aug 6 1997 159752 ASCII

AM 06 15:30 j9S File gu: osglat SB1A370D0-017¶17020o000044 REVGO LTAETX - P49e 2 AT O4lCR3AU 515DC03T5I3AC WTO.a4 .IX.f66 29 A 6 97 137495 ASCII

.04,CRA"012D0COTG CMT0097.on .IX.f6J 31 Av 6197 1982 ASCII 04/CW04N12DCO8TD97ACO8TI39.ut

• iX.f6C 32 AM 61997 1s234 ASCII K04/cR3AwoUl2DCIT8139AC08T404.cUt X.if69 33 Aug 61997 154297 ASCII N"/C3A04N12CWT4WAC0T4D9.eut SI-f7O 33 Aug 61997 1570 ASCII K4ICRUAO04ZDCO&T409ACO3T55 .Sut stK.f71 34 Aug 6 1997 lSY592 ASCII HU/0/3A44N2DC0T5I5ACO9TOcut 8Ix.-f2 29 AM 6 1997 137412 ASCII UO4ICR3AGMI13 OCOTOOOACST097.cut

• IX.f7 31 AUg 6 1997 146216 ASCII N04/C3IA041130CO4T097ACO5T139.cut *iXf74 32 Aug 61997 151745 ASCII No4/CW3A04N13oC08T139ACOBT404.cut asX.f75 33 Aug 6 1997 154297 ASCII 04=/Ct3AD4113DC08T404ACG8T409.Cut X.1f76 33 Aug 6 1997 1570s0 ASCII 104/CR3A041l3DCO684D9ACO8TS15.Cut IX.f77. 34 Aug 6 1997 159752 ASCII KU4/CRUAO4MM30COSTSISACO9TMOO.Cut SLK.OS 29 Aug 6 1997 137412 ASCII KO4/CR3AUON04DCO8TOOOACO8TO97.cut a*X.f79 31 ALg 6 1997 146133 ASCII N04/CRA04N140CO&TDV7ACW8T139.cut *IX.fa 32 ALW 6 1997 15164Z ASCII KO4ICR3AO4NU4DCOMT39ACOBT404.Cut Il.f8l 33 AWu 61997 154297 ASCII N04/CRcA04N1UCO8T404IACOT409.cut *IX.f82 33 ALu 6 1997 157C60 ASCII N04ICt3AC4N140C0T409AC08TSlS.cut aK.fJ3 34 Aug 6 1997 159e35 ASCII N04/R3Ao4M4DCOST5ssACw DOOO.Sft *tX.fU4 29 Aug 6 1997 137412 ASCII f04/CR3304315SDCU O T097.tt aIX.fS5 31 Aug 6 1997 145967 ASCII 104/CR3A04N15DC08T0978AC0T139.uCt GIK.f86 32 LU 6 1997 151579 ASCII nK0/CR3A04M1SOC08W139AC08T404.cut OIX.f67 33 Aug 6 1997 154214 ASCII K04/Cct3AO4N15CCO8T404ACT409.cut alLfs 33 AUg 6 1997 157080 ASCII

• 0/Ct3AO4N15DCO8T409ACO8TS5c.Mut XM.f89 34 Aug 6 199 159J55 ASCII

04/CN3At4NI5DCO8TSSAC09TOOO.cut alX.f90 29 Aug 6 1997 137495 ASCII N04/CR3AO4Ni6DCOBTOOOACO8T97.Cut AIXf91 31 Aug 6 1997 145801 ASCII NO4/CR3AGU116DC8T1D97ACO8Ti39.eut mIX.f92 32 Au 6 1997 151579 ASCII N04/CR3AO4N14C08TU39AC08T404.cUt aIX.f93 33 AL 6 1947 1S3799 ASCII M04/CR3A04N16DC08T404ACO8T409.ut SIM.f94 33 Aug 6 1997 156997 ASCII N04/CR3AO416DCOWT409ACOT515.cut aIX.f95 34 Aug 6 1997 159669 ASCII K04/CR3AO4lKDCO8TSISAC09TOOO.CUt WIXf96 29 Aug 6 1W7 137329 ASCII 0/CPJAO4N1T7COWTOOOCM T097JcUt *!X.f97 31 Aug 6 1W7 14319 ASCII HOK/C33A04N17bCOT8097ACOT139.cut uIX.f98 32 Aug 6 1997 151103 ASCII N04/WA041N17DCO8T139ACW8T404.cut uIX.f99 33 Aug 6 1997 153131 ASCII H04/CM3A0417TC8T404ACOT409.cut aXf.100 33 Aug 6 1997 156665 ASCII N04/CR3AO4NI7bCO8T409ACO8TSIS.Cut 4IKI.101 34 ug 6 1997 159171 ASCII 41/Ct3A04117DC08TS1SACO9TOOO.cut aIXf.102 29 Aug 6 197 137097 ASCII 304/CR3A54Ni8DCUTODOOACO8TO97.cut aIXf.103 30 ug 6 197 141811 ASCII Ho4/CR3A0MtI0DC08T097AC08T139.cut aIXf.104 31 Au 6 197 147071 ASCII 304/CR3A0641,DCOaTI39ACOBT404.cut aXI.105 32 Aug 6 1997 149535 ASCII K04/Ct3A04N11DC08T404ACOOT409.cut 4Xf,106 32 Aug 6 1997 152889 ASCII 104/CR3A04N18DCOWT409ACOT5IS5.CUt 41Xf.107 33 Aug 6 1997 155747 ASCII 04/CN3A4a18DCOTSISACO9T0OO.Cut uiXf.10 28 Au 6 197 13414 ASCII 304/CR3AO7NOIDCO9TOOOACO9TIS.cut cIXf.109 36 Aug 6 t997 168496 ASCII X04/C3A07M010DC09T15aACM219.cut IXf.110 29 Aug 6 1997 137061 ASCII N04/C33A07N01DC09TZ19AC09T363.Cut IXf.111 36 Aug 6 1997 16921 ASCII H04/C13A07)IO2DCMTOOOACD9T1SS.cut *IXf.112 36 Aug 6 1997 171243 ASCII W4/CAf7M02DC09T158AC09T219.cut dIXf.113 29 Aug 6 1997 139306 ASCII KG4/CUA07kCQ9T219AC09T363.cut clXt.114 36 Aug 6 1997 17222 ASCII M04MMC33A073130C09 AC09?158.Cut - *Xf.115 37 Aug 6 1997 172409 ASCII II4/CR3A07X03DC09T1SACWT219.cut clXf.116 30 au 6 1997 140332 ASCII N04/C1A07Th03DC9T219ACT363.cut adXf.117 36 Au 6 1W7 17339 ASCII V04/C3A07V104DC9TOOOAC09T13.cut aIXf.115 37 Au 6 1997 1O730 ASCII 104I/CRA07W040CMtIS1ACOM219.cut atXf.119 30 Aug 6 1997 140684 ASCII 104/12A073040C09T219AC09T363.eut alif.120 36 Aug 6 1997 173554 ASCII I04/C13A071O1DC09TOOOACW9T150.cut cIXf.121 37 Au 6 1997 173073 ASCII 904lA3A07I05DC09T153ACOt219.cut uIXf.l2U 30 Au 6 1997 140684 ASCII ND04/CI3A071150C09T219AC09T363.cut aIXf.123 37 Aug 61997 m63 ASCII 9041C3A0W060C09TOWMAC09I15B.cut aXf.124 37 lug 6 1997 173239 ASCII 041C33A0R706DC09r15&C09t219.cut 1Xt.125 30 AuL 6 17 140U4 ASCII V04/CI3A07N06MC09M219AC091363.Cut a!Xt.126 37 Aug 6 1997 173637 ASCII 104/C3AMOMhO7CWTOOOACWTISO.cut aiXf.127 37 aug 6 1997 1239 ASCII 04/CU3A071070C09T1SUAC09T219.cut aIXf.128 30 Aug 6 1997 1406 ASCII 304/Cl3A0707DC09T219AC09T363.cut alXf.129 37 Au 6 197 17637 ASCII I C040L7KC09TO000AC09t1S8.cut aIXf.130 7 aug 6 1997 173239 ASCII 1104/CR3AlOa8DC091TSACO9219.eut aIXf.131 30 LW 6 1997 14064 ASCII U04/C3A071D80C09M19AC0973M3.cut *IXf.132 37 Aug 6 1997 173637 ASCII 904/CRUA7N09OC09TOOOAC09715.cut aIXf.133 37 Aug 6 1997 173239 ASCII 104/CR3A07T09DC09T1S8AC09T219.cut dIf.134 s0 Aug 6 1997 140U ASCII N04ICR3A07UWhDC09TZ19AC09TS63.cut aIXf.135 37 aug 6 1997 173637 ASCII

7 17 Aug 06 13:30 19" File NWW3 witilit SAFA0001 -0200.000 KEY CO ATTACWr Ii - Pa.e 3 N04Icu30711100c09ooC097153.tut &11f.136 37 Amg 6 1997 17332 ASCII IIOUC13A07K1Oc9T158C09210.ut aiXf.137 38 AMg 6 1997 Ina=

140684 ASCII K04ICt3AD7M1O~c09T219AC09wU3.ft sixf.138 37 AAg 6 1997 173637 ASCI I

I~f .139 37 A4u 6 1997 ASCII g04/CKWA7R¶¶o=W9ToC9Ti53.tut Aug 6 1997 N04/CRUOMD79¶C09T15ACM09T29.ut .111.140 30 ASCII Aug 6 1997 K04/CL3A07WI11COMT19AC09lW 63CUt slxf .idI 37

¶73239 ASCII M0/CR3AO7N2DCO9TMUOC091153-cut mlxf .142 37 Aug 6 1997 ASCI I aixf.143 30 Aug 6 1997 140684 ASCII N04/CR3AO7HI2DC09T1S8AC09TZ19.cut Aug 6 ¶997 173637 No4IC,3A8T12Dc09T219Ac09T363.cut .I2f.14" ASCII H04ICa3A57N13DC09TWU0C09T158.CUt aIxf.14s 37 Aug 6 1997 173239 ASCII K04/c23AO7M130CD9T158ACO T219.cut aIxt.¶467 30 AMg 6 1997 140684 ASCII M04It3071113DC09T219ACO"MA3.Ut al1t.1' 37 Aug 6 1997 173637 ASCII R04/CR3A0TJI4DCMO9OOA0A9T153.5Ut aI1f.148 37 Aug 6 1997 173156 ASCII

• Ixt.149 30 km Aug 6 197 ASCII a04/cR3Ao7NI4DCO9TIS8ACO9TZ19.cut 1737 w04/ca3A07M140c09T2I9Ae09T363.eut 6111.150 37 Aug 6 1997 ASCII M/0A/3A7M15 MDcOCTOAC09TISB.cut S111.15 37 Aug 6 1997 ASCII 30 140684 ASCII uo4/CK3A07V5DC09T158AC09T219.Cut mlIif.152 36 Am 66 1997 173554 ASCII K0OWRUAMIS1DC09T219AC09M6.Cut aIxfi.¶5 37 Aug 6 1997 1997 172737 ASCII K04/Ca3UDINUDC09TO00Ac09t15.ut a111.154 Aug 140518 30 ASCI I KU/0R3A07VI60CV9T1S8Ac09T19.CUt aI1f.155 36 Aug 66 1997 1997 173305 ASCII H04/CR307II15OC09T219AC09W6.cut slXf .156 171907 Ho4ICE3AO7MI7DhOMOGTACMIS18.cut alxf .157 37 Au 6 ¶997 ASCII Ho4/CIC3A7N17DcO9TIS8AC091219.eut .11f.158 29 Au 6 1997 13985 ASCII U04/CRUA0T1?DC09T219ACO9T363.cut 6lii.159 36 Au 6 1997 172554 171387 A5CI I ISM98 169662 ASCII H04/CR3A07180C09M00AC0915A.Cut a11f.160 36 Am 6 1997 17255 H041CL3A7NMMO9T¶5AC09T219.Sut 6111.161 29 AM 6 1997 ASCII N04/C13A07N18Oc09T219AC09T363.cut aItf .162 36 6 1W7 ASCII Computer Tap. Backup Number of File Date llte size Film Type file NNWe P1fItNeW Print Pages toutput) (ByteS) (Format) aI1f.163 30 Am 6 1997 141226 ASCII MU2Ca3A¶2N010COM8 CT097A0TZ.cut aIllf.164 31 Aug 6 1997 146925 ASCII N12/Ca3A12N010C08T139Ac087404.eut aIxf.165 32 Am 6 1997 14897 ASCII HNI/CRA¶2010CO8TW0ACOSUM0.eut sixf.166 32 Au 6 1997 153328 ASCII MUCIMUA¶2N0DCOBT409ACOMTS1.Cut mI1f.167 33 Aug 6 1997 155771 ASCII NUMUItA1VO0DM78515AC09T000.eut SIMMS16 28 Au 6 1997 1457 ASCII 1112/c3A12M02DC081000ACT097.eut a11f.169 31 Au 6 1997 ASCII

• 12/Cat3A12M02DC08T097AC08T139.Cut a11f.170 32 Lu 6 1997 150269 ASCII MU1ZCK312NO2DCOST139ACo8T404.eut alXf.171 33 Aug 6 197 15Z567 ASCII NI2/CR3A1202DC08T40AC0T409.cUt a11f.172 32 Aug 6 1W7 155004 ASCII NI2/CR3A12N02DC08T409AC08T515.cut al1f.173 3' Aug 6 1997 158858 ASCII NI2/Ca3A1ZN0ZDC0T5¶5AC09T000.eut alxf .174 29 Aug 6 1997 136997 ASCII NUIZCNARUMUDCOSTOOOACOST097.cut a111.175 31 Aue 6 1997 145408 ASCII atxi .176 32 Aug 6 1997 151269 ASCII NIZ/CR3AI2NM30C8T09A=0T¶39.cvt 153301 N12/cR3A12N03CCOT139ACOST404.cu.t £111f.177 33 Aug 6 1997 ASCII aixf.178 33 Au 6 1997 156748 N12/cU3A12NMC08140AC08T409.cutt ASCII N1¶2/C3A12M03CWOT409ACG8T515.cut: 6111.179 34 Aug 6 1997 159254 ASCII MU2CKWU1M03W0T511SA009TOCcut 6111.180 29 Aug 6 1997 137578 ASCII sixf.131 Au 6 1997 145U88 U1Z/C23A123I04C08T000ACG8T097.cvt 31

¶51579 ASCII N12/CR3A12N04DC08T097AC08T139.eut sillf.182 32 Aug 6 1W7 ASCII a11f.183 Lu 6 199 153 0 NI2/CR3A1IN04DC08T139AC08T404.aat 33 156914 ASCII NUK WUMCM1UDUCU8T0400T409.eUt a11f.181. 33 AuG 6 1997 ASCII mlxf .185 34 Au 6 1W7 159669 II¶/CRAUUN040CWT409ACOST515.ctt 137661 ASCII MU2CN3AIZI04CV8TS1SCO9TOO~octi~ aixf.186 29 Lu 6 197 ASCII NI2/CR3A12N05DDc08T000AC08T097.cut .111f.117 31 Aue 6 1997 145967 ASCII mlxf .188 Aug 6 1997 151579 NiZC2IcUA1N05DC08T097AC08T¶39.cut 32 ASCII NII/CR3A12JI05D08T139AC08T404.cut 411f.189 33 Aug 6 1997 153882 ASCII sixf.190 33 Au 6 1997 156914 NI2/CR3A12N05DC08T404AC08T409.Cut ASCII NIZ/CR3A1I1050DC08T409AC081SIS.Cut 4lxi.191 3 ' Aug 6 1997 159835 ASCII N CKU2~312iI05DC0T51IAM 9T00.eUt &11f.I92 29 Aug 6 1997 137661 ASCII alXf.193 Aug 6 1997 14617 u12/Ca3A1206Dc0T000AC08T097.cut 31 15166Z ASCII MU2CR3A12060C8T097ACOST139.eut alXf.194 32 Auo 6 1997 ASCII 4111.195 Au 6 1W97 ¶53965 M1IUCRUA1N060C0T139AC08T40.sut 33 156914 ASCII E1Z/CRA1ZN06COBT404AC08T409.Cut Glxf .196 33 Aug 6 1997 ACI I c12/CKU31ZX06o0G8T409ACGMIS5.cUt *lf.197 3' Ago 6 1997 159752 ASCII N1ZCKR312N06DC08515ACOMT00.Cut o11f.198 29 Aug 6 1997 137661 ASCII

• Ixf.199 Au 6 1997 146133 NIZ/CR3AI2NM7DOBTOOOAC08TO97.eut 31 1S166Z ASCII H¶2,CAI2N70C00T97ACO8T139.cut oi1f.200 32 Au 6 1997 ASCI I

4 Aug 06 13:30 199 Fit* NW: mogtist AIADOO-01717-0200.0004 REV s ATTACMIe TX - pag 4 K 12/C3At2j0M7DC08T139AC08T404.cut alXf.201 33 Ag 6 1997 15408 ASCI I U12ICU2A2IIO7tCOST404AC0ST409.eut *If.202 33 Aug 6l9T 15614 ASCII 12/ 107COBST409ACT515.Mt ulXf.203 34 au 6 1997 15932 ASC NIZAK12NOt0COBTSIlC0ON.cut *IXf.2m 29 AUG 6 9 137661 ASCII N12/CU3A¶2NO8DCO8TOOOACO097.cut GlXf.5 31 Au 6 1997 14133 ASCII u12/CZt3A2N0DC08T097AC08T139.cm vlXf.Z06 2 A 6 199 151745 ASCII u1VZ CaARU Uo2COT139AC087404.ou *sXf.207 33 Lug 6 1997 11 ASCII U12/CRJ3A12NC0ST404AC08T409.crt .IXf.Zw 33 Lug 6 1997 156914 ASCII KI2ICR3Al2I CDC8T409ACOSTSI`5.cut atxf.209 3 Aug 6 1997 159752 ASCII 2CaU3A121MCOTS1AC09T0O.Cut alXf.210 29 Aug 6 1997 13757 ASCII U12EAlNUM0c8MUO TNA.cut *IXf.211 31 Au 6 1997 146133 ASCII N12VClt12N09DCT0897A=T139.cut

• IXf.212 32 Aug 61 151745 ASCII N12/C1A290CO&T139ACMTA04.cut i1Xf 213 33 Aug 61997 154131 ASCII 12/CRA12N09COST404 7409.cut clXf.214 33 Aug 6 1997 14 ASCII N121CU3AIZNO9DC8T409ACOSTSI5.cut *IXf.215 34 Aug 6 1T 1S9752 ASCII 12M3AIZU9DCOSISAC DTOO.cut *1I1.216 29 Aug 6 1997 13737 ACII 312/C3A12N100C081TOOAC081097.cut alXf.217 31 Aug 6 1997 146133 ASCII 1Z2/Ca3A12M10DCOS09TACOTt39.cut WM.218 32 AW 6 1997 1S1745 ASC? I N121C3A12N100C08T139AC08T404.cu IlXf.219 33 Ag 6 1997 154214 ASCII 11CALUZIODCO8T4MACUT409.et *JXt.220 33 Aug 6 1997 16914 ASCII NIIC3A2NICOCO8T409ACWOTS15.cu

• IXf.221 34 Aug 61 159732 ASCII 112/CRI1ZODCOTSIACM9TOO.cut mIXf.222 29 Aug 6 17 U7495 ASCII N2/CR3A12NIIDCOBTOOOACOT8O97.CUt If,223 31 Aug 6 1997 6133 ASCII 112CR3A1Z211DC081T97ACO0T139.eut sIll.224 32 Aug 6 1997 151662 ASCII K121CR3A12Xml1CWT139AC08T404.Pt

• IXf.225 33 Aug 6 1997 154214 ASCII 32/ClA3Ai21iiDCO8T4O4ACOBT4O9.cut aIXf.226 33 Aug 6 1997 156914 ASCII X1/CR13A12Nll10COS409AC3OBT15.cut aIXf.227 34 Aug 6 1997 159732 ASCII U1/CR3Al2NOlDCOTSISACWTOO.Cut WOIM22 29 Aug 6 1997 137495 ASCII Nl2/CR3Al2ml2DCWTOOACMT0 97.cut atXf.229 31 Aug 6 17 613 ASCII N1Z/C3AAZM12DCWTO97ACM7139.vA 6lX.230 32 Aug 6 1997 151662 ASCII N11CR3A12120DCO8T139ACOJT404.cut 1IXf.231 33 Aug 6 1997 154214 ASCII NI2/C13A121120CO8U40UC08T409.cut *S Xf.232 33 Aug 6 1997 156914 ASCII

• 12/CR1A12m12DC08409AC08T515.cut MO1.233 34 Aug 6 1997 159732 ASCII N12/CR3AI2MI2DCOT51SAC09TOOO.cut 411.234 29 Aug 6 1997 137329 ASCII h2/CR3Ai2Ni3DCO8TOOACO8TO97.cut IX.235 31 . Aug 6 1997 1U133 ASCII N12/CR3A121113DCOT097ACOOT139.cut .1.236 32 Aug 6 1997 151662 ASCII N1UC13A12N13DCOB8T139AO404.cut ilXf.237 33 Aug 6 1997 154214 ASCII N12/C13A12N13DC08T404ACaT409.cut Xf.236 33 Aug 6 1997 156997 ASCII 1UC2A12N130C0T409AC08T515.cUt , 1Xf239 34 Aug 6 1997 159732 ASCII K1ZICR3A12NIOCO8TS1SACO9TSOO.Sut aIXf.240 29 Aug 6 1997 137412 ASCII Ku2C53A12K14UDC8T ACOA TO97.cut a1.241 31 Aug 6 1997 146133 ASCII H2/CR3A12N14DC08T097ACWT139.cut sIXf.242 32 Aug 6 1997 151662 ASCII 912/cL5A12140DCOST139ACM74U.cut sIXf.243 33 Aug 6 197 1542U14 ASCII NI12CRSAi2Ni4oCOST4O4ACOBT4f9.cit sIXf.244 33 Aug 6 1997 15699 ASCII N2MA12N140C08T409AC08T515.eut liXf.2.5 34 Aug 6 1T 159a35 ASCII 112/C 12140CUTM15A09TOO.n alXf.21.6 29 Aug 6 1997 137495 ASCII h12/CR12NI1SOCO8TOOOACOSTO97.Cut sIXf.247 31 Aug 6 1997 1454 ASCII K12/CAU12N150COtT097AC08T139.cut 611.248 2 Au 6 1997 15157 ASCII Nl2/Ct3A12ZNiSDCMTll9ACOT404.cut IXtf.249 33 Aug 6 197 154214 ASCII NIUC23121150C8T404AC087409.cut 8Xf.250 33 Aug 6 1997 15697 ASCII NIC13A12N150DCOT409ACUT1S.cut I1f.251 34 Aug 6 197 159I 5 ASCII N12ICR3AI2MiSDCO8TS1SACO9TOO.cut aixf.252 29 Aug 6 997 137412 ASCII NuZCR 12160DC0 T000ACWT097.eut e1Xf.253 31 Aug 6 1997 145633 ASCII N112/C3A2106DC08T097AC08T139.cu aIXf.254 32 Aug 6 1997 151496 ASCII NIZCRCU312IUDCUT139ACOT44.cut 611.255 33 Aug 6 1997 1534 ASCII K12/CKU12MI0COT404ACM5T409.cut 1X.Z6 33 Aug 6 197 156997. ASCII NU1/C3AU2N1DCOBT409ACOSTSI5.Cut .11.257 34 Aug 61997 159586 ASCII H12CR3AI216DCOWTSISACO9TO.cut .IXf.238 29 Aug 6 1997 1379 ASCII VCLUAU2MI7OCOBTOOAMOT97.cut IlXf.259 31 Aug 6 1997 145159 ASCII K1/CR3A2NI17RCCOT097AC08TI39.cut *lXf.260 32 Aug 6 1997 151020 ASCII 0121CLUUM117C0T139 08144.eut d1Xf.261 33 Aug 6.1997 153048 ASCII NlZCR3Al2N1ThC0T404AC08T409.cut IXf.262 33 Aug 6 1997 156532 ASCII NKI/CR3AlI2NlDCO8T409ACOOTS15.cut *IXf.263 34 Aug 6 1997 159001 ASCII NIlCRU12N17C087S5SAcMDO0.cut alXf.264 29 Au 6 1997 1377 ASCII NlV/CR3A12N18COTOAC08T097.cut *TXf.265 30 Au 6 1997 141811 ASCII N12/CRA12NIDC01TO97ACVBT139.cut 811f.266 31 Aug 6 1997 146905 ASCII K2/C33AlZ11180DCT139AC08T404.cut *S1f.267 32 Aug 6 197 149369 ASCII N1VCR3A12l180CWT4D4ACD8T409.cut alXf.268 32 Aug 6 1W7 15297 ASCII N12/C13AI2NlOCVT409ACD8TII.eut aIXf.269 33 Aug 6 1997 156245 ASCII N1UCRUIAUM1CWTSISAC09IOOD.cut dXf.27 28 Aug 6 1997 134 ASCII

Aug 06 13:30 1997 Fite Now: ngtfat uooooo-71I7-0200-ooo4 Aug06 mglit 3:3 ¶97i~eUrn: REV 00 AIIACUIENT 1X pape 5 121C3AswO1DcC0TMWAcM 58.cut eIXf.271 38 AUG 61 99r ASCII N1j/CaI8NOlOCD9TI8ACM9TZI9.cvt &Ixf.M 32 Auw 61997 14611 ASCII 1V1/CRt3AlSNO0C09TZ19AW93.CWt GIxf.Om 39 ug 1997 U1 ASCII NlV1AR8N02JC09MOA9T1S8.cUt *Ixf.274 39 Aug 61997 1805 ASCII 91E1COAMM02Wt¶SBAC09TV9.sut l*fxf.5 33 Au 6 :997 9SM9 ASCII m1u/c3Al8N0DXC9T219AC9T3n.eUt sIXf.276 40 Aug 6 1997 IB2 ASCII IZ/MAISNO MOO9TO0A9TIDS.sut GIxf.M 39 Aug 6 1997 S15 ASCII Z/cA18lWDCOT15BAC09T219.vt alxf.27 33 Aug 6 1997 1s28 ASCII NIZ/Ct3A¶81=C09T219AC09T363.tut sixt.279 40 Aug 6 1997 185195 ASCII gIZ/CR3A1SMUC0TOr0 C09r158.cut aIXf.ZM 39 Aug 6 1997 181876 ASCII U2/CR3lAOU CO0TlSBACD9TZ¶9.cut alXf.281 33 Aug 6 1997 152400 ASCII

¶Z/00AI 4CO9TZI9AC09T3.Sut oif.282 40 Aug 61997 185195 ASCII HM2MCU3A¶NCSCO9TOOOACO91.Cut aIxf.W 39 am 6 199 182125 ASCII NI2ICAISNDC09TISaMT2I9.Cut alXf.284 33 Au 61997 15248 ASCII U¶2ICRZl¶8W5DC09TZ19AC09T363.cut d X .25 40 Aug 61997 18610 ASCII Z/CR3A1SMNO TOOOACOPT1a.cut slxf.2a 39 Aug 6 197 18208 ASCII Z/Cl3A1H060C09T185AC9T219.eut siXf.2W7 33 Au 6 199 1S245 ASCII

• ¶2/CR3A81060CD9T219AC09T363.cM Gll .2U 4D LU 6 1997 1810 ASCII NIZIC3AIUM79CO9TOOOACOWTIScut siXf.289 39 Au 61997 182098 ASCII vcZUAI07bCo9TslsAC09TZI9.ut GIl.20 33 Lm 1997 ¶s26 ASCII NlZ/CR3A8IU COC 29AC09I363.cut IlfX.291 40 Lu 6 1997 185693 ASCII N12f/cA1l8DC0OD00ACW15.ft Olxf.292 Lu 6 199 820 ASCII IlZ/CR3AlBO8DC09T`U8ACO9T2M9.CUt cXf.293 33 Lu 61997 1S2566 ASCII 412/C03A CO T219AC09T63.Sut aIXf.294 40 Aug 6 1997 185693 ASCII K1/CR3A1U09DCO9TOOOACO9158.cut a1Xf.295 39 Lu 61997 ¶3097 ASCII

¶Z/CR3A18wO C9T15AC9TZ19.cut SIXf.296 33 Au 61997 1s48 ASCII RUMMAlO DC09T219AC09T363.cut IXf.297 40 Aw 6 1997 18692 ASCII N¶21mC3AN10ODC9TOOOACWT158.cut aIXf.298 39 Lu 6 1997 1279 ASCI I u1CRISNIODCTIS8ACOMt19.Cut Illf.299 33 Aug 6 1997 153175 ASCII U12UCl3A18W10C09T219ACD91W6.t 1Xf.300 40 Aug 6 1997 165 ASCII Nl¶ZCR3AlNllDCO9tOOAC09153-.S sIXf.301 39 Aw 6 1997 1820 ASCII

• I2Ck3A18IZ110C l9T15AC Z19.Cu *11.302 33 Aug 6 997 153175 ASCII j2/CR3A¶110C09T29AC9T363.cut a1tX.303 40 Aw 4 197 385 ASCII 1112/C3AI820SCTOOOAC09`153.Sut sIXf.304 39 Aw 6 1997 18 ASCII N12/CR3AI8NZDC09T158AC09T2I9.eut a11f.305 33 Luw 6 1997 133258 ASCII N1z/Ck3A1812DCW9T219AC09T363.eu 1Xf.306 40 Aw 6 1997 186555 ASCII NIZIcR3AN13DCMtOOOAC09TIS.cvt s1Xf.307 39 Aug 6 1997 1¶2202 ASCII N121C3AlU C09T¶5C0T219.cut aIXf.308 33 Aug 6 ¶W7 152985 ASCII N12ZCK3All13DCMZ19AC09T3O.Ct &.Xf.309 40 Aw 6 1997 1852 ASCII HI2ICUAINil40COPTOOOACWT150.Cut alf.310 39 Aug 6 1997 179967 ASCII HlVC3AW140C015aAC09T219.cut sIXf.31i 33 Lu 6

• 1502s4 ASCII 121C13A8NI140C09T219AC09T363.rut *IXf.312 40 Aug 6 1997 183534 ASCII 9I2/0C3ALI85DCO9TODAC09TI58.Cut atXf.313 39 Aug 6 1997 180050 ASCII l2CR3A¶8115DC09T15aACD9T219.Cut *IXf.314 33 Lw 6 1997 150924 ASCIl I121CR3AIUI5DC09T219Aco9163.cut alXt.315 39 Aug 6 1997 18451 ASCII RIZ/~atAK8N146C09T0ODACO9T158.Cut uIXf.316 39 Aug 6 1997 179658 ASCII NIZ/CR3A8l6DC09Tl58ACD9T2I9.cut alIXf.317 33 AuL 6 1997 150692 ASCII NIHVCU3li16DOMC09T2¶9AC09T33.eut eIXf.318 39 Auw 6 1997 183115 ASCII NIZ/C03AI8170CW09TOAC09T58.Ecut d1Xf.319 39 Aug 6 1997 179243 ASCII v¶/cL3AlUil7tDCQ9TI58ACO9TZ9.cut .IXf.320 32 Aug 6 197 150111 ASCII NIH/CRAllN17DC09TZ19AC09T363.cut o1Xf.321 39 Auw 6 1997 ¶83147 ASCII 12/CH3AISNISDCWTOOOACO9T158..Ut a1Xf.322 38 AuL 6 997 1330 ASCII NH12/C13A18N¶0C09T58AC09T219.cut 1IXf.323 32 Aug 6 1997 14Uu ASCII N12/CL3Ai8NUl8DCTZ9AC09T363.cut 111.324 39 Aug 6 1997 181483 ASCII Computer Tape lacku lNumber of File Date File Size File Type File Uwe File Nam Print Pages (Output) Clytes) (Format)

N123/CR3A16N1ODC09TOOAC09t158.cut zlXt.325 36 Aug 6 1997 169409 ASCII U23tC23A16NO1DCV9T1S8ACO9T219.out elMf.326 29 Aug 6 1997 137480 ASCII NZ3/CU3Al6KOiDcMT2i9AC9T363.cut TXtf.327 36 AuL 6 1997 179807 ASCII N23/CR3AI6RG2DcO9TOOACO9TI5B.cut Ixf.328 37 AUL 6 1997 172156 ASCII N23/C33Ali61O2DCM9TI58ACD9TZ19.cut alXf.329 29 Aug 6 1997 139U4 ASCII K23/CR3Al6N02DC09T219ACD9W63.cUt sixf.330 36 ALu 6 1997 172803 ASCII NZI/CRU3M1H6O030C09TOOCAC09MtS8.cut 11Xf.331 37 Aug 6 1997 172990 ASCII NZ3/CL3A16N3DC9T15UAC09T219.cut aItf.332 30 Lu 6 1997 140684 ASCII H23/C3A161NO3CO9T2¶9ACM9T363.cut .IXf.333 37 Lu 6 1997 173637 ASCII K231CLA16NW040C09T ACtl158.cut 1IXf.334 37 Aw 6 1997 173544 ASCII N23/CO3A16N040CMIt158AC09t219.cut *IXt.335 30 Lwu 6 1997 140999 ASCII

ALLV 06 13:30 199 Flte RU: beglst A19C9aAOMOO -0 .020.0 004 KU id iTTOACI? 1X- PA 6 f(Z3/C #6NW4DC9T219AC0MT3a.wut 80f.336 37 61997 Aug'73m22 ASCII

• Z3/CR316XOSODCOTODOAC9T58.= GIXf.337 37 AUG 6&1 173627 ASCII H231c13A1l6N5DCD9T159AC09T219.cut slXf.338 sO Aug 1997 141414 ASCII n3/cR3AO5DCO9T29ACO9T363.cut .1X .339 37 Aug 61997 1¶73 ASCII 1123J/CAI6NO6OCO97O0ACO9TIS.cut 6Xf.340 37 Aug 1997 73627 ASCII K2Z3C23A16mo60CD9T15lAC09T219.cut aXf.34i 30 Aug 6 197 141414 ASCII H23C2Al16No6DCC9T219AC09T363.cut IXf.342 37 Aug 6 1997 1735 ASCII K23/CR3AI6N7DCO9TOOOAC09T1S.cut xf .343 37 Aug 61997 13627 ASCI I 23 A160070C09T15U AC09TZ19cut aIXf.3U 30 Am 61997 14144 ASCII H23/CR3A16X070C09T219AC09TW.Cut lXf.345 37 Au 6 19 173858 ASCII K23fCI3A16NIDCV9TOVOAC0915.cut If.346 37 Aug 6 1997 173627 ASCII H23/C13Ai6NO8DCO9TISACO9TZ19.cut *IXf.347 30 Aug 6 1997 141497 ASCII K23/C3A16NO )C09T219AC09T363.tut *IXf.348 37 Aug 6 1997 73941 ASCII 1/CUIAMIUO9DCO9TDOOAC9T15.ct 8It .349 37 Aug 6 1997 173627 ASCII V23/CR3A16M09C09T15C09T219.cut IXt.350 30 Aug 6 1997 141497 ASCII IQ /CR3A161109MC09T219AC09T363.cut IXt.331 37 Aug 6 1997 173941 ASCII U23/cR3Al6ujODCO9TOOOACO9T8.cut !Xf.352 37 Aug 6 1997 173627 ASCII U23/CL3A16I0DC09T15AUC09T219.cut aIXf.= 30 Aug 6 1997 141497 ASCII N23/CR3A161¶0DC09T219AC09T363.cut alXt.354 37 Aug 6 1997 173941 ASCII N23CL3AM6U1OCO9TOOOACM15B.Ct JSXf.355 57 Aug 6 1997 173627 ASCII K23/CR3ALI10CO9TIMSACOZI9.ut aXf5.36 30 Aug 6 1997 141497 ASCII K23jCR3Al6wlDCO9T219AC09W .aft sIXf.357 37 Aug 6 1997 173941 ASCII N23/ClUA1621DC09TOOAC09t15.cut sIXf.358 37 Aw 6¶997 173627 ASCII N23/ClU16N1CO9T15UC09t219.cut *lXf.359 30 Aug 61997 141497 ASCII 123/CU3A16NiZDCO91219AC09T363.cut dXt .360 37 Aug 6 1997 17m5 ASCII 123/CU3A1i613DCO9TOOOACO9TIS8.cut dIXf.361 37 Aug 6¶9 173627 ASCII 123/CR3A16l13DCO9Tl58AC9T29.cwt dIXf.362 30 Aug 6 1997 141497 ASCII K23/C23A1613DC09T219AC09T363.eut dIXt.363 37 Aug 6 1997 173858 ASCII 23/CR3A1l6l4DCO9TOOOACO9T1I8.cut dXf .364 37 Aug 6 1997 173627 ASCII N23/CR3Al6164DCC9T15UC097219.cut *IXf.365 30 Aug 6 1997 141414 ASCII N23/CR3A16Ml4DCO9T219ACO97363.CUt *IXf.366 37 AuG 6 1997 173941 ASCII

• 1231C23A16N15DCO9TM0AC097158.Cut aIXf.367 37 Aug 6 ¶997 m310 ASCII v23/CUAMIMiIDCO9TA15COMT2¶.cut dlXf .36 30 Aug 6 1997 1414141 ASCII 1123/Cl3A16t15DC09M219AC09VM3.mut sXf .369 37 Aug 6 1997 173941 ASCII 1232/CA161160C091OODAC09715B.Cut adXf.370 37 Aug 6 1W 173401 ASCII M23/C23Al616DCD9T15AC09T219.cut dlXf.371 30 Aug 6 1997 140999 ASCII 323/CR3AIA16DXC9TZ19ACO9T363.cut alXf.372 37 Aug 6 1997 1M22 ASCII K23/CR3Al6NI7DCO9TOOOAC09Tl55.cut *lXf.373 37 Aug 6 1997 17MM2 ASCII N23/C3Ai6N17DCO9TIS8AC09T219.cut *lft.374 30 Aug 6 1997 140518 ASCII U23/CL3A1617DCO9T219ACO9D763.cut sIXf.375 37 Aug 6 1997. 173637 ASCII U23/C23A16i18DC09T1OOACD9Tl55.cut *IXf.376 36 Aug 61997 17099 ASCII K23/CR3A16N1UDC09T15UAC09T219.cut slXf.377 29 Aug 6 1997 138891 ASCII H23/CR3A1668tDC09T219AC09T363.cut slXf.378 36 Aug 6 1997 171807 ASCII 623/CU3A23NOICOBTTOOOACOBTO9.Cut cXf.379 30 Aug 6 1997 141226 ASCt I N23/CR 23A O1DC8T097ACM7T139.cut &3Xf.3BO 31 Aug 6 1997 14682 ASCII N23/C13A3D1C8T139AC0T404.cut sIXf.3t1 32 Aug 6 1997 48m95 ASCII M23/C33A23N01D C08T4D4AC0tT409.cut cXf .312 32 Aug 6 1997 1¶3245 ASCII 123J/C3A231010C8T409ACOtT51S.Cut lXf.353 33 Aug 6 1997 15568 ASCII C23/C33A231010C08T515AC09TOOO.cut alXf.3U 28 Aug 6 1997 134251 ASCII 023/C02DU N COtTDOOAC0tT097.cut clXf.385 31 Aug 6 1997 1443 ASCII N23/03A23D MCOST097ACUt139.cut *IXf.3t6 32 Aug 6 1997 1S0269 ASCII K23/C3A23DC CO8T139AC0T404.cut lIXf.3t7 33 Au 6 1997 15248 ASCII V23/CL3AZ32DCO8T404ACG8T409.u clf0.358 32 Aug 6 1997 154735 ASCII U23fcRAZ3N02DC08T409ACO8T515.a 6Xf0.389 34 Au 6 197 158692 ASCII N23/C3AM23DCOST515AC09T00.c alXf.390. 29 Aug 6 1997 136997 ASCII RU3/CR3AIODCO&TOOOACOUST97.cut aXf.391 31 Aug 6 1997 143491 ASCII N23/CU23A MCTO79ACOST139.sut slXf.392 32 Aug 6 1997 151352 ASCII N23/C33AZ3NO3DC08T139ACT404.cut olXf.393 33 Aug 6 1997 S3218 ASCII K23/C3A23NC3D0C8T404ACO8T409.cut *IXf.394 33 Aug 6 1997 156748 ASCII NR CA23lM 030COBT409ACBTSS.wt I.395 34 Aug 6 1997 59254 ASCII N23/C323NO03DC8T515ACC091D .cut IXf.396 29 Aug 6 1997 13737 ASCII N23/C23A23NO04CG3TGOODACT097.sut IXf .397 31 Aug 6 1997 143M4 ASCII 023/CLU2U=CtT097ACD8T139.eut clXf.398 32 Aug 6 197 1¶1579 ASCII NZ3/CR3A23N040 C0 T139AC08T404.cut sXf.399 33 Aug 6 1997 153550 ASCII V23/CL3AN40C08T404A0C814@9.cut *Xf.400 33 Aug 6 1997 156748 ASCII N23/C23 040C8T409ACG8T515.cut alXf.401 34 Aug 6 1997 ¶5 ACI N23/CLA23uO4DCQ3T0515AC0O .cut alXf.42 29 Aug 6 1997 137661 ASCII K23CRL3A231050DC0TODOACOT097.cut clXf.403 31 Aug 6 1997 146133 ASCII N23/0C3A35CUT097ACM1139.Cut uK .404 32 Aug 6 1997 151662 ASCII N231CLU3OSDCOST139ACM8404.cut MO S.405 33 Aug 6 W7 152 ASCII

Aug 06 IWO 199 Fits gm*: "glist A 1ou01317 :1.00.04" Kw bO ATTAcea TX - Pag 7 K23C33JA050C8T44ACMT4G9.Cut *2Xf.406 33 AUG 61997 156914 ASCII u23ICR3AZ35DcO8T409ACO8TSIS.cut sixf.407 34 Aug 61"9 159752 ASCII

• 23/CL UNMSCWTSI5ACMOT .cut sIXf.408 29 Aug 6 199 1371 ASCII 1123A/LANO6COBTOOACOSTO.cut sIXf.409 31 Aug 6 1997 16133 ACII N23MU/C3 O0ST097AMT139.cut Ilf.410 32 Aug 6 1997 1Sl7 ASCII K23/CLAUOM6MC8T139ACO8T404.cUt uIXf.411 33 Aug 6 1997 15388 ASCI I Ku2/cUMO3 60c8404ACO8T409.cut SIVR.412 33 Aug 6 1997 56914 ASCII H23/CR3A231060CO8T409ACO8T515.eut 6If.413 3 AUG 6 1997 159752 A CII 923/CU3A23N06DCO8TSISACO9TM0O.cut .111.414 29 Aug 6 1997J U7661 ASCII U23/CU3ANUO7MCOWTOODACORTO97.cut *IXf.41S 31 Aug 6 1997 146299 ASCII K23/CL3A23VD7DCQ8T097ACO3Tl39.cut d Xf.416 32 Aug 6 1997 151828 ASCII 123/CU3A23NO7bCOWTI39ACO8T4C4 .Ct *10 .417 33 Aug 6 1997 15396S ASCII N23/CLUA23307DC08T404AC08T409.cut *IXt.4 1 J 33 Aug 6 1997 136914 ASCII N23/C33A23N0h7DC0T4M9AC08TS1.cut aIXf.419 34 Aug 6.1997 159752 ASCII K23/C 3A23M07DC08TS1SAC09TOOO.cut *IXf.420 29 Aug 61997 I3737Z ASCII K23/CR3A23N080C08TGDDACO3TW9J.cut aIXf.421 31 Aug 6 1997 146382 ASCII NZ23CaZA23M08DC08T097ACG5T139.cut alf.422 32 AuG 6 1997 I51s28 ASCII HRU3CL3AZ3UMOEC08T139ACO8T40K.cut &1Xf.423 33 Aug 6 1997 1S4048 ASCII K23/CR3A23080C08#T404AC08T4W9.cut oIXf.424 33 Aug 6 1997 156914 ASCII N23/CR3A23N8DCO8T4O9ACO8TSIS.Cut *IXf.425 34 Aug 6 1997 159752 ASCII X23/CUAZU =08T5I5AC09TOOO.cut &IXf.426 29 Aug 61 997 137537 ASCII N23O/C23ILO9DCB8TOOOACOMT097.cut aIXf.42r 31 AuG 6 1997 146382 ASCII K231CL33A23U090CWT097AC08T139.cut sIXf.428 32 Aue 6 1997 15182 ASCII H23/CEUU9MCO8TI39ACO5T404.cUt aIXf.429 33 AuG 6 1997 1404U ASCII N23JC13A2N09DC08T404AC08T409.cut *It.430 33 AUG 6 19T 156914 ASCII N231Ca3 C090O8T409AC08T51t.cut IXt.431 34 AuM 6 1997 159752 ASCII K23/C23NO9DCM8TSISACO9TOOO.cut4Xt.U2 29 Au9 6 1997 13757J ASCII N23/CR3A25IO0DC08TOOOACO8T097.cut IVY.455 31 Aug 6 1997 14632 ASCII H23/CM3A1OD10C081097AC08T139.cut *IXt.434 32 Aug 6 1997 15128 ASCII K23/C 1110DC08T139ACOJT4K.cut *Ift.435 33 Aug 6 1997 1540 ASCII N3Z/CR3A2310DC08T404ACOJT409.cut d1Xf.436 33 Aug 6 1997 156914 ASCII H23/C3A231ioODCOT4OUACO5TSI.cut adXf.437 34 Aug 6 1997 1597S2 ASCII 923/CUIO31 D0Ct851SACOPTOO.cut 61Xf.43 29 Aug 6 1W97 137495 ASCII NZY3/CU3 1DCW TOOOACOUTO97.cut *IXf.439 31 Aug 6 1997 146382 ASCII NU23/CLU23mI11DC8T097AC08T139.cum Ilt.4O 32 . Aug 6 1997 15242 ASCII KZ3/CR3A23311DCOBT139AC8404.wut *IXt.441 33 Aug 6 1997 154131 ASCII N2/CRAZ3N111DC08T4UAC08T409.cut *IXt.U2 33 Aug 6 1W7 156914 ASCII N23/CR3A2311t0CG8T409AC0T515.cut *IXf.U3 34 Aug 6 1997 159752 ASCII 323/3A2IDCOcTISACO9TOOO.cut SIXf.4 29 Aug 6 1997 137495 ASCII M3/CR3A2311ZDC08T0O ACG8TW7.cut If.445 31 Aug 61 997 14382 ASCII N23/CRU N12UD0CT097AC0T139.cut 61l.446 32 Aug 6 1997 132428 ASCII K23/CLA112DCDBTI39ACWT404.cUt *IXf.447 33 Aug 6 1997 1S4214 ASCII N23/CU3A l2DCO3T404ACOT409.ut Slxf."s 33 Aug 6 1997 156914 ASCII H23/3A23 DCOIT409ACO8T5IS.cut s1Xf.449 3 Aug 6 1997 15972 ASCII 323/CR3C23MI2DCUSTSISAC9TOOO.cut aXf.450 29 Aug 6 1997 137329 ASCII N2/CR3A23313DCW7tQ0C08Z097.cut SIXf.451 31 Aug 61 997 14638 ASCII 2/C3A2313DC08T097ACO$T139.cut aIXf.452 32 AuG 6 1997 152428 ASCII N23/Cm3A23130COST139AC08T4M.cut aIXf.433 33 Aug 6 1997 154214 ASCII K23fCR3A23N13DCG8T404A8T409.cut .1Xf.454 33 Aug 6 1997 156 ASCII N23,CLUA3M13DCW T409AC08T515.cut s11.455 34 Aug 6 1997 159732 ASCII UCLA23130CO8T515AC09T000.cut mSXt.4S6 29 Aug 6 1997 137412 ASCII

• 23/C3AN14DC08T0ACWT97.cut I1f.457 31 Aug 6 1997 14299 ASCII 13/Ct3A23Nl4DC08T097ACO8T139.cut &1IX.458 32 Aug 6 1997 151662 ASCII 23/CA23Nl4bCUTI39ACT44.cut clXf.459 33 Aug 6 1997 154214 ASCII N23/C13A306CMT404ACt409.cut e1Xf.460 33 Aug 6 197 156997 ASCII 1123/CUUMUDC087409ACOST515.cut 6IO.4l 34 Aug 6 197 159732 ASCII 13/CR3A23N14OCO8T5ISACO9TOOO.cut 10f.4a 29 Aug 6 1997 13741z ASCII 3O/C3LA233150C08TA T097.cut *tf.463 31 Aug 6 1997 146133 ASCII N23/C3A23HM5DCWT097ACOST139.cut aXf.464 32 ALM 6 1997 151579 ASCII N23/c33A23N150C08T139AC08T404.cut d1Xf.465 33 Aug 6 1997 154214 ASCII N231C313150C08T404AC08T409.cut a1Xf.466 33 Aug 6 1997 156914 ASCII H23/jC3A2Ll5DCD8T409ACD8T5l5.cut &1Xf.467 34 Aug 6 1997 159752 ASCII N23/CR3A23N150C08T315AC09TO00.cut ItXf.468 29 Aug 6 199 137495 ASCII K23/C3A23160COBTOMC08T .cut *tXf.469 31 AUg 6 1997 14588 ASCII U23/C3t233160C0CTo97tAC0139.cut *I1f.470 32 Aug 6 197 151496 ASCII 1C33A2316DC08T139AC8T4M.cut MIMI.471 33 Aug 6 1997 153716 ASCII n/CL N16D0CU8T44ACOT4.cut 1lXf.472 3 Aug 6 1997 156914 ASCII U232/CLA3K16C08T409ACWT515.cut atXf.473 34 Aug 6 1997 1599 ASCII H23/C3A23MiC08T515AC09TOO.cut 1lXf.474 29 Aug 6 1997 137329 ASCII N23/C2A2N1I7bCWT000ACO8TO97.cut *IXf.475 31 Aug 6 1997 15242 ASCII

Aug1 06 t3:30 1 m Fite Name 01911st AUDAoooo-W17I?02 00-o 4 ItEv 00 ATTAM WT IX - Page 9 K123/CAul708TOA97A08T139.eut aIXf.476 32 Aug 6 197 151103 ASCII 123/C 323MN710C08739AC8T4&04.cut a1Xf.477 33 Aug 6 1997 1530U ASCII 33 AuW 6 1997 156352 ASCII H23/C23A23M17DCT404ACftT409.9Ut aixf.478 K23jCR3A23NtThC08T409AC"0TS5S.cu IXf.479 AU9 6 1997 159001 ASCII 123/CL3A23H7DC8T5l3AC09TOO0.cUt *IXf.480 29 Aug 6 1997 13797 ASCII N23/C3A23I1mCO8T000ACO8T097.est *IXf.481 30 Aug 6 1997 141811 ASCII N23/CLUMMCWT097AC0T19.CUt GIxf.43Z 31 Aug 6 1997 147071 ASCII I23/CL3A23N1a0C0T139AC08T404.eut oixf.483 32 AUG 6 1997 149452 ASCII

%U/CL3A2 8T4G4ACU0T409.cUt COl alXf.4U 32 Aug 6 1997 152I89 ASCII 1M23/CJ3Al2DCWT4O9ACo8TSlS.eUt alSX.485 33 Aug 6 1997 155747 ASCII N23/CR3A23KlIDCOSTSlSACO9TOOO.cut Ixf.436 28 AMg 6 1997 13406 ASCII Camputer Tape Backup Number of Flle oate File Size File Type Fite Mume File Mame Print Pages (Output) (Sytas) (Fomt) 2CUt3AO05O1DA09TOAC9T158.ut sIXf.487 38 Aug 6 1997 176150 ASCII 31 Aug 6 1997 143956 ASCII 270CRUO5MDCO9TISBAWT219.eut sixf.488 ASCI I 12jCRASUOICOc 9t29A 9T363.eut sIxf.489 33 Aug 6 1997 1m63 v27a/CMM02 C0TOOCW09t1S3.eut 6lt.490 38 Aug 6 199 1799 ASCII K27aICR3AD5N=C09T15U8ActZ19.cut siXf.91 30 Aug 6 1997 142559 ASCII K2Tm/Cu3AO5V=C09TZ19ACOTa.cUt aIX.492 37 Aug 6 1997 17475 ASCII N27/CRA05NWCOM9TO0A915t 6151.493 38 AUG 6 1997 175243 ASCI I KZhaCR3AUDNOMCM9T15AACWT99.cut sIXf.494 30 Aug 6 1997 14295T ASCII V 6 197 ASCII N2741CRA 0530C0TZ19AC091M.eut alXf.495 Aug 176326 CR73AO5UM4S009T0A1ISS.cut sIXf.496 38 Aug 6 1997 175631 SCI I

• 27a/Ca3A05N04DC09T15UC09TZ19.ceut 815.497 31 Aug 6 1997 143501 ASCI I N27a/CR3AO5KMCD9TZ19ACD9T363.cut oIXf.498 3N Aug 6 1997 176941 SCI I 27a/CIAAO5N05DC09TOOOACO9T158.Cut 815.499 38 Aug 6 1997 175797 ASCII K278A1C 05N05DC09T15ACO9T219.Cut lXf.500 31 Aug 6 1997 1454 ASCII K27aCU3A05NO5DCO9TZ19AC 9TM363.ct I8f.501 38 Aug 6 1997 176941 ASCII 927a/"A05NOC09TOACOI9T15.t *101.S02 38 Aug 6 1997 17388 ASCI I U27aMCRA0OWC09T158AM09T219.9ut 1Xf .503 31 Aug 6 1997 143837 ASCI I E27XacR3A0x060C09T29AC09 .cut *IXf.504 38 Aug 6 1997 176941 ASCI I U27a&CR3A05N7C M9TO0AAC9T158.cut oIXf.505 31 Aug 6 1997 176046 ASCII ZICRRA05KO DC09t150ACO9T219.cut aXf.506 31 Aug 6 1997 143920 SCII Z7a/CR3A05ODCO9TZ9AC09T5O.cut SIX1.507 38 Aug 6 1997 176941 ASCI I Aug 6 1997 MCI I Z7,/CR3A05UO8C09TOOOACO9T1SS.cut *IXt.508 38 176046 SCII U271CRa3A05110MCI9T5UAC9T19.Ut t.SW1.80 31 Aug 6 1997 143920 SCI I N27/CR3AD5NOI0C09T219AC09T363.ceut IXt.510 38 Aug 6 1997 176941 ASCI I

• 27a5U03A05N9DC09TOOAC09T158.cut a151.511 38 Aug 6 1997 176129 ASCII 127A4/3050 9DC09T158ACN9TZ9.eut IKf.312 31 Aug 6 199 143920 ASCI I u27afcx3A05ib09DC09T29AC09T363.cut sxf.513 38 Aug 6 1997 176941 ASCII K I/CR3A05N1I0cO9TOOOAMT158C.ut aIXf.St4 33 Aug 6 1997 176129 SCII 1127 MAOSNiODC09TIMCAO9T219.cut *I8t.515 31 Aug 6 1997 143920 ASCII N27a/A05N10ODC09T219AC09T363.eut aIt.516 38 Aug 6 1997 176941 ASCI I NZa/CR3AO5811DCO9TOUOACO9TIS8.eut alxf.517 38 Aug 6 1997 176046 ASCI I N27/ClR3AOSNiIDC09TISUC09T219.Cut a!5.51s 31 AUG 6 1W7 143920 ASCI I U27a/CLAMll1DC09T219AC09T363.cut aIxf.519 38 Aug 6 1997 176941 ASCII iIZh/cR3AOSNIZDC09TOOaACO9TISB.cut a15.520 38 Aug 6 1997 lT6046 ASCII

• 127./C3A05NlC09T1AC09T219.cut aIXf.521 31 Aug 6 1997 14920 ASCII N27afC3A05NZDC09T219AC09T3.cut aISXf.522 38 Aug 6 1997 176941 ASCII 927a3A0513C09T0AC09T158.eut alXf.523 38 Aug 6 1997 175963 ASUI I 27/CR3A0 l3DCOO9T15ACM9T2P.cut aIXf.5Z4 31 Aug 6 1997 143920 ASCII N27/C3A05K3C09TZ19ACG9T63.Cut alXf.SZ5 38 Aug 6 1997 176941 ASCII N2Ta/CR3AMN14SCD9TOOOACO9TI58.eut aIXf.5Z6 38 Aug 6 1997 175963 SCI I N27T/CR3A0SU14C09T15UCO9T219.cut aIxf.SZ2 31 Aug 6 1997 143920 ASCl I NI27/Cl3A051140C09TZ19AC09T363.cut aIf.529 38 Aug 6 1997 176941 ASCII 1z7a/c3Ao3NI5DCo9TOOACO9TIs8.cut aXf.529 37 Aug 6 1997 175710 SCII X27cA051015DCWT715C09219.cut *1Xf.530 31 AUG 6 1997 W7S4 SCII 2T7aCU3AO5XlI5DC09T219ACO9T363.cut aSXf.531 38 Aug 6 1997 176941 SCII N27/CA05N16DC09TGO0AC09158.cut aIXf.532 38 Aug 6 1997 175373 ASCII H27alCR3AO5X16DC09T158AC09TZ19.cut .lXf.533 30 Aug 6 1997 143252 ASCII N27./C 3A01160C9T219AC09T363.cut sIXf.S3 38 Aug 6 1997 176941 ASCII H274/1CARD51hCO9TOOOAcO9T058.cut G1xf."5 37 Aug 6 1997 174741 ASCII RZ7a/CR3A5N17CO9T15&U 9T29.Cut 8151.536 30 Aug 6 1997 142b0 ASCII u2Z7a/C3A0SN1Thc7219AC09T363.cut c6SE.537 3T Aug 6 1997 176143 ASCII K27J/CR3A05I18DCO9TOOOAC09TlS8.cut 1IXt.538 Aug 6 1997 172662 ASCII N127./C3DSNISODCO9TISAC09T219.cut aIXf.539 AUG 6 1997 141063 ASCII N27a/CR3AO51ODC09TZ19AC09W.cM 6Jll.540 37 Aug 6 1997 173811 ASCII

2 ATTACIWKT X PAP 9 Aug 06 13:30 199 Fl e Nae: mllett 013097ma OO0000-01717-00O-000 LW 00 X

• 9I.S4 ixf.301 30 AG 6 1979 1384C ASCII ASCII M257./~CU6TA27l0COSTOODACUT .S42 s3 A% 6 1997 144162 U27.:C13AO10DC C0T09TACO8T139.CUt *If 6 1997 145962 ASCII I.f43 txt 32 ALg V27y./CL MO210C0TI39AC08T404.cut 31 AL 6 1997 1501U ASCII uA27altc3A27OIDCWT404AC084409.cUt sixf.S44 152312 ASCII 8TSIScut S.45 ixt 32 Aug 6 199 U27 ICU3A2O7 IDCOST4 9ACO 2 AUG 6 1997 132397 ASCII

• 27a/CNAOIOcOT5ISACoqTa00.cIA SIMS4 AScII sixf.547r 30 Aug 6 1997 U087' ler aCU3o K 30OOO 8Tc9T.Cv? Aug 6 1997 16636 ASCII

.f.549 31 ASCII V27a/CR3A27M04C08TO97ACWTI39.Cut 3ug 32 6 1997 148705 K27UC3A27WOM T139ACW0T404.ut sxl.549 2640 ASCII aixf.550 32 Aug 6 1997 15 27u3103A27W02DC8T404AC0T409.cut 33 6 1 Aug 997 155 249 ASCII IZ7a1C3OZCR2708T4WAC409AC6T T5.eu.t t txt .51 ASCII f lx.5.5 5 2 Au 6 1997 13389 NuoZ/CtA2N02DCOBTSIMCWTO D0.cut 409 ASCII ixf.55 3 30 Aug 6 1997 1 tC 27aC33AO NNZ7 DC03S0T00ACuT097.9vt Aug 6 1997 149 ASCII cxu IO3DCOTO97AC8TI39.cut *.554 31 H27.TCR3A/pU 32 Aug 6 1997 149705 ASCII N27a/CR3A271I03DC08T139AC08T404.cUt aIxf..55 1527Z ASCI I lklxf.556 32 Aug 6 1947 N27I/CA13271 0304C08T404AC8s1409.cut Luw 6 1997 156162 ASCII 6ls .57 33 ASCII K7271DCR3A27IOi30CT409AC08T51S.CWt 2.58 8 Au 1996 7U 136 16 K2Ta/CR3A27NO3DC0OTSISACO9T0DOut t.xSt 14293 ASCII TOA8000AC8T09.t cUt . li 3.09 30 Aug 6 1997 H27aMI MOmC2 W 31 Aug 61997 1569 ASCIAI 2I7CR3AM700C087097AC0T139.cut aixf.550 ASCII sixf.561 33 6 g 1997 1502S03 27/atCa3A29 C0TI39ACD8T4D.cut 32 6 Lw 1997 1 5264 ASCII

• 27.1a0cD A7W040C08T44AC8T409.cut xf.f6U ASCII lX..563 33 Au 6 1997 156328 Z2a1C3A27140CO8T409AC08T5I5.cut

• 28 6 A9 1997 13 4982 ASCII N27Y0C OJT51SAC0WTOOOAC09TO ut tf.564 ASCII sIt. .565 30 Au9 6 19971 143056 7 127.C3A27MC5OCOB8TOOACOSTO97.cut 31 6A9 1997 1432 2 ASCIAI N27a5CR3AT085DC08T097C 7AC8T139ut .Ixf.566 ASCIAI sIf.567 33 Aug 6 1997 15026 K27./CR3A2ThD5COSBTK39ACO8T4O4.cut 32 Aug 6 1997 1S5206 ASCII 1271C13A25C08T0C08T404AC0t409.tut t.Stx.568 ASCII

? *lXf. .569 33 Aug 6 1997 1563IS 2 a/C CR3A27DD05DCO8T409ACO1515.cU 28 Au9 6 1997 134982 ASCII NV/CS3A2 L05D0TSC0DOT51O5 t0O.Cut ul f. .570 143222 ASCII t s x.571 30 Au9 16 99 HZraIcZ3AZUMW6OCOSTOOACOBTo97s.cu 1 wAu6 1997 148822 ASCII Z 72a/C3IAZTNOECC0 8TO27ACOSTO39.cut sItf.572 ASCII T404.Cu t i.SX.573 33 Au g 16 9 15lSO6 N227W/CLD27h06DC08T139ACCO 32 Aug 1I9 6 152606 ASCII N27a/c13A7W06DC0 T404AC06 T409.cu t alit.574 ASCII

.575 33 . AL9 6 1997 156325 K27a/CR327706DC08T409ACOT515 .cut *1Xf 134982 ASCII t *Iif.S 76 28 Aug 6 1997 K27&ICR3A27NO6DCOBT5SIACMOOO.cu 30 Au 1997 6 143222 ASCII N27a/CR3A27NO7DCOMTOOOACOST097tus t sIXf.577 148822 ASCII 31 Aug 6 1997 K27ya/c13A70W7AC08197c3 39.cut *IXf.578 33 Aug 6 1997 150369 ASCII m27a/CR3A270 c08T139ACT404.cut Xsi .S79 152U8 9 ASCII T4041C084409.cut .txt.St 32 Aug 6 1997 H27a/CR3A27I07DOCt 33 AUg 6 1997 156328 ASCII 9276/CR3A27K070C08T409AC0OT515.Cut 4tit.581 ASCII olxf.582 28 Au 6 1997 134982 (27.ICR3AZ7IW7DCO8TSISAC09TOOO.Cut 30 LAU 6 1997 14338 ASCII N27a/CR3AZ7 M8TOO8 AC0T097.cut OIXf.5O3 ASCII SIMf.S54 31 Au 61997 14822 N27a1C13A2711l 80CM8T097ACOST139.cut Aug 6 1997 150369 ASCII N27aCLUZ7110DC08T139ACO8T404.cut aIXf.5J5 33 32 Aug 6 1997 15289 ASCII K27Ta/CR3AZ7 8C0T404AC08T409.ut X tf.586 156494 ASCII

.Xf.587 33 Aug 61997 H27a/CL3AMV0DC0T409ACD8TS15.cut 28 Aug 6 1997 134982 ASCII 927a/C3AM7 OBODCO8T5ISAC090ooo0cut atxf.5s ASCII

• tf.589 3D Aug 61997 143283 N27aCR3A 09DCG8TOO4AC8T*97.cut 31 Lu 6 1997 148905 ASCII H27a1CR3A27809DCO8T097ACOST139.sut S If.590 ASCII aIxtf.591 33 AU 61997 150369 27a/CR3AU 19DC08T139AC08T404.eu 32 Aug 6 1997 15313S ASCI I N27u/CR3A271090C0T404ACO8T409.cut *IXf.592 ASCII

• IXf.593 33 AUg 6 1997 156494 N27aC33L27090C08T409AC075I5.Cut

• IXt.594 28 Aug 6 1997 134982 ASCI I 127aIC53A27N09DC08T515ACO9T00.Cut Aug 6 1997 143Z83 ASCII N27.aCU3A27N1ODCOCTODOO OTO97.CUt *tif.S95 30 31 Aug 6 1997 148905 ASCII K27asCR3A2M ODC8TO97ACWT139.cut *Ixt.596 ASCI I aIxf.597 33 Aug 61997 1S0369 N2Ta/CR3AM I00CO8T139ACO8T404.cut 32 Au 6 1997 153138 ASCII KZ7aIC1ZA27U100c08T404AC8409.cut tXt.598 ASCII aIXf.5W 33 Aug 6 1997 156494 N27a/CR3A2711ODC08T409AC08T55.Cut 28 AuL 6 1997 W 899 ASCII 027aIC3A2hMIOCO8TSISAC09TOOO.Sut *lXf.600 ASCII dIXf.601 30 Aug 6 1997 143283 N27a/tC3A7lI11CTO 00ACO0T097.cut 31 Aug 6 1997 148905 ASCII 027aJCa3A27Ul1DC08TO97AC08T139.eut alXf.602 ASCII

• IXf.603 33 Aug 6 1997 1504SZ 027atCL3A27N11DC08T139ACWT404.cut 32 Aug 6 1997 153135 ASCII 027aUCA2M1DCOST404ACU T409.cut *IXf.6K ASCII

• IXf.605 33 AuL 6 1997 156494 1127.1C13A2Th110COST409AM81515.Cut 2B Au 6 199T 134816 ASCII I70CU27110C8T515AC09TOW.Cut aIXf.606 ASCII 1Xf.607 30 AUL 6 1997 143283 27a/OCA27H12MC08TOODACO8T097.eut Aug 6 1997 148905 ASCII N27aICI3A27K12D C8T97ACOBT139.cut *IXf.608 31

• I4f.609 33 Aug 6 1997 1504S2 ASCII H27&fCR3A I12DCD8TI39ACWT404.cut Aug 6 1997 153138 ASCII H27.1CL3AM12DC08T404AC08T409.cut *Itf.610 32

tofiule: he Spinlt IlOWOo-oo170?-0 200

-OO4 4 UV 00 AITACENT ZX - Pace 10 Aug 06 13530 1997 aIxf.611 33 A 61997 156494 ASCII

.27&/CLa27M12DC0T4D9AC08TS15.cut 2t Au 6 1997 W163¶ ASCII Kz7mCL3AZDDC07TS1AC09TOO .6ut d lXf.612 ASC3I

• IXf.613 30 Aug 6 1997 1 H27mICUAZl3DCW8TOOOACoeMT.cut 31 Au 6 1997 182 ASCII N27V.cLAN30CMTO7AtTl39.Cut mSXf.614 ASCII aIXt.615 33 " 61997 1S5052 m27IC3WA27NI3DCWTI39A=T4G4.cut 32 Au 617 1S3138 ASCII H27v=WN Ml30CWT404AC0T409.cut Xf.616 ASCII ixf.617 33 AUW 6 1997 156411 K7Z1CR327N1D3DCO8T409ACO8T515.Cut 28 Ag 6 1997 134733 ASCII N27aIC2l3AZ T13DCO8T5I5AC09TO0.cUt *iXf.618 ASCII

• I l .619 30 Au 6 1997 143222 N27s/CW7U14DC09700AM8T097.cut 31 KW 61997 I4"=22 ASCII g27Cu3AZ7114EC8T097ACD8T139.cut *tXt.6Z0 ASCII siXf.621 33 Aug 61997 1SO9 27aCLA27(14DCM139AC8T404.cut 32 Au 6 1997 1 972 ASCII N27&/CLU3 K4DCD$8T4G4ACUT409.cut *Ilf.622 ASCII COBT49TACOMtS cUt .X*.62 33 Aug 6 1997 1¶3611 27C43AM 28 AUg 6 1997 1416 ASCII H27m/CLUA27v1I4CD8T55ACD9T000.cut *IXf.624 dXt .625. 30 AU 6 1997 143056 ACII H27N/c MISDCOTOOGACUT097.cut 6 1997 1482 ASCII NZ7s/Ct3AZ15DC08tO97AC08T139.cut mixf.6?A 31 AM

• IXf.6Z7 33 Aug 61997 15M ASCII N271C3A7m150CO8Tt39ACO8T4G4.cut Au 6 1997 1S8 ASCII m27s/cL3A27 5DCO8T4AC08T409.cut oliX.6n 32 dXt.629 n A 6 1997 156C11 ASCII 7a/CUA2NISDCD8T409ACA8T5SS.cut Aug 6 1997 13450 ASCII N27a/CI3AZTSDCO8TS5ISACO9TOO.cut alXf.f30 28

• IXf.631 30 ALu 6 1997 142890 ASCII UV27/CR3AZMA16OCO8TOOOACO8TO97.cut Aug 6 1997 148569 ASCI I 27m/C13A211DC08T097ACWT139.cut aiXf.632 31 aiXf 633 32 -Au 6 1997 14995 ASCII v7m/C13Au116oC08TI39ACO08404.cut 32 Aug 6197 1S2806 ASCII W&/7 71C608T4W#ACGT409.cut 6A2 cilf.634 msXf.635 33 Aug 6 1997 156328 ASCII 127m/CLA7 I6CO8T409ACO8TIS.Ccut 134733 ASCII ciXf.636 8 Aug 6 1997 KZ7/aIc3AZ7NI6CO8T515AC09TOOO.cut AM 6 1997 141977 ASCII IQ7/1R3AZ7N7CTODAC08T097.cut iXf.637 30 ItXf.638 31 Aug 6 1997 147490 ASCII a127a/cLA2717DC0C8T097AC08T139.cut Aug 6 197 149452 ASCII H27&/c3A27VlDCM8T139ACM8T4G4.cut *IXf.639 32 mlxf.640 32 *Au 6 1997 152723 ASCII NW7&CILW27117bCO8T404AC08T409.cut Aug 6 1997 15S830 ASCII 1127m/C2AZ7(1?OC08T409AC08T51.cut 6 IXf.i . 33 lIif.642 28 Aug 6 1997 134397 ASCII N127a/CW327Ml7DCD8T5I5ACG9TOOO.cut Aug 6 1997 139708 ASCII fZ7aCR3A2718DC08TO=AC08T097.cUt clXf.643 30 dlXt.64U 30 Au 6 1997 145075 ASCII N271/CR3A27N1DCO8T097ACOT139.cut 32 A u 6 1997 147290 ASCII K27a/C13AZThl8C08T139AC08T4.cut alXf.S5 ASCII aIXf.646 32 Au 6 1997 151391 KZ7ICRUAZ7K18DC8T404ACO8T49.Ccut Aug 6 1997 15S146 ASCII N27a/CuAZ718DC8T409ACT515.wct alXf.647 32 diXf.648 2 Aug 6 1997 132733 ASCII u2z7sCa3A2718C087S1SMAC09TOOO.cut

Aug 06 13:39 i997 file Nam: notesthst A 1D011DOO9D-9U01717200-00o UEV 00 ATTACNWT X - Page 1 Capter Kumber of Fite Date file Size File Tye File Inm File low Print Pages cOutput) (keis) (Forwat)

N04/C04N01Dw0TW7AeCT139.fltes a.X11` 7 Aug 61997 9499 ASCII K04/CMA040t1DCOBTl39ACO8T404.flotes *.xn2 J Aug 61997 9987 ASCI I N04/CAO0401Dm CT404ACOaT409 .ote a.Kf2 a Xf3 a Aug 6 1997 ASCI I 4/CR3A004K010C08T409AC08trtS.rotas m.xf4 a Am 61997 10141 ASCI I N04/CR3A04N010COOT515OAC09TO.not@5 a Au 61997 10477 ASCI I N4/Cc3AO102DC08'r097ACaT139.notes *.Xf5 U Au 61997 9t8 ASCI I Nx4/R3A04U02DC08T139ACOlT404.notes

• LA 61997 10233 ASCII N04/cR3A04N02DC08T404AC0aT409.notes .. xf8 J Aug 61997 10069 ASCII K0/4C3A04N02DCO8T4O9ACOSTS1S.notas a.Xt 9 J Aug 61997 10377 ASCII N04/CR3A04NOZDCOSTS1SAC09TOOO.notes aX.f10 9 Aug 61997 IOUs ASCII 104/cR3A04N0WCOCT097AC0tl39.notes aX.f11 a Au 61997 9857 ASCII ND4/CR3A04N03DCO8T139AC0T40M.nOteS GX.f12 a Au 61997 10535 ASCII N04IC13A041N30C38T404AOOT409.nctes a AW 61997 10013 ASCI I GMx~ 13 AW 6197 10666 ASCII No4/cR3A04KUO3C0OT409AC08TS1S.notes 9 "04cR3AUCO T3515AC09100.nots& ax.f1i 9 LW 61997 10991 ASCII 104/CR3AK04DC08T097AC08T139.notes ex.f 16 a LWg 6 1997 "79 ASCII K04/CR3AO4I04DC08T139AC0T404.notas 0x.f17 t AW 6M199 10497 ASCII K04/CR3A0404DCW8T404ACWT409.not6s eX.fis Au 6o1997 ASCI I 04/CR3A04U04DC0T409AC08T515.rntos M.f 19 9 AW 6 197 10658 ASCII NK04/CR3A4N4DCO8TS1SAC9ToO.notes M.M.O 9 LA 61997 10944 ASCII N04/CR3A04NR5DC08T097AC08T139.rotes mX.fZ1

• LW 61997 9891 ASCII N0I4cR3AKN05DC08T139AC0BT404.rotes aX.f2 t AW 61997 10439 ASCII

• 04/cR3A04NO5DC08T404AC8T409.notes aX.f23 a AW 61997 10070 ASCII N04/C"A0 05DC0UT409ACOT515.notes ox.f`24 9 LW 61997 10614 ASCII moCvR3A04uumOSOC8TS1SACMO0M.notes ax.125 9 AW 61997 10994 ASCI I U04/CR3A04U060CT097AO8T139.notes ex.f26 a AW 61997 932 ASCII u04/cR3A04U06DCWT13AC8T404.notas mX.f27 a Aug 61997 10405 ASCII KD4/CR3A34m06MC08T4O4ACT4W09.nots ox.f2s a AW 61997 10140 ASCII

• 04/CR3A04NO6DCO8T4O9ACO8TSIS.notes a.MM 9 AW 6W197 10610 ASCII Ko4/cR3AO4NO6oCO8TS1SACO9TOOO.n~tes M.xMn 9 Aug 61997 10960 ASCII U04/CR3A04J07DC08T097AC08T139.notes aX.131

• LA 61W7 872 ASCII N4ICR3A04I10TC08T139AC08T404.nots aX. 32

• LA 61997 1082 ASCII N04/1c3AUO4N7C08T404ACUT409.ntoes sx.m3 a AW 61997 10128 ASCII

• o4/cR3AOtN00C08T409AC0BT515.notes aM.34 9 Au 61997 10675 ASCII ASCII N04/cR3A04R07MC08T515AC09TOO0.rnotes a.f35 9 LW 61997 10970 ASCII Ko/lcR3A04NODCO8T097AC T139.notes x.f36 8 LWg 61997 9538 ASCI I Iu0/cR3AKIO80C08T139ACO8T4C4.notes Sm37

• Aug 61997 10460 ASCII F04/CaAR04XODCUT404ACUT409.aotes ax.fss a LW 6M197 10070 ASCII Ko4fcR3A04K08DC08T409AC8T31S.fotes ax.n9 9 Au 61997 10684 ASCII

04/CR3AD4U MC08TS15ACo9lOOOnotes ax.f40 9 LW 61997 109W8 ASCII H04/UR3A4NO9CO8T097Ac08T139.rots MMf41 a AW 6197 9890 ASCII 304/CR3A04N09DC08T139ACO8T404.notes ax .142 a AW 61997 10492 ASCI I 04/C3A04N09MCO8T404ACOBT409.nates ax.143 a LW 6197 10116 ASCII N04CR3A0.NO9C08T409AC08TS1S.mteS ax.tf 9 LWg 61997 10666 ASCII N04ICR3AKNR9DCOBTS1SA009T040 notes aX.f4S 9 AW 61997 10946 ASCII o4/ca3A04U 0cOC8T97AC8T139.notas ax.f" a AL 61997 9876 ASCII N04/CR3A0N10DCOJT139AC08at44.ntes ax. 147 a AW 61997 10498 ASCII H04/CR3A0410D0CT404AC06T409.nts ax.f4 ALW 61997 10113 ASCI I s04ICR3AKNR100DCT409AC08T515.notas X.ff9 9 LW 61997 10632 ASCII 104/CR3AK4N10DCOT515AC09TOO.notes aX.f50 9 AW 61997 10904 ASCII K04/CR3A04N110C08T097ACTU0 9.rots aX.ff1 a LW 6197 986 *ASCII H04/CR3A04NIlDCO0T139AC08T404.notH eX.f52 8 LA 61997 10484 ASCII MO4/cR3A04ll1DCO8T404ACe8T4V9.notei aX.f53 I LA 61997 10176 ASCII NK/CR3A04N110C08T409AC08T513.notes X.fS4 9 LW 6 1997 10624 ASCII H04/CR3AO4N11OCDBTSI5ACO9IOOO.notes ax.f's 9 LW 61997 10J36 ASCII f04,CR3A04N12DCGBT097AC08T139.ncte aX.f56 a LW 61997 9nu ASCII HK2D3AC4U12DCBT139AC4BT404.notas IX.f5T J WA 61997 10510 ASCII N04/cR3A04N1120C0T404AcO81409.notas OX.ff$ a LW 61997 10096 ASCI I N04fCR3A04N1ZDC T409AC085T15.nates &X.f59 9 LW 61997 10737 ASCII 1104/CLUMlDCUTSISACO9TO.notes ax.f60 9 LW 61997 10954 ASCII K04I/AK04130CO8T097ACO8t139.ntes &X.f61 a AW 61997 841 ASCII N04/CR3AL I130DCT139AC08T404.notas a.f62 a LW 6197 10469 ASCI ASCIII 04/Ca3A0413DC08T404AC08T409.notes A363 a AW 6 1997 10132 Nl4KCR3AD4N30C8T409AT08S15.notes ax.f64 AW 6M197 ASCII 9 10711 K04/CM3A0ORCMT1SAC09T000.nates ax.165 9 AW 61997 1094

0 04 17 Page 2 Aug 06 13:39 1997 Ftl Ra: he ot"Ifet g5A0000997F~O Lug0613:9 au:lit~sf 1.000omow wi DO ATTACOMIN X

• NO4/COAD4NV4DCW8T AC08T139.Otf sx.f66 8 i 6 1997 6e ASCII N04/Cu3A04N14Dc0T139AC08T404.ntus ex.f67 a Lw 6 1997 10450 ASCII NUO/CR3AX14DCM4WC T409.rlot.s x.f68 a Aug 6 1997 10166 ASCII K04/CU3A)4Nl4DCO8T409AC08T515.flot u ex.f69 A 6 1W97 1069 ASCII N0/ca3AD4NI4DOC8TS15ACO9TOOO.Ntes mx.970 9 AU. 6 1997 10928 ASCII N04/CmumI5cCD8T097AC0T139.fotvI ex.fTI a Aug 6 1997 9m3 ACII KUO4/cR3AINDCOST139ACD8T404.notn ax.f72 a AU 6 1997 1471 ASCII No&/CAO4XI15DCOST4ACOaT4D9.notvs ax.f73 a u 6 1997 10134 ASCII N04/C33A04N15DC WT409AC08T51S.notes ex.f74 9 Aug 6 1"T 105 ASCII N04/CR3A4Nl15DCO8T515ACO9TOOO. otes mx.f75 9 Aug 6 1997 10m ASCII N04/Cl3A04N16DCWT097AC08T139.mtes 4x.fT6 I Aug 6 1997 9889 ASCII NK4/CR3AUN16DC08T139AC WT404.note ax.fT7 I Am 6 1997 1041 ASCII H04/cR3AO4316DC08T40AC08T409.notes ax.f7s 6 Aug 6 1997 10102 ASCII NKO4CR3AO4Nl6DCOT409ACOT5IS.notes ax..9 9 Auw 6 1997 1068 ASCII NO4Ct3AO4I1dOC8TSISAC09TOO.ntes IX 180 9 Aug 6 1997 1098 ASCII 104/CR3A04N170C8T197AC81139.notes ex.fal a Aug 6 1997 M1 ASCII U04/Ct3A04N170C08T1S9AC0MT4U.nct*s ex.f2 a Aw 6 1997 10402 ASCII N04/CR3A041N7C084T&ACO8T409.fotes ex.f3 8 Au 6 1997 10052 ASCII NUH/CCRt3AO4U0CO8T4O9ACOSTSIS.nteS a.f$4 9 Auw 6 199 10588 ASCII K04/CR3A04K17DC08T513AC09TO0.notes aX.185 9 AM 6 199 10879 ASCII H04/CR3AXK16DC08T097AC0T139.notes ax.fJ6 a Aw 6 1997 9622 ASCII N104/C53A04N180C08T139A T404.notes &.MVr t Aw 6 1997 10052 ASCII N04/cR3A4180Dc08T404AC08T409.notes t..18 a Aug 6 1997 9918 ASCII N04/CR3AO4Ul8DC8T49AC8TI1S.notes Ax.f.9 6 Aug 6 1997 10201 ASCII N04CR3A04N18aC08TS5IAC09TOO0.notes aX.t90 9 4u 6 1997 10681 ASCII O//cR3AOG7NOIOC09TOOOACO9TIS8.noteX G.f9l 7 Aug 6 1997 3836 ASCII N04IC13AU07WODCMT15kCMT219.notes eX.t92 9 AuL 6 1997 11661 ASCII g0/CR3A07WI01DC09T219AC09T363.note.s U.J93 a Aug 6 1997 9212 ASCII K04/cR3ANl02DCW9000AC09T158.nctes eX-t94 7 Aw 6 1997 g97 ASCI I N14/CR3A7N020C09T158ACM9T219.not5 dt.n95 9 AUg 6 1997 11928 ASCII N04/CR3A071102DCMT219ACD9T360.nctuS eX.t96 a Lu 6 1997 9645 ASCII N4/c3A0th0CD9?OO00C*9TI58.nots .x.197 a Auw 6 1997 9189 ASCII N041cm3A0ODC09715UCO9T219.notes ax.f98 10 Au 6 199 121K6 ASCII N04n30?WM CT219AC091363.nrts Sf99 a Aug 6 1W7 9750 ASCII mouC3AZO7ON C09TOOACO9l538.motes 80.100 a . Lw 6 1997 9111 ASCII NO4ICR3AO7M 0CO9TI5kCO9T29.fOtu .xt.101 10. Ava 6 1997 12302 ASCII N04/CR3A07W04DC09T219AC09W363.notes .1f.102 J Auw 6 1997 9u ASCII f/CR3AO7WOI5DCWTOOOACO9TI5Lr.ts .f.103 a Lu 6 1997 9147 ASCII 04/CR13AT7N05DC09T15AC09Z19.notes eXf.104 10 Aug 6 1997 U270 ASCII O4/C3AU7ON50C091219AC09T363.notes .1f.105 a AM 6 1997 963/ ASCII NK04CR3A7MO6CoD9TOACOWT158.notos dtf.106 I Alg 6 1997 92g3 ASCII 041CR3A7OM06WC09T158AZ09T219.note .11.107 1o Aug 6 t997 12188 ASCII N04/CR3Ao 60Co9T219AC09T363.notes OXf.105 a Au 6 1W9 963/ ASCII KO./CR3AO7NO7C0O90OOOACO9TI5J.notes tOt.109 a AuL 6 1997 09 ASCII N04/1C1A07N07CMT138UC09D219.nctes aXt.110 10 AL. 6 1997 12312 ASCII N04/CR3A07N070C09T219ACWT363.notes .xf.111 a Aug 6 1997 9716 ASCII N04nCW3A07T08DC09TOO0AC09T158.notes elf.112 a Lw 6 1997 9175 ASCII N04iCU3AO7MOCTMISBACO9T2I9.notes eXf.113 10 Au 6 1997 12250 ASCII N04/CU3A07W0a0C09T219ACO9T363.notes .1f.114 8 Au 6 1997 98 ASCI I NU4/CZ3AO7WO9MC9TOOOACO9TIS8.rotes olf.1S a Auw 6 1997 9155 ASCII 4cLMA07 9C09T1SAC0T o19.otes .1f.116 10 Aw 6 1997 1228/ ASCII 304/cR3A071109DC09T219AC09T363.notes eXf.117 a AW 6 1997 .9661 ASCII N04/CaA07M10oDC09TOOAC09T1SJ.nots .f1.118 a AuL 6 1997 9135 ASCII K04/CR3AhIoDC09T1s5AC09TZ19.notss o1f.119 10 AuL 6 1W7 1Z270 ASCII N4z/CR3A07K10C09T29AC09T363.notes o1f.120 a Aug 6 1997 9700 ASCII N0./CR3A0Th1tDC09TrOOAC09T58.fotes eX.1.Z11 a Aug 6 197 9101 ASCII K04/CR3AO7ItDCD9T15BAC09T219.notes .Xf.122 10 Aug 6 1997 12264 ASCII NK041C3A07h10CW0T19AC09T363.notes &Xf.l3 2 Auw 6 1997 96U ASCII N04/CR3A07112DC9TOOOAC09T1S8.notes 60f.124 0 Aug 6 1997 9097 ASCII H/04/CR3A07i12)DC9T158AC09TZ19.notu GJf.125 10 AUg 6 1997 12228 ASCII 1104/CR3A07112DC 9T219AC09T363.notes Wf.126 I Aug 6 1997 9620 ASCII 0./CR3A7M13DC9TOO0ACO9TIS8.naotes Xf.127 a Aug 6 1997 9159 ASCII NO4/CR3AO7?13DCO9T15AC09T19.notes .Xf.128 10 Aug 6 199 1Z204 ASCI H04/CU3A7I13DC09T219AC09T363.notes .Xf.129 I Au 6 19" 9658 ASCII

• 04/Ca07 l4DC09TOOOAC09T1S.notus .f1.130 a AuL 6 1"7 9127 ASCII

• 0/CR3A0714OC09T158AC09T219.notes .Xf.131 10 Au 6 1997 1225Z ASCII 104/CRA071114DCOZ9ACO9T363.riotnz m1f.132 a Aug 6 1997 9716 ASCII 1104/CR3A07150C09TOOOAC09T1S8.notes eXf.133 a - AU 6 1997 9171 ASCII K04/Ct3AM7IISDCO 9T15UAC09TZ19.notes mXf.134 10 AuL 6 19T 12234 ASCII N0./CR3AO7T1SDC09T219AC09T363.notus eXf.135 0 Aug 6 1997 9712 ASCII

0 Aug 06 13:39 1997 Pt*l V" ntstzist AuOOOOOO-3 9 lt-ttG0-t W uEV oo ATTACOM x- Page 3 N04I/CAWl16D@CMOACO9T15S.noti4 OXf.136 7 6 1997 916 ASCII 10 Li 6 1997 12M0 LSCII am/mum3Am7II1DC09T153AC9T219.note elf.137 b04/C3uf W1CZ19AC09T30.noteS eXf.138 a 19W7 990 ASCII elf.139 7 Lug 6 1997 ASCII Num4 uMC09TOOMMA7CT15.Ote KG4/Ch3A4 1TDC0 2158AC029.at" aX .140 10 Lug 6 1W7 12069 ASCII N04I/A07N170C09TZ19AC09T363.AotOS eUf 141 a Aug 6 1W9 9704 ASCI I D4CRAO7lDCmO 0Ac9Tr5I.notee oxf.142 7 LWg 6 19T ana ASCII N04/fAO7N1DC09T1ISAC09T219.nts tf.1U3 9 LWg 6 1997 11841 ASCII N04/C53A0W1DC09T219AC09T363.notes O1.144 a Aug 6 1997 938 ASCII Compiter Tape Backup lurber of. File Data File SOz File TM.

Flle EarnS file Iaoe Print Pages (Output) (Bytes) (Format)

I12J33A12UOlDC08T097ACO8T139.not2s exf.145 7 Aug 61997 9347 ASCII

.1Z/CR3A12MUOlC08T139AC08T404.notes .11.146 a Aug 61997 9831 ASCII u12/CR3A12MU01DCOT404AC0T409.nots oxf.147 a Aug 61997 9454 ASCI I h12/CR3AI2NU0DCOST409ACOBT5IS.otes axf.148 a Aug 61997 10021 ASCI I UK2Ic/CIL2MOCOCSTSIACO9TDOO.mtes 'f.149 E Aug 61997 10303 ASCII KHC1U3A12NO2DC8T097LAC0T139.not6s aXf.150 a Aug 61997 9068 ASCII U12/R3AUOMCW8T139ACWT4U.ntes, exf.151 a Aug 61997 10156 ASCII U12/CJ312U02DCW8T404A T409.notes mlf .152 8 Aug 61997 9861 ASCII K12/CR3A12N0DC08T409ACt0TIS1.nota mXf.153 a AUL 6 1997 10163 ASCII

.12/3A1NU0DC0T515AC9TOO.ntes 0f.154 9 Aug 61997 1064Z ASCII N12/CR3A12U03DCC0T097AC08T139.Uots elf .153 Lug 61997 9715 ASCII N12/CR3A12U3DCT139A CMT404.fotes .11.156 6 AuL 61997 10345 ASCII h12/CR3A12J1030CCT404AC08T409.nots aXf.157 6 Aug 61997 9863 ASCII HN2/C*3A1i203C08T409AC0S751S.ntn axf.151 9 lug 61997 10412 ASCII E12ClE3A12NO3DC08T515AC09TO0D.notff alf.159 9 Aug 61997 10645 ASCII N12/cR3AMUDO40C03TWACOT139.notes oxf.160 8 Aug 61997 751 ASCII V12/cR3AZNi 4DCOJT139MACJT404.notns elf.161 a AUL 61997 10355 ASCII u12/cR3A120DCWT404AACOT409.afOts elf.162 a Aug 61997 "E57 ASCII E12/CR3A12NO4CD8T409ACt0T515.notOs lf .163 9 Aug 61997 10452 ASCI I Kl1/CR3A12nMCO8T515AC09TOW.rlta 9 Aug 61997 10704 ASCI I u12/CRaA12N05DCDtT097AC0T139.notes 8 .WAug 61997 9755 ASCII K2I/cR3A12N05DcOJT139Ac08T404.notoe eXf.166 LWAu61997 ASCII 2/CR33A12N05DCO8T404AC08T409.nots def.167 WAug 61997 9196 ASCII N12lcR3A1NDO5DCo8T49ACOMTSl5.notes alf.163 9. Aug 61997 104S0 ASCII N12/CR3A12N05DC08T515AC09TOOO.nltes alf.169 9 Aug 61997 10710 ASCII NI2/CR3A12N06DC08TO97Ac0T139.lotOs aXf.170 LAug61997 9755 ASCII u12/R3A12UN 6DCWtT339AWST40.nOtT elf.171 5 LW~~P 61997 10313 ASCII

/CU3At2Un6DCO8T404ACC8T409.notas exf.172 8 l ~~Aug LW 66 1997 m7 9898 ASCII NI1/CR3A12N066D8T409ACC8TS15.notes. aOf . 173 9 Aug 61997 10418 ASCII Kl2/CR3A12D06DCOJT515AC09TOOO.notes eXf.174 9 LW 61997 10700 ASCII N12/CR3AZNO7DC0O8TO97AC08T139.notes elf.175 WAug 61997 9725 ASCII f12/CI3Al1M07DC08T139ACOtT404.notes Xf .176 8 WAm 61997 10317 ASCII KYZtCR3AI2zo7DCoaT4O4ACOST409.notes oXf.177 8 Aug 61m7 9924 SCII KlZ/CR3Al2NU7DCOJT4W9AC08TSIS .notes 40.178 9 Aug 61997 10432 LAug61997 ASCII K1CI3AI2Ul07CO8TS15ACO9TOOO.notes aXf.179 10696 ASCII 112/CR3A12Ul080CO97AC08T139.nIotes atf.180 WAug 61997 9m ASCII

/RI3A12lNOJDUT139AC0tT404.notes Xf .181 WAug 61997 10315 ASCII NIZ/cR3A12010cD8T404AC0ST409.notes Xf.182 8 WAu 61997 9924 ASCII N12/=c3Al2N0BDC08T409ACW8T515.notaz elf.103 9 Aug 61997 10430 10700 ASCII ulZ/3CLR13N0Z808T51SAC09TOO0.notes eXf.184 9 Aug 61997 ASCII N1ZICR3A12090 CMT097AC08T139.notes aXf.185 8 Aug 6'1997 9,724 10303 ASCII KlIVCR3Al1209DC08T139AC08T404.notes elf.186 8 Aug 61997 ASCII UC/RAl12N09DC08T404AUCOT409.notes elf.187 a Aug 61997 9912 972 10410 ASCII Nl1/C3AIZUn9DCWT49ACO8TSl S.notes elf.188 9 Aug 61997 ASCII NlV/CR3Ai2NO9OC0BTSISAC09TOOO.notes elf~189 9 Aug 61997 10702 ASCII 112,CR3AI20ODCO tTl97AC0T139.notes exf. 190 a Aug 61997 10291 ASCII U1CR3AU12M1ODC0T139AC T404.note ef.191 a AuL 6 1997 9912 ASCII NIZ/0R3AUNIODcUTM404AC08T409.nates elf.192 E AuL 61997 11Z/CR3Al2CiODCOBT409ACOT51S.notes aXf.193 9 Aug 61997 104K0 ASCII 10694 ASCII h12m/C3A12N10O081515AC09TOOO.notes eXf.194 9 ALW61997 9709 ASCII 112/cA1ZN1108D1097AC08T139.notes eXf.195 a AuL 61997 ASCII K12/CR3A1I?11DC08T139AC08T404.notes f.196 8 WAM 61997 1C302 E12/CR3AlZM11DCO8T4O4AC08T409.1otes axf.19r 8 LW 61l997 9922 ASCII 10404 ASCII N12/CR3Ai21iIDCOIT409ACO8TSIS.notes elf.198 9 Aug 61997 ASCII N12/CR3A2lWIiODC0TS1SAC09TOOO.notes elf.199 9 Aug 61997 10696 MSCII NIZ/CR3AIZN12DCO8TO97ACO8TI39.notes elf .20D a Aug 61997 9719

ALw906 13:39 1997 Fitl N-es natestst 11MOODOO-i67-1ZOO -00044 REV X0 ATTACNT K - pae 4 g1ZVCR31A21t2DC08T139AC08T4O4.no*ts axf.2N1 a £ug 6 1997 10310 ASCII u121C2tA12H120C0T404AC0r409.rot~s aIf .202 8 Aw 6 1997 96 ASCII HSl/CRA¶12DC0ST48T09AC08T515.notas GUAM 9 AM 6 1997 1041Z ACII N12/CRLI2N1aDCOTSISAco9Toco.ntas sXf.204 9 A 6 1997 1071 ASCII 12U3N1C08TOSI C08T139.Ates oxf .o5 a Au 6 1997 vny ASCII N12I/CA1NA130C08T139ACS0T404.nrotes f.206 a Au 6 1997 10302 ASCII

• 12iCU3A12N1i3C08T404AcCOT4o9.notes a.f.207 O Aw 6 1997 906 ACII NiZ/C3A12N130C08T409AC0TS15 .notas af.208 9 Lw 6 199 10406 ASCII IZI1cRUAIDDCOUT3I5LSC T .notes af.209 9 u 6 1997 10M ASCII N12/CR3A121140C08T097AC08T139.notes .1.210

• Aw 6 1997 95 ASCII NIZ1C13A121X 4CO8T139AC08T404.notae axf.211 a Aw 6 1997 10319 ASCII N12/CR3A¶2N14DC0ST404ACOT409.nates axf.212

• Aw 6 1997 900 ASCII Z/CRIAMI14COWT409AC8TSIS.notes af .213 9 Aug 6 197 10404 ASCII hZ2/CR3AL2K140CM T513AC091000.notes alf.214 9 wAu6 1997 10708 ASCII 112/C3A12MISDCORT097AC08T139.notas *axf.21S a Aw 6 1997 975 ASCII 12/CR3A12N915DC0T139AC8OT404.nats alf.216 a Aw 6 1997 10311 ASCII 12/0C3A1215C08740CU8TU 9.nts WAIT.217 a Au 1997 9922 ASCII HNZ/C33A12N150C08T409AC08T515.notes axf.21 9 ALw 6 1997 10400 ASCII N12/CR3AIZ2JlS COBTSISAC9TO000.Mmta af.219 9 Aw 6 1997 1070 ASCII HZ12CU3A12N16DC08T097AC8TU19.ntes af.220 ALw 6 1997 9751 ASCII NI2/C3A12N160CC8T139AC08T404.natas &Xf.221 a Au 6 1997 137 ASCII N121CR3A1Z216DCO8T404AC08t409.notes alf.22 a ALw 6 1997 966 ASCII 1112AC1A12H0DC840ACO8t5I5.mtes f.223 9 Aw 6 1997 10453 ASCII

• 1Z/CR3AIZM16OCO TIISACD9TOOD.notes alf.224 9 Aw 6 1997 10712 ASCII K2/CR3A12N170C08T097AC08T139.notus .1f.22 I ALw 6 1997 9715 ASCII 312/c1A312N17bC08T139ACO8T404.nots .1f.226 I Aw 6 1997 10258 ASCII KZ/CR3A12N17bC08T404AC08T409.notes a.f.227 a Lu 6 19 907 ASCII K12C/C3A12117DC8T409AC08T515.notas f.22 I AU L 6 1997 077 ASCII IZ2/CR3AI2Ni7DCO8TSISACO9tOO0.ata af.229 9 Lu 6 1997 1067 ASCII 1Z1/CRA12NIaDCO8TO97AC08T79.nots af.230 a AuL 6 1997 9498 ASCII N12/CS3AI2N1IOC08TI39ACOT44.notos .Xf.231 a Aw 6 1997 960 ASCII I2ICR3Ai21W8DCOST4OGACOST409.notes olf.232 a ALw 6 1997 96s ASCII N12ZCi3A1ZN18DCO0T409AC8TIS.rkltas o1f.233 8 Auw 6 1997 10092 ASCII N1V/CE3AI2N18DCO8TSIACO9TOOO.t. a f.Z34 9 ALw 6 1997 10508 ASCII N1/ACRSA OIDCO9TOBACO9tIS.notus o1f.235 7 Auw 6 1997 62 ASCII Y12/CR3AISNOlDC tISlUC09T219.notus .1f.236 9 Auw 6 1997 11642 ASCII 112/C33A181010C0 19AC09T363.notes af.237 a ALw 6 1997 9119 ASCII 12/CR3A1N0ZDCOWTOOOAC 158.mtes Gf.238 7 Aw 6 1997 817 ASCII NIZcR3IS8O2DC9IISCO9219.notes atf.239 10 ALw 6 1997 11921 ASCII NlZ/CR3A18N0ZDC09T219AC09T33.lltes aXf.240 a ALw 6 1997 9416 ASCII NI2/CR3A1I03DCX9tO0 CAC09TIS8.otas &l1.241 a ALw 6 1997 6949 ASCII N1/CR3A¶60DC09T158AC09T219.nots Wa.242 10 ALw 6 1997 12016 ASCII HNUCRUA18N030C09T219AC09T363.notes .Xf.243 a Auw 6 1997 9462 ASCII 11I/C13A8I1040C09T0OC09T158.note aXf.244 8 ALw 6 1997 8947 ASCII HNICR3A1N040DC09T158CO9219.notes .1f.245 1G Aw 6 197 1195 ASCII H12C3A1804oCC9TZI9AC9T363.notes alf .246 a Au 6 619 W9m ASCII N12/CR3AIJQ5DCO9TOAC9T¶58.rotes .1f.247 6 ALw 6 1997 3947 ASCII K12/C33A15CMT58CM9219.nvtes a4.243 10 ALw 6 1997 12013 ASCII NIUCRUA1lMOC0219AC09T363.rate alf.249 a ALw 6 1997 531 ASCII NIUtCRUIUO6OCO9tOOOLCn9TIS.nts alf.250 a ALw 6 1997 8939 ASCII NRICR3AUMOM6OC A9TI58CO9TZ1P.ote af.251 10 AUL 6 1997 12013 ASCII N2/CR3A1U060C09T219AC09T363.notes Xtf.252 a Aw 6 1997 90539 ASCII NUC3AIU7MCOO9TCAC9tIS8.nots of.253 a Aw 6 1997 6933 ASCII N121CR3AIN670C09T15UC09T219.notes alf.254 10 Aw 6 1997 12013 ASCII UCRU3A1UIDC09T21C09 .nots al.255 I AL 6 1997 9573 ASCII UCU3AIO8DCM9T0OAC09T153.notes alf.256 a ALw 6 1997r 943 ASCII N12103A1OMCMS5BAC09T219.nots a .257 10 Aw 6 1997 12011 ASCII Il2/CA3A1J1OJDC0tZ9AC097363.notns aXf.258 a ALw 6.1997 9587 ASCII NIZICR3ALIN09DCO9tOOOACO9TI58.notes Of.259 a AuL 6 1997 3943 ASCII RU1CR33L1090C097158AC0t219.notes f.260 10 Aug 6 1997 12013 ASCII K1ZfC3L18109C0T219AC09T363.tes .1f.261 S AuL 6 1997 9589 ASCII U1I2CR3AI8100CD tO9 AC09TIIa.rotes tXt.26Z a Aug 6 1997 8937 ASCII NIZCR3AIUNIODCOtI58MCO9T219.notes .1.263 10 AuL 6 1997 11989 ASCII NIUCR33A18N100C09219ACC9363.notos xf.264 I AUL 6 1997 9587 ASCII E12/CR3A1N11DCC09T00AC09T158.notes .1f.265 a Aug 6 1997 6935 ASCII K2ICLI811DC09T158AC09t219.nots af.266 10 Aw 6 197 11993 ASCII NI12CI3AIU1IDC09T219AC09T363.notes aXf.267 a Aug 6 1997 9577 ASCII NI1/CR3AL112DC09tOOAC09t158.rwotes dtf.268 Aug 6 1997 6937 ASCII NI2/C33A18N12DC09T15UC09M219.nlotas oXf.269 10 AuL 6 1997 11997 ASCII NIZ/CR3A1N1ZD0C0T219AC09T363.notes Xfl.270 a Aw 6 1997 9632 ASCII

Aug 06 13:39 IW7 File Sam: noteallat Aug 61:39199 105g11t FieUue:

BA000OM-0il.OZ-0200-0o REV to ATTACUNENI X - Page 5

• 1ZlC33A18N13DC09T000AC09TZ15.hotes alf.271 ug 6 1997 99 ASCII hIct3AI8N13OC09T58AC09T219.Mt* olf .m 10 Ai 6 199 119 ASCII U121C13A18N13DC09r219AC091T3.notes *Xf.275 a Q 6 199 9 ASCII NIZIC3A1I814OC09TOOOACT5I.nct5 sf.274 a AUG 6 19 ASCII v121UAU1140CC9T15&AC09T219.fot*S UfLM 10 A 6 199 11989 ASCII v12Uc3A18M140C9T219AC09T363.nots UfL a Au 6 1997 9690 ASCII N,2/cA181UDC09TOA0T1.notes alf.277 a Aug 6 1997 39 ASCII O1MC23A1 1 9T15SAC09T219.JOS oxf.2 10 Aug 6 1997 11991 ASCII RiZ/C33A1St1DC09T219AC09T363.ntts eXf.279 a Aug 6 1997 984 ASCII N1ZCRUAIU16DC09TOOAC9T158.not" eXf .2W0 7 Aug 6 1997 3906 ' ASCII 912/CR3AI88ISDC09TISUACO9T2.9rbots axf.281 10 Aug 6 1W7 12003 ASCII NIZ/CU3At186DC09T219AC09T363.otWs aXf.23U a Aug 6 1997 94J0 ASCII 1Z/CRAIINMthCO9T0WAC09TI58.lnotes aXf.283 7 Aug 6 1997 tJ6w ASCII N12/CA3AI8N17OCOT5UACC9TZ19.rptes axf.2J4 10 Aug 6 1W7 12016 ASCII N1Z/CR3A1N17DC09T219AC09T363.notes Xf.2J5 a Aug 6 1997 9460 ASCII N1Z/CR3AISNIUDC09T@00AC09T58.notes oXf.286 7 Aug 6 1997 6664 ASCII HN2/CR3AIUNI8DCO9TWISBACT219.notes oXf.287 9 Aug 6.1997 11690 ASCII H12/CLAU8NUIC09T219AC09T363.notes xf .288 a Aug 6 1997 9364 ASCII Caoputer Ta lackup kuwber of File Date File Size File Type File mam file mam Print Pages Cutput) (Bytes) (Format)

N23/CR3A16IOIDC09TOOOAC09TIS5.notes Xf.209 7 AuW 6 1997 8786 ASCII a23/CR3AI6NOlDC09TiSBACO9TZ19.notes oXf.290 9 Aug 6 1997 1191S ASCII KZ3/CR3Al6N10DC09TZ19AC09T363.nots aXf.291 a Aug 6 1997 9323 ASCII N23/CR3AI6NO2DC09TOOOAC09TI58.notes .Xf.m 7 Aug 6 1997 1987 ASCII Hz3/C13A16N02DC09T138AC09T219.noteu o1f.293 10 Aug 6 1997 12217 ASCII N23/Ct3Al6N#DC09T219ACO9T363.notes aXf.294 a Aug 6 1997 9608 ASCII N23/CRSAI61i3DC09TOOOAC09TISS.notes aof.2 8 Aug 6 1997 9201 ASCII N23/C33A6103D0C09T8AC09TZ19.notes oXf.296 10 Aug 6 1997 12286 ASCII N23/CR3A161103DC09T21AC09T363.notea .1.297 a Aug 6 1997 9656 ASCII N23/CR3Al6NO4DC09TOOAC09TSJ.fnotes olf.298 0 ALg 1997 9195 ASCII U23/U3A604OCO9TISBACO9T es9JneS axf.299 10 Aug 6 1997 122S ASCII H23/CR3A16104DC09T219AC091363.ntes atf.300 a Aug 6 1997 977 ASCII N23/CR3Ai6NO5DCO9TOOACM9T158.notes Xf.301 a Aug 6 1997 9167 ASCII K23/CR3A16K05DCM9T15UC09T2I9.Iotes Xf.302 10 AuL 6 1997 12209 ASCII K23C3A161050C09T219AC09T363.notes eXf.303 a Aug 6 1997 9942 ASCII I23/CR3Ai6N6ODCO9TOOOACO9T1JS.notes .Xf.304 a Aug 6 1997 9131 ASCII NZ3/CR3A16NO6DCO9T15UC09TZI9.noteZ .Xf.305 10 Aug 6 1997 12325 ASCII HZ3/CR33A1606bCMT219AC09T363.notes &Xf.306 a Aug

• 1997 9950 ASCII NZ3/CRIA16NO7DCO9TOOOAC09TISI.notes oXf.307 a Aug 6 197 9097 ASCII N23ICR3A16N07DC09T15AC09T219.notes oXf.308 10 Aug 6 1997 12305 ASCII N23/C13A16N07bC09TZ19AC09T363.notes aXf .309 a Aug 6 1997 9958 ASCII N23/CR3A16NO8DC09TOOOACM9TIS8.noteI 1Xf.310 a Aug 6 1997 9113 ASCII N23/CR3A16N080C09T158AC09TZ19.notes aXf.311 10 Aug 6 1997 12Z49 ASCII N23/CR3A16N8DC09T219AC09T363.notes aXf.312 8 AuL 6 1997 994Z ASCII N23/CRA16NOWC09TOOOACO9TI5.notes oXf..313 AuL 6 1997 9195 ASCII N23/C3A16109DC09T158AC09?219.hotes ef.314 10 Aug 6 1997 12287 ASCII N23/CL3A16N09DC09T219AC09T363.notes axf.315 a Aug 6 1997 9902 ASCI I g23/CRa316UlOC09TMOOAC09T158.notes atf.316 a AuL 6 1997 9177 ASCII N23/CR3Ai6IlCDC09TIS8AC09TZ2I.note a*X.317 10 Aug 6 1997 12257 ASCII H23/C33A16U1ODC09T219AC09J363.nots Xf.1518 a Aug 6 1997 9980 ASCII NH3/C13A6lIM1DCO9TOOOACO9TIS8.notes oXf.319 a Au 6 1997 9179 ASCII N23/3A16N11DC09T158AC09TZ19.notes dtf.520 10 Au 6 1997 12237 ASCII N23/CR3A16#11DC09T219AC09T363.notes tf.321 a Aug 6 1997 9960 ASCII N23/CRAI6N12DCO9TOOOAXC9II53.wotas al.322 J Aug 6 1997 9203 ASCII N23/CR3A6N12DCM9T158AC09T129.notes aXf.323 10 Aug 6 1997 12259 ASCII N23/CR3Al6Nl2DCO9T219AC09T363.nots a&Xf.324 a Aug 6 1997 922 ASCII N23/CR3AI61113DCO9 000ACO9TISE.notes axf.325 a AuL 6 1997 9155 ASCII 123/CR2A1611130C0T1S8ACU T219.notes aXf.326 10 Aug 6 1997 12273 ASCII l23/C3A16U3DC09TZ19AC09T363.notns aXf.327 a Aug 6 1997 9914 ASCII N23/CR3AI6H14CD9TOOaAC09TIS8.nots ft .328 a Aug 6 1997 9151 ASCII N23/CR3A16N14DC09T15AC09TZ19.nots eXf.329 10 AuL 6 1997 12195 ASCII 23/C33A161140C09T219AC09T33.notes elf.330 a AuL 6 1997 9966 ASCII KZ3/CR3AI6115DCM9TOGAC09TIS.notes oXf.331 a AuL 6 1997 9195 ASCII N23/CR3A16NI5DC09T1S8AC09T219.nates etf.332 10 Aug 6 1997 12271 ASCII N23/C13A161150C09T219AC09T363.notas Of.333 a Aug 6 1997 9890 ASCII NZ3/CR3A16N16DCOTOOACO9T158.notes dtf.334 7 AuL 6 1997 9106 ASCII N23/CR3A16N16DC09T15AC09TZ19.notes aXtf.335 10 Aug 6 1997 1277 ASCII

06 13:39 1997 FRIe Iuse: notestlt g&A000000-01717 4 2?0 O4£0044 KU o ATTACHET X . Page 6 Nu23lRAmimt609T2I9ACO9MT303idtei exf.36 a A 6 1997 9726 ASCII 10tCXAi6mi7bCO9TOOOAUC9TI5.notes Xf. 7 ug 1997 9126 ASCII U/CLU16K17D CMT158AC09T219.nottS eXf.338 10 l 6 199 12266 ASCII nJCR3A161170CMT219AC09T363.nates eXf.339 a Aug 6 1997 9710 ASCII K23/0C3AU6N180C01000AC0T158.otes olf.3o 7 Aug 61997 847 ASCII N23/cLA161N18IC09TCSMA09T19.Iiote sltf.3l 9 LAg 6 1997 11962 ASCII N23/CL3A16N1IOC7T29AC09WIS3otes &Xf.3 a kAug 6 1997 9608 ASCII N23/COA3010CO8T 7AC8T139. otS aef .3 7 Aug 6 1997 9507 ASCII I123/CLUZ3 010CC8T139AC0T404.nates aox.34 a Aug 6 1997 966 ASCII N23/C53A3Ui010C08T404ACUT409.nates &lf.3/.4 a Au 6 1997 9594 ASCII H23/CR3AZ3NiOCO8T409ACOBTSIS.noteS axf.36 aEw 6 197 1014S ASCII H23/CR3AZ3NOIDCOSTISACMOT .ntes at f.37 a Aw 6 1997 10695 ASCII N123/CL3A 0ZDCU8T097Ac8T139.viteR lf .348 6 Au 6 1997 "18 ASCII N23/cA02DC08T139ACOST404.notes aX 49 a Aug 6 1997 10266 ASCII N23/CR3A23M2DC08T404AC0T409.notes elf.330 a Aug 6 1997 93 ASCII 23/c3A23N02DC8T409AC8T515.notes axf.351 I Au 6 1997 10259 ASCII N23/CRAZ3MOZDCOUT5ISAC9TOO.niotes Xf .35Z 9 Aug 6 1997 10860 ASCII 1123ICAR23A 3DCOa8T097ACO8T139.otf UfL.353 a ug 6 1997 9817 ASCII 23/CRA3MO3DCO8T139AC08T404.notes eXf.354 8 kg 6 1997 10473 ASCII N23/CR3A231103CO8T404ACOBT409.rotas exf.35S a Aug 6 1997 10038 ASCII Z3/CR33A 3N030C0T409AC0T115.notes OM.3%6 9 Aug 6 1997 10 ASCII Z3/CRAZ3nO3CO8TSi5ACO9TO=.rwtes mXf.5 9 Au 6 1997 o899 ASCII u23/CiL3A23040CUT097AC8T139.notes sXf.353 a ug 6 1997 97 ASCII H231CRLA3NOCc8T139ACOJT404.notes axf.359 a Aug 6 197 lO0S ASCII H23CL MC0T40ACM8T409.lotS etf.360 a Am 6 1997 O189 ASCII K23C33A23N4WCU8T409AC08T13.nlates UXt.361 9 AuL 6 1997 10652 ASCII K231CR3AZ3NO4OCOBTMSACO9TO0O.notes elf.362 9 AuL 6 1997 10946 ASCII N23/CR3A23N05DCO8T097ACOST139.notes eUf.363 a AuL 6 1997 9891 ASCII N23/CR3A23NO5DCO8T139AC*T404.notes xf .364 8 Lw 6 1997 10463 ASCII 123/C323U05DCOJT404AC08TU9.notes ef.365 a Aug 6 1997 10148 ASCII 231CAZ3M05DC0T6409AC08T515.notes Uf.366 . u 6 1997 10646 ASCII K2/CR3AZ3MO5DCOBTSSACOTOOO.notes lf .367 9 Lu 6 1997 10984 ASCII 23I/C323lil6DC08TO97Ac0tTl39.nots sft.368 a Am 6 1997 981 ASCII 23tCAZ31106DC08T139ACOOT404.rotes eXf.369 a Lu 6 1997 10431 ASCII N231cR3A23MO6COBUT40 8T409.notes lf .370 . Aug 6 1997 10126 ASCII N23ICR3A23NO WC08T409AZ08T15.notes alt.371 9 AuL 6 1997 1058 ASCII H23/CL3A23NWOCO8TSISACO9TOO.notfs eXf.372 9 Aug 6 1997 10912 ASCII H23CR3AZ3N070C08T097ACO8T139.note eOf.373 a AuL 6 1997 9859 ASCII N23ICR3AfNO7bCWTI39AC8T4U4.notes dXf.374 a Lu 6 1997 10459 ASCII H23/CLAN7C0T404ACO0T09.notes sXf.375 a AL 6 1997 10148 ASCII N23/CR3AZ3117DCO8T4C9AC08TSIS.notes aef.376 9 Aw 6 1997 10698 ASCII N23/CR3A23NO07CO8ISl5ACO9TOOO.notes Xf.377 9 Au 6 1997 10904 ASCII K23/C3A23NDBCO8T097AC08T139.notes eXf.378 a Aw 6 1997 9870 ASCII W23/ClAOD CO8T139AC08T404.notes eXf.379 a Aug 6 1997 1061Z ASCII N23/CR3AN108DCD8T404ACOtT409.noten eXf.380 8 AUL 6 1997 10106 ASCII H23/C33A23t8cOC8T409AC08TSI5.nott .tf 381 9 AuL 6 197 10664 ASCII u23/CR3AZ3NO8OCOST5ISACO9T0OO.notes aXf.32 9 AL 6 1997 1089S ASCII N23/cu3Al3l09DC08ro97ACOtT139.notes exf.383 a ug 6 197 9902 ASCII N231CR3AZ3NMCO8T139AC081404.notes &Xf.354 8 ug 6 1997 10453 ASCII K23/C53AZ3N009COt7404AC08T409.notes eXf.385 a Au 6 1997 10125 ASCII M23/CR3A23NO9DCO8T4O9ACO8TSIS.notes aXf.336 9 Aug 6 1997 10622 ASCII H23JCR3A23109DCO8T515AC09TOOO.notes aef.38 9 Aug 6 1997 1088 ASCII 123/CRA23N100DC0ST097ACO0T139.notes exf.388 8 Aug 6 1997 W24 ASCII Z23/CR3AZ3HlCDC08T139AC08UT04.nots elf.389 8 AuL 6 1997 10U45 ASCII Kn3/C3AZ3N100DCMT40WAC0T409.notes elf.390 a Aug 6 l17 10116 ASCII 23t/CRAZ33210DCOST409AC08T515.notne eXf.391 9 Aug 6 1997 106m ASCII I1Z3/CUAZ3INi0DCOSTSISACO9TOO.notns eXf.392 9 Aug 6 1997 10986 ASCII K23/CR3A211DC8T097AC0T139.notes dtf.393 a AuL 6 1997 9S90 ASCII N23/CL21111DC08T139ACWt4D4.notes lt.394 a Aug 6 1997 10475 ASCII 2U31C 8T4110C4041CtT4W natn &Xf.395 a Aug 6 1997 10180 ASCII IZ3/Cl3A3l11DCO#T4W9ACWTS1S.pWt olf.396 9 Aug 6 1997 10626 ASCII E23ICLUAZI D CO8TS1IAC09TOOO.notes eXf.397 9 AuL 6 1997 10946 ASCII K23/Ct3A23o12DC8T097AC08T139.nates eXf.398 a Aug 6 1997 9m4 ASCII U23/CR3A23N12DC0T139ACOBT404.notes eXf.399 a Aug 6 1997 10426 ASCII 123/CE3A23N12DC08T404AC081409.notes aXf.400 a Aug 6 1997 10152 ASCII U23/CI323N11ZDCO?409AC08TSIS.notes elf.401 9 Aug 6 1997 10632 ASCII 123/CR3A23N120DCOT515AC09TOO .noten dXf.402 9 AuL 6 1997 10974 ASCII H23ICa3D23CC08 T097ACOtT139.note ef .403 8 Aug 6 1997 9856 ASCII IZ3/Cl3A231113DCOT139AC08T404.notes ef.404 I Aw 6 1997 1048 ASCII 3/CRl3A13DCOST404ACOST409.notes ef.405 a Au 6 1997 1083 ASCII

Alug 06 13:39 1997 File Nam: mtntist 0mA0M000O717-0200.000A RlEV 00 ATTACNIT X - Page 7 v23/I3Af1ZxC8T4C9ACWTS15.; 6tij oxf .406 Aug 6 1997 10632 ASCII 323/C33U23tDCOATS15AC09TOOO.notes eXf.407 Aug 6 1997 ASCI I Nz;/Ct33Am23 v4 T097AC0TI39.notes oXf.408 Aug 6 1997 ASCII K23/C33Al114DCO0T139A008T404.notea eXf.409 6 1997 10431 ASCII

/C3UMcUA40cO4ACUT409.noes oXf.410 AMB 6 1997 10052 ASCII 123c3ALU3N4D0E0T409AC08TS13.nots exf.411 Aug A41 6 197 10640 ASCII N23/CNA23 DC0815AC09TOGO.notes etf.412 Aug 6 1997 10896 ASCII n2/CR3L23Nl5DCO8T097ACO8T139.uiotes exf.413 AuA 6 1997 934 ASCII N23/CR3A23N15ED08Tl39AC08T4K.sotes e0.414 ALu 6 1997 10463 ASCII N23/CRUAE3N15D8T404ACC8T409.motos eXf.415 Aug 6 1997 10070 ASCI I N23/c33A23N15DS08T409ACOMTI1S.lotes elf.416 6 1997 ASCI I lU3/CR3 N 50O8TSAC09MTO0.mt eXf.417 AW 6 1997 10954 ASCI I N23/C23A23NI06C08T097ACO8T139.rotes Xlf.418 AAl 6 1997 ASCII 0/CJAt23N160C08T139AC0T404.notes eXf .419 6 197 10475 ASCt I 2/CR3A23M16DCO8T4D4ACC8T409.ncts aXf .420 Aug 6 1997 Auo0 10040 ASCI I H23/CR33A23N1i6C8T409AC00T515.notes xtf.421 Lug 6 1997 10616 ASCI I N23/CRJA UDCOMTISA 1TOOO.fotas etf.422 Aug Aug 6 1997 AA 10944 ASCI I H23/CR3A23i170CCT097AC08T139.notes elf.423 Auo 6 1997 849 ASCII N23/CR3A2CN17bCWT139AC08T404.notes Of .424 Aug 6 1997 1043 ASCII N23/CR3A23Nl70CO8T404AC T409.notes axf .425 6 1W7 10056 ASCII 23IC3AZ3IThCO8T409ACO8TIIS.fnotes Of .426 Aug 66 1997 10611 ASCII 3/CR3A23N117DCOT51SAC09TO0O.notes Xf .427 1997 10911 ASCII 123,cR3AZ3NIBDCO8TO97AT8TI39.rotes aXf 428 Aug 6 1997 ssn ASCI I

• 23/CR3A23T808T139AC08T404.notes eXf.429 Aug 6 1997 10078 ASCII N23/CR3A23M180CT404ACO8T4W.fotes eXf .430 6 1997 9797 SCII N23/CR3A23N1SDC08T4O9AC08TSlS.notes Of .431 6 1997 10239 ASCI I N23/CRU2l3H80DCOT51IAC09TOOO.notes aXf .432 6 1997 10773 ASCII cempater Ta Backup Kuw"r of fIle Date File size Fit* Type File URom File Name Print Pages (output) (lytft) (Feimt) i27ecL3A05101CC09TOOOAC09T158.notes eXf.433 7 AuL 6 1997 £483 ASCII 12I7e1R3AM05tiOIDC9TI5BACWT219.notes eXf.434 9 Au 6 1997 11466 ASCI I H27e/CR3A05N01D09T219ACM33.fotes elf.435 7 AUL 6 197 9046 ASCII HZa/CR3AO5K02DCOT0DDACMT158.rlates f .4u6 7 AUL 6 1997 8631 ASCII K27a/cR3A5052DC09T158AC9T219.fotes aXf.437 9 AUL 6 1997 ASCII K27e/C3A05N0S DC0T219AC09T363.ots aXf .43 a Aug 6 1997 9454 ASCII K127a/CR3A05N03DC09TOCOAC09T1S5.noten Wt.U9 7 Lu 6 1997 £776 ASCII H27a/CR3A05M03DC09T158AO9T219.notes &lf.4O 10 AUL 6 1997 11917 ASCII K27a/CR3AO5KO3DCO9T219ACO9T63.notes elf.4l a AUL 6 1997 9465 ASCII 6 1997 9sn 12T7eCU3ADU04DCO9TOOOAC09TIS8.notes xt .4z 7 Aug ASCII 1127TeiC3AD5U04DC09T15AC09T219.notes eXf.43 10 LW 6 1997 11971 ASCII U2eCR3AD5404DC09T219ACD9T363.notn elf.U4 8 Lu 6 1997 9512 ASCII N27glCR3AO5N05D5c9TOOAC09T158.notes elf.45 7 AUL 6 1997 1738 ASCII 1127e/C33A0505DCO9T1SaAC9T219.notes aXt.446 10 Aug 6 1997 12020 ASCII 1127a/CR3A05N05DC09T219AC09363.nftes exf.4J 8 AuL 6 1997 9508 ASCII N27/CR3A05N06DC09CTOOOAC0T15L.notes Mf.4W 7 AuL 6 1997 £726 ASCII 117aCR3AC5NO60o9CT153Ae9T219.notes elf.49 10 AuL 6 1997 12068 ASCII 27eCR3A05X060C09T219AC09T363.nots *Xf.450 a AUL 6 1997 9544 ASCII 127a2CR3A05N07DCWTOOACW09T5I.note elf.451 7 AUL 6 1997 £734 ASCII 27eU/AU5*07C09tlS ACOM21Y.notes elf.45 10 ALW 6 1997 12070 ASCII 127 /CR3A05N1070C9T219AW9T363.notes exf.453 a ug 6 1997 953Z ASCII NZ7eICt3AM05Uac89TOO0ACC9T15.notes lf .4S4 7 LW 6 1997 ASCII EZ7a/CR3A05018DC0M9T1S5ALCT219.notes WAS.455 10 AuL 6 1997 12062 ASCII N27efCR3A05KU0D:O9T219AC09T363.nots dtf.456 a LuW 6 1997 9524 ASCII N27eC33A0509DC09TOO0AC09T 156.notes MfU.437 7 AUL 6 1997 9526 ASCII 12T7/C3A051109DC09TlSUCWT219.notes AfS.458 10 AuW 6 1997 12060 ASCII U27e/CR3A05N09DC09T219ACWT363.notes eXf.459 a AUL 6 1997 9526 ASCII N27alCa3A5N1oDC09TOOAC09T158.notes exf.460 T LW 6 997 120n 8734 ASCII IlZ7e/CR3A051 9DC9T1SBAC09T219.natn exf.461 10 LW 6 1997 12068 12054 ASCII N27a/CRAO5M1OC09T219AC09T363j.otee eXf.46 1 AL9 6 197 524 ASCII N27/C33A05N110DC09TOOAC09T158.notee elf.463 7 AuL 6 197 8742 ASCII 127a/CR3A05N11DC9T158AC09T219.notes ef.46C 10 AuL 6 1997 12060 1730 ASCII 1127/CR3A05111DC09T219AC09T363.notes elf.US a Au 6 1997 ASCII K27a/0R354t2DC09T000AC09T158.notes elf.466 7 AUL 6 197 8722 ASCII R27ECR3A051112DC09T1MSAC091T19.notes elf.467 10 AUW 6 1997 ASCII 127eBcR3A0H152Dc0T219ACWT6.notes eXf.468 a AuL 6 1997 9524 ASCII N27aeCU3A05N13DC09TO00ACM9T1Stnotas eXf.469 7 AuL 6 1997 ASCII N27e/CR3A05N130C09T1M8AI09T219.notes eXf.470 10 Aug 6 1997 12072 ASCII

7 Amo 06 13:39 1997 Fit*NaeI notelstla aA13oo:9M-oKEW 0200.000 REV00 ATTArENT X - Pae 4 N27IO3A05N13OC09TZ19AC0936J'tes ef.471 a Aug 6 1997 9528 ASCII 1127a0CR3AO5040CO ACM158S.6lt exf.472 7 Aug 61997 a0 ASCII TeIR3AO5II4DCMISStCO2I9.ntff .1f.4n 10 Aug 6 1997 12060 ASCII HZ71C3AOSN140XC0T219AC09363.ots efL.44 a Aug 6 1997 9516 ASCII UZ7eICR3AO5Nl5DCMOOOAC09TIS8.nOts L.4 7 Aug 6 1997 58 ACII H27eICt3A05N150C09T153AC09TZ19.notds olf.476 10 Aug 6 1997 116 ASCII 27a/"CR l5C09T21AC9T363.not s Xf.477 a AMu 6 1997 9500 ASCII

• 27.aC3A05360C0O9000AC09T158.nots L.47 r Aug 6197 693 ASCII K27e/CUAOSN16DC09TISSACT219.flt@5 af.479 10 Aug 6 1997 11969 ASCII N27aJCR3A05N16DC09T219AC09T363.riats elf.480 5 Aug 6 1997 9475 ASCII NZ7&/CA5N17DC09TODCAC958.Imtes &lf.4U1 7 Aug 6 1997 526 ASCII NZ7CR3AON17DCO9TISACO9T2i9.mtes aef .482 10 Aug 6 1W7 115 ASCII N127ICR305N17DC09T219AC09T363.notes L.48 Aug 6 1997 9475 . ASCII N27eC>R3AO3fl80C09TOOAOCM1S8.mts a9.484 7t Aug 6 1997 534 ASCII H27a/CR3A05118DC09T15ACU 219.rlotU xf .485 9 Aug 6 1997 11761 ASCII UZ7ICR3AOSN18OCO9T219ACO9133.nots elf.486 a Aug 6 1997 9255 ASCII N27I/CLU3AMlO10COT097AC08T139.mtes lf .487 7 Aug 6 1997 9131 ASCII H27e/C3AZIIOC08TI3PACO8T4O4.att 01.488 8 Aug 6 1997 9619 ASCII H27ICLA7W01DC08T404ACO8T409.flats a.f.489 a Aug 61997 98 ASCII H27Je/CA27W1DC081409AC08TS15.nots aXf.490 a Aug 6 1W7 9573 ASCII N27/CR3A27W010DC08T15AC09TO0O.nrote dtf.491 a Aug 6 1997 10011 ASCII RI271CRa3A27ULO0C8TO9RAcOT139.notes U.492 8 Aug 6 1997 9506 ASCII Z7&/CZA7M02DCO8T139ACC8T4O4.rotes lfL.493 8 Aug 6 1997 "35 ASCII NZ7e/CR3AZ71lODCWT404AC08T409.rotes eXf.494 a Aug 6 1997 63 ASCII Z7e/CRl3A27110ZC08T409AC0T515.rotts dtf.495 a Aug 6 1997 10053 ASCII

• 27aJCR3A27N020C08T515AC09TO00.notus o1f.496 5 Aug 6 1997 10489 ASCII N27a/CR3A27iO3Dc08T097AC0aTU9.nrots elf.497 a Aug 6 1997 9566 ASCII N27uCA27lUO3DC08T139AC08T404.notts .xt.49a 5 Aug 6 1997 10043 ASCII M27.'CR3A27N03DC08T404AC08T409.motes ef.499 8 Aug 6 1997 9678 ASCII N27e/CR3A27NO3DCO8T4O9ACOSTS1S.mtU s axf.500 a Aug 6 1997 1004t ASCII 327s/C3A27X030C08T515AC09TOOO.notUs eXf.501 9 Aug 6 1997 13579 ASCII 027a/C13A27104DC08TW27AC08T139.nomts exf.50z a Aug 6 1997 9607 ASCII

.27aICRIA271O0C08lT39ACO8T404.notes .Xf.503 8 Aug 6 1997 10201 ASCII 027e/C13A27 W4DC0CT404ACC8T409.notes sXf.504 a Aug 6 1997 974 ASCII N27e/CR3A270O4ICOBT4O9ACO8TSIS.nots .f.505 6a Aus 6 1997 104T ASCII K27oCR3A2714C0CCTSISAC09T000.notes .Xf.506 9 Aug 6 1997 10577 ASCII 027atCR3A27805DC08T097AC08T139.rotn t1f.507 a Aug 6 1997 9658 ASCII K0 m CR3 O0SDCO8T139ACO8T404.otus oXf.508 a Aug 6 1997 1018 ASCII KN7ua/C3A27N1050COT404AC08T409.mot6 sXf.9509 Aug 6 1997 9736 ASCII N27eICR3A27WO5DCO8T4O9ACO8T5IS.mot s eXf.510

• Aug 6 1997. 995 ASCII N27/CR3A27NO5OCOSTSISACOMTOOO.motes eXf.511 9 Aug 6 1997 10623 ASCII N27a/CR3A27N06OCO8T097ACO0T139.mttes Xf.512 a Aug 6 1997 9656 ASCII llZ7aC3A271106DCOCT39AC08T404.motes eXf.513 a Aug 6 1997 10179 ASCII N2h /Ct3A27mow0CO8T404ACw8T4 .notes eXf.514 a Aug 6 1997 9748 ASCII N27eICD.3A271106DC0T409ACO8T515.nots o1f.515 a Aug 6 1997 "997 ASCII K27eICR3A7MOOCOMc8TIS5ACO9TMOO.notes .xf.516 9 Aug 6 1997 10607 ASCII N27/CR3A27M0ThCOtT097ACrtT139.notes eXf.517 a Aug 6 1997 966 ASCII 2j7aC3AZm07bCG8Tl39ACO8T4O4.mntes .Xf.518 a Aug 6 1& 7 10187 ASCII Hz7/CR3A27TO7bC08T404AC08T409.notes Xf.519 a Aug 6 1997 9772 ASCII u27a/CaA7N07C8T409AC08TS15.notes .Xf.520 a Aug 6 1997 10001 ASCII H27a/CU3A27C07DC38T51SAC09TO00.notes eff.521 9 Aug *6 1997 10611 ASCII 1127I/CR3A27N80DC0T097AC08T139.aotes .Xf.522 £ Aug 6 1997 .9712 ASCII Z7eIC3A2T7hOac8T139ACC8T404.ntes nXf.523 5 Au 6 1997 i1061 ASCII I27a/CL3AW7vOC08T404ACc8T409.notos .Xf.S24 a Aug 6 1997 976 ASCII N7Ct3A2710CDC08T409ACO8T515.notes .Xf.S25 I Aug 6 1997 9999 ASCII N27/CR3AmODCO08T515AC0T000.notus .Xf.S26 9 Aug 6 1997 10642 ASCII N27/tC3A7Uc09C8T097ACO8T139.notes .X1.527 I Aug 6 1997 9692 ASCII HZ74C13A27h09DC08T139ACO8T404.notes .Xf.528 a Aug 6 1997 1021 ASCII 1271CL3A2NM0CC8T4C4Ac05T4D9.notu 9Xf.529 I Aug 6 1997 976 ASCII N27e/CR3A27W090C08T409ACCO855.notn eXf .530 a Aug 6 1997 997 ASCII N27/CR3AZ7MO9DCO8TSISACO9OOO.notuu .X9.531 9 Aug 6 1997 1066 ASCII H27e/CR3A271SODC08T097AC08T139.notes Xf.532 a Aug 6 1997 9692 ASCII

/7aCLA2mIOCO8TI39ACOST404.notes GO= a Aug 6 1997 l102m ASCII 7eIssCLZ7N1oDCo8T4o4ACo8T4o9.natu .Xf.S34 a Aug 6 19W7 g78 ASCII N27.ICR3A7IOOCO8T4o9ACOSTSIS.notus .xf.53 a Aug 6 1997 9 ASCII K27ICR3A2W1CGoc8T515ACo9TOW.notes xf.s36 9 Aug 6 17 10660 ASCII z7aCR3A27NllDCOsTO97ACosT139.otes oxf.537 a Aug 6 1997 682 ASCII 127ICR33A27N11DC08T139ACO8T404.notes X.S938 5 Aug 6 1997 10233 ASCII UWa27CR3AlDCCBT404ACO8T4O9.nots elf.539 a Aug 6 1997 978 ASCII N27aCLA7iDCw T4o9ACO8TsIS.notes gXf.540 a Aug 6 1997 9997 ASCII

Aug 06 I3SM 1997 File hma: rt"tiat u 1tAOOOO-1I717-0200-000" 00 ATTACoWIT X - Pap 9 127u/c"uA27miDCO8T5ISACO9T000.noI inXtf.S41 9 Am 6 1997 1 ASCII N27a/CLA2 12DXCT097AC08T139.at Lf.52 8 Aug 6 1997 NW ASCII N27a/CA27D CT139A1C0T04.noti Gef .543 1 Lug 6 1997 127 ASCII t2741C327M U ACUT409.nwtes ULf I44 Aug 6 1997 4 ASCII NUV7aC3A2712CT409AC0TS15.not exf.45 Aug 6 1997 gm ASCII E27eZt3A27Nl2DCWT15Aco9 O.notsv lf .546 9 Aug 6 17 1 ASCII N27eIC33A27WIl3DCO8TO97ACO0T139.notn eXf.547 a Aug 6 19 970 ASCII K27a/CR3A279i13DCOT139ACO8T404.notee oXf.548 a Aug 6 197 10181 ASCII K270CER3AWUNIMDCC8T404ACORT409.notes ef.S49 5 Aug 6 1997 9786 ASCII N27CR3A27DCOT409ACUTSl.notes xf .550 a Aug 6 1997 1O07 ASCII N27u/C37A7113C8T15SAC090O.nates f.51 9 Aug 6 1997 10636 ASCII H27l/C33A27WD1C0T097ACO8T139.notu elf.S52 a Aug 6 1997 9" ASCII.

N27ICM3 h4DC08T139ACO8T44.n teas af.S53 I Aug 6 1997 10191 ASCII WZeIC3A27WI4OCO8T404AC0T409.mtes et.554 a Aug 6.197 97m ASCII EZ7ICR3A27Nl4DCO8T409ACO8TSIS.notes eX.555 a Aug 6 1997 995 -ASCII NZY6eICalZ7l1I4CO8T51SACO9TOOO.notes xtf.556 9 Auo 6 1997 10630 ASCII N27TaCR3AZNI5DC08T097AC8U139.notes et-.5J7 a Aug 6 1997 9656 ASCII 127a/CR3tA27lSDCOTi39ACOBT4O4.notes 4f.558 a Aug 6 t97 10195 ASCII N27a/CR3A27I5DCOST4O4ACO8T4O9.notes elf .59 a Aug 6 1997 9742 ASCII N27aICR3AZThISDCO8T409ACO8TSIS.notes §Xf.560 6 Aug 6 1997 9949 ASCII N27CR3AZTISDC8TSISAC09TOOO.notes ext.561 9 Aug 6 1997 10662 ASCII Te/C3A27816DC08T097AC08T139.notes exf.562 Aug 6 1997 627 ASCII K A2e/C3A7M16DC0=T139AC08T404.nrote eXf.563 8 AUG 6 1997 10217 ASCII K27e/C3LA2U1dDCU8T404AC08T409.notes axf.S64 Au 6 1997 9720 ASCII U27JaIC3A27Ni6DC08U49ACO8TSIS.notes Xf.S63 a Aug 6 1J 10047 ASCII H271C33AZ7M16DC08T515AC097O0.notes tXf.566 9 Aug 6 1997 10583 ASCII 127e/C33AZ7it1DC08T097ACO0T139.notes eXf.567 a Aug 6 1997 9g ASCII U27u/CL3A270IC08T139AC0ST404.notes exf.su a Aug 6 1997 9968 ASCII EZ7aCR3AZMh17TCOaT404AC0T409.nota eXtf.569 a Aug 6 1997 96 ASCII 127e/CR3AZ7I17)C08T409AC08T515.note eLf.50 a Aug 6 1997 10053 ASCII N270CIU3AZnIRT1CO8TS1SACO9TO0.notes axf.571 9 Aug 6 1997 10517 ASCII 12TaJ/C 21318DC08T0AC08T139.nrats UL.M 7 Aug 6 1997 93 ASCII 1a273A27i18DCO8Ti39AC=8T404.noten eXf.7 a Aug 4 1997 9677 ASCII Ul27a/Ct3A27M18DCO0T404AC08T&9.notee Xf.=74 t Aug 6 1997 9411 ASCII N274XICRA27h11tDCOBUU 9ACO8TSIS.notes axf.S75 8 . Aug 6 1997 9O9 ASCII N27Ja/CR3A2laDCO8TSISAC09TOOO.notes oXt.576 a Aug 6 1997 10196 ASCII