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6. TitleSIMULATING OF THE EFFECT ON CRITICALITY OF SIMULTANOUS MATRDC DEGRADATION AND ASSEMBLYCOLLAPSE FOR THE 21 PWR WASTE PACAKGE

7. Document Numberls) S. ersion

CAL-EBS-NU-M00D2 REV. 00

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M{OL. 19990928.6234 MO L.19990928 .0234

OFFICE OF CMIVAN RADIOACTIVE WASTE MANAGEMENT. CA QA

CALCULATION COVER SHEET Page: I Of. 30

2. Calctulton TitleSimulating the Effect on Citicality of'Simultaneous Matrix Degradation and Assembly Collapse for the 21 PWR Waste Package

3. Docurment Idenrffir Pincludfn Revision Nurnber)CAL-EBS-NU40W0 REV 00

4. Totat Attachments I. AttAchment Numbers- Nwnber of paGes In each2 V ________1-3,CDROM_

Pft Nare Sinpue Date

6. odgintor Abdelhalim A. Alsaed z /2 /T7

7. Checkar Laeta Angers 4 A __3_*_ _

S.~~~ ~ ~ ~ .L.a_

S. Lead Peter Gottlieb 4Z4

E. Remarks

Revision Nstory

10. Revsion No. I1. Oescri4Won of Revision

00 Initial Issue

A'41ZRe. 03119

Ar-s4.1 ZCl Rev. 06J3011E99

Waste Package Operations CalculationTitle: Simulating the Effect on Criticality of Simultaneous Mtr Degradation and AssemblyCollapse for the 21 PWR Waste PackageDocument Identifier CAL-EBS-NU 000002 REV 00 Page 2 of 30

CONTENTS

Page

1. PRPOSE_.__........_.._.__...... _ ._ 5

2. METHOD _..... ....... n... ... ...... 5.....n........ _ ..... 5

3. ASSUMPTIONS 6

4. USE OF COMPUTER SOFTWARE AND MODELS_. ........ 8

4.1 SOFTWARE APPROVED FOR QUALIrT ASSURANcE (QA) WORK ............................. ..... 842 SOFFvARE ROurIEs.. . ......... ..................4 4 . o m 3 .. ...... M........DEL...S...................... ........ ...............

S. CALLATIN 9 . ...

5.1.1 SpentFuelAssenblyParameters .. 95.1.2 lact Waste Package Geometry Parameters .. 115.1.3 Material Propertes .. 115.1.4 Fuel Isotopic Concentratons.. 145.1.5 BasketadFuelDegradationProdut Compositions .............................................. , 1

5.2 CALcuAToN OF NUmBER DENSTES FOR DECIDED BASKET MATEnAL...... .... 165.3 CALCAnoNoFNumBERDEmfmEsFoRFuELREOioN .............................. 175.4 MCNP CASE DEscpnON .... . ............ .... 17

6. RESULTS i....................n.. .... _ .. _....n_...n.n. 187. ATACHMENTS .~._. -.................... __. .. 24

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Title: Simulating the Effect on Criticality of Simultaneous Matrix Degradation and AssemblyCollapse for the 21 PWR Waste PackageDocument Identifier CAL-EBS-NU-000002 REV 00 Page 3 of 30

FIGURES

Page

2-1. Degraded 21 PWR Fuel Waste Package with Unifonn Corrosion Product Distibution ....... 6

Waste Patkage Operations CalculationTitle: Simulating the Effect on Criticality of Simultaneous Matrix Degrdation and AssemblyCollapse for the 21 PWR Waste PackageDocment Identlfier. CAL-EBS-NU-0 02 REV 00 Page 4 of 30

TABLES

Page

3-1. Principal Long-Term Bumup Credit Isotopes ............................................................. 75-1. Mechanical Parameters ofB&W IS 15 Fuel Assembly .................................................. 105-2. Fuel Region Node eigs and Volumes .... . ............ 105-3. Waste Pacige Dimensions .. ........ . ................. 1154. Densities ofNon-Fuel Materials ..... ... ........... -... . 11S-S. Atomic Weights &nole) ............ ................ . .............. . ...... . ....... 135-6. Chemical Compositions of WP and Fuel Assembly Alloys Modeled ............ .................... 145-7. Corrosion Products Remaining Following Basket Degradation ................................. ...... 155-8. Effects of Fuel Degradation on Principal Isotope Inventoy ..................... ... 166-1. Reactivity Evaluation of Simultaneous Matrix Degradation and Assembly Copse......... 196-2. Reactivity Evaluation of Simultaneous Matrix Degradation and Assembly Collapse..... 206-3. Regression Results of Ak as a Function of Fission Product Loss and Assembly Collapse.. 237-1. List of Attachments ....... . ..... . ;...... 247-2. List of Files in Attachnent II ..... ........ . ....... ...................... 24

-

Waste PAckage Operations CalculationTitle: Simulating the Effect on Criticality of Simultaneous Matrix Degradation and AssemblyCollapse for the 21 PWR Waste PackageDocument Identifier: CAL-EBS-NU-000002 REV 00 Page 5 of 30

1. PURPOSE

The purpose of this calculation s to evaluate the effects of fission products loss on the rctivityof commercial pressurized water reactor (PWR) spent nuclear fuel (SNF) in 21 PR wastepackages (VPs) in the event of simultaneous fuel matrix degradation and assembly collapse.ibis is in support of the work outlined in Reference 1.

Referencing in this calculation refers to the input document number appearing in column 2a ofthe Document Input Reference Sheets (DIRS), Attachment I hereto.

.2. METHOD

The Commercial PWR assembly design is based on the Babcock and Wilcox (B&W) 15 x 15Mark B assembly (see Assunption 3.3) In this calculation, multiplication factor (kw) values arecalculated for various degraded WP configurations using the Monte Carlo N-Particle transportcode system version 4B2 (MCNP4B2; CSCI: 30033; Ref. 2). For each combination ofenrichment and burnup evaluated, 18 axial fuel nodes are utilized to allow the effects ofdifferences in burnup along the assembly length to be considered. Fuel region number densitiesused in this criticality evaluation were extracted from the MCNP cases from Reference 3 for aparticular fuel node and decay time.

This calculation considers the waste package with uniform corrosion product distribution Sixfuel configurations, which are based on varying the rod pitch, will be considered for eachcombination of enriciment and bumup. Considering a conservative early breach of the wastepackage, this calculation assumes that the waste package will be full of uniform corrosionproducts at 10,000 years. For the first set of cases the reactivity of the waste package isevaluated for an intact fuel matrix at the nominal rod pitch with funl fission product inventory.At 45,000 years the fuel matrix is considered completely collapsed such that the rods aretouching and all the fission products released Four intermediate cases are also evaluted at14,000, 18,000, 2,000 and 35,000 years for which the rod pitch and fission productconcentrations are linearly evaluated. he general geometry for these cases is presented inFigure 2-1. The reactivity of the collapsed cases is compared to the nominal case at the sametime in life. The time in life of maximum increase of waste package reactivity is chosen to runthe cases needed for the probability calculation. These cases cover all possible combinations offission product loss and collapse fractions with which regression analyses were performed.

The MCNP cases of the three combinations of enrichment and bumup and all four decay times atoriginal rod pitch were taken fion the Tae Attaciment of Reference 3. Input Cards 56 through59 were modified to reflect original rod pitch between assemblies.

Waste Package Operations Calculationdtie: Simulating the Effect on Criticality of Simultaneous Matrix Degradation and AssemblyCollapse for the 21 PWR Waste PackageDocument Identifier, CA-EBS-NU0002 REV 00 Page 6 of 30

hZN'g. Sw t Mflu. O w

(L100J0 ..0000 W100)aim WI000 MM000W. .10000

giuFe 1 i Uftm 5 or1 1o 4,;Xut D

3.1 Principal+ Istpb p cret is asue tob an =qta meto toacut fr

Controlled Desig Awmpio Ie 00 (Rf 4). M aspin sue throuhou

3.2~ge o SF th lit o rnia stoe rvusystbihdO ., . 3-6 fo log-

asut21. Degraed 21roueo astion ge t o t D3t fu

,~~~~~3 ASUMTIN

3.1 Principal Isotope burnup credit is assmed to be an accale mehod to acount forreduced reactivty of SNF In criticality vutCiouL The basis for this assupion iscOnlld Design Assumption Key 009 (Ref. 4). This assumption is used throughoutSection 5.

3.2 For SNF, the list of '"Principal Isotopes" previously established (Ref. 5, p. 326) for long-term ctcit control was used. lhe 29 pripal isotopes are shown in Tabic 3-1. Thebasis for this asspion is to maintain tconsistencyt wih established preedens Thisassumption is uised throughout Section 5.

I

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Title: Simulating the Effec on Criticality of Simultaneous Matrix Degradation and AssemblyCollapse for the 21 PWR Waste PackageDocument Identifier- CAL-EBS-NU-000002 REV 00 Page 7 of 30

Table 3-1. Pncipat Long-Term Bumup Credit Isotopes

._ MoOS To49 Ru-101 Rh-103Ag-09 Nd-143 Nd-145 Sn147 Sn-149SM-i150 Sm151 SM-152 Eu-151 Eu-153Gd- 155 13 1-4 L25 U-M. = Np-.37 P*238 Pu-2W Pu-240Pu-241 Pu-242 Am-241 . Am-242m Am-243

3.3 It is assumed that B&W Mark B 1S x 15 fiuel type is atypical PWR assembly designs tobe used in this analysis. The basis for this assumption is that this assembly design is usedin several existg PWRS. his assumption is used throughout Section 5.

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Title: Simulating the Effect on Criticality of Simultaneous Matrix Degradation and AssemblyCollapse for the 21 PWR Waste PackageDocument Identifier: CAL-EBS-NU-000002 REV 00 Page 8 of 30

4. USE OF COMPUTER SOFTWARE AND MODELS

4.1 Software Approved for Quality Assurance (QA) Work

The calculation of I:z of degraded nternal WP configurations was performed with the MCNPcomputer code version 4B2 (CSCI: 30033; Ref. 2), which calculates kff for a variety ofgeometric configurations wnth neutron cross sections for elements and iotopes described in theEvaluated Nuclear Data File version B-V (ENDF-BV). The calculations using the MCNPsoftware were executed on a Hewlett-Packard workstation. The software qualification of theMCNP software version 4B2, including problems related to calculation of kr for fissile systems,is summarized in the Software Qualification Report for the Monte Carlo N-Particle code (Ref. 2).The MCNP evaluations performed for this calculation are fully within the range of the validationfor the MCNP software versions used. Access to and use of the MCNP software for this analysiswas granted by Software Configuation Management and performed in accordance with eappropriate procedures. Inputs and outputs for the MCNP software are included as AttachmentII as descibed in Section 7.

4.2 Software Routines

Microsoft Excel 97. loaded on a Pentium H PC. This software was used to perform regressionanalyses for which the data are listed in Section 6.

4.3 Models

None used.

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5. CALCULATION

5.1 Inputs

5.1.1 Spent Ful Assembly Parameters

The fuel as bly upon which this calculon is based is the Babcock & Wlcox S x 15 Mark Bfuel assembly. Ihe mechanicalpameters for this assembly tpe are shown in Table S-1. Thisinformation represents actual B&W fel assembly dimensions and is considered qualified data.Table 5-2 provides information on the fel region node heights used in this calculation.

Waef, Patjmtop nnirsntlnnt

Title: Simulating the Effect on Criticality of Simultaneous Matrix Degradation and AssemblyCollapse for the 21 PWR Waste PackageDocument Jdentifier CAL-EBS-NU-000002 REV 00 Pse 10 of 30

Table 61. Mechanical Parameters of B&W 15 x 15 Fuel Assembly(Ref. 3, p. 9)

Parameter Metric Units

Fuel rods 208 /assembly

Fuel Rods on lawce sde 15 side

Guide tubes 16 lassembty

nsruentadon b bes 1 /assembly

Wotai ude + k ntnent tubes 17 fassembly

dftube materibl Ziro4

u! pellet outer dlameter OD) 0.9398 cm

u £tadc helg* 360.172 cm

Fuel assembly helght 420.7 cm

Aass ofU 464 kg

Mass of UO2 526.38 kg

Percent of ca l densy 95

Fuel dad OD 1 cm

Clad thickness 0.06731 cm

Fuel clad Iner diameter DM 0.657I8 cm

Fuel rod pikh 1.4422 cm

Gde tube OD 13482 cn

de tUbe thickness 0.04064 cm

Guldetel? 126492 cm

Instumentallon ube 9D 125222 cm

tQIpIaced Volume per Fuel Assembly 0.081 R

Table 6-2 Fuel Reglon Node Heights and Volumes(Ref. 3. p. 10)

Node Height (cm) Volume (cmY. 1 1 7800 2585.404521o 17 20.0025 2886.0801

Volumes calculated as (Pellet OD)2(HelghW4

Waste Pscklge Onerations CalculationTitle: Simulating the Effect on Criticality of Simultaneous Matrix Degradation and AssemblyCollapse for the 21 PWR Waste PackageDocument Identifier: CAL-EBS-NU-0002 REV 00 Page 11 of 30

5.1.2 Intact Waste Package Geometry Parameters

The intact waste package geometry parameters used In this calculation are listed in Table S-3.This information is based on unqualified drawings or QAP-3-9 analyses and is thereforeconsidered unqualified. Corrosion product volume information for the 21 PWR WP wascalculated in Reference 6 and is ummarized in Section S.1.5. The corrosion productinformation is considered unqualified.

Table 6-. Waste Package Dimensions(Ref. 3. p. 10)

21 PWRWP Material, Component Dimensions R.. p. 0)

Outer barrier length (skirt edge to skirt edge) 633.60Outer baier skir length (both ends) 22.50Outer barrier Rd Uckness 11.00 Aste CarcnOuter barrir hner radi 73.17Outer barrer outer radU 63.17Gap between Inner and outer lids 3.00 NotAppcable

Inner barrier length (overall 483.60

Iner barrier Ed tickness 2.60 Alloy 22nner barrer nner radi 71.17 (UNS N0=02)

innr barrier outer radi 73.17

S13 Material Properties

Densities of non-fuel materials used in this analysis are listed in Table 54, which are consideredunqualified:

Table 64. Densiltes of Non-Fuel Materials(Re£ 3, p. 11)

Mterial |Dense (kmS) |

A 16 Grade 70 carbon teel 7832

Inconel Aloy U2 (UNS N065) 8442

;oddyite (U02(SO4)2H2O 4700

Zrcaloy.4 6560Aloy 22 HastelloyAfloyC-22, UNS N060 8890

Water 1000

The atomic weights of isotopes are listed in Table 5-5 ef. 3, p. 11). Avogadros Number [NA]

Waste Package Onerations CalculationTItle: Simulating the Effect on Criticality of Simultaneous Matrix Degrdation and AssemblyCollapse for the 21 PWR Waste PackageDocument Identifier CAL-EBS-NU-000002 REV 00 Page 12 of 30

= 0.602252 x 104 (atoms/mole) (Rel 3, p. 1 1) Chemical compositions of alloys used in tbiscalculation are given in Table 5-6. This nformation is obtained fom qualified QAP-3-9analyses, or is considered established filt, and is therefore considered qualified.

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Title: Simulating th* Eec on Citicality of Simultaneous Ma& Degradation and AssemblyCollapse for the 21 PWR Waste PackageDocument dentifien CAI-EBS-NU-000002 REV 00 Page 13 of 30

Table 5. AtomIc Weihts (moe)(Ref. 3, p. 12)

isotope MCNP ID$ Atomc WelghtB-10 6010.600 10.0129388B-11 5011.66C 11.093

NaL 0 ot sed 15.90-16 8016.600 15.094915tF 2000.650: 65.847

Mo5 42095. 94.9Tc-9 43099C 98.90827501Ru-101 44101.0 10.905576Rh103 45103600 102.08511Ag-109 47109.500 108.90756Nd-143 60143fX0: 142.909779Nd-145 6014SfXX0 144.912538SG 147 62147.500 146.914867Sm-149 62149.500 148.91718Sm-150 6210O5 149.917276SM-151 62151.500 150919919Sn-152 62152.500 151.919756Eu-151 63151.55C 150.919838Eu-153 63153.550 152.921242Gd-155 64165f.50 15492664 U33 92 60C 233.039522U-234 92234600 234.04904U-235 92235.500 235.043915U-236 9380 236.045637TUM-238 92238.500 238.05077Np-237 93237.f5C 237.048056Pu-238 94238.ZX0 238.049511Pu-239 94239.550 239.052146Pu-240 94240.500 240.053882PU-241 94241J500 241.05637PU-242 9424250 242.058725Am-241 9241.500 241.056714

Arn242m 95242.50 242.059502Am-243 95243.50 243.061387

* i

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Tide: Simulating the Effect on Criticality of Simultaneous Mat Degradation and AssemblyCollapse for the 21 PWR Waste PackageDocument Identifier, CALEBS-NU-O00002 REV 00 Psge 14 of 30

Table 6. Chem~cal Compositons of WP nd Fuel Assembly Alloys Modeled(Ref. 3, p. 13)

Alloy 22 InconeAlloyMat"rlalIElement A 616 ade (Hastelloy Alloy C- 625 Zlrcay4

65Carbon Steel 22, UNS N06022) (UNS 406625)Fe 95835% 3.000% 6.00% 0.200%Cr _______ 22.000Y 21500% 0.10WeNl . 66.000Y 68.000%

Mn 090% 0.00% 0.600%Mo . 13.000% 9.000% -

6 0.035% 0.015% .Sl 0275% 0.080% 0A.00YeP 0.035% 0.015%C 0220%6 0.010% 0.100%o . 0.120%Co . 2.060% 0930% W -3.000% -

T1 0.400% Al _ * 0A00% -

V 0.350Y% .6Y0Nb+50%Ta -. 3600%Y

Zr N 98.180%Sn . 1.A00%

TOTAL 100.00% 100.% 100.00% 100We%

I

.. -1 �

.IA Fuel Isotopic Concentrations

The fiel isotopic concentritions are the same as those In the MCNP cases from Reference 3 for18 axdal nodes per assembly. The following combinations of enrichment and burnup wereutilized for this calculation: 3 wt% at 20 gigawatt dayshton (OWd/l), 4 wPK at 35 GWdtF and4.5 wt/o at 40 GWd/T.

5.1.5 Basket and Fuel Degradation Product Compositions

Reference 6 performed gcochemsty calculations to determine the composition of the corrosionproduct mixte remaining in the 21 PWR waste package following complete basketdegradation. Table 5-7 summaizes the concentrtions of insoluble corrosion products thatremain after the basket has completely degraded. Reference 6 indicates that this finalcomposition remains fairly constant over the range of possible borated stainless steel degradationrates and drip rates. The molestWP column is calculated by multiplying the moles/L H20column by 4,550 liters of 120, which is the amount of water considered to be in the WP inReference 6 (equivalent to the void space available in a loaded WP with an undegraded basket).

WAste Package Oeratious. CalculationTitle: Simulating the Effect on Criticality of Simultaneous Matrix Degradation and AssemblyCollapse for the 21 PWR Waste PackageDocument Identifier, CAL-EBS-NU-000002 REV 00 Page S of 30

Table 67. Corroslon Products e"alniV Folowing Basket Degradatlon(lRef. 3, P. 14)

Vouatwer molesfilterBast Corrosion Product WP tnv HIO matesw~

Daspore 0 1.8392E-01 2291 10424.05Hemnate (F02 1.7707E+00 12.7? 68103.6Pyusite n2 2.7361E-02 0.35 1592.5N 4S1 04 3D867E-02 0.1592 724.36Nonbon!t-Ca CaAlm Fe2Ha00) 12874E.02 0216 9828Non(Ste-K (S6,KvAJ= Fe*2 O) 6.25E04 0.0009151 4.1630Nortordle-Mg (Ss4X1g2AuS F 402H) BS323E-03 0.01513 68.8415Norfronte-Na (SaINaAlasn Fe2O,2 9.0407E.04 0.001504 6.8U2

OTAL , 2.0362E400

Reference 6 also examined the effects that fiiel degradation will have on the principal isotopeinventory. Reference 6 examined two cases for both commercial and mixed oxide (MOX) PWRfuel: I) fuel degradation concurrent with basket degradation, and 2) fuel degradation beginningafter basket degradation is completed. The former case for the commercial PWRnasulted in thegreatest loss of principa Iotopes due to lower pH conditions during degradation of the boratedstainless steel and fuel. Table 58 summariz the percentage of each principal isotoperaining at different times from the beginning of fuel degradation. Note that the geochemistrycalculations of Reference 6, and thus the results in Table 54, do not account for the decay of theprinciple isotopes. Decay was accounted for by applying the reduced principle isotopeconcentrations for a given degradation time to a decay time that is equally offset from the pointat which degradation began (i.e., if degridtion is assumed to begin at 10,000 years, the principleisotopeinventories at 12,000 years will be reduied as indicated for a degradation time of 2,000years).

Waste Packnae Oneratlons CalculationTite: Simulating the Effect on Criticality of Simultaneous Mai Degdation and AssemblyCollapse for the 21 PWR Waste PackageDocument Identifier, CAL-EBS-NU-000002 REV 00 Page 16 of3O

Tnble 64. Effects of Fuel Degradation on Principal Isotope Inventory(Ref. 3. p. 16)

_______ ~~Fuel Degradatlon Time &O)_______ ___

Element ZO0 4,O0 8,000 15,000 15,00 35.000 90,000 24000U 100% 100% 100% 100% 09% 9% 08% 88%NP 85% 70% % 0% 0% 0% 0% 0%Pu 100% 100% 100% 100% 100% 100% 100% 100%Am 0% MD 0% 0% 0% 0% 0% 0%Mo 0% 0% 0% 0% 0% 0% .o% 0%Tc 0% 0% 0% 0% 0% 0% 0% 0%Ru 100% 100% 100% 100% 100% 100o 100% 100%Rh 100% 100% 100% 100% 100% 100% 100% 100%A_ 87% 80% Gm 43% 12% 0% 0% 0Nd 09% 98% 97% 95% 95% 95% I5Y% 95%Sm 80% 70% 46% 27% 26% 26% 24% 20%Eu 82% 71% 48% 9% . 8% 7% 2% 0%Gd 66% 35%. .14% 6% 6% %: C% 3%

I

52 Calculation of Number Densities for Degraded Basket Material

Based on the total volume of corrosion products remaining following full basket degradation (seeSection 5.1.5), and the total volume contained within the nner barrier minus that occupied by thefitel assemblies (volume of the fiel rods), the corrosion products will ocupy 36.4% of theinterior void space of a 21 PWR WP. If the corrosion products settle to the bottom of the WP,the physical geometry of packed solids will result in a density that is less than theoretical. Forexample, the percent solid content noted for a tight packing of sand (Ref. 3, p;.15) is 58%. Theporosity (the complement of the solids content) of tightly packed carbon-.steel tubesheetcorrosion products that led to the denting of steam generator tubes at two Westinghouse plantswas found to be between 7% and 2S% (Ref. 3, p. 15). Since the oxides in the tubesheet werecompressed to the point of denting the tube, and no such restriction of the oxides in the VIP iscxpected, the tight.packing of sand will be taken to be r ste of that of iron oxide scalethat has settled. At 58% dense packing, If all of the oxides settle to the bottom, they willcompletely cover the bottom three rows of assemblies, and cover more than 95% of the fourthrow (93% or 14 rod rows of a B&W 1 x 15 Mark B assembly is conservatively used for thisanalysis). Number densities were calculated for the above corrosion product and water mixturesby dividing the moles of each element per WP (as indicated in Table 5-7) by the void space theyoccupied and multiplying by Avogadro's Number (0.602252 x 10" atoms/mole). Thesecalculations are performed in Reference 3.

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5.3 Calculation of Number Densities for Ful Region

The gratns/assembly output for each time step was used to calculate the number density of eachprincipal sotope (see Assumption 3.1). Ie number densities of e principal isotopes in thenominal cases for each combination of enrichment and burnup were calcuIated in Reference 3.The reduced number densities in the degraded matrix cases are simply calculated as a frationalchange from the nominal.

5.4 MCNP Case Description

The purpose of this section is to describe the MCNP cases considered for the 21 PWR wastepackage design with intact fuel and filly degraded basket structures. In all of the cases, eachB&W 15 x 15 fuel assembly is treated as a heterogeneous system with the fuel rods and controlrod guide tubes and instrument tubes represented explicitly using the information contained inSection 5.1.1. The fuel assemblies are conservatively represented with water in the fuel rod gapregion, and the instrument and guide tubes, even when surrounded by watercorosion productmixtures, as there is no physical mechanism for getting basket corrosion products into theselocations while the assembly remains intac The composition and dimensions of thecontainment barriers are represented explicitly using the information in Section 5.1.2.

The MCNP cases will consider the evaluation of basket corrosion product composition discussedin Sections .1.5 and S2. The uniformly distributed corrosion product configurations isevaluated. Figure 2-1 shows the geometry details of the MCNP4B2 model for the 21 PWR WPwith a fully degraded basket and uniformly distributed corrosion products for a range of rodpitch values of nominal spacing 1.44272, 1A0266, 13626, 1.2925, 1.19235 cm and touchingrods in a square lattice 1.0922 cm which correspond to decay times of 10,000, 14,000, 18,000,25,000, 35,000 to 45,000 years, respectively. The following combinations-of enrichment andburnup will be evaluated: 3 wP% U-235 at 20 GWdIr, 4 wtc/ 23U at 35 GWd/T, and 4.5 wt/U-235 at 40 GWdIT. The diameter of the guide tubes is slightly larger than the collapsed pitchsuch that a small portion of the clad is lost in the case representation, which has no effect on thesystem reactivity. he pitchldecay time combination that yields the highest increase in wastepackage reactivity will be used to perform the cases for the probability calculations. The threecombinations of burnup and enrichment at the most reactive time in life will be used to evaluatethe waste package reactivity at all pitch values and fission loss fractions such that a total of 108cases will be run.

Waste Package Operatlons CalculationTitle: Simulating the Effect on Citicalt of Simultaneous Matrix Degradation and AssemblyCollapse for the 21 PWR Waste PackageDocument Identifier: CAT-EBS-NU000002 REV 00 Page 18 of 30

6. RESULTS

Table 6-1 lists cff and standard deviation (a) values for the cases used to determine epitchldecay time combination that yields the highest increase in reactivity. The ases at 25,000years with a pitch of 0.64625 cm yield the highest activity inrease Table 6.2 lists the kvalues for the cases for the three combinations of enrichment and brnup at 25,000 years decayfor all possible fission product loss (FPL) fiactions and pitch combinaons Using the data inTable 6-2. a regression analysis was performed to evaluate Ak as a function of pitch and fissionproduct loss for each combination of enrichment and bumup as listed in Table 6-3. The averageof the three regression fits was evaluated and is listed in Table 6-3. The average energy ofneutron causing fission (AENCF) is also included is the aforementioned tales . The fissionproduct loss fraction used for some of the cases in Table 6-1 was rounded off, thus some of thekeff values are slightly different but within the standard deviation, than the simila cases in Table6-2.

The results reported in Section 6 are based on unqualified data and must be verified prior to usein quality affecting activities or for use n analyses affecting procurement, construction, orfabrication.

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Title: Simulang the Effect on Criticality of Simutameous Maix Degmdatin and Assembly Collpe for lhe 21 PWR WastePackageDocunit Identifier-, CAL-EBS..NU-000002 REV 00 Nre 19 gf 30

Table 6-1. Readily Evaluaon clShiftrno Md Degradalon and Ass~mby Collpse

0e"d"o k0FP_ AENCF MM AZNCPEzuchment unmi nm 072138 n I FPL . F.(wU-235) (OWd) 7 r4 Pitch so Ma Me Nam (CM) 1 kw 2 (MaY "me k

4.50 40 1000.0 as883 0420 WJ4540bo 0.13 C.M. 0 .00 m.24m8 4Sbo t OOO

4.iO 40 1400.00 0 0.0030 024519 A540do 0.70133 113 0U50 0.00 0.25J R540do 4.00151

4.0 40 18000.00 U886 0AM03024384 m54no 013810 .8 CAM G0022 527004 M454o 001004

: - :.4~~~~50 0. 00= - --:0.oo8 _OS .0.0020 ;Wi5. *2X:40.,,52 S AM- 1 UM Z=0F

4.50 40 35000.00 O0 0 M 03882 u4540go 0.6 177.4 03 2 003 0.305 w45dgo 0O013

4.50 40 45000.00 O 184 0.00304 023039 nu4UOh 05410 100.00 085289 002 8 428 4ho ..02895

4;00 35 10000D0 0.7101 .0280 0250M nSbo 0.72130 0.0 O.7O 0. 002M 0250 nu403o OD004.00 85 UOOO.0 0.87427 0.0028 @248 nu4do 0.70133 11A3 06 o00350 02=03do 0.001524.00 35 18000.00 O.8241 0.00248 0.45 m 035eo 0.130 2.S 0.89 0 8 017133 uOSSeo OA

- 4m-.-' 7-735. -25000-.00 :. 087934 ... ~ -os*'. 2 u4 403Wo0 2- 0 .8524... " iU i iR 0 ; *'0904.00 35 35000.00 OS03S4 0.08 014020 035go 517 T1A3 073 0.00242 0O9 w Sg40040

4.00 35 45000.00 _0755 0.0028 021 mO35ho O.510 1OAO 0.3905 oCoozu OA329 nh435ho 450

3.00 20 10000*0 09948 000218 52455 iuO2bo 0.72138 0.00 094 .00216 024555 nu32Obo 0*00003.00 20 14000.00 O.909 O.014 02475 n6302do 0.70133 11 090475 0. 2 02509 nOOdo OO

3.00 20 1000 007 .0204 24230 nu32o 08130 2Z8 0.100 0.00300 2882 3 o 0093

3.00 20 . 2 0- 0 02 so00. 0.e394 mz'O2Of 04525 . ii 0.00242 n3.00 20 35000.00 0775 0.01 023SU So 0917 713 0.983 0.00318 0451 tOo 00130

3.00 20 45000w*0 09408 00418 M23735 m t3 OS(1 100.00 014 .4327 nOOho 0* 0

Vawn.,, Paoega vat~, 9"Al0en

Title: Simulating the Effect on Criticalty of Simultaneous Matrix Degradation and Assembly Collapsefor the 21 PWR Waste PackageDocument Identifier: CALEBS-NU- 02 REV 00 Page 20 of 30

Table 6-2. Reacity Evaluabon of Simuftaneous Matrbx Degradation and AssemblyCollapse

Enrlchmern Bup _AENCF FPL Collapse ICase I(w% U235) (GWdT) w 2 (MOV) ) I ) a

32Oaao: 3.00 20 0.R021 0.005 024083 0 0.00 03020abo: 3.00 20 0.897 0.07 0250 0 11.4 1 . 0444302Oaco: 3.00 20 0.88834 .44 027114 0 22. -0.0138530208do: 3.00 20 0U77 0044 03266 0 42.88 .0.024313020aeo: &00 20 0.83745 0.0027 0.37118 0 714 -004743020ahb: 3.00 20 0.797 0.00258 0A8549 0 100.00 -0.142923020bao: 3.00 20 0.02 0.0074 023759 11A3 0.00 0.00509S02Obbo: 3.00 20 0.9042 0.00268 025147 11.43 1.A3 0323020bco: 3.00 20 088 0.00242 026771 11A3 22.86 0.003763020bdo: 3.00 20 88706 029 0.30091 11A3 4286 .0.015133o20beo: 3.0 20 0.84516 0.00348 0.8887 1143 71.43 .0.057033020bfo: 3.00 20 0.76537 .0096 0.48038 1 A3 100.00 .0.13682302Ocao: 3.00 20 0.9151 0.0023 023607 22.86 0.00 0.01291302Ocbo: 3.00 20 001185 0.00196 024890 22.86 11.3. 0.009330200: 3.00 20 O93 0J00228 028387 22.88 22.86 0.00774320cdo 3.00 20 09484 0.00288 029725 22.8 42.88 :.o035S020ceo: 3.00 20 0.85174 0.00276 O.87 22.86 71A 0.050453020do: 3.00 20 0.7732 0.00298 0.47534 22.86 100.00 .0.128993020dao: 3.00 20 0M27 0.00296 0.23543 42.9 0.00 0.020513020dbo: 3.00 20 0M491 0.00274 0.24612 42.9 11.A3 .O022723020dco: 3 3.00 20 0.921 0.03266 0282 42.9 22.86 0.018813020ddo: &00 20 0.9099 0.00244 027 42.9 428 0.007773020deo: . 3.00 20 O.88818 OA068 0.3036 42.9 71.43 0.034013020dfb: 3.00 20 0.78912 0.00270 0.48849 42.9 100.00 .0.113073020eao: 3.00 20 094988 0.00256 022653 71A3 0.00 0.047673Q20ebo: 3.00 20 0.94823 0.00294 024076 71A3 11.43 0.048043020eco: 3.00 20 0.94893 0.00288 025248 71.A3 22.6 0.044743020edo: 3. 20 0.3497 O07 028711 71A3 42.86 0.032783020eeo: 3.00 20 0.893 0.00252 080 71.43 7tA3 -0.009193020oefo: 3.00 20 0.81187 0.00254 0.45823 71.43 100.00 .0.090323020fao: 3.00 20 0.97601 0.00258 0.22135 100 0.00 0.073823020fbo: 3.00 20 0.97392 0.00276 023494 100 11A3 0.07173302M0f: 3.00 20 0.97359 0.00306 024792 100 22.8 0.07143020fdo: 3.00 20 0.96038 0.00312 027983 100 42.86 0.058193O2Ofeo: 3.00 20 0.92103 0.00274 0.34198 100 71A3 0.018843020fo 3.00 20 0838 0.00Q84 U.44057 100 100.0 .006333

4035aao: 4.00 135 0.87686 0.00348 024338 0 0.00 04035abo 4.00 35 0.87492 I000302 025518 O 11.43 .O004

-

.

Wattg Paeker nnisraflnnv Calcutline~a- - . f . .

Title: Simulating the Effect n Criticality of Simultaneous Matix Degradation and Asembly Collapsefor the 21 PWR Waste PackageDocument Identifier: CAL-EBS-NU-000002 REV 00 Pae 21 of 30

Table 6-2. Reactivt EvaluatIon of Simultaneous Matrx Degradation and AssemblyCollapse

Enrichmant BuInIp AENCF I FPL Colapse Case tot%1 5) (GW4m k j Z (MOV) (%) In c

4o3a: 4.00 35 0668 0.0054 027289 0 22.86 -O09438do: 40 35 0.84407 O03 0.31335 0 42.6 .031794035aeo: 4.0 35 M M 003 0.8 0 7143 4.07584035ab: 4.00 35 02499 0 0.6077 0 100.00 4.15W7403Sbao: 4.00 35 0824 02 024189 114 O0 MO0=4035bbo: 4.00 35 08189 0.002 025820 1A 1143 0.00634035bco: 40 35 0.86819 0.00328 0277 1143 228 -0.007674035bdo: 4.00 35 0.84986 0.00272 0.31202 11.43 42.86 -0264035beo: 4.00 35 0.81253 000328 038307 1.43 71.43 . 0.063334035blo: 4.0 35 0.73908 0 0026 0.49194 1.43 100.00 -0.13878=35cao: 4.00 35 0.89574 0.00322 024138 22.88 O.O 0.01988

40do: 4.00 35 0.9537 0.00294 025430 2286 113 0.019514035cco 4.00 35 0.8816 0.00288 027345 22.86 22. 8 0.00834035cdo: 4.0 35 0.8883 o0033 o 22.86 42.8 .0.0070343ceo: 40 35 0.82394 0.00344 0.37389 22.86 7143 -0.051924035do: 4.00 5S 0.74846 0.0032 0A9118 2288 100.00 4.12744035dao: 4.00 35 0.91255 OA0284 023662 42.9 00 0.03694035dbo: 4.00 35 0.91682 0.00286 0.242 42.9 1.43 0.039964035do: 4.00 35 0.9048 O.O058 026527 42.9 22.86 0030624035ddo: 4.00 35 0.87908 0.00286 00382 42 42.86 00x34035deo: 4.0 35 0.84197 0.O294 0.3573 42.9 71.43 .0.033894035dfo: 4.00 35 0.76791 0.00304 04303 42.9 100.00 .0.107954035eso: 4.00 35 0.94328 0.00278 022864 71.3 0.00 0.067424035ebo: 4.00 35 04076 0.0031 024208 71.43 11.A3 0.0644035eco: 4.00 35 0.93187 O.0028 025938 713 22.68 0M014035edo 4.00 35 09196 000274 029138 71A3 4288 0.043744035eeo: 4.0 35 0.87468 o0266 035808 71.3 71.43 4.001184035efo. 4.00 35 0.70494 0.00256 0.48596 71.43 100.00 4.080924035fao 4.0 35 0.979 0.0026 022015 100 0.00 0.103634035fbo 4.00 35 0.9764 0.00302 023309 100 1A3 0.099544035fc=o 4.00 35 0.97445 0.002U 024663 100 22.88 0.098594035fdo: 4.0 35 0.96187 0.0076 027614 100 42. 0.086014035feo- 4.00 35 .91677 032 0.34297 100 71A3 0.040914035ffo: 4.00 35 03295 0.0032 044631 100 100.00 4.04291454aao: 450 40 0.a3 0.0043 024202 0 0.00 04540abo: 450 40 087585 0.00328 025514 0 .11A3 4.007374540aco: 4.50 40 0.88737 0.00376 027197 0 22.86 0.015854540ado * 4.50 40 08448 000372 031176 0 428 4.03842

Wnw#^ o prik nrvnf;n ^slenlt;nnTitle: Simaing the Effect on Criticality of Simultaneous Matrix Degradation and sly Collapsefor the 21 PWR Waste PackageDocument Identifier: CAL-EBS-NU.0OOD02 REV 00 Page 22 of 30

Table 6-2. ReactvIty Evaluation of Simultaneous Matrix Degradation and AssemblyCollapse

Enrchment mup I Il I AENCF FPL IColapselCase (wt U-235) (WdJT) j_ 20o (MOV) 4%) [%) 6k

4540seo: 4.50 40 0.80341 0.0034 0.8390 0 713 -.. M7814540Saf 4.5O 40 o.m276 0.00348 0A9870 0 100.00 .0.15#84540bao: 4.50 40 0.94 . 0.00316 024048 1A3 0.00 0.007184S40bbo: 4.I0 40 0.88711 0.00372 025825 11.43 11.43 0.003894540boo: 4.60 40 0.88601 00034 026774 11.A3 22.88 0.00O274540bdo: 4.60 40 O5572 0.00352 0074 s13 42.86 0.02764540beo 4.60 40 08124 0.00398 o.m53 t1.A 71A3 0.070824540b60: 4.C0 40 0.74004 0.00328 .902 11.A3 100.00 *0.143184S4Omo: 4.50 40 0.90395 0.00406 023400 22.86 0.00 0.020734540cbo: 4.50 40 0.90054 0.00292 024939 22.8 AS 0.01732440cco: 4.50 40 0.89134 0.00316 026629 22 22 2286 0.008124540cdo: 4.50 40 0.87262 0.0030 30071 22.86 42i6 - 0.01064540ceo 4.50 40 .8563 000308 072 22.86 7143: .0.057594540do: 4.60 40 0.7498 0.00348 Q48670 22.86 100.00 .0.133424540dao: 4.5D 40. 0.91819 020 02332 42.9 0.00 0.034974540dbo: 4.50 40.- 0.9153 0.00330 024811 42. 11A3 0.032314540dco 4.50 40. 0.913 0.00358 026363 42.9 22.86 0.029784540ddo: 4.50 40 0.89357 0.00354 029618 42.9 42.86 0.010354540deo: 4.60 40 0.84152 0.00324 0.36605 42.9 71A3 .0.04174540dfo: 4.50 40. 0.76986 0.00346 0.47709 42.9 100.00 0.113364S40eaeo 4.60 40 0.95989 .00364 022425 71.3 0.00 0.076674540ebo 4.50 40 0.95205 0.00288 024043 71A3 11.3 O68834540eco: 4.50 40 .4811 0.00306 025294 71.A3 22.88 0.064894540edo: 4.60 40 0.92473 0.00292 028479 71.3 42.6 0.041514540eeo: 4.50 40 0.8831 O.O07 0.35276 71.43 71.A3 *0.000124540efo: 4.50 40 0*013 0.00338 0.45987 71.3 100.00 .0.081924540fao: 4.60 40 0.99W 0.0024 021681 100 0.00 0.109054540tbo: 4.60 40 0.99148 0.O2 022990 100 11.3 0.108264540fco: 4.50 40 0Q887 0.0028 024262 100 22.68 0.105484540ftdo: 450 40 0.6699 0.0027 0277 100 42.B 0.083774540feo: *.50 40 0.92047 0.00316 0.33767 100 71.43 0.03725454ff o: 4.50 40 0.84063 0.00258 0.44114 100 100.00 0.04259

RVU-4a- Da tn fl nno4

fh fPai.,,Ia4;rnVW X% A dPLJf UUj_- IIIWA .0

tle: Simulating the Effect on Criticality of Simultaneous Matrix Degradation and Assembly Collapsefor the 21 PWR Waste PackageDocument Identifier: CAL-EBS-NU.0002 REV 00 Parc 23 of 30

Table 63. Regression Resuts of Ak as a Funclion of Fission Product Loss and AssemblyCollapse

Enruichment Bumup Intercept % FPL % Collapse(wMU-2 (GWd)

3.0 20 0 0.00090428 .0.0012381

4.0 35 0 0.0011859 .0.0013417

4.6 40 0 0.0012478 .0.0014189

Average 0 0.0011127 .. 001332

Waste Paclaze Onerations - - ~~~~~~~~~~~. CculationTitle: Simulating the Effect on Criticality of Simultaneous Matrix Degradation and Assembly Collapsefor the 21 PWR Waste PackageDocument Identifier: CAL-EBS-NU-0MO2 REV 00 Page 24 of 30

7. ATTACHMENTS

Attaclments to this document are listed in Table 7-1 below.

Table 7-1. LstofAttachments

Attachment DescriptionNumber

I Document Input Reference Sheets (DIRS)

nI CD-ROM Cntainingte Input and Out Fles for the MCNPuIculstions.

The following supporting documents listed n Table 7-2 are in electronic form on a CD. Each file isidentified by its name, size (in bytes), the date and time of last access. Note that for files transferredfrom the Hewlett-Pacard to the Personal Computer, the date and time will reflect the time of trander.The actual date and time of run completion can be found in the file.

Table 72. List of Fies in Altachment II

Foe Name Date Time Size.__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ (bytes)

u3020b 082499 02:48 PM 44,372Ci530ow- 08124)9 02.49 PM 699,267

u ad 0124/99 02:49 PM 4,835UiX3020do 0824199 02:49 PM 692,466mz3020e 0 499 02:49 PM 42,718nu302Oeo 0814)99 02:49 PM 678,408n3020f 0884/9 02:49 PM 42,720

nu3020fo 0824/99 02:49 PM 678,328m:3020g -0824199 02:49 PM 42,701uu3020go _ 081499 02:49 PM 678,508m3020h 08124)99 02:49 PM 42,710nu3020ho OJ24199 02:49 PM 678,369nu4035b OV24199 02:49 PM 44,394nu4O3Sbo MUM 02:49 PM 699,206nu4035d 08124199 02:49 PM 43,832nu4O3Sdo 0812499 02:49 PM 692,553uu403Se 084/99 02:49 PM 42,675nu403$co 0824/99 02:49 PM 678,321ou4035f 08124/99 02:49 PM 42,712=u403Sfo 0&499 02:49 PM 678,529u403Sg OV12499 02:49 PM 2,728

nu4035go 0824f9 02:49 PM 678,707nu403Sh 0884199 02:49 PM 42,706nu403Sho 0824199 02:49 PM 678,360im4$40b ii747 02:49 PM 44,377nu4S40bo 0&4/99 02:49 PM 699,206DU4540d OU24f99 02:49 PM 43,856nu4S40do 08M24)99 02:49 PM 692,S08

.Wade Package Operations CalculationTitle: Simulatg the Effect on Criticality of Simultaneous Matrix Degradation and Assembly Collapsefor the 21 PWR Waste PackageDocument Identifier, CAI-EBS-NU-00002 REV 00 Page 25 of 30

---l~c Narnt Date Time She_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ~(byt s)

=n4S40c 08W4199 02:49 PM 42,735ru4S40eo 084bUst 02:49 PM 678,622nu4S40f 08r2/99 _ QQ:49 PM_ 42,732nu4S40fo GUAMg9 02:50 PM 678,538nu4540g ftt24__9 02:50 PM 42,747nu4S40zo M MSUU59 02:50 PM 678,408nu4S40h CF224U9i 02:50 PM = 42,759u4S40ho 0 F2:50 PM 676,408w3mw 0V24M 03:26 PM 45,313

ru3020do OW2419 03:26 PM 624,498su3020c OW224/99 333 PM< 4,15_

ru3020co 024/99 0333 PM 609,476nu32f OM S 03:33 PM 44,121

* ni3S2Ofo 082499 03:33 PM 608,428ru3 Oat" 03:33 PM - 44,121ru02g OU2419 03:33 PM WOMru3020h 009709 03:27 PM 34,020ru302Oho 0824/99 1 03 27 PM 488,177MOM____2 P499 03:27 PM 4S313_ _

n4O3Sdo 03:27 PM 624,443ni403Sc 08*4199 03:33 PM 44,125ru4O35eo V2499 03:33 PM 609,517wr4033 0884/99 03 33 PM 44,121

_r403Sfo - 018499 03.34 PM 608,474nu4 g CV2499 03:34 PM 44,121403 o 0V2499 _ 03:34 PM 06908*n4035h 0V24799 03:27 PM 33,372ru403Sho 0124J99 03:27 PM 488,259ru4S40d 082499 03 27 PM 44,557

ru4S40do O08W 03:27 PM 624w_ _ 0824199 03:34 PM 43,388

zu4S40eo 0 99 03:34 PM 609,610ru4540f OV24199 0334 PM 43,383MUM________ 0V24/99 03:34 PM 608,494u4540g 08099 03:34 PM 43,383454jo- 0 03:34 PM 606903u4S40h II24/99 03:28 PM 33 211u4S40ho 08 9 03:28 PM 48,2233020aa 08/24199 03:01 PM 42,7193020aao 024f99 03:01 PM 61129930Qs 08n499 03:01 PM 42,9073020abo 0824/99 03:01 PM 610,5273020ac 08849 03:01 PM 42,9073020aw 0824/99 03:01 PM 6095693020ad OW24/99 03:01 PM 429033020ado 0__499 03:01 PM 60,5693020ae 0824/99 03:01 PM 42,9033020a 0849 03:01 PM 607.1323020af W-24-99 03:01 PM 42,9033Q20afo 08f2U99 03:01 PM 605,249

Waste Package Operations - Calculation'Title: Simulating the Effect on Criicality of Simultaneous Matrx Degradation and Assembly Collapsefor the 21 PWR Waste PackageDocument Identifier; CAL-EBS-NU-0002 REV 00 Page 26 of 30

Foe Name Date Time sin_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ~~~~ ~~~(bytes)

302Oba 02/ 03:01 PM 43,9383020bao 0L?4l99 03:01 PM 611,4903020bb Of1 03.01 PM 44,12S3020bbo a 4199 03:02 PM 610,3933QQ0bc ouml 0)3.02 PZ- 4412 -3020bo__ 03.02 PM 609,0073020W 08D4199 ~ 03-02 PM 44,1213020bdo MUMW9 03:02 PM 607,9573020be _ V24/U99 03-02 PM 44,121

3020beoo O4/99 03:02 PM 607,0043020bf 014M 03:02 PM 44,1213020bfo MUM 03.02 PM 605,2033020ca O8V24/99 03:02 PM 43,9373020cao OVUM 03. M 611,2533020cb 08&24/99 03:02 PM 44,t2S

3020cbo 08=24199 03:02 PM 610,4943020cc 0&24l99 03:02 PM 44,125300o 03:02 PM 609rS243020ed 08)2499 03 P 44.121

3020cdo 08t24f99 03:02 PM 608,6103Q2Ce OVUM 03:02 PM 44,1213020ceo& 03.02 PM 606X9573020cf V0324/99 0302 PM44,121

3Q20cfo 0824/99 03:02 PM 605,2983024da 0824f99 03:31 PM 44,121

3020dao O-24J99 03:31 PM 608,9523020db 012499 03:31 PM 44,121

3020dbo 084f99 03:32 PM 610,44030Q0dc 08f24f99 03 32 PM 44,121

3020dco O2499 03-32 PM69,S33020dd 0824/99 03.32 PM 44,119

3Q20ddo 08f2499 03:32 PM 608,4763020dc 08t2499032 PM 44,119

3020deo 0V24199 03:32 PM 606,855302df 08499 03:32 PM 44,1193020dfo OV24t99 0332 PM 60,2023020cs 0824f99 03 03 PM 431373020cao - V24/99 03:03 PM 611,3S33020CD 0V24/99 03 03PM 44,1253020ebo 084f99 03:03 PM 610,6413020e 0&4i99 03:03 PM 44,1213020eo 08MM 03.e03 PM 6W,6243020ed MUM 03:03 PM 44,1213020edo 08124f99 03 03 PM 608,47530Q0ce 824199 03:03 PM 44,1213020eoo 08/24/99 03 03 PM 606,9513020cf _: 03:03 PM 44,121

3020cfo 084199 03:03 PM 605,2023024h 08f24)99 03.03 PM 33,839

3020fao 08f24f99 03:03 PM 494,127

-

VW-ae4a la- ,adnn4a.foina4niV )~A ~ WF~ 51A fi~lomlof;nrnTsV :a 541ff~r pVxw" 4,9S,,

Tile: Simuling the Effect on Criticality of Simultaneous Matrix Degadation and Assembly Collapsefor the 21 PWR Waste PackageDocument Identifier: CALBS-NU-000002 REV 00 Page 27 f 30

File me Date Time Sie__ _.__ .___ _ ,___ (b*1e)

3020Ft 02W499 03:03 PM 34.0273020fbo 081499 0304 PM 493,6793020Sc 081249 03:04 PM 34,0273020foo 0 M" 03:04 PM 492,6673020(d RPIiM* 03.04 PM 34,023302"fdo 084799 03:04 PM 491,7143020fe 08a4M 03:04 PM 34,024

3020fo U24 03:04 PM 490,13530W 0&24/99 03:04 PM 34,0233020ffo .24199 03:04 PM 488,129403Sa 08a4/99 0 04 PM 42,711

403Saao O8_ _ 03:04 PM 611,3404035&Sb MUM 03:04 PM 42,8994035abo 0V499 03:04 PM 610,480403Sac OVW499 03:04 PM 42,899

403Saco O 4W99 03:04 PM 60,7364035ad 782419 03:04 PM 42,t95

403Sado 0&2499 03:04 PM 608,5674035ae 0=49 03:04 PM 42,895

403Saeo - OMMJ9 0.04 FM 606,948403Sf 49 .0304 PM 42895403Sfo osnuss 03:05 PM 605,342403Sba OV24/99 03:0S PM 4,3

403bao 01 03:05 PM 611,3184035bb -ii s 03.05 PM 44,12S403Sbbo OL124/99 03:05 PM 610,334035bc 0onw 03 0SPM ~ 44,US5

4035bco. oV24199 03:05 PM 609,521403Sbd MUM7ZT 03:05 PM 4,12140353o- osn419 03 os PM 608,521403Sbe 08n4199 03:05 PM 44121

4035beo 0&24/99 030os PM 606,90e4035bf & 24/99 0_03 os PM 44.121403Sbo oW4199 03.05 PM 60S,2434035tz 0&24/9 03:0S PM 43,937403Scao U824/99 - 03:0 PM 61 1,245 403Scb UO8470 - 03.0S PM 44.125403Rceo 04799 03:06 PM 610,345403Scc oW4199 0oS PM 44,121

403Scco 0_4_99 0305 PM_ 609,614035dd o 03.06 PM 44,1214035cto 0&24/99 03.% PM 609,4204035ce URN419 03:06 PM ".1l21403Sceo - 0n4/99 03:06 PM 606,902403Scf 0&24/99 006 PM 44,1214035cf6 08R24/99 03:06 PM 60S,20COMAd OV24/99 03:32 PM .-U. l20~403Sdao OUP24/99 . 03 32 PM 608,944.403Sdb OsRVOs 0332 PM 44035dbo _ _24_99 032 M 610,440

Waste Packlne Opnrations CalculationTitle: Simulating the Effect bn Criticality of Simultaneous Matrix Degradaion and Assembly Collapsefor the 21 PWR Waste PackageDocument Identifier: CAL.EBS-NU-000002 REV 00 Page 28 of 30

File Name Date Time Sie_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ~~~~(byte)

4035dc 08&24/99 03:32 PM 44,121403Sdso 08)24-/99 03 32 P M 609,516403Sdd - W M 03 32 PM 44,119403Sddo 082499 03 32 PM 608,4764035de 0&24/99 03 32 PM 44,119403Sdeo -024199 03:32 PM 606,997403Sdf 1W499 03:32 PM .44,119403Sdo 0/2499 0332 P M 605,203403Se i8499 03:06 PM 43,937

403Scao 0I41F9 03.06 611,443403Seb 08/24/99 0306 PM 44,12S403Sebo OV4/99 03.06 PM 610,44S4035ec iU24l9 03:06 PM 44,125

403Seco _ 0824/99 03:06 PM 609,516403Sed i 03:06 PM 44,121403Sedo 08*4-i9 03 07 PM 608,4754035ee 08I1 49 03:07 PM 44,121

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