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License Amendment Request for Spent Fuel Pool Region I Criticality - Palisades SFP Region 1 Criticality Evaluation
	ML083360624
Person / Time
Site:	Palisades
Issue date:	11/25/2008
From:	; AREVA, AREVA NP, Siemens
To:	; Office of Nuclear Reactor Regulation
References
	ANP-2779NP - 001
	Download: ML083360624 (120)
	v • d • e

ENCLOSURE4 LICENSE AMENDMENT REQUEST FOR SPENT FUEL POOL REGION I

CRITICALITY AREVA NP Inc. Report Document No. ANP-2779NP - 001 PALISADES SFP REGION I CRITICALITY EVALUATION 119 Pages Follow

AR EVA NON PROPRIETARY AREVA NP Inc.,

an AREVA and Siemens company Document No:

ANP-2779NP 001 20004-015 (09/30/2008)

Palisades SFP Region 1 Criticality Evaluation AREVA NP INC.

NON PROPRIETARY Page 1 of 119

A AREVA 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 AREVA NP Inc.,

an AREVA and Siemens company NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation Safety Related?

Lnj YES q NO Does this document contain assumptions requiring verification ?

q YES E NO Signature Block Name and TittefDisctpline Signature P/LF, R/LRS A/A-CRP Date Pages/Sections Prepared/Reviewed/

Approved or Comments R.C. Deveney /

Supervisory Engineer LP 11/14/08 All S.T. Horton I Engineer Ill r,r

^c LR 11/14/08 All W*

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ALL Note :

PILP designates Preparer (P), Lead Preparer (LP)

RILR designates Reviewer (R), Lead Reviewer (LR)

AIA-CRF designates Approver (A), Approver of Customer Requested Format A-CRF Page 2

A AREVA AREVA NP Inc.,

an AREVA and Siemens company Palisades SFP Region 1 Criticality Evaluation 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY Record of Revision Revision Pages/Sections/ Paragraphs No.

Date Changed Brief Description / Change Authorization 000 11/11/08 NA Original Release 001 11/14/08 Reissue Miscellaneous typos, clarifications and customer comments resolved.

Page 3

A AREVA AREVA NP Inc.,

an AREVA and Siemens company Palisades SFP Region 1 Criticality Evaluation Table of Contents 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY Page SIGNATURE BLOCK..........................................................................................................................

......2 RECORD OF REVISION....................................................................................................................

......3 LIST OF TABLES...............................................................................................................................

......6 LIST OF FIGURES.............................................................................................................................

......8 1.0 EXECUTIVE

SUMMARY

......9

2.0 INTRODUCTION

...... 9 3.0 ANALYTICAL METHODS.......................................................................................................

....10 3.1 Computer Programs and Standards................................................................................10 3.2 Analytical Requirements and Assumptions.....................................................................10 3.3 Computational Models and Methods...............................................................................12 3.3.1 Bounding Fuel Assembly Description............................................................ 12 3.3.2 Region 1 Rack Data.......................................................................................12 3.3.3 Material Specification.....................................................................................15 3.3.4 Conservative Model for Degradation of Carborundum Plates...................... 16 3.4 Analytical Model Conservatisms..................................................................................... 18 3.5 Tolerances, Penalties, Biases, and Uncertainties........................................................... 18 3.5.1 Method Discussion of Tolerances, Biases, and Uncertainties....................... 19 3.5.2 System and Tolerance Effects....................................................................... 19 3.5.3 System and Tolerance Results......................................................................20 3.5.4 Summary of Bias and Uncertainty Values..................................................... 25 4.0 RACK ANALYSIS.....................................................................................................................

... 26 4.1 Region 1 A with Checker Board Pattern...........................................................................27 4.1.1 Region 1A - Boron Dilution............................................................................27 4.1.2 Misload Conditions......................................................................................... 27 4.1.3 Conservatism s............................................................................................... 28 4.2 Region 1B with Face Adjacent Assemblies............................

........................................ 28 4.2.1 Region 1 B - Boron Dilution............................................................................ 30 4.2.2 Misload Conditions......................................................................................... 30 4.2.3 Conservatism s............................................................................................... 32 Page 4

A AREVA AREVA NP Inc.,

an AREVA and Siemens company Palisades SFP Region 1 Criticality Evaluation 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 PROPRIETARY Table of Contents (continued)

Page 4.3 Region 1 E........................................................................................................................

32 4.3.1 Region 1 E - Boron Dilution............................................................................32 4.3.2 Misload Conditions......................................................................................... 33 4.4 Definition of Non-Fuel Bearing Components (NFBC )......................................................34 4.4.1 NFBC Conclusions.........................................................................................35 4.5 Rack Interactions............................................................................................................. 35 4.5.1 Interaction Effects Results............................................................................. 35 5.0

SUMMARY

AND CONCLUSIONS..............................................................................................37 6.0 LICENSING REQUIREMENTS...................................................................................................38

7.0 REFERENCES

............................................................................................................................40 APPENDIX A

BIAS AND BIAS UNCERTAINTY................................................................................................. A-1 APPENDIX B

TOLERANCE CALCULATIONS...................................................................................................

B-1 APPENDIX C

RACK C, RACK E, AND REGION 2 INPUT DECKS.................................................................... C-1 5

Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company Palisades SFP Region 1 Criticality Evaluation List of Tables 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY Page TABLE 3-1: BATCH X1 DIMENSIONS AND TOLERANCES 12 TABLE 3-2: DIMENSIONS OF PALISADES REGION 1 RACKS 13 TABLE 3-3:

'C' RACK 2-OF-4 WITH SWELLING BIAS/UNCERTAINTIES 21 TABLE 3-4:

'C' RACK 3-OF-4 WITH SWELLING BIAS/UNCERTAINTIES 21 TABLE 3-5:

'E' RACK 2-OF-4 WITH SWELLING BIAS/UNCERTAINTIES 22 TABLE 3-6:

'E' RACK 3-OF-4 WITH SWELLING BIAS/UNCERTAINTIES 22 TABLE 3-7:

'C' RACK 2-OF-4 NO SWELLING BIAS/UNCERTAINTIES 23 TABLE 3-8:

'C' RACK 3-OF-4 NO SWELLING BIAS/UNCERTAINTIES 23 TABLE 3-9:

'E' RACK 2-OF-4 NO SWELLING BIAS/UNCERTAINTIES 24 TABLE 3-10:

'E' RACK 3-OF-4 NO SWELLING BIAS/UNCERTAINTIES 24 TABLE 3-11:

K95195 DETERMINATION BASED UPON CALCULATED BIAS/UNCERTAINTY 25 TABLE 4-1: REGION 1A K95/95 DETERMINATION FOR BORON DILUTION 27 TABLE 4-2: REGION 1A K95/95 DETERMINATION FOR MISLOAD CONDITIONS 28 TABLE 4-3: REGION 1B K95/95 DETERMINATION FOR BORON DILUTION 30 TABLE 4-4: REGION 1B K95/95 DETERMINATION FOR MISLOAD CONDITIONS 31 TABLE 4-5: REGION 1E K95195 DETERMINATION FOR BORON DILUTION 33 TABLE 4-6: REGION 1E K95i95 DETERMINATION FOR MISLOAD CONDITIONS 33 TABLE 4-7: NFBC REACTIVITY EVALUATION FOR SWELLED RACK 34 TABLE 4-8: NFBC REACTIVITY EVALUATION FOR NOMINAL RACK 35 TABLE 4-9:

INTERACTION RESULTS FOR REGION 1C AND REGION 2 RACKS 36 TABLE 4-10: INTERACTION RESULTS FOR REGION 1E AND REGION 2 RACKS 36 TABLE 4-11: INTERACTION RESULTS FOR REGION 1E MISLOAD CONDITION NEXT TO REGION 2 36 TABLE A-1:

RANGE OF VALUES OF KEY PARAMETERS IN SPENT FUEL POOL A-2 TABLE A-2: DESCRIPTIONS OF THE CRITICAL BENCHMARK EXPERIMENTS A-3 TABLE A-3: RESULTS FOR THE SELECTED BENCHMARK EXPERIMENTS A-6 TABLE A-4: TRENDING PARAMETERS A-8 TABLE A-5:

SUMMARY

OF TRENDING ANALYSIS A-10 TABLE A-6: RANGE OF VALUES OF KEY PARAMETERS IN BENCHMARK EXPERIMENTS A-15 TABLE B-1: FABRICATED BOX MODEL DIMENSIONS B-1 Page 6

A AREVA AREVA NP Inc.,

an AREVA and Siemens company 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 PROPRIETARY Palisades SFP Region 1 Criticality Evaluation List of Tables (continued)

Page TABLE B-2: INTER BOX MODEL DIMENSIONS B-1 TABLE B-3: LEAD DUMMY ASSEMBLY ROD DIMENSIONS B-5 TABLE B-4:

LITE DUMMY DIMENSIONS B-6 TABLE B-5: STAINLESS STEEL NFBC MODEL DIMENSIONS B-6 TABLE B-6: ROD REMOVAL RESULTS FOR ASSEMBLY G42 WITH EITHER ABSORBER OF 4 FUEL RODS REMOVED B-7 TABLE B-7: MODERATOR TEMPERATURE EFFECTS FOR 'C' RACK - NOMINAL MODEL B-8 TABLE B-8: MODERATOR TEMPERATURE EFFECTS FOR 'C' RACK - SWELLING MODEL B-8 TABLE B-9: MODERATOR TEMPERATURE EFFECTS FOR `E' RACK - NOMINAL MODEL B-9 TABLE B-10: MODERATOR TEMPERATURE EFFECTS FOR 'E' RACK - SWELLING MODEL B-9 TABLE B-11: MODERATOR TEMPERATURE EFFECTS FOR `C' RACK WITH 238 GROUP CROSS SECTIONS WITH NOMINAL MODEL B-10 TABLE B-12: PLANAR ENRICHMENT SENSITIVITY FOR 'C' RACK B-13 TABLE B-13: PLANER ENRICHMENT SENSITIVITY FOR `E' RACK B-14 TABLE B-14:

SUMMARY

OF OFFSET PLACEMENT PENALTY FOR CENTERED ASSEMBLY MODEL B-14 TABLE B-15: RACK 'C' TOLERANCE RESULTS - NOMINAL MODEL B-15 TABLE B-16: RACK `E' TOLERANCE RESULTS B-16 TABLE B-17: RACK 'C' SWOLLEN TOLERANCE RESULTS B-17 TABLE B-18: RACK `E' SWOLLEN TOLERANCE RESULTS B-18 TABLE B-19: RACK 'C' TOLERANCE RESULTS B-19 TABLE B-20: RACK `E' TOLERANCE RESULTS - NOMINAL MODEL B-20 TABLE B-21: RACK 'C' FUEL TOLERANCES - SWELLING MODEL B-21 TABLE B-22: RACK 'E' FUEL TOLERANCES - SWELLING MODEL B-22 7

Page

A

!AREVA AREVA NP Inc.,

an AREVA and Siemens company Palisades SFP Region 1 Criticality Evaluation 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY List of Figures Page FIGURE 2-1: PALISADES FUEL STORAGE AREAS 9

FIGURE 3-1: SKETCH OF MODEL OF `C' RACK 14 FIGURE 3-2: SKETCH OF MODEL OF `E' RACK 15 FIGURE 3-3: PHOTOGRAPH OF DISTORTED PLATE 17 FIGURE 3-4: KENO-V.A SWELLING MODEL FOR RACK C 18 FIGURE 4-1: FUEL LOADING PATTERN FOR REGION 1A 27 FIGURE 4-2: REGION 1A MISLOAD LOCATION 28 FIGURE 4-3: REGION 1B ANALYZED PATTERNS FOR FOUR OR LESS IN A ROW 29 FIGURE 4-4: REGION 1113 ANALYZED PATTERNS FOR THREE IN AN L.

29 FIGURE 4-5: REGION 1B ANALYZED PATTERNS FOR MISLOAD CONDITIONS 30 FIGURE 4-6: FUEL LOADING PATTERN FOR REGION 1E 32 FIGURE 4-7: REGION 1E MISLOAD LOCATIONS 33 FIGURE 6-1: REGION 1E ALLOWED FUEL STORAGE PATTERN 39 FIGURE A-1 DISTRIBUTION OF KEFF DATA VERSUS EALF FOR THE SELECTED POOL OF BENCHMARK EXPERIMENTS A-11 FIGURE A-2: DISTRIBUTION OF KEFF DATA VERSUS ENRICHMENT (235U) FOR THE SELECTED POOL OF BENCHMARK EXPERIMENTS A-12 FIGURE A-3: DISTRIBUTION OF KEFF DATA VERSUS H/X FOR THE SELECTED POOL OF BENCHMARK EXPERIMENTS A-12 FIGURE A-4: DISTRIBUTION OF KEFF DATA VERSUS SOLUBLE BORON CONCENTRATION FOR THE SELECTED POOL OF BENCHMARK EXPERIMENTS A-13 FIGURE A-5: PLOT OF STANDARD RESIDUALS FOR REGRESSION ANALYSIS WITH EALF AS TRENDING PARAMETER A-13 FIGURE A-6: PLOT OF STANDARD RESIDUALS FOR REGRESSION ANALYSIS WITH ENRICHMENT AS TRENDING PARAMETER A-14 FIGURE B-1: SKETCH OF KENOV.A MODEL AT EDGE OF REGION 2 RACKS B-2 FIGURE B-2: SKETCH OF A PORTION OF THE `C'-REGION 2 MODEL B-3 FIGURE B-3: SKETCH OF A PORTION OF THE REGION 1E -REGION 2 MODEL B-4 FIGURE B-4:

LITE DUMMY ARRANGEMENT SKETCH B-5 FIGURE B-5:

PIN ARRANGEMENTS FOR BATCH X FUEL ASSEMBLIES B-11 FIGURE B-6: FUEL ORIENTATION FOR ASSEMBLY PLACEMENT B-12 Page 8

A AREVA AREVA NP Inc.,

an AREVA and Siemens company 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation 1.0 EXECUTIVE

SUMMARY

This report contains the criticality evaluation of the Palisades Spent Fuel Storage Racks for the Region 1 racks that contain Carborundum"'plates ' as a poison. There are indications of swelling and of boron loss through attenuation measurements.

This evaluation assumes total boron loss from the Carborundum" plates and a conservative swelling model. No burnup credit is assumed for these calculations.

The same soluble boron credit that was used in Region 2 is assumed for the Region 1 evaluations. Rack interaction effects are evaluated and found to be acceptable.

2.0 INTRODUCTION

The Palisades Nuclear Plant (PNP) requires a criticality analysis to address the Spent Fuel Storage Racks (SFSR) that are currently designated as Region 1 and contain Carborundum plates that may be degraded. These fuel storage locations at Palisades are shown in Figure 2-1.

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PAUTADES NUCLEAR PLANT f'f FUEL STATUS NEW fUCL STOL+

E RACK CASK WAS0DOfNV This study determines the maximum K-effective (keo)of three different regions for the effects associated with fuel storage in the Palisades Region 1 Spent Fuel Storage racks relative to a conservative treatment of the degradation of the Carborundum`' plates. The three regions are:

9 Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation 1)

Region IA - Region 1 Main Spent Fuel Pool with checkerboard loading of fuel with empty cells for fuel having a nominal planar average U-235 enrichments less than or equal to 4.54 weight percent.

2)

Region lB - Region 1 Main Spent Fuel Pool with face adjacent fuel surrounded by face adjacent empty cells having a nominal planar average U-235 enrichments less than or equal to 4.34 weight percent.

3)

Region I E -Region 1 North Tilt Pit with selective loading of one assembly having a nominal planar average U-235 enrichment less than or equal to 3.26 weight percent and 34 locations having a nominal planar average U-235 enrichments less than or equal to 3.05 weight percent and with 15 empty cells.

This report defines the acceptable geometries and demonstrates that the reactivity effects of the rack and fuel assembly manufacturing tolerances, the reactivity effects of pool moderator temperature variations, swelling in the poison plates, complete loss of the absorber material contained within the walls, and accident conditions for each region are acceptable.

Criticality results and Licensing Requirements are summarized in Section 1.0 and Section 6.0, respectively.

3.0 ANALYTICAL METHODS The analytical methods are discussed in this section.

It briefly describes computer programs, licensing requirements, and computer models used for this analysis.

3.1 Computer Programs and Standards The KENO-V. a computer code (Reference [2]), a part of the SCALE 4.4a package, was used to calculate the keff of 100 critical systems (criticality benchmark experiments ). The 44 group cross section set was used by the SCALE driver module CSAS25, which used modules BONAMI-2 and NITAWL to perform spatial and energy self-shielding of the cross sections for use in KENO-V.a.

This code system is run on the AREVA NP Linux-based scientific cluster. The hardware and software configurations are governed by AREVA NP procedures to ensure calculational consistency in licensing applications. The code modules are installed on the system and the installation check cases are run to ensure the results are consistent with the installation check cases that are provided with the code. The binary executables are put under configuration control so that any changes in the software will require re-certification. The hardware configuration of each machine in the cluster is documented so that any significant change in hardware or operating system that could result in a change in results is controlled.

In the event of such a change in hardware or operating system, the hardware validation suite is re-run to confirm that the system still performs as it did when the code certification was performed.

3.2 Analytical Requirements and Assumptions The purpose of the spent fuel storage racks is to maintain the fresh and irradiated assemblies in a safe storage condition.

The current licensing basis as defined by the existing Technical Specification Requirements and federal code requirements, 10 CFR 50.68, specifies the normal and accident parameters associated with maintaining the fresh and irradiated assemblies in a safe storage condition.

10 CFR 50.68 defines the criticality accident requirements associated with the spent fuel racks and states the following:

"If credit is taken for soluble boron, the keff of the spent fuel storage racks loaded with fuel of the maximum fuel assembly reactivity must not 10 Page

A ARE VA AREVA NP Inc.,

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Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation exceed 0.95, at a 95% probability, 95% confidence level, if flooded with borated water, and the keff must remain below 1.0, subcritical, at a 95% probability, 95% confidence level, if flooded with unborated water."

The current analysis basis for Region 2 from Reference 3 is a maximum ken of less than 1.0 when flooded with unborated water, and less than, or equal to 0.95 when flooded with water having a boron concentration of 850 ppm.

In addition, the ken in accident or abnormal operating conditions is less than 0.95 with 1350 ppm of soluble boron.

This analysis demonstrates that the effective neutron multiplication factor, ka, is less than 1.00 with the racks loaded with fuel of the highest anticipated reactivity, and flooded with un-borated water at a temperature corresponding to the highest reactivity.

In addition, the analysis demonstrates that keff is less than or equal to 0.95 with the racks loaded with fuel of the highest anticipated reactivity, and flooded with borated water at a temperature corresponding to the highest reactivity. The maximum calculated reactivity included a margin for uncertainty in reactivity calculations including manufacturing tolerances and is shown to be less than 0.95 with a 95% probability at a 95% confidence level with boron credit.

Reactivity effects of abnormal and accident conditions were also evaluated to assure that under all credible abnormal and accident conditions, the reactivity will not exceed the regulatory limit of 0.95 under borated conditions or a limit of 1.0 with unborated water.

The double contingency principal of ANS-8. l/N16.1-1975 (and the USNRC letter of April 1978; see third bullet below) specifies that it shall require at least two unlikely, independent and concurrent events before a criticality accident is possible.

This principle precludes the necessity of considering the simultaneous occurrence of multiple accident conditions.

Applicable codes, standard and regulations or pertinent sections thereof, include the following:

Code of Federal Regulations, Title 10, Part 50, Appendix A, General Design Criterion 62, "Prevention of Criticality in Fuel Storage and Handling."

Code of Federal Regulations, Title 10, Part 50.68, "Criticality Accident Requirements."

USNRC Standard Review Plan, NUREG-0800, Section 9.1.1, "Criticality Safety of Fresh and Spent Fuel Storage and Handling," Rev. 3 - March 2007.

USNRC letter of April 14, 1978, to all Power Reactor Licensees - OT Position for Review and Acceptance of Spent Fuel Storage and Handling Applications (GL-78-011), including modification letter dated January 18, 1979 (GL-79-004).

L. Kopp, "Guidance on the Regulatory Requirements for Criticality Analysis of Fuel Storage at Light-Water Reactor Power Plants," NRC Memorandum from L. Kopp to T. Collins, August 19, 1998.

USNRC Regulatory Guide 1.13, "Spent Fuel Storage Facility Design Basis," Rev. 2, March 2007.

ANSI ANS-8.17-1984, "Criticality Safety Criteria for the Handling, Storage and Transportation of LWR Fuel Outside Reactors."

This calculation is performed according to the general methodology described in the ReferenceA-2 (NUREG/CR-6698 "Guide for Validation of Nuclear Criticality Safety Methodology") that is also briefly described in Section A. 1. The critical experiments selected to benchmark the computer code system are discussed in Appendix A.4.

11 Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation The results of the criticality calculations, the trending analysis, the basis for the statistical technique chosen, the bias, and the bias uncertainty are presented in Appendix A.4.

3.3 Computational Models and Methods Section 3.3 describes the basic models used to evaluate the three regions in the PNP SFSR.

Results using these models are described in later sections.

3.3.1 Bounding Fuel Assembly Description Batch X1 with an initial average planar enrichment of 4.54 wt% 235U is used to bound the possible enrichments and different fuel types in the storage rack evaluations. Some specific storage requirements are enrichment dependent. No burnup credit is taken. Table 3-1 shows the dimensions of bounding X1 model employed in this report.

Appendix B provides a discussion of the appropriate biases to apply to bound the other assembly designs.

Fuel end details are not modeled. Fuel in the racks are modeled as surrounded by full (12 inches) water reflection at top and bottom. Appendix B also shows that a zone loaded assembly has an equivalent or less reactivity than an assembly with a constant enrichment equal to the average of the assembly.

Table 3-1: Batch Xl Dimensions and Tolerances Parameter Nominal Tolerance Units in in Pitch 0.55 Pellet OD 0.3600 0.0005 Clad ID 0.3670 0.0015 Clad OD 0.417 0.002

Guide Bars 8

Effective Area*

0.1586 in,

Instrument Tubes I

IT ID 0.3670 0.0015 IT OD 0.417 0.002 Active Fuel 132.6 0.29 Density, %TD 96%**

1.50%

Represents a conservatively small area for this parameter.

- A slightly higher percent theoretical density (TD) of 96% is used to bound the densities of other assemblies.

3.3.2 Region 1 Rack Data Region 1 of the Palisades spent fuel storage pool comprises two rack designs. The main region consists of six `C' racks for storage of 372 fuel assemblies.

Regions IA and lB are rack type `C'. Another rack, the `E' rack is placed in the `North Tilt Pit' and can hold 50 assemblies on a slightly wider pitch than the `C' racks. Region 1E is rack type `E'. Table 3-2 lists the dimensions of the two racks.

Figure 3-1 and Figure 3-2 provide sketches of each rack type, which illustrate the geometries used in KENO-V.a for each fuel cell. The actual corners of the box walls are rounded whereas the sketch is squared off. A single 12 Page

A AREVA AREVA NP Inc.,

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Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation SS-304 separation rod of --0.25" OD is placed at each corner of the `C' rack. A set of two similar SS-304 separation rods is placed before the rounded section of each corner of the `E' rack. The fuel box in the rack is primarily SS-304, absorber material, and moderator. The standard SS-304 mixture of the composition library is used for this material. The moderator is water at 1.00 g/cc. The current analysis in Reference 4 for the Region 1 rack assumed that the absorber plate was composed of only B4C with a reduction in the plate density due to the neglect of the phenol filler material. A carbon mass of 0.2720 g/cc was calculated for the reduced density plate.

For this evaluation the absorber material is assumed degraded and this degraded condition will be briefly examined in a later section.

Table 3-2: Dimensions of Palisades Region 1 Racks Region 1 Rack Type

'C' Rack

`E' Rack Dimension Nominal, in Tolerance, in Nominal, in Tolerance in Cell Pitch-x 10.25

+0.04/-0.04 11.25

+0.04/-0.04 Cell Pitch-y 10.25

+0.04/-0.04 10.69

+0.04/-0.04 Box ID 8.56

+0.00/-0.12 9.00

+0.00/-0.12 Box OD 9.56

+0.12/-0.00 10.00

+0.12/-0.00 Box Wall Thickness, Inside 0.125

+0.010/-0.010 0.125

+0.010/-0.010 Box Wall Thickness, Outside 0.125

+0.010/-0.010 0.125

+0.010/-0.010 Absorber Thickness 0.210

+0.035/0.02 0.210

+0.035/0.02 Absorber Width 8.26

+0.05/-0.010 8.26

+0.05/-0.010 13 Page

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Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation Figure 3-1: Sketch of Model of `C' Rack 0.21" 0.^23"^

'4- 0.25" 8.56" 10.25" 14 Page

A AREVA AREVA NP Inc.,

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Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation 3-2: Sketch of Model of `E' Rack 3.3.3 Material Specification The fuel materials include the uranium oxide pellets, the clad material, and the moderator surrounding the cladding.

All materials in the base model are assumed to be at 293°x.

Parametric studies are described in a later section evaluating reactivity temperature effects.

15 Page

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Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation The fuel pellets are assumed to have a 96% TD to correspond to the highest nominal density of past, current, or proposed pellets. No dish or chamfer is included in the density, thus the fuel column is conservatively modeled as a solid cylinder of fuel. Five enrichments are included: the four nominal enrichments in the assembly and the pin weighted average of these four enrichments.

The cladding, instrument tubes, and guide bar are zirconium alloys.

In the past these components have been Zirc-4, however, Batch Y, next reload for the Spring 2009 outage, will use M5' cladding for the fuel rods and the instrument tube. These components are assumed to be composed of pure zirconium.

This approximation will be slightly conservative because the alloy additives generally are absorbers (such as Tin and Niobium) and thus tend to slightly reduce the assembly reactivity.

The moderator for the base case is assumed to be unborated water with a density of 1.0 g/cc. The moderator density and temperature will be evaluated.

The fuel box in the rack is primarily SS-304, absorber material, and moderator.

The standard SS-304 mixture of the composition library is used for this material. The moderator is again water at I g/cc. The absorber material composition is based upon an assumption of the degraded condition of the B4C absorber material.

The evaluation assumed zero boron in the absorber plate.

Thus, the plate will be modeled with its original dimensions but containing only carbon with a density of 0.2720 g/cc.

3.3.4 Conservative Model for Degradation of Carborundum Plates Evidence of stuck assemblies and recent attenuation testing of the absorber plates in Region 1 has indicated a reduction in the absorption capability of the flux trap between the fuel locations in the Region 1 rack. A possible cause is leaching of boron from the B4C absorber plates due to a combination of gamma irradiation of the phenol material and water in the absorber region of the box. An alternate, or complimentary, cause of the loss of attenuation capability could be swelling of the box walls that reduce the moderator between the fuel assembly and the wall and between the walls of the flux trap.

Either swelling condition can reduce the effectiveness of the absorber plates without any loss of boron. To bound the boron loss, the boron contained in the Carborundum"^

plates is assumed to be zero. The poison plate is modeled with its original dimensions but containing only the carbon from the B4C with a density of 0.2720 g/cc. No other materials are assumed in the poison plate even though the Carborundum°" plate contains hydrogen, oxygen, and additional carbon.

Complete loss of boron is unlikely since limited testing has shown the presence of attenuation larger than the absence of boron but less than the minimum design value.

There is also evidence of swelling of the Stainless Steel wall next to the assembly cell that contains the Carborundum' plates. The nature of the swelling is a central bulge (side to side) on one face of the fuel cell and is shown in Figure 3-3.

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Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation It is not clear whether the bulge is full height.

In addition, the displaced volume could be backfilled with water which would be minimal impact on the kff. The assumption for the swelling model is that all four walls displace a water thickness of 0.155 inches on the assembly wall and a water thickness of 0.345 inches on the flux trap wall for the entire active height of the fuel and for the entire rack.

Additionally, the space of 0.04 inches between the poison plate and the stainless steel is also assumed void of water. The large flux trap swelling is assumed since the structure of the racks is such that the flux trap stainless steel walls are not accessible to view.

Rather than moving the stainless steel and poison plate structures and conserving their masses, the water is simply replaced with a void. For the rack C model, this displaces all the water between the assemblies.

If this bow is triangular (which would be a good estimate of this picture), all four walls are bowed (other three walls look flat), and the plate inside the flux trap bowed the same distance (0.155 inches), only 31 % of the water assumed in this model would be displaced. Also, assuming this geometry for the entire rack rather than one side panel is also conservative.

Both the displacement model and no displacement are evaluated for the three regions in this document.

The KENO-V.a model for this geometry for Rack type `C' is illustrated in the next figure where all the dark gray areas are voided of water.

17 Page Figure 3-3: Photograph of Distorted Plate

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Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation Figure 3-4: KENO-V.a Swelling Model for Rack C 3.4 Analytical Model Conservatisms This section lists the major conservatisms associated with this evaluation.

1)

No credit was taken for burnup.

2)

No credit is taken for intermediate spacer grids or end fittings.

3)

No credit is taken for any boron in the CarborundumRplates.

4)

The maximum fuel enrichment tolerance of 0.05 wt% is considered in the tolerance evaluation.

5)

All plates are assumed swelled by replacing a thickness of 0.54 inches of water that surrounds each absorber plate with voids.

6)

No removable control components in the fuel are credited in the analysis.

3.5 Tolerances, Penalties, Biases, and Uncertainties This section describes the tolerances, penalties, uncertainties, and biases utilized in the analysis of Racks C (Regions I A and 113) and E (Region I E). The penalties that pertain to the rack design tolerances and system parameters are discussed in detail in Appendix B.

Additionally, the KENO-V.a bias with its associated uncertainty is discussed in Appendix A. The results of these sections are summarized in this subsection.

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A R E VA Document No.: ANP-2779NP-001 AREVA NP Inc.,

an AREVA and Siemens company NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation 3.5.1 Method Discussion of Tolerances, Biases, and Uncertainties Criticality analysis methodology involves the computation of a base ken for the Spent Fuel Storage Rack (SFSR) using a code such as KENO-V.a. As an example, a KENO-V.a code bias plus uncertainty on the bias is determined based on comparison to measured critical fuel configurations (i.e., critical benchmarks; see Appendix A) and is then applied to the base absolute keff. The bias is not assembly specific but can be dependent on the type of fuel involved (UO2 versus MOX for example) or on intervening absorber materials.

Typically, a bias is determined using critical benchmark calculations that are appropriate for the type of rack and fuel being analyzed.

There is an uncertainty component on the bias that is the result of both measured and calculated uncertainties associated with the critical configurations analyzed. The uncertainty on the bias may be statistically combined with other uncertainties as it is independent.

Reactivity penalties due to fuel and rack structural tolerances and other uncertainties are determined by difference calculations and applied to the base keff plus bias (See Appendix B). When Monte-Carlo codes are used in difference calculations an answer is provided with an associated uncertainty and the uncertainty on the difference calculation must be considered at the 95/95 confidence level.

The K9si95 for the evaluation is calculated using the following formulation:

K95 95 = keff + biasn, + Ak,YS + [C2(ak2 + 6m2 + (T5ys2 )

+ Ak^o12]",

where, keff

= the KENO-V. a calculated result;

bias,

= the bias associated with the calculation methodology benchmarks; Ak, s

= summation of Ak values associated with the variation of system and base case modeling parameters, e.g. moderator temperature and geometry biases; C

= confidence multiplier based upon the number of benchmark cases; (yk, (Tm, asys

=standard deviation of the calculated keff, methodology, and system Ak,y,;

Ak01

=statistical combination of statistically independent Ak values due to manufacturing tolerances, e.g. fuel enrichment, cell pitch, etc.

3.5.2 System and Tolerance Effects System and tolerance effects are calculated for several combinations of conditions. They are:

1)

Two out of four and three out of four fuel loading configurations.

2)

Rack C and Rack E configurations.

3)

Swelling and nominal (no swelling) conditions.

KENO-V. a is used for all the system and tolerance calculations. A two by two cell KENO-V. a model is used to calculate these effects.

System Effects The system effects are different conditions from the base model of the fuel and rack that could result in a higher calculated kff.

Theses effects are considered additive unless otherwise noted. The system effects are listed below.

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Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation 1)

Rack to Rack Interaction Model (see Section 4.5) 2)

Non Fuel Bearing Components in the Empty Cells (see Section 4.4) 3)

Modified Fuel Geometries Relative to the Bounding Assembly Design Defined in Section 3.3.1. (Guide tubes rather than fuel pins, removed fuel pins, removed burnable absorber pins, failed fuel containers) 4)

Pool Temperature from 32°F to 70°F (accident conditions up to 200 OF were found to decrease keff) 5)

Water inside the SS-304 channels for the nominal rack Fuel and Rack Tolerance Effects The fuel and rack tolerances that are examined are listed below.

1)

Centered to Off-Centered Assembly in Fuel Cell 2)

Fuel Tolerance - Enrichment, +/-0.05 weight percent U-235 3)

Fuel Tolerance - Theoretical Density, +1.5%

4)

Fuel Tolerance - Pellet OD, +0.0005" 5)

Fuel Tolerance - Clad Inner Dimension, +0.0015 6)

Fuel Tolerance - Clad Outer Dimension, +0.002" 7)

Fuel Tolerance - Instrument Tube Dimension, ID, +0.0015 8)

Fuel Tolerance - Instrument Tube Dimension, OD, +0.002" 9)

Rack Tolerance - Box Inner Dimension, -0.12"

10) Rack Tolerance - Box Outer Dimension, +0.12"

11) Rack Tolerance - Inner Box Wall Thickness, +0.01"

12) Rack Tolerance - Outer Box Wall Thickness, +0.01"

13) Rack Tolerance - Cell Pitch Decrease, +0.04" 3.5.3 System and Tolerance Results Table 3-3 through Table 3-10 summarizes the tolerance and uncertainty values obtained in the evaluation. Only positive bias/uncertainty values have been extracted from the various evaluations previously described.

Detailed results can be found in Appendix B. The tables list the applicable bias and uncertainty, the case providing the tabulated value, and the table from which it was extracted. The additive biases are generally related to the rack configuration or environment that is defined in the equation as Aks,s. The parameters related to randomly varying 20 Page

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an AREVA and Siemens company Palisades SFP Region 1 Criticality Evaluation NON PROPRIETARY manufacturing tolerances for fuel and/or racks are statistically combined and defined in the equation as Akroi.

In addition, the off-center placement is assumed to be a random parameter.

Table 3-3:

`C' Rack 2-of-4 with Swelling Bias/Uncertainties Description Ak a of Ak Storage Pool Model Configuration Bias Interaction Model, 850 ppm boron NFBC in 2-of-4 `Empty' Cell 0.0018 0.0003 Modified Assembly (bounded by 4.54 wt% Assembly)

Temperature from 32°F to 70°F 0.0003 0.0004 TOTAL (Arithmetic Sum of Penalties) 0.0021 0.0005 Tolerance Uncertainty Ak Off-Centered Not Available Due to Swelling Fuel Tolerance - Enrichment, +Wt%

0.0018 0.0004 Fuel Tolerance -Theoretical Density, +%TD 0.0016 0.0004 Fuel Tolerance - Clad Inner Dimension, +ID 0.0005 0.0004 Fuel Tolerance - Clad Outer Dimension, -OD 0.0024 0.0004 Rack Tolerance - Inner Box Wall Thickness, -

0.0023 0.0004 Rack Tolerance -Outer Box Wall Thickness, -

0.0019 0.0004 TOTAL (Statistical Combination of Uncertainties )

0.0046 0.0010 Table 3-4:

`C' Rack 3-of-4 with Swelling Bias/Uncertainties Description Ak a of Ak Storage Pool Model Configuration Bias Interaction Model, 850 ppm boron NFBC in 2-of-4 `Empty' Cell (not applicable in 3-of-4)

Modified Assembly (bounded by 4.54 wt% Assembly)

Temperature from 32°F to 70°F 0.0005 0.0003 TOTAL (Arithmetic Sum of Penalties) 0.0005 0.0003 Tolerance Uncertainty Ak Off-Centered Due to Swelling Fuel Tolerance - Enrichment, +Wt%

0.0026 0.0003 Fuel Tolerance - Theoretical Density, +%TD 0.0010 0.0003 Fuel Tolerance - Clad Inner Dimension, +ID 0.0005 0.0003 Fuel Tolerance - Clad Outer Dimension, -OD 0.0019 0.0003 Rack Tolerance - Inner Box Wall Thickness, -

0.0027 0.0003 Rack Tolerance - Outer Box Wall Thickness, -

0.0024 0.0004 Rack Tolerance - Pitch Decrease 0.0005 0.0003 TOTAL (Statistical Combination of Uncertainties )

0.0050 0.0008 21 20004-015 (09/30/2008)

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`E' Rack 2-of-4 with Swelling Bias/Uncertainties Description Ak a of Ak Storage Pool Model Configuration Bias Interaction Model, 850 ppm boron 0.0000 0.0004 NFBC in 2-of-4 `Empty' Cell (Not Applicable)

Batch B/C/I + Empty Cells Bounded By G42 0.0040 0.0003 Temperature from 32°F to 70°F 0.0000 0.0004 TOTAL (Arithmetic Sum of Penalties) 0.0040 0.0006 Tolerance Uncertainty Ak Assembly Not Centered In Rack Fuel Tolerance - Enrichment, +Wt%

0.0011 0.0004 Fuel Tolerance -Theoretical Density, +%TD 0.0008 0.0004 Fuel Tolerance - Clad Inner Dimension, +ID 0.0000 0.0004 Fuel Tolerance - Clad Outer Dimension, -OD 0.0018 0.0004 Rack Tolerance - Inner Box Wall Thickness, -

0.0001 0.0004 Rack Tolerance - Outer Box Wall Thickness, -

0.0008 0.0004 Rack Tolerance - Pitch Decrease 0.0023 0.0004 TOTAL (Statistical Combination of Uncertainties )

0.0033 0.0011 Table 3-6:

`E' Rack 3-of-4 with Swelling Bias/Uncertainties Description Ak a of Ak Storage Pool Model Configuration Bias Interaction Model, 850 ppm boron 0.0000 0.0004 NFBC in 2-of-4 `Empty' Cell (Not Applicable)

Batch B/C/I + Empty Cells Bounded By G42 0.0034 0.0003 Temperature from 32°F to 70°F 0.0010 0.0003 TOTAL (Arithmetic Sum of Penalties) 0.0044 0.0006 Tolerance Uncertainty Ak Assembly Not Centered In Rack Fuel Tolerance - Enrichment, +Wt%

0.0022 0.0004 Fuel Tolerance -Theoretical Density, +%TD 0.0016 0.0004 Fuel Tolerance - Clad Inner Dimension, +ID 0.0003 0.0003 Fuel Tolerance - Clad Outer Dimension, -OD 0.0019 0.0003 Fuel Tolerance - IT Inner Dimension, +ID 0.0002 0.0003 Rack Tolerance - Inner Box Wall Thickness, -

0.0023 0.0004 Rack Tolerance - Outer Box Wall Thickness, -

0.0024 0.0004 Rack Tolerance - Pitch Decrease 0.0062 0.0004 TOTAL (Statistical Combination of Uncertainties )

0.0078 0.0010 22 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 Page

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an AREVA and Siemens company Palisades SFP Region 1 Criticality Evaluation Table 3-7:

`C' Rack 2-of-4 No Swelling Bias/Uncertainties NON PROPRIETARY Description Ak a of Ak Storage Pool Model Configuration Bias Absorber Plate Model with Water in Gap 0.0022 0.0004 NFBC in 2-of-4 `Empty' Cell 0.0010 0.0003 Temperature from 32°F to 70°F 0.0003 0.0003 TOTAL (Arithmetic Sum of Penalties) 0.0035 0.0006 Tolerance Uncertainty Ak Off-Centered Assembly in Fuel Box 0.0004 0.0004 Fuel Tolerance - Enrichment, +Wt%

0.0015 0.0004 Fuel Tolerance -Theoretical Density, +%TD 0.0019 0.0004 Fuel Tolerance - Pellet OD, +OD 0.0003 0.0004 Fuel Tolerance - Clad Inner Dimension, +ID 0.0002 0.0004 Fuel Tolerance - Clad Outer Dimension, -OD 0.0023 0.0003 Fuel Tolerance

- IT Dimension, +ID 0.0005 0.0004 Fuel Tolerance - IT Dimension, -OD 0.0004 0.0004 Rack Tolerance - Box Outer Dimension, +

0.0007 0.0004 Rack Tolerance - Inner Box Wall Thickness, -

0.0009 0.0003 Rack Tolerance - Outer Box Wall Thickness, -

0.0004 0.0004 Rack Tolerance - Pitch Decrease 0.0024 0.0003 TOTAL (Statistical Combination of Uncertainties) 0.0044 0.0012 Table 3-8:

`C' Rack 3-of-4 No Swelling Bias/Uncertainties Description Ak a of Ak Storage Pool Model Configuration Bias Absorber Plate Model with Water in Gap 0.0077 0.0004 NFBC in 3-of-4 `Empty' Cell (Not Applicable)

Temperature from 32°F to 70°F 0.0003 0.0004 TOTAL (Arithmetic Sum of Penalties) 0.0080 0.0006 Tolerance Uncertainty Ak Off-Centered Asssembly in Fuel Box 0.0009 0.0004 Fuel Tolerance - Enrichment, +Wt%

0.0020 0.0004 Fuel Tolerance -Theoretical Density, +%TD 0.0012 0.0004 Fuel Tolerance - Pellet OD, +OD 0.0004 0.0004 Fuel Tolerance - Clad Inner Dimension, +ID 0.0008 0.0004 Fuel Tolerance - Clad Outer Dimension, -OD 0.0024 0.0004 Fuel Tolerance - IT Dimension, -ID 0.0002 0.0004 Rack Tolerance - Inner Box Wall Thickness, -

0.0013 0.0003 Rack Tolerance - Outer Box Wall Thickness, -

0.0008 0.0004 Rack Tolerance - Pitch Decrease 0.0085 0.0003 TOTAL (Statistical Combination of Uncertainties )

0.0094 0.0011 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 23 Page

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Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation Table 3-9:

`E' Rack 2-of-4 No Swelling Bias/Uncertainties Description Ak a of Ak Storage Pool Model Configuration Bias Absorber Plate Model with Water in Gap 0.0010 0.0004 NFBC in 2-of-4 `Empty' Cell (Not Stored In `E')

Batch B/C/I + Empty Cells Bounded By G42 0.0040 0.0003 Temperature from 32°F to 70°F 0.0012 0.0004 TOTAL (Arithmetic Sum of Penalties) 0.0062 0.0006 Tolerance Uncertainty Ak Off-Centered Asssembly in Fuel Box 0.0000 0.0004 Fuel Tolerance Enrichment, +Wt%

0.0019 0.0004 Fuel Tolerance -Theoretical Density, +%TD 0.0018 0.0004 Fuel Tolerance

- Pellet OD, +OD 0.0002 0.0004 Fuel Tolerance

- Pellet OD, -OD 0.0006 0.0004 Fuel Tolerance

- Clad Inner Dimension, +ID 0.0009 0.0004 Fuel Tolerance - Clad Outer Dimension, -OD 0.0027 0.0004 Instrument Tube OD +0.002" 0.0005 0.0004 Rack Tolerance - Inner Box Wall Thickness, -

0.0006 0.0004 Rack Tolerance -Outer Box Wall Thickness, -

0.0005 0.0004 Rack Tolerance - Pitch Decrease 0.0017 0.0004 TOTAL (Statistical Combination of Uncertainties )

0.0044 0.0013 Table 3-10 :

`E' Rack 3-of-4 No Swelling Bias/Uncertainties Description Ak a of Ak Storage Pool Model Configuration Bias Absorber Plate Model with Water in Gap 0.0050 0.0004 NFBC in 2-of-4 `Empty' Cell (Not Stored In `E')

Batch B/C/I + Empty Cells Bounded By G42 0.0034 0.0003 Temperature from 32°F to 70°F 0.0003 0.0004 TOTAL (Arithmetic Sum of Penalties) 0.0087 0.0006 Tolerance Uncertainty Ak Off-Centered Asssembly in Fuel Box 0.0060 0.0004 Fuel Tolerance - Enrichment, +Wt%

0.0022 0.0004 Fuel Tolerance -Theoretical Density, +%TD 0.0016 0.0004 Fuel Tolerance - Pellet OD, -OD 0.0006 0.0004 Fuel Tolerance - Clad Inner Dimension, +ID 0.0009 0.0004 Fuel Tolerance - Clad Outer Dimension, -OD 0.0025 0.0004 Fuel Tolerance - IT Dimension, +ID 0.0006 0.0004 Fuel Tolerance - IT Dimension, +OD 0.0007 0.0004 Rack Tolerance - Inner Box Wall Thickness, -

0.0007 0.0003 Rack Tolerance - Outer Box Wall Thickness, -

0.0005 0.0003 Rack Tolerance - Pitch Decrease 0.0072 0.0004 TOTAL (Statistical Combination of Uncertainties) 0.0102 0.0013 24 Page

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Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation 3.5.4 Summary of Bias and Uncertainty Values Table 3-11 summarizes the final Ak adder and the supporting components for each of the configurations examined.

For this formulation it is assumed that a of kea is less than or equal to 0.0007.

If this value is appropriate, then K95195 can be obtained by merely adding the calculated keff value to the Ak values in the table based upon the appropriate rack and loading configuration.

Unless otherwise noted a Akm

, of 0.03 is used to provide a K95195.

Table 3-11:

K95195 Determination Based Upon Calculated Bias/Uncertainty Swelled K9S195

bias, Ak,s a m a of kea Ak.1 a of Ak1a, Rack C 2-of-4 kff+

0.0187 0.00542 0.0021 0.0051 0.0007 0.0046 0.0011 Rack C 3-of-4 ka+

0.0172 0.00542 0.0005 0.0051 0.0007 0.0050 0.0009 Rack E 2-of-4 k ff +

0.0201 0.00542 0.0040 0.0051 0.0007 0.0033 0.0012 Rack E 3-of-4 kea +

0.0226 0.00542 0.0044 0.0051 0.0007 0.0078 0.0011 Nominal Rack C 2-of-4 kff+

0.0201 0.00542 0.0035 0.0051 0.0007 0.0044 0.0013 Rack C 3-of-4 keff +

0.0273 0.00542 0.0080 0.0051 0.0007 0.0094 0.0013 Rack E 2-of-4 ka +

0.0228 0.00542 0.0062 0.0051 0.0007 0.0044 0.0014 Rack E 3-of-4 kea +

0.0286 0.00542 0.0087 0.0051 0.0007 0.0102 0.0014 25 Page

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Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation 4.0 RACK ANALYSIS The current analysis basis for Region 2 from Reference 3 is a maximum ken of less than 1.0 when flooded with unborated water, and less than, or equal to 0.95 when flooded with water having a boron concentration of 850 ppm.

In addition, the keff in accident or abnormal operating conditions is less than 0.95 with 1350 ppm of soluble boron.

This same basis is used for Region 1A, 1B, and lE. The following abnormal conditions are considered:

1.

The deboration of the pool 2.

Misplacement of a fresh assembly within a cell that should be empty 3.

Drop of a fuel assembly outside the rack but adjacent to the rack 4.

Off-center assembly 5.

The `straight deep drop' accident 6.

T-Bone drop accident 7.

Rack interactions The deboration of the SFSR is considered the baseline case and the K95195 is calculated at both 0 ppm boron and 850 ppm boron.

All other abnormal conditions are evaluated at 1350 ppm boron. The misplacement of an assembly into an empty cell is referred to as a `misload.' The misload is important to evaluate since empty cells are used to control reactivity.

The misload condition bounds the drop outside the rack module because the misloaded assembly can increase the the number of face adjacent fuel assemblies by at least four whereas outside the rack will at most be two face adjacent assemblies to the dropped assembly. The off-center assembly which is a horizontal movement of the assembly within the rack is included in the tolerance evaluation. The drop accident within an empty cell is represented by the misload condition. The T-Bone drop accident has an assembly lying on top of the rack structure and is several inches above the active fuel.

This is bounded by the misloaded condition.

The analysis for each of the regions is presented in this section for the unborated and borated condition (boron dilution event). The assembly misload conditions are presented for the borated condition of 1350 ppm boron.

In addition, non-fissile components are addressed relative to being placed into empty cells and rack interface effects are addressed.

26 Page

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A R E VA Document No.: ANP-2779NP-001 AREVA NP Inc.,

an AREVA and Siemens company NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation 4.1 Region 1A with Checker Board Pattern This region is comprised of rack type C with 4.54 weight percent U-235 (w/o) fuel in a checkerboard pattern.

The model, shown in Figure 4-1, has periodic boundary conditions in both the x and y directions.

Figure 4-1:

Fuel Loading Pattern for Region 1A Empty Cell

< 4.54 w/o U235 Assembly 4.1.1 Region IA - Boron Dilution Region IA is analyzed with soluble boron credit. The acceptance criteria with credit for soluble boron are a K95195

<1.0 without soluble boron and <0.95 with 850 ppm of soluble boron. The above array is modeled in KENO-V.a without and with the swelling model at 0 ppm boron and 850 ppm boron. All cases are shown in Table 4-1 and are more than a 0.05 Ak below the respective criterion for no soluble boron and boron dilution.

Table 4-1: Region IA K95195 Determination for Boron Dilution Case Description Boron, ppm keff a

Akm9x K95195 Criterion Region IA without Swelling 0

0.8646 0.0005 0.03 0.8946

< 1.0 Region 1A with Swelling 0

0.9169 0.0005 0.03 0.9469

< 1.0 Region to without Swelling 850 0.7821 0.0004 0.03 0.8121

< 0.95 Region IA with Swelling 850 0.8243 0.0004 0.03 0.8543

< 0.95 4.1.2 Misload Conditions One misloaded location is analyzed with 1350 ppm in an eight by eight array with periodic boundary conditions and is shown in Figure 4-2. The result is shown in Table 4-2 and the K95,95 is below the criterion of 0.95.

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A AREVA AREVA NP Inc.,

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<4.54 w/o U235 Assembly Misloaded 4.54 w/o U235 Assembly Location Table 4-2: Region 1A K95ro5 Determination for Misload Conditions Case Description Boron, ppm kea a

Akmel K91,95 Criterion Region lA misload X 1350 0.9100 0.0005 0.03 0.9400

< 0.95 4.1.3 Conservatisms The misload accident for Region IA is a close approach of 0.01 Ak to the respective limiting criterion of 0.95.

Section 4.2.3 contains a discussion of the conservatisms for Region lB that are also representative of Region IA.

4.2 Region 1B with Face Adjacent Assemblies Region IB is analyzed with soluble boron credit. The acceptance criteria with credit for soluble boron are a K95195

<1.0 without soluble boron and <0.95 with 850 ppm of soluble boron.

This region is required because some assemblies are stuck (not removable) and could be face adjacent to other assemblies.

Region 1 B is defined as the Region 1 Main Spent Fuel Pool with face adjacent fuel (average enrichments less than or equal to 4.34 w/o U235) surrounded by face adjacent empty cells.

4.34 w/o is the maximum nominal average enrichment of the fuel residing in Region 1, during Cycle 20 operation.

There are four allowable regions that are analyzed as acceptable storage patterns. There are two assemblies in a row, three assemblies in a row, four assemblies in a row, and 3 assemblies in an `L' pattern. The first three patterns are governed by the rule, four or less assemblies in a row that have only empty cells in their remaining face adjacent cells. These are displayed in Figure 4-3. The two possible `L' patterns shown in Figure 4-4 and are analyzed. The definition of the pattern is three assemblies in an L shape are allowed, as long as all face adjacent cells to the square box formed by the `L' are empty. There are two orientations based on the alignment with the checkerboard pattern.

First one is an `L' and the second is a reversed V. There are currently only two known 20004-015 (09/30/2008)

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Figure 4-3: Region lB Analyzed Patterns for Four or Less in a Row Empty Cell

< 4.54 w/o U235 Assembly

< 4.34 w/o U235 Assembly Figure 4-4: Region 113 Analyzed Patterns for Three in an L.

Empty Cell

< 4.54 w/o U235 Assembly

< 4.34 w/o U235 Assembly 29 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 Page Two In a Row Three in a row Four in a Row L Pattern Reversed L Pattern

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Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation 4.2.1 Region 1B - Boron Dilution Region 1 B is analyzed with boron credit and the acceptance criteria with credit for soluble boron are K95195 <1.0 without soluble boron and <0.95 with 850 ppm of soluble boron.

This KENO-V.a model has periodic boundary conditions and only the swelling model is presented since in Region IA showed an increase of 0.05Ak. The results are presented in Table 4-3 for the Region lB geometries. The known condition for two assemblies in a row has a K95/95 of more than 0.05 Ak less than the respective criteria. The K95195 for other allowed geometries that may be found during movement are less than the respective criterion. The closest approach is still 0.0242 Ak margin to the 1.0 criterion for 0 ppm. The closest approach at 850 ppm is more than 0.05 Ak from the 0.95 limit.

Table 4-3: Region lB K95195 Determination for Boron Dilution Case Description Boron, ppm key a

Ak, K95195 Criterion Region I B with Swelling 2 in a row 0

0.9118 0.0004 0.03 0.9418

< 1.0 Region I B with Swelling 3 in a row 0

0.9292 0.0005 0.03 0.9592

< 1.0 Region 1 B with Swelling 4 in a row 0

0.9384 0.0005 0.03 0.9684

< 1.0 Region 113 with Swelling 3 in an L 0

0.9458 0.0005 0.03 0.9758

< 1.0 Region 1B with Swelling 3 in a reversed L 0

0.9450 0.0006 0.03 0.9750

< 1.0 Region 1 B with Swelling 2 in a row 850 0.8238 0.0005 0.03 0.8538

< 0.95 Region lB with Swelling 3 in a row 850 0.8453 0.0004 0.03 0.8753

< 0.95 Region I B with Swelling 4 in a row 850 0.8549 0.0005 0.03 0.8849

< 0.95 Region lB with Swelling 3 in an L 850 0.8627 0.0005 0.03 0.8927

< 0.95 Region lB with Swelling 3 in a reversed L 850 0.8627 0.0004 0.03 0.8927

< 0.95 4.2.2 Misload Conditions Several misloaded locations are shown in the Figure 4-5 and are analyzed with 1350 ppm. The results are shown in Table 4-4 and all cases are below the criterion of 0.95.

All the cases are run with the swelling model.

Figure 4-5: Region 1B Analyzed Patterns for Misload Conditions 30 Page Four in a Row Two In a Row Three in a row

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Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation Empty Cell

< 4.54 w/o U235 Assembly

< 4.34 w/o U235 Assembly Misloaded 4.54 w/o U235 Assembly Location [D Table 4-4: Region 1B K95195 Determination for Miisload Conditions Case Description - swelling model Boron, ppm keff a

Ak K95 95 Criterion Region 1B - 2 in a row misload 1 1350 0.9100 0.0005 0.03 0.9400

< 0.95 Region lB - 2 in a row misload 2 1350 0.8870 0.0005 0.03 0.9170

< 0.95 Region 1B - 3 in a row misload 1 1350 0.9115 0.0005 0.03 0.9415

< 0.95 Region lB - 3 in a row misload 2 1350 0.8899 0.0006 0.03 0.9199

< 0.95 Region lB - 4 in a row misload 1 1350 0.9122 0.0005 0.03 0.9422

< 0.95 Region lB - 4 in a row misload 2 1350 0.8759 0.0005 0.03 0.9059

< 0.95 Region lB - 4 in a row misload 3 1350 0.8900 0.0004 0.03 0.9200

< 0.95 Region 1 B - 3 in an L misload 0 1350 0.9021 0.0005 0.03 0.9321

< 0.95 Region I B - 3 in an L misload 1

1350 0.8798 0.0005 0.03 0.9098

< 0.95 Region I B - 3 in an L misload 2 1350 0.8632 0.0004 0.03 0.8932

< 0.95 Region I B - 3 in an L misload 3 1350 0.8938 0.0004 0.03 0.9238

< 0.95 Region I B - 3 in a reversed L misload 0 1350 0.9017 0.0004 0.03 0.9317

< 0.95 Region 1 B - 3 in a reversed L misload 1 1350 0.8987 0.0005 0.03 0.9287

< 0.95 31 Page Reversed L Pattern L Pattern

A 20004-015 (09/30/2008)

A R^E\\VA Document No.: ANP-2779NP-001 AREVA NP Inc.,

an AREVA and Siemens company NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation 4.2.3 Conservatisms The four major conservatisms are no boron in the poison plates, swelling model (0.54" which is no water between the assemblies), no burnup credit, and a 1350 ppm boron rather than a 1720 ppm minimum boron (a Technical Specification Requirement).

Estimates are provided to illustrate the conservatisms in the model. Removing the swelling model yields an approximate Ak of -0.04 as illustrated in Region IA section.

If as little as 10% of the boron in the plates exists, a Ak of -0.08 results even if swelling is retained.

If the boron concentration were at 1720 ppm rather than 1350 ppm, a Ak of -0.03 would result. For the misload, even with no boron in the plates, maximum swelling, and a boron dilution event to 850 ppm, the K95195 would be 0.9849 which still remains below critical with two major abnormal occurrences.

4.3 Region 1E Region lE is analyzed with soluble boron credit. The K95195 acceptance criteria are < 1.0 without soluble boron and < 0.95 with 850 ppm of soluble boron.

Region 1 E contains a five by ten rectangular array of cells with Region 2 racks placed on both ends of the rack as shown in Figure 2-1 in the North Tilt Pit.

This region is defined as a selective loading of one assembly with 3.26 w/o U235 on a corner cell and 34 locations with planar average enrichments less than or equal to 3.05 w/o U235.

Fifteen empty cells are checker boarded in the center region.

The sketch for the KENO-V.a model is shown in Figure 4-6 and is surrounded by 12" of water.

Interaction with the other Region 2 racks is handled in Section 4.5.

< 3.26 w/o U235 Assembly Empty cell or water reflector

< 3.05 w/o U235 Assembly 4.3.1 Region 1E - Boron Dilution The above array was run and the results are shown in Table 4-5 with and without the swelling model at 0 ppm and 850 ppm.

All cases are more than 0.03 Ak below the respective criteria.

32 Page Figure 4-6: Fuel Loading Pattern for Region 1E

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Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation Table 4-5: Region 1E K95/95 Determination for Boron Dilution Case Description Boron, ppm keff a

Ak K95/95 Criterion Region lE without Swelling 0

0.8879 0.0005 0.03 0.9179

< 1.0 Region 1 E with Swelling 0

0.9322 0.0005 0.03 0.9622

< 1.0 Region 1 E without Swelling 850 0.7725 0.0004 0.03 0.8025

< 0.95 Region 1 E with Swelling 850

0. 8224 0.0004 0.03 0.8524

< 0.95 4.3.2 Misload Conditions Three misloaded locations are shown in Figure 4-7 and are analyzed with 1350 ppm of soluble boron. The results are shown in Table 4-6.

Since the swelling model is clearly limiting, only the swelling model is used. The misloaded assembly is conservatively assumed to be 4.54 w/o.

All cases are more than 0.05 Ak below the criterion of 0.95.

Interaction with the other Region 2 racks is addressed in section 4.5.

< 3.26 w/o U235 Assembly Empty cell or water reflector

< 3.05 w/o U235 Assembly Misloaded 4.54 w/o U235 Assembly Location ID Table 4-6: Region IE K95195 Determination for Misload Conditions Case Description Boron, ppm ken a

Ak K95195 Criterion Region 1 E Misload 1 1350 0.8359 0.0004 0.03 0.8659

< 0.95 Region lE Misload 2 1350 0.8638 0.0005 0.03 0.8938

<0.95 Region 1 E Misload 3 1350 0.8379 0.0004 0.03 0.8679

< 0.95 33 Page Figure 4-7: Region 1E Misload Locations

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Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation 4.4 Definition of Non-Fuel Bearing Components (NFBC)

There are several NFBC that may potentially be inserted into the racks. They are:

1.

Heavy Test Assembly - A Standard Assembly with lead (Pb) pellets rather than U02 2.

Test Gauge Assembly - comprised of stainless steel angles and plates to allow testing the box inner dimension 3.

An assembly containing SS-304 Replacement Rods 4.

Vessel Fluence Capsule and Carrier ( bounded by a 5.48" square block of SS304 or square shell with the same mass, -522 Kg or 1100 lbs)

The calculations of these NFBC placed in the required empty cells are shown in Table 4-7 and Table 4-8 for the swelled rack model and nominal rack model, respectively.

Only Rack C is evaluated since it currently contains these components. The base case is a two out of four fuel loading pattern in a ten by ten array of cells with a periodic boundary condition.

All the swelled cases have a Ak < 0.0018 and the nominal cases have a Ak <

0.0010. None of these NFBC is anticipated to be in Rack E so NFBC will be excluded from the required empty cells in Region 1 E.

Table 4-7: NFBC Reactivity Evaluation for Swelled Rack Description kei a

eke, a of Akeft BASE RACK `C' 2-of-4 10x10 Array Model 0.9159 0.0002 Dummy Assembly Results Two Component 2s on opposite sides of an assembly 0.9177 0.0003 0.0018 0.0003 Component 1 0.9159 0.0002 0.0000 0.0004 Component 1 and 2 face adjacent to same assembly 0.9175 0.0002 0.0016 0.0003 Component 1 and 2 diagonal to each other 0.9172 0.0002 0.0013 0.0003 Component 3 0.9167 0.0003 0.0008 0.0003 Stainless Steel Block/Tubes Component 4 5.48" Sq uare SS block in Water Cell 0.9161 0.0003 0.0002 0.0004 5.48" Square SS at Edge of Water Cell 0.9168 0.0002 0.0009 0.0004 SS Square Shell in Water cell with 7.75" OD and 5.48" ID 0.9169 0.0003 0.0010 0.0003 34 Page

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Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation Table 4-8: NFBC Reactivity Evaluation for Nominal Rack Description keff a

Ak,,

a of Akeff BASE RACK `C' 2-of-4 10x10 Array Model 0.8654 0.0003 Dummy Assembly Results Component 1 0.8662 0.0002 0.0008 0.0004 Component 3 0.8659 0.0003 0.0005 0.0003 Component 2 0.8664 0.0003 0.0010 0.0003 Component 1 and 2 face adjacent to same assembly 0.8664 0.0003 0.0010 0.0004 Component 1 and 2 in Diagonal Water Cells 0.8664 0.0003 0.0010 0.0003 Stainless Steel Block/ Tubes Component 4 5.48" Square SS block in Water Cell 0.8653 0.0003

-0.0001 0.0004 5.48" Square SS at Edge of Water Cell 0.8657 0.0003 0.0003 0.0004 SS Square Shell in Water cell with 7.75" OD and 5.48" ID 0.8660 0.0002 0.0006 0.0004 4.4.1 NFBC Conclusions This KENO-V. a problem is a ten by ten array with either both NFBC components 1 and 2 inserted near each other or 3 or 4 inserted.

Therefore, each component number 3 or 4 placed in a required empty cell must be at least 10 locations away from another NFBC. Region 1 B is not a true two out of four checker board array so that the three out of four cells filled would be more representative of its arrangement. The tables in Section 3.5.3 did not include an explicit Oksys for 3 of 4 cells for NFBC.

Since the Ak max of 0.03 is 0.0074 more conservative for the limiting case of swelling for 3 of 4 cells and it is significantly larger than the Ak penalty of 0.0018 for NFBC, the NFBC can be placed in an empty cell in Region IB.

4.5 Rack Interactions The interactions evaluated are between Region IA and Region 2 and between Region 1 E and Region 2. The interface between Region 1 and the Palisades fuel elevator and fuel inspection station remains bounded by reference 3 since the assembly loading of the rack at the boundary will at most be every other cell. The detailed models to perform this study are defined and discussed in detail in Appendix B. The swelling model is used for both the Region IA and Region lE evaluations.

4.5.1 Interaction Effects Results The keff for each rack region model is determined separately and the highest kea of the two racks defines the maximum keff. The two racks are combined at the minimum separation distance of 2.18" and the kea for the combined model is computed. The interaction effect is determined by the difference between the model with the two combined racks and the maximum of the two separate models.

Table 4-9 lists the results for the `C' rack interaction with Region 2 at 0 and 850 ppm. Both Akeff are slightly negative and close to zero indicating no interaction effect. Note that Region 2 is the limiting region with 0 ppm and Region 1 A (rack C) is the limiting region at 850 ppm.

35 Page

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Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation Table 4-9:

Interaction Results for Region 1C and Region 2 Racks Case Description Icea a

Akeo to Reg 2 a of Ak Interaction Model, 0 ppm 0.9563 0.0002

-0.0001 0.0003 Region 2 Model, 0 ppm 0.9564 0.0002 Rack C Model, 0 ppm 0.9107 0.0003 Case Description keff a

Akea to Reg C a of Akeff Interaction Model, 850 ppmB 0.8205 0.0002

-0.0004 0.0003 Region 2 Model, 850 ppmB 0.7541 0.0002 Rack C Model, 850 ppmB 0.8209 0.0002 The Region 1E is a five by ten array of cells reflected by 12" of water so that some effect is expected between Region lE and the neighboring Region 2 racks. The same set of cases is modeled as for Region 1A and Region 2 except two minimum separation distances are modeled as 3.33"and 9". Table 4-10 lists the results for the `E' rack interaction evaluation at 0 and 850 ppm. The first section examines the unborated condition and shows that there is a small interaction effect of 0.0009 Ak for the unborated condition which is negligible. The second set of cases in the table examines the interaction effects with 850 ppm soluble boron. No interaction effect is noted but in the 850 ppm the `E' rack controls the combined reactivity.

Table 4-10:

Interaction Results for Region 1E and Region 2 Racks Case Description Boron, ppm keo a

Akeff to Reg 2 a of et a Interaction Model, 3.33" Minimum Gap 0

0.9409 0.0003 0.0009 0.0004 Interaction Model, >9" Minimum Gap 0

0.9407 0.0003 0.0007 0.0004 Region 2 Model 0

0.9400 0.0003 Rack E Model 0

0.9218 0.0004 Case Description Boron, ppm kea a

Akea to Reg E a of Akeff Interaction Model, 3.33" Minimum Gap 850 0.8139 0.0003 0.0000 0.0004 Region 2 Model 850 0.7420 0.0002 Rack E Model 850 0.8139 0.0003 The dropped/misloaded assembly adjacent to the edge Region I E rack next to the closest Region 2 rack is also evaluated. Region I E primarily contains fuel with enrichments less than 3.05 w/o; however, one 3.26 w/o assembly is placed in the corner of the Region IE rack in a 3-of-4 layout. The dropped or misloaded assembly with 4.54 w/o is assumed to fall face-adjacent to this assembly with 3.05 w/o assemblies in the surrounding rack cells. Table 4-11 lists the results for this calculation for 850 ppm. The presence of the Region 2 rack causes an increase in reactivity of 0.0006 Ak.

This amount is not significant.

Table 4-11: Interaction Results for Region 1E Misload Condition next to Region 2 Case Description o

a Akeff to Reg E a of eke Interaction Model, 850 ppmB 0.8798 0.0004 0.0006 0.0004 Region 2 Model, 850 ppmB 0.7420 0.0002 Rack E Model, 850 ppmB 0.8792 0.0004 36 Page

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Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation 5.0

SUMMARY

AND CONCLUSIONS This report fully documents the criticality safety analysis for the Palisades Region 1 fuel pool storage and meets all the requirements.

The Region 1 racks are analyzed to allow storage of fresh fuel up to a nominal planar average enrichment of 4.54 weight percent U-235 with a very conservative degradation model of the Corborundum'^' plates that assumes significant swelling and complete loss of boron. More than 0.02 Ak margin to the respective criterion is calculated for the boron dilution event (both borated and unborated).

All abnormal conditions meet the 0.95 criterion at 1350 ppm of boron. The conservatisms in the degradation model of the plates are such that if as little as 10% of the boron is retained in the plates, the reactivity in the pool would decrease by more than 0.08 Ak.

37 Page

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Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation 6.0 LICENSING REQUIREMENTS This analysis requires that the Technical Specifications for the Region 1 SFSR be modified to accommodate fuel in the manner defined by this document.

Final wording of the Technical Specifications may differ from the wording presented here as long as the intent of the requirements remains the same. The following requirements apply to Region 1.

1)

Change the Region 1 definition to the following new regions a)

Region IA - Region 1 Main Spent Fuel Pool with checkerboard loading of fuel with empty or non-fuel bearing component cells for fuel having a nominal planar average U-235 enrichments less than or equal to 4.54 weight percent.

This region should not contain any face adjacent fuel.

For those locations that are face adjacent, these locations will be declared Region IB and Region lB requirements must be met at Region IA and 113 interfaces.

b)

Region 113 - Region 1 Main Spent Fuel Pool with face adjacent fuel having a nominal planar average U-235 enrichment less than or equal to 4.34 weight percent surrounded by empty or non-fuel bearing component cells.

i)

Up to four assemblies in a row are allowed, as long as all face adjacent cells are empty or contain non-fuel bearing components.

ii)

Three assemblies in an L pattern are allowed, as long as all face adjacent cells to the square box formed by the L are empty or contain non-fuel bearing components.

c)

Interface Requirements for the Main Spent Fuel Pool i)

The continuous cells with locations of F24 through U24 next to Region 2 must be loaded with at least 1 empty cell between each fuel assembly in these specified cells.

ii)

The fuel locations next to the area containing the elevator and inspection station are 11, 12, 13, J3, K3, L3, M3, N3, 03, P1, P2, and P3. Any assemblies in these locations must be loaded with at least 1 empty cell between each fuel assembly in these locations.

iii) Walls are considered empty cells.

d)

Region I E - Region 1 North Tilt Pit with selective loading of one assembly having a nominal planar average U-235 enrichment less than or equal to 3.26 weight percent and 34 locations having a nominal planar average U-235 enrichments less than or equal to 3.05 weight percent and with 15 empty cells in the pattern Figure 6-1. The right edge (north end) of this pattern must be at least 9" from the Region 2 rack.

38 Page

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< 3.26 w/o U235 Assembly Empty cell

< 3.05 w/o U235 Assembly 2)

Non-fissile bearing components NON PROPRIETARY a)

Any component with non-fissile material can be stored in any designated fuel location in Region IA, 1B, or 1 E without restriction.

b)

If a non-fissile material meets the criteria for a non-fuel bearing component (NFBC) as listed below it can be stored face adjacent to fuel in an empty cell in Region IA or Region 1B.

i)

The gauge dummy assembly and the lead dummy assembly can be stored diagonally adjacent to each other anywhere in Region 1 A or 1 B.

ii)

A fuel assembly composed of up to 216 solid SS rods can be stored face adjacent to fuel in a designated empty cell as long as the non-fuel bearing component is at least ten locations away from another NFBC that is face adjacent to fuel.

iii) A component composed of primarily SS that displaces less than 30 in2 of water at any plane within the active fuel can be stored face adjacent to fuel in a designated empty cell as long as the NFBC is at least ten locations away from another non-fuel bearing component that is face adjacent to fuel.

39 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 Page

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Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation

7.0 REFERENCES

"Quality Assurance Data Final Report, Boron Carbide Neutron Absorbing Plate, NUS Corporation Purchase Order No. PT-5097-9 Si", Research & Development Division, The Carborundum Company.,

Niagara Falls, New York, September, 1977.

2.

SCALE4.4a, "A Modular Code System for Performing Standardized Computer Analysis for Licensing Evaluation," NUREG/CR-0200, Revision 6, May 2000, Oak Ridge National Laboratory (ORNL).

3 EA-SFP-99-03, Palisades New Fuel Storage, Fuel Pool and Fuel Handling Criticality Safety Analysis",

10/23/2000.

EA-SFP-97-01, "Region I Fuel Pool Rack Reactivity Calculations :

Sensitivity to Manufacturing Tolerances ", 3/27/2000 40 Page

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Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation APPENDIX A: BIAS AND BIAS UNCERTAINTY The purpose of the present analysis is to determine the bias of the keacalculated with SCALE 4.4a computer code by using a statistical methodology to evaluate criticality benchmark experiments that are appropriate for the range of parameters expected for spent fuel pool criticality analysis. The scope of this report is limited to the validation of the KENO V.a module and CSAS25 driver in the SCALE 4.4a code package for use with the 44 energy group cross-section library 44GROUPNDF5 spent fuel criticality analysis. These results were previously submitted in reference 1.

This calculation is performed according to the general methodology described in Reference A-2 (NUREG/CR-6698 "Guide for Validation of Nuclear Criticality Safety Methodology") that is also briefly described in Section A. 1. The critical experiments selected to benchmark the computer code system are discussed in Section A.4. The results of the criticality calculations, the trending analysis, the basis for the statistical technique chosen, the bias, and the bias uncertainty are presented in Section A.4.

Final results are summarized in Section A.5.

A.1 Statistical Method for Determining the Code Bias As presented in Reference A-2, the validation of the criticality code must use a statistical analysis to determine the bias and bias uncertainty in the calculation of kff. The approach involves determining a weighted mean of keff that incorporates the uncertainty from both the measurement (Cr,,p) and the calculation method (acaIc). A combined uncertainty can be determined using the Equation 3 from Reference A-2, for each critical experiment:

at = (6calc z

+ GeV 2

)

1n The weighted mean of keff (kff ), the variance about mean (s), and the average total uncertainty of the benchmark experiments (6 2) can be calculated using the weighting factor 1 / 62 (see Eq. 4, 5, and 6 in Reference A-2). The final objective is to determine the square root of the pooled variance, defined as (Eq. 7 from Reference A-2):

sp =

s- +6 The above value is used as the mean bias uncertainty, where bias is determined by the relation:

Bias = keff -1, if keff is less than 1, otherwise Bias = 0 (Eq.8 from Reference A-2)

The approach for determining the final statistical uncertainty in the calculational bias relies on the selection of an appropriate statistical treatment.

Basically, the same steps and methods suggested in Reference A-2 for determining the upper safety limit (USL) can be applied also for determining the final bias uncertainty.

First, the possible trends in bias need to be investigated. Trends are identified through the use of regression fits to the calculated kea results.

In many instances, a linear fit is sufficient to determine a trend in bias.

Typical parameters used in these trending analyses are enrichment, H/X or a generic spectral parameter as the energy of the average lethargy causing fission (EALF).

Reference A-2 indicates that the use of both weighted or unweighted least squares techniques is an appropriate means for determining the fit of a function. For the present analysis linear regression was used on both weighted A-1 Page

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Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation and unweighted keff values to determine the existence of a trend in bias.

Typical numerical goodness of fit tests was applied afterwards to confirm the validity of the trend.

When a relationship between a calculated keff and an independent variable can be determined, a one-sided lower tolerance band may be used (Reference A-2) to express the bias and its uncertainty. When no trend is identified, the pool of keff data is tested for normality.

If the data is normally distributed, then a technique such as a one-sided tolerance limit is used to determine bias and its uncertainty.

If the data is not normally distributed, then a non-parametric analysis method must be used to determine the bias and its uncertainty (Reference A-2).

A.2 Area of Applicability Required for the Benchmark Experiments The spent fuel pool at Palisades will primarily contain commercial nuclear fuel in uranium oxide pins in a square array.

This fuel is characterized by the typical parameter values provided in Table A-1.

These typical values were used as primary tools in selecting the benchmark experiments appropriate for determining the code bias.

Table A-1:

Range of Values of Key Parameters in Spent Fuel Pool Parameter Range of Values Fissile material UO2 rods Physical/Chemical Form Enrichment natural to 5.05 wt% U-235 Moderation/Moderator Heterogeneous/Water Lattice Square Pitch 1.2 to 1.45 cm Clad Zircaloy Soluble Boron Anticipated Absorber/Materials Stainless steel, Boron H/X ratio 0 to 445 Reflection Water, Stainless Steel Neutron Energy Spectrum (Energy of the Average 25 to 2.5 eV 0

Lethargy Causing Fission)

Benchmark calculation have been made on selected critical experiments, chosen, in so far as possible, to bound the range of variables in the spent fuel rack designs.

In rack designs, the most significant parameters affecting criticality are (1) the fuel enrichment, (2) the t°B loading in the neutron absorber, and (3) the lattice spacing.

Other parameters have a smaller effect but have been also included in the analyses.

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Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation One possible way of representing the data is through a spectral parameter that incorporates influences from the variations in the parameter.

Such a parameter is computed by KENO V.a, which prints the EALF. The expected range for this parameter analyses was also included in Table A.2-1 above. Note that there are no critical experiments for low density (mist) moderator cases; however, interspersed moderator cases analyzed in subsequent sections demonstrate that the interspersed moderator cases were not limiting (had very low values of keff) compared to fully flooded (100% dense moderator) cases.

A.3 Description of the Criticality Experiments Selected The set of criticality benchmark experiments has been constructed to accommodate large variations in the range of parameters of the rack configurations and also to provide adequate statistics for the evaluation of the code bias.

One hundred critical configurations were selected from various sources as the International Handbook of Evaluated Criticality Safety Benchmark Experiments (Reference A-3) and previous validation analyses done with configurations from References A-4, A-5, A-6 and A-7. These benchmarks include configurations performed with lattices of U02 fuel rods in water having various enrichments and moderating ratios (H/X). A set of MOX criticality benchmarks is also included in the present set (Reference A-3). The area of applicability (AOA) is established within this range of benchmark experiment parameter values.

A brief description of the selected benchmark experiments, including the name of the SCALE 4.4a input files that have been constructed to model them, is presented in Table A-2. The table includes the references where a detailed description of the experiments and their range of applicability are presented.

Table A-2 : Descriptions of the Critical Benchmark Experiments Experiment Case Name Measure d k a exp Brief Description Neutron Absorber Reflector NUREGlCR-0Ol3 PN L ex eriments Reference A-0 c004 1.0000 0.0020 U02 pellets with

.31 wt%

U None Water and acr lic c005b 1.0000 0.0018 Cluster of fuel rods on a 25.4 mm 0.625 cm Al plates y

plates as well as c006b 1.0000 0.00 19 pitch. Moderator; water or borated 0.625 cm Al plates a biological c007a 1.0000 0.0021 water.

0.302 cm SS-304L shield serve as c008

--b 1.0000 0.0021 Various separation distances plates primary reflector c009b

___c010b_ _

c011 b 1.0000 1.0000 1.0000 0.0021 0.0021 0.0021 used between clusters. Those so indicated have plates of neutron absorbing material poison placed 0.298 cm SS-304L absorber plates with 1.05 wt % or material. A minor contribution c012b between clusters of fuel rods.

For additional details on the 1.62 wt% B comes from the 1.0000 0.0021 experiments and the com t

0.485 cm SS304L channel that c013b 1.0000 0.0021 pu er models used see Referen A 8 plates supports the rod l

c014b ce and evaluated experiments LEU-c usters and the 9.52 mm carbon 1.0000 0.0021 COMP-THERM 002 and LEU-Zircaloy-4 steel tank wall c029b 1.0000 0.0021 COMP-THERM-009 in Reference absorber plates c03Ob 1.0000 0.0021 A-9.

c031 b 1.0000 0.0021 Boral absorber BAW-1484-7 experiments (Reference A-5 e_14 Page

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Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation Experiment Case Name Measure d

ff a exp Brief Description Neutron Absorber Reflector aclpl 1.0002 0.0005 Enrichments of 2.459 wt%

U None Water and aclp2 1.0001 0.0005 3x3 array of fuel clusters. Various 1037 ppm boron aluminum base aclp3 1.0000 0.0006 B4C pins and stainless steel and 764 ppm boron plate are the aclp4 0.9999 0.0006 boron-aluminum sheets were None primary reflective aclp5 1.0000 0.0007 used as neutron absorbers.

None materials in the aclp6 1.0097 0.0012 Cases so indicated also had None experiments.

aclp7 0.9998 0.0009 dissolved boron in the water None Minor aclp8 1.0083 0.0012 moderator.

None contribution from aclp9 1.0030 0.0009 None the steel tank aclpl0 1.0001 0.0009 143 ppm boron walls.

aclpl1a 1.0000 0.0006 510 ppm boron aclpl 1 b 1.0007 0.0007 514 ppm boron aclpl1c 1.0007 0.0006 501 ppm boron aclpl ld 1.0007 0.0006 493 ppm boron aclp11e 1.0007 0.0006 474 ppm boron aclp11f 1.0007 0.0006 462 ppm boron aclpl lg 1.0007 0.0006 432 ppm boron aclpl2 1.0000 0.0007 217 pm boron aclpl3 1.0000 0.0010 15 ppm boron aclpl3a 1.0000 0.0010 28 ppm boron aclpl4 1.0001 0.0010 92 ppm boron aclpl5 0.9998 0.0016 395 ppm boron aclpl6 1.0001 0.0019 121 ppm boron aclp17 1.0000 0.0010 487 ppm boron aclpl8 1.0002 0.0011 197 ppm boron aclpl 9 1.0002 0.0010 634 ppm boron ac p 0 1.0003 0.0011 320 ppm bo ron aclp21 0.9997 0.0015 72 ppm boron BAW-1 645-4 experiments Reference A-6 rcon01 1.0007 0.0006 2.46 wt% z3O U 435 ppm boron Water and rcon02 1.0007 0.0006 5x5 array of fuel cluster. Rod 426 ppm boron aluminum base rcon03 1.0007 0.0006 pitch between 1.2093 cm and 406 ppm boron plate are the rcon04 1.0007 0.0006 1.4097 cm. Cases so indicated 383 ppm boron primary reflective rcon05 1.0007 0.0006 also had dissolved boron in the 354 ppm boron materials in the rcon06 1.0007 0.0006 water moderator.

335 ppm boron experiments.

rcon07 1.0007 0.0006 361 ppm boron minor rcon08 1.0007 0.0006 121 ppm boron contribution from rcon09 1.0007 0.0006 886 ppm boron the steel tank rcon10 1.0007 0.0006 871 ppm boron walls.

rcon11 rconl2 1.0007 1.0007 0.0006 0.0006 852 ppm boron 834 ppm boron rcon13 1.0007 0.0006 815 ppm boron rconl4 1.0007 0.0006 781 ppm boron rcon15 1.0007 0.0006 746 ppm boton rcon16 1.0007 0.0006 1156 p m boron rcon17 1.0007 0.0006 1141 ppm boron A

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Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation Experiment Case Name Measure d keff a exp Brief Description Neutron Absorber Reflector rconl8 1.0007 0.0006 1123 ppm boron rconl9 1.0007 0.0006 1107 ppm boron rcon20 1.0007 0.0006 1093 ppm boron rcon2l 1.0007 0.0006 1068 ppm boron rcon28 1.0007 0.0006 121 ppm boron CEA Valduc mdis01 Critical Mass 1.0000 Laborato 0.0014 ry Experiments (Reference A-7) 4.738 wt% `-5u None The actual mdis02 1.0000 0.0014 CEA Valduc Critical Mass reflector mdis03 1.0000 0.0014 Laboratory experiments. A key boundaries vary mdis04 1.0000 0.0014 aspect of these experiments was from case to mdis05 1.0000 0.0014 to examine the reactivity effects of case.

mdis06 1.0000 0.0014 differing densities of hydrogenous mdis07 1.0000 0.0014 materials within a cross shaped mdis08 1.0000 0.0014 channel box placed between a mdis09 1.0000 0.0014 two by two array of fuel rod bli Th bli mdis10 1.0000 0.0014 assem es.

e assem es h

i t d f

18 18 mdis 11 mdis12 1.0000 1.0000 0.0014 0.0014 eac cons s e o an x

array of aluminum alloy clad fuel U02 pellet columns mdisl3 1.0000 0.0014 The reader is referred to mdisl4 1.0000 0.0014 Reference A-8 for a description of mdisl 5 1.0000 0.0014 the critical mass experiments and mdisl6 1.0000 0.0014 the computer models used for mdisl7 1.0000 0.0014 these validation cases.

mdisl8 1.0000 0.0014 mdis19 1.0000 0.0014 LEU COMP-THERM-0 22, -024 -025 Ex^enments_(Reference A-3 )

Ieuct022-02 1.0000 0.0046 9.83 and 7.41 wt% enriched U02 None Water is the leuct022-03 1.0000 0.0036 rods of varying numbers in primary reflector.

leuct024-01 leuct024-02 Ieuct025-01 1.0000 1.0000 1.0000 0.0054 0.0040 0.0041 hexagonal and square lattices in water.

Minor contribution from the steel tank leuct025-02 1.0000 0.0044 walls.

Mixed Oxide Reference A-3 epri70b (PNL-31) 1.0009 0.0047 Experiments with mixtures of natural U02-2wt%PuO2 687.9 ppm boron Reflected by water and Al.

epri70un

( PNL-30 )

1.0024 0.0060 (8%240Pu).

Square pitched lattices, with 1.7 ppm boron epri87b

( PNL-33 )

1.0024 0.0024 1.778 cm, 2.2098 cm, and 2.5146 cm pitch in borated or pure water 1090.4 ppm boron epri87un (PNL 32^.....

Epri99b

( PNL-35 )

1.

0042 1.0029 0.0031 0.0027 moderator.

0.9 ppm boron 767.2 ppm boron A-5 Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company Palisades SFP Region 1 Criticality Evaluation NON PROPRIETARY Experiment Measure 6 exp Brief Description Neutron Reflector Case Name d keff Absorber Epri99un 1.0038 0.0025 1.6 ppm boron PNL-34 )

Mixed Oxide Reference A-3 saxtn104 1.0000 0.0023 Experiments with mixtures of None Reflected by (case 6 )

natural U02-6.6wt%PuO2 mixed-water and Al.

saxtn56b 1.0000 0.0054 oxide (MOX), square-pitched, 337 ppm boron (case 3 )

partial moderator height lattices.

saxtn792 1.0049 0.0027 Moderator:

borated or pure water None (case 5 )

moderator.

saxton52 1.0028 0.0072 None case 1 saxton56 1.0019 0.0059 None (case 2)

PN L-35 A.4 Results of Calculations with SCALE 4.4a The critical experiments described in Section A.3 were modeled with the SCALE 4.4a computer system. The resulting keff and calculational uncertainty, along with the experimental keff and experimental uncertainty are tabulated in Table A-3.

The parameters of interest in performing a trending analysis of the bias (Including EALF calculated by SCALE 4.4a) are also included in the table.

Table A-3:

Results for the Selected Benchmark Experiments No Case name Benchmark values k.ff 6-P 1

c004 1.0000 0.002 2

c005b 1.0000 0.0018 3

c006b 1.0000 0.0019 4

c007a 1.0000 0.0021 5

c008b 1.0000 0.0021 6

cOO9b 1.0000 0.0021 7

c010b 1.0000 0.0021 8

c011 b 1.0000 0.0021 9

c012b 1.0000 0.0021 10 c013b 1.0000 0.0021 11 c014b 1.0000 0.0021 12 c029b 1.0000 0.0021 13 c03Ob 1.0000 0.0021 14 c031b 1.0000 0.0021 15 ACLP1 1.0002 0.0005 16 ACLP2 1.0001 0.0005 17 ACLP3 1.0000 0.0006 18 ACLP4 0.9999 0.0006 19 ACLP5 1.0000 0.0007 20 ACLP6 1.0097 0.0012 21 ACLP7 0.9998 0.0009 22 ACLP8 1.0083 0.0012 23 ACLP9 1.0030 0.0009 24 AC LP 10 1,0001 0.0009 SCALE 4.4a EALF Enrichment B

H/X Calculated Values (eV) wt% 235U (ppm) k^ff Cy ca4c 0.9966 0.0008 0.1126 4.31 0.0 255.92 0.9950 0.0008 0.1128 4.31 0.0 255.92 0.9964 0.0008 0.1130 4.31 0.0 255.92 0.9973 0.0009 0.1128 4.31 0.0 255.92 0.9966 0.0008 0.1135 4.31 0.0 255.92 0.9967 0.0008 0.1136 4.31 0.0 255.92 0.9977 0.0008 0.1142 4.31 0.0 255.92 0.9949 0.0009 0.1143 4.31 0.0 255.92 0.9967 0.0008 0.1148 4.31 0.0 255.92 0.9969 0.0008 0.1130 4.31 0.0 255.92 0.9958 0.0008 0.1133 4.31 0.0 255.92 0.9972 0.0008 0.1126 4.31 0.0 255.92 0.9972 0.0009 0.1132 4.31 0.0 255.92 0.9993 0.0009 0.1144 4.31 0.0 255.92 0.9912 0.0007 0.1725 2.46 0.0 215.57 0.9951 0.0006 0.2504 2.46 1037.0 215.79 0.9958 0.0006 0.1963 2.46 764.0 215.83 0.9889 0.0008 0.1912 2.46 0.0 215.91 0.9906 0.0007 0.1660 2.46 0.0 215.87 0.9899 0.0009 0.1712 2.46 0.0 215.87 0.9891 0.0008 0.1496 2.46 0.0 215.87 0.9873 0.0007 0.1537 2.46 0.0 215.87 0.9908 0.0008 0.1409 2.46 0.0 215.87 0.9916 0.0007 0.1495 2.46 143.0 215.22 A-6 20004-015 (09/30/2008)

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Document No.: ANP-2779NP-001 NON PROPRIETARY No Case name Benchmark SCALE 4.4a EALF Enrichment B

H/X values Calculated Values (eV) wt% 235U (ppm) k.r crw k^r 25 ACP11A 1.0000 0.0006 0.9948 0.0007 0.1996 2.46 510.0 215.32 26 ACP11B 1.0007 0.0007 0.9947 0.0007 0.1994 2.46 514.0 215.73 27 ACP11C 1.0007 0.0006 0.9944 0.0006 0.2019 2.46 501.0 215.32 28 ACP11D 1.0007 0.0006 0.9952 0.0007 0.2028 2.46 493.0 215.14 29 ACP11 E 1.0007 0.0006 0.9940 0.0006 0.2037 2.46 474.0 214.70 30 ACP11F 1.0007 0.0006 0.9932 0.0007 0.2050 2.46 462.0 214.52 31 ACP11G 1.0007 0.0006 0.9954 0.0007 0.2045 2.46 432.0 215.97 32 ACLP12 1.0000 0.0007 0.9930 0.0008 0.1700 2.46 217.0 215.05 33 ACLP13 1.0000 0.001 0.9933 0.0008 0.1965 2.46 15.0 215.67 34 ACP13A 1.0000 0.001 0.9902 0.0007 0.1981 2.46 28.0 215.91 35 ACLP14 1.0001 0.001 0.9891 0.0008 0.2011 2.46 92.0 215.83 36 ACLP15 0.9998 0.0016 0.9855 0.0007 0.2063 2.46 395.0 215.83 37 ACLP16 1.0001 0.0019 0.9856 0.0007 0.1730 2.46 121.0 215.83 38 ACLP17 1.0000 0.001 0.9899 0.0006 0.2053 2.46 487.0 215.89 39 ACLP18 1.0002 0.0011 0.9886 0.0008 0.1725 2.46 197.0 215.89 40 ACLP19 1.0002 0.001 0.9912 0.0006 0.2061 2.46 634.0 215.89 41 ACLP20 1.0003 0.0011 0.9899 0.0007 0.1730 2.46 320.0 215.89 42 ACLP21 0.9997 0.0015 0.9883 0.0008 0.1532 2.46 72.0 216.19 43 RCON01 1.0007 0.0006 0.9997 0.0007 2.4282 2.46 435.0 17.41 44 RCON02 1.0007 0.0006 1.0004 0.0007 2.4360 2.46 426.0 17.40 45 RCON03 1.0007 0.0006 0.9985 0.0008 2.4972 2.46 406.0 17.40 46 RCON04 1.0007 0.0006 0.9983 0.0007 2.4989 2.46 383.0 17.41 47 RCON05 1.0007 0.0006 1.0002 0.0007 2.4988 2.46 354.0 17.41 48 RCON06 1.0007 0.0006 0.9982 0.0007 2.5119 2.46 335.0 17.41 49 RCON07 1.0007 0.0006 0.9984 0.0006 1.6313 2.46 361.0 17.43 50 RCON08 1.0007 0.0006 1.0155 0.0008 1.1134 2.46 121.0 17.43 51 RCON09 1.0007 0.0006 0.9973 0.0007 1.4481 2.46 886.0 44.81 52 RCON10 1.0007 0.0006 0.9982 0.0008 1.4623 2.46 871.0 44.81 53 RCON11 1.0007 0.0006 0.9958 0.0007 1.5006 2.46 852.0 44.79 54 RCON12 1.0007 0.0006 0.9979 0.0007 1.4942 2.46 834.0 44.81 55 RCON13 1.0007 0.0006 0.9971 0.0006 1.4973 2.46 815.0 44.81 56 RCON14 1.0007 0.0006 0.9967 0.0007 1.5185 2.46 781.0 44.79 57 RCON15 1.0007 0.0006 0.9980 0.0006 1.5122 2.46 746.0 44.79 58 RCON16 1.0007 0.0006 0.9954 0.0006 0.4182 2.46 1156.0 118.47 59 RCON17 1.0007 0.0006 0.9963 0.0007 0.4293 2.46 1141.0 118.47 60 RCON18 1.0007 0.0006 0.9929 0.0007 0.4354 2.46 1123.0 118.44 61 RCON19 1.0007 0.0006 0.9952 0.0007 0.4371 2.46 1107.0 118.44 62 RCON20 1.0007 0.0006 0.9952 0.0007 0.4367 2.46 1093.0 118.44 63 RCON21 1.0007 0.0006 0.9945 0.0007 0.4404 2.46 1068.0 118.44 64 RCON28 1.0007 0.0006 0.9970 0.0008 0.9984 2.46 121.0 17.44 65 MDIS01 1.0000 0.0014 0.9929 0.0008 0.2822 4.74 0.0 137.61 66 MDIS02 1.0000 0.0014 0.9862 0.0009 0.2641 4.74 0.0 137.61 67 MDIS03 1.0000 0.0014 0.9845 0.0009 0.2636 4.74 0.0 137.61 68 MDIS04 1.0000 0.0014 0.9895 0.0008 0.2513 4.74 0.0 137.61 69 MDIS05 1.0000 0.0014 0.9901 0.0009 0.2411 4.74 0.0 137.61 70 MDIS06 1.0000 0.0014 1.0010 0.0008 0.2292 4.74 0.0 137.61 71 MDIS07 1.0000 0.0014 0.9901 0.0009 0.2250 4.74 0.0 137.61 72 MDIS08 1.0000 0.0014 0.9858 0.0008 0.2493 4.74 0.0 137.61 73 MDIS09 1.0000 0.0014 0.9856 0.0009 0.2483 4.74 0.0 137.61 74 MDIS10 1.0000 0.0014 0.9928 0.0009 0.2221 4.74 0.0 137.61 75 MDIS11 1.0000 0.0014 1.0029 0.0009 0.2043 4.74 0.0 137.61 76 MDIS12 1.0000 0.0014 1.0080 0.0008 0.1946 4.74 0.0 137.81 77 MDIS13 1.0000 0.0014 0.9916 0.0009 0.1947 4.74 0.0 137.61 78 MDIS14 1.0000 0.0014 0.9887 0.0008 0.2299 4.74 0.0 137.61 79 MDIS15 1.0000 0.0014 0.9881 0.0010 0.2270 4.74 0.0 137.61 80 MDIS16 1.0000 0.0014 1.0015 0.0008 0.1905 4.74 0.0 137.61 81 MDIS17 1.0000 0.0014 0.9987 0.0008 0.1794 4.74 0.0 137.61 82 MDIS18 1.0000 0.0014 0.9961 0.0008 0.1747 4.74 0.0 137.61 83 MDIS19 1.0000 0.0014 0.9928 0.0009 0.1747 4.74 0.0 137.61 84 Ieuct022-02 1.0000 0.0046 1.0056 0.0013 0.2920 9.83 0.0 80.00 85 Ieuct022-03 1.0000 0.0036 1.0048 0.0013 0.1253 9.83 0.0 151.00 86 Ieuct024-01 1.0000 0.0054 0.999 0.0015 1.0568 9.83 0.0 41.00 A-7 Page 4

A AREVA AREVA NP Inc.,

an AREVA and Siemens company Palisades SFP Region 1 Criticality Evaluation No Case name Benchmark values k^ff 6-P 87 Ieuct024-02 1.0000 0.0040 88 leuct025-01 1.0000 0.0041 89 Ieuct025-02 1.0000 0.0047 90 epri70b (PNL-31) 1.0009 0.0047 91 epri70un (PNL-30) 1.0024 0.0060 92 epri87b (PNL-33) 1.0024 0.0024 93 epri87un (PNL-32) 1.0042 0.0031 94 epri99b (PNL-35) 1.0029 0.0027 95 epri99un (PNL-34) 1.0038 0.0025 96 saxtn104 (case 6) 1.0000 0.0023 97 saxtn56b (case 3) 1.0000 0.0054 98 saxtn792 (case 5) 1.0049 0.0027 99 saxton52 (case 1) 1.0028 0.0072 100 saxton56 (case 2) 1.0019 0.0059 NON PROPRIETARY SCALE 4.4a EALF Enrichment B

H/X Calculated Values (eV) wt% 235U (ppm) k.ff a.l^

1.0048 0.0014 0.1435 9.83 0.0 128.00 0.9851 0.0014 0.4401 7.41 0.0 66.30 0.9936 0.0013 0.2015 7.41 0.0 106.10 0.9995 0.0016 0.7631 688.0 146.15 0.9967 0.0015 0.5648 2.0 146.20 1.0046 0.0013 0.2780 1090.0 308.83 1.0034 0.0013 0.1894 1.0 308.99 1.0066 0.0009 0.1802 767.0 445.41 1.0088 0.0019 0.1353 2.0 445.57 1.0056 0.0017 0.1001 0.0 473.11 0.998 0.0019 0.6523 337.0 95.24 1.0027 0.0019 0.1547 0.0 249.70 0.9987 0.0013 0.8878 0.0 73.86 0.9997 0.0018 0.5450 0.0 95.29 In order to address situations in which the critical experiment being modeled was at other than a critical state (i.e.,

slightly super or subcritical), the calculated keff is normalized to the experimental ke,p, using the following formula (Eq.9 from Reference A-2):

knarm

- kcarc

/ kexp In the following, the normalized values of the keff were used in the determination of the code bias and bias uncertainty.

A.5 Trending Analysis The next step of the statistical methodology used to evaluate the code bias for the pool of experiments selected is to identify any trend in the bias.

This is done by using the trending parameters presented in Table A-4.

Table A-4: Trending Parameters i

Energy of the Average Lethargy causing Fission (EALF)

Fuel Enrichment (wt% 235U)

Atom ratio of the moderator to fuel (H/X)

Soluble Boron Concentration The first step in calculating the bias uncertainty limit is to apply regression-based methods to identify any trending of the calculated values of ken with the spectral and/or physical parameters.

The trends show the results of systematic errors or bias inherent in the calculational method used to estimate criticality.

For the critical benchmark experiments that were slightly super or subcritical, an adjustment to the keff value calculated with SCALE 4.4a (kcajc) was done as suggested in Reference A-2.

This adjustment is done by 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 A-8 Page

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Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation normalizing the calculated (kcaic) value to the experimental value (kexp).

This normalization does not affect the inherent bias in the calculation due to very small differences in keff.

Unless otherwise mentioned, the normalized keff values (k,o,,,,) have been used in all subsequent calculations.

Each subset of normalized kea values is first tested for trending against the spectral and/or physical parameters of interest (in this case, presented in Table A-4 above), using the build-in regression analysis tool from any general statistical software (e.g., Excel).

Trending in this context is linear regression of unweighted calculated keff on the predictor variable(s) (spectral and/or physical parameters).

In addition, the equations presented in Reference A-2 are also applied to check a linear dependency in case of weighted kff, using as weight the factor 1 / a'y as previously discussed.

The linear regression fitted equation is in the form y(x) = a + bx, where y is the dependent variable (kff) and x is any of the predictor variables mentioned in Table A-4. The difference between the predicted y and actual value of it is known as the random error component (residuals).

The final validity of each linear trend is checked using well-established indicators or goodness-of-fit tests concerning the regression parameters. As a first indicator, the coefficient of determination (r2) that is available as a result of using linear regression statistic can be used to evaluate the linear trending.

It represents the proportion of the sum of squares of deviations of the y values about their mean that can be attributed to a linear relation between y and x.

Another assessment of the adequacy of the linear model can be done by checking the goodness -of-fit against a null hypothesis on the slope (b) (Reference A-10, p. 371). The slope test requires calculating the test statistic "T" as in the following equation along with the corresponding statistical parameters (Reference A-10, p. p. 371).

T =

A S/

S CL where, /3, is the estimated slope of the fitted linear regression equation S.,1=

(x1 -x)-

t=1.n

and, s _ (

Y(y, -Y;)2 n-2),=,.n where, y, is the estimated value using the regression equation.

The test statistic is compared to the Student ' s t-distribution (ta,2,,,_2) with 95% confidence and n-2 degrees of freedom (Reference A-11, p. p.T-5 ), where n is the initial number of points in the subset. Given a null hypothesis Ho:f3i=0, of "no statistically significant trend exists (slope is zero)", the hypothesis would be rejected if }TJ >

t,,/2,-2. By only accepting linear trends that the data supports with 95% confidence, trends due to the randomness of the data are eliminated. A good indicator of this statistical process is evaluation of the P-value probability (calculated by the regression tool in Excel) that gives a direct estimation of the probability of having a linear trending due only to chance.

A-9 Page

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Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation The last step employed as part of the regression analysis is determining whether or not the final requirements of the simple linear regression model are satisfied.

The error components (residuals) need to be normally distributed with mean zero, and also the residuals need to show a random scatter about the center line (no pattern). These requirements were verified for the present calculation using the built-in statistical functions in Excel and by applying an omnibus normality test (Anderson-Darling [Reference A-12, p.372]) on the residuals.

The results of the trending parameter analysis for the criticality benchmark set (unweighted ka) are summarized in Table A-5.

Table A-5: Summary of Trending Analysis Trend Goodness-of-Valid Parameter n

Intercept Slope r2 T

t0.025 n-2 P-value fit Tests Trend EALF 100 0.9937 0.002 0.061 2.53 1.987 0.013 Not Passed No (residuals not normal and show a pattern

-see Figure A-1 Enrichment 90a 0.9911 0.0008 0.070 2.57 1.991 0.012 Not passed No (wt% 235U)

(residuals not normal and show a pattern

- see Figure A-2 H/X 100 0.9952

-2.2E-06 0.001

-0.37 1.987 0.714 Not Passed No Boron in 100 0.9945 1.5E-06 0.009 0.95 1.987 0.345 Not passed No moderator (ppm )

Note:

° Benchmark experiments with MOX fuel excluded.

The results in above table show that there are no statistically significant and valid trends of keff with the trending parameters. An additional check was done by determining if there are any trends on the weighted data. The results of the regression analysis obtained using weighted ke ff (with the weight factor 1 / (T' as previously discussed) show that the determination coefficient (r2) has similar low values as in the above table, evidencing very weak and statistically insignificant trends.

Figure A-1 to Figure A-6 show the distribution of the normalized keff values versus the trending parameters investigated.

A-10 Page

20004-015 (09/30/2008)

A R E VA Document No.: ANP-2779NP-001 AREVA NP Inc.,

an AREVA and Siemens company NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation Figure A-i Distribution of keff Data versus EALF for the Selected Pool of Benchmark Experiments 1.02 1.01 1

0.99 0.98 0.97 0.00 11 It s

0.50 1.00 1.50 2.00 2.50 3.00 EALF (eV)

A-11 Page

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Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation Figure A-2:

Distribution of keff Data versus Enrichment (235U) for the Selected Pool of Benchmark Experiments 1.02 1.01 1

=

0.99 0.98

=

0.97 0.00 1.00 2.00 3.00 4.00 5.00 6.00 7.00 8.00 9.00 10.00 Enrichment (wt%)

Figure A-3:

Distribution of keff Data versus H/X for the Selected Pool of Benchmark Experiments 1.02 1.01 0.99 t

0.98 s

0.97 0.00 50.00 100.00 150.00 200.00 250.00 300.00 350.00 400.00 450.00 500.00 WX A-12 Page

20004-015 (09/30/2008)

A R E VA Document No.: ANP-2779NP-001 AREVA NP Inc.,

an AREVA and Siemens company NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation Figure A-4:

Distribution of keff Data versus Soluble Boron Concentration for the Selected Pool of Benchmark Experiments 1.02 1.01 1

0.99 0.98 0.97

,y^

N

*N **

0.00 200.00 400.00 600.00 800.00 1000.00 1200.00 1400.00 Boron (ppm)

Figure A-5:

Plot of Standard Residuals for Regression Analysis with EALF as Trending Parameter 4.0000 3.0000 2.0000 1.0000 0.0000 0.

I

-1.0000

-2.0000

-3.0000 EALF (eV)

A-13 Page

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Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation Figure A-6:

Plot of Standard Residuals for Regression Analysis with Enrichment as Trending Parameter 5.0000 4.0000 3.0000 N

J 2.0000 41 1.0000 0.0000 rn 0.

-1.0000

-2.0000

-3.0000 A.6 Bias and Bias Uncertainty For situations in which no significant trending in bias is identified, the statistical methodology presented in Reference A-2 suggests to first check the normality of the pool of keff data. Applying the Shapiro-Wilk test (Reference A-2) the null hypothesis of a normal distribution is not rejected. A visual inspection of the normal probability plot of the keff data is also evidencing that the pool of keff data for the selected benchmarks can be considered normally distributed.

This situation allows the application of the weighted single-sided lower tolerance limit to determine the bias uncertainty (Reference A-2).

First by determining of the factor for 95% probability at the 95% confidence level (C95/95) and then multiplying it with the evaluated squared-root of the pooled variance, the uncertainty limit is determined.

From Reference A-13, C95195 for n equal to 100 is 1.927. The squared root of the pooled variance calculated using the formulas presented is:

s p =

s_ + 6' = (2.45212E-05+l.63005E-06)05 =0.00511 Bias Uncertainty = C959 SP = 1.927

0,00511 = 0.00985 The bias is obtained using the formula that includes the weighted average of kff A-14 Page Enrichment (wt %235U)

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Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation Bias = keff -1= 0.99458 - 1 = -0.00542 These represent the final results that can be further used to evaluate the maximum kea values in the criticality analysis of the Palisades spent fuel pool.

A.7 Areas of Applicability A brief description of the spectral and physical parameters characterizing the set of selected benchmark experiments is provided in Table A-6.

Table A-6: Range of Values of Key Parameters in Benchmark Experiments Parameter Range of Values Geometrical shape Heterogeneous lattices; Rectangular and hexago nal Fuel type U02 rods MOX fuel rods Enrichment (for U02 fuel) 2.46 to 9.83 wt % 235U Lattice pitch 1.04 to 2.6416 cm H/X 17.4 to 445 EALF 0.11 to 2.51 eV Absorbers Soluble boron Boron in plates:

Reflectors Water Stainless Steel Aluminum A.8 Bias Summary and Conclusions The results of this evaluation for a selected set of criticality benchmark experiments with enrichments ranging from about 2.5 to about 10 wt% 235U and including also some experiments with MOX fuel rods provide the following information relative to the SCALE4.4a bias.

Bias = kef. -1 = 0.99458 - 1 = -0.00542 Note that this bias will be applied as a positive penalty in the equation for computation of km.

Bias Uncertainty = C95195' s,, = 1.927

0.00511 = 0.00985 A-I 5 Page

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Document No.: ANP-2779NP-001 NON PROPRIETARY The bias and its uncertainty (95/95 weighted single-sided tolerance limit) was obtained applying the appropriate steps of the statistical methodology presented in Reference A-2 (NUREG 6698) taking into account the possible trending of keff with various spectral and/or physical parameters. The results are intended to support the criticality analysis of Palisades spent fuel pool.

A.9 Appendix A References A-1 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO.

1 DOCKET NO. 50-400/LICENSE NO.

NPF-63 REQUEST FOR LICENSE AMENDMENT, Framatome ANP, Inc 77-5069740-NP-00, "Shearon Harris Criticality Evaluation." ML052510504 2005-08-3 1, A-2 Nuclear Regulatory Commission, "Guide for Validation of Nuclear Criticality Safety Calculational Methodology", NUREG/CR-6698, January 2001.

A-3 Nuclear Energy Agency, "International Handbook of Evaluated Criticality Safety Benchmark Experiments." NEA/NSC/DOC(95)03, Nuclear Energy Agency, Organization for Co-operation and Development, 2002.

A-4 Bierman, S. R.., Durst, B. M., Clayton, E. D., "Critical Separation Between Subcritical Clusters of 4.29 Wt% 235U Enriched UO2 Rods in Water With Fixed Neutron Poisons," Battelle Pacific Northwest Laboratories, NUREG/CR-0073(PNL-2615).

A-5 Baldwin, M. N., et. al.,"Critical Experiments Supporting Close Proximity Water Storage of Power Reactor Fuel," BAW-1484-7, July 1979.

A-6 Hoovler, G. S., et.al., "Critical Experiments Supporting Underwater Storage of Tightly Packed Configurations of Spent Fuel Pins," BAW-1645-4, November, 1981.

A-7 "Dissolution and Storage Experimental Program with U[4.75]02 Rods," Transactions of the American Nuclear Society, Vol. 33, pg. 362.

A-8 ANSI/ANS-57.2 - "Design requirements for Light Water Reactor Spent Fuel Storage Facilities at Nuclear Power Plants," American Nuclear Society, 1983.

A-9 SCALE4.4a, "A Modular Code System for Performing Standardized Computer Analysis for Licensing Evaluation," NUREG/CR-0200, Revision 6, May 2000, Oak Ridge National Laboratory (ORNL).

A-10 Rosenkrantz W.A., Introduction to Probability and Statistics for Scientists and Engineers,

. The McGraw-Hill, New York, NY, 1989.

A-11 Natrella, M.G., Experimental Statistics. National Bureau of Standards Handbook 91, Washington, D.C.,

U.S. Department of Commerce, National Bureau of Standards, 1963.

A-12 D'Agostino, R.B. and Stephens, M.A., Goodness-of-fit Techniques. Statistics, Textbooks and Monographs, Volume 68. New York, New York, 1986.

A-13 Owen, D.B., Handbook of Statistical Tables, Addison-Wesley, Reading, MA.

A-16 Page

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Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation APPENDIX B: TOLERANCE CALCULATIONS This appendix includes the details of the system and tolerance studies that define the Ak,,,ax adder for the accident evaluations.

B.l System Bias (AkS,,S and a,y,)

These are the calculations that define the biases on the reactivity calculations that are not considered random variation.

These effects that could lead to such biases are rack interaction effects, the use of NFBC in required empty cells, modified fuel assemblies, and pool temperature. These effects are represented in the equation by Oks,s and as,s (see Section 3.5.1)

B.l.l Rack Interaction Models This section describes the rack interface models to support the results presented in section 4.5. The Region 2 rack geometry is needed to perform a rack interface model and is more complicated than either of the racks in Region

1. The model must split the rack into unit arrays that in this case requires a portion of the fabricated rack cell to be modeled in the inter-box cell. The cut off portion encompasses a large portion of the Boraflex gap region (hence forth referred to as the gap region).

The fabricated box model is the simplest because it is simply a stainless steel box with a small slice of the gap region. Table B-1 lists the dimensions in the model.

Table B-l:

Fabricated Box Model Dimensions Component in Cumulative cm 1/2 cm Cell ID 9.00 9.00 22.860 11.43 Box Wall thickness 0.075 9.15 23.241 11.6205 Gap/wrapper 0.010 9.17 23.292 11.6459 Gap length 7.400 7.400 18.796 9.398 Gap/wrap box 1 horizontal length 9.17 23.2918 11.6459 Gap/wrap box 1 vertical length 9.15 23.241 11.6205 The inter-box is a bit more complicated due to the need to have different units for the gap/wrapper on each side.

Table B-2 lists the dimensions for the model.

Table B-2:

Inter Box Model Dimensions Component in Cumulative cm 1/2 cm Cell ID 9.066 9.066 23.028 11.51382 Wrapper 0.020 9.106 23.129 11.56462 Gap 0.022 9.15 23.241 11.6205 wrapper/gap 0.010 9.17 23.292 11.6459 gap length 7.400 18.796 9.398 gap+wrapper 7.44 18.898 9,4488 gap/wrap box 1 horizontal length 9.17 23.2918 11.6459 gap/wrap box 1 vertical length 9.066 23.02764 11.51382 R-1 Page

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Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation This arrangement works fine for an infinite rack array.

However, this model is being developed for an evaluation of the possible coupling between the Region 1 and Region 2 racks.

Thus, edge units must be developed to provide a finite rack array.

For this evaluation it is assumed that the Region 2 rack will reside to the left of the Region 1 rack.

Thus, right edges are needed to terminate the rack.

Figure B-1 illustrates an expanded section of the KENO-V, a model of the fabricated and inter boxes at the edge of the rack. A listing of a KENO-V.a input deck is for Region 2 is provided in Appendix C.

Figure B-1:

Sketch of KENOV. a Model at Edge of Region 2 Racks B.1.1.1 The `C' rack interaction model uses the maximum swelling model for the `C' rack and the Region 2 model discussed previously. The nominal separation distance between the two regions is 2.43" +/- 0.25" that gives a minimum separation of 2.18" (5.5372 cm). The `C' rack interaction distance uses the minimum separation distance in the model of the two racks. The `C' rack is modeled as a 10x10 array in a 2-of-4 loading pattern. The model extends 102.5" in the y direction based upon the 10.25" pitch. The Region 2 rack is modeled as an 11 x 10 array with a y distance of 100.87" based upon the 9.17" pitch. To provide common y-direction values for the joint array, a 1.63" (4.1402 cm) water gap is placed at the top of the array. This is slightly larger than the -1.438" gap between two modules; however, it is within the 0.25" uncertainty in placement.

Figure B-2 provides a sketch of the model (note only 2 of the 10 axial rows are shown to enable enlargement of the sketch). The two separated racks have a 12" water reflector in the x and z directions. The y-direction has a periodic condition to simulate an infinite rack in that dimension.

B-2 Page Interaction Combined Models

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Sketch of a Portion of the `C'-Region 2 Model The `E' rack interaction model uses the maximum swelling model for the `E' rack and the Region 2 model discussed previously. The nominal separation distance between the two regions is 3.58" +/- 0.25", which gives a minimum separation of 3.33" (8.5482 cm). The `E' rack interaction distance uses the minimum separation distance in the model of the two racks. The `E' rack is modeled as a 5x 10 array in the loading pattern defined in Section 4.3. The model extends 53.45" in the y direction based upon the 10.69" y-pitch. The Region 2 rack is modeled as a 6x7 array with a y distance of 55.02" based upon the 9.17" pitch. To provide common y-direction values for the joint array, a 1.57" (3.9878) water gap is split over the top and bottom of the `E' rack. Figure B-3 provides a sketch of the model (note only 2 of the axial rows are shown to enable enlargement of the sketch). The two separated racks have a 12" water reflector on all sides. Note the lack of top/bottom plates in the Region 2 model is assumed to have an insignificant effect on results.

B-3 20004-015 (09/30/2008)

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Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation Figure B-3: Sketch of a Portion of the Region 1E -Region 2 Model

,r:

f B.1.2 NFBC Models There are several components stored in Region 1 that do not contain fissile material.

There are two types of dummy assemblies. The first is a dummy assembly that is a standard assembly with lead (Pb) replacing the uranium pellets in the fuel rods. The second is a test gauge comprised of stainless steel angles and plates to allow testing the box inner dimension to ensure an assembly can be inserted into the box.

In addition, there are two stainless steel components related to the vessel fluence surveillance program: one empty surveillance capsule awaiting disposal and a `surveillance capsule carrier'.

Neither contains fissile materials.

The lead dummy assembly comprises lead `fuel' rods with a central instrument tube in the same arrangement as a normal fuel assembly. The reference does not provide a pitch for the fuel rods but it is assumed that the same CE grid used in the actual assemblies was used for this dummy.

Thus, the standard pitch is used. The dimensions of Page

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Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation the fuel rod and the instrument tube are listed in the Table B-3.

It is assumed that the lead completely fills the inner dimension of the fuel rod. The model uses the dimensions in the table.

Table B-3: Lead Dummy Assembly Rod Dimensions Dimension in cm cm Fuel Clad ID 0.3655 0.92837 0.46419 OD 0.413 1.04902 0.52451 IT clad OD 0.413 1.04902 0.52451 thickness 0.015625 ID 0.38175 0.96965 0.48482 The gauge dummy assembly (Lite) is essentially a cage comprised of 1"xl" %" angle iron and 1"x1/4" plate attached to a 'A" top, bottom, and three intermediate plates to provide stability to the cage. The outer square of the assembly is 8.25". Figure B-4 presents a sketch illustrating the outer structure of the assembly with the top and intermediate plates not shown. The three intermediate plates are smeared equally over the active fuel length (132.60") in the model rather than try to model their actual axial locations. Minor deviations in these plate locations will not significantly affect the results.

The top and bottom plates are neglected because they are outside the active fuel region. Table B-4 provides the dimensions for the materials.

Figure B-4:

Lite Dummy Arrangement Sketch 11 r

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Lite Dummy Dimensions Lite Dummy Plate Dimension in AngleBar Thickness 0.25 Angle/Bar Width I

In Outer Square 825 Inner Square (within angle supports) 7.75 Inner Plate Thickness 0.5 The vessel surveillance capsules are made of stainless steel and may be water filled or contained vessel carbon steel components. To bound these components, it was assumed that the Lite Dummy 7.75" square central section is completely filled with stainless steel.

Such a component will bound the dimensions of any other non-fuel bearing steel components that may be stored in a rack location.

This model was subsequently reduced to a stainless steel cuboid and square shell with /2 the cross sectional area of the central section of the Lite Dummy.

The cuboid was either placed in the center of the water cell or centered on an edge of the Lite Dummy angle array, i.e. an outer edge of the block against a center bar on the angle cage. The square shell was placed in the angle array with the outer edge against the angles/bars.

Table B-5 shows the dimensions of the reduced volume models used in the evaluation.

Table B-5:

Stainless Steel NFBC Model Dimensions Box/Shell with SS Cm`

Length, cm

/2 Length, cm Area/side of Inner Region of Lite Dummy 387.50 19.6850 9.8425 One Half Area/Side Length in block 193.75 13.1194 6.9597 1/2 SS Area in Shell 7.75" OD 193.75 13.9194 6.9597 B.1.3 Modified Fuel Assemblies The nominal planar U-235 enrichment of 4.54 bounds the fuel to be stored in Regions 1 A and 1 B. However, Region IE will store older fuel at lower enrichments and some of the assemblies have had their geometry altered.

This section addresses these effects.

There are several assemblies in Region 1 that do not have a complete loading of fuel rods. The batch B and C assemblies, as are all batches up to batch K, were designed with guide tubes containing burnable absorber rods.

Some of these have had the absorber rods removed from the guide tubes to provide more water to the under moderated fuel lattice.

In addition, other assemblies have had rods removed without filling the water holes.

These generally were due to leaking rods and/or for shielded assemblies. The reactivity effect of these empty locations is examined in this section.

Fuel in batches B, C, G, and I are chosen due to guide tube configuration, enrichment, or component dimensions.

In addition, some of those chosen have other rods removed so that this evaluation provides a model for both fuel conditions with guide tubes and missing fuel pins. The results are presented here for batch G that determined the limiting delta Ak for the tolerance table for Region I E.

The G42 assembly that has the C guide tube configuration and has had four fuel rods removed from the interior portion of the assembly.

The locations of these pins are C-13, E-09, H-12, and K-11.

For completeness the G assembly was evaluated for conditions either with empty guide tubes or for the guide tubes replaced with fuel but with the 4 rods removed, but not both. Note that the absorber rods have not been removed from C configuration 20004-015 (09/30/2008)

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Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region I Criticality Evaluation guide tube assemblies.

The results, Table B-6 for the absorber rod removal for a lower enriched assembly are the same as that for the higher enriched I assembly, as expected. The removal of the four rods gives a positive bias

<0.0043 + 0.0004Ak for the 2-of-4 loading for either rack and <0.0034 + 0.0004Ak for the 3-of-4 loading for either rack.

Table B-6: Rod Removal Results for Assembly G42 with either Absorber of 4 Fuel Rods Removed Description a

Akeff a of a ff 2-of-4 Loading in `C' Rack Assembly G42 Filled w Fuel 0.8329 0.0003 Assembly G42w A Guide Tubes 1

0.8381 0.0002 0.0052 0.0004 Assembly G42w A Guide Tubes less 4 rods 0.8372 0.0002 0.0043 0.0004 3-of-4 Loading in `C' Rack Assembly G42 Filled w Fuel 1.0502 0.0002 Assembly G42w A Guide Tubes 1 1.0540 0.0002 0.0038 0.0003 Assembly G42w A Guide Tubes less 4 rods 1.0528 0.0002 0.0026 0.0003 2-of-4 Loadin in `E' Rack Assembly G42 Filled w Fuel 0.8107 0.0002 Assembly G42w A Guide Tubes 1

0.8156 0.0002 0.0049 0.0003 Assembly G42w A Guide Tubes less 4 rods 0.8147 0.0002 0.0040 0.0003 3-of-4 Loadin in `E' Rack Assembly G42 Filled w Fuel 0.9963 0.0002 Assembly G42w A Guide Tubes I

1.0009 0.0002 0.0046 0.0003 Assembly G42w A Guide Tubes less 4 rods 0.9997 0.0002 0.0034 0.0003 B.1.4 Moderator Temperature Effects The reactivity effects with moderator temperature are shown in Table B-7 through Table B-10 for racks C and E without and with swelling. The first case in each table is that for the base model. A comparison with the 32°F shows that it is slightly non-conservative with this value for both loading patterns, although within the uncertainty of the calculation. The following cases provide results for temperatures increasing from 32 to 200°F.

In all cases there is essentially a monotonic decrease in reactivity as the temperature increases.

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Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation Table B-7: Moderator Temperature Effects for `C' Rack - Nominal Model Mod Temperature kea a

Ak ff a of ekea 2-of-4 Base Case - 273K, 1.0 g/cc 0.8653 0.0002

-0.0003 0.0003 32F 0.8656 0.0002 60F 0.8654 0.0002

-0.0002 0.0003 80F 0.8641 0.0003

-0.0015 0.0004 100F 0.8639 0.0003

-0.0017 0.0004 120F 0.8630 0.0003

-0.0026 0.0004 160F 0.8595 0.0003

-0.0061 0.0004 180F 0.8578 0.0003

-0.0078 0.0004 200F 0.8560 0.0003

-0.0096 0.0004 3-of-4 Base Case - 273K, 1.0 g/cc 1.0559 0.0002

-0.0003 0.0004 32F 1.0562 0.0003 60F 1.0557 0.0002

-0.0005 0.0004 80F 1.0557 0.0002

-0.0005 0.0004 IOOF 1.0560 0.0002

-0.0002 0.0004 120F 1.0555 0.0002

-0.0007 0.0004 160F 1.0545 0.0003

-0.0017 0.0004 180F 1.0539 0.0002

-0.0023 0.0004 200F 1.0533 0.0002

-0.0029 0.0004 Table B-8: Moderator Temperature Effects for `C' Rack - Swelling Model Mod Temperature key a

ekeq a of Akeff 2-of-4 Base Case - 273K, 1.0 g/cc 0.9159 0.0003

-0.0003 0.0004 32F 0.9162 0.0002 60F 0.9160 0.0002

-0.0002 0.0003 80F 0.9154 0.0002

-0.0008 0.0003 100F 0.9145 0.0003

-0.0017 0.0004 120F 0.9138 0.0002

-0.0024 0.0004 160F 0.9121 0.0002

-0.0041 0.0003 180F 0.9110 0.0002

-0.0052 0.0003 200F 0.9094 0.0002

-0.0068 0.0003 3-of-4 Base Case - 273K, 1.0 g/cc 1.1473 0.0002

-0.0005 0.0003 32F 1.1478 0.0002 60F 1.1471 0.0002

-0.0007 0.0003 80F 1.1463 0.0002

-0.0015 0.0003 100F 1.1454 0.0002

-0.0024 0.0003 120F 1.1442 0.0002

-0.0036 0.0003 160F 1.1415 0.0002

-0.0063 0.0003 180F 1.1399 0.0002

-0.0079 0.0003 B-8 Page

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Document No.: ANP-2779NP-001 NON PROPRIETARY 20OF 1.1379 0.0002

-0.0099 0.0003 Table B-9: Moderator Temperature Effects for `E' Rack - Nominal Model Mod Temperature ken a

eke,,

a of Akeff 2-of-4 Base Case - 273K, 1.0 g/cc 0.8630 0.0003

-0.0012 0.0004 32F 0.8642 0.0002 60F 0.8632 0.0003

-0.0010 0.0004 80F 0.8622 0.0003

-0.0020 0.0004 100F 0.8612 0.0003

-0.0030 0.0004 120F 0.8601 0.0003

-0.0041 0.0004 160F 0.8568 0.0003

-0.0074 0.0004 180F 0.8546 0.0003

-0.0096 0.0004 200F 0.8520 0.0003

-0.0122 0.0004 3-of-4 Base Case - 273K, 1.0 g/cc 1.0061 0.0002

-0.0003 0.0004 32F 1.0064 0.0003 60F 1.0058 0.0002

-0.0006 0.0004 80F 1.0057 0.0003

-0.0007 0.0004 100F 1.0056 0.0002

-0.0008 0.0004 120F 1.0053 0.0002

-0.0011 0.0004 160F 1.0049 0.0003

-0.0015 0.0004 180F 1.0048 0.0003

-0.0016 0.0004 200F 1.0039 0.0002

-0.0025 0.0004 Table B-10: Moderator Temperature Effects for `E' Rack - Swelling Model Mod Temperature ken a

Akeff a of Akea 2-of-4 Base Case - 273K, 1.0 g/cc 0.8872 0.0003 0.0000 0.0004 32F 0.8872 0.0003 60F 0.8866 0.0003

-0.0006 0.0004 80F 0.8858 0.0003

-0.0014 0.0004 100F 0.8847 0.0003

-0.0025 0.0004 120F 0.8838 0.0002

-0.0034 0.0004 160F 0.8815 0.0002

-0.0057 0.0004 180F 0.8796 0.0002

-0.0076 0.0004 200F 0.8775 0.0002

-0.0097 0.0004 3-of-4 Base Case - 273K, 1.0 g/cc 1.0894 0.0002

-0.0010 0.0003 32F 1.0904 0.0002 60F 1.0891 0,0002

-0.0013 0.0003 80F 1.0884 0.0003

-0.0020 0.0004 100F 1.0888 0.0002 0.0016 0.0003 120F 1.0877 0.0002

-0.0027 0.0003 Page

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Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation 160F 1.0861 0.0002

-0.0043 0.0003 180F 1.0844 0.0003

-0.0060 0.0004 200F 1.0834 0.0002

-0.0070 0.0003 As an independent check of the 44 group cross section calculations for temperature tolerance effects, the 238 group cross sections are repeated for the same range of temperatures.

Table B-11 lists results for the 2-of-4 `C' rack with the 238 group cross sections for the nominal 2 of 4 rack model.

This set provides similar values and trends to those in Table B-7 for the same conditions. There is a slight anomaly at the 80°F value which seems to indicate a slight hump in the values, however, this trend in the 238 group results could be to due to the statistical uncertainty. While a validation file has not been prepared for the 238 group cross section set, this comparison gives credence to the results using the 44-group cross section set.

Table B-11: Moderator Temperature Effects for `C' Rack with 238 Group Cross Sections with Nominal Model Mod Temperature key a

Akeff a of Akeff 2-of-4 32F 0.8618 0.0002 60F 0.8613 0.0003

-0.0005 0.0004 80F 0.8600 0.0003

-0.0018 0.0004 100F 0.8604 0.0003

-0.0014 0.0004 120F 0.8590 0.0003

-0.0028 0.0004 160F 0.8559 0.0003

-0.0059 0.0004 180F 0.8540 0.0003

-0.0078 0.0004 200F 0.8518 0.0003

-0.0100 0.0004 B.2 Statistical Tolerance Studies for Akro, and (Ft.,

This section describes the details of the random varying parameters that contribute to Akt°, and 6,°,.

B.2.1 Planar Enrichment and Assembly Placement The planar enrichment and assembly placement assessments are performed with the same set of cases. The enrichment zoning of the fuel is illustrated in Figure B-5.

Palisades has a wide and narrow water gap between each assembly and the lower enrichments are loaded in the core next to the wide water gaps.

In the SFSR, these assemblies can be placed in any orientation.

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Document No.: ANP-2779NP-001 NON PROPRIETARY Figure B-5:

Pin Arrangements for Batch X Fuel Assemblies x1 900000000000000 900000000000000 NOOOOOOOOOOOOO 00000000000000 900000000000000

@00000000000000 e00000000000000 GOOOOOOOOOOOOOO e000000000000 00000000000000 000000000000000 000000000000000 W

X2 000 000 O

600000000000W 000000000000000 NOOOOOOOOO000 900000000000000 0000000000000

@00000000 000000 900000000000000

@00000000000000 6O04)0OO0OO000 90000000000000

@W000000000000W 0900000000000TO X3 O

O uo2 4.95 4. 13 3.23 3.23 2.43

Rods, wt%

ooo 0000000000000 00

@0 000000000000

@MOOOOOOOOOOO0 000000004000

@00000000000000 O00000000000 900000000000000

@@0000000001000 000000000000000 00000000000009S 0000000000000 4D0000000000000 006000000000000

Guide Bar (DO Gd Rods 0

Instr.

Eight different orientations of the fuel assembly are analyzed with explicit pin enrichments and averaged pin enrichments. The orientations are:

1)

Planar Average Wt% Centered in Rack 2)

Planar Average Wt% in corner not adjacent - all assemblies shifted to the same South East corner as an example.

3)

Planar Average Wt% common side - Every two assemblies are moved toward each other 4)

Planar Average Wt% In Adjacent Corner - Every four assemblies in a square are moved toward their common corner in the rack.

5)

Explicit Wt% Centered 6)

Explicit Wt% in Adjacent Corner - Same as 4 but the all the assemblies are orientated with the South East corner of the assembly in the South East corner of the rack cell. The North West corner refers to the orientation of the pins as shown in Figure B-5.

7)

Explicit Wt% Rotated for high wt% Adjacent, centered - Assemblies are rotated so that every four assemblies in a square have their South East assembly corner in a common corner of the rack.

See Figure B-6.

8)

Explicit Wt% Rotated for high wt% Adjacent, in Adj Corner - Same as 7 but same four assemblies in a square are moved toward their common corner in the rack.

See Figure B-6.

B-11 Page

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Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation Figure B-6:

Fuel Orientation for Assembly Placement Orientation 7 SE SE SE SE Orientation 8 SE SE SE SE Assembly I

I water gap The results are shown in Table B-12 and Table B-13 for rack C and E, respectively. The first difference column represents the differences between the averaged enrichment and the zoned fuel for each fuel pin location. The second column of differences represents those for the same fuel model but different positions within the fuel box.

This is first done for 4 out of 4 cells to determine the trends even though there are no 4 out of 4 cells allowed.

The limiting configuration for the asymmetric assembly is then run 2-of-4 and 3-of-4 rack loadings. The planar enrichment results for the first set of cases (4-of-4) are all negative by about 1 % 4k, thus showing the conservatism in the average enrichment model for the 4-of-4 rack loading for any location in the assembly.

For the average enrichment cases the corner position provides the largest difference of about 0.2%Ak for either corner position and exceeds that for the horizontal offset. The zone cases provide similar results except that the rotated case significantly exceeds the non-rotated case, as expected. These cases are not rerun for the swelled model since the Rack C model with swelling has no room to move the assembly off center and Rack E showed a negative reactivity effect with movement.

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Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation Table B-12: Planar Enrichment Sensitivity for `C' Rack Difference (Zoned -Avged) by Equivalent Assy Locations (Off-centered -

Centered) for Each Fuel Type Case Description keff a

A kef A ken a

4 of 4 assemblies Planar Average Wt% Centered in Rack 1.1662 0.0003 0.0 0.0 Planar Average Wt% in corner not adjacent 1.1681 0.0003 0.0019 0.0004 Planar Average Wt% common side 1.1670 0.0003 0.0008 0.0004 Planar Average Wt% In Adjacent Corner 1.1680 0.0003 0.0018 0.0004 Explicit Wt% Centered 1.1554 0.0003

-0.0108 0.0004 Explicit Wt% in Adjacent Corner 1.1568 0.0003

-0.0112 0.0004 0.0014 0.0004 Explicit Wt% Rotated for high wt% Adjacent, centered 1.1550 0.0002

-0.0112 0.0004 Explicit Wt% Rotated for high wt% Adjacent, in Adj Corner 1.1576 0.0002

-0.0104 0.0004 0.0026 0.0003 2 of 4 assemblies Planar Average Wt% Centered in Rack 0.8654 0.0003 0.0 0.0 Planar Average Wt% in corner not adjacent 0.8658 0.0003 0.0004 0.0004 Planar Average Wt% common side 0.8656 0.0003 0.0002 0.0004 Planar Average Wt% In Adjacent Corner 0.8655 0.0003 0.0001 0.0004 Explicit Wt% Rotated for high wt% Adjacent, in Adj Corner 0.8641 0.0003

-0.0014 0.0004 3 of 4 assemblies Planar Average Wt% Centered in Rack 1.0559 0.0003 0.0 0.0 Planar Average Wt% in corner not adjacent 1.0565 0.0003 0.0006 0.0004 Planar Average Wt% common side 1.0563 0.0003 0.0004 0.0004 Planar Average Wt% In Adjacent Corner 1.0568 0.0003 0.0009 0.0004 Explicit Wt% Rotated for high wt% Adjacent, in Adj Corner 1.0493 0.0003

-0.0075 0.0004 B-13 Page

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Document No.: ANP-2779NP-001 NON PROPRIETARY Table B-13:

Planer Enrichment Sensitivity for `E' Rack Difference (Zoned -Avged) by Equivalent Assy Locations (Off-centered -

Centered) for Each Fuel Type Case Description kea a

A keR a

A kea a

4 of 4 assemblies Planar Average Wt% Centered in Rack 1.0823 0.0003 0.0 0.0 Planar Average Wt% in corner not adjacent 1.0815 0.0003

-0.0008 0.0004 Planar Average Wt% common side 1.0883 0.0003 0.0060 0.0004 Planar Average Wt% In Adjacent Comer 1.0915 0.0003 0.0092 0.0004 Explicit Wt% Centered 1.0725 0.0003

-0.0098 0.0004 Explicit Wt% in Adjacent Corner 1.0819 0.0003

-0.0096 0.0004 0.0094 0.0004 Explicit Wt% Rotated for high wt% Adjacent, centered 1.0727 0.0003

-0.0096 0.0004 Explicit Wt% Rotated for high wt% Adjacent, in Adj Corner 1.0841 0.0003

-0.0074 0.0004 0.0114 0.0004 2 of 4 assemblies Planar Average Wt% Centered in Rack 0.8632 0.0003 0.0 0.0 Planar Average Wt% in corner not adjacent 0.8614 0.0003

-0.0018 0.0004 Planar Average Wt% common side 0.8632 0.0003 0.0000 0.0004 Planar Average Wt% In Adjacent Corner 0.8627 0.0003

-0.0005 0.0004 Explicit Wt°/o Rotated for high wt% Adjacent, in Adj Corner 0.8606 0.0003

-0.0021 0.0004 3 of 4 assemblies Planar Average Wt% Centered in Rack 1.0055 0.0003 0.0 0.0 Planar Average Wt% in corner not adjacent 1.0054 0.0003

-0.0 001 0.0004 Planar Average Wt% common side 1.0099 0.0003 0.0044 0.0004 Planar Average Wt% In Adjacent Corner 1.0115 0.0003 0.0060 0.0004 Explicit Wt% Rotated for high wt% Adjacent, in Adj Corner 1.0062 0.0003

-0.0053 0.0004 In summary, the uniform zone average enrichment model bounds the results of the explicit zone average enrichment model by at least 0.7% Ak for a 4-of-4 loading, 0.5% Ak for a 3-of-4 loading, and 0.1% for a 2-of-4 loading for both the `C' and `E' racks. Note the decreasing trend with loading corresponds to a decrease trend of ken, so that a larger margin exists for the higher reactivity cases. Table B-l4 lists the summary results for the off-center placement of the assembly in the rack.

Table B-14: Summary of Offset Placement Penalty for Centered Assembly Model Rack C-rack E-rack Loading Pattern a kea a

A kea a

4-of-4 Loading 0.0019 0.0004 0.0092 0.0004 3-of-4 Loadin g 0.0009 0.0004 0.0060 0.0004 2-of-4 Loading 0.0004 0.0004 0.0000 0.0004 Swelled Rack B-14 Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company Palisades SFP Region 1 Criticality Evaluation NON PROPRIETARY B.2.2 Rack Tolerance Studies The detailed results of the rack tolerance calculations are listed in Table B-15 for the `C' rack and Table B-16 for the `E' rack with nominal rack geometry (no swelling) and repeated in Table B-17 and Table B-l8 with the swelling model.

Generally, if the Ak value is equal to or less than the uncertainty in the value, the tolerance effect can be considered equal to zero. However, for conservatism the maximum positive value for a +/-tolerance change will be included in the total tolerance summation. The uncertainty, a, in the Ak value, or the summation of the Ak values is calculated as the square root of the sum of the squares of the individual Ak values. The nominal model assumes that the empty spaces between the inner and outer box contain water.

This assumption becomes a system bias and is included in the section and is labeled "Absorber Plate Model with Water in Gap."

It is also in Italic to differentiate it from the other random tolerances.

Table B-15: Rack `C' Tolerance Results - Nominal Model Description of Case kea a

Ak to base a Ak Rack C with 2 Assemblies Diagonally in 4 Rack Cells Base C Rack 2-of-4 0.8653 0.0002 Absorber Plate Model with Water in Gap 0.8675 0.0003 0.0022 0.0004 Box ID -0.12: Assy Gap-/Absbr Gap+

0.8585 0.0003

-0.0068 0.0004 Box OD +0.12": Abs Gap+/Flux Trap Gap-0.8660 0.0003 0.0007 0.0004 Box OD +0.12": Abs Gap+/Pitch+

0.8594 0.0003

-0.0059 0.0004 Inner Box Wall Thickness +0.01:ID-0.8639 0.0002

-0.0014 0.0003 Inner Box Wall Thickness +0.01:Absrb Gap-0.8651 0.0003

-0.0002 0.0004 Inner Box Wall Thickness -0.01: Absrb Gap+

0.8662 0.0002 0.0009 0.0003 Outer Box Wall Thickness +0.01:OD+/FT Gap-0.8648 0.0003

-0.0005 0.0004 Outer Box Wall Thickness +0.01:OD+/Pitch+

0.8643 0.0003

-0.0010 0.0004 Outer Box Wall Thickness +0.01:OD+/Abs Gap-0.8655 0.0003 0.0002 0.0004 Outer Box Wall Thickness -0.01:Abs Gap+

0.8657 0.0003 0.0004 0.0004 Pitch +0.04" 0.8634 0.0003

-0.0019 0.0004 Pitch -0.04" 0.8677 0.00 2 0.0024 0.0003 Total Positive A k 0.0044 0.0006 Rack C with 3 Assemblies in 4 Rack Cells Base C Rack 3-of-4 1.0559 0.0002 Absorber Plate Model with Water in Gap E

1.0636 0.0003 0.0077 0.0004 Box ID -0.12: Assy Gap-/Absbr Gap+

1.0467 0.0002

-0.0092 0.0003 Box OD +0.12": Abs Gap+/Flux Trap Gap-1.0551 0.0002

-0.0008 0.0003 Box OD +0.12": Abs Gap+/Pitch+

1.0303 0.0003

-0.0256 0.0004 Inner Box Wall Thickness +0.01 *ID-1.0543 0.0002

-0.0016 0.0003 Inner Box Wall Thickness +0.01:Absrb Gap-1.0550 0.0002

-0.0009 0.0003 Inner Box Wall Thickness -0.01: Absrb Gap+

1.0572 0.0002 0.0013 0.0003 Outer Box Wall Thickness +0.01:OD+/FT Gap-1.0549 0.0002

-0.0010 0.0003 Outer Box Wall Thickness +0.01:OD+/Pitch+

1.0527 0.0002

-0.0032 0.0003 Outer Box Wall Thickness +0.01:Absrb Gap-1.0553 0.0002

-0.0006 0.0003 Outer Box Wall Thickness -0.01:Abs Gap+

1.0567 0.0003 0.0008 0.0004 Pitch +0.04" 1.0476 0.0003

-0.0083 0.0004 B-15 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation Description of Case keff a

Ak to base a Ak Pitch -0.04" 1.0644 0.0002 0.0085 0.0003 Total Positive A k 0.0106 0.0005 Table B-16: Rack `E' Tolerance Results Description of Case keu a

Ak to base a Ak Rack E with 2 Assemblies Diagonally Loaded in 4 Rack Cells Base E Rack 2-of-4 0.8630 0.0003 Absorber Plate Model with Water in Gap 0.8640 0.0003 0.0010 0.0004 Box ID -0.12: Assy Gap-/Absbr Gap+

0.8567 0.0002

-0.0063 0.0004 Box OD +0.12": Abs Gap+/Flux Trap Gap-0.8627 0.0003

-0.0003 0.0004 Box OD +0.12": Abs Gap+/Pitch+

0.8591 0.0003

-0.0039 0.0004 Inner Box Wall Thickness +0.01:ID-0.8626 0.0003

-0.0004 0.0004 Inner Box Wall Thickness +0.01:Absrb Gap-0.8631 0.0002 0.0001 0.0004 Inner Box Wall Thickness -0.01: Absrb Gap+

0.8636 0.0003 0.0006 0.0004 Outer Box Wall Thickness +0.01:OD+/FT Gap-0.8627 0.0003

-0.0003 0.0004 Outer Box Wall Thickness +0.01:OD+/Pitch+

0.8629 0.0003

-0.0001 0.0004 Outer Box Wall Thickness +0.01:Absrb Gap-0.8635 0.0003 0.0005 0.0004 Outer Box Wall Thickness -0.01:Abs Gap+

0.8630 0.0003 0.0000 0.0004 Pitch +0.04" 0.8624 0.0003

-0.0006 0.0004 Pitch -0.04" 0.8647 0.0003 0.0017 0.0004 Total Positive A k 0.0028 0.0007 Rack E with 3 Assemblies in 4 Rack Cells Base E Rack 3-of-4 1.0061 0.0002 Absorber Plate Model with Water in Gap 1.0111 0.0003 0.0050 0.0004 Box ID -0.12: Assy Gap-/Absbr Gap+

0.9966 0.0002

-0.0095 0.0003 Box OD +0.12": Abs Gap+/Flux Trap Gap-1.0057 0.0002

-0.0004 0.0003 Box OD +0.12": Abs Gap+/Pitch+

0.9862 0.0003

-0.0199 0.0004 Inner Box Wall Thickness +0.01:ID-1.0045 0.0003

-0.0016 0.0004 Inner Box Wall Thickness +0.01:Absrb Gap-1.0054 0.0003

-0.0007 0.0004 Inner Box Wall Thickness -0.01: Absrb Gap+

1.0068 0.0002 0.0007 0.0003 Outer Box Wall Thickness +0.01:OD+/FT Gap-1.0051 0.0002

-0.0010 0.0003 Outer Box Wall Thickness +0.01:OD+/Pitch+

1.0038 0.0003

-0.0023 0.0004 Outer Box Wall Thickness +0.01:Absrb Gap-1.0056 0.0002

-0.0005 0.0003 Outer Box Wall Thickness -0.01:Abs Gap+

1.0066 0.0002 0.0005 0.0003 Pitch +0.04" 0.9989 0.0002

-0.0072 0.0003 Pitch -0.04" 1.0133 0.0003 0.0072 0.0004 Total Positive A k 0.0084 0.0005 B-16 Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation Table B-17: RACK `C' SWOLLEN TOLERANCE RESULTS Description of Case keu a

Ak to base a Ak Rack C with 2 Assemblies Diagonally in 4 Rack Cells Base C Rack 2-of-4 0.9159 0.0003 Inner Box Wall Thickness +0.01:ID-0.9141 0.0003

-0.0018 0.0004 Inner Box Wall Thickness +0.01:Absrb Gap-0.9138 0.0002

-0.0021 0.0004 Inner Box Wall Thickness -0.01: Absrb Gap+

0.9182 0.0002 0.0023 0.0004 Outer Box Wall Thickness +0.01:OD+/FT Gap-0.9136 0.0003

-0.0023 0.0004 Outer Box Wall Thickness +0.01:OD+/Pitch+

0.9142 0.0002

-0.0017 0.0044 Outer Box Wall Thickness +0.01:OD+/Abs Gap-0.9137 0.0003

-0.0022 0.0004 Outer Box Wall Thickness -0.01:Abs Gap+

0.9178 0.0003 0.0019 0.0004 Pitch +0.04" 0.9158 0.0002

-0.0001 0.0004 Pitch -0.04" 0.9154 0.0003

-0.0005 0.0004 Rack C with 3 Assemblies in 4 Rack Cells Base C Rack 3-of-4 1.1473 0.0002 Inner Box Wall Thickness +0.01:ID-1.1453 0.0002

-0.0020 0.0003 Inner Box Wall Thickness +0.01:Absrb Gap-1.1450 0.00 2

---:60023 0.0003 Inner Box Wall Thickness -0.01: Absrb Gap+

1.1500 0.0002 0.0027 0.0003 Outer Box Wall Thickness +0.01:OD+/FT Gap-1.1450 0.0002

-0.0023 0.0003 Outer Box Wall Thickness +0.01:OD+/Pitch+

1.1447 0.0002

-0.0026 0.0003 Outer Box Wall Thickness +0.01:OD+/Abs Gap-1.1456 0.0002

-0.0017 0.0003 Outer Box Wall Thickness -0.01:Abs Gap+

1.1497 0.0003 0.0024 0.0004 Pitch +0.04" 1.1464 0.0002 0.0009 0.0003 Pitch -0.04" 1.1478 0.0002 0.0005 0.0003 R-17 Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company Palisades SFP Region 1 Criticality Evaluation NON PROPRIETARY Table B-18: RACK `E' SWOLLEN TOLERANCE RESULTS Description of Case key a

Ak to base a Ak Rack E with 2 Assemblies Diagonally Loaded in 4 Rack Cells Base E Rack 2-of-4 0.8872 0.0003 Inner Box Wall Thickness +0.01:ID-0.8857 0.0002

-0.0015 0.0004 Inner Box Wall Thickness +0.01:Absrb Gap-0.8857 0.0003

-0.0015 0.0004 Inner Box Wall Thickness -0.01: Absrb Gap+

0.8873 0.0003 0.0001 0.0004 Outer Box Wall Thickness +0.01:OD+/FT Gap-0.8866 0.0003

-0.0006 0.0004 Outer Box Wall Thickness +0.01:OD+/Pitch+

0.8857 0.0002

-0.0015 0.0004 Outer Box Wall Thickness +0.01:OD+/Abs Gap-0.8864 0.0003

-0.0008 0.0004 Outer Box Wall Thickness -0.01:Abs Gap+

0.8880 0.0002 0.0008 0.0004 Pitch +0.04" 0.8808 0.0003

-0.0064 0.0004 Pitch -0.04" 0.8895 0.0003 0.0023 0.0004 Rack E with 3 Assemblies in 4 Rack Cells Base E Rack 3-of-4 1.0894 0.0002 Inner Box Wall Thickness +0.01:ID-1.0881 0.0003

-0.0013 0.0004 Inner Box Wall Thickness +0.01:Absrb Gap-1.0878 0.0003

-0.0016 0.0004 Inner Box Wall Thickness -0.01: Absrb Gap+

1.0917 0.0003 0.0023 0.0004 Outer Box Wall Thickness +0.01:OD+/FT Gap-1.0881 0.0002

-0.0013 0.0003 Outer Box Wall Thickness +0.01:OD+/Pitch+

1.0870 0.0003

-0.0024 0.0004 Outer Box Wall Thickness +0.01:OD+/Abs Gap-1.0875 0.0002

-0.0019 0.0003 Outer Box Wall Thickness -0.01:Abs Gap+

1.0918 0.0003 0.0024 0.0004 Pitch +0.04" 1.0786 0.0002

-0.0108 0.0003 Pitch -0.04" 1.0956 0.0003 0.0062 0.0004 B-18 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company Palisades SFP Region 1 Criticality Evaluation 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY B.3 Assembly Tolerance Results The results of the assembly tolerance calculations are listed in Table B-19 for the `C' rack and Table B-20 for the

`E' rack with nominal rack geometry (no swelling) and repeated in Table B-21 and Table B-22 with the swelling model.

Generally, if the Ak value is equal to or less than the uncertainty in the value, the tolerance effect can be considered equal to zero. However, for conservatism the maximum positive value for a +/-tolerance change will be included in the total tolerance summation.

The uncertainty, a, in the Ak value, or the summation of the Ak values is calculated as the square root of the sum of the squares of the individual Ak values.

Table B-19: Rack `C' Tolerance Results Description of Case keff a

Ak to base a Ak Rack C with 2 Assemblies Diagonally in 4 Rack Cells Base C Rack 2-of-4 0.8653 0.0002 Enrichment +0.05 wt%

0.8668 0.0003 0.0015 0.0004 Enrichment -0.05 wt%

0.8639 0.0002

-0.0014 0.00 33 Theoretical Density +1.5%

0.8672 0.0003 0.0019 0.0004 Theoretical Density -1.5%

0.8633 0.0002

-0.0020 0.0003 Pellet OD +0.0005" 0.8656 0.0003 0.0003 0.0004 Pellet OD -0.0005" 0.8655 0.0003 0.0002 0.0004 Clad ID +0.0015" 0.8655 0.0003 0.0002 0.0004 Clad ID -0.0015" 0.8644 0.0003

-0.0009 0.0004 Clad OD +0.002" 0.8629 0.0003

-0.0024 0.0004 Clad OD -0.002" 0.8676 0.0002 0.0023 0.0003 Instrument Tube ID +0.0015" 0.8658 0.0003 0.0005 0.0004 Instrument Tube ID -0.0015" 0.8653 0.0003 0.0000 0.0004 Instrument Tube OD +0.002" 0.8656 0.0003 0.0003 0.0004 Instrument Tube OD -0.002" 0.8657 0.0003 0.0004 0.0004 Rack C with 3 Assemblies in 4 Rack Cells Base C Rack 3-of-4 1.0559 0.0003 Enrichment +0.05 wt%

1.0579 0.0002 0.0020 0.0004 Enrichment -0.05 wt%

1.0539 0.0002

-0.0020 0.0004 Theoretical Density +1.5%

1.0571 0.0003 0.0012 0.0004 Theoretical Density -1.5%

1.0548 0.0002

-0.0011 0.0004 Pellet OD +0.0005" 1.0563 0.0002 0.0004 0.0004 Pellet OD -0.0005" 1.0560 0.0003 0.0001 0.0004 Clad ID +0.0015" 1.0567 0.0002 0.0008 0.0004 Clad ID -0.0015" 1.0556 0.0003

-0.0003 0.0004 Clad OD +0,002" 1.0544 0.0002

-0.0015 0.0004 Clad OD -0.002" 1.0583 0.0002 0.0024 0.0004 Instrument Tube ID +0.0015" 1.0559 0.0003 0.0000 0.0004 Instrument Tube ID -0.0015" 1.0561 0.0002 0.0002 0.0004 Instrument Tube OD +0.002" 1.0558 0.0002

-0.0001 0.0004 Instrument Tube OD -0.002" 1.0557 0.0002

-0.0002 0.0004 B-19 Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company Palisades SFP Region 1 Criticality Evaluation 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY Table B-20: Rack `E' Tolerance Results - Nominal Model Description of Case key a

Ak to base a Ak Rack E with 2 Assemblies Diagonally in 4 Rack Cells Base E Rack 2-of-4 0.8630 0.00 3 --

Enrichment +0.05 wt%

0.8649 0.0003 0.0019 0.0004 Enrichment -0.05 wt%

0.8614 0.0003

-0.0016 0.0004 Theoretical Density +1.5%

0.8648 0.0003 0.0018 0.0004 Theoretical Density -1.5%

0.8614 0.0003

-0.0016 0.0004 Pellet OD +0.0005" 0.8632 0.00 33 0.0002 0.0004 Pellet OD -0.0005" 0.8636 0.0003 0.0006 0.0004 Clad ID +0.0015" 0.8639 0.0003 0.0009 0.0004 Clad ID -0.0015" 0.8625 0.0003

-0.0005 0.0004 Clad OD +0.002" 0.8603 0.0003

-0.0027 0.0004 Clad OD -0.002" 0.8657 0.0003 0.0027 0.0004 Instrument Tube ID +0.0015" 0.8630 0.0003 0.0000 0.0004 Instrument Tube ID -0.0015" 0.8630 0.0003 0.0000 0.0004 Instrument Tube OD +0.002" 0.8635 0.0003 0.0005 0.0004 Instrument Tube OD -0.002" 0.8626 0.0003

-0.0004 0.0004 Rack E with 3 Assemblies in 4 Rack Cells Base E Rack 3-of-4 1.0055 0.0003 Enrichment +0.05 wt%

1.0077 0.0003 0.0022 0.0004 Enrichment -0.05 wt%

1.0037 0.00 33

-0.00 8

- 0.00 44 Theoretical Density +1.5%

1.0071 0.0002 0.0016 0.0004 Theoretical Density -1.5%

1.0053 0.0002

-0.0002 0.0004 Pellet OD +0.0005" 1.0058 0.0003 0.0003 0.0004 Pellet OD -0.0005" 1.0061 0.0003 0.0006 0.0004 Clad ID +0.0015" 1.0064 0.0003 0.0009 0.0004 Clad ID -0.0015" 1.0051 0.0003

-0.0004 0.0004 Clad OD +0.002" 1.0038 0.0002

-0.0017 0.0004 Clad OD -0.002" 1.0080 0.0003 0.0025 0.0004 Instrument Tube ID +0.0015 1.0061 0.0002 0.0006 0.0004 Instrument Tube ID -0.0015" 1.0059 0.0003 0.0004 0.0004 Instrument Tube OD +0.002" 1.0059 0.0003 0.0004 0.0004 Instrument Tube OD -0.002" 1.0062 0.0003 0.0007 0.0004 B-20 Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company Palisades SFP Region 1 Criticality Evaluation 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY Table B-21: Rack `C' Fuel Tolerances - Swelling Model Description keff Ak to base a Ak 2-of-4 Loading Pattern Base C Rack 2-of-4 0.9159 0.0003 Enrichment +0.05 wt%

0.9177 0.0003 0.0018 0.0004 Enrichment -0.05 wt%

0.9118 0.0002

-0.0041 0.0004 Theoretical Density +1.5%

0.9175 0.0003 0.0016 0.0004 Theoretical Density -1.5%

0.9143 0.0002

-0.0016 0.0004 Pellet OD +0.0005" 0.9155 0.0003

-0.0004 0.0004 Pellet OD -0.0005" 0.9159 0.0002 0.0000 0.0004 Clad ID +0.0015" 0.9164 0.0003 0.0005 0.0004 Clad ID -0.0015" 0.9151 0.0003

-0.0008 0.0004 Clad OD +0.002" 0.9129 0.0002

-0.0030 0.0004 Clad OD -0.002" 0.9183 0.0002 0.0024 0.0004 Instrument Tube ID +0.0015 0.9158 0.0003

-0.0001 0.0004 Instrument Tube ID -0.0015" 0.9156 0.0002

-0.0003 0.0004 Instrument Tube OD +0.002" 0.9156 0.0002

-0.0003 0.0004 Instrument Tube OD -0.002" 0.9157 0.0002

-0.0002 0.0004 3-of-4 Loading Pattern Base C Rack 3-of-4 1.1473 0.0002 Enrichment +0.05 wt%

1.1499 0.0002 0.0026 0.0003 Enrichment -0.05 wt%

1.1431 0.0002

-0.0042 0.0003 Theoretical Density +1.5%

1.1483 0.0002 0.0010 0.0003 Theoretical Density -1.5%

1.1463 0.0002

-0.0010 0.0003 Pellet OD +0.0005" 1.1471 0.0002

-0.0002 0.0003 Pellet OD -0.0005" 1.1472 0.0002

-0.0001 0.0003 Clad ID +0.0015" 1.1478 0.0002 0.0005 0.0003 Clad ID -0.0015" 1.1467 0.0002

-0.0006 0.0003 Clad OD +0.002" 1.1447 0.0002

-0.0026 0.0003 Clad OD -0.002" 1.1492 0.0002 0.0019 0.0003 Instrument Tube ID +0.0015" 1.1473 0.0002 0.0000 0.0003 Instrument Tube ID -0.0015" 1.1475 0.0002 0.0002 0.0003 Instrument Tube OD +0.002" 1.1471 0.0002

-0.0002 0.0003 Instrument Tube OD -0.002" 1.1471 0.0002

-0.0002 0.0003 Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company Palisades SFP Region 1 Criticality Evaluation NON PROPRIETARY Table B-22: Rack `E' Fuel Tolerances - Swelling Model Description 1ff a

Ak to base Ak 2-of-4 Loading Pattern Base E Rack 2-of-4 0.8872 0.0003 Enrichment +0.05 wt%

0.8883 0.0003 0.0011 0.0004 Enrichment -0.05 wt%

0.8850 0.0002

-0.0022 0.0004 Theoretical Density +1.5%

0.8880 0.0003 0.0008 0.0004 Theoretical Density -1.5%

0.8853 0.0002

-0.0019 0.0004 Pellet OD +0.0005" 0.8862 0.0002

-0.0010 0.0004 Pellet OD -0.0005" 0.8865 0.0003

-0.0007 0.0004 Clad ID +0.0015" 0.8872 0.0003 0.0000 0.0004 Clad ID -0.0015" 0.88 0

- 0.0003

-0.0012 0.0004 Clad OD +0.002" 0.8840 0.0003

-0.0032 0.0004 Clad OD -0.002" 0.8890 0.0003 0.0018 0.0004 Instrument Tube ID +0.0015" 0.8867 0.0003

-0.0005 0.0004 Instrument Tube ID -0.0015" 0.8850 0.0003

-0.0022 0.0004 Instrument Tube OD +0.002" 0.8865 0.0002

-0.0007 0.0004 Instrument Tube OD -0.002" 0.8869 0.00 22

-0.0003 0.0004 3-of-0 Loading Pattern Base E Rack 3-of-4 1.0894 0.0002 Enrichment +0.05 wt%

1.0916 0.0003 0.0022 0.0004 Enrichment -0.05 wt%

1.0869 0.0003

-0.0025 0.0004 Theoretical Density +1.5%

1.0910 0.0003 0.0016 0.0004 Theoretical Density -1.5%

1.0877 0.0003

-0.0017 0.0004 Pellet OD +0.0005" 1.0892 0.0003

-0.0002 0.0004 Pellet OD -0.0005" 1.0893 0.0002

-0.0001 0.0003 Clad ID +0.0015" 1.0897 0.0002 0.0003 0.0003 Clad ID -0.0015" 1.0892 0.0003

-0.0002 0.0004 Clad OD +0.002" 1.0879 0.0002

-0.0015 0.0003 Clad OD -0.002" 1.0913 0.0002 0.0019 0.0003 Instrument Tube ID +0.0015" 1.0896 0.0002 0.0002 0.0003 Instrument Tube ID -0.0015" 1.0889 0.0002

-0.0005 0.0003 Instrument Tube OD +0.002" 1.0892 0.0002

-0.0002 0.0003 Instrument Tube OD -0.002" 1.0892 0.0002

-0.0002 0.0003 The positive values of the these tolerances are listed in the summary tables in Section 3.5.3.

B-22 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 Page

A ARE VA AREVA NP Inc.,

an AREVA and Siemens company 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation APPENDIX C: RACK C, RACK E, AND REGION 2 INPUT DECKS C.1 Rack C Base Model KENO-V.a Input Deck The input deck for Region 1 A is provided below.

It is a 8 by 8 cell model at 0 ppm.

=csas25 parm=size=400000 mark CE 15x15 fa,assy 44groupndf5 latticecell uo2 1

0.96 293 92235 4.54 92238 95.46 end

'm5 modeled as pure Zirc zr 2

1.0 293 end h2o 3

1.0 293 end h2o 4

1.0 293 end zr 5

1.0 293 end

'carbon remaining in absorber w

only C density c

6 den=

0.2720 1.0 293 end he 7

1.0 293 end ss304 8

1.0 293 end h2o 9

1.0 293 end uo2 10 0.96 293 92235 4.34 92238 95.66 end uo2 11 0.96 293 92235 4.19 92238 95.81 end uo2 12 0.96 293 92235 4.05 92238 95.95 end uo2 13 0.96 293 92235 3.95 92238 96.05 end uo2 14 0.96 293 92235 3.62 92238 96.38 end uo2 15 0.96 293 92235 3.26 92238 96.74 end uo2 16 0.96 293 92235 3.05 92238 96.95 end uo2 17 0.96 293 92235 2.43 92238 97.57 end uo2 18 0.96 293 92235 1.20 92238 98.80 end end comp squarepitch 1.3970 0.9144 1

3 1.0592 2

0.9322 7

end more data res=10 cylinder 0.4572 dan(10)=0.23801701 res=ll cylinder 0.4572 dan(11)=0.23801701 res=12 cylinder 0.4572 dan(12)=0.23801701 res=13 cylinder 0.4572 dan(13)=0.23801701 res=14 cylinder 0.4572 dan(14)=0.23801701 res=15 cylinder 0.4572 dan(15)=0.23801701 res=16 cylinder 0.4572 dan(16)=0.23801701 res=17 cylinder 0.4572 dan(17)=0.23801701 res=18 cylinder 0.4572 dan(18)=0.23801701 end more data Palisades 15x15 read parm tme=100 gen=1075 nsk=75 run=yes plt=no npg=3000 nub=yes end parm read geom unit 1

'fuel pin cell 4.54 wt'%%

C-1 Page

A 20004-015 (09/30/2008)

A R E VDr Document No.: ANP-2779NP-001 AREVA NP Inc.,

an AREVA and Siemens company NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation cylinder 1

1 0.4572 cylinder 7

1 0.4661 cylinder 2

1 0.5296 cuboid 3

1 4p0.6985 unit 2

'fuel pin cell 4.34 wt%

cylinder 10 1

0.4572 cylinder 7

1 0.4661 cylinder 2

1 0.5296 cuboid 3

1 4pO.6985 unit 3

'fuel pin cell 4.19 wt%

cylinder 11 1

0.4572 cylinder 7

1 0.4661 cylinder 2

1 0.5296 cuboid 3

1 4pO.6985 unit 4

'fuel pin cell 4.05 wt%

cylinder 12 1

0.4572 cylinder 7

1 0.4661 cylinder 2

1 0.5296 cuboid 3

1 4pO.6985 unit 5

'fuel pin cylinder cylinder cylinder cuboid 336.81 0.0 336.81 0.0 336.81 0.0 336.81 0.0 336.81 0.0 336.81 0.0 336.81 0.0 336.81 0.0 336.81 0.0 336.81 0.0 336.81 0.0 336.81 0.0 336.81 0.0 336.81 0.0 336.81 0.0 336.81 0.0 3.95 wt%

0.4572 336.81 0.C 0.4661 336.81 0.0 0.5296 336.81 0.0 4pO.6985 336.81 0.0 cell 13 1

7 1

2 1

3 1

unit 6

'fuel pin cell 3.62 wt%

cylinder 14 1

0.4572 336.81 0.0 cylinder 7

1 0.4661 336.81 0.0 cylinder 2

1 0.5296 336.81 0.0 cuboid 3

1 4pO.6985 336.81 0.0 unit 7

'fuel pin cylinder cylinder cylinder cuboid 3.26 wt%

0.4572 336.81 0.C 0.4661 336.81 0.C 0.5296 336.81 0.0 4pO.6985 336.81 0.0 cell 15 1

7 1

2 1

3 1

unit 8

'fuel pin cell 3.05 wt° cylinder 16 1

0.4572 336.81 0.0 cylinder 7

1 0.4661 336.81 0.0 cylinder 2

1 0.5296 336.81 0.0 cuboid 3

1 4p0.6985 336.81 0.0 C-2 Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation unit 9

'fuel pin cylinder cylinder cylinder cuboid 2.43 wt%

0.4572 336.81 0.0 0.4661 336.81 0.0 0.5296 336.81 0.0 4pO.6985 336.81 0.0 cell 17 1

7 1

2 1

3 1

unit 10

'fuel pin cell 1.20 wt%

cylinder 18 1

0.4572 336.81 0.0 cylinder 7

1 0.4661 336.81 0.0 cylinder 2

1 0.5296 336.81 0.0 cuboid 3

1 4pO.6985 336.81 0.0 unit 60

'instrument tube cell cylinder 4

1 0.4661 336.81 0.0 cylinder 5

1 0.5296 336.81 0.0 cuboid 4

1 4p0.6985 336.81 0.0 unit 70

'Tie Bar Top cuboid 2

1 2pO.4757 0.6985

-0.37715 336.81 0.0 cuboid 4

1 4pO.6985 336.81 0.0 unit 71

'Tie Bar Bottom cuboid 2

1 2p0.4757 0.37715

-0.6985 336.81 0.0 cuboid 4

1 4pO.6985 336.81 0.0 unit 72

'Tie Bar Left cuboid 2

1 0.37715

-0.6985 2pO.4757 336.81 0.0 cuboid 4

1 4pO.6985 336.81 0.0 unit 73

'Tie Bar Right cuboid 2

1 0.6985

-0.37715 2pO.4757 336.81 0.0 cuboid 4

1 4pO.6985 336.81 0.0 unit 80

'Absorber slot Horizontal

(+X)

Top cuboid 6

1 2p10.49 2pO.2667 336.79 0.0 replicate 0

1 0.00 0.00 0.0508 0.0508 0.0 0.0 1

unit 81

'Absorber slot Horizontal

(+X)

Bottom cuboid 6

1 2plO.49 2pO.2667 336.79 0.0 replicate 0

1 0.00 0.00 0.0508 0.0508 0.0 0.0 1

unit 82

'Absorber slot Horizontal

(+Y)

Left Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation cuboid 6

1 2p0.2667 2p10.49 336.79 0.0 replicate 0

1 0.0508 0.0508 0.00 0.00 0.0 0.0 1

unit 83

'Absorber slot Horizontal

(+Y)

Left cuboid 6

1 2pO.2667 2plO.49 336.79 0.0 replicate 0

1 0.0508 0.0508 0.00 0.00 0.0 0.0 1

unit 85

'Space Cylinder cylinder 8

1 0.3175 336.79 0.0 cuboid 0

1 0.3175

-0.3175 0.3175

-0.3175 336.79 0.0 unit 90

'15 x

15 fa in rack 4.54 Planar Average array 1

-10.4775

-10.4775 0.0 cuboid 0

1 10.4775

-10.4775 10.4775

-10.4775 336.81 0.0 replicate 0

1 0.3937 0.3937 0.3937 0.3937 0.0 0.0 1

replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

replicate 0

1 0.635 0.635 0.635 0.635 0.0 0.0 1

'absorber slot top hole 80 0.0 11.5062 0.01

'absorber slot bottom hole 81 0.0

-11.5062 0.01

'absorber slot left hole 82

-11.5062 0.0 0.01

'absorber slot right hole 83 11.5062 0.0 0.01

'support top left hole 85

-11.5062 11.5062 0.01

'support top right hole 85 11.5062 11.5062 0.01

'support bottom right hole 85 11.5062

-11.5062 0.01

'support bottom left hole 85

-11.5062

-11.5062 0.01 replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

replicate 0

1 0.8763 0.8763 0.8763 0.8763 0.0 0.0 1

unit 91

'15 x

15 fa in rack 4.34 planar average array 2

-10.4775

-10.4775 0.0 cuboid 0

1 10.4775

-10.4775 10.4775

-10.4775 336.81 0.0 replicate 0

1 0.3937 0.3937 0.3937 0.3937 0.0 0.0 1

replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

replicate 0

1 0.635 0.635 0.635 0.635 0.0 0.0 1

'absorber slot top hole 80 0.0 11.5062 0.01

'absorber slot bottom hole 81 0.0

-11.5062 0.01

'absorber slot left hole 82

-11.5062 0.0 0.01

'absorber slot right Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation hole 83 11.5062 0.0 0.01

'support top left hole 85

-11.5062 11.5062 0.01

'support top right hole 85 11.5062 11.5062 0.01

'support bottom right hole 85 11.5062

-11.5062 0.01

'support bottom left hole 85

-11.5062

-11.5062 0.01 replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

replicate 0

1 0.8763 0.8763 0.8763 0.8763 0.0 0.0 1

unit 92

'15 x

15 fa in rack 4.19 array 3

-10.4775

-10.4775 0.0 cuboid 0

1 10.4775

-10.4775 10.4775

-10.4775 336.81 0.0 replicate 0

1 0.3937 0.3937 0.3937 0.3937 0.0 0.0 1

replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

replicate 0

1 0.635 0.635 0.635 0.635 0.0 0.0 1

'absorber slot top hole 80 0.0 11.5062 0.01

'absorber slot bottom hole 81 0.0

-11.5062 0.01

'absorber slot left hole 82

-11.5062 0.0 0.01

'absorber slot right hole 83 11.5062 0.0 0.01

'support top left hole 85

-11.5062 11.5062 0.01

'support top right hole 85 11.5062 11.5062 0.01

'support bottom right hole 85 11.5062

-11.5062 0.01

'support bottom left hole 85

-11.5062

-11.5062 0.01 replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

replicate 0

1 0.8763 0.8763 0.8763 0.8763 0.0 0.0 1

unit 93

'15 x

15 fa in rack 4.05 array 4

-10.4775

-10.4775 0.0 cuboid 0

1 10.4775

-10.4775 10.4775

-10.4775 336.81 0.0 replicate 0

1 0.3937 0.3937 0.3937 0.3937 0.0 0.0 1

replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

replicate 0

1 0.635 0.635 0.635 0.635 0.0 0.0 1

'absorber slot top hole 80 0.0 11.5062 0.01

'absorber slot bottom hole 81 0.0

-11.5062 0.01

'absorber slot left hole 82

-11.5062 0.0 0.01

'absorber slot right hole 83 11.5062 0.0 0.01 Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation

'support top left hole 85

-11.5062

'support top right hole 85 11.5062

'support bottom right hole 85 11.5062

'support bottom left hole 85

-11.5062 replicate 8

1 0.3175 replicate 0

1 0.8763 11.5062 0.01 11.5062 0.01

-11.5062 0.01

-11.5062 0.01 0.3175 0.3175 0.3175 0.0 0.0 1

0.8763 0.8763 0.8763 0.0 0.0 1

unit 94

'15 x

15 fa in rack 3.95 array 5

-10.4775

-10.4775 0.0 cuboid 0

1 10.4775

-10.4775 10.4775

-10.4775 336.81 0.0 replicate 0

1 0.3937 0.3937 0.3937 0.3937 0.0 0.0 1

replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

replicate 0

1 0.635 0.635 0.635 0.635 0.0 0.0 1

'absorber slot top hole 80 0.0 11.5062 0.01

'absorber slot bottom hole 81 0.0

-11.5062 0.01

'absorber slot left hole 82

-11.5062 0.0 0.01

'absorber slot right hole 83 11.5062 0.0 0.01

'support top left hole 85

-11.5062 11.5062 0.01

'support top right hole 85 11.5062 11.5062 0.01

'support bottom right hole 85 11.5062

-11.5062 0.01

'support bottom left hole 85

-11.5062

-11.5062 0.01 replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

replicate 0

1 0.8763 0.8763 0.8763 0.8763 0.0 0.0 1

unit 95

'15 x

15 fa in rack 3.62 array 6

-10.4775

-10.4775 0.0 cuboid 0

1 10.4775

-10.4775 10.4775

-10.4775 336.81 0.0 replicate 0

1 0.3937 0.3937 0.3937 0.3937 0.0 0.0 1

replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

replicate 0

1 0.635 0.635 0.635 0.635 0.0 0.0 1

'absorber slot top hole 80 0.0 11.5062 0.01

'absorber slot bottom hole 81 0.0

-11.5062 0.01

'absorber slot left hole 82

-11.5062 0.0 0.01

'absorber slot right hole 83 11.5062 0.0 0.01

'support top left C-6 Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation hole 85

-11.5062 11.5062 0.01

'support top right hole 85 11.5062 11.5062 0.01

'support bottom right hole 85 11.5062

-11.5062 0.01

'support bottom left hole 85

-11.5062

-11.5062 0.01 replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

replicate 0

1 0.8763 0.8763 0.8763 0.8763 0.0 0.0 1

unit 96

'15 x

15 fa in rack 3.26 array 7

-10.4775

-10.4775 0.0 cuboid 0

1 10.4775

-10.4775 10.4775

-10.4775 336.81 0.0 replicate 0

1 0.3937 0.3937 0.3937 0.3937 0.0 0.0 1

replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

replicate 0

1 0.635 0.635 0.635 0.635 0.0 0.0 1

'absorber slot top hole 80 0.0 11.5062 0.01

'absorber slot bottom hole 81 0.0

-11.5062 0.01

'absorber slot left hole 82

-11.5062 0.0 0.01

'absorber slot right hole 83 11.5062 0.0 0.01

'support top left hole 85

-11.5062 11.5062 0.01

'support top right hole 85 11.5062 11.5062 0.01

'support bottom right hole 85 11.5062

-11.5062 0.01

'support bottom left hole 85

-11.5062

-11.5062 0.01 replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

replicate 0

1 0.8763 0.8763 0.8763 0.8763 0.0 0.0 1

unit 97

'15 x

15 fa in rack 3.05 array 8

-10.4775

-10.4775 0.0 cuboid 0

1 10.4775

-10.4775 10.4775

-10.4775 336.81 0.0 replicate 0

1 0.3937 0.3937 0.3937 0.3937 0.0 0.0 1

replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

replicate 0

1 0.635 0.635 0.635 0.635 0.0 0.0 1

'absorber slot top hole 80 0.0 11.5062 0.01

'absorber slot bottom hole 81 0.0

-11.5062 0.01

'absorber slot left hole 82

-11.5062 0.0 0.01

'absorber slot right hole 83 11.5062 0.0 0.01

'support top left hole 85

-11.5062 11.5062 0.01 C-7 Page

A ARE VA AREVA NP Inc.,

an AREVA and Siemens company 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation

'support top right hole 85 11.5062

'support bottom right hole 85 11.5062

'support bottom left hole 85

-11.5062 replicate 8

1 0.3175 replicate 0

1 0.8763 11.5062 0.01

-11.5062 0.01

-11.5062 0.01 0.3175 0.3175 0.3175 0.0 0.0 1

0.8763 0.8763 0.8763 0.0 0.0 1

unit 98

'15 x

15 fa in rack 2.43 array 9

-10.4775

-10.4775 0.0 cuboid 0

1 10.4775

-10.4775 10.4775

-10.4775 336.81 0.0 replicate 0

1 0.3937 0.3937 0.3937 0.3937 0.0 0.0 1

replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

replicate 0

1 0.635 0.635 0.635 0.635 0.0 0.0 1

'absorber slot top hole 80 0.0 11.5062 0.01

'absorber slot bottom hole 81 0.0

-11.5062 0.01

'absorber slot left hole 82

-11.5062 0.0 0.01

'absorber slot right hole 83 11.5062 0.0 0.01

'support top left hole 85

-11.5062 11.5062 0.01

'support top right hole 85 11.5062 11.5062 0.01

'support bottom right hole 85 11.5062

-11.5062 0.01

'support bottom left hole 85

-11.5062

-11.5062 0.01 replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

replicate 0

1 0.8763 0.8763 0.8763 0.8763 0.0 0.0 1

unit 99

'15 x

15 fa in rack 1.20 array 10

-10.4775

-10.4775 0.0 cuboid 0

1 10.4775

-10.4775 10.4775

-10.4775 336.81 0.0 replicate 0

1 0.3937 0.3937 0.3937 0.3937 0.0 0.0 1

replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

replicate 0

1 0.635 0.635 0.635 0.635 0.0 0.0 1

'absorber slot top hole 80 0.0 11.5062 0.01

'absorber slot bottom hole 81 0.0

-11.5062 0.01

'absorber slot left hole 82

-11.5062 0.0 0.01

'absorber slot right hole 83 11.5062 0.0 0.01

'support top left hole 85

-11.5062 11.5062 0.01

'support top right C-8 Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation hole 85 11.5062

'support bottom right hole 85 11.5062

'support bottom left hole 85

-11.5062 replicate 8

1 0.3175 replicate 0

1 0.8763 unit 100

'Empty Rack Cell 11.5062 0.01

-11.5062 0.01

-11.5062 0.01 0.3175 0.3175 0.3175 0.0 0.0 1

0.8763 0.8763 0.8763 0.0 0.0 1

cuboid 4

1 10.4775

-10.4775 10.4775

-10.4775 336.81 0.0 replicate 0

1 0.3937 0.3937 0.3937 0.3937 0.0 0.0 1

replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

replicate 0

1 0.635 0.635 0.635 0.635 0.0 0.0 1

'absorber slot top hole 80 0.0 11.5062 0.01

'absorber slot bottom hole 81 0.0

-11.5062 0.01

'absorber slot left hole 82

-11.5062 0.0 0.01

'absorber slot right hole 83 11.5062 0.0 0.01

'support top left hole 85

-11.5062 11.5062 0.01

'support top right hole 85 11.5062 11.5062 0.01

'support bottom right hole 85 11.5062

-11.5062 0.01

'support bottom left hole 85

-11.5062

-11.5062 0.01 replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

replicate 0

1 0.8763 0.8763 0.8763 0.8763 0.0 0.0 1

global unit 110

'rack cells array array 20 0.0 0.0 0.0 replicate 4

1 0.0 0.0 0.0 0.0 30.48 30.48 1

'replicate 4

1 30.48 30.48 30.48 30.48 0.0 0.0 1

end geom read array

'4.54 planar average fuel assembly ara=l nux=15 nuy=15 nuz=1 fill 1

1 1

1 71 1

1 1

71 1

1 1

72 1

1 1

73 1

1 1

C-9 Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company Palisades SFP Region 1 Criticality Evaluation 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY 1

1 1

1 60 1

1 1

72 1

1 1

73 1

1 1

70 1

1 1

70 1

1 1

1 end f il l

'fuel a ssembly 4.34 ara=2 nux= 15 nuy=1 5 nu z=1 fill 2

2 2

2 71 2

2 2

71 2

2 2

72 2

2 2

73 2

2 2

60 2

2 2

72 2

2 2

73 2

2 2

70 2

2 2

70 2

2 2

2 end fi ll

'fuel assembly

4. 19 ara=3 nux=1 5 nuy=15 nuz=l fill 3

3 3

3 72 3

3 3

72 3

3 3

70 3

3 3

71 3

3 3

60 3

3 3

70 3

3 3

71 3

3 3

73 3

3 3

73 3

3 3

3 end fi ll

'fuel assembly 4.05 ara=4 nux=15 nuy=15 nuz=l C-10 Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company Palisades SFP Region 1 Criticality Evaluation 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY fill 4

4 4

4 70 4

4 4

70 4

4 4

73 4

4 4

72 4

4 4

60 4

4 4

73 4

4 4

72 4

4 4

71 4

4 4

71 4

4 4

4 end fill

'fuel assembly

3. 95 ara=5 nux =1 5 nuy=1 5 nuz=1 fill 5

5 5

5 73 5

5 5

73 5

5 5

71 5

5 5

70 5

5 5

60 5

5 5

71 5

5 5

70 5

5 5

72 5

5 5

72 5

5 5

5 end fi ll

'fuel assembly 3.62 ara=6 nux=15 nuy=15 nuz=1 fill 6

6 6

6 73 6

6 6

73 6

6 6

71 6

6 6

70 6

6 6

60 6

6 6

71 6

6 6

70 6

6 6

C-11 Page

A 20004-015 (09/30/2008)

A R E VA Document No.: ANP-2779NP-001 AREVA NP Inc.,

an AREVA and Siemens company NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation 6

6 6

6 72 6

6 6

72 6

6 6

6 end fill

'fuel assembly 3.26 ara=7 nux= 15 nuy=1 5 nuz= l fill 7

7 7

7 73 7

7 7

73 7

7 7

71 7

7 7

70 7

7 7

60 7

7 7

71 7

7 7

70 7

7 7

72 7

7 7

72 7

7 7

7 end fi ll

'fuel assembly 3.05 ara=8 nux=15 nuy=15 nuz=l fill 8

8 8

8 73 8

8 8

73 8

8 8

71 8

8 8

70 8

8 8

60 8

8 8

71 8

8 8

70 8

8 8

72 8

8 8

72 8

8 8

8 end fill

'fuel assembly 2.43 ara=9 nux=15 nuy=15 nuz=1 fill 9

9 9

9 73 9

9 9

73 9

9 9

71 9

9 9

70 C-12 Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company Palisades SFP Region 1 Criticality Evaluation 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY 9

9 9

60 9

9 9

71 9

9 9

70 9

9 9

72 9

9 9

72 9

9 9

9 end fi ll

'fuel assemb ly 1.20 ara=10 nux=1 5 nuy=15 nuz=1 fill 10 10 10 10 73 10 10 10 10 10 73 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 71 10 10 10 10 10 10 10 10 10 10 10 10 10 70 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 60 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 71 10 10 10 10 10 10 10 10 10 10 10 10 10 70 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 72 10 10 10 10 10 72 10 10 10 10 end fi ll

'fuel assembly rack array ara=20 nux=8 nuy=8 nuz=1 fill 100 90 100 90 100 90 100 90 90 100 90 100 90 100 90 100 100 90 100 90 100 90 100 90 90 100 90 100 90 100 90 100 100 90 100 90 100 90 100 90 90 100 90 100 90 100 90 100 100 90 100 90 100 90 100 90 90 100 90 100 90 100 90 100 end fill end array read bounds xyf=periodic

+zb=h2o

-zb=h2o

'read bounds xyf=h2o

+zb=h2o

-zb=h2o end bounds read plot ttl='x-y slice top right cell C-13 Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation xul=-0.1 yul=54.0 zul=168 xlr=54.0 ylr=-0.1 zlr=168 uax=l vdn=-l nax=260 end ttl='x-y slice 4

cells' xul=-54 yul=54.0 zul=168 xir=54.0 ylr=-54 zlr=168 uax=l vdn=-l nax=260 end ttl='x-z slice xul=-101 yul=10.82 zul=368.0 xlr=54 ylr=10.82 zlr=-33 uax=1 wdn=-1 nax=260 end end plot end data end C.2 Rack E Base Model KENO-V.a Input Deck The input deck for Region 1 E is provided below.

It is a 5x 10 cell model at 0 ppm.

=csas25 parm=size=400000 Palisades,mark CE 15x15 fa,assy, carbon

absorber, E

rack 44groupndf5 latticecell uo2 1

0.96 293 92235 4.54 92238 95.46 end

'm5 modeled as pure Zirc zr 2

1.0 293 end h2o 3

1.0 293 end h2o 4

1.0 293 end zr 5

1.0 293 end

'carbon remaining in absorber w only C density c

6 den=

0.2720 1.0 293 end he 7

1.0 293 end ss304 8

1.0 293 end h2o 9

1.0 293 end uo2 10 0.96 293 92235 4.34 92238 95.66 end uo2 11 0.96 293 92235 4.19 92238 95.81 end uo2 12 0.96 293 92235 4.05 92238 95.95 end uo2 13 0.96 293 92235 3.95 92238 96.05 end uo2 14 0.96 293 92235 3.62 92238 96.38 end uo2 15 0.96 293 92235 3.26 92238 96.74 end uo2 16 0.96 293 92235 3.05 92238 96.95 end uo2 17 0.96 293 92235 2.43 92238 97.57 end uo2 18 0.96 293 92235 1.20 92238 98.80 end end comp squarepitch 1.3970 0.9144 1

3 1.0592 2

0.9322 7

end more data res=10 cylinder 0.4572 dan(10)=0.23801701 res=ll cylinder 0.4572 dan(11)=0.23801701 res=12 cylinder 0.4572 dan(12)=0.23801701 res=13 cylinder 0.4572 dan(13)=0.23801701 res=14 cylinder 0.4572 dan(14)=0.23801701 C-14 Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation res=15 cylinder 0.4572 dan(15)=0.23801701 res=16 cylinder 0.4572 dan(16)=0.23801701 res=17 cylinder 0.4572 dan(17)=0.23801701 res=18 cylinder 0.4572 dan(18)=0.23801701 end more data Palisades 15x15 read parm tme=100 gen=1075 nsk=75 run=yes plt=no npg=3000

'read parm tme=300 gen=5075 nsk=75 run=yes plt=yes npg=10000 nub=yes end parm read geom unit 1

'fuel pin cylinder cylinder cylinder cuboid 4.54 wt%

0.4572 336.81 0.C 0.4661 336.81 0.C 0.5296 336.81 0.0 4pO.6985 336.81 0.0 cell 1

1 7

1 2

1 3

1 unit 2

'fuel pin cell 4.34 wt%

cylinder 10 1

0.4572 336.81 0.0 cylinder 7

1 0.4661 336.81 0.0 cylinder 2

1 0.5296 336.81 0.0 cuboid 3

1 4pO.6985 336.81 0.0 unit 3

'fuel pin cylinder cylinder cylinder cuboid 4.19 wt%

0.4572 336.81 0.0 0.4661 336.81 0.0 0.5296 336.81 0.0 4p0.6985 336.81 0.0 cell 11 1

7 1

2 1

3 1

unit 4

'fuel pin cell 4.05 wt%

cylinder 12 1

0.4572 336.81 0.0 cylinder 7

1 0.4661 336.81 0.0 cylinder 2

1 0.5296 336.81 0.0 cuboid 3

1 4pO.6985 336.81 0.0 unit 5

'fuel pin cylinder cylinder cylinder cuboid 3.95 wti 0.4572 336.81 0.0 0.4661 336.81 0.0 0.5296 336.81 0.0 4pO.6985 336.81 0.0 cell 13 1

7 1

2 1

3 1

unit 6

'fuel pin cell 3.62 wta cylinder 14 1

0.4572 336.81 0.0 cylinder 7

1 0.4661 336.81 0.0 cylinder 2

1 0.5296 336.81 0.0 cuboid 3

1 4p0.6985 336.81 0.0 C-15 Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company Palisades SFP Region 1 Criticality Evaluation 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY unit 7

'fuel pin cylinder cylinder cylinder cuboid cell 15 1

7 1

2 1

3 1

3.26 wt%

0.4572 336.81 0.0 0.4661 336.81 0.0 0.5296 336.81 0.0 4pO.6985 336.81 0.0 unit 8

'fuel pin cell 3.05 wt%

cylinder 16 1

0.4572 336.81 0.0 cylinder 7

1 0.4661 336.81 0.0 cylinder 2

1 0.5296 336.81 0.0 cuboid 3

1 4pO.6985 336.81 0.0 unit 9

'fuel pin cylinder cylinder cylinder cuboid cell 17 1

7 1

2 1

3 1

2.43 wt%

0.4572 336.81 0.C 0.4661 336.81 0.0 0.5296 336.81 0.0 4pO.6985 336.81 0.0 unit 10

'fuel pin cell 1.20 wt%

cylinder 18 1

0.4572 336.81 0.0 cylinder 7

1 0.4661 336.81 0.0 cylinder 2

1 0.5296 336.81 0.0 cuboid 3

1 4pO.6985 336.81 0.0 unit 60

'instrument tube cell cylinder 4

1 0.4661 336.81 0.0 cylinder 5

1 0.5296 336.81 0.0 cuboid 4

1 4pO.6985 336.81 0.0 unit 70

'Tie Bar Top cuboid 2

1 2pO.4757 0.6985

-0.37715 336.81 0.0 cuboid 4

1 4pO.6985 336.81 0.0 unit 71

'Tie Bar Bottom cuboid 2

1 2pO.4757 cuboid 4

1 4pO.6985 0.37715

-0.6985 336.81 0.0 336.81 0.0 unit 72

'Tie Bar Left cuboid 2

1 0.37715

-0.6985 2pO.4757 336.81 0.0 cuboid 4

1 4pO.6985 336.81 0.0 unit 73

'Tie Bar Right cuboid 2

1 0.6985

-0.37715 2pO.4757 336.81 0.0 cuboid 4

1 4pO.6985 336.81 0.0 Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation unit 80

'Absorber slot Horizontal

(+X)

Top cuboid 6

1 2plO.49 2pO.2667 336.79 0.0 replicate 0

1 0.00 0.00 0.0507 0.0507 0.0 0.0 1

unit 81

'Absorber slot Horizontal

(+X)

Bottom cuboid 6

1 2p10.49 2pO.2667 336.79 0.0 replicate 0

1 0.00 0.00 0.0507 0.0507 0.0 0.0 1

unit 82

'Absorber slot Horizontal

(+Y)

Left cuboid 6

1 2pO.2667 2plO.49 336.79 0.0 replicate 0

1 0.0507 0.0507 0.00 0.00 0.0 0.0 1

unit 83

'Absorber slot Horizontal

(+Y)

Left cuboid 6

1 2pO.2667 2p10.49 336.79 0.0 replicate 0

1 0.0507 0.0507 0.00 0.00 0.0 0.0 1

unit 85

'Space Cylinder cylinder 8

1 0.3174 336.79 0.0 cuboid 0

1 0.3174

-0.3174 0.3174

-0.3174 336.79 0.0 unit 90

'15 x

15 fa in rack 4.54 Planar Average array 1

-10.4775

-10.4775 0.0 cuboid 4

1 10.4775

-10.4775 10.4775

-10.4775 336.81 0.0

'replicate 4

1 0.9525 0.9525 0.9525 0.9525 0.0 0.0 1

replicate 4

1 0.5588 0.5588 0.5588 0.5588 0.0 0.0 1

replicate 0

1 0.3937 0.3937 0.3937 0.3937 0.0 0.0 1

replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

replicate 0

1 0.635 0.635 0.635 0.635 0.0 0.0 1

'absorber slot top hole 80 0.0 12.065 0.01

'absorber slot bottom hole 81 0.0

-12.065 0.01

'absorber slot left hole 82

-12.065 0.0 0.01

'absorber slot right hole 83 12.065 0.0 0.01

'support top left

+x hole 85

-11.1252 12.065 0.01

'support top right

-x hole 85 11.1252 12.065 0.01

'support bottom right

-x hole 85 11.1252

-12.065 0.01

'support bottom left

+

x hole 85

-11.1252

-12.065 0.01

'support top left

-y hole 85

-12.065 11.1252 0.01 C-17 Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation

'support top right

-y hole 85 12.065 11.1252 0.01

'support bottom right

+y hole 85 12.065

-11.1252 0.01

'support bottom left

+y hole 85

-12.065

-11.1252 0.01 replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

'replicate 4

1 1.5875 1.5875 0.8763 0.8763 0.0 0.0 1

replicate 0

1 0.8763 0.8763 0.8763 0.8763 0.0 0.0 1

replicate 4

1 0.7112 0.7112 0.0 0.0 0.0 0.0 1

unit 91

'15 x

15 fa in rack 4.34 planar average array 2

-10.4775

-10.4775 0.0 cuboid 4

1 10.4775

-10.4775 10.4775

-10.4775 336.81 0.0

'replicate 4

1 0.9525 0.9525 0.9525 0.9525 0.0 0.0 1

replicate 4

1 0.5588 0.5588 0.5588 0.5588 0.0 0.0 1

replicate 0

1 0.3937 0.3937 0.3937 0.3937 0.0 0.0 1

replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

replicate 0

1 0.635 0.635 0.635 0.635 0.0 0.0 1

'absorber slot top hole 80 0.0 12.065 0.01

'absorber slot bottom hole 81 0.0

-12.065 0.01

'absorber slot left hole 82

-12.065 0.0 0.01

'absorber slot right hole 83 12.065 0.0 0.01

'support top left

+x hole 85

-11.1252 12.065 0.01

'support top right

-x hole 85 11.1252 12.065 0.01

'support bottom right

-x hole 85 11.1252

-12.065 0.01

'support bottom left

+

x hole 85

-11.1252

-12.065 0.01

'support top left

-y hole 85

-12.065 11.1252 0.01

'support top right

-y hole 85 12.065 11.1252 0.01

'support bottom right

+y hole 85 12.065

-11.1252 0.01

'support bottom left

+y hole 85

-12.065

-11.1252 0.01 replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

'replicate 4

1 1.5875 1.5875 0.8763 0.8763 0.0 0.0 1

replicate 0

1 0.8763 0.8763 0.8763 0.8763 0.0 0.0 1

replicate 4

1 0.7112 0.7112 0.0 0.0 0.0 0.0 1

unit 92

'15 x

15 fa in rack 4.19 array 3

-10.4775

-10.4775 0.0 cuboid 4

1 10.4775

-10.4775 10.4775

-10.4775 336.81 0.0 C-18 Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company Palisades SFP Region 1 Criticality Evaluation 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY

'replicate 4

1 0.9525 0.9525 0.9525 0.9525 0.0 0.0 1

replicate 4

1 0.5588 0.5588 0.5588 0.5588 0.0 0.0 1

replicate 0

1 0.3937 0.3937 0.3937 0.3937 0.0 0.0 1

replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

replicate 0

1 0.635 0.635 0.635 0.635 0.0 0.0 1

'absorber slot top hole 80 0.0 12.065 0.01

'absorber slot bottom hole 81 0.0

-12.065 0.01

'absorber slot left hole 82

-12.065 0.0 0.01

'absorber slot right hole 83 12.065 0.0 0.01

'support top left

+x hole 85

-11.1252 12.065 0.01

'support top right

-x hole 85 11.1252 12.065 0.01

'support bottom right

-x hole 85 11.1252

-12.065 0.01

'support bottom left

+

x hole 85

-11.1252

-12.065 0.01

'support top left

-y hole 85

-12.065 11.1252 0.01

'support top right

-y hole 85 12.065 11.1252 0.01

'support bottom right

+y hole 85 12.065

-11.1252 0.01

'support bottom left

+y hole 85

-12.065

-11.1252 0.01 replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

'replicate 4

1 1.5875 1.5875 0.8763 0.8763 0.0 0.0 1

replicate 0

1 0.8763 0.8763 0.8763 0.8763 0.0 0.0 1

replicate 4

1 0.7112 0.7112 0.0 0.0 0.0 0.0 1

unit 93

'15 x

15 fa in rack 4.05 array 4

-10.4775

-10.4775 0.0 cuboid 4

1 10.4775

-10.4775 10.4775

-10.4775 336.81 0.0

'replicate 4

1 0.9525 0.9525 0.9525 0.9525 0.0 0.0 1

replicate 4

1 0.5588 0.5588 0.5588 0.5588 0.0 0.0 1

replicate 0

1 0.3937 0.3937 0.3937 0.3937 0.0 0.0 1

replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

replicate 0

1 0.635 0.635 0.635 0.635 0.0 0.0 1

'absorber slot top hole 80 0.0 12.065 0.01

'absorber slot bottom hole 81 0.0

-12.065 0.01

'absorber slot left hole 82

-12.065 0.0 0.01

'absorber slot right hole 83 12.065 0.0 0.01

'support top left

+x hole 85

-11.1252 12.065 0.01 C-19 Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation

'support top right

-x hole 85 11.1252 12.065 0.01

'support bottom right

-x hole 85 11.1252

-12.065 0.01

'support bottom left

+

x hole 85

-11.1252

-12.065 0.01

'support top left

-y hole 85

-12.065 11.1252 0.01

'support top right

-y hole 85 12.065 11.1252 0.01

'support bottom right

+y hole 85 12.065

- 11.1252 0.01

'support bottom left

+y hole 85

-12.065

- 11.1252 0.01 replicate 8

1 0.3175 0.3175 0.31 75 0.3175 0.0 0.0 1

'replicat e 4

1 1.5875 1.5875 0.8763 0.8763 0.0 0.0 1

replicate 0

1 0.8763 0.8763 0.8763 0.8763 0.0 0.0 1

replicate 4

1 0.7112 0.7112 0.0 0.0 0.0 0.0 1

unit 94

'15 x

15 fa in rack 3.95 array 5

-10.4775

-10.4775 0.0 cuboid 4

1 10.47 75

-10.4775 10.4775

- 10.4775 336.81 0.0

'replicate 4

1 0.952 5 0.9525 0.9525 0.952 5 0.0 0.0 1

replicate 4

1 0.5588 0.5588 0.5588 0.5588 0.0 0.0 1

replicate 0

1 0.3937 0.3937 0.3937 0.3937 0.0 0.0 1

replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

replicate 0

1 0.635 0.635 0.635 0.635 0.0 0.0 1

'absorber slot top hole 80 0.0 12.065 0.01

'absorber slot bottom hole 81 0.0

-12.065 0.01

'absorber slot left hole 82

-12.065 0.0 0.01

'absorber slot right hole 83 12.065 0.0 0.01

'support top left

+x hole 85

-11.1252 12.065 0.01

'support top right

-x hole 85 11.1252 12.065 0.01

'support bottom right

-x hole 85 11.1252

-12.065 0.01

'support bottom left

+

x hole 85

-11.1252

-12.065 0.01

'support top left

-y hole 85

-12.065 11.1252 0.01

'support top right

-y hole 85 12.065 11.1252 0.01

'support bottom right

+y hole 85 12.065

- 11.1252 0.01

'support bottom left

+y hole 85

-12.065

- 11.1252 0.01 replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

C-20 Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation

'replicate 4

1 1.5875 1.5875 0.8763 0.8763 0.0 0.0 1

replicate 0

1 0.8763 0.8763 0.8763 0.8763 0.0 0.0 1

replicate 4

1 0.7112 0.7112 0.0 0.0 0.0 0.0 1

unit 95

'15 x

15 fa in rack 3.62 array 6

-10.4775

-10.4775 0.0 cuboid 4

1 10.4775

-10.4775 10.4775

-10.4775 336.81 0.0

'replicate 4

1 0.9525 0.9525 0.9525 0.9525 0.0 0.0 1

replicate 4

1 0.5588 0.5588 0.5588 0.5588 0.0 0.0 1

replicate 0

1 0.3937 0.3937 0.3937 0.3937 0.0 0.0 1

replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

replicate 0

1 0.635 0.635 0.635 0.635 0.0 0.0 1

'absorber slot top hole 80 0.0 12.065 0.01

'absorber slot bottom hole 81 0.0

-12.065 0.01

'absorber slot left hole 82

-12.065 0.0 0.01

'absorber slot right hole 83 12.065 0.0 0.01

'support top left

+x hole 85

-11.1252 12.065 0.01

'support top right

-x hole 85 11.1252 12.065 0.01

'support bottom right

-x hole 85 11.1252

-12.065 0.01

'support bottom left

+

x hole 85

-11.1252

-12.065 0.01

'support top left

-y hole 85

-12.065 11.1252 0.01

'support top right

-y hole 85 12.065 11.1252 0.01

'support bottom right

+y hole 85 12.065

-11.1252 0.01

'support bottom left

+y hole 85

-12.065

-11.1252 0.01 replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

'replicate 4

1 1.5875 1.5875 0.8763 0.8763 0.0 0.0 1

replicate 0

1 0.8763 0.8763 0.8763 0.8763 0.0 0.0 1

replicate 4

1 0.7112 0.7112 0.0 0.0 0.0 0.0 1

unit 96

'15 x

15 fa in rack 3.26 array 7

-10.4775

-10.4775 0.0 cuboid 4

1 10.4775

-10.4775 10.4775

-10.4775 336.81 0.0

'replicate 4

1 0.9525 0.9525 0.9525 0.9525 0.0 0.0 1

replicate 4

1 0.5588 0.5588 0.5588 0.5588 0.0 0.0 1

replicate 0

1 0.3937 0.3937 0.3937 0.3937 0.0 0.0 1

replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

replicate 0

1 0.635 0.635 0.635 0.635 0.0 0.0 1

'absorber slot top hole 80 0.0 12.065 0.01 C-21 Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation

'absorber slot bottom hole 81 0.0

-12.065 0.01

'absorber slot left hole 82

-12.065 0.0 0.01

'absorber slot right hole 83 12.065 0.0 0.01

'support top left

+x hole 85

-11.1252 12.065 0.01

'support top right

-x hole 85 11.1252 12.065 0.01

'support bottom right

-x hole 85 11.1252

-12.065 0.01

'support bottom left

+

x hole 85

-11.1252

-12.065 0.01

'support top left

-y hole 85

-12.065 11.1252 0.01

'support top right

-y hole 85 12.065 11.1252 0.01

'support bottom right

+y hole 85 12.065

-11.1252 0.01

'support bottom left

+y hole 85

-12.065

-11.1252 0.01 replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

'replicat e 4

1 1.5875 1.5875 0.8763 0.8763 0.0 0.0 1

replicate 0

1 0.8763 0.8763 0.8763 0.8763 0.0 0.0 1

replicate 4

1 0.7112 0.7112 0.0 0.0 0.0 0.0 1

unit 97

'15 x

15 fa in rack 3.05 array 8

-10.4775

-10.4775 0.0 cuboid 4

1 10.4775

-10.4775 10.4775

-10.4775 336.81 0.0

'replicate 4

1 0.9525 0.9525 0.9525 0.9525 0.0 0.0 1

replicate 4

1 0.5588 0.5588 0.5588 0.5588 0.0 0.0 1

replicate 0

1 0.3937 0.3937 0.3937 0.3937 0.0 0.0 1

replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

replicate 0

1 0.635 0.635 0.635 0.635 0.0 0.0 1

'absorber slot top hole 80 0.0 12.065 0.01

'absorber slot bottom hole 81 0.0

-12.065 0.01

'absorber slot left hole 82

-12.065 0.0 0.01

'absorber slot right hole 83 12.065 0.0 0.01

'support top left

+x hole 85

-11.1252 12.065 0.01

'support top right

-x hole 85 11.1252 12.065 0.01

'support bottom right

-x hole 85 11.1252

-12.065 0.01

'support bottom left

+

x hole 85

-11.1252

-12.065 0.01

'support top left

-y C-22 Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company Palisades SFP Region 1 Criticality Evaluation 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY hole 85

-12.065 11.1252 0.01

'support top right

-y hole 85 12.065 11.1252 0.01

'support bottom right

+y hole 85 12.065

-11.1252 0.01

'support bottom left

+y hole 85

-12.065

-11.1252 0.01 replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

'replicate 4

1 1.5875 1.5875 0.8763 0.8763 0.0 0.0 1

replicate 0

1 0.8763 0.8763 0.8763 0.8763 0.0 0.0 1

replicate 4

1 0.7112 0.7112 0.0 0.0 0.0 0.0 1

unit 98

'15 x

15 fa in rack 2.43 array 9

-10.4775

-10.4775 0.0 cuboid 4

1 10.4775

-10.4775 10.4775

-10.4775 336.81 0.0

'replicate 4

1 0.9525 0.9525 0.9525 0.9525 0.0 0.0 1

replicate 4

1 0.5588 0.5588 0.5588 0.5588 0.0 0.0 1

replicate 0

1 0.3937 0.3937 0.3937 0.3937 0.0 0.0 1

replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

replicate 0

1 0.635 0.635 0.635 0.635 0.0 0.0 1

'absorber slot top hole 80 0.0 12.065 0.01

'absorber slot bottom hole 81 0.0

-12.065 0.01

'absorber slot left hole 82

-12.065 0.0 0.01

'absorber slot right hole 83 12.065 0.0 0.01

'support top left

+x hole 85

-11.1252 12.065 0.01

'support top right

-x hole 85 11.1252 12.065 0.01

'support bottom right

-x hole 85 11.1252

-12.065 0.01

'support bottom left

+

x hole 85

-11.1252

-12.065 0.01

'support top left

-y hole 85

-12.065 11.1252 0.01

'support top right

-y hole 85 12.065 11.1252 0.01

'support bottom right

+y hole 85 12.065

-11.1252 0.01

'support bottom left

+y hole 85

-12.065

-11.1252 0.01 replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

'replicate 4

1 1.5875 1.5875 0.8763 0.8763 0.0 0.0 1

replicate 0

1 0.8763 0.8763 0.8763 0.8763 0.0 0.0 1

replicate 4

1 0.7112 0.7112 0.0 0.0 0.0 0.0 1

unit 99

'15 x

15 fa in rack 1.20 array 10

-10.4775

-10.4775 0.0 C-23 Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company Palisades SFP Region 1 Criticality Evaluation 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY cuboid 4

1 10.4775

-10.4775 10.4775

-10.4775 336.81 0.0

'replicate 4

1 0.9525 0.9525 0.9525 0.9525 0.0 0.0 1

replicate 4

1 0.5588 0.5588 0.5588 0.5588 0.0 0.0 1

replicate 0

1 0.3937 0.3937 0.3937 0.3937 0.0 0.0 1

replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

replicate 0

1 0.635 0.635 0.635 0.635 0.0 0.0 1

'absorber slot top hole 80 0.0 12.065 0.01

'absorber slot bottom hole 81 0.0

-12.065 0.01

'absorber slot left hole 82

-12.065 0.0 0.01

'absorber slot right hole 83 12.065 0.0 0.01

'support top left

+x hole 85

-11.1252 12.065 0.01

'support top right

-x hole 85 11.1252 12.065 0.01

'support bottom right

-x hole 85 11.1252

-12.065 0.01

'support bottom left

+

x hole 85

-11.1252

-12.065 0.01

'support top left

-y hole 85

-12.065 11.1252 0.01

'support top right

-y hole 85 12.065 11.1252 0.01

'support bottom right

+y hole 85 12.065

-11.1252 0.01

'support bottom left

+y hole 85

-12.065

-11.1252 0.01 replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

'replicate 4

1 1.5875 1.5875 0.8763 0.8763 0.0 0.0 1

replicate 0

1 0.8763 0.8763 0.8763 0.8763 0.0 0.0 1

replicate 4

1 0.7112 0.7112 0.0 0.0 0.0 0.0 1

unit 100

'Empty Rack Cell cuboid 4

1 10.4775

-10.4775 10.4775

-10.4775 336.81 0.0

'replicate 4

1 0.9525 0.9525 0.9525 0.9525 0.0 0.0 1

replicate 4

1 0.5588 0.5588 0.5588 0.5588 0.0 0.0 1

replicate 0

1 0.3937 0.3937 0.3937 0.3937 0.0 0.0 1

replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

replicate 0

1 0.635 0.635 0.635 0.635 0.0 0.0 1

'absorber slot top hole 80 0.0 12.065 0.01

'absorber slot bottom hole 81 0.0

-12.065 0.01

'absorber slot left hole 82

-12.065 0.0 0.01

'absorber slot right hole 83 12.065 0.0 0.01

'support top left

+x hole 85

-11.1252 12.065 0.01 C-24 Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation

'support top right

-x hole 85 11.1252 12.065 0.01

'support bottom right

-x hole 85 11.1252

-12.065 0.01

'support bottom left

+

x hole 85

-11.1252

-12.065 0.01

'support top left

-y hole 85

-12.065 11.1252 0.01

'support top right

-y hole 85 12.065 11.1252 0.01

'support bottom right

+y hole 85 12.065

-11.1252 0.01

'support bottom left

+y hole 85

-12.065

-11.1252 0.01 replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

'replicate 4

1 1.5875 1.5875 0.8763 0.8763 0.0 0.0 1

replicate 0

1 0.8763 0.8763 0.8763 0.8763 0.0 0.0 1

replicate 4

1 0.7112 0.7112 0.0 0.0 0.0 0.0 1

global unit 210

'rack cells array array 20 0.0 0.0 0.0 replicate 4

1 0.0 0.0 0.0 0.0 30.48 30.48 1

'replicate 4

1 0.0 0.0 30.48 30.48 0.0 0.0 1

replicate 4

1 30.48 30.48 30.48 30.48 0.0 0.0 1

end geom read array

'4.54 planar average fuel assembly ara=l nux= 15 nuy=15 nuz= 1 fill 1

1 1

1 71 1

1 1

71 1

1 1

72 1

1 1

73 1

1 1

60 1

1 1

72 1

1 1

73 1

1 1

70 1

1 1

70 1

1 1

1 end fi ll

'fuel assembly 4.34 ara=2 nux=15 nuy=15 nuz=l C-25 Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation fill 2

2 2

2 71 2

2 2

71 2

2 2

72 2

2 2

73 2

2 2

60 2

2 2

72 2

2 2

73 2

2 2

70 2

2 2

70 2

2 2

2 end fill

'fuel assembly

4. 19 ara=3 nux= 15 nuy=1 5 nuz=1 fill 3

3 3

3 72 3

3 3

72 3

3 3

70 3

3 3

71 3

3 3

60 3

3 3

70 3

3 3

71 3

3 3

73 3

3 3

73 3

3 3

3 end fi ll

'fuel assembly 4.05 ara=4 nux =15 nuy=15 nuz=1 fill 4

4 4

4 70 4

4 4

70 4

4 4

73 4

4 4

72 4

4 4

60 4

4 4

73 4

4 4

72 4

4 4

Page

A 20004-015 (09/30/2008)

A R E VA Document No.: ANP-2779NP-001 AREVA NP Inc.,

an AREVA and Siemens company NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation 4

4 4

4 71 4

4 4

71 4

4 4

4 end f ill

'fuel ass embly 3.95 ara=5 nu x= l5 nu y=l 5 nu z= l fill 5

5 5

5 73 5

5 5

73 5

5 5

71 5

5 5

70 5

5 5

60 5

5 5

71 5

5 5

70 5

5 5

72 5

5 5

72 5

5 5

5 end fi ll

'fuel assembly 3.62 ara=6 nux=15 nuy=l 5 nuz=1 fill 6

6 6

6 73 6

6 6

73 6

6 6

71 6

6 6

70 6

6 6

60 6

6 6

71 6

6 6

70 6

6 6

72 6

6 6

72 6

6 6

6 end fi ll

'fuel asse mb ly

3. 26 ara=7 nux =1 5 n uy=15 nuz =l fill 7

7 7

7 73 7

7 7

73 7

7 7

71 7

7 7

70 C-27 Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company Palisades SFP Region 1 Criticality Evaluation 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY 7

7 7

60 7

7 7

71 7

7 7

70 7

7 7

72 7

7 7

72 7

7 7

7 end f il l

'fuel assembly 3.05 ara=8 nux= 15 nuy=1 5 nu z= l fill 8

8 8

8 73 8

8 8

73 8

8 8

71 8

8 8

70 8

8 8

60 8

8 8

71 8

8 8

70 8

8 8

72 8

8 8

72 8

8 8

8 end fi ll

'fuel assemb ly

2. 43 ara=9 nux=1 5 nuy=15 nuz=l fill 9

9 9

9 73 9

9 9

73 9

9 9

71 9

9 9

70 9

9 9

60 9

9 9

71 9

9 9

70 9

9 9

72 9

9 9

72 9

9 9

9 end fi ll

'fuel assembly 1.20 C-28 Page

A ARE VA AREVA NP Inc.,

an AREVA and Siemens company 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation ara=10 nux=15 nuy=15 nuz=l fill 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 71 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 71 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 end fill 73 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 72 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 60 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 73 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 70 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 70 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 72 10 10 10 10

'fuel assembly rack array ara=20 nux=10 nuy=5 nuz=1 fill 97 97 97 97 97 97 97 97 97 97 100 97 100 97 100 97 100 97 100 97 97 100 97 100 97 100 97 100 97 100 100 97 100 97 100 97 100 97 100 97 96 97 97 97 97 97 97 97 97 97 end fill end array

'read bounds xyf=periodic

+zb=h2o

-zb=h2o

'read bounds xfc=periodic yfc=h2o

+zb=h2o

-zb=h2o read bounds xyf=h2o

+zb=h2o

-zb=h2o end bounds read plot ttl='x-y slice top right cell xul=-0.l yul=54.0 zul=168 xlr=54.0 ylr=-0.l zlr=168 uax=l vdn=-l nax=260 end ttl='x-y slice 4

cells' xul=-54 yul=54.0 zul=168 xlr=54.0 ylr=-54 zlr=168 uax=1 vdn=-1 nax=260 end ttl='x-z slice xul=-101 yul=10.82 zul=368.0 xlr=54 ylr=10.82 zlr=-33 uax=l wdn=-l nax=260 end end plot end data end C-29 Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation C.3 Region 2 Base Model KENO-V.a Input Deck The input deck for Region 2 is provided below.

This deck is for the Region 2 model for the Region 1A to Region 2 interface calculations.

It is a 10x11 cell model at 850 ppm.

=csas25 parm=size=400000 4.95wto max mark CE 15x15 fa,assy

'Palisades rack base case,carbon absorber,large cutouts offset 44groupndf5 latticecell uo2 1

0.96 293 92235 4.54 92238 95.46 end

'm5 modeled as pure Zirc zr 2

1.0 293 end h2o 3

1.0 293 end arbm-bormod 1.0 1

1 0

0 5000 100 3

850.0e-6 293 end h2o 4

1.0 293 end arbm-bormod 1.0 1

1 0

0 5000 100 4

850.0e-6 293 end zr 5

1.0 293 end

'carbon remaining in absorber w only C

density c

6 den=

0.2720 1.0 293 end he 7

1.0 293 end ss304 8

1.0 293 end h2o 9

1.0 293 end arbm-bormod 1.0 1

1 0

0 5000 100 9

850.0e-6 293 end uo2 10 0.96 293 92235 1.14 92238 98.86 end uo2 11 0.96 293 92235 3.23 92238 96.77 end uo2 12 0.96 293 92235 4.13 92238 95.87 end uo2 13 0.96 293 92235 4.95 92238 95.05 end end comp squarepitch 1.3970 0.9144 1

3 1.0592 2

0.9322 7

end more data res=10 cylinder 0.4572 dan(10)=0.23801701 res=11 cylinder 0.4572 dan(il)=0.23801701 res=12 cylinder 0.4572 dan(12)=0.23801701 res=l3 cylinder 0.4572 dan(13)=0.23801701 end more data Palisades 15x15 Xl Batch Assembly read parm tme=100 gen=2075 nsk=75 run=yes plt=no npg=5000 nub=yes end parm read geom unit 1

'fuel pin cell cylinder 1

1 cylinder 7

1 cylinder 2

1 cuboid 3

1 nar average wtl 336.81 0.0 336.81 0.0 336.81 0.0 336.81 0.0 4.54 pla 0.4572 0.4661 0.5296 4pO.6985 unit 2

'fuel pin cell 1.14 wt%

cylinder 10 1

0.4572 336.81 0.0 C-30 Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company Palisades SFP Region 1 Criticality Evaluation 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY cylinder 7

1 0.4661 336.81 0.0 cylinder 2

1 0.5296 336.81 0.0 cuboid 3

1 4pO.6985 336.81 0.0 unit 3

'fuel pin cell 3.23 wt%

cylinder 11 1

0.4572 336.81 0.0 cylinder 7

1 0.4661 336.81 0.0 cylinder 2

1 0.5296 336.81 0.0 cuboid 3

1 4pO.6985 336.81 0.0 unit 4

'fuel pin cell 4.13 wto cylinder 12 1

0.4572 336.81 0.0 cylinder 7

1 0.4661 336.81 0.0 cylinder 2

1 0.5296 336.81 0.0 cuboid 3

1 4pO.6985 336.81 0.0 unit 5

'fuel pin cell 4.95 Planar Average cylinder 13 1

0.4572 336.81 0.0 cylinder 7

1 0.4661 336.81 0.0 cylinder 2

1 0.5296 336.81 0.0 cuboid 3

1 4pO.6985 336.81 0.0 unit 60

'instrument tube cell cylinder 4

1 0.4661 336.81 0.0 cylinder 5

1 0.5296 336.81 0.0 cuboid 4

1 4pO.6985 336.81 0.0 unit 40

'Region 2

Nominal Cell Box less outer wrapper area w

1.14 wto assy array 2

-10.4775

-10.4775 0.0 cuboid 4

1 10.4775

-10.4775 10.4775

-10.4775 336.81 0.0 cuboid 4

1 4pl1.43 336.81 0.0 replicate 8

1 4*0.1905 0.0 0.0 1

unit 41

'Region 2

Nominal Cell Box outer wrapper area horizontal cuboid 4

1 2p9.398 2p0.0127 336.81 0.0 cuboid 8

1 2pll.6205 2p0.0127 336.81 0.0 cuboid 4

1 2pll.6459 2p0.0127 336.81 0.0 unit 42

'Region 2

Nominal Cell Box outer wrapper area vertical cuboid 4

1 2p0.0127 2p9.398 336.81 0.0 cuboid 8

1 2p0.0127 2pll.6205 336.81 0.0 unit 43

'Region 2

Inter Box Cell less wrapper

areas, w

1.14 wt%

assy array 2

-10.4775

-10.4775 0.0 cuboid 4

1 10.4775

-10.4775 10.4775

-10.4775 336.81 0.0 C-31 Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company Palisades SFP Region 1 Criticality Evaluation 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY cuboid 4

1 4pll.51382 336.81 0.0 unit 44

'Region 2

Inter Box Cell wrapper top horizontal up cuboid 4

1 2p9.398 0.0

-0.05588 336.81 0.0 cuboid 8

1 2p9.448 0.0

-0.10668 336.81 0.0 cuboid 4

1 2pll.645 9 0.0

-0.10668 336.81 0.0 unit 45

'Region 2

Inter Box Cell wrapper top vertical right cuboid 4

1 0.05588 0.0 2p9.398 336.81 0.0 cuboid 8

1 0.10668 0.0 2p9.448 336.81 0.0 cuboid 4

1 0.10668 0.0 2pll.51382 336.81 0.0 unit 46

'Region 2

Inter Box Cell wrapper top horizontal bottom cuboid 4

1 2p9.398 0.05588 0.0 336.81 0.0 cuboid 8

1 2p9.448 0.10668 0.0 336.81 0.0 cuboid 4

1 2pll.6459 0.10668 0.0 336.81 0.0 unit 47

'Region 2

Inter Box Cell wrapper top vertical left cuboid 4

1 0.0

-0.05588 2p9.398 336.81 0.0 cuboid 8

1 0.0

-0.10668 2p9.448 336.81 0.0 cuboid 4

1 0.0

-0.10668 2pll.51382 336.81 0.0 unit 48

'Region 2

Inter Box Cell gap horizontal cuboid 4

1 2p9.398 2p0.0127 336.81 0.0 cuboid 8

1 2pll.51382 2pO.0127 336.81 0.0 cuboid 4

1 2pll.6459 2p0.0127 336.81 0.0 unit 49

'Region 2

Inter Box Cell gap vertical cuboid 4

1 2p0.0127 2p9.398 336.81 0.0 cuboid 8

1 2p0.0127 2pll.51382 336.81 0.0 unit 50

'Nominal cell horizontal array array 40 0

0 0

unit 51

'Nominal cell total array 41 0

0 0

unit 52

'Inter Box cell horizontal array array 42 0

0 0

unit 53

'Inter Box total array 43 0

0 0

C-32 Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company Palisades SFP Region 1 Criticality Evaluation unit 55

'Region 2

Inter Cell Box outer wrapper area vertical cuboid 4

1 0.0254 0.0 2p9.398 336.81 0.0 cuboid 8

1 0.0254 0.0 2p11.64.592 336.81 0.0 cuboid 8

1 0.2159 0.0 2p11.64592 336.81 0.0 unit 56

'Region 2

Normal Box Cell outside cuboid 4

1 0.05588 0.0 2p9.398 336.81 0.0 cuboid 8

1 0.10668 0.0 2p9.448 336.81 0.0 cuboid 4

1 0.1905 0.0 2pll.64592 336.81 0.0 unit 57

'Region 2

Normal Box Cell outside vertical cuboid 4

1 2p0.0127 2p9.398 336.81 0.0 cuboid 8

1 2p0.0127 2pl1.64592 336.81 0.0 unit 58

'Nominal cell total with edge array 44 0

0 0

unit 59

'Inter Box total with edge array 45 0

0 0

unit 70

'Tie Bar Top cuboid 2

1 2pO.4757 0.6985

-0.37715 336.81 0.0 cuboid 4

1 4p0.6985 336.81 0.0 unit 71

'Tie Bar Bottom cuboid 2

1 2pO.4757 cuboid 4

1 4p0.6985 0.37715

-0.6985 336.81 0.0 336.81 0.0 unit 72

'Tie Bar Left cuboid 2

1 0.37715

-0.6985 2pO.4757 336.81 0.0 cuboid 4

1 4p0.6985 336.81 0.0 unit 73

'Tie Bar Right cuboid 2

1 0.6985

-0.37715 2pO.4757 336.81 0.0 cuboid 4

1 4p0.6985 336.81 0.0 unit 80

'Absorber slot Horizontal

(+X)

Top cuboid 6

1 2plO.49 2pO.2667 336.79 0.0 replicate 0

1 0.00 0.00 0.0508 0.0508 0.0 0.0 1

unit 81 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY C-33 Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation

'Absorber slot Horizontal

(+X)

Bottom cuboid 6

1 2plO.49 2pO.2667 336.79 0.0 replicate 0

1 0.00 0.00 0.0508 0.0508 0.0 0.0 1

unit 82

'Absorber slot Horizontal

(+Y)

Left cuboid 6

1 2p0.2667 2p10.49 336.79 0.0 replicate 0

1 0.0508 0.0508 0.00 0.00 0.0 0.0 1

unit 83

'Absorber slot Horizontal

(+Y)

Left cuboid 6

1 2pO.2667 2p10.49 336.79 0.0 replicate 0

1 0.0508 0.0508 0.00 0.00 0.0 0.0 1

unit 85

'Space Cylinder cylinder 8

1 0.3175 336.79 0.0 cuboid 0

1 0.3175

-0.3175 0.3175

-0.3175 336.79 0.0 unit 90

'15 x

15 fa in rack 4.54 Planar Average array 1

-10.4775

-10.4775 0.0 cuboid 0

1 10.4775

-10.4775 10.4775

-10.4775 336.81 0.0 replicate 0

1 0.3937 0.3937 0.3937 0.3937 0.0 0.0 1

replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

replicate 0

1 0.635 0.635 0.635 0.635 0.0 0.0 1

'absorber slot top hole 80 0.0 11.5062 0.01

'absorber slot bottom hole 81 0.0

-11.5062 0.01

'absorber slot left hole 82

-11.5062 0.0 0.01

'absorber slot right hole 83 11.5062 0.0 0.01

'support top left hole 85

-11.5062 11.5062 0.01

'support top right hole 85 11.5062 11.5062 0.01

'support bottom right hole 85 11.5062

-11.5062 0.01

'support bottom left hole 85

-11.5062

-11.5062 0.01 replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

replicate 0

1 0.8763 0.8763 0.8763 0.8763 0.0 0.0 1

unit 91

'15 x

15 fa in rack wide/wide top left array 2

-10.4775

-10.4775 0.0 cuboid 4

1 10.4775

-10.4775 10.4775

-10.4775 336.81 0.0 replicate 4

1 0.3937 0.3937 0.3937 0.3937 0.0 0.0 1

replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

replicate 4

1 0.635 0.635 0.635 0.635 0.0 0.0 1

'absorber slot top C-34 Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company Palisades SFP Region 1 Criticality Evaluation hole 80 0.0 11.5062 0.01

'absorber slot bottom hole 81 0.0

-11.5062 0.01

'absorber slot left hole 82

-11.5062 0.0 0.01

'absorber slot right hole 83 11.5062 0.0 0.01

'support top left hole 85

-11.5062 11.5062 0.01

'support top right hole 85 11.5062 11.5062 0.01

'support bottom right hole 85 11.5062

-11.5062 0.01

'support bottom left hole 85

-11.5062

-11.5062 0.01 replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

replicate 4

1 0.8763 0.8763 0.8763 0.8763 0.0 0.0 1

20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY unit 92

'15 x

15 fa in rack

- wide/wide top right array 3

-10.4775

-10.4775 0.0 cuboid 4

1 10.4775

-10.4775 10.4775

-10.4775 336.81 0.0 replicate 4

1 0.3937 0.3937 0.3937 0.3937 0.0 0.0 1

replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

replicate 4

1 0.635 0.635 0.635 0.635 0.0 0.0 1

'absorber slot top hole 80 0.0 11.5062 0.01

'absorber slot bottom hole 81 0.0

-11.5062 0.01

'absorber slot left hole 82

-11.5062 0.0 0.01

'absorber slot right hole 83 11.5062 0.0 0.01

'support top left hole 85

-11.5062 11.5062 0.01

'support top right hole 85 11.5062 11.5062 0.01

'support bottom right hole 85 11.5062

-11.5062 0.01

'support bottom left hole 85

-11.5062

-11.5062 0.01 replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

replicate 4

1 0.8763 0.8763 0.8763 0.8763 0.0 0.0 1

unit 93

'15 x

15 fa in rack wide/wide bottom right array 4

-10.4775

-10.4775 0.0 cuboid 4

1 10.4775

-10.4775 10.4775

-10.4775 336.81 0.0 replicate 4

1 0.3937 0.3937 0.3937 0.3937 0.0 0.0 1

replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

replicate 4

1 0.635 0.635 0.635 0.635 0.0 0.0 1

'absorber slot top hole 80 0.0 11.5062 0.01 C-35 Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company Palisades SFP Region 1 Criticality Evaluation

'absorber slot bottom hole 81 0.0

-11.5062 0.01

'absorber slot left hole 82

-11.5062 0.0 0.01

'absorber slot right hole 83 11.5062 0.0 0.01

'support top left hole 85

-11.5062 11.5062 0.01

'support top right hole 85 11.5062 11.5062 0.01

'support bottom right hole 85 11.5062

-11.5062 0.01

'support bottom left hole 85

-11.5062

-11.5062 0.01 replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

replicate 4

1 0.8763 0.8763 0.8763 0.8763 0.0 0.0 1

20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY unit 94

'15 x

15 fa in rack wide/wide bottom left array 5

-10.4775

-10.4775 0.0 cuboid 4

1 10.4775

-10.4775 10.4775

-10.4775 336.81 0.0 replicate 4

1 0.3937 0.3937 0.3937 0.3937 0.0 0.0 1

replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

replicate 4

1 0.635 0.635 0.635 0.635 0.0 0.0 1

'absorber slot top hole 80 0.0 11.5062 0.01

'absorber slot bottom hole 81 0.0

-11.5062 0.01

'absorber slot left hole 82

-11.5062 0.0 0.01

'absorber slot right hole 83 11.5062 0.0 0.01

'support top left hole 85

-11.5062 11.5062 0.01

'support top right hole 85 11.5062 11.5062 0.01

'support bottom right hole 85 11.5062

-11.5062 0.01

'support bottom left hole 85

-11.5062

-11.5062 0.01 replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

replicate 4

1 0.8763 0.8763 0.8763 0.8763 0.0 0.0 1

unit 200

'Empty Rack Cell cuboid 4

1 10.4775

-10.4775 10.4775

-10.4775 336.81 0.0 replicate 0

1 0.3937 0.3937 0.3937 0.3937 0.0 0.0 1

replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

replicate 0

1 0.635 0.635 0.635 0.635 0.0 0.0 1

'absorber slot top hole 80 0.0 11.5062 0.01

'absorber slot bottom hole 81 0.0

-11.5062 0.01 C-SR Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation

'absorber slot left hole 82

-11.5062 0.0 0.01

'absorber slot right hole 83 11.5062 0.0 0.01

'support top left hole 85

-11.5062 11.5062 0.01

'support top right hole 85 11.5062 11.5062 0.01

'support bottom right hole 85 11.5062

-11.5062 0.01

'support bottom left hole 85

-11.5062

-11.5062 0.01 replicate 8

1 0.3175 0.3175 0.3175 0.3175 0.0 0.0 1

replicate 0

1 0.8763 0.8763 0.8763 0.8763 0.0 0.0 1

unit 100

'Rack C

10x10 array array 100 0.0 0.0 0.0 replicate 4

1 30.48 30.48 0.0 0.0 0.0 0.0 1

'replicate 4

1 30.48 2.7686 0.0 0.0 0.0 0.0 1

unit 101

'Region 2

llxlO rack array 101 0.0 0.0 0.0 replicate 4

1 30.48 30.48 4.1402 0.0 0.0 0.0 1

'replicate 4

1 2.7686 30.48 4.1402 0.0 0.0 0.0 1

global unit 210

'4x4 rack cells 4

of 4

loaded array 60 0.0 0.0 0.0

'replicate 4

1 30.48 30.48 30.48 30.48 30.48 30.48 1

replicate 4

1 0.0 0.0 0.0 0.0 30.48 30.48 1

end geom read array

'4.54 wt° planar average fuel assembly ara=1 nux=15 nuy=15 nuz=l fill 1

1 1

1 71 1

1 1

71 1

1 1

72 1

1 1

73 1

1 1

60 1

1 1

72 1

1 1

73 1

1 1

C-37 Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company Palisades SFP Region 1 Criticality Evaluation 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY 1

1 1

1 70 1

1 1

70 1

1 1

1 end fill

'1.14 wt%

fuel assembly ara=2 nux=15 nuy=15 nuz=l fill 2

2 2

2 71 2

2 2

71 2

2 2

72 2

2 2

73 2

2 2

60 2

2 2

72 2

2 2

73 2

2 2

70 2

2 2

70 2

2 2

2 end fill

'fuel assembly wwg/wwg top right ara=3 nux=15 nuy=15 nuz=1 fill 4

4 4

4 72 4

4 4

72 4

4 4

3 4

5 5

5 4

4 3

4 5

5 5

5 4

3 4

5 5

4 3

70 5

5 5

5 4

71 4

5 5

4 3

4 5

5 5

5 4

3 4

5 5

60 5

5 5

4 3

4 5

5 5

5 4

3 4

5 5

4 3

70 5

5 5

5 4

71 4

5 5

4 3

4 4

5 5

4 4

3 4

4 4

3 2

3 3

73 3

3 3

73 3

3 2

2 end fill

'fuel assembly wwg/wwg bottom right ara=4 nux=15 nuy=l5 nuz=l fill 3

3 3

3 70 3

3 3

70 3

3 2

2 4

4 4

3 2

4 4

5 5

4 4

3 4

5 5

4 3

73 5

5 5

5 4

72 C_3R Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation 4

5 5

4 3

4 5

5 5

5 4

3 4

5 5

60 5

5 5

4 3

4 5

5 5

5 4

3 4

5 5

4 3

73 5

5 5

5 4

72 4

5 5

4 3

4 5

5 5

5 4

3 4

5 5

5 4

4 3

4 4

71 4

4 4

71 4

4 4

3 end fill

'fuel assemb ly wwg /wwg bot tom l eft ara=5 nux=1 5 nuy= 15 nuz=1 fill 2

2 3

3 73 3

3 3

73 3

3 3

3 2

3 4

4 4

3 4

4 5

5 5

5 4

4 3

4 5

5 5

5 4

71 4

5 5

70 3

4 5

5 5

5 4

3 4

5 5

4 3

4 5

5 5

60 5

5 5

5 4

3 4

5 5

4 3

4 5

5 5

5 4

71 4

5 5

70 3

4 5

5 5

5 4

3 4

5 5

4 3

4 4

5 5

5 4

3 4

4 4

72 4

4 4

72 4

4 4

4 end fi ll

'fuel assembly ara=6 nux=2 nuy=2 nuz=1 fill 200 90 90 200 end fill

'nominal box horizontal ara=40 nux=3 nuy=1 nuz=1 fill 42 40 42 end fill

'nominal box total ara=41 nux= 1 nuy=3 nuz=1 fill 41 50 41 end fill

'inter box cell horizontal ara=42 nux=5 nuy=1 nuz=1 fill C-39 Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company Palisades SFP Region 1 Criticality Evaluation 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY 49 45 43 47 49 end fill

'inter box cell total ara=43 nux=1 nuy=5 nuz=l fill 48 46 52 44 48 end fill

'nominal box horizontal edge ara=44 nux=3 nuy=l nuz=l fill 51 57 56 end fill

'inner box total edge ara=45 nux=2 nuy=l nuz=l fill 53 55 end fill

'Region 2

Racks ara=100 nux=10 nuy=10 nuz= 1 fill 200 90 200 90 200 90 200 90 200 90 90 200 90 200 90 200 90 200 90 200 200 90 200 90 200 90 200 90 200 90 90 200 90 200 90 200 90 200 90 200 200 90 200 90 200 90 200 90 200 90 90 200 90 200 90 200 90 200 90 200 200 90 200 90 200 90 200 90 200 90 90 200 90 200 90 200 90 200 90 200 200 90 200 90 200 90 200 90 200 90 90 200 90 200 90 200 90 200 90 200 end fill

'Region 2

Racks ara= 101 nux= 10 nuy=11 nuz=1 fill 53 51 53 51 53 51 53 51 53 58 51 53 51 53 51 53 51 53 51 59 53 51 53 51 53 51 53 51 53 58 51 53 51 53 51 53 51 53 51 59 53 51 53 51 53 51 53 51 53 58 51 53 51 53 51 53 51 53 51 59 53 51 53 51 53 51 53 51 53 58 51 53 51 53 51 53 51 53 51 59 53 51 53 51 53 51 53 51 53 58 51 53 51 53 51 53 51 53 51 59 53 51 53 51 53 51 53 51 53 58 end fill

'Region 1

2 Racks C-40 Page

A AREVA AREVA NP Inc.,

an AREVA and Siemens company 20004-015 (09/30/2008)

Document No.: ANP-2779NP-001 NON PROPRIETARY Palisades SFP Region 1 Criticality Evaluation ara=60 nux = 1 nuy=l nuz=1 fill 101 end fill end array read bounds xyf=periodic

+zb=h2o

-zb=h2o

'read bounds xyf=vacuum

+zb=h2o

-zb=h2o end bounds read plot ttl='x-y slice top right cell xul=-0.l yul=54.0 zul=168 xlr=54.0 ylr=-0.l zlr=168 uax=1 vdn=-l nax=260 end ttl='x-y slice 4

cells' xul=-54 yul=54.0 zul=168 xlr=54.0 ylr=-54 zir=168 uax=1 vdn=-1 nax=260 end ttl='x-z slice xul=-101 yul=10.82 zul=368.0 xlr=54 ylr=10.82 zlr=-33 uax=l wdn=-1 nax=260 end end plot end data end C-41 Page

v t e Letter Sequence Request
TAC:ME0161, (Approved, Closed)
Initiation Request Acceptance Administration Meeting Questions Answers Results Approval Other: ML083370059
MONTHYEAR2008-12-19 [Table View]

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Latest revision as of 14:10, 14 January 2025

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