ML17041A443
| ML17041A443 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 02/10/2017 |
| From: | Fisher M J Omaha Public Power District |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17044A062 | List: |
| References | |
| CAC MF9067, LIC-17-0024 | |
| Download: ML17041A443 (150) | |
Text
{{#Wiki_filter:Withhold from Public Disclosure under 10 CFR 2.390 Omaha Public Power District LIC-17-0024 February 10, 2017 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
References:
Fort Calhoun Station, Unit No. 1 Renewed Facility Operating License No. DPR-40 NRC Docket No. 50-285 10 CFR 50.12 10 CFR 50.47 1 0 CFR 50, Appendix E 1. Letter from OPPD (S.M. Marik) to USNRC (Document Control Desk), "Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E," Dated December 16, 2016 (LIC-16-01
- 09) (ML 16356A578)
- 2. Letter from USNRC (J. Kim) to OPPD (M.J. Fisher), Fort Calhoun Station, Unit No. 1 -Supplemental Information Needed For Acceptance Of Requested Licensing Action RE: Exemptions from 10 CFR 50.47 and 10 CFR Part 50, Appendix E (CAC NO. MF9067)
Subject:
Supplemental Information Needed For Acceptance of Requested Licensing Action RE: Fort Calhoun Station Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E (CAC NO. MF9067) Reference 1 from the Omaha Public Power District (OPPD requested exemptions from portions of Sections 50.47(b) and 50.47(c)(2) of Title 10 of the Code of Federal Regulations (10 CFR), and 10 CFR Part 50, Appendix E for the Fort Calhoun Station, Unit No. 1 (FCS). The proposed exemptions would allow FCS to reduce emergency planning requirements consistent with the permanently defueled condition of the station. Reference 2 from the USNRC requested additional information from OPPD in order to make the application complete. ENCLOSURE 1 CONTAINS INFORMATION BEING WITHHELD FROM PUBLIC DISCLOSURE PER 10 CFR 2.390. UPON SEPARATION, THIS LETTER IS DECONTROLLED 444 South 16th Street Mall* Omaha, NE 68102-2247 U. S. Nuclear Regulatory Commission LIC-17-0024 Page 2 As requested, Fort Calhoun Station is submitting the following additional information in support of the Exemption requested in Reference
- 1. There are no new regulatory commitments contained in this submittal.
If you have any questions or require additional information, please contact Mr. Bradley Blome at (402) 636-3056. Respectfully, ,/J, Mary J. Fisher Senior Director Decommissioning, Fort Calhoun Station MJF/epm Enclosure 1 Fort Calhoun Station Calculation FC08514, Eighteen Month Shutdown: Hottest Assembly-Heat Load, Core Offload and Spent Fuel Pool Gamma and Neutron Source Term, PROPRIETARY Enclosure 2 Fort Calhoun Station Calculation FC08514, Eighteen Month Shutdown: Hottest Assembly-Heat Load, Core Offload and Spent Fuel Pool Gamma and Neutron Source Term, NON-PROPRIETARY Enclosure 3 Affidavit for Withholding Information Pursuant to 10 CFR 2.390 c: K. M. Kennedy, NRC Regional Administrator, Region IV J. S. Kim, NRC Senior Project S.M. Schneider, NRC Senior Resident Inspector LIC-17-0024 Enclosure1
Page 1 OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION DOCKET NUMBER 50-285 / LICENSE NUMBER CPR-40 ENCLOSURE 1 Fort Calhoun Station Calculation FC08514 Eighteen Month Shutdown: Hottest Assembly-Heat Load, Core Offload and Spent Fuel Pool Gamma and Neutron Source Term PROPRIETARY
THIS ENCLOSURE (1) CONTAINS INFORMATION BEING WITHHELD FROM PUBLIC DISCLOSU RE PER 10 CFR 2.390. UPON SEPARATION, THIS LE TTER IS DECONTROLLED LIC-17-0024 Enclosure 2
Page 1 OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION DOCKET NUMBER 50-285 / LICENSE NUMBER CPR-40 ENCLOSURE 2 Fort Calhoun Station Calculation FC08514 Eighteen Month Shutdown: Hottest Assembly-Heat Load, Core Offload and Spent Fuel Pool Gamma and Neutron Source Term NON-PROPRIETARY
Fort Calhoun StationCALCULATION SHEET FC08514 Revision 0 P I ofS Design Analysis I Last Page No.6 attachment 10.6 paqe 25 Analysis No.: , FCO8514 Revision: , 0 Major ! Minor E Title:' Eighteen Month Shutdown: Hottest Assembly-Heat Load, Core Offload and Spent Fuel Pool Gamma and Neutron Source Term EC/ECR No., . FA L9-Qb9 Revision: , Station(s):, FCS Unit No.: a l Discipline:, RADDescrip. Code/Keyword: ,o SFP Safety/QA Class: ,, Non-Safety Related System Code: ,, Structure: ,, Spent Fuel Pool Component(s):'o CONTROLLED DOCUMENT REFERENCES Document No.:From/ToDocument No.: From/To FC08424FromEA08-034 From FC07586 From TDB-1il.1 From TDB-I.A.2FromEA08-017 From EA16-023FromEA15-014 From EA07-003FromEAo9-046 From EA05-020 From EA11-024 From EA10-013FromEA14-006 From TDB-I.B-1FromEAo8-001 From EA15-022 From TDB-I.8.5 From ls this Design Analysis Safeguards tnformation? ,. Yes E No I lf yes, see SY-AA-101-106 Does this Design Analysis contain Unverified Assumptions? ,7 Yes E No I lf yes, ATI/AR#' _This Design Analysis SUPERCEDES: ,' N/A in its entirety. Description of Revision (list changed pages when all pages of original analysis were not changed): ,, This is a new calculation Preparer: .Jan Bostelman, P. E.)' i^n-{* l/,^,* ultlsa Method of Review:,, Reviewer:, Detailed Review ffiSteve Gebers, CHP ATTACHTUENT 1 Design Analysis Cover Sheet L Fort Calhoun Station CALCULATION SHEET FC08514 Revision 0 2 (For Extemal Anatyses only) EXtgfnal Approver:
- Exelon Reviewer:
rulndependent 3d Party Review Exelon Approver:,, Fort Calhoun Station CALCULATION SHEET FC08514 Revision 0 Paqe 3 Table of Contents Contents 1.0 Purpose and Scope .......,..52.0 lnputs....... ........7 2.1 Basic FuelAssembly Data .............7 2.2 Fuel Operating Parameters ............I 2.3 Data Bases............... ......................9 2.4 Plot Options Units lnputs....... ....... 103 Assumptions........,... .........114 Reference ........15 5 Method of Analysis and Acceptance Criteria..... ................... 16 5.1 Acceptance Criteria ..... 16 5.2 Method of Analysis ......16 5.3 Gamma and Neutron Source Term Derivation Method..... ..................20
5.4 Benchmark
of ORIGEN-ARP........... .................21 6 Computer Programs. .........22
6.1 Microsoft
Software EXCEL Version 2013........ ...............22
6.2 Microsoft
Software WORD Version 20'13........ ...............22
6.3 Adobe
Acrobat DC 2015.............. .................22 6.4 Oak Ridge National Laboratories, RSICC ORIGEN-ARP (June 201 I ySCALEversion 6.1 February 2013.............. .......22 7 Numeric Analysis ..............23
7.1 Average
Uranium Values - Tables for core Offload and Spent Fue1................23 7.1.1 Core Offload Average Uranium Values ...................23 7.1.2Fuel in the Spent Fuel Poo! .......23 Fort Calhoun StationCALCULATION SHEET FC08514 Revision 0 4 7.2 Average 235U Enrichment - Tables for Core Offload and Spent Fuel......... ......24 7.3 Moderator Density Check - Tare converted to K.......... ....................25
7.4 Temperature
Conversion Comparison ........ ...................26
7.5 Average
Power Calculation - MWMTU ........27
7.6 Burnup
Adjustment - Multiplication ...............28 7.7 ORIGEN-ARP lnputs Generic ......29 7.8 Decay Heat Calculation Fuel Groups.............. ...............30
7.9 Source
Term Calculation - photons, neutrons adding and binning..................30 7.10 Scaling Approach to Other Time Points - DD1 batch assembly DD07 various time points and scaler ...........31 8 Results .............34
8.1 Decay
Heat Highest Heat Load Assembly......... ................34
8.2 Gamma
Source Term Results .........37
8.3 Neutron
Source Term Results .........398.4 Benchmark Resu1ts............. .............419 Conclusions.............. ........44
9.1 Decay
Heat for Hottest Assembly ....44 9.2 Gamma Source term ........ ...............45
9.3 Neutron
Source Term .....47 10.0 Attachments ....48 Fort Calhoun StationCALCULATION SHEET FC08514 Revision 0 Paqe 5 l-.0 Purpose and Scope Fort Calhoun Station (FCS)will be permanently shutting down prior to December 1,2016.As a result of this shutdown al! fuel from the reactor will be offloaded to the existing SpentFuel Pool (SFP). The fuel assemblies from the core to be discharged are noted in TDB-I-A.2 (Ref. 4.1). This fuel will have significant decay heat load that has to be removed via the Spent Fuel Poo! Cooling System (SFPCS). Also stored in the SFP are previouslydischarged spent fue! assemblies (SFAs) (TDB-l.B.1, Ref. 4.2) that still contain residualdecay heat and must be cooled via the SFPCS. Since it takes time for the decay heat produced from SFAs to decrease a considerable amount analyses have to be performed to evaluate the potential consequences if SFPC is not available. The consequences of a loss of SFPC are such that the pool water would heat up, potentially boi! off and then expose the SFAs to air. Without a water cooling media the fuel cladding can heat up to excessive temperatures and must be evaluated to ensure the integrity of the fuel clad remains. The Zirconium cladding around the radioactive fuel itself can be susceptible to failure if heated too quickly (i.e. without a water cooling medium) and above a certain temperature threshold. The fuel cladding provides a significant protective barrier for the plant staff and the public and as such must be maintain intact. ln order to understand the potential impact to the cladding post shutdown one aspect of this calculation will focus onderiving the decay heat produced by the fuel discharged from the reactor core that hasthe highest heat load.The first part of this calculation will be to determine the hottest assembly to be discharged from the reactor core, and what the heat output of that assembly would be '18 monthsafter shutdown or at June 1, 2018. The decay heat produced by the hottest assembly discharged from the reactor will be calculated and then utilized in subsequent calculations for Zirconium clad heating.The Iast aspect of this calculation will be to generate a source term (gamma and neutron) from the fuel being offloaded from the reactor and for the fuel that is in the pool currently (Refs. 4.1 and 4.2). When the reactor is shutdown the decay process immediately begins and the available radionuclide activities change as a function of time (decay). Thus at an 18 month point after shutdown it is not expected that the same leve! of radionuclideswould be in the fuel inventory that is discharged to the pool after reactor shutdown. This is important to understand regarding potential radioactive dose consequences if there is a loss of SFPC event. The dose to the plant staff and public is significantly different with a pool drain down event at 18 months after shutdown than immediately after reactor shutdown. So the last aspect of this calculation is to document the available source termof the fuel discharged from the reactor (assuming a full core offload prior to December 1,2016) and the subsequent decay of that fuel to June 1,2018. lmportant for dose considerations during a loss of all SFP water inventory is also the fuel that is currently in the SFP. The gamma and neutron source term for fuel stored in the pool (i.e. fuel that has decayed longer than 3 years) will be included. Fort Calhoun StationCALCULATION SHEET FC08514 Revision 0 Paqe 6 Objective The objective of this calculation is twofold: 1. Determine the hottest assembly being discharged from the reactor, heat load as a function of time after one year with one month increments in watts and BTU/hr out toat least eighteen months, after that the time point is every six months until three years.The information for the hottest assembly will be used in subsequent analysis to determine potential Zirconium clad interactions.
- 2. Determine the source term (gamma and neutron) for the fuel discharged from thereactor and that of old fuel in the SFP 18 months after plant discharge. The gammaand neutron source term willbe used in subsequent analysis to determine the potential integrated dose to the plant staff at the Control Room (CR), the Exclusion Area Boundary (EAB) and the Low Population Zone (LPZ). The gamma and neutron source term of exposed fuel (without water shielding) results in both sky shine and directexposure dose to CR personnel and at the EABILPZ boundaries.
Fort Calhoun StationCALCULATION SHEET FC08514 Revision 0 7 2.0 lnputs 2.1 Basic FuelAssembly Data Table 2.1 Fuel Basic Parameters lnformation Value Reference Assemblv Pitch (core)8.18 in 4.17 Fuel Rods oer Assemblv 176 4.17Pin Lattice CE14x 14 4.17Fuel Rod Pitch 0.58 in 4.17Reference Core Loadino - U Varies 4.17 Reference Assemblv Loadinq - UOz Varies 4.17 Reference Assemblv Loadino -U Varies 4.17 Non welded Clad Lenoth 6.2 in 4.17Fuel Stack Lenoth 129.3 in 4.17 Nominal Pellet OD 0.3805 in 4.17Nominal Clad OD 0.440 in 4.17Nominal Clad lD 0.387 in 4.17 Guide Tube lD 1.035 in 4-17Guide Tube OD 1.115 in 4.17 Nominal Fuel Pellet Densitv 96%4.17 Power oer MTU Varies 4.17 Claddino Material M5 4.17 Guide Tube Material (without sleeves)M5 4.17 Clad Material Composition-M5 (in percent by material)ln reference document 4.17 Nominal \ io/o2351)Varies by fuel desiqn 4.17Reactor Coolant System: Taw 567.6 F 4.15,4.17 Fuel Pin temperature 839.5 K 4.17 Enriched Pellet Dish and Chamfer Volume 0.2o/o 4.17 Blanketed Pellet Dish. and Chamfer Volume O.82o/o 4.17 Fort Calhoun Station CALCULATION SHEET FC08514 Revision 0 Page 8 Stack Density blanket fuel Varies by fuel design TOOl-BE-16-0PPO-001 T bl 2 2 ORIGEN ARP PWR F I D a e -ue estgn 10 *peratmg D at a c ompanson to FCSS ipeCIIC ORIGEN-Assembly ARP/CE lattice Model 14x14 FCS specific design Notes TOOI-BE-16-0PPD-001 enrichments vary and are within Enrichments the ORIGEN *wt% 235U} 1.5-6 database TOOI-BE-16-0PP0-001 Maximum Burnup cross sections run for 58,500 which aligns well burn up with FCS specific with 6% uncertainty, TOOI-BE-16-0PPO-(MWO/kgU) 72 55.041 maximum 001 confirms 6% uncertainty to be applied No. rods per assembly 176 176 TOOI-BE-16-0PP0-001 AREVA Draw i ng 02-5038187A1, Revision 1, "Guide Tube," no. water holes s 5 rebruary 2006. rod pitch (em) 1.473 1.4732 .58in
- 2.54 em/in calculated, TOOI-BE-16-0PP0-001 Assembly pitch (em) 20.78 2o.nn 8.18 in
- 2.54 em/in calculated, TODI*BE-16-0PPD
-001 Fuel Rod Data fuel density (g/cm 3) 10.41 10.4143 TOOI-BE-16-0PPD-001 pellet diameter .3805 in* 2.54 em/in calculated, TODI-BE-OPPD-001 is (em) 0.968 0.96647 incorrect 1% Nb, .14% 0, .00225% Zircaloy* S, remainder clad material 4 MS Zr TOOI-B£-16-0PP0-001 clad inner diameter (em) 0.985 0.98298 .387 in*2.54 em/in calculated, TOOI*BE-16-0PPD-001 clad outer diameter (em) 1.118 1.1176 .44in*2.54 em/in calculated, TOOI-BE-16-0PPD-001 fuel temperature (*K) 873 839.5 TODI-BE-16-0PPD-001 clad temperature see attached hottest rod shows the Tclad well within the value used, (*K) 620 output the average would be reasonable as proposed Guide tube data inner radius 1.035in*2.54/2 em/in radius calculated, TOOI-BE-16-(em) 1.314 1.31445 OPP0-001 outer radius 1.115 in*2.54/2 em/in radius calculated, TODI*BE-16-(em) 1.416 1.41605 OPP0-001 1% Nb, .14% Table M8.2.5 of SCALE Manual identifies the composition guide tube Zircaloy-0, .00225% of Zircaloy-4 to be: Zr 98.23%, Sn 1.45%, Fe .21%, Cr .1%, material 4 MS S, remainder Hf .01%, 00.09% FC08514 , RO EC 68969 8 Fort Calhoun Station CALCULATION SHEET FC08514 Moderator data average density g/cm3l 0.7332 0.7314 average bo r on concentrat i on (ppm) 331 600 moderator temperature (*I() 570 570.706 2.2 Fuel O perating Paramet ers 2.2.1 Fuel Clad Temperature-620 OK 2.2.2 Moderator Temperature-570 OK 2.2.3 Operating Power Level-1500 MWt 2.2.4 Power History -100% Revision 0 Page 9 Zr The difference on fuel clad material is that M5 contains fewer trace elements than Zi rc-4 and has Niob i um in it. MS has 98.86% Zr whereas Zirc-4 has about 98.23% for long term calculations this difference is not considered significant assumed at TDB 111.1 indicates Tave at 567.6F , Ope r ating Pressure is at 2100 psig, 2100 psig, calculated density appro)(lmately .7314 , TOOl-567.6 F BE-16-0PPD-001 A delta of 300 ppm boron does not have si gnificant di fference on the cross section for the typ i cal CE 14xl4. it would have significant impact for criticality KENO SCALE calculations , but not for decay heat. CASMO design informat i on TDB 11 1.1, Tave = 567.6 F, converted to K equals 570.706K 2.2.5 Operating Specific Power (MW/MTU) varies by fuel loading assumed to be constant through entire modeled operating cycle. 2.2.6 Average Boron Concentration-331 ppm (Ref. 4.19) 2.2.7 Enrichments (wt% 235 U)-varies with Fuel Assembly see Table 2.2.8 Maximum Burnup (MWd/kgU)- varies with Fuel Assembly See Table and EA16-023 Core Projections for Cycle 28 Coastdown (Ref. 4.5) 2.2.9 Burnup Uncertainty-6°/o (Refs. 4.22, 4.25 , 4.26, 4.27, 4.28) EA08-001 2.2.10 Number of Cycles of Operation-3 (with exception to Core Batch DO, 4 cycles assumed) 2.2.11 Number of Assemblies in Core-133 (Ref. 4.1) as of 8/31/2016 2.3 Data Bases 2.3.1 Neutron Group Structure by Energy Group-44 Group ENDF5 See Table 2.3.2 Gamma Group Structure by Energy Group-18 Group ORIGEN2 See Table 2.3.3 Decay (Alpha, n)-U02 2.3.4 Decay Bremsstrahlung-U02 2.3.5 Gamma Library-Total (Light Elements, Actinides and Fission Products)
2.3.6 Libraries
per cycle-Default 1 FC08514, RO EC 68969 9 Fort Calhoun StationCALCULATION SHEET FC08514 Revision 0 10 2.4 Plot Options Units lnputs 2.4.1 Gamma Spectra - Photons/s/mev
2.4.2 Neutron
Spectra - Neutrons/s/mev
2.4.3 Nuclides
- watts Fort Calhoun Station CALCULATION SHEET FC08514 Revision 0 P 11 3.1 AssumptionsThe highest burnup and 23sU enriched assembly was used for each fuel sub group in thereactor core to determine the "hottest fuel assembly". Basis: The highest burnup fuel assembly from each fuel sub batch is used because it wil!generate the highest decay heat, and the largest gamma and neutron source term. This assumption is a best estimate value and does not require further verification. The highest burnup represents a best estimate number from the GARDEL core projections, is a bounding number for the assembly. The thirteen assembly sub batches (DD1 , DD2, DD3,EE1, EE2, EE3, FF1 , FF2, FF3, FF4, GG1, GG2, GG3, and Ref. 4.14) were evaluated and the pattern of higher burnups yielding higher decay heats and gamma/neutron source terms was documented. This pattern also represented use of the highest enriched assemblies as well. As such, since thirteen fuel sub batches were modeled for the core they are representative and bounding for offloaded core decay heat and source term generation.44 ENDF5 Neutron Energy Group (energy bins) was assumed.Basis: The 44 ENDF5 is a standard neutron energy group from the ENDF/B cross section library in the SCALE 6.1 code package. ORIGEN-ARP has a default of 27 group for neutrons, but for finer resolution the standard 44 group from SCALE 6.1 code was used for this best estimate calculation. FC07586 utilized the 44 neutron group and as such, abenchmark comparison could be performed as well related to the neutron calculations. The SCALE package 44 neutron group ENDF/B-V library is supplemented with select ENDF/B-VI data which includes some additional materials that are considered light elements, and Europium. Typical shielding calculations use the broad group library (27 group neutron) for adjoint discrete ordinate calculations with biased source distributions in Monte Carlo shielding calculations that have to use MAVRIC shielding analysis.However, per SCALE manual the broad and fine group libraries have the same dose factor information. As such, the utilization of a finer group library for further downstreamMonte Carlo calculations would still have the same dose factor information. lt was used in this calculation in order to perform benchmark assessments. 18 ORIGEN2 Gamma Energy Group (energy bins) was assumed.Basis: The 18 energy group from ORIGEN2 was used as it is slightly more conservative for decay heat calculations than the standard 18 group SCALES in ORIGEN-ARP.FC07586 utilized the ORIGEN2 18 group and as such benchmark calculations were able to be performed side by side against FC07586 from the full ORIGEN-S assembly crosssection calculation. The use of an 18 group is applicable versus higher groupings (i.e.finer energy bin resolutions). Eighteen group gamma or photons is typical for decay calculations. A continuous 100% power level was assumed for the calculations in ORIGEN-ARP. Basis: Use of a 100o/o power level for 3 cycles is conservative slightly as it drives specific power density and thus, a higher decay heat and source term production for gammas andneutrons. AIso this assumption then discounts any shutdown in between cycles which would have some short term decay occurring (i.e. 30-60 days). It is assumed that the reactor moderator temperature and fuel cladding temperature remain constant during the 3 reactor operating cycles (4 for batch DD1).3.2 3.3 3.4 3.5 3.6 3.7 Fort Calhoun StationCALCULATION SHEET FC08514 Revision 0 12 Basis: Slight differences in clad and moderator temperature would be important for transient conditions, but for Iong term steady state operations to drive fission product generation this would not need to be evaluated. Small variances in moderator and clad temperature would not impact the overall cross section library for this type of fuel in steady state operation. Variation in moderator and clad temperatures would however, be important for calculating axial burnup profiles necessary for safety analyses related to storage rack and cask loading criticality. The effective absorption cross section of 235U as a function of water moderator density between 0.7 and 0.8 g/cm3 is flat and as such related to fission process has very little impact. lt is important though related tointerpolation of cross section generation. Axial moderator density would be important for calculating axia! burnup dependent credits for criticality assessments. This also would be part of axia! clad temperature material impacts related to burnup credits. This calculationdoes not perform burnup credit assessments and as such, the fixed moderator densityversus variable is utilized in ORIGEN-ARP. The SCALE manual also indicates, "Waterdensity variation has typically not been included for PWR libraries developed at ORNLbecause of the relatively small variation in pressurized water reactors."The automated irradiation and decay process was used in ORIGEN-ARP. Basis: ORIGEN-ARP has the automatic capability to default and track irradiation of each cycle of operation based upon the given set burnup. The code then cumulatively tracksall irradiation time from the start of each cycle and based upon how many cycles are input to be calculated. The decay function is performed automatically upon cycle completion to the time point chosen by the analyst. The decay cumulative time points can be picked byanalyst or time increments can be automated using a common rule of thirds (the rule of thirds time step increment is used if possible to follow the nuclides exponential decay). Burnup Uncertainty for all fuel evaluated is applied in the positive direction, the burnup numbers from GARDEL are multiplied by 1.06 (6% uncertainty). Basis: EA08-001 identifies that a 6% uncertainty is to be applied for GARDELmeasurement uncertainty, unless an NRC submittal is docketed to change that value.The application of the uncertainty in the positive direction ensures a higher burnupnumber is used which results in higher decay heat per assembly and in a gamma/neutronsource term. The application of this uncertainty is on burnup only and it is also applied in procedures RE-ST-DFS-0001 and RE-ST-RX-0007 for criticality applications in theopposite direction. From documents referenced EA08-001, the only way to remove this uncertainty would be through an NRC submittal to credit actual GARDEL measurement uncertainty which is only slightly less than that required to be applied (i.e.4.22% versus6%). To reduce or remove the uncertainty an NRC submittalwould be required. The radia!peaking factor measurement uncertainty was evaluated and approved by the NRC in License Change 84-02,84-02 Revision 1, Technical Specification Amendment 77 dated April 26, 1984 (see pages 48 and 64). The methodology document reviewed and approved regarding the uncertainty is CENPD-153-P, Revision 1-P-A, which is alsoidentified in USAR section 3.4.7.2, and USAR specific reference 3-17. This measurement uncertainty approvalwas discussed in NRC letter NRC-85-0267, daled August 26, 1985.Radial peaking is not applied or assumed.Basis: Radial peaking is not applied since the direct output by assembly is used from theGARDEL core online measurement system or that documented in the Special Nuclear 3.8 Fort Calhoun StationCALCULATION SHEET FC08514 Revision 0 13 Material inventory. Therefore, since the direct GARDEL measurement is used with its uncertainty, a radial peaking factor for rod or assembly is not required to be provided. The highest burnup by sub batch is used and then multiplied by the number of assemblies in that batch to be bounding versus applying an overall peaking factor.3.9 Constant specific power is applied throughout the core operating cycle.Basis: this is more conservative slightly as it will force calculation to burn al! the available enriched uranium at this specific power leve! and is a function of the total Uraniumavailable and by percentage of enrichment as well.3.10 The pool is assumed to contain 944 spent fuel assemblies at time of shutdown assumed to be December 1,2016.811 assemblies are currently in the pool (TDB-1.B.1), and 133 are from core discharge (TDB-1.A.2). The 811 assemblies are reported in the Special Nuclear Material inventory list attached. lt is assumed that this information is still representative from FC08424 (Ref. 4.16) since no fuel has been offloaded to canisters (TDB-1.B.5) since that calculation was approved. lt is assumed that the old fuel can be grouped into batches based upon discharge date to the SFP. The SNM inventory providesthe actual discharge date which is then used for the decay heat and source term grouping.It is assumed that for old fuel the worst case burnup and enriched assembly is used to represent all fuel discharged on that date. This is considered conservative for the old fuel decay heat and source term calculation. Basis: Only the actual fuel count is utilized for this calculation to be best estimate. The assumption about using the highest burnup and enrichment for each old fuel batch discharged is conservative as it will calculate a higher decay heat and a fission product source term. AIso the activation of Iight elements and actinide production will be higheras well which also contribute to the gamma source term, but not as much to the decay heat. The mass of potential activation products (i.e. mostly from end fittings is small compared to the fissile material mass that results in the fission product inventory. The ORIGEN-ARP cases were run to include the actual CE 14 x 14 fuel type which included light elements and activation products, but was not modeled explicitly with AREVA 14 x14 assembly. The SNM inventory was provided by Exelon Corporation, March 24,2015 (TracWorks Version 3.20.2 through February 28,2015, Attachment 10.2). The FCS Cycle 28 new fuel receipts from up to March 2015 had been included along with the exposure and isotopics through February 28,2015.3.11 The Average Uranium mass of the assembly used is from depletion and designcalculations and varies with each fuel batch evaluated. Basis: The average uranium loading per assembly was taken as is from the various engineering analyses and Special Nuclear Material inventory as is without any adjustment. There are variations between each assembly due to poison loading and enrichment, as such the average uranium per sub batch is used as noted in the EAs referenced. 3.12Scaling of gamma and neutron sources will be assumed to calculate source terms at different time points from the eighteen month decay.Basis: Scaling can be applied to gamma and neutron source terms at different time pointsof decay since the dose relationship for absorbed dose is strictly a dependent function of the gamma/neutron flux as noted in Radiation Dosimetry equation 6.9 page 143. Gamma (or neutron) flux is the only variable that would change when calculating an exposure rate Fort Calhoun Station CALCULATION SHEET FC08514 Revision 0 P 14for tissue. The attenuation/self absorbsion of materials would hold constant, and also thedensity of materials. The only variable in this aspect is flux, which can then linearly scalethe dose. That is if a different flux is calculated at a different time point it can be linearlyscaled by using a multiplier. Therefore, one calculation will be performed to determine the overall gamma and neutron source term at eighteen months. This value will then be scaled at different time point for further dose analyses versus running ORIGEN-ARP cases for every distinct time point. The gamma and neutron source term scaling will be performed using the highest burnup assembly to be conservative. Cases are run for thisassembly at different decay time points in order to develop the scaler factor. 3.13 Fuel Rod Component Materials are assumed based upon the ORIGEN-ARP typical CE 14 x 14 model.Basis: Regarding the ORIGEN-ARP model, the top and bottom nozzles and end fittings of the fuel assembly are not explicitly modeled in the decay heat analysis. That is to say the ORIGEN-ARP CE 14 x 14 model is not changed for the settings included regardingthe fuel structure. Typically stainless steel and lnconelgenerate heat only from activation products. They are considered in the total heat generated output in ORIGEN-ARP output options, i.e. (light elements, actinides and fission products) but they are not explicitly modeled. As shown in Ref. 4.23 the AREVA calculation shows that light element heat production is relatively low in comparison to actinides and fission products (Tables 5-4 through 5-7 ol that calculation). FC07586 (Ref. . ) page 29 also noted that light element activation (from top end fittings, plenum, and bottom end fittings) accounts for insignificant contribution to energy from neutron and gamma radiation. Therefore it is acceptable to utilize the standard CE 14 x 14 fuel assembly including its materials related to light element activation.3.14 The Average Power per metric ton uranium is assumed to be uniform for every assembly. Basis: ORIGEN-ARP uses the unit of Power per mass for an assembly to perform itscross sectional interpolations. The power per uranium mass per assembly is in units of MW per Metric Ton Uranium (MTU). lt is assumed that every assembly in the reactor core and those in the pool have been burned with a uniform power history 100o/o, and that each assembly "burns" uniformly for power distribution. ln the norma! course of reactoroperations some assemblies have a higher power function than others due to core pattern Ioading. But overall discounting axial distributions to operate a core with large distinctions in power density per assembly would cause power tilts, shifts that could be outside oftechnical specifications. So each assembly power worth would be represented as 1500 M\ ,V133 (core output limiU# of assemblies) or 11.2782 MWUassembly. Fort Calhoun Station CALCULATION SHEET FC08514 Revision 0 Paqe 15 4 References 4.1 TDB-I.A.2 FuelAssembly and lnserts for Cycle 28, R28, page 2 4.2 TDB-!.B.1 , Spent Fuel Pool Layout and FH-12 Coordinates, R72 4.3 ORIGEN-ARP-Automatic Rapid Processing for Spent Fuel Depletion, Decay and Source Term Analysis, ORNL/TM-2005/39, Version 6.1, June 2011 4.4 FC07586, Maximum Gamma Energy Deposition rates in Spent Fue! Storage Pool Walls and Floor with EPU Spent Fuel Assemblies, Rev. 0 4.5 EA16-023, Cycle 28 Beyond End of Life Exposure Power and Temperature Coastdown, Rev.0 4.6 EA05-020, FuelTemperature Correlation Generation with lnterpin-3, Rev. 0 4.7 EA07-003, Cycle 25 Design Depletions, Rev. 0 4.8 EA10-013, Cycle 27 Design Depletions, Rev.0 4.9 EA08-034, Cycle 26 Design Depletions, Rev. 0 4.10 EA15-014, Cycle 28 As Built Depletions and GARDEL Update Preparation, Rev. 0 4.11 EA09-046, Cycle 26 As-Built Depletions and GARDEL Update Preparation, Rev. 1 4.12 EA11-024, Cycle 27 As-Built Depletions and GARDEL Update Preparation, Rev. 2 4.13 EA14-006, Cycle 28 Design Depletions, Rev. 0 4.14 EA08-017, Cycle 25 CECOR Coefficient Generation, Rev. 04.15 TDB-lll.1, Tare Program, R14 4.16 FC08424, Spent Fuel PoolTime to Boil and Boiloff Rate Curves, Rev. 0 4.17 TODI-BE-16-OPPD-001 , Revision 1 , August 15, 20164.18 TDB-1.B.5, R2, pages 4 through 13.4.19 SCALE 6.1 Manual.4.20 Radiation Dosimetry, Cember page 143, equation 6.9 4.21 Southern California Edison, Docket No. 50-206, 50-361, and 72-041 Response toRequest for Additional lnformation Regarding Emergency, Planning Exemption request San Onofre Nuclear Generation Station, Units 1, 2, 3 and ISFSI, page 25 4.22 EA08-001, GARDEL Core Monitoring Code lmplementation, Rev. 0 4.23 FC07688, Rev. draft, Ft. Calhoun Station Unit 1 EPU Spent Fuel pool Decay Heat Calculation, AREVA Document No. 32-9128125-000, AREVA Letter AREVA-11-01908, dated July 28, 2Oll Transmittal of Project Deliverable 4.24 EA15-022, Cycle 29 Neutronics input to Safety Analysis, Rev. 0.4.25 EA-06-042, evaluation of Pin Peaking Uncertainty with the GARDEL Core Monitoring System, Rev.04.26 NRC License Change 84-02,84-02 Revision 1, Technical Specification Amendment 77,Section 3.3, pages 48 and 64, April 26,1984 4.27 USAR Sections 3.4 and 3.9, revisions 36 and 19 respectiv.ely 4.28 NRC-85-0267, August 26, 1985 5.1.Fort Calhoun StationCALCULATION SHEET FC08514 Revision 0 16 Method of Analysis and Acceptance CriteriaAcceptance Criteria The purpose of this calculation is to determine the following as a minimum 1) peak decayheat as a function of time from one year to eighteen months for one assembly, and
- 2) the gamma and neutron source term from fuel in the spent fuel pool at eighteen months, scaling for other time points as necessary. The results of this calculation are to be used in a subsequent analysis to determine zirconium fuel clad interactions, and dose to plantpersonnel (Control Room) and at EAB and LPZ boundaries.
As such, there are no acceptance criteria for this calculation. Method of Analysis5.2.1 ldentification of Computer Program ORIGEN-ARP/ORIGEN-S ORIGEN-ARP/ORIGEN-S is part of the SCALE 6.1 depletion analysis sequence and was used in this calculation to perform point depletion calculations with the ORIGEN-S code.ORIGEN-ARP was utilized with the CE 14 x 14 pre generated cross section libraries since the fue! design and operating conditions for FCS fuel were established to be bounded within the code database typical fuel type. ln the analysis scheme, time dependent materialconcentrations are solved using the ORIGEN-S isotope and depletion and decay code. Further details about ORIGEN-ARP are provided in Reference 4.3 throughout. ORIGEN-ARP was used to generate the decay heat for fuel assemblies (watts), gamma and neutron source terms for the FCS CE 14 x 14 fuel type. ORIGEN-ARP utilizes a Graphical User lnterface (GUl) to build input decks with preset fuel types. The CE 14 x 14 fuel type option was selected, and plant specific parameters for power, burnup, initial 235U enrichment, initial uranium loading, power history and cooling times were input.ORIGEN-ARP has been utilized by other licensees for the same applications, i.e. Ref.4.21.ORIGEN-ARP/ORIGEN-S was used to derive the gamma and neutron source strength inunits of photons/neutrons per second and energy spectrum. The Generic PWR assembly parameters from Table D1.A.2 of ORIGEN-ARP Reference Manual for a CE 14 x 14 assembly were utilized. Sample input file is provided in Attachment 10.5. The 18 group gamma ORIGEN2 and 44 ENDF/S group neutron energy structures were used to be explained further later.The ORIGEN-ARP/ORIGEN-S computer code was run to obtain the time dependent gamma and neutron radiation source terms as noted above to be used in the downstream dose calculations. Separate ORIGEN-ARP/ORIGEN-S runs were made to obtain decayheat output in watts for determining the hottest fuel assembly being offloaded from the core. The separate ORIGEN-ARP/ORIGEN-S runs for the decay heat calculations 5.2 Fort Calhoun StationCALCULATION SHEET FC08514 Revision 0 17included fission products, light elements in the active fuel region, and actinides. Each run for the gamma and neutron source term looked at separate batches of fuel type (i.e.enrichment, burnup and uranium loading) and various decay times. Each run for evaluating the "hottest" assembly (watts) only looked at fuel being discharged from the reactor as a function of the thirteen sub batches of fuel discharged and decay time. The input parameters such as specific power, are calculated in other sections of this document. The maximum burnup from the core operating projection map was utilized to determine the "hottest" assembly. That is the highest burnup with enrichment from eachof the thirteen sub batches in the core at August 31,2016 was used.The automated processing of irradiation and decay was utilized within ORIGEN-ARP/ORIGEN-S. ORIGEN-S input includes the energy values for the energy bins for the 18 gamma energy groups and the 44 neutron energy groups and the input includes thedecay times at which radiations source terms are to be calculated. The gamma andneutron energy bin values are the 18 ORIGEN2 gamma energy bin values and the ENDFs44 neutron energy bin values provides as an option in ORIGEN-S code package. Gamma and neutron energy bin values (MeV) are provided in the sample input deck in attachment 10.5. There are 19 gamma energy bin values in descending order and 45 neutron energy bin values in descending order. The source term in these energy bins is then utilized in further downstream calculations such as MCNP6 for dose rates. Various decay times were chosen depending upon the focus area of this calculation, i.e. hottest assembly, or gamma/neutron sou rce term.A Iist of the ORIGEN-ARP/ORIGEN-S input and output files is included in Attachment 10.5.5.2.2 Core Offload Decay Heat Overview ln order to determine the "hottest" assembly that should be modelled for further Zirconium clad interactions the thirteen sub batches of fuelin the reactorwere evaluated. The output from EA16-023 (Ref.4.5) core operating projection was utilized to screen each sub batch of fuel that was operating in the core as of August 31,2016. With the burnup projections the highest burnup for each fuel sub batch was then derived. ln terms of decay heat generation as a function of time a high burnup assembly yields normally the highest heat generation rates as well. The core map noted in TDB-1.A.2 and EA15-014 values were then used to screen the fue! operating in the core further to identify those assemblies that had the highest burnup within each fuel sub batch. The core map burnup projection is shown in Attachment 10.1.Once the highest burnup assembly was screened in for each fuel sub batch then the burnup was multiplied by the uncertainty factor that is part of the GARDEL measurement system (1.06). This multiplication of the uncertainty factor then yields higher burnups than from the raw GARDEL measurement projection. This is a conservative but required application for decay heat calculation related to the individual assembly. Radial peaking factors were not applied to burnup or power since the measured output for burnup was Fort Calhoun StationCALCULATION SHEET FC08514 Revision 0 18 used for the specific assembly batch.Once the highest burned assembly was derived for each sub batch, then it was identified if the fuel had gone through 1, 2, or 3 cycles of burn. Also the enrichment for each sub batch, and initial uranium average were identified. Lastly the number of assemblies for each sub batch of fuel in the core was identified and tabulated for further processing related to section 5.3 methods. Tables 5.1 through 5.4 show the sub batch groupings for the core offload. Table 5.1 Assembly Batch DD Assembly Batch DO GARDEL 6%Uncertainty Sub Batch DD1 DD2 DD3 Libraries Average Burnup Uranium Enrichment Burnup per Power Power Assembly (GWD/MTU) (er) wt% U235) (MWD/MTU) Cycles cycle (MWMTU) History %DD07 ss.041 388300 4.336 s8343 3 1 29.6032 100 DD23 51.803 385400 4.194 55971 3 1 29.6032 100DD33 38.204 38s800 4.001 40496 3 1 29.6032 100 Table 5.2 Assembly Batch EE Assembly BAtCh EE GARDEL 6%Uncertainty Libraries Average Sub Burnup Uranium Enrichment Burnup per Power Power Batch Assembly (GWD/MTU) (gd Wt% U23s) (MWD/MTU) Cycles cycle (MWMTU) History %EE1 EE04 52.803 389300 4.335 53825 3 1 29.3092 100 EE2 EE20 42.s45 386400 4.794 45098 3 1 29.3092 100EE3 EE32 38.52 385200 4.001 40831 3 1 293092 100 Table 5.3 Assembly Batch FF Assembly BAtCh FF Sub Batch FF1 FF2 FF3 FF4 5%U ncertainty GARDEL Burnup Uranium Assembly (GWD/MrU) (er)FF01 35.764 387300 FF09 37.436 386700 tF22 39.434 384800tF37 37.851 384800 Enrichment wt% u235)4.475 4.443 4.794 4.001 Libraries Average Burnup per Power Power (MWD/MTU) Cycles cycle (MW/MTU) History %37909.82729.310s100 396922729.3105100 418002729.3105100 401222729.310s100 Table 5.4 Assembly Batch GG Assembly BAtCh GG Sub Batch GG1 GG2 GG3 6/, Uncertainty GARDEL Libraries Average Burnup Uranium Enrichment Burnup per Power Power Assembly (GWD/MTU) (Cr) Wt% U235) (MWD/MTU) Cycles cycle (MWMTU) History %GG06 77.775 387300 3.76 18205.5 L 7 29.2128 100 GG15 76.977 38660 3.733 17995.6 1 1 29.2128 100 GG33 20.673 384800 3.355 2t973.4 1 1 29.2128 100With this screening process then the ORIGEN-ARP/ORIGEN-S runs were performed totabulate and identiff which assembly yielded the highest heat output in watts as a function of decay time. Decay times of 12, 13, 14, 15, 16, 17, 18,24,30 and 36 months were Fort Calhoun StationCALCULATION SHEET FC08514 Revision 0 19 evaluated for each fuel sub batch type and data put into an EXCEL spreadsheet for furtherranking and sorting to determine the "hottest" individual assembly as a function of cooling time.To determine the total core offload decay heat to be used by subsequent calculations. The number of assemblies in each sub group was tallied and that value was multiplied by the individual decay heat to derive the total core offload decay heat as a function of time. This information is not provided in this calculation but in subsequent calculations for further processing (FC08513, EAB Radiation Shine Dose 18 Months Post Shutdownwith the SFP Drained).5.2.3 Spent Fuel Pool OId Fue! Decay ORIGEN-ARP/ORIGEN-S was utilized to calculate fuel stored in the spent fuel pool as of December 1, 2016 (excluding core offload). The method to evaluate the "old" fuel contribution from decay was slightly different than noted above and is considered conservative. The SNM inventory for FCS was utilized to sort fuel in the SFP by discharge date. That is those assemblies noted within a certain time period for discharge to the pool were clustered as having the same discharge date. For example any fueldischarge in theApril 2015 to May 2015 timeframe were clustered as a batch of "old" fuel with a distinct discharge time point. The number of assemblies in each of these distinct discharge time points to the SFP were counted. Any fuel that had a discharge date earlier than 1999 was lumped together with this last evaluated discharge date. Screening was then performed to identify an assembly within a discharge cluster that had the highesl 23sg initial enrichment and burnup. That assembly then became therepresentative assembly for that discharge cluster of assemblies or group. The assembly parameters were then input into ORIGEN-ARP/ORIGEN-S as noted in section 5.2.2including a 60/o uncertainty on burnup. The noted enrichment, initial uranium loading and discharge date were all derived from the SNM inventory. The SFP map located in TDB-1.8.1 was also utilized to determine that the assemblies in the SNM inventory were still located within the pool versus those discharged to Dry Storage (TDB-l.B.5). Once the group assembly was identified then the cases were run for each discharged assembly group. That value which represented one assembly was then multiplied by the number of assemblies in that discharge group. This is considered conservative as some discharge groups included much lower enrichments and burnups. As such, the source term from the poolwas deliberately skewed towards being conservative and bounded. Fort Calhoun Station CALCULATION SHEET FC08514 Revision 0Paoe 20Table 5.5 Old Fuel ORIGEN-ARP Inputs Assemblv Coolins Period SNM 5% Uncertainw CoolingTime - YearsAssembly Burnup (GWD/MTU)Uranium lsr'l Enrichment Wt%u2351 Burnup (MWD/M TU)Cvcles Libraries oer cvcle Average Power{MW/MTUI Power Historv %3.t67 DD22 50.29*38s493 4 s3314 3 1 29.257 10c 7.083 BBO2 49.3s6 373428, 4.77 523li 3i 1 30.202 10c 8.5 Y031 55.274 3743L4 4.05 5859C 3i 1 30.13 10c10.083AA17 s1.s19 372053 4.255461C3 30.313 10c lt-61 YO39 44.L84 37273t3.9547503 3 L 30.2s8 10c L3.l6t Y013 44.386 373374 4.O2 47049, 3l L 30.20*10c 14.67 x013 47.767 373242 4.t9s063:3i 1 30.2t7 10c 16 T001 43.14L8 374752 4.\6 4602?3i 1 30.09s 10c 5.3 Gamma and Neutron Source Term Derivation Method The gamma and neutron source term derivation is the same as that noted above in sections 5.2.2 and 5.2.3 with exception that for the full core offload the number of assemblies in a sub batch from the core was then used as a multiplier for the representative assembly from that batch. This multiplier then was used on the gamma and neutron source term that had been derived per assembly to generate a bounding source term, this is conservative as some fuel within the sub batches had lower enrichments and burnups. This then skewed the gamma and neutron source term to beused in subsequent calculations in the conservative direction (higher dose since higher flux). The gamma and neutron source term calculations were performed to 18 months decay for each fuel type (core offload and "old" fuel in the pool). Only one time point for the fuelassembly ORIGEN-ARP/ORIGEN-S (i.e. 't8 months) was distinctly calculated for every fuel sub batch in the core and discharged to the pool.ln order to determine the impact for a shorter decay period a scaling approach wasutilized. Since the only thing that changes is the flux from the fuel this is a reasonable approach that can be used for evaluating shorter decay periods in and around the 18 month decay point. ln order to justify a scaling factor approach subsequent ORIGEN-ARP/ORIGEN-S runs were made for the hottest assembly in fuel sub batch DD1.Computer cases were run for both gamma and neutron to validate the scaling approach.Cases from 12 months to 18 months at one month increments were run to establish the change in flux versus cooling time for this hottest assembly. From those calculations then a subsequent curve fit spline in EXCEL was applied to derive an equation to represent the gamma and neutron flux as a function of cooling time. Since the hottest assembly wasmodeled this conservatively bounds any other assemblies to be considered that may havea lower heat generation profile due to burnup or enrichment. Once the curve fit equation was derived, then a multiplier was back calculated for a 14 month decay source term as an example. This multiplier was then applied to al! the core Fort Calhoun StationCALCULATION SHEET FC08514 Revision 0 P 21offload and "old" fuel for a conservatism. Certainly the "old" fuel in the poolwould not be anticipated to be sensitive to a change in 4 months as a core offload would be, but for conservatism and ease of application this was performed. The subsequent output wasthen applied in EXCEL spreadsheets forthe gamma and neutron source term to represent a scaled 14 month source term. Further discussion about this application is provided in the calculation section. The 14 month gamma and neutron source term is scaled from the 18 month calculation and is considered conservative since it was applied to all fuel batches even those stored in the pool that has had much longer decay. This scaling application can be used for other time points in between if other dose calculations are needed.5.4 Benchmark of 0RlGtN-ARP A comparison of ORIGEN-ARP Combustion Engineering (CE) type 14 x 14 fuel was performed against a previously documented FCS calculation FC07586 and draft calculation submitted to the Extended Power Uprate (EPU) project Ref. 4.23 (FC07688). This benchmark was performed to check the ORIGEN-ARP CE 14 x 14 fuel type against the FCS specific AREVA 14 x 14 fuel assembly (which is predicated upon CE 14 x 14 with subtle differences overall in clad - M5 and poison material). As noted earlier in the input section the comparison of the ORIGEN-ARP CE 14 x 14 typica! aligned with the FCS AREVA 14 x 14 fuel. Benchmarks were run to further check the ORIGEN-ARPcapability against a previously documented ORIGEN-S with SAS2H calculation. The gamma and neutron source for an assembly was checked and evaluated by running ORIGEN-ARP/ORIGEN-S and comparing results both in gamma and neutron source term. For this comparison the 18 ORIGEN2 energy group had been utilized in FC07586 and this was used for the benchmark comparison in ORIGEN-ARP. The 44 ENDFsneutron energy group was used in the FC07586 calculation and as such used in the ORIGEN-ARP run for comparison. The comparison results from this benchmark are discussed in the results section. An additional benchmark case against an AREVA calculation FC07688 was performed given a very explicit model generated for the AREVA fuel assembly in SAS2H/ORIGEN-S. Only the actinide product was compared since that calculation had utilized the ANS 5.1 method for fission product decay heat generation. For that benchmark case lhe 44 ENDF5 neutron group and the 18 cases are further discussed in the results section.ORIGEN2 group were used for comparisons. Two different fuel enrichments were compared in the AREVA benchmark. The AREVA benchmark comparison results are discussed later. Fort Calhoun StationCALCULATION SHEET FC08514 Revision 0Paoe 22 6 Computer Programs 6.1 Microsoft Software EXCEL Version 2013. General Use computer code 6.2 Microsoft Software WORD Version 201.3. General Use computer code 6.3 Adobe Acrobat DC Version 2015. Converts WORD files to .pdf format 6.4 Oak Ridge National Laboratories, RSICC ORIGEN-ARP (June 2011)/SCALE Version 6.1 February 2013. Per Procedure NCM-1 SCALE 6.1 is included in SWIMS and classified for use in this calculation. Fort Calhoun Station CALCULATION SHEET FC08514 Revision 0Paoe 23 7 Numeric Analysis 7.1 Average Uranium Values - Tables for core Offload and Spent Fuel 7.1.1. Core Offload Average Uranium ValuesThe average uranium mass was used for each sub batch of fuel evaluated. The average uranium mass from the fuel depletion analyses was utilized to derive the inputs for the ORIGEN-ARP cases for core offloaded fuel. The average uranium mass reported for eachfuel sub batch are in units of Kg and as such was converted to grams by multiplying the average mass by 1000 gr/Kg. The masses noted to be used for the core offload caseswere converted and reported below. Table 7.1 Average U ranium Mass for ORIGEN-ARP lnput FuelSub Batch Assembly Batch/Number Average Uranium Mass -Kp Average Uranium Mass -sr Core Offload DDUDDOT 388.3 388300 DD2lDD23 385.4 385400 DD3/DD33 385.8 385800 EELIEEO4 389.3 389300 EE2IEEZO 386.4 385400 EE3/EE32 385.2 385200 FFt/FFOt 387.3 387300 FtzlFFOg 386.7 386700 FF3lFF22 384.2 384200 FF4IFF37 384.8 384800 GGl/GG03 387.3 387300 GG2lGG15 385.5 385600 GG3/GG33 384.8 384800Core Offload 7 .1.2 Fuel in the Spent Fuel PoolThe average uranium mass for spent fuelwas reported in the SNM inventory list in unitesof Metric Tons of Uranium. Therefore the conversion for this unit to the desired format for ORIGEN-ARP was to multiply the SNM reported value by 1E6 gm/metric ton. As an example, the mass for Assembly AA17 was reported as 0.372057 MTU, this equates to a uranium mass of 372057 gr when applying the multiplication factor. The table below provides the converted values of Uranium mass from the SNM inventory list convertedfor ORIGEN-ARP input. Fort Calhoun Station CALCULATION SHEET FC08514 Revision 0 P 24 Table 7.2 Average Uranium Mass for ORIGEN-ARP Input by Analyzed Fuel Sub Batch Fuel Stored in the SFP Assembly Number/YearsCooled in SFP Average Uranium Mass MTU Average Uranium Mass sr DD22/3.L67 880217.083 Y03u8.s AA17l10.083 YOL3lLL.67 YO39lt3.t67 xot3lL4.67 T001/15 0.385493 0.373428 0.3743t4 0.372057 0.37273L 0.373374 0.373242 0.374752 38s493 373428 3743L4 372057 37273L 373374 373242 374752 7.2 Average 235U [nrichment -Tables for Core Offload and Spent Fuel The raw reported average enrichments by fuelsub batch for the core offload were utilized in ORIGEN-ARP input database. No conversion was necessary for the core offload calculations, values reported in Refs.4.7 through 4.13 were used as recorded, i.e. in percent 235U enrichment. These values represent the average 235U enrichment for the particular fuel sub batch or the assembly itself from the SNM list. Fort Calhoun StationCALCULATION SHEET FC08514 Revision 0 P 25 Table 7.3 Average 235U Enrichment by Assembly Evaluated Assembly Number Average 235U Enrichment %Core Offload Ref.4.7-4.13 DDOT 4.336 DD23 4.194 DD33 4.001 EEO4 4.33e EE20 4.L94 EE32 4.001 FFOl 4.475 FFO9 4.443 iF22 4.t94 FF37 4.001 GGO3 3.76 GG15 3.733 GG33 3.355 SFP SNM List DD22 4 BB02 4.77 Y031 4.05 AA17 4.25 Y013 3.96 Y039 4.O2 x013 4.L9 T001 4.L6 7.3 Moderator Density Check - T,u* converted to K Moderator Density check was performed to understand the comparison to that which is assumed in the ORIGEN-ARP calculations. The Tave of the normal 100o/o power condition is found in TDB-lll.1. The value for Tare at 100% power is 567.6 "F. This value is used to represent the average moderator temperature for the calculation. The operating pressure for FCS at 100% can vary slightly with it being assumed to be about 2100 psig. The density of water at these conditions is calculated to be 729.6027 kg/m3. Converting that to gr/cm3 results in a value of about 0.72936 g/cm3 per toolbox calculator. TODI-BE-16-OPPD-001, Revision 1, reports that the density of the moderator is 0.7314 g/cm3. The Fort Calhoun StationCALCULATION SHEET FC08514 Revision 0 26 value for the water moderator used in ORIGEN-ARP calculations is 0.7332 g/cm3. The value utilized is just slightly denser than that calculated and reported in the TODI. The pre generated cross section in ORIGEN-ARP for CE 14 x 14 fuel type would be based uponthe moderator density being 0.7332 g/cm3. Figure D1 .3.3 of ORIGEN-ARP manual shows that the effective absorption cross section as a function of water-moderator density is flatbetween 0.7 and 0.8 for 235U which is criticalwhen evaluating fission product generation. Therefore, the slight difference in the ORIGEN-ARP used moderator density for the calculations (i.e. pre generated cross sections) does not have an impact on the fission product generation (i.e. decay heat).7.4 Temperature Conversion Comparison For evaluating temperature comparisons between values reported in Fahrenheit they must be converted first to Celsius and then Kelvin. The equation to perform the conversion is noted below. I..r = (I,.o -32) x 5/9 Once the Celsius temperature is determined it is converted to Kelvin by the noted equation.7i^r= 7i..r+273.15The following parameters were converted to Kelvin in order to compare to ORIGEN-ARP set parameters. Table7.4 Temoerature Paran reters Converted to Kelvin for Comparison Temperature Parameter FCS Specific ("F)Converted to ('K)ORiGEN-ARP ('Kl T.r.a (average)625.1 note 1 602.65 620 T.u" 567.6 570.70555 570 Ttuet note 2 839.5 873 Itiotel - the average clad temperature is provided, ORIGEN-ARP manual does not specify if the Tcrao parameter is the average or not. An inner clad temperature from RODEX output EA15-022 (Ref. a.2a), Table 5.1.22.3 Cladding Temperatures would be 646.8 "F converted to 614.8'K which is close to the ORIGEN-ARP parameter. Although Ref .4.24 was for Cycle 29 which shall not be used, it provides relevant data that is for normal core operations.Note 2 - parameter provided in desired unit All of the temperature parameters noted above are well within tolerance for the decay 7.5Fort Calhoun Station CALCULATION SHEET FC08514 Revision 0 Pase27 calculations. The moderator temperature is almost the same as that used for the cross section generation. The clad and fuel temperature are slightly different which can be the slight difference when comparing the benchmark cases.Average Power Calculation - MWMTU In order to calculate the Average Power input for ORIGEN-ARP the following information is required - Average mass of uranium per assembly and the Rated Power for the Reactor. Assumption 3.14 identifies the Average Power per Assembly of 11.2782 MWU per assembly. This value is then utilized to calculate the Average Power per MTU to be input into ORIGEN-ARP. An example is shown below.The average uranium mass of Assembly DD07 per Table 7.1 is 388300 gr or 0.3883 MTUTo solve for the Average Power per MTU one applies the following: Average Power per assembly = 1 1.2782 MWassembly Average Uranium mass for DD07 Assembly = 0.3883 Average Power per MTU = 11.278210.3883 = 29.045 MWMTU This value is then input into ORIGEN-ARP. Table 7.5 identifies the Average Power for Core Offload, and Table 7.6 identifies the Average Power for Old Fuel in the SFP.Table 7.5 Core Offload Average Power lnputs by Fue! Sub Batch Assembly Batch/Number Average Power Mw/MTU Core Offload DD1/DDO7 29.041 DD2/DD23 29.264 DD3/DD33 29.233 EETIEEO4 28.97C E2lEE2O 29.188 E3/EE32 29.279=FL/FFO7 29.72t=F2/FF09 29.165=F3lFF22 29.3ss=F4lFF37 29.309 3GuGG03 29.L20 3G2lGG1s 29.t73 3G3/GG33 29.309 Fort Calhoun StationCALCULATION SHEET FC08514 Revision 0 28Table 7.6 Old FuelAverage Power lnputs by Fuel Discharge Batch Assembly Number/YearcCooled in SFP Average Power MW/MTU DD2213.767 29,257 BBO2/7.083 30.202 Y03u8.s 30.130 M17l10.083 30.313 Y0L311L.67 30.258 YO39/73.L67 30.206 xo73174.67 30.2L7 foo7l1.6 30.09s 7.6Burnup Adjustnrent - Multiplication Burnup is measured and reported in MWd per MTU in the GARDEL system. The ORIGEN-ARP utilizes units of MWd/MTU as input for the calculation. Therefore, no conversion is necessary for the data that is derived from the core map reported in TDB-1.4.2 or the SNM inventory. However, an uncertainty factor does need to be applied (6%)and therefore all burnup data extracted from the core projection map and the SNM inventory must be multiplied by 6% to increase the burnup value. The values reported in lable 7.7 show the raw data from GARDEL or SNM and then adjusted for the 6%uncertainty for each assembly sub or discharge batch. Fort Calhoun StationCALCULATION SHEET FC08514 Revision 0 P 29Table 7.7 Adjusted Burnup lnputs for ORIGEN-ARP Assembly Number GARDEI Burnup GWd/MTU Adjusted Burnup MWd/MrU lxl.06l Core Offload TDB-1.A.2 EA15 014 DDOT 55.041 58343.5)D23s2.80355977.2)D33 38.204 40496.2:E04 50.779 53825.i:E20 42.545 45097.1 E32 38.52 4083'.1..2
- F01 35.764 37909.8:F09 37.436 39682.2=F22 39.434 41800.C=F37 37.851 40L22.1 3G03 77.775 L8205.5 sG15 75.977 L7995.e 3G33 20.673 27973.4'FP SNM list (MWd/MTUI)D22 50296 53313.E lB02 49355 523L7.4 r031 55274 58590.4 qA175151954610.1 r013 4481.4 47502.t r039 44386 47049.2 (013 47767 50533.C r001 434!8 46023.7 7.7 ORIG EN-ARP lnputs Generic With the information from tables 7.1 through 7.7 ORIGEN-ARP data was input into individualassembly runs to derive the following output data, 1) watts per decay time point, 2) gamma source term, and
- 3) neutron source term. Three cases were run for each assembly to derive the output information noted above. This is required because ORIGEN-ARP requires setting plot options for the type of information required.
For 7.8Fort Calhoun Station CALCULATION SHEET FC08514 Revision 0Paoe 30 example to derive the output units in watts and to provide the data for light elements, actinides and fission products the analyst must set the plot type to nuclides, and thenspecify the output units in watts and select the run to evaluate all decay cases. ln orderto look at the Gamma spectra source term a different run is performed and the plot options must indicate a plot type of Gamma Spectra. Once that option is selected the analyst has to select the case to plot, i.e. all decay cases and the units. For the further downstream calculation in MCNP the units must be set in photons/s/mev, and as such that option is selected. For the Neutron source term, all Neutron Spectra are selected and then the code reports the output as a default in neutrons/s/mev. Therefore, three cases were run per individual identified assembly type, and the output in watts, gamma and neutrons extracted accord ing ly.Attachment 10.5 lists all the inpuUoutput files that were generated during the calculation process using ORIGEN-ARP. The files are stored on CD for future retrieval.Also files were run at different time points to evaluate the decay cooling time impact. The output from the ORIGEN-ARP was further manipulated by copying and pasting into EXCEL spreadsheets for further analysis which will be discussed next.Decay Heat Calculatron Fuel Groups The output from the ORIGEN-ARP cases for decay heat (watts) was extracted directly in order to perform a comparison. The purpose for this manipulation was to determine that assembly which has the highest heat load as a function of time. The decay heat for each individual sub batch assembly being discharged from the core was evaluated. The time points chosen were monthly increments for decay from twelve to eighteen months. After the eighteen month point the decay was further calculated at six month increments to three years. The output from the decay heat calculations was not further manipulated for reporting, only raw output is provided in the results section. A comparison technique in EXCEL was performed to identify that assembly which had the highest heat load in watts per unit time (decay). That assembly then was tabulated for further calculations requiring decay heat load as a function of time (i.e. Zirconium clad interactions). Only the fuel assemblies from the core offload were modeled for reporting in this calculation as it has the highest heat load versus fuel stored in the SFP discharged circa mid-April2015 that has cooled over sixteen months as of 8/31/2016. Source Term Calculation - Photons, Neutrons adding and BinningThe output from the ORIGEN-ARP cases for Gamma (photons) and Neutrons was further manipulated to derive a source term to be used in downstream dose calculations. The reason for the further manipulation was that the ORIGEN-ARP runs were performed for an individual assembly. So the source term represents only one assembly. The output from the ORIGEN runs was extracted for the tota! gamma and neutrons by the respective 7.9 Fort Calhoun StationCALCULATION SHEET FC08514 Revision 0 31 energy group. That information was then put into an EXCEL spreadsheet for eachassembly evaluated. The number of assemblies representing that batch were then input to use as a multiplier to derive a total source term for that particular batch of assemblies. For example if the number of assemblies in sub batch DD1 in the core equaled 12, thenthe Gamma and neutron source term was multiplied by 12 for each energy group to derivethen the tota! source term by energy group and the total source term. This technique was applied to all thirteen sub batches of the core offioad and to the batches grouped in the SFP. This output is provided in Attachment 10.4.The number of assemblies per batch was previously identified and applied for this derivation as well. This is the same approach that was utilized in Ref. 4.21 and is considered conservative because it uses the highest burnup and enrichment to represent each fuel assembly in the group, whereas this is considered bounding especially for the spent fuel pool source term.The same energy bins that are output from ORIGEN-ARP were utilized in the assembly grouping and total source term derivation, that is none of the energy groups were collapsed or adjusted. The raw data in the EXCEL spreadsheets then can be readily applied in further downstream calculations such as MCNP without adjustment. 7.10 Scaling Approach to Other Time Points - DD1, batch assembly DD07 various time points and scalerThe source term for Photons and Neutrons can be scaled for other decay time points.The methodology for scaling a source term is a direct relationship to the radiation dosimetry first principle equation from Cember related to exposure. The equation for calculation exposure rate is a function of gamma flux, energy of that flux, the attenuation coefficient, and density of material only. As such the only variable in the equation is fluxas all other items are constants. The equation for exposure rate in air is given below: X = 6 photons/cm2/sec x E MeV/photon x 1.6x1O13 J/MeV x u, cm-1 pa kg/cm3 x 34 J/kg/C/kg The Energy is fixed per photon by the energy bin process, the attenuation value for air is constant as is the density. Thus, the exposure is only dependent on change in flux.Therefore, by scaling a source term the dose rate itself is scaled and applicable for furtherdownstream calculations. The scaling of the source term is performed with a bounding application. A bounding application for scaling is used to be conservative. The highest burnup assembly was utilized to derive the scaling factors. The process is explained as follows;1. The highest burnup assembly was used for the scaling process and identified as assembly DD07.2. ORIGEN-ARP runs were then made at different decay times to generate photons andneutron output for each different decay time point. Fort Calhoun Station CALCULATION SHEET FC08514 Revision 0 P 32 3. The outputwas then scaled againstthe original calculation at 18 months to derive a scaling factor. This was performed in EXCEL spreadsheets. For example the ORIGEN output for assembly DD07 for total Gammas (photons/s/mev) at 18 month decay was 2.71E16. This then becomes the comparison point. Output from a 14 month decay time yielded that the total Gammas available was 3.28E16 or a 20.92%increase. Thus, the scalar of 1.2092 would be applied to ALL assembly outputs related to the gamma source term. This is considered appropriate as the decay process typically follows a powerfunction and the other assemblies would decay via the same approximate function. Therefore, to derive a gamma source term to be used at the 14 month interval each energy bin group would be scaled using the 1.2092 factor, with the overall gammas increasing as well. The scaled source term can then be utilized in further MCNP calculations. This same approach was used for both core offload and fuel in the SFP. This is considered very conservative for fuel in the poo! as majority of the fuel stored would bewithin the decay curve portion that is flat and not decreasing significantly.Figure 7.1 shows the gamma flux change as a function of decay time for assembly DD07 (sub batch DD1). The power curve spline fit was used to evaluate the statistics of the output. The regression shows a good fit for the curve derived. This curve can be used for deriving the total gamma spectrum within only the range noted as further interpolation less than twelve or greater than eighteen months would have to be evaluated. Gamrna Flux EDl Assembly Versus Months Decay 3.*#.+16 3.6ffi+Ltr 3".{*t+!S 3-3fir+ tr*3.**Y.+L 2.*0t+L*2.6ffi*Ltr 2.40(+ trS14 1S 1& ;SMr:nthr alter 0isrhargeFigure 7.1 Assembly DD07 Gamma Tota! Flux versus Decay The same type of application is applied for the neutron source term as noted above.ORIGEN runs were made for assembly DD07 at different time points to generate theneutron source term as a function of different decay points. Output for example from the eighteen month yielded a tota! neutron flux of 7.4E8 neutrons/s/mev. The output from thefourteen month case yielded a total neutron flux of 7.66E8, which is only an increase of 3.5o/o. Therefore, a different scaling factor is applied to the neutron source term than the gammas. Figure 7.2 shows the neutron flux change as a function of decay time for 1*r U E E V
- 2{+27x'?:;;
cJ -. fr n00, Fort Calhoun Station CALCULATION SHEET FC08514 Revision 0 e33 assembly DD07.Neutron Flux 0Dl Asse mbly Versus Months Decay 7.gffi+08 u ff 7.85e+SS? r.B*e+ffi E 7.758+08= 7"7*{+*B# r.osg**s L l.btt+(.ll, L /r-55t+LI5
- $ z.**tlt+ffi
,3 z"sx*u$S z.aoe+*s? 7.35t*08 u ,t't 10 11 i (J L?. 13 tr4 15 16 17 18 ZsMonlhs after OischargeFigure 7.2 Assembly DD07 Neutron Total Flux versus Decay A power curve spline was applied as well to derive a fit equation. The regression showsreliable statistics as well for the twelve to eighteen month projection. Table 7.8 below shows the scalers that are to be applied for further downstream analysis related to exposure rates for dose calculations. Note for time points less than twelve months or greater than eighteen months further analyses would need to be performed to validate application. Table 7.8 Gamma and Neutron Scalars versus Decay TimeHottest Assemblv Total Photons and NeutronsAssemblv Batch DDl Gamma Gamma ScalarNeutronNeutron ScalalMonthsTota! Photons Tota! Neutrons L2 3.55E+15 1.34517.83E+081.0578 133.45E+15L.2742 7.74E+OB 1.0459 14 3.28E+76 1.2092 7.66E+08 1.0350 153.12E+161.1s067.59E+081.02s1 16 2.97E+161.09537.52E+081.0151 77 2.84E+L6 1.0465 7.46E+OB L.OO77 18 2.7LE+!G1.000c7.40E+08 1.000c For a fourteen month source term calculation the scalers of 1.2092 and 1 .0350 for gamma and neutrons was used respectively. Other decay source term can be likewise scaled in Y
- 1E+6Sx"* iis&i
- 0.9$99 Fort Calhoun StationCALCULATION SHEET FC08514 Revision 0 34 further dose calculations (between twelve and eighteen months).Resu lts 8.1 Decay Heat Highest Heat Load Assembly This calculation required addressing the following objectives, 1) determine the highest heat load per assembly in watts, and 2) determine a gamma and neutron source term tobe used in subsequent calculations. The first objective is addressed in this section related to results for further downstream calculations.
The results from these calculations are shown in the raw ORIGEN-ARP code output.Tables 8.1 through 8.4 show the output from ORIGEN-ARP as a function of decay timefor the fuel batches to be discharged from the core. The data is reported for each batch type and individual sub batches are provided within a table. Note Assembly DD07 was run for a four cycle operation just to see which would be more conservative 3 versus 4 cycle. lt was determined that the 3 cycle was more bounding, but the 4 cycle energyoutput is shown just for that assembly only. Since the 3 cycle burn was illustrated to be bounding allfurther computations in ORIGEN-ARP were done with a 3 cycle Ioop.Table 8.1 Batch DD Fuel Core Offload versus Time Sore Map TDB-LA.2 page 2 and EA15-014\ssembly DD07 iub Batch DDl[ime 1 year 1.0833 year 1.157 vea 1.25 vear 1.33 vear 7.4L67 ve 1.5 vear 2 vear 2.5 vear 3 vear)ower watts 5043 4764 4515 4297 408*3898 3726 292t 238(2002I cvcle burns034 3718 1996[ssembly DD23 iub Batch DD2 lime 1 vear 1.0833 vea 1.157 vea 1.25 vear 1.33 year 7.4167 ve 1.5 vear 2 vear 2.5 vear 3 vear)ower watts48294560 4320 4103 3906 3725 3558 2782 2261 1898{ssembly IDD33 iub Batch DD3 Iime L vear 1.0833 vea 1.167 vea 1.25 vear 1.33 vear 1.4157 ve 1.5 vear 2vear 2.5 vear 3 vear)ower watt!38773637 342432353053 2906 2t62 2700 766i 7362Table 8.1 illustrates that the highest heat load is projected to be from Assembly DD07 as a function of decay time in comparison to other DD assemblies. Fort Calhoun StationCALCULATION SHEET FC08514 Revision 0 P 35 Core Map T--DB-l:A.2 page 2 and EA15:011 Assembly EE04 Sub Batch EE1 lime 1 year.0833 vear 1.157 vea1.25 vear1.33 vear 1.4157 ve1.5 vear 2 year 2.5 year 3 year Power watts472L 4454 42t43999381136243460 2694 2187 r82!Assemblv EE20 Sub Batch EE2 Time 1 year.0833 year 1.167 vea 1.25 vear 1.33 vear t.4t67 ye 1.5 vear 2 year 2.5 year 3 year Power watts 4t3L38833663 3466 3287 3L2 2974 2281 1827 1504 Assembly EE32 Sub Batch EE3 Time 1 year 1.0833 year L.167 yea 1.25 year 1.33 vear 1.4167 ue 1.5 vear 2 vear 2.5 year 3 year Power watts3871 363334213232 3068 2905 2762 2103 166(136*Table 8.2 Batch EE Fuel Core Offload versus Time Table 8.2 illustrates that the highest heat load is projected to be from Assembly EE20 as a function of decay time in comparison to other EE assemblies. Fort Calhoun Station CALCULATION SHEET FC08514 Revision 0 P 36 Core Map TDB-l.A.2 page 2 and EA15-014 Assembly FF01Sub Batch FF1 lime 1 year 1.0833 vear 1.157 vea25 year 1.33 year 1.4767 vear 1.5 vear 2 vear 2.5 year 3 vear 3624 3395 3191 3011 2854 270C2s64194L1531L251,:ore MaD TDB-!.A.2 oase 2 and EA15-014[ssembly FFOg iub Batch FF2[ime 1 year 1.0833 vear 1.167 yea 1.25 vear 1.33 year 1.4L57 vear 1.5 year 2 vear 2.5 year 3 year37393508 3301.31152949279826572019 1597 1309 Core Map TDB-l.A.2 pace 2 and EA15-014 q';[ilFFz lub Batch FF3 Time 1 vear 1.0833 year 7.!67 vea 1..25 vear 1.33 Vear 1.4167 vear 1.5 vear 2 vear 2.5 year 3 year 3898 3662 3448 3259 3093 293t 2787 2t261588138 Core Mao TDB-l.A.2 oase 2 and EA15-014 Assembly FF37 Sub Batch FF4 Time 1 vear 1.0833 vear 1.167 yea 1.25 year 1.33 year 1.4167 vear 1.5 vear 2 vear 2.5 year 3 year38213593 3382 3194303028652727 20741642134:Table 8.3 Batch FF Fuel Core Offload versus TimeTable 8.3 illustrates that the highest heat load is projected to be from Assembly FF22 as a function of decay time in comparison to other FF assemblies.Table 8.4 Batch GG Fuel Core Offload versus Time Fort Calhoun StationCALCULATION SHEET FC08514 Revision 0 37:ore Map TDB-!.A.2 page -2 and EA15-014 lssembly GG06 or GG03 iub Batch GG1 lime 1 vear1.0833 ve157 vea1.25 vear 1.33 year 1.4167 ve 1.5 vear 2 vear 2.5 vear 3 vear 2375 2140198818551737 1632 L537 110s 836.E 6s4.t Core MaD TDB-!.A.2 oase 2 and EA15-014 Assembly GG15 iub Batch GG2 Iime 1 vear 1.0833 ve L.L67 yea 1.25 year 1.33 vear 1.4767 ve 1.5 vear 2 vear 2.5 year 3 year 2296 2!24 7971 1839 L726 t6t1 L5221099827.9 547.1 Core Map TDB-l.A.2 pase 2 and EA15-014 Assembly GG33 iub Batch GG3 Iime 1 vear 1.0833 ver!.167 vea 1.25 vear 1.33 vear 1.4767 ve 1.5 vear 2 vear 2.5 vear 3 vear26272441 2275 213C 2006 1884L7787299 988.8 780.t Table 8.4 illustrates that the highest heat load is projected to be from Assembly GG33 asa function of decay time in comparison to other GG assemblies. ln comparing the heatoutput from all the sub batches evaluated (Tables 8.1 through 8.4), assembly DD07 is identified as the assembly with the highest heat load as a function of time. Therefore, for further downstream calculations related to Zirconium clad interactions the following information is to be utilized. The tabulated information relates to Assembly DD07.Iime i1 year 1.0833 year1.167 vea1.25 vear 1.33 vear 1.4167 ved 1.5 vear 2 vear 2.5 vear l3 vear Power wattsl 50434764451542914086 3898i 3726 292t 2380t 200i B.2 Gamma Source Term Results The output from ORIGEN-ARP was manipulated to include multiplying the individualassembly source term by the number of assemblies in that group. The assembly batch information is provided in Attachment 10. Only the total gamma (photon) source term is provided in this section.Table 8.5 Gamma Source Term (Eighteen Month) by 18 Energy Group Fort Calhoun Station CALCULATION SHEET FC08s14 Revision 0Paoe 38 18 Month ,Decay Tota! Gamma Energy.... Old Fuef Core Offload Spectrum , aore Offload Output Group 811 Assemblies,l33 Assemblies and Old Fuel photons/s/mev, photons/s/mev photons/s/mev 7 8.4OE+\7 8.29E+17 1.678+18 2 L.77E+17 1.80E+17 3.51E+U 3 2.2LE+!7 2.O4E+11 4.25E+L7 4 L.49E+171.51E+173.00E+17 5 9.56E+16 1.L4E+L1 2.LOE+L1 5 9.78E+16 7.57E+tj 2.55E+17 7 8.45E+16 1.08E+17 1.93E+17 8 3.84E+155.67E+169.51E+16 91.43E+186.07E+77 2.O4E+L8L01.30E+17 2.16E+77 3.45E+17 LL 3.08E+15 3.11E+15 6.19E+16 12 1.40E+15 3.25E+15 4.55E+15 13 4.29E+t4 4.24E+ts 4.67E+tS L4 1.38E+137.72E+L39.108+115L.28E+125.95E+128.24E+12L68.96E+09 1.45E+09 1.04E+1C t71.03E+091.68E+081.20E+09 18 1.19E+08 1.93E+07 1.38E+08 total 3.29E+18 2.65E+18 5.95E+18 Table 8.5 Total Gamma Spectrum output is to be used in further dose calculations for an eighteen month decayed source term.Table 8.6 Scaled Gamma Source Term (Fourteen Month) by 18 Energy Group Fort Calhoun Station CALCULATION SHEET FC08514 Revision 0 39 14 Month Decay Scaled ,TotalGamma E--n-ergy. __.specquq_- Core Offload Output Group :and Old Fuel photons/s/mev 1 2.02E+18 2 4.25E+t7 3 5.14E+17 4 3.53E+U 5 2.53E+1763.08E+17 7 2.33E+17 8 1.15E+U 9 2.45E+18104.18E+17 7L 7.48E+1*12 5.63E+15 13 5.55E+15 74 1.10E+14 15 9.97E+12 16 1.26E+10 77 1.45E+09 18 1.57E+08!-otal 7.2OE+18 Values noted in Table 8.6 are to be used for a fourteen month source term dose calculation.
8.3 Neutron
Source Term Results The output from ORIGEN-ARP was manipulated to include multiplying the individual assembly source term by the number of assemblies in that group. The assembly batch information is provided in Attachment 10. Only the total neutron source term is provided in this section. Tables 8.7 and
8.8 provide
the information for the neutron source term for an eighteen month decay and a scaled fourteen month decay.Table 8.7 Neutron Source Term (Eighteen Month) by 44 Energy Group Fort Calhoun StationCALCULATION SHEET FC08514 Revision 0 Paqe 40 Eighteen Month Decay Total Neutron Energy Old Fuel Core Offload Spectrum Core Offload OutputGroup 8ll Assemblies 133 Assemblies and Old Fuelneutrons/s/mpv neutrons/s/mev nerrtrons/s/mev 13.17E-033.36E-023.51E-03 "_4 3 L2!.E:99 1.79E-03?,3*g: 7.97E-Ot?:??F:H 1.99E-03 4 5.30E-03 5.58E-0r 5.85E-03 5 2.18E-03 2.42E-0t 2.428-0367.58E-039.06E-0r8.laE-0375.45E-03 6.19E-0r 6.07E-03 81.t7E-021.34E-0: 1.31E-0291.94E-022.22E-Oi2.t5E-O2103.70E-O24.2sE-Oi4.t2E-O2 114.35E-025.24E-014.88E-02 t2 2.55E-02 3.23E-0!2.97E-Oz133.45E-024.28E-Oi3.88E-0i 142.9tE-O23.54E-0: 3.26E-Ot154.90E+007.81E-015.68E+00161.698+002.73E-O11.95E+0( t7 1.73E+OC2.94E-012.03E+0(181.81E+002.94E-O72.11E+00 191.60E+012.59E+0(1.85E+01 20 3.80E+O1 5.16E+0(4.42E+O7 2L 1.06E+O2 1.73E+01 1.24E+O2222.10E+023.418+012.44E+Oi 233.90E+026.32E+014.53E+02
243.378+025.45E+01 3.91E+0i256.33E+02 1.038+0i 7.36E+0i255.49E+021.05E+O:7.54E+0: 271.01E+041.63E+0: 1.17E+0r 28 6.37E+OA1.03E+047.40E+0r299.06E+051.47E+0:1.05E+0(30 1.15E+07 1.87E+O(1.34E+0i311.55E+082.52E+01 1.81E+01 321.31E+082.72E+01 1.52E+01332.04E+093.31E+0t2.37E+0! 341.47E+1C2.39E+0S 1.71E+1(353.21E+10 5.21E+0!3.73E+1(35 3.21E+15.21E+O!3,73E+1(372.57E+7 4.18E+0S 2.99E+1(38 2.42E+tA 3.94E+OS 2.82E+ll395.24E+09 8.53E+0t 6.10E+0!40 1.87E+1C 3.05E+O!2.188+1(4l 3.408+10 5.56E+0S 3.95E+1(42 9.66E+09 1.57E+0S 1.12E+1(433.07E+09 4.97E+Ot 3.57E+0: 441.06E+091.71E+Ot1.23E+0! fotal 2.038+1 3.30E+1(2.36E+11Table 8.8 Scaled Neutron Source Term (Fourteen Month) by 44 Energy Group Fort Calhoun Station CALCULATION SHEET FC08514 Revision 0 41 14 Month Decay Scaled TotalNdiro; ineqy - -- - Sp"gt-.n... .. _Core Offload)utputGroup and Old Fue!neutrons/s/mev I 3.63E-0: 2.61E-0! 2.06E-0!6.06E-0! 2.51E-0: 8.78E-O: 7 6.28E-0!8 1.35E-0i 2.24E-O2 10 4.27E-O2 11 5.05E-0: x2 3.08E-0t 13 4.02E-01 14 3.37E-O2 15 5.88E+fi 16 2.03E+0(77 2.10E+O(18 2.18E+ff 19 1.92E+O1 20 4.57E{-01 2l L2AE+O2 22 2.S3E+O2234.59E+02244.05E+02 25 7.62E+O2267.81Er02 27 1.21E+&2A 7.56E+&291.09E+0t 30 1.39E+O7 31 1.87E{-08 32 1.588+O8 33 2.45E+O!yl 1.77E+11353.87E+1(363.86E+1(37 3.09E+1(382.91E+1(396.31E+o! N 2.25E+X414.09E+1( 42 1.16E+1(433.59E+0! 44 l.27Et0l fotal 2.UlE+l1 8.4 Benchmark Resuits Fort Calhoun Station CALCULATION SHEET FC08514 Revision 0 e42 Benchmark calculations were performed to check ORIGEN-ARP CE 14 x 14 typical pre generated cross information against explicit FCS AREVA 14 x 14 fuel cross section data.This comparison is not a side by side comparison of the cross sections themselves but the results of the use of those cross sections generated in explicit FCS assembly models against ORIGEN-ARP generic PWR CE 14 x 14 model. The first comparison was to take a3.22 and 4.95% 235U enriched set of assemblies and model decay heat from such as a function of time for the actinides only. Calculation FC07688 performed a detailed SAS2H/ORIGEN-S calculation with explicit fuel clad, pellet, upper/lower end fiftings and fuel operating details. As previously discussed only the actinides were compared asFC07688 used a different method for fission product generation (i.e. ANS 5.1). Details regarding the ORIGEN input deck can be found in that calculation. The benchmark calculation comparison shown in Table 8.9 below shows that the ORIGEN-ARP output for 2 to 5000 days is on average slightly under predicting actinide heat generation by approximately 2.6 to2.8% when evaluating out to 62,000 MWD/MTU. The ORIGEN-ARP cross section database for CE 14 x 14 typical fuel was generated out to 72,000 MWD/MTU as such, this benchmark comparison is within the confines of the cross section databases generated. The enrichments that were utilized for the ORIGEN-ARP cross section generation were 1.5,2,3,4,5 and 60/023sU. The range utilized forcross section generation of the ORIGEN-ARP libraries is well within the range of the comparison as well (i.e. 3.22 and 4.95% AREVA 14 x 14 comparison). The slight differences in the actinide heat production can be justified since an explicit fuel assembly was built in the FC07688 calculation, and had a slightly more complex power history. The results thoughhave very good statistical comparison to justify the use ORIGEN-ARP for the source term calculations. Also ORIGEN-ARP utilizes the SCALE 6.1 resonance self-shielding enhancements which would explain some of the under prediction.Table 8.9 Decay Heat versus Time Comparison Benchmarks FC07688 Calculatlon FC07588 Comparison to ORIGEN-ARP 3.22 62,000 MWD/MTU, Calculated 393,264 kg Time lDavs 2 3 5 10 50 100355500 730 1000 5000 ARP actinides (watts)AREVA actfnides _---A%o 16930 16900-0.18 13130 1-3?09 0.53 82L9 8300 0.855 3460 3560 2.809 1644._1740 5.517 t422 1-50-0 5.2 796.7-828 3.78 663.4 684 3.012 552.3 565 2.248 501.3 s.1_!1.8982 379:8..390 2.6754 2.5776L3 averase delta %4.95 62,0q) MWD/MT ARP actinides (watts)AREVA actinides L%U, Calcr 14780 14800 0.135 rlated 39 I risoo I rrioo lo ,-z:97ttlt 724:e 7310 0.834 3082 3160 2.468 1409 1480 4.797 1196 1260 5.O79 603.7 629 4.022 478.7 498 3.876 376.7 390 3.41 332:8 3!4 3.2558 272:9 283 3.5689 2.8s88s1 averagedelta% I t i 44 ENDF Group Neutron4T grp Gamma or 18 Group Additional benchmark comparison was performed against FC07586 calculations. This calculation performed an extensive fuel modeling of an AREVA 14 x 14 assembly andused SAS2H/ORIGEN-S to perform the calculation including generation of cross section libraries. An ORIGEN-ARP input deck was created using the inputs from FC07586 that Fort Calhoun StationCALCULATION SHEET FC08514 Revision 0 43 were relevant. The results for the gamma source term were favorable as shown in Table 8.10.Table 8.10 Gamma Comparison 4.5% 235U Assembly 4.5%235U Gamma Model Decav Time Hours 72 100 200 300 400: 876(Gamma Enersv (MeV/Sec)ORIGEN-ARP totals all sroups7.947E+771.722E+L7 1.274E+17 1.048E+17 9.086E+16 1.113E+1(FC07586 Table 5-1 totals all groups l.7lE+17 1.57E+Ll1.24E+171.05E+179.22E+751.15E+1(\%-14.15-9.95-2.92 0.27 1.5C 3.45-3.63 averase delta %Vlodel Decav Time Hours 72100200300 400 876(Gamma (Photons/Sec) ]RIGEN-ARP totals all prouos6.81E+175.63E+173.47E+L72,62E+172.21E+17 3.97E+U:C07586 Table 6-3 totals all sroups6.85E+175.58E+173.51E+172.66E+772.24E+174.05E+1t \o/" 0.75 0.941.341.551.64 2.2i 7.4t averase delta %For the photons/sec total overa!! energy groups the average difference from a span of 72 to 8760 hours was 1 .41o/o. The gamma energy calculation with output in MeV/sec had a greater statistica! average for difference (-3.63%) which indicates that the ORIGEN-ARP model was slightly over predicting the MeV/sec value and for the photons/sec output itwas slightly under predicting. The differences noted are well within understanding the limits of the typical model used in the ORIGEN-ARP model (explicit nuances in cladmaterial, dimensions were not accounted for in the typical fuel design). However, the difference illustrates a very good comparison overall for both short term and long term decay calculations. A 5% enrichment was documented in FC07586. The comparison for the MeV/sec for the 5% enrichment is documented in table 8.11. Note FC07586 did not document a photons/sec output for the 5% enrichment and as such that comparison is not performed. The ORIGEN-ARP comparison yields a slightly larger average difference for the 5% enriched assembly versus the 4.5%. Since the fuel modeled for this calculation does not exceed a 5% enrichment the ORIGEN-ARP model is further justified since the difference is less than that found in the higher enriched assembly.Table 8.11 Gamma Comparison 5.0% 235U Assembly 5%23sU Vlodel Decav Time Hours 72 100 200: 300' 400 876C Gamma Enerey (MeV/Sec))RIGEN-ARP totals all prouos L.947E+77 1.724E+17 L.28OE+L71.055E+179.146E+15 1.089E+1:C07585 Table 6-1 totals all sroupst.7OE+171.56E+17 7.24E+ll1.05E+179.22E+76 1.13E+1\%-L4.25-10.87-3.45-o.44 0.81 3.39-4.1 averase delta %The neutron productwas also checked against results reported in FC07586. Table 8.12 show the results of comparing the ORIGEN-ARP model against Table 6-4 results in Fort Calhoun Station CALCULATION SHEET FC08514 Revision 0 44 FC07586.Table 8.12 Neutron Comparison 4.5% 235U Assembly Model Decav Time Hours 72Neutrons Neutrons/sec)RIGEN-ARP totals all groups 9.250E+0E FC07586 Table 5-4 totals all srouos 1.05E+09 f\%12.rcL2.16averase delta%The benchmark comparison for neutrons was limited to one time point comparison sinceonly one time point was reported in FC07586, i.e. at 72 hours. One difference for the deltabetween the two calculations is that ORIGEN-ARP uses ENDFS for the neutron group library with SCALE 6.1. FC07586 was run with SCALE 4.4a and NDF5 neutron library group. The differences can be explained due to the fact that significant upgrade in SCALE occurred in the area of resonance self-shielding. The methodology difference for computing the resonance self-shielded cross sections is identical, however what is different is the addition of an extra cross section to be used by other sequences in SCALE to pass Dancoff factors computed by other libraries to within other modules. Therefore, the resonance self-shielding extra cross section can explain both the neutron and gamma source term slight differences in source term. Additionally the FC07586 calculation explicitly modeled the AREVA 14 x 14 assembly for the reporting of neutrons related tothe active fuel region. Slight differences would be expected in some of the minor fuel type inputs.Conclusions 9.1- Decay Heat for Hottest Assembly The maximum bounding heat rate in output of watts for Assembly DD07 is found in Table9-1 as a function of spent fuel decay time (for decay times of 12, 13, 14, 15, 16, 17 , 18,24, 30 and 36 months after reactor shutdown). The heat rate was calculated for thehighest burnup and enriched assembly and included the licensed methodology burnup uncertainty of 60/o. No peaking factor was applied since the burnup and enrichment for each batch of assemblies was utilized. The decay heat information provided is for thehighest heat load calculated. Other heat loads for the remaining twelve sub batchesoffloaded from the core can be found in Tables 8.1 through 8.4.Table 9.1 Decay Heat versus Time Assembly DD07 (Hottest Assembly)tme 1 vear 1.0833 vear 1.167 vea 1.25 vear i 1.33 vear 1.4157 ve 1.5 vear 2 vear 2.5 vear 3 vear)ower watts 5043 4764 4515 42971 408538983726 2921 2380 2002 It should be noted that the only conservatism related to developing the decay heat versus time is the unceftainty in burnup which is a methodology requirement per EA08-001. ln Fort Calhoun StationCALCULATION SHEET FC08514 Revision 0 P 45 order to remove the burnup uncertainty of 6% which would result in lower decay heatvalues versus time a license methodology change would be required. Currently EA08-001 indicates that GARDEL unceftainty is 4.22% but is not the FCS methodology. Thus, even with considering a license change it appears that very little uncertainty could beremoved from the current methodology thatwould substantially benefit reduction in decay heat terms (potential long term applications).9.2 Gamma Source term The bounding gamma energy source term for the offloaded core and fuel stored in the spent fuel pool at eighteen months was calculated. The results for the eighteen group gamma source term at eighteen months were provided in Table 8.5 (not repeated here).The results for a scaled fourteen month source term (after shutdown) were provided intable 8.6. The fourteen month source term scaled is considered conservative as thescaling factor from assembly DD07 was applied to al! fuel groups including those in the pool stored for much longer periods which have a relatively flat decay profile. The sourceterm calculated is considered bounding for dose calculations. ln comparison the gamma source term computed for Assembly FF01 (core offload)which had a burnup of 37,909.8 MWD/MTU (including uncertainty) and an enrichment of 4.475o/o 23sU to FC07586 Table 6-3 illustrated that the total photons/sec were reasonable (FC07586 modeled a 34,635.6 MWD/MTU and 4.5o/o 235U enrichment, Table 6-3) 2.774E16 versus 4.065E16 photons/sec respectively at one year decay time. The gamma source term computed in ORIGEN-ARP is considered therefore representative and includes the SCALE 6.1 resonance self-shielding updates.The gamma source term from Tables 8.5 through 8.6 include the energy bin structures for further dose calculations that are to be performed. For information the Energy Profile by photons/sec is illustrated to show where the peak energy bin populations are located. Figures 9.1 through 9.3 show energy profiles for thecore offload sub batches DD1 and GG1, and the total core. Fort Calhoun StationCALCULATION SHEET FC08514 Revision 0 46 Energy Profile DSl liffi*1V*.**f.416 s.s4*+ls 7.Sfi{r16 5.08(+16$.$ffi+:^6 4,$*f +:*3.$0{+16 .1_ULJI{ tb 1.0fi{+ 16 0.00t+ffi Figure 9.1 Energy Profile by Energy Group Structure Number versus photons/s (Sub batch DD1)Figure 9.1 shows an initial peak at the Energy group 1, and then a spike at energy group 9 which aligns with the 1 MeV gamma energy structure. This spike illustrated above realistically illustrates the typical gamma profile from a fission process spectrum. The peak also shows that the expected dose would be from this energy group.fnergy Frofile Gfi1 4.$S{+16 3"5rN+16 3.0C$+16;.$tr+16 2.0ffi.+16.t .)LE i tb 1"offi+16 5.flffi+1.* S.00frfi*? 3 4 5 6 7 & e 10 11 1-::3 14 13 16 17 18 Figure 9.2 Energy Profile by Energy Group Structure Number versus photons/s (Sub batch GG1)Figure 9.2 illustrates a less pronounce peak at energy group g versus the high burnupassembly sub batches. Sub batch GG1 are only one cycle burned, and therefore, have Fort Calhoun StationCALCULATION SHEET FC08514 Revision 0 P 47 not had enough reactor residence time to buildup fission products in the gamma energy spectrum range that are ofdose consequence. Enengy Profile Total Core*,*&"*17 8.0tf+1?7.O{N.+27 6.4&3\7 5.0Ci+17 4.ffif.+lV 3.00*+37?.*0f + l7 1.00(+ 37{:.0r(+*0 Figure 9.3 Energy Profile by Energy Group Structure Number versus photons/s (Core Offload)Figure 9.3 is a graphical representation of the Core Offload values from Table 8.5. Onlythe core offload was graphed above to illustrate the energy structure predominance thatwas evident in Figures 9.1 and 9.2 as well. Thus the projection would be anticipated that the dose contribution would be most impacted by the gamma energy group with lMeV photons/s. Radial peaking factor and axia! power distribution differences were not utilized in this gamma source term calculation. Direct GARDEL projections for burnup were usedwith 6% uncertainty applied.
9.3 Neutron
Source Term The bounding neutron energy source term for the offloaded core and fuel stored in the spent fuel pool at eighteen months was calculated. The results for the eighteen group gamma source term at eighteen months were provided in Table 8.7 (not repeated here).The results for a scaled fourteen month source term (after shutdown) were provided intable 8.8. The fourteen month source term scaled is considered conservative as the scaling factor from assembly DD07 was applied to a!! fue! groups including those in the pool stored for much longer periods which have a relatively flat decay profile.The neutron source term from Tables 8.7 through 8.8 include the neutron energy bin structures for further dose calculations that are to be performed. Note the neutron source term is orders of magnitude less than the gamma source term and would not be expected to contribute much regarding the dose consequence of exposed spent fuel. The source term though is provided for completeness in further downstream dose calculations.1 ? 3 4 5 6 7
- t 1*11"1??3l,x15161718 Fort Calhoun StationCALCULATION SHEET FC08514 Revision 0 48 10.0 Attachments 0.1: TODI Aftachment 10.2: SNM Attachment 1 0.3: ORIGEN-ARP Manual Attachment 10.4: EXCEL Sheets (lncludes Tables and Formula Sheets)Attachment 10.5: ORIGEN-ARP Express InpuUOutput Files on CD Attachment 10.6: Alternative Calculation MicroShield and NRC BTP Examples Attachment 10.1 Transmittal of Design InformationFC08514 Page 1 of7 GC-FC.3l0-F-01 Rev.0 Transmittal of Design Information (TODI)TODI No.: TODI-BE-I6-OPPD-q01 Transmittial Letter Number (if applicable):
From: CarolWaszak Refer to CC-M-31 0 for requirements Revision: 1 Date: 8/15/16 To: Jan Bostelman Subject Revision 1 to TO.PI-BE-I6-OPPD-001 lnformation Provided and lntended Use: (List any reference documents or attachments) A best estimate tuelassembly decay heat calculation is being performed via ORIGEN-S for plant end of life conditions. lnputs for that calculation are provided via this TODI. Classification: Non-QASource and Basis of transmittal FCS Tech. Specs.; TDB-lll.1, R14; EA08-034, R0; EA05{20, R0; EA09-046, R1; EA07-0OSR0; EA08-017, R0; EA16-023, R0; EA08-001, R0; ANP-2849(P), R2; ANP-2705(P); AREVnSpecification 08'1023224, R2; OPPD Dwg. J-23866-164-033, R6;AREVA Dwg.02-5036725A1, R0, 02-5056837A1, R1, 02-5056937 A1, R2, 02-5056942A1, R0, 02-5056936A1, R0, 02-50381 8741, Rl, 0g-l 02322+02, R1, 02-5056947A1, R0.Status of Infonnation: ffi Approved for use E Preliminary, Scheduled for Confirmation on Limitations on Use: None TOD! Preparer TODI Reviewer Distribution: Per RM-AA-101 Project File Date 8/15/2016 Date 8/15/2016 Use TODI Number in any subsequent correspondence conceming input Revision 0
- 1. CE 14 x 14 Assembly Panmeters General Assembly lnformation fior AREVA Batch EE (Q;cle 25 Depletions)
Rated Core Power (without I uncertainty) Average Assembly Power Assembly Pitch (core)Attachment 10.1 1500MWth / 133 fuel assemblies = 1L.278 MWth/assembly 8.18 in FC08514 Page2olT TODI-BE-16OPPD{EI Revislon I Page 2 Fort Calhoun Technical Specifi cations, Definitions Page 1.EA08{34, Revision 0, "Cycle 25 Design Depletions," March 2009. Pace 49.OPPD Drawing J-2386G1O4-033(11541), Revision 6, "Fuel Alignment Plate (11541)"November 18, 1968.ANP-2849P, Revision 0, "PWRFuel Design Criteria Review for Fort Calhoun Unlt 1 Reload FCA1-26 (rfC-12)and Cycle 26EA09-046, Revision 1, "Cycle 25As-Built Depletions and GARDEL Update Preparation," December 2(F9. Page 28.Fort Calhoun Technlcal Specifications, Deflnitions Page 1.Fuel Rods per Assembly ANP-2M9P, Revision 0, "PWR Fuel Design Crfteria Review for Fort Calhoun Unit 1 Reload FCA1-26 (FTC-12) and Cycle 26AREVA Drawi ng 02-50367 25 AL, Revision Q "Spacer Grid HTP," Mav 2004.Reference Core Loading - U 5L.1784 MTU Reference Assembly Loading -uo2 387.M2ke I EA09{46, Revision L,"Cycle26 As-Built Depletlons and GARDEI Update Preparation," Reference Assembly Loading -U 15.685 G I EA09-046, Revlslon 1, "Cycle 26As-Built Depletions and GARDEL Update Preparation," Non welded Clad Length6.20 in I AREVA Drawlng 02-5056837A1, I Revision 2!,"u62Fuel Rod Revision 0 Attachment 10.1 Fuel Stack length 129.3 in Nominal Pellet 00 0.3805 in f Nominal Clad 00 0.440in Nominal Clad 10 : 0.387 in I Guide Tube 10 1.0351n i l Guide Tube OD 1.115 in I i i Nominal Fuel Pellet Density 96% Power per MTU 29.3092 MWD/MTU Cladding Material MS Guide Tube Material (without MS I sleeves) I j Clad Material Composition -MS -1 (In percent by material) I I I j I ! Nominal wt% U235 8 assemblies at 4.001 12 assemblies at 4.194 16 assemblies at 4.336 FC08514, RO EC 68969 -FC08514 Page 3 of 7 TODI-8E-16-0PP().()()1 Revision 1 Pagel 1 AREVA Drawing 02-5056837A1, t Revision 2, "U02 Fuel Rod Assembly,"' July 2007. AREVA Drawing 02-5056842A1, Revision 0, "U02 Pellet," February 2005. ; AREVA Drawing 02-5056836A1, l Revision 0, "'Cladding," February ! 2oos. I AREVA Drawing 02-5056836A1, Revision 0, 11 Ciadding," February 2005. AREV A Drawing 02-5038187 Al, Revision 1, "'Guide Tube," February 2006. AREVA Drawing 02-5038187Al, Revision 1, "'Guide Tube," February 2006. AREVA Drawing 02-5056842A1, Revision 0, "'U02 Pellet," February 2005. EA09-046, Revision 1, "Cycle 26 As-Built Depletions and GARDEL Update Preparation,"' December I 2009. Page 28. I ANP-2849(P), Revision 2, "PWR i Fuel Design Criteria Review for i Fort Calhoun Unit 1 Reload FCA1-26 (FTC-12) and Cycle 26 Assemblies, n ANP-2849(P), Revision 2, 11 PWR Fuel Design Criteria Review for Fort Calhoun Unit 1 Reload FCA1-26 (FTC-12) and Cycle 26 Assemblies," AREVA Specification
- 08-1023224-02, Revision 2, "Material Specification MS Sheet." (Average of minimum and maximum values) EAOS-034 , Revision 0, "Cycle 26 Design Depletions," March 2009. Page 18. Revision 0 51 Reactor Coolant System: Tavg 567.6 F TDB lll.1, Revlslon 14 "TaveProsram." October 27 . 2ffJ,6.Fuel Pin temperature 839.5 K EA05-020, Revision Q "Fuel Temperature Correlatlon Generation With INTERPIN-3,"December 2005.Enriched Pellet Dish and Chamfer Volume Enriched Pellet Dish Volume =0.94%Enriched Pellet OLTvolume
=o.2%AREVA Drawing 02-5056842A1, Revislon O,"UO2 Pellet," March 2005-Blanketed Pellet Dish, and ChamferVolurneBlanketed Pellet Dish Volurne =0.82%Blanketed Pellet OLTvolume =o.2%AREVA Drawlng 02-5056847A1, Revislon 0, "Blanket Pellet," February 2005.Stack Density blanket fuel 10.4143 g/cm3 EA08{34 Revision Q "Cycle 26 Design Deptetions," March20O9. Pase 31.Attachment 10.1FC08514 Page 4 of 7 TODI*E-1 G-OPPt)-{Xrl ReYision 1 PagG 4 2. CE 14 x 14 fusembh Parameters General Assembly lnformation for ARR/A Batch DD (Cycle 25 Depletions) EA07{03, Tables 3.3, 3.4 and 3.7 are appropriate for Batch DD. Table 3.7 is calculated in EA07-003 and remalns valid.lnformation Value Reference Rated Core Power (without uncertainty) 1500 MWth Fort C-al hou n Technical Specffi cations, Deflnitions Page L.Average Assembly Power 1500MWth / 133 fuel assemblies =LL.278 MWth/assembly Fort Calhoun Technical Specifi cations, Definitions Page t.EA07{03, Revlsion Q "Cycle 25 Design Depletions," June 2007. Paee 51.Assembly Pitch (corel 8.18 ln OPPD Drawing J-2386G164-033(11541), Revision 6, "Fuel Alignment Plate (11541)"November 18, 1968.Fuel Rods per Assembly i 175 t i l , I i I ANP-2705(P), Revlsion 1, "PWR I FuelDesign Criteria Reviewfor I fort Calhoun Reload FCA1-25! (FTC-11) and Cycle 25ANP-2705(P), Revision 1, "PWR Fuel Design Criteria Review forFort Calhoun Reload FCA1-25 Revision 0 Attachment 10.1FC08514 Page 5 of 7 TODI*E-1&OPPD-001 Revision'lPage 5 (FrC-11) and Cycle 25 Assemblies." Julv 2011.Fuel Rod Pitch0.58 in AREVA Drawing 02-5036725A1, Revision g "Spacer Grid Assemblv HTP," Mav 2(X)4.Reference Core loading - U 50.6702 MTUEA08-017, Revision 0, "Cycle 25 CECOR Coeffi cient Generation,"June 2008. Paee 31.Reference Assembly Loading -u02 386,s97 kgEA08-017, Revision 0, "Cycle 25 CECOR Coeffi cient Generation,"June 2008. Pase 26. Reference Assembly Loading -U 15.578 kg EA08-017, Revision 0, "Cycle 25 CECOR Coefficlent Generation," June 2@8. Paee 26.Non welded Clad Length 6.20 in AREVA Drawing 02-5056837A1, Revision 2,"Fuel Rod Assembly UO2,* )ulv2OO7.Fuel Stack Length 129.3 in AREVA Drawing 02-5056837A1,Revislon 1, "Fuel Rod Assembly UO2." Aoril 2007.Nominal Pellet OD 0.3805ln AREVA Drawing 02-5056842A1, Revision 0, "UO2 Pellet," Februarv 2005.NomlnalClad OD 0.440 in AREVA Drawing 02-5056835A1, Revision Q "Cladding," February 2005.NominalClad lD0.387 in AREVA Drawing 02-5056835A1, Revision 0, tladding," February 2m5.Guide Tube lD 1.035 in AREVA Drawing 02-5038187A1,Revision 1, "Guide Tube,'Februarv 2fi)5.Guide Tube OD 1.115 in AREVA Drawing 02-5038187A1,Revision 1, "Guide Tube," Februarv 2006.Nomlnal Fuel Pellet Density 96%AREVA Drawing 02-5056842A1, Revision O, "UOz Pellet," Februarv 2005.Power per MTU Cl.dding [{.t"rial 29.6032 MWD/MTU M5 EA08{17, Revision 0, "Cycle 25 CECOR Coefficient Generatlon," June 2008. Page 31.ANP-2705(P), Revision L "PWRFuel Design Criteria Review forFort Calhoun Reload FCA1-25 (FrC-11) and Cycle 25 i s I Assemblies ," July ZOLL.Revision 0 Attachment 10.1 FC08514 Page 6 of 7 TODl-BE-16-0PPD-001 Remlon 1 Page6 !I Guide Tube Material (without sleeves) ! MS I ANP*2705(P), Revision 1, "'PWR Fuel Design Criteria Review for i Fort Calhoun Reload FCAl-25 (FTC-11) and Cycle 25 Assemblies," July 2011. Clad Material Composition-MS -AREV A Specification
- 08-(in percent by material) 1023224-G2, Revision 2, "Material Specification MS Sheet." (Average of minimum and maximum values) Nominal wt% U235 12 assemblies at 4.001 EA07 -003, Revision 0, .,Cycle 25 16 assemblies at 4.194 ! Design Depletions," June 2007. 16 assemblies at 4.336 Page 18. Reactor Coolant System: Tavg 567.6 F TOB 111.1, Revision 14, "Tave Program," October 27, 2006. Fuel Pin temperature I 839.5 K EAOS-020, Revision 0, .,Fuel Temperature Correlation Generation With INTERPIN-3, 11 December 2005. Enriched Pellet Dish and 1 Enriched Pellet Dish Volume= AREVA Drawing 02-5056842Al, Chamfer Volume 0.94% Revision 0, "U02 Pellet," Enriched Pellet Ol T volume :: February 2005. 0.2% Blanketed Pellet Dish, and Blanketed Pellet Dish Volume = AREVA Drawing 02*5056847A1, Chamfer Volume 0.82% ! Revision 0, .,Blanket Pellet," ! ! Blanketed Pellet Ol T volume :: 1 February 2005. I I 0.2% ; Stack Density blanket fuel 10.4143 g/cm 3 EA07..()()3, Revision 0, .,Cycle 25 I 3. Bum-up Map for Cyde 28 coastdown EA16-023 projections 14.51 GWD/MTU, 10 ppm Boron Design Depletions," June 2007. Page 30. ... 1 2 3 5 6 ., 8 9 10 11 12 13 ... l 53.172 55.041 So&.873 53.121 01 2 39.334 38.203 4,.359 16.321 32.557 16.277 44.3*5 38.154 39.363 02 3 39.869 43.5?6 16.972 17.911 37.076 20.164 37.063 17.905 16.976 tl.SSO 39.848 03 ' 40.383 35.764 37.823 20.529 39.215 20.504 16.911 40.198 04 5 38.520 44.863 17.978 37.844 45.947 37.580 50.654 37.568 45.992 37.846 17.977 44.848 38.109 05 6 ,2.541 17.175 37.436 20.672 37.711 !9.971 37.501 19.955 37.651 20.655 37.417 17.142 42.481 06 7 33.502 20.563 39.434 50.776 37.409 52.803 37.428 50.779 39.432 20.564 33.500 07 8 ,2.484 17.14: 37.418 20.653 37.646 19.949 37.513 19.976 37.7:3 20.673 37.435 17.175 42.545 08 9 38.1'02 H.85l 17.976 37.850 45.99t 37.563 50.65!> 37.583 -45.945 37.851 17.976 44.878 38.520 09 I i I i ; i I ,0.198 :6.911 35.714 37.813 20.5C3 39.216 20.529 37.826 35.763 16.893 10 :1 39.850 43.547 16.977 17.905 37.066 2C.16t 37.C74 :7.918 16.971 43.580 39.869 ll :2 39.315 38.154 44.340 16.276 32.555 16.321 44.355 38.2C4 39.348 12 ::&3 53.125 54.936 55.024 53.174 13 ,.. N-!4-L* K-.... H* G-F-B-D-C-B* A-Revision 0 FC08514, RO EC 68969 54 Attachment 10.1FC08514 Page 7 of 7 TODI-BE-16OPPD{01 Rcvlslon 1 Page Z 4. Unerahtywlth Burnup Predlctlon 6% is acknowledged as the burnup uncertainty
Reference:
EA0&q)1, Revision 0, "GARDEI Core Mon]torlng Code lmplementatlon," May 2(X)8.Revision 0 Attachment 10.2 (:SHUFFLE-HEADER
- PLANT-ID
- OPPD :DATE 03 l24l20l 5)DD4r 4.00 41382 0 0.38s411 031241201s 3.85 03/24/2015 AA44 4.30 46172 0 0.372690 0312412015 4.30 0312412015 AA43 4.30 45623 0 0.372802 0312412015 4.30 0312412015 DD42 4.00 41297 0 038s429 031241201s 3.85 031241201s cc08 4.00 44984 0 0.388807 0312412015 3.99 0312412015 cc03 4.00 41020 0 0.388864 03/2412015 3.99 03/2412015 2020 3.68 418s6 0 0.372111 0312412015 3.68 0312412015 FF01 4.00 14936 0 0.386595 0312412015 4.280312412015 EE30 4.00 32033 0 0.385374 0312412015 3.86 031241201s FF02 4.00 14877 0 0.386747 03/24120rs 4.28 03124/20ts AA37 4.28 48361 0 0.372396 0312412015 4.28 03124/2015 cc04 4.00 40984 0 0.389186 0312412015 3.99 03124/201s cc07 4.00 45036 0 0.388662 031241201s 3.98 031241201s BBls 4.09 45314 0 0.373381 0312412015 4.09 0312412015 EE07 4.00 27479 0 0.389134 031241201s 4.ts 03124120rs FF09 4.00 15880 0 0.385997 0312412015 4.25 0312412015 FFlT 4.00 16525 0 0.384329 031241201s 4.02 0312412015EEOl 4.00 32665 0 0.389s72 031241201s 4.ls 031241201s FF2l 4.00 17667 0 0.384041 0312412015 4.02 0312412015 EE02 4.00 32s75 0 0.389434 031241201s 4.15 031241201s FFl8 4.00 16490 0 0.384304 031241201s 4.02 031241201s FFl0 4.00 1s879 0 0.385738 03124/2015 4.2s 03124/2015EE08 4.00 27s6s 0 0.389308 0312412015 4.15 031241201s 8816 4.09 4s300 0 0.373470 03/241201s 4.09 0312412015DD40 4.00 431s6 0 0.385195 0312412015 3.85 0312412015 FF13 4.00 1s802 0 0.38s782 0312412015 4.2s 0312412015 EE36 4.00 348s4 0 0.385318 0312412015 3.86 03124/201s EE24 4.00 34507 0 0.386356 0312412015 4.03 03124/2015 FF33 4.00 17208 0 0.383038 03/24120rs 3.86 031241201s DDlg 4.00 48987 0 0.385075 0312412015 4.03 031241201s FF34 4.00 17214 0 0.382980 0312412015 3.86 03/24/2015 EE23 4.00 34475 0 0.386rs6 0312412015 4.03 03/2412015 EE35 4.00 34832 0 0.385329 031241201s 3.86 031241201s FF14 4.00 15817 0 0.385842 03124/201s 4.2s 03124/201sDD38 4.00 43099 0 0.385442 03l24DAl5 3.86 031241201s DD30 4.00 45889 0 0.38s747 031241201s 4.03 0312412015FF2s 4.00 16464 0 0.3843s3 03124120t5 4.03 0312412015 EE20 4.00 34434 0 0.386599 031241201s 4.03 0312412015 EEl2 4.00 33432 0 0.389367 0312412015 4.15 0312412015DD03 4.00 482s1 0 0.388472 03124120rs 4.ts 0312412015EE27 4.00 34100 0 0.386372 0312412015 4.03 03124/2015DD04 4.00 48204 0 0.388446 0312412015 4.15 0312412015 EEl l 4.00 33420 0 0389273 031241201s 4.15 03124/201s EEl9 4.00 34J13 0 0.3866s1 0312412015 4.03 03124/201s FF26 4.0016488 0 0.384319 03/241201s 4.03 031241201s DD32 4.00 4s812 0 0.38s673 03/24/2015 4.03 03124/201sBB39 3.84 41847 0 0.370731 0312412015 3.84 03124/201s 8836 3.83 418s7 0 0.371029 031241201s 3.83 03124/2015 FF0s 4.00 15143 0 0.387041 0312412015 4.28 03/24/20rs EEl3 4.00 32913 0 0.389371 031241201s 4.ls 0312412015 FF37 4.00 17188 0 0.383066 0312412015 3.86 031241201s DD08 4.00 48733 0 0.388210 0312412015 4.15 0312412015FC08514 Page 1 ot24 Revision 0 FF29 4.00 16803 0 0.3g3904 o3r24r2or5 4.03 l3r24/?Attachment 10'2 DDl0 4.00 33730 0 0.388627 03124120rs 4.ts 0312412015 FF30 4.00 16908 0 0.384319 031241201s 4.02 0312412015 DD07 4.00 48899 0 0.38828s 03/2412015 4.r5 0312412015 FF38 4.00 17196 0 0.383111 0312412015 3.86 03124/2015 EEl4 4.00 32862 0 0.389390 031241201s 4.ls 03124/2015 FF06 4.00 15154 0 0.387020 03/2412015 4.28 03124/2015 DDl6 4.00 40665 0 0.388618 0312412015 4.15 03124/201s DDl5 4.00 40566 0 0.388557 0312412015 4.15 0312412015 EE32 4.00 32462 0 0.385003 0312412015 3.86 0312412015 FF22 4.00 17769 0 0.384044 0312412015 4.02 031241201s DDl7 4.00 49074 0 0.385515 0312412015 4.03 03124/2015 EE28 4.00 34076 0 0.386213 0312412015 4.03 0312412015 DDt2 4.00 33769 0 0.387970 03124120rs 4.15 03124/2015 DD22 4.00 s0296 0 0.38s493 0312412015 4.03 03124/201s DD09 4.00 33752 0 0.388373 0312412015 4.15 03124/2015 EE25 4.00 340910 0.386346 0312412015 4.03 031241201s DD20 4.00 49060 0 0.385361 0312412015 4.03 0312412015 FF23 4.00 17764 0 0.384497 0312412015 4.03 03124/2015 EE29 4.00 324610 0.38s384 03/24120rs 3.86 031241201s DDr4 4.00 40s65 0 0.3877ss 031241201s 4.15 0312412015 DDl3 4.00 40664 0 0.387976 03/24/2015 4.15 0312412015 FF07 4.00 15157 0 0.386707 03/2412015 4.28 03/24/2015 EEl5 4.00 32867 0 0.3891t5 0312412015 4.15 03/2412015 FF39 4.00 17203 0 0.383r8s 0312412015 3.86 03/2412015 DD06 4.00 48882 0 0.388442 0312412015 4.rs 03/241201s FF3r 4.00 16924 0 0.384010 0312412015 4.03 03/2412015 DDl l 4.00 33734 0 0.388273 0312412015 4.rs 03/241201s FF32 4.00 16792 0 0.383586 03/2412015 4.02 03/2412015 DDO5 4.00 48800 0 0.388340 03124/2015 4.t5 03/24/201s FF40 4.00 17178 0 0.383004 031241201s 3.86 03/24120t5 EEl6 4.00 32907 0 0.389190 0312412015 4.15 03124/20rs FF08 4.00 15140 0 0.386718 03124/201s 4.28 0312412015 BB33 3.84 41858 0 0.370547 031241201s 3.84 0312412015BB30 3.84 41846 0 0.370586 03/2412015 3.84 0312412015 DD29 4.00 458r2 0 0.38s638 0312412015 4.03 03124120rs FF27 4.00 16493 0 0.384517 03124/201s 4.03 031241201s EEr S 4.00 34376 0 0.386679 0312412015 4.03 031241201s EEl0 4.00 33426 0 0.389236 03124/201s 4.15 03124/2015 DDOl 4.00 48208 0 0.388610 0312412015 4.r5 0312412015 EE26 4.00 34048 0 0.386401 03124/201s 4.03 0312412015DD02 4.00 482s3 0 0.388623 031241201s 4.ts 031241201s EE09 4.00 33427 0 0.389228 0312412015 4.r5 0312412015 EElT 4.00 34430 0 0.38629s 03124/201s 4.03 03124/2015 FF28 4.00 164s9 0 0.384s97 03124/2015 4.03 03124/2015 DD3l 4.00 4s891 0 0.385633 0312412015 4.03 03124/201s DD39 4.00 43098 0 0.386196 031241201s 3.87 0312412015 FFl5 4.00 15821 0 0.385249 03124/2015 4.25 0312412015 EE34 4.00 34827 0 0.38s207 03124/2015 3.86 03124120t5 EE22 4.00 34478 0 0.386389 03124/201s 4.03 03124/201s FF3s 4.00 17220 0 0.382814 0312412015 3.86 03124/201s DDl8 4.00 48980 0 0.385043 031241201s 4.03 03124/2015 FF36 4.00 17210 0 0.382882 03124120t5 3.86 03/24/201s EE2l 4.00 34508 0 0.386632 0312412015 4.03 03/2412015FC08514 Page 2 ol 24 EE33 4.00 34858 0 0.385002 03/2412015 3.86 03r24r7fi\'3n'"nt to'z FFl6 4.00 15799 0 0.385980 031241201s 4.25 031241201s DD37 4.00 43157 0 0.386732 031241201s 3.87 03/24/2015 BB05 4.09 4s301 0 0.373421 03124/2015 4.09 03124/2015 EE05 4.00 27569 0 0.389285 0312412015 4.15 0312412015 FFI r 4.00 r5883 0 0.385600 031241201s 4.25 03124/2015 FFlg 4.00 16494 0 0.384197 0312412015 4.02 0312412015 EE03 4.00 32579 0 0.389471 0312412015 4.15 0312412015 FF24 4.00 17670 0 0.384379 0312412015 4.03 031241201s EE04 4.00 32666 0 0.389406 03124/20rs 4.ts 03/24/2015 FF20 4.00 16524 0 0.384436 0312412015 4.02 0312412015 FFl2 4.00 15878 0 0.385876 0312412015 4.25 0312412015 EE06 4.00 27476 0 0.389175 0312412015 4.t5 03124/201s 8806 4.09 45312 0 0.373396 0312412015 4.09 0312412015 cc06 4.00 4s037 0 0.389209 03124/201s 3.99 03124/201s cc09 4.00 40986 0 0.389185 0312412015 3.98 0312412015 AA40 4.28 48362 0 0.372437 031241201s 4.28 0312412015 FF03 4.00 t4879 0 0.386799 031241201s 4.28 0312412015 EE3l 4.00 32039 0 0.385236 0312412015 3.86 0312412015 FF04 4.00 14936 0 0.3868s6 031241201s 4.28 0312412015 Z0213.69 41851 0 0.37204s 0312412015 3.69 0312412015 cc10 4.00 4r0r7 0 0.389334 031241201s 3.99 03124/2015 cc05 4.00 44983 0 0.388978 0312412015 3.99 03124/201s DD43 4.00 41303 0 0.38s37s 031241201s 3.8s 03124/2015 AA42 4.30 4s624 0 0.3727s1 0312412015 4.30 031241201s AA4l 4.30 46172 0 0.372962 03124/2015 4.30 03/24/2015 DD44 4.00 41378 0 0.38s420 03/2412015 3.85 03/24/20rs GGOI 3.76 0 20 0.386803 0310412015 3.63 03/0412015 GG02 3.76 0 20 0.387593 0310412015 3.63 03/04120t5 GG03 3.76 0 20 0.387466 031041201s 3.63 03/041201s cc04 3.76 0 20 0.386906 0310412015 3.63 0310412015 cG05 3.76 0 20 0.387838 0310412015 3.63 03104120rs GG06 3.76 0 27 0.387418 02125120rs 3.63 0212s12015 GG07 3.76 0 20 0.387502 03104120rs 3.63 03104120rs GG08 3.76 0 20 0.3870s8 0310412015 3.63 031041201s cc09 3.73 0 27 0.386394 02125/20rs 3.61 0212s12015 GGl0 3.73 027 0.386320 0212512015 3.61 02l2sl20ls GGl l 3.73 0 27 0.38683t 02/2sl20ts 3.61 0212s120r5 GGl2 3.73 0 27 0.386210 02/2s12015 3.61 021251201s GGl3 3.73 0 20 0.386116 03/0412015 3.61 0310412015 GGl4 3.73 0 20 0.387240 03/041201s 3.60 0310412015 GGl5 3.73 0 20 0.387086 03/0412015 3.60 0310412015 GGl6 3.73 0 34 0.386770 02/l8l20ls 3.61 02/1812015 GGIT 3.3s 0 34 0.3844s0 02/1812015 3.27 02/18/2015 GGls 3.3s 0 34 0.384486 02/r8l20ts 3.27 02118/2015 ccl9 3.35 0 34 0.384s8s 0211812015 3.27 02/l8l20lsGG20 3.3s 0 20 0.384600 0310412015 3.27 03/04/20t5 GG2r 3.3s 0 20 0.384541 0310412015 3.27 0310412015 GG22 3.35 0 27 0.38439s 02/2512015 3.27 02125/201s GG23 3.35 0 27 0.384383 021251201s 3.27 02125120t5GG24 3.35 0 27 0.384485 0212512015 3.27 02/25120rs GG25 3.35 0 27 0.384635 0212512015 3.27 021251201sGG26 3.35 0 27 0.384633 0212512015 3.27 0212512015 cG27 3.35 0 2t 0.384707 0212512015 3.27 0212s12015FC08514 Page 3 of 24 GG28 3.35 0 27 o.3g44or 02r25/zor5 3.27 o2l2slzotinachment 10 2 GG29 3.35 0 l3 0.384599 03/lv20rs 3.27 03lltl20l5 GG30 3.3s 0 l3 0.384s70 031112015 3.27 03lttl20l5 GG31 3.35 0 13 0.384481 03llll20l5 3.27 03llll20l5 GG32 3.35 0 13 0.384512 03llll20l5 3.27 03llll20l5 GG33 3.35 0 13 0.384374 03llll20t5 3.27 03ltll20l5 GG34 3.35 0 t3 0.384647 03llv20l5 3.27 03ltrl20ls GG3s 3.35 0 13 0.384387 03llll20l5 3.27 03lrr/2015 GG36 3.35 0 l3 0.384708 03llll20l5 3.27 03lll/2015 GG37 3.35 0 13 0.384596 03llll20l5 3.27 03llll20l5 GG38 3.35 0 13 0.384148 03llll20l5 3.27 03lttl20ls GG39 3.35 0 l3 0.384683 03llll20r5 3.27 03llll20t5GG40 3.3s 0 t3 0.384462 03llll20l5 3.27 03/lll20t5 HA34 3.48 33387 10244 0.357966 0310711987 3.48 0312411987 D0362.97 3334612849 0.372728 0l/18/1980 2.97 04116/1980 D0422.97 3334612849 0.372172 0l/18/1980 2.97 0411611980 rA28 3.sl 36088 10769 0.357363 091281198s 3.51 t2l08ll98srA29 3.51 3612410769 0.357223 0912811985 3.51 1210811985 HA26 3.48 37219 10769 0.3s7592 091281198s 3.48 r2l08lt98s A031 l .38 9026 r46s4 0.372313 02108/1975 1.38 04/1011975 Bt04 2.37 20080 14054 0.3ss704 rDl}tl 1976 2.37 1210811976 HA I 8 3.48 37219 10769 0.3s7004 091281198s 3.48 12108/198srA30 3.51 36124 10769 0.3s7860 0912811985 3.51 1210811985 D044 2.97 3334612849 0.372510 0l/18/1980 2.97 04116/19808103 2.37 22090 t4054 0.3548s9 l0l0lll976 2.37 12/0811976 A022 1.39 7842 14654 0.372793 0210811975 r.39 0411011975 A024 1.39 8439 146s4 0.372167 021081197s 1.39 0411011975 B2t7 2.38 22810 140s4 0.352194 l0l0lll976 238 1210811976 D034 2.97 33748 12849 0.372135 0l/18/1980 2.97 041161t980 D037 2.97 3374812849 0.371912 0l/18/1980 2.97 04/1611980 80022.37 2704113690 0.353537 0913011977 2.37 tyt6/t977 4034 l .39 8439 14654 0.371428 0210811975 1.39 04/1011975 A0261.39 9026146s4 0.370167 02/081197s 1.39 04lt0lt97s GOl9 3.02 31973 fi799 0.362020 1210311982 3.02 0211811983 G004 3.02 332s3 tt799 0.363l68 12103It9823.02021l8lt983 tA32 3.51 36124 10769 0.357101 091281198s 3.51 t2l08ll98sG036 3.02 36183 10244 0.364700 0310711987 3.02 0312411987G024 3.02 31973 lL799 0.363194 1210311982 3.02 02118/1983D03s 2.97 3334612849 0.372246 0l/18/1980 2.97 0411611980 JA35 3.sl 38788 9166 0.3ss086 021t711990 3.51 0311211990 HA37 3.48 37219 10769 0.3s6980 0912811985 3.48 r2l08lt98s HAlT 3.48 37219 10769 0.356843 091281r98s 3.48 12108/1985 G02r 3.02 33253 t t7 99 0.363 I 05 l2l 03 I 1982 3.02 021 l8l 1983G027 3.02 332s3 rt799 0.363469 1210311982
? 02 0211811983HA2s 3.4837219 10769 0.3s7236 0912811985 3.4812/0811985 HA29 3.48 33061 10244 0.3s8162 0310711987 3.48 03/24/1987 8112 2.72 30618 12241 0.363930 09/1 8/1981 2.72 l2/01/198t Et04 2.72 30618 12241 0.364565 09/18/1981 2.72 t2l0t/1981 HA31 3.48 33061 10244 0.3s8229 0310711987 3.48 03124/1987 HA32 3.48 33387 10244 0.358303 0310711987 3.48 03124/1987 rA2s 3.51 36088 10769 0.357023 0912811985 3.sl 12108/1985 Btt3 2.37 22030 14054 0.353997 l0l0llt976 2.37 12/0811976 Bl l0 2.38 22090 14054 0.353638 l0l0vr976 2.38 1210811976 JAzt 3.513s80s 10244 0.355636 0310711987 3.5t 0312411987 FC08514 Page 4 oI 24 Revision 0 Aftachment 10.2 HA33 3.48 33387 10244 0.357979 03107/1987 3.48 03/2411987G026 3.02 3 l 07 I I t7 99 0.36397 4 l2l 03 I 1982 3.02 02/ t8/ 19838220 2.41 22660 140s4 0.354481 t0l0ut976 2.41 1210811976 A0l6 1 .40 784214654 0.371694 0210811975 1.40 0411011975 A042 r.39 784214654 0.372978 0210811975 1.39 04/10/1975 D0412.97 30218 12849 0.372380 0l/18/1980 2.97 04/16/1980 G028 3.02 31071 fi799 0.363818 1210311982 3.02 0211811983 F0t2 3.02 32398 12241 0.364179 09/l 8/l 98 I 3.02 t2l0r / r98r D009 2.96 302 l 8 12849 0.37 1249 0 I /l 8/ I 980 2.9 6 041 I 6/ 1980 A00l 1.40 7913 146s4 0.374609 0210811975 1.40 04/1011975 4039 1.40 7913 14654 0.37131s 0210811975 1.40 04/1011975 E009 3.03 30324 t2241 0.364641 09 I l8l l98l 3.03 r2l0l I l98lF003 3.01 3239812241 0.364707 09i l8/1981 3.0r 12/01/1981 r{r2 3.st 34980 10769 0.3s6890 091281198s 3.5t t2/08/1985 IA22 3.5135805 10244 0.3s4637 0310711987 3.5r 03/2411987 FI}t 2.74 30618 122410.364407 09/l8/1981 2.74 t2/0llt98t Et09 2.72 30618 1224t 0.364306 09/18/1981 2.72 12101/1981 HAl6 3.48 37338 10769 0.357586 091281198s 3.48 1210811985 IA13 3.s l 34980 10769 0.3s7s40 0912811985 3.5r t2/08/t98s rAls 3.s1 34980 10769 0.357357 0912811985 3.sr 12108/198sD039 2.97 3334612849 0.372766 0l/18/1980 2.97 0411611980 HA213.48 33061 10244 0.357581 0310711987 3.48 0312411987rAl6 3.sl 34980 10769 0.3s6948 0912811985 3.51 r2l08lt98sG037 3.01 3981s 10769 0.364435 091281198s 3.01 l2l08/1985 E00I 3.03 32830122410.364744 09/l8/198I 3.03 t2/01/t98tG038 3.01 39343 10769 0.364789 091281198s 3.01 12108/1985E005 3.03 32830122410.364742 09/l8/l98I 3.03 t2l0tll98t JA09 3.s l 38792 10244 0.35s130 0310711987 3.51 03124/1987E006 3.03 32830 122410.365235 09/l8il98l
3.0 31210y1981
pl07 3.60 37854 7851 0.349992 09/2s11993 3.60 10i08/1993 pl06 3.60 37809 78s10.349805 09/2511993 3.6010106/1993 E007 3.03 32830 122410.365071 09i18i1981
3.0 3l2l0lll98l
JAl0 3.51 38792 10244 0.3ss962 0310711987 3.51 0312411987 A011 r .39 7913 14654 0.374684 0210811975 1.39 04ll0ll97s Gol3 3.03 4t606 10244 0.362815 0310711987 3.03 031241t987 G020 3.02 41606 t0244 0.363463 03107/1987 3.02 031241t987 c023 3.02 41606 t0244 0.363349 0310711987 3.02 03124/t987 G030 3.02 41606 10244 0.363s12 0310711987 3.02 0312411,987 ,4008 I .40 82s214654 0.376111 02/08/1975 1.40 04110/1975 A0l9 1.39 ls3l0 13310 0.3719s4 t0lts/19781.39 t2lt0lt978 G006 3.02 42169 lL344 0.363047 03 1021 1984 3.02 061 r81 1984 Gol0 3.02 42169 11344 0.362847 03102/1984 3.02 06118/1984 G0t7 3.02 42169 11344 0.362825 03102n984 3.02 061t811984GOl8 3.02 42169 11344 0.362864 0310211984 3.02 06118/1984 A0321.39 15310 133l0 0.370902 t0lt5lt9781.39 t2lt0lt978 Bt23 2.37 22030 140s4 0.354377 t0l0yt976 2.37 t2/081r976 B109 2.38 22090 14054 0.3s3315 t0l0yt976 2.38 1210811976 JA33 3.51 39106 9166 0.3551310211711990 3.5r 03/1611990 JA32 3.st 39278 9166 0.3ss661 0211711990 3.51 0311611990 Btot 2.37 22090 14054 0.35420r t0l0t/1976 2.37 t210811976 81 1 4 2.37 22090 1 40s 4 0.3s4509 10 1 0u 197 6 2.37 t2/ 081 197 6 8008 2.38 27041 13690 0.370709 0913011977 2.381t/1611977 800t 2.37 2704t 13690 0.372140 0913011977 2.37 tvt6/t977 8003 2.37 27041 13690 0.372140 0913011977 2.37 tur6lt977 FC085'14 Page 5 of 24 Revision 0 Boo4 2.37 27041 136e0 0.372140 ost3o/1s77 2.37 fiff6mT+to Ett3 2.7227932 12849 0.363579 0l/18/1980 2.72 04/16/1980 Et}s 2.72 27932 12849 0.363561 0l/18/1980 2.72 0411611980 Et08 2.72 27932 12849 0.364188 01/18i 1980 2.72 0411611980 Ett} 2.72 27932 12849 0.364156 01/18/1980 2.72 0411611980 A.028 1.38 15310 13310 0.370816 t0llsll978 t.38 t2ll0ll978 A0291.38 15310 I3310 0.370274 t0ltsl1978 t.38 t2lt0l197I tA29 3.5139834 9166 0.3s5824 0211711990 3.51 03112/1990 HA15 3.48 39859 t0769 0.357572 0912811985 3.481210811985 A02l l .3915667 r3310 0.371048 l0ll5lt978 t.39l2ll0ll978 A025 1.39 15667 13310 0.37123210115/19781.39 t2ll0ll978 F002 3.01 32398122410.364681 09/18/1981 3.01 t2l0lll98l JA08 3.s l 39570 9674 0.35491s 0912711988 3.sl l0/30/1988 KA223.49 396209674 0.339385 09/2711988 3.49 10/30/1988 KAl3 3.30 39620 9674 0.3s9640 0912711988 3.30 10/30/1988 JAI I 3.51 38972 9166 0.355915 0211711990 3.51 0311611990F004 3.01 3239812241 0.364266 09i18/1981 3.01 l2l0r/r981 B2t0 2.38 22190 r40s4 0.354792 1010l/1976 2.38 12/0811976 HA36 3.48 38933 10769 03s7s48 0912811985 3.481210811985 HA38 3.48 38933 10769 0.358240 091281198s 3.48121081198s HA40 3.48 38933 10769 0.3s7283 0912811985 3.4812/0811985 HAl0 3.48 369s3 9674 0.357s08 091271t988 3.48 l0/30/1988 B2tr 2.38 22t90 r40s4 0.354658 l0l0lll976 238 1210811976 c007 3.19 2739613690 0.373380 0913011977 3.19 I lll6lt977 c009 3.19 2764213690 0.370411 0913011977 3.19 tt/161r977 KA29 3.51 385s7 96740.3385600912711988 3.51 10/30/1988 KAlT 3.50 38ss7 9674 0.33927s 0912711988 3.50 10/30/1988 col5 3.18 2764213690 0.371193 0913011977 3.18 1t/t611977 c014 3.18 27642 13690 0370322 0913011977 3.18 1 tll6ll977 D00t 2.96 28394 r 3310 0.371s67 t0ltslt978 2.96 t2lt0lr978 D004 2.95 28394 13310 0.372248 l0ll5lt978 2.9s l2ll0ll978 D007 2.96 28394 I 33 I 0 0.37 0829 tOl l 5 / 197 I 2.96 t2/ t 0 I 197 8 D008 2.96 28394 133 l0 0.371708 l0lt5lt978 2.96 12/10/1978 D0t62.9s 28394 r33l0 0.372148 tOlI5I19782.9s 12/10/1978 D0t7 2.96 28394 13310 0.371586 r0lt5ll978 296 t2lt0lt978 D0l8 2.9s 28394133r0 0.372109 l0ll5lt9782.9s 1211011978 Efit 2.7227677 12849 0.364382 0l/18/1980 2.7204116/1980 4,036 I .40 8439 146s4 0.370801 021081t97s 1.40 0411011975 A033 1.39 1s667 13310 0.370965 l0ll5lr978 t.39 t2ll0lt978 pr l4 3.60 37346 78sl 0.349927 0912s1r993 3.60 10108/t993 KA08 3.49 42296 9674 0.3s5s75 0912711988 3.49 l0/30/1988 A030 1 .3815667 133r0 0.371626l0llsll9781.38 t2lt0lt978 4007 1 .40 849414654 0.376427 02108/r97s 1.40 0411011975 8222 2.4 1 22660 t 40s 4 0.3 s2802 r0 l 0 U t97 6 2.4 1 121 08 1 197 6 rA40 3.5 r 38091 10769 0.357766 091281198s 3.s l l2108/1985 HAI l 3.48 398s9 10769 0.356794 0912811985 3.48121081198sG025 3.02 39051 11344 0.363365 0310211984 3.02 06118/1984 HA35 3.48 38933 10769 0.3s7s46 0912811985 3.4812108/198s 8223 2.40 22660 14054 0.353601 t0l0ut976 2.40 1210811976 EOl2 3.03 2644212849 0.363947 0l/18/1980 3.03 0411611980E014 3.04 36880 122410.363130 09/r8/198r 3.0412/01/1981 E0ls 3.04 36880 122410.363416 09/18/1981
3.0 41210U1981
E0l7 3.04 36880 1224t 0.363643 09/18/1981 3.04 l2l0lll98r HA39 3.48 33387 10244 0.3s7292 0310711987 3.48 03/2411987FC08514 Page 6 of24 E0r6 3.04 26442 t2s4s 0.3637760l/18/re80 3.04 o4ffilTlq$6'o,F008 3.03 29083 122410.366603 09/18/1981 3.03 l2l0lll98lF009 3.02 29083 12241 0.3663 19 09118/1981
3.0 2l2l0tlt98t
JA13 3.sl 39669 10244 0.3ss653 0310711987 3.510312411987 JAl4 3.51 39669 10244 0.355647 0310711987 3.5r 0312411987 rA04 3.51 27167 10769 0.357470 0912811985 3.51 12108/1985 rA08 3.51 27167 10769 0.357665 0912811985 3.sl 12108/1985 D025 2.96 27608 13310 0.3726s9 tDlrsl1978 2.96 t2/10/1978 D03t 2.96 33748 12849 0.372769 0l/18/1980 2.96 0411611980D026 2.96 27608 13310 0.372652 1011511978 2.96 l2/t011978 D0322.97 3374812849 0.372054 01/18/1980 2.97 04/1611980 8206 2.37 29014 13690 0.3s4452 09130/1977 2.37 1111611977 81022.37 28s6413690 0.353537 0913011977 2.37 rtlt6lt977 BttT 2.38 28s64 13690 0.3s3448 0913011977 2.38 ll/16/1977 Ettg 2.72 27932 12849 0.363928 0l/18/1980 2.72 0411611980 Et20 2.72 27932 12849 0.3631 17 0tll8ll980 2.72 0411611980 F0 1 1 3.02 39667 I 17 99 0.364417 12103 / 1982 3.02 021 l8l 1983 8209 2.38 22190 I 405 4 0.3 s s0 I 2 l0 I 0t I r97 6 2.38 t2l 08/ r97 6 B2t2 2.38 22810 14054 0.3549A2 t0l}lll976 2.38 1210811976 F00l 3.02 39667 fi799 0.364499 1210311982 3.02 02118/1983EOl3 3.04 39667 rr799 0.363836 12103119823.0402118/1983 Bttg 2.37 2856413690 0.353468 0913011977 2.37 ltlt6lr977 B2t8 2.38 22810 140s4 0.352503 l0l0tlt976 2.38 1210811976 A003 1.38 8638 146s4 0.37 l3s4 021081197s 1.38 04/10/r97s A035 l .39 15667 r3310 0.37r20s l0lr5lt978 t.39 l2lt0lt978 B2t9 2.38 22810 t40s4 0.353384 t1ljlll976 238 1210811976 Bt20 2.37 28564 13690 0.3s3930 0913011977 2.37 l1/t6/r977 Bt05 2.37 28s64 r3690 0.354479 0913011977 2.37 trlt6lt9778204 2.37 22810 14054 0.3s4280 r0l0vt976 2.37 1210811976 A044 1.39 15667 133 l0 0.370506 l0ll5ll978 1.39 r2ll0ll978 A04s I .39 15667 13310 0.37144210115119781.39 r2lt0lt978 8006 2.39 27041 13690 0.372876 0913011977 2.39 tvl6ll977 8208 2.38 2901413690 0.353888 0913011977 2.38ll/16/1977EOl8 3.03 39667 11799 0.364477 12103119823.03 02118/1983 F005 3.02 39667 fi799 0.365234 1210311982 3.02 02118/1983 B005 2.37 77041 13690 0.354479 09130/1977 2.37 rt/r6/r977 Bl08 2.38 28s6413690 0.3s22s4 0913011977 2.38ll11611977 G044 3.03 38488 10244 0.364029 0310711987 3.03 03124/1987 E021 3.03 39667 11799 0.364331 12103119823.03 02/18/1983 F006 3.03 39667 11799 0.364971 1210311982 3.03 02/18/1983 82022.37 2901413690 0.354817 091301t977 2.37 ll11611977 8203 2.37 29014 r3690 0.354085 09/3011977 2.37 tut6lt977F010 3.02 39667 rr799 0.364368 12/0311982 3.02 0211811983 KA20 3.49 3368410244 0.339397 0310711987 3.49 0312411987 KA24 3.49 33684 10244 0.339696 0310711987 3.49 03/2411987 c010 3.18 3s491 13310 0.370021 l0lt5lt9783.l8l2ll0lt978 rAll 3.51 34980 10769 0.357816 0912811985 3.5r 1210811985 A0l4 I .39 9026 146s4 0.372467 021081197s 1.39 0411011975 D002 2.9 6 27 388 l 33 1 0 0.372267 l0 I t 5 I r97 8 2.96 12/ l0 / 197 8 G033 3.0r 38488 10244 0.365073 03/0711987 3.0t 03/24/1987 rA03 3.sl 38s57 96740.3s73s00912711988 3.sl 10/30/1988 D0t1 2.96 27388 13310 0.373103 l0ll5l1978 296 r2lt0lt978 4020 l .39 902614654 0.370s47 0210811975 r.39 0411011975 B2t4 238 22810 14054 0.3s4s30 l0l0lll976 2.38 1210811976 FC08514 PageT ot24 Revision 0 p10l 3.60 37400 TBst 0s4s747 ostzsnss3 3.60 rorcihli.BB3"'o' rA35 3.51 38091 10769 03569s4 0912811985 3.5r 1210811985 IA39 3.sl 38091 10769 0.357640 09128/t98s 3.sl 12108/1985 pl02 3.60 37744 78st 0.3498t4 0912s11993 3.60 t0/08/1993 B2t5 2.38 22810 14054 0.354247 l0l0l11976 2.38 t2/0811976 D010 2.96 27608 13310 0.372764 l0ll5lr978 2.96 l2ll0ll978 JA3l 3.s l 38792 t0244 0.3559t7 0310711987 3.51 0312411987 HAOl 3.48 23264 tr344 0.35633 l 03/0211984 3.48 0611811984 HA28 3.48 33061 10244 0.3s8483 0310711987 3.48 0312411987 G00l 3.03 38488 10244 0.363494 0310711987 3.03 0312411987Er03 2.7227677 12849 0.364978 0l/18/1980 2.720411611980 F 103 2.7 4 29637 12241 0.364440 09/l 8/ I 98 I 2.7 4 l2l 0l I l98l Ft04 2.74 29637 12241 0.365063 09/18/1981 2.74 l2l0lll98t IA27 3.5I3646410244 0.355399 0310711987 3.5t 0312411987 JA28 3.51 3646410244 0.355552 0310711987 3.510312411987 Ft05 2.74 29637 12241 0.364946 09/18/1981 2.74 l2l01ll98l Ft06 2.74 29637 r224r 0.365679 09/18/1981 2.74 l2l0lll98lD033 2.97 3334612849 0.372408 0l/18/1980 2.97 0411611980D027 2.96 33748 12849 0.372722 01/18/1980 2.96 0411611980D029 2.97 33748 12849 0.37180s 0l/l8i 1980 2.97 0411611980 D030 2.97 3374812849 0.3721s8 0l/18/1980 2.97 041161t980 rA36 3.sl 38091 10769 0.3s7206 0912811985 3.51 r2l08ll98s cl l6 3.16 2924s 13690 0.362840 0913011977 3.16 1t/16/1977 cr03 3.19 29445 13690 0.363221 0913011977 3.19 1111611977 rA37 3.5r 38091 10769 0.357401091281198s 3.sr r2l08lr98s rA38 3.51 38091 10769 0.356769 091281t985 3.sl 1210811985 JA06 3.sl 39570 9674 0.3s4919 09/2711988 3.51 l0/30/1988 Bl 18 2.38 20080 t40s4 0.3s5201 r0l0t/1976 2.38 1210811976Bl l6 2.38 2203014054 0.353951 t0l0r/19762.381210811976 JA07 3.51 39570 9674 0.355237 0912711988 3.sl l0/30/1988 lArT 3.sl38879 10244 0.3ss860 0310711987 3.51031241t987 cl05 3.19 2944513690 0.361935 0913011977 3.19 I lll6lt977 c006 3.19 2739613690 0.372591 09130/1977 3.r9 I lr6lt977 A004 r.38 ls3l0 13310 0.371553 t0lt5lr978 t.38l2ll0ll978 A012 1.39 15310 r3310 0.373137 l0/lsll978l.39 l2/t01t978 D0t9 2.9 6 27 388 l 3 3 l 0 0.37 2833 t0 / t 5 I 197 I 2.96 t2/ l0 I 197 8 cl0l 3.182944s 13690 0.363890 0913011977 3.18 l t/t511977 ctt2 3.16 29445 13690 0.3635s2 09130/1977 3.16 I Ut6ll977 D020 2.96 27388 13310 0.373033 t0/151r978 2.96 12/1011978 A0l3 r .3915667 13310 0.371733 t0lt5lt9781.39l2ll0ll978A.038 1.40 r7050 14054 0.370336 t0/01r976 1.40 t2/0811976 cl l0 3.17 2924s 13690 0.362883 09130/1977 3.r7 1t/r6/1977 IA05 3.51 27167 10769 0.3s7691 091281t985 3.5t t2l08lr98sJA20 3.s1 38879 10244 0.3ss479 03/0711987 3.sl 03/2411987 JA04 3.sl 39620 9674 0.3ss8tt 0912711988 3.51 10/30/1988 cfit 3.t7 29245 13690 0.364077 0913011977 3.17 1111611977 cl ls 3.16 2924s 13690 0.364787 09130/1977 3.t6 tt/r6/1977 JA03 3.51 39620 9674 0.3s6163 0912711988 3.s1 l0/30/1988 JAls 3.51 39669 10244 0.355696 03/0711987 3.s10312411987 JAl6 3.51 39669 10244 0.3s5347 03/0711987 3.51 031241t987 rA06 3.51 27167 10769 0.357353 0912811985 3.51 1210811985rA07 3.5127167 10769 0.357761 09/281198s 3.sl 12108/1985JA05 3.5139570 9674 0.3s5384 0912711988 3.sl l0/30/1988 D0r2 2.96 27388 13310 0.373068 tOlt5lt978 296 r2lt0lt978 FC08514 Page8ol24 Revision 0 Doz4 z.e 6 27 3 BB r 3 3 I 0 o .37 zB7 7 l o t t s t t s7 t 2.s 6 l;,ffff]\ffflt', D0t4 2.96 27608 13310 0.371840 l0lt5ll978 2.96 t2ll0ll978 D}ts 2.96 27608 13310 0.371909 t0lt5lt978 2.96 l2ll0ll978Bl l5 2.38 22090 t40s4 0.355522 10101119762.381210811976 A009 r .40 8494 14654 0.37s812 021081r97s 1.40 04110/197s pl08 3.60 377s0 7851 0.349963 0912s1t993 3.60 t0/08/1993 c03l 3.01 38488 10244 0.36s396 0310711987 3.0103124/1987 A00s 1.39 849414654 0.375948 0210811975 1.39 04lt0lt97s Br22 2.37 22090 t4054 0.354729 t0l0lll976 2.37 12108/1976 Ett4 2.72 27677 t2849 0.364716 01/18/1980 2.72 041t611980 c009 3.03 38s77 tt344 0.363321 0310211984 3.03 06/1811984 G035 3.02 38577 t1344 0.364678 0310211984 3.02 06/1811984 G034 3.01 38577 11344 0.364882 0310211984 3.01 061t811984 IA34 3.sl 38091 10769 0.357857 0912811985 3.sl t2l08lt98s Et t 6 2.7 2 27 67 7 12849 0.3 64s06 0 I /1 8/1 980 2.7 2 04 I I 6/ 1980 A037 r.40 17050 14054 0.3703s6 1010111976 1.40 12108/1976 HA08 3.48 398s9 10769 0.3s8097 0912811985 3.48 1210811985lA25 3.5136464 10244 0.355753 0310711987 3.sl 03124/1987 HA09 3.48 398s9 10769 03s7490 091281198s 3.48121081198s lA26 3.5r 36464 10244 0.3s5442 0310711987 3.5r 0312411987 Bt2t 2.40 20080 14054 0.3s3292 r0l0tlt976 2.40 1210811976 HA03 3.48 23264 11344 0.3s742s 0310211984 3.48 0611811984 HA07 3.48 33270 11344 0.357421 0310211984 3.48 0611811984 G043 3.03 36183 10244 0.364463 0310711987 3.03 0312411987 G002 3.03 38294 11344 0.363338 0310211984 3.03 06/1811984 HArz 3.48 33270 t1344 0.356787 0310211984 3.48 06/1811984 HA06 3.48 33270 tt344 0.3s6742 0310211984 3.48 06/1811984 ctt4 3.162924s 13690 0.364433 0913011977 3.16 I tlt6lt977 c003 3.19 25442 13690 0.372834 0913011977 3.19 I 111611977 c012 3.18 2544213690 0.372710 0913011977 3.18 I llt6lt977 B2t3 2.38 29014 r 3690 0.3s4233 0913011977 2.38 tr/1611977 Fr07 2.74 29637 12241 0.365215 09/18/1981 2.74 l2l0tlt98t Fr09 2.74 29637 12241 0.365376 09/18/1981 2.74 t2/0tlt98l Fl08 2.74 29637 12241 0.364933 09/18/1981 2.74 t2/0tll98l Ftr} 2.74 29637 12241 0.365307 09/18/1981 2.74 t2l0ll198l ErtT 2.7227677 12849 0.364392 0l/18i1980 2.720411611980 Et}t 2.72 27677 12849 0.364s14 0U18/1980 2.72 0411611980 HA20 3.48 398s9 10769 0.3s6347 091281t98s 3.481210811985 HA23 3.48 39859 10769 0.3576720912A]985 3,4812108/1985 Et02 2.72 27677 12849 0.364s 13 0l/18/1980 2.72 0411611980 81182.7227677 12849 0.364780 01/18/1980 2.72 0411611980 A023 1.39 8768 14654 0.371384 0210811975 r.39 04/1011975 G003 3.03 38294 11344 0.3632s3 0310211,984 3.03 06/1811984 G008 3.02 38577 11344 0.364294 0310211984 3.02 0611811984 G022 3.03 38294 t1344 0.36352-7 0310211984 3.03 06118/1984G042 3.03 36183 10244 0.3643s103107/1987 3.03 0312411987 Bt07 2.38 20080 14054 0.354307 l0l0llr976 2.38 12/08119768224 2.39 22810 r40s4 0.353799 tuljlll976 2.39 1210811976 E008 3.03 3283012241 0.364716 09/18/1981 3.03121011198r EOl l 3.03 32830 1224t 0.365042 09/18/1981 3.03 t2/011r981 E010 3.03 32830122410.364784 09/18/1981 3.03 t2/0111981 E;022 3.03 32830 12241 0.3647 24 09/ 1 8/1 98 1 3.03 l2l0v t98t c002 3.19 25442 l 3690 0.37 1824 09 I 30 I t97 7 3. I 9 1 t / t 6l r97 7 HA02 3.48 23264 I 1344 0.3 57 044 03 I 021 1984 3.48 061 l8/l 984FC08514 Page 9 ot 24 Revision 0 rAre 3.s l 32tus to76e o.3s74sz ostzsnels 3.sl l2ATifBBT'o' HA27 3.48 37219 10769 0.357921 0912811985 3.48 1210811985 HAl3 3.4836266 10244 0.358358 0310711987 3.480312411987 IA20 3.51 32189 10769 0.356980 091281198s 3.sl 1210811985 rArT 3.sr 32189 10769 0.3s7482 091281r98s 3.st t2l08lt98sF1022.74 30618 122410.364430 09/l8/l98I 2.74 t2l0llt98l rA26 3.sl 36088 10769 0.3s72s3 091281r98s 3.sr 1210811985 Fttz 2.74 30618 t2241 0.36391 8 09/l 8/1981 2.74 l2l0lll98l rA27 3.5136088 10769 0.356952 091281r98s 3.51 1210811985 col I 3.19 35491 13310 0.371382 l0lt5ll978 3.19 12110/1978 NOl4 3.69 45167 7851 0.36404s 0912511993 3.69 1010811993 KA31 3.50 38557 9674 0.339152 0912711988 3.s0 10/30/1988 LA4l 3.80 33512 9674 0.340449 0912711988 3.80 l0/30/1988 Bttt 2.37 2203014054 0.3s3873 1010u19762.37 12108/1976 ct07 3.t9 29445 13690 0.362737 091301t977 3.19 1llr6lt977 LA27 3.80 33078 9674 0.339872 0912711988 3.80 l0/30/1988 rA02 3.51 27167 10769 0.3s73r2 0912811985 3.51 t2/08/198s u004 0.27 10630 5122 0.376000 031t512001 0.27 031301200t A04l 1.39 8439 14654 0.372254 0210811975 1.39 04/t0ll97s LA38 3.80 32681 9674 0.340997 0912711988 3.80 l0/30/1988 LA42 3.80 33512 9674 0.340701 0912711988 3.80 l0/30/1988 c005 3.19 2739613690 0.372789 0913011977 3.19 I U1611977 rA01 3.5 t 27167 10769 0.3s6862 0912811985 3.5 I l2l08/1985 4002 1.38 8638 146s4 0.37 1653 02/081197s 1.38 04/10/1975 LA43 3.80 335 12 9674 0.340733 0912711988 3.80 l0/30/1988 KAl S 3.49 25716 10244 0.339772 0310711987 3.49 03124/1987rA2l 3.sl 23835 10769 0.357727 0912811985 3.sr l2l08ll98s G0t2 3.02 33253 11799 0.362846 1210311982 3.02 0211811983 cc22 4.00 419s9 l44s 0.386387 04109120113.70 04124/201r cc40 4.00 439621445 0.38s70s 041091201I 3.87 04/2412011 LA35 3.80 33078 9674 0.341182 0912711988 3.80 10/30/1988BB08 4.09 45065 1968 0.3732681U0y2009 4.09 tllr0/2009 AA31 4.19 46701 1968 0.3706241U0U2009 4.t9 tutr/2009BB29 3.84 465301968 0.3706921110112009 3.84 tytt/2009 y034 4.0s ss269 1968 0.3740841U0U2009 4.0s lutll2009E024 3.03 29083 12241 0.364665 09/18/1981 3.03 12/01/198r rA223.s123835 t0769 0.3s7297 091281198s 3.st t2/0811985 cc34 4.00 4200s t44s 0.386428 04109/2011 3.70 0412312011BB42 3.84 39731 1968 0.370923 rll0ll2009 3.84 turv2009AA26 4.18 477061968 0.370888 l1/0r/2009 4.18 llll0l2009 col6 3.19 27396 r3690 0.372647 09/3011977 3.19 1Ut6lr977BB26 3.84 39743 1968 0.370642 tu0t/2009 3.84 lll1ll2009 AA27 4.18 477121968 0.370932 rll01/2009 4.18 11/1212009 y037 4.03 445s0 1968 0.373747 ll/0y2009 4.03 rlltv2009 y036 4.03 44s44 1968 0.3737281U0y2009 4.03 lllll/2009 BBr9 3.97 4317s 1968 0.370690 1u0U2009 3.97 tut2l2009 BBl S 3.97 43174 1968 0.370740 lll0l/2009 3.97 llllll2009 y033 4.06 ss230 1968 0.373970 tr/0v2009 4.06 tlll0l2009 BB28 3.84 46sr0 1968 0.3707s211101/2009 3.84 tr/1y2009 AAzs 4.18 44215 1968 0.370840 111012009 4.18 lllt0l2009 cl06 3.19 2944s 13690 0.362271 0913011977 3.19 l r/1611977 rA23 3.51 23835 10769 0.3s7303 091281198s 3.51 1210811985 2018 3.68 42239 3rt8 0.372288 0910912006 3.68 09/18/2046 A018 1.40 784214654 0.3719t9 021081197s 1.40 0411011975FC08514 Page 10 ol 24 Revision 0 ro44 3.7s 37448 62ot 0.374814 o4tlytssl 3.7so4llT/fBBilt',o' LA39 3.80 32681 9674 0.340s07 091271t988 3.80 l0/30/1988 KA27 3.s0 45692 9674 0340519 09127/t988 3.50 l0/30/1988 D02t 2.96 27 608 I 33 I 0 0.3727 84 I 0 I I 5 I t97 8 2.96 l2l l0 I 197 8ROl5 3.86 45857 6745 0.374084 10/05/19963.8610120/1996 KAl6 3.50 45048 9674 0.339987 09/2711988 3.50 l0/30/1988 R05l 3.60 48643 6201 0.375086 04/01/1998 3.60 041t911998 G029 3.02 39051 1t344 0.363713 0310211984 3.02 06/1811984T047 3.75 37411 6201 0.374725 0410111998 3.75 04/19/1998 G01 I 3.03 3998s 11344 0.362773 0310211984 3.03 0611811984D028 2.97 33346 12849 0.372849 0l/18/1980 2.97 0411611980 M002 3.8r 44t72 8452 0.3647 17 0210r I 1992 3.81 021201 1992 JA36 3.51 38659 9166 0.355370 02117/1990 3.51 03116/1990 tA24 3.st23835 10769 0.356757 0912811985 3.51 12108/1985 JAl2 3.sl 3879210244 0.35ss86 0310711987 3.5103/2411987 KA03 3.49 42296 9674 0.3s5775 0912711988 3.49 l0/30/1988 KAl4 3.s0 456929674 0.339821 0912711988 3.50 l0/30/1988 G0 I 6 3.02 3 107 l I 17 99 0.3 63 462 l2l 03 I 1982 3.02 021 l8l 1983 s020 3.36 38841 6201 0.374298 0410111998 3.36 04120/1998 B22t 2.41 22660 14054 0.353744 l0l0llt976 2.41 12/0811976 LA23 3.81 39504 9166 0.3s6637 0211711990 3.81 0311411990 R016 3.85 4s799 6745 0.373987 l0l0slt996 3.8s 10119/1996 HAos 3.48 33270 11344 0.3s7256 0310211984 3.48 0611811984 A.043 r.38 8439 t46s4 0.376878 02108/197s 1.38 04lt0lr97s HA14 3.48 2s270 11344 03s7691 0310211984 3.48 061t811984 y028 3.91 42532 3fi8 0.371251 09/0912006 3.91 09/1912006 R0l9 3.86 41447 6745 0.374486 1010511996 3.86 10119/1996 M0l4 3.77 42710 84s2 0.364609 0210y1992 3.77 0212011992N002 3.69 44707 7851 0.363733 0912511993 3.69 1010811993 KA30 3.50 44281 9674 0.339716 0912711988 3.50 l0/30/1988 u009 4.2s 46971 st22 0.374138 03/1s12001 4.2s 031301200r 8n22.37 28s6413690 0.3s3802 0913011977 2.37 tl/1611977 KAzt 3.5l 4s048 9674 0.339923 0912711988 3.51 10/30/1988JAl8 3.sl 38879 10244 0.355960 03107/t987 3.st0312411987 LA31 3.80 43655 9166 0.34r6ss 0211711990 3.80 0311611990 20083.65 37238 3l l8 0.371363 09109/2006 3.65 0911712006 2006 3.65 37405 3 r l8 0.371406 09/0912006 3.6s 09118/2006 G032 3.01 38294 11344 0.364941 0310211984 3.01 06/1 8119842005 3.6s 37298 3ll8 0.371413 09/0912006 3.65 09/18/2006 IA33 3.sl 38091 10769 0.357106 09128119853.51 12108/198s u0t7 4.25 41641 5122 0.375593 0311512001 4.25 0313012001BB23 3.97 40546 1445 0.370794 04109/2011 3.97 04123/201r 2038 3.63 3791s 3l 18 0.371074 09/0912006 3.63 09119/2006 yOl0 3.74 49401 r968 0.371s87 lll0t?009 3.74 fi11112009 w020 3.60 30007 sr22 0.371263 0311s120013.60 031301200t LAos 3.80 37296 8452 0.3s8 594 0210y1992 3.80 02/2011992 LAl0 3.81 37773 8452 0.357575 02/01/1992 3.8t 02/2011992 MOl l 3.78 42819 84s2 0.36s19s 0210y1992 3.78 0212011992 LAl6 3.81 38255 9166 0.35752s 0211711990 3.81 0311211990 LAl5 3.8r 38000 9166 0.3s68s7 02/1711990 3.8r 0311211990 LA29 3.80 43276 9166 0.341151 0211711990 3.80 0311211990 LA06 3.81 37868 8452 0.357s76 0210111992 3.81 02122/1992 LA323.80 43739 91660.340807 0211711990 3.80 0311411990 LA34 3.80 43914 9166 0.341743 0211711990 3.80 0311211990FC08514 Page 1'l of24 Revision 0 plls 3.60 3722s Tsst 0.34s7s2 xstzsnse3 3.6010/&1iB 3"o'cc38 4.00 42849 r44s 0.386734 04109120113.87 041241201t cc26 4.00 37165 1445 0.386670 04109120113.70 04123/2011 A.040 1.40 170s0 t4054 0.372073 l0l0vt976 1.40 12/0811976 BB27 3.84 39731 1968 0.370566 ry0ll2009 3.84 lllt0/2009 wOl7 3.60 36r t8 sl22 0.371817 03llsl200t 3.60 03/30/2001 R02l 3.86 51770 6201 0.374670 04101/1998 3.86 0411911998 wOl5 3.60 36131 5t22 0.371635 0311512001 3.60 0312812001 R020 3.86 38602 674s 0.374577 1010511996 3.861012011996 w027 3.60 37583 5122 0.371472 03lrsl200l 3.60 03/3012001 AA123.95 444942530 0.371239 0411912008 3.9s 0510112008 A017 r.40 17050 140s4 0.37166210101119761.40 t2108/1976 s029 3.35 388s2 6201 0.374348 0410111998 3.35 04119/1998 cclS 4.00 39882 1445 0.386483 0410912011 3.70 0412412011 BB11 4.09 46385 1445 0.373145 0410912011 4.09 041231201r BBr0 4.09 46380 t44s 0.373268 0410912011 4.09 0412312011 cc39 4.00 42816 1445 0.386642 041091201I 3.87 04/2412011 BB04 4.tt 49378 r44s 0.373868 041091201I 4.1I 0412312011 MOl0 3.80 38176 8452 0.364127 0210111992 3.80 0212011992 y043 4.03 447061968 0.37343s rv0y2009 4.03 llltr/2009 y005 3.74 396961968 0.37r s90 lll0ll2009 3.74 tlltll2009 cc29 4.00 37078144s 0.386282 04109120113.70 04123/2011BB40 3.83 46s321968 0.370889 lll0ll2009 3.83 rtllll2009 y042 4.03 44687 1968 0.373609 110U2009 4.03 lvt2l2009 MOl2 3.77 42993 8452 0.36520t 0210U1992 3.77 02/2011992BB43 3.84 39744 1968 0.370818 ll/0112009 3.84 tytl/2009 y024 3.9t 42418 3118 0.371100 0910912006 3.91 0911812006 AAl4 3.9s 41047 2530 0.371279 0411912008 3.95 04/3012008 JA34 3.51396119166 0.3ss973 02117/1990 3.sl 03/12/1990AAr r 3.9s 39439 1968 0.3713s3 lll0ll2009 3.95 rr/12/2009 LA04 3.81 38832 9166 0.358167 0211711990 3.81 03116/t990 w029 3.60 31459 st22 0.371s39 0311512001 3.60 03/30/2001 rA18 3.sl 32189 10769 0.357212 09128/198s 3.51 t2/08/198s p006 3.94 4s229 7337 0.366187 02/20/199s 3.94 0310411995 E0l9 3.03 30324 12241 0.364488 09/18/1981 3.03 l2l0l/1981 y007 3.74 492s9 2530 0.371629 0411912008 3.74 04130/2008 BB35 3.84 37720 2530 0.370676 0411912008 3.84 0413012008 D005 2.95 51s04 11799 0.371986 t2103119822.95 02118/1983 ccl3 4.00 42936 1445 0.389018 0410912011 3.97 0412412011 AA08 3.9s 40317 1968 0.371400 1U0y2009 3.9s I lll2l2009 u002 0.27 r06s0 5122 0.376000 03/15/200t 0.27 03129/200r Z007 3.6s 37387 3l l8 0.371158 09/09/2006 3.6s 09/18/2006 AA32 4.t9 43693 2s30 0371A03 0411912008 4.19 0412912008D022 2.96 27388 13310 0.373091 l0llsll978 2.96 t2lt0lr978 yDtt 3.74 39689 1968 0.371796 1U0y2009 3.74 t1/tv2009 R032 3.8s 42484 6201 0.374708 0410111998 3.85 04/1911998 x039 4.20 39565 4212 0.371794 0911212003 4.20 0912312003 Nl08 3.70 41302 s654 0.348198 l0/01/1999 3.701011211999 u038 4.25 44978 st22 0.374709 03llsl200l 4.25 0312912001 y020 3.96 417761968 0.372479 111012009 3.96llllll2009 LA26 3.80 4323s 9166 0.339944 021t711990 3.80 0311211990T029 3.76 406t5 4709 0.373862 0s10312002 3.76 0511312002 KA06 3.50 44304 9166 0.3s6442 021t711990 3.50 0311411990 y002 0.3s rt67t 2530 0.375198 0411912008 0.3s 04/3012008FC08514 Page 12 oI 24 Revision 0 Attachment 10.2 lA243.sl 3580s 10244 0.3s5853 0310711987 3.sl0312411987 LA09 3.8 r 3 8089 8452 0.357 92s 021 0t I 1992 3.81 021221 1992 2034 3.63 35888 3677 0.370810 021261200s 3.63 03113/2005 s009 3.84 30264 6745 0.373698 l0/05/1996 3.84 1011911996 w023 3.60 37423 5122 0.371546 03llsl200l 3.60 0312812001 KA09 3.49 42296 9674 0.35s406 0912711988 3.49 10/30/1988 s0l6 3.36 36702 6745 0.373779 1010511996 3.36 t0/1811996 D040 2.97 33346 12849 0.372233 01/18/1980 2.97 0411611980rA3l 3.sl 36124 10769 0.357380 0912811985 3.51 1210811985 AA22 4.18 46703 1968 0.370797 rll0ll2009 4.18 llll2/2009 JAOI 3.51 34439 10244 0.355329 0310711987 3.510312411987 AA3s 4.31 44093 1445 0.373388 0410912011 4.31 041231201r LA30 3.80 43016 9166 0.339868 021t711990 3.80 0311211990 Ml07 3.80 39613 sl22 0.348245 03llsl200t 3.80 03/31/200r AA07 3.95 44435 2530 0.37t267 0411912008 3.95 0412912008Nl l3 3.70 48430 56s4 0.349s33 10/01/1999 3.701011111999BB25 3.84 376s6 2s30 0.370698 0411912008 3.84 04/30/2008 y027 3.92 42484 3l l8 0.37111109109120063.920911912006 B20t 2.41 22190 r40s4 0.353333 l0l0tlr976 2.41 12/08/1976 ct04 3.19 2944s 13690 0362046 0913011977 3.19 I tll6l19772040 3.63 38829 2530 0.37tr36 0411912008 3.63 04/3012008 AAlg 4.2s 51224 2s30 0.372320 0411912008 4.25 04130/2008 s030 3.3s 38842 6201 0.374873 0410t11998 3.35 04/20/1998 R049 3.60 48s73 62010.375088 04/01/1998 3.60 04/1811998 A027 r.38 rs3l0 13310 0.371103 t0l1sll978 t.38 t2ll0ll978 AAl8 4.2s 51197 2s30 0.372270 041t912008 4.2s 04130/2008N122 3.69 40240 s654 0.3474281010111999 3.69 t0/tl/1999 y009 3.74 396961968 0.371681 rll0y2009 3.74 ttlt0/2009 BB07 4.09 457s7 1968 0.373015 tv0ll2009 4.09 ttllll2009Z039 3.63 37852 3l l8 0.371069 09109120063.63 09/1712006 z02s 3.63 38797 2530 0.370888 0411912008 3.63 05/01/2008 AA04 3.95 41035 2530 0.371333 0411912008 3.95 0412912008 N0r2 3.70 4s420 56s4 0.364942 r0l0lll999 3.701011311999 AAl6 3.9s 46860 2s30 0.371232 0411912008 3.95 0412912008 y025 3.9r 42s24 3l l8 0.3711810910912006 3.91 09/1812006 AA0s 3.9s 44s60 2s30 0371246 0411912008 3.9s 04/3012008 y00l 0.34 11666 2530 0.37s094 04/1912008 0.34 05/01/2008 s0r7 3.36 25321 674s 0.374218 tDl}slt996 3.3610/20/1996 s027 3.3s 36245 674s 0.374839 l0/05/1996 3.35 t0lt9lt996 u03t 4.25 44201 sl22 0.375261 03llsl200t 4.25 0312912001 KA05 3.s2 44202 9166 0.354659 021t71t990 3.52 031161t990 BB32 3.84 38136 2s30 0.370764 04/1912008 3.84 04130/2008 c008 3.18 2764213690 0.372316 0913011977 3.18 I yl6ll977 KA2s 3.st 45564 9674 0.341691 0912711988 3.51 l0/30/1988 pl l6 3.58 47s20 s6s4 0.349767 t0l0vt999 3.58 t0lt2/r999 KA02 3.49 42296 9674 0.3s5943 0912711988 3.49 l0/30/1988T048 3.7s 37s51 6201 0.374416 0410u1998 3.7s 041t811998 w028 3.61 3t4tt sl22 0.3712s3 03ltsl200t 3.6t 03/2912001 R0l2 3.8s 41988 674s 0.373083 10i05/1996 3.8s t0lt8lt996 Et06 2.72 27932 12849 0.363336 0l/18/1980 2.72 0411611980 lA02 3.51 34439 10244 0.354770 0310711987 3.51 0312411987 AA03 3.9s 41031 2530 0.371547 0411912008 3.9s 05/01/2008 y030 3.91 41687 1968 0.3713r1 11012009 3.91 ttlrrl2009 BB38 3.83 37962 2530 0.370922 0411912008 3.83 0413012008 FC08514 Page 13 oI 24 Revision 0 yol3 3.e6 448t4 3trl 0.372731 ostostz006 3.e6 osififfil"o, y0l4 3.96 44723 3tt8 0.372666 09109/2006 3.96 091t712006 u024 4.25 43491 5122 0.375182 0311512001 4.2s 031301200r x025 4.19 37726 4212 0.372119 091t2/2003 4.19 0912612003 LA18 3.8129735 9674 0.357750 0912711988 3.81 l0/30/1988 u04t 4.25 42776 5t22 0.375170 031t512001 4.25 03/2812001 AA09 3.95 40319 1968 0.371332 1U0112009 3.9s 1y1U2009 B2t6 2.39 29014 13690 0.352519 09/3011977 2.39 tt/r6/r977 8207 2.37 2901413690 0.3s3755 09/3011977 2.37 tllt6lt977 pt22 3.s9 41923 7337 0.349746 02120/1995 3.59 031041199s KAl9 3.45 442s4 9674 0.348792 0912711988 3.45 l0/30/1988 HA24 3.48 398s9 10769 0.35701 5 09/281t98s 3.48 12108/198s AAls 3.95 46840 2530 0.37t402 0411912008 3.95 04/3012008 T0t9 4.t6 38489 4709 0.3741s4 0510312002 4.t6 0511312002 s028 3.35 38922 6201 0.374912 0410U1998 3.3s 0411911998 u0t4 4.2s 4r73s 5122 0.375222 0311512001 4.25 0312912001R046 3.60 38369 674s 0.37489s 10/0s/1996 3.60 t0/20/1996 u00t 0.27 10s37 sl22 0.375000 0311512001 0.27 0312812001M003 3.81 44041 8452 0.364529 0210yr992 3.8r 0212011992 R025 3.8s 4s998 6201 0.374760 04101/1998 3.8s 04/18/1998 4436 4.30 44074 1445 0.373088 041091201 l 4.30 0412412011 NOl9 3.70 4s864 78sl 0.36s613 0912s1r993 3.701010811993 JA23 3.51 35805 10244 0.355138 03107/1987 3.5103124/1987 BB41 3.84 46s061968 0.3710001U0U2009 3.84 tyt0l2009 BB3l 3.84 38079 2530 0.370575 0411912008 3.84 0413012008 AA34 4.31 440941445 0.373298 0410912011 4.3r 0412412011 2024 3.68 42298 3tt8 0.37228s 0910912006 3.68 09/18t2006 HA30 3.48 37219 10769 0.356571 0912811985 3.4812/081198s Etts 2.72 30618 122410.364168 09/18/1981 2.7212/0yt98t 2029 3.63 3s729 3677 0.371144 021261200s 3.63 03n3t2005B20s 2.37 29014 13690 0.354273 091301t977 2.37 tyt6lt977 w03r 3.60 37s39 st22 0.371877 03ltsl200r 3.60 03t28t200t A006 r .39 8494 146s4 0.376843 0210811975 1.39 04lt0lt97ss002 3.8s 33872 6201 03727s1 0410U1998 3.85 0411811998 u033 4.25 41484 5122 0.374703 0311512001 4.2s 0312812001 w0l8 3.60 30005 5122 0.371030 03/t 512001 3.60 03129/2001 20323.6336037 3677 0.370827 0212612005 3.63 03/131200sAA23 4.18 43731 2s30 0.37t076 0411912008 4.r8 05/01/2008 AA30 4.19 437s4 2s30 0.370694 04tr9t2008 4.19 04t30t2008 BB22 3.97 40s44 1445 0.370696 0410912011 3.97 04/23t2011 LAl3 3.81 37793 9166 0.3573s9 0211711990 3.81 03fi2n990 E002 3.03 29083 t22410.364773 09/l8/t98I 3.03 t2/0rlt98t 2026 3.63 37838 31r8 0.370744 0910912006 3.63 09/t8t2006 T033 3.75 34088 4709 0.37467s 0s10312002 3.75 05/1312002 8023 3.04 26442 t2849 0.362838 0l/r8/1980 3.04 04/t6n980 AAzt 4.18 436682s30 0.370989 04n9t2008 4.18 05/01/2008 s001 3.85 33851 6201 0.373236 0410U1998 3.85 04t20n998 T03l 3.75 30286 4709 0.373934 05t03t2002 3.75 0sn4t2002 w033 3.61 37289 5122 0.372177 031151200t 3.61 03t29t2001R031 3.8s 42492 6201 0.374s32 04t0ur998 3.85 04n9n998 R018 3.8s 38ss2 6745 0.374928 t0l0slt996 3.8s r0119fi996 BB34 3.84 37748 2530 0.370822 04119t2008 3.84 04t30t2008 AAlT 4.25 st5t9 2530 0372057 04n9/2008 4.25 04t30t2008 cl08 3.18 29245 13690 0.362804 09/3011977 3.18 I t/1611977 FC085'14 Page 14 of 24 Revision 0 u040 4.zs 44usr stz2 0.374687 03nst20ot 4.zs 03/i6iiUbT"o' rA103.47 34917 10769 0.36s548 09128/19853.47 121081198s y04l 4.03 4466919680.373647 lll0t/2009 4.03 llll2l2009 LA20 3.81 38770 9166 0.3s6522 0211711990 3.81 0311211990 cl02 3.18 29445 13690 0.3637rs 0913011977 3.18 I 111611977 T025 3.76 32898 6201 0.374130 0410Ur998 3.76 04118/1998 HA04 3.48 23264 tt344 0.356752 0310211984 3.48 06/1811984Z033 3.63 36163 3677 0.371049 0212612005 3.63 03112/2005 cc36 4.00 39856 144s 0.386235 04109/201I 3.70 04/2212011s031 3.36 38847 6201 0.373969 0410111998 3.36 0411911998 KA32 3.s1 45048 96740.3398760912711988 3.51 l0/30/1988 y017 3.96 41757 1968 0.372469 1y01/2009 3.9611/1U2009 KA23 3.s0 44281 9674 0.339879 0912711988 3.50 10/30/19882027 3.63 37923 3l l8 0.370860 0910912006 3.63 09/1812006 w024 3.60 31442 5122 0.371652 03llsl200l 3.60 0312912001 N020 3.70 45898 78sl 0.365768 0912s11993 3.70 1010811993 ctt3 3.t7 2924s 13690 0.363228 0913011977 3.17 1111611977 G040 3.01 39343 10769 0.365096 091281198s 3.01 12108/1985T028 3.76 34802 6201 0.374232 0410U1998 3.76 0411911998 cc42 4.00 4281s 1445 0.386031 04109/2011 3.87 0412312011 s038 3.35 48s7s 6201 0.373712 0410yr998 3.35 04119/1998 R006 3.85 42250 6745 0.374372 t010511996 3.85 10/1911996 w040 3.61 36885 5t22 0.370715 0311512001 3.61 0312812001 z0r9 3.68 3 t 456 3 67 7 0.37 2t t 4 0212612005 3.68 03 I t3 1200s LA40 3.80 32681 9674 0.340803 0912711988 3.80 l0/30/1988 R030 3.8s 42480 6201 0.374704 0410111998 3.85 04/2011998 r{t4 3.47 34897 10769 0.36s647 0912811985 3.47 t2/081198s KA28 3.52 44281 9674 0.337411 09127/1988 3.52 10i30/1988 LA08 3.81 37411 84s2 0.3s77s8 0210y1992 3.8r 0212011992 LA28 3.80 33078 9674 0.340534 0912711988 3.80 l0/30/1988 pll0 3.s8 42487 56540.349885 l0/01/1999 3.s8 t0ll2ll999s036 3.36 366s3 6745 0.373830 t0l0sll996 3.36 t01t8/1996 R044 3.8s 41706 6745 0.374781 l0/05/1996 3.85 1011811996 ccOl 4.00 439121445 0.3888910410912011 3.98 0412412011 p109 3.s8 41477 7337 0.3s03010212011995 3.s8 03/04/1995 pl l8 3.58 41552 7337 0.349842 021201r99s 3.s8 0310411995 BBl4 4.09 45758 1968 0.3732341U0y2009 4.09 tlllll2009 u008 4.2s 4895s sr22 0.37s138 03lts/200r 4.25 0313012001 BB0l 4.1t 49362 t44s 0.373530 0410912011 4.ll 0412312011 c00l 3.18 3549r 13310 0.36998s t0lt5lt9783.t8 r2lt0lt978 BB44 3.84 3766s 2s30 0.370734 0411912008 3.84 04/29/2008 A0l5 1.39 r5310 13310 0.371855 t0lt5/1978 r.3912/1011978 cc02 4.00 43979 144s 0.388799 04109120113.99 041231201r cc37 4.00 43930 t44s 0.386754 04109120r I 3.88 04123/20rrR027 3.8s 4s9s7 62010.374827 0410U1998 3.85 0411911998 LA37 3.80 3268r 9674 0.340547 0912711988 3.80 l0/30/1988 y003 0.34 11687 2s30 0.375097 0411912008 0.34 04/3012008F007 3.03 30324 12241 0.365771 09/18/1981 3.03 r2/0,/r98t HAl9 3.43 37229 10769 0.364860 091281198s 3.43 t2l08lt98s cc27 4.00 37181 1445 0.386800 04109120113.70 0412312011 y029 3.91 43409 t44s 0.371245 0410912011 3.91 04124/2011 cc3s 4.00 39882 1445 0.386270 04109/20113.70 0412312011 LA03 3.80 38555 9166 0.358652 0211711990 3.80 0311411990 cl09 3.r 82924s 13690 0.362s29 0913011977 3.18 I 111611977FC08514 Page 15 oI 24 Revision 0 cc434.00 428s0 l44s 0.3860 43 o4toe/2ott 3.B7 o+zYilffii"o' Bt24 2.37 22090 14054 0.3s4786 t0l0lll976 2.37 1210811976 y008 3.74 33047 4212 0.37t428 0911212003 3.74 0912312003 R052 3.60 48625 6201 0.374949 04101/1998 3.60 0411811998 u028 4.26 47457 5122 0.374980 0311512001 4.26 0313012001 u02s 4.26 44329 st22 0.37s022 03/lsl200t 4.26 0313012001 s037 3.35 38889 6201 0.373s02 0410111998 3.35 0411911998R023 3.86 5175t 6201 0.374439 0410111998 3.86 0411811998s013 3.84 51971 6201 0.373915 0410111998 3.84 04/1811998 z0t5 3.42 36019 3677 0.370740 0212612005 3.42 0311312005 R039 3.86 42216 6745 0.374315 10/05/19963.861011911996 y006 3.74 39687 1968 0.37171s tll0ll2009 3.74 tt/tt/2009 BB13 4.09 45066 1968 0.373180 1110112009 4.09 llllll2009 pt23 3.s9 41502 7337 0.349752 021201199s 3.s9 03/041t995 pl04 3.58 41s66 7337 0.349967 02120/1995 3.58 03/04/t99s pl30 3.s8 43466 7337 0.349848 0212011995 3.s8 03/0411995 pt25 3.59 41475 7337 0349620 0212011995 3.59 031041199s w032 3.60 37491 5122 0.371268 0311512001 3.60 0313012001 AA02 3.95 467982530 0.371417 0411912008 3.95 0413012008 pl3l 3.58 43229 7337 0.349643 02/Z0ll99s 3.58 03/0411995 cctz 4.00 439141445 0.3892s3 0410912011 3.99 0412212011 DD24 4.00 38026 1445 0.38s462 041091201 I 4.03 0412312011 BBlT 3.97 40337 1445 0.37077604109/20113.97 04122120rr KAI l 3.48 42174 9166 0.363137 0211711990 3.48 0311611990 HA22 3.49 39487 10769 0.366404 09/2811985 3.49 t2l08lr98sE004 3.05 303rs 12241 0.373243 09/18/1981 3.0s l2l0l/r981 ccl9 4.00 42004 t445 0.386s1s 04109/201I 3.70 041231201r ROl I 3.85 4r9tt 6745 0.3734741010511996 3.8s 10/1811996 u0r2 4.2s 49026 5122 0.375598 0311512001 4.25 03130/200r T0t4 4.t6 33582 4709 0.374403 0510312002 4.16 0s11412002 BB37 3.83 38060 2530 0.370901 0411912008 3.83 0413012A08 Mll8 3.80 39s41 51220.348827 0311512001 3.80 031281200t p132 3.58 47473 5654 0.349743 1010111999 3.58 t0llvl999 pt24 3.58 47s36 s6s4 0.349729 l0/0yt999 3.s8l0ll2/1999 y0s2 4.00 42367 3677 0.372s10 02/261200s 4.00 03/1312005 R024 3.86 51657 620t 0.373480 04/01/1998 3.86 04118n998 Ml04 3.80 39249 5654 0.34857210101/1999 3.80 t0lt2lt999 Nl20 3.70 3843s s6s4 0.347626 t0/0U1999 3.70 10/1311999 Nl I I 3.70 48376 5654 0.349783 l0l0lll999 3.70 t0lt2lr999 Ml r 1 3.79 4s6s0 7851 0.3489t0 0912s11993 3.79 l0/08/1993 Mtzt 3.80 45926 8452 0.3488s1 0210U1992 3.80 02/20/1992 Nl05 3.71 45750 78sl 0.348332 09/2511993 3.71 l0/08/1993 pl l2 3.58 43425 7337 0.349619 02/2011995 3.58 0310411995 p004 3.93 44350 7337 036s8s3 0212011995 3.93 031041r99s pt28 3.s9 41979 7337 0,349859 021201199s 3.s9 03/041199s 2003 3.44 35893 3677 0.371504 02/2612005 3.44 03/13/200sM020 3.79 42892 8452 0.364579 0210yr992 3.79 02/221t992 Nl03 3.71 45727 78sl 0.348584 09/2511993 3.71 t0/08/1993 L At2 3.8 1 3 8089 84s2 0.3 s7 4s2 021 0l I 1992 3.81 02122/ 1992 2004 3.44 35840 3677 0.371377 0212612005 3.44 03113/200s u034 4.26 41644 5122 0.374865 03/l 512001 4.26 03/2912001 KA26 3.42 45144 9674 0.357948 0912711988 3.42 1013011988Bt06 2.4t 28661 13690 0.361462 091301t977 2.41 t1/161t977 cc16 4.00 42937 1445 0.389068 0410912011 3.97 0412312011FC08514 Page 16 ol 24 Revision 0 Aftachmenl 10.2 JAlg 3.51 38879 10244 0.355988 0310711987 3.510312411987 D023 2.96 27 608 r 33 l 0 0.3727 57 I 0l I 5 I r97 8 2.9 6 l2l l0 I 197 8 x034 4.20 40681 42t2 0.371443 0911212003 4.20 0912312003 u029 4.26 47446 sl22 0.375183 0311512001 4.26 0312912001 w0l4 3.60 29926 5122 0.370632 0311512001 3.60 0313012001 N I 2 I 3.69 40267 5654 0.34748 I I 0/0 I /l 999 3.69 l0/ 13 I 1999 BB03 4.tt 49334 t445 0.373629 041091201I 4.1I 04123/2011 Ml05 3.81 40s93 5654 0.348307 l0/0y1999 3.81 10/13/1999 M00s 3.8t 37978 84s2 0.36410s 0210111992 3.8r 02/20/1992Nl l4 3.70 48402 5654 0.349366l0l0lll999 3.70l0/ll/1999N009 3.69 44813 7851 0.364190 0912s11993 3.69 1010811993 pl19 3.59 41795 7337 0.350090 0212011995 3.59 0310411995 Nl rg 3.71 41318 7337 0.347864 0212011995 3.71 031041199sZ030 3.63 3s600 3677 0.371025 021261200s 3.63 0311312005 p005 3.93 44448 7337 0.36s963 0212011995 3.93 0310411995 p121 3.s8 415727337 0349901 0212011995 3.58 0310411995 p1l3 3.59 41729 7337 0.3s0064 0212011995 3.59 03104/199s y026 3.9t 417081968 0.371170 1U0112009 3.91 llll2/2009 u043 4.2s 42874 5122 0.374945 03lls/2001 4.25 03129/2001 D003 2.96 27 618 I 3 3 I 0 0.37 87 93 t0 I t s I 197 I 2.9 6 t2l r0/ r97 8 cc24 4.00 37079 r445 0.386s77 041091201t 3.70 04/231201r AA20 4.2s 51519 2s30 0.372314 0411912008 4.2s 0413012008 x002 3.s l 35762 4212 0.370772 09/1212003 3.s l 0912612003 u005 4.2s 46960 5122 0.374314 0311512001 4.25 0312912001 u032 4.26 47301 st22 0.374963 03llsl200l 4.26 03129/2001N008 3.70 4s535 5654 0.36s0s7 l0l0ll1999 3.70 t0lllll999 Nl23 3.69 40306 s6s4 0.3472t0 r0l0yr999 3.69 l0ll2lt999Nl l5 3.70 41341 5654 0.348374l0l0lll999 3.70 10/1311999 M006 3.81 37860 8452 0.364430 0210111992 3.8r 02/2011992 Nl12 3.70 48425 s6s4 0.349659 t0l0ur999 3.701011211999N007 3.70 41469 5654 0.364ss8 l0/01/1999 3.70 t0lt2lr999 Ml 19 3.81 45901 84s2 0.348793 0210t/1992 3.81 0212011992 s034 3.35 48846 6201 0.373656 0410U1998 3.35 04/1911998 Z0123.43 36151 3677 0.3709240212612005 3.43 031r21200sN102 3.70 4lLs8 7337 0.34890s 02120/199s 3.70 0310411995 pt26 3.59 4rs87 7337 0.349$8 0A20n99s 3.s9 031041199s p103 3.s9 41842 7337 0.349803 0212011995 3.59 03104/1995 R034 3.8s 384s9 62010.374229 04101/1998 3.8s 0411711998 R050 3.60 48577 6201 0.374648 0410111998 3.60 0411911998 yol8 3.96 44681 3677 0.372462 0212612005 3.96 03/13/200s pt29 3.58 43410 7337 0.349956 0212011995 3.s8 0310411995 Rol4 3.85 45845 6745 0.3742841010511996 3.85 t0/r81r996 R007 3.85 42348 6745 0.374419 1010511996 3.85 rc/r91r996 8009 2.38 28040 133r0 0.370572 t0/1511978 2.38 t2/10/1978 KA07 3.44 43206 9166 0.364807 0211711990 3.44 0311611990 sol9 3.36 36777 674s 0.373901 l0/05/19963.361A/19/1996 y022 3.96 43489 t44s 0.372632 0410912011 3.96 0412312011 LAl9 3.80 29735 9674 03s6964 0912711988 3.80 10/30/1988E003 3.03 36880 122410.364343 09/18/1981
3.0 31210U1981
x028 4.19 37746 42t2 0.37rs81 0911212003 4.19 0912312003 w037 3.61 36860 5122 0.370142 0311s12001 3.61 0312912001 w030 3.60 37167 5122 0.371248 0311512001 3.60 0313012001 pl l7 3.58 47445 5654 0.350018 l0/01/1999 3.58 t0ltvt999 Ml02 3.80 40577 5654 0.349052 t0l0vt999 3.80 t0/1211999 FC08514 Page 17 ol24 Attachment 10.2 Ml20 3.80 40552 56s4 0.348954 r0l0lll999 3.80 l0ll3ll999 M009 3.8t 37397 84s2 0.364133 0210111992 3.81 02120119922036 3.63 3s509 3677 0.370803 021261200s 3.63 031t312005Nl l6 3.70 38424 s6s4 0.3474341010111999 3.70 t0lt2/1999 LA02 3.81 38541 9166 0.3580380211711990 3.81 0311211990M122 3.80 46097 84s2 0.349126 0210U1992 3.80 02/20/1992 s04l 3.35 48849 6201 0.373608 04/01/1998 3.35 0411811998N107 3.70 4t292 7337 0.348739 021201199s 3.70 03104/1995 y045 4.00 42242 3677 0.372556 0212612005 4.00 031121200s u007 4.25 46963 5122 0.374545 03llsl200l 4.25 0312812001 z00t 3.44 35649 3677 0.371545 021261200s 3.44 0311312005 u030 4.26 4740t 5122 0.375355 03ltsl200l 4.26 0312812001 s0l0 3.84 30141 6745 0.3741 l5 l0/05/l 996 3.84 r01201t996 N110 3.70 4tt6l 7337 0.348868 0212011995 3.70 031041199s y053 3.43 46667 3677 0.373085 0212612005 3.43 03/1312005M017 3.77 42671 8452 0.36412s 0210111992 3.77 0212211992 w044 4.24 38415 5122 0.371077 03lrsl200l 4.24 0313012001 G015 3.02 3t973 Il799 0.362668 t2l03l19823.02021t8l1983 Et07 2.7 2 27 932 12849 0.363 I 60 0 1 / I 8/ I 980 2.7 2 04/ 16 / 1980 x023 4.19 44249 4212 0.372934 09112/2003 4.19 09126/2003 u0r5 4.2s 40279 5122 0.37s87s 0311512001 4.25 03/29/200t w02l 3.60 37505 51220.3719220311512001 3.60 03/291200t N00l 3.70 41449 56s4 0.363994 t0l0yt999 3.70 t0/13/1999 ccl5 4.00 42941 1445 0.388928 0410912011 3.97 0412412011 Nl09 3.70 41334 5654 0.3483s0 l0/01/1999 3.701011311999M007 3.81 37671 84s2 0.3642s8 0210U1992 3.81 0212011992 Nr06 3.69 38438 56s4 0.347778 t0l0ut999 3.69 l0lt2ll999 u0t6 4.25 41789 5122 0.37ss00 03llsl200r 4.25 0313012001 u035 4.26 41628 5122 0.37s153 031t5/2001 4.26 0313112001 AA24 4.18 442s61968 0.37ttsl tv0ll2009 4.18 tut2l2009 LA33 3.80 44194 9166 0340701 021t711990 3.80 03/16/1990G005 3.02 3 197 3 I 17 99 0.3 634 I 0 r2l 03 I 1982 3.02 021 t8/ 1983 s033 3.36 38828 62010.373943 0410y1998 3.36 04/1811998 LA24 3.80 39199 9166 0.3s6290 021t711990 3.80 0311611990 R040 3.85 422t5 6745 0.373845 l0/05/1996 3.85 1012011996 LALT 3.8r 2973s 9674 0.357785 0912711988 3.81 l0/30/1988s006 3.85 46217 6201 03738s7 0410U1998 3.8s 04/19/1998BB24 3.97 43285 1968 0.37 07 62 l l l 0l 12009 3.97 r U t0 12009 xOl5 4.19 47s33 4212 0.373251 0911212003 4.19 0912612003 x010 4.17 45440 4212 0.374352 0911212003 4.17 0912612003 y03l 4.05 ss274 1968 0.374314 tU0U2009 4.05 rlllll2009 u006 4.24 46926 5122 0.3743s8 03/1 sl200t 4.24 03129/2001 Nr24 3.69 40231 5654 0.347086 l0/01/1999 3.691011y1999 Ml0l 3.80 40557 56s4 0.348716l0l0l/1999 3.80 t0ll2ll999 pl I I 3.59 42524 s6s4 0.349747 l0l0ut999 3.59 t0ll3ll999 M00 r 3.8 r 38 I 67 8452 0.364042 0210t I 1992 3.81 021201 1992 u042 4.25 42863 5122 0.37s088 03llsl200t 4.25 0313012001Ml l7 3.79 38914 s654 03492s9 10101/1999 3.79 t0lt2lt999Nl l8 3.71 41t70 s6s4 0.347824 l0l0ut999 3.71 t0lt2/1999 u0t3 4.25 40246 5122 0.375322 0311s12001 4.25 0313012001 w038 3.61 36913 sl22 0.370256 03ltsl200l 3.61 03/3012001 D043 2.99 30218 12849 0.373206 0l/18/1980 2.99 0411611980 LA44 3.80 33s12 96740.3402610912711988 3.80 l0/30/1988 AA39 4.27 s09t41445 0.372699 04109120t1 4.27 0412312011FC08514 Page 18 of24 Revision 0 AA10 3.ss 444s0 2s30 o.37tz2t o4nstzool:.qs os6ti?'rfl6$'o' 8007 2.38 27041 13690 0.372805 0913011977 2.38 1111611977 w043 4.24 38247 sr22 0.370862 0311512001 4.24 03/2912001s039 3.3s 36580 674s 0.373925 t0l0slr996 3.35 l0lt9/1996N006 3.69 45116 7851 0.364490 0912s11993 3.69 1010811993 u02r 4.25 43491 sl22 0.375349 03llsl200t 4.25 0312912001KA04 3.5r 42747 9t66 0.354s04 0211711990 3.51 03114/1990 R0l3 3.85 45732 6745 0.374207 101051t996 3.8s 10/1911996 x026 4.19 37677 4212 0.372061 0911212003 4.19 0912212003 xol9 4.19 47604 4212 0.373296 0911212003 4.19 0912612003 xol6 4.19 47666 4212 0.373126 0911212003 4.19 0912212003 x009 4.17 45561 4212 0.374063 0911212003 4.t7 0912612003 w036 3.61 37262 5122 0.371436 0311512001 3.61 03129/2001Ml l5 3.79 39628 5122 0.349055 03115120013.79 0312912001 BBl2 4.09 477rs r44s 0.373264 0410912011 4.09 0412312011 Ml l2 3.79 48373 5654 0.348803 l0i0ll1999 3.79 l0lllll999 }l4t23 3.80 38919 5654 0.348319 l0i0ll1999 3.80 l0ll3ll999 Ml03 3.8139214 56s4 0.3482261010U1999 3.81 l0lt3lr999 Nl0l 3.71 45737 7851 0.34836s 0912511993 3.7r 1010611993 2022 3.68 31448 3677 0.372211 0212612005 3.68 0311212005 M0 r 3 3.80 38264 84s2 0.364489 021 0t / 1992 3.80 02/20 / 1992 Z03t 3.63 362683677 0.371007 021261200s 3.63 03/1212005 R04r 3.8s 41768 674s 0.373908 l0/0s/1996 3.8s 1012011,996Z035 3.63 35s91 3677 0.370837 0212612005 3.63 03/1212005 sol s 3.35 368s8 6745 0.373905 l0/0s/1996 3.3s 10/2011996 y049 4.00 4214t 3677 0373132 021261200s 4.00 0311312005s035 3.35 36839 6745 0.373818 10/0s/19963.351012011996 z0t4 3.43 35957 3677 0.370908 0212612005 3.43 0311312005 s0l8 3.36 2s264 6745 0.373966 t0l0sll996 3.36 t0lr9/1996 LA36 3.80 33078 9674 0.341248 0912711988 3.80 10i30/1988 T026 3.76 32859 6201 0.374311 0410yr998 3.76 04119/1998 u020 4.25 41644 sl22 0.375899 03ltsl200l 4.2s 031291200r G04l 3.01 39343 10769 0.364138 091281198s 3.01 12/0811985 BB02 4.tt 493s6 t445 0.373428 0410912011 4.110412312011 xOl3 4.19 47767 4212 0.373242 0911212003 4.19 0912312003 R028 3.8s 46013 6201 0.374700 041011998 3.85 04119/1998 x040 4.20 44s10 4212 0.37t327 0911212003 4.20 09/2s12003 pl20 3.s8 44724 5654 0.3s020310101/1999 3.58 t0/1211999 u039 4.25 4s000 st22 0.374785 0311512001 4.2s 03/2912001 y0l9 3.96 43s061445 0.372398 04109120r l 3.96 04/2312011 N00s 3.69 4t4r7 5654 0.364632l0l0lll999 3.69 10/11/1999Ml l4 3.79 39155 5654 0.349374 l0l0lll999 3.79 t0/rr/1999 AA0l 3.95 46757 2s30 0.371349 04/1912008 3.95 04/3012008 NOl3 3.69 44797 78sl 0.363973 0912s11993 3.69 l0/08/l qe3T027 3.76 34882 620t 0.374358 04101/1998 3.76 04/1811998R037 3.86 42224 6745 0.3735r6 10/0s/1996 3.86 1012011996 R005 3.86 42402 674s 0.374199 10/0511996 3.86 1012011996 R008 3.85 42298 674s 0.37436210/0s11996 3.8s 1012011996 R009 3.85 42ttt 6745 0.3741l5 l0/05/1996 3.8s t0ll9ll996T042 3.75 37417 6201 0.374341 0410111998 3.75 0411911998 R036 3.8s 3846s 6201 0.374144 0410U1998 3.8s 0412011998 w042 4.23 38351 5122 0.370872 03llsl200l 4.23 0312812001BB09 4.09 47731 1445 0.373239 0410912011 4.09 04/2312011 R026 3.85 45979 6201 0.374516 0410y1998 3.85 0411811998FC08514 Page 19 of24 Revision 0 Attachment 10.2 x036 4.20 44499 4212 0.370998 0911212003 4.20 0912612003 DD2l 4.00 38016 1445 0.385009 0410912011 4.03 0412312011N015 3.69 4t404 56s4 0.364732l0l0llr999 3.69 l0/lllt999 Ml l6 3.80 3892s s654 0.348148 l0/01/1999 3.80 1,011311999 Ml t0 3.80 38905 5654 0.348467 l0l0,/r999 3.80 l0ll2lr999 y004 0.34 l1658 2530 0.375152 0411912008 0.34 05/01/2008s024 3.35 36733 6745 0.373985 l0/05/1996 3.35 1011911996 u036 4.25 41469 5122 0.375063 03115/2001 4.25 031301200r R00l 0.74 13047 6745 0.375851 l0/05/19960.74 1012011996 z0t3 3.43 35918 3677 0.3708210212612005 3.43 03/1312005 ROl7 3.86 41381 6745 0.3737981010511996 3.861012011996 y040 4.01 44410 3677 0.373404 0212612005 4.01 0311312005 s023 3.36 36056 674s 0.374380 l0/05/1996 3.36 10/1911996 R004 0.75 12980 6745 0.37s813 1010511996 0.75 l0lt9lt996 R003 0.74 13078 6745 0.375935 1010511996 0.741011911996 y047 4.00 42173 3677 0.372407 021261200s 4.00 031t3/200s M008 3.81 43960 8452 0.364667 02101/1992 3.81 0212011992 G0l4 3.03 39051 11344 0.362929 0310211984 3.03 0611811984 Ftlt 2.74 30618 122410.364407 09/18/1981 2.74 t2l0tlt981s004 3.8s 33780 62010.373030 04/01/1998 3.85 04120/1998BB20 3.97 403381445 0.370749 04109120113.97 04124120rr cc3l 4.00 419s9 l44s 0.386198 041091201 I 3.70 0412212011 c004 3.19 2544213690 0.371920 0913011977 3.19 I 111611977 x024 4.19 44369 4212 0.372732 0911212003 4.19 09/2612003 pt27 3.s9 44837 56s4 0.349619 t0l0lll999 3.59 r0ll3ll999 u027 4.2s 44328 5122 0.374693 0311512001 4.2s 0312912001 w022 3.60 3 t266 sr22 0.372s36 03115/2001 3.60 03130/2001N004 3.70 45302 s6s4 0.364715 r0l0lll999 3.70 t0ltrll999 NOl6 3.70 4s459 5654 0.36s183 l0/01/1999 3.701011211999 w04l 4.24 3827s sl22 0.3707s6 03llsl200l 4.24 0312812001 Nl l7 3.70 38446 5654 0.347594 l0l0llt999 3.70 l0ll3ll999 Ml06 3.80 39140 s6s4 0.3488921010,/1999 3.80 t0lr2lt999 s02s 3.3s 38839 6201 0.37471s 0410Ut998 3.3s 041201t998R047 3.60 38359 674s 0.37s385 l0/05/1996 3.601011911996 LA2s 3.80 43394 9166 0.340664 021t711990 3.80 031t6/1990 y044 4.02 44687 1968 0.3730s21U0112009 4.02 t1/1U2009R048 3.60 38357 6745 037s421 10105/1996 3.6010119/1996 s0r 1 3.84 37446 674s 0.374087 1010511996 3.84 l0lt8lr996 s032 3.3s 35305 674s 0.374413 t0l0slr996 3.3s 1012011996 R002 0.75 r29s2 674s 0.376043 1010511996 0.75 t0lt8/1996 2009 3.42 35805 3677 0.370895 0212612005 3.42 03/1312005s026 3.3s 36194 6745 0.374474 t0l0s/1996 3.35 l0/1811996 JA30 3.51 38738 9166 0.355146 0211711990 3.sl0311211990R045 3.60 38374 674s 0.37s012 t0l0slt996 3.60 1012011996 KAl2 3.50 42892 9166 0.3s6159 0211711990 3.50 0311411990 R033 3.8s 38477 62010.374s37 0410111998 3.85 0411911998s005 3.84 46261 6201 0.373814 0410vt998 3.84 0411811998 s007 3.8s 46244 62010.3729610410111998 3.85 0411811998 ccl l 4.00 43979 1445 0.389364 04109/20113.99 04124/2011 z0t6 3.42 36077 3677 0.370720 0212612005 3.42 03112/2005 M0l9 3.79 38530 8452 0.36s119 021011t992 3.79 0212011992 R029 3.8s 42479 6201 0.37sr64 04101/1998 3.85 04120/1998G039 3.03 36183 10244 0.3641ss 0310711987 3.03 0312411987 N003 3.69 4s098 78sl 0.364310 091251t993 3.69 10108/t993FC08514 Page 20 ol 24 Revision 0 N 1 04 3.7 l 4s72878s l 0.348 2s6 oe t2s I tss3 3.7 t I o/d$iiBTt'o' s022 3.35 2s263 674s 0.374838 10/0s/1996 3.3s 10119/1996 Ml 13 3.81 45904 84s2 0.349070 0210U1992 3.81 0212011992 KA01 3.52 43910 9166 0.3s4s93 0211711990 3.52 03/1411990 LA07 3.81 37 07 s 8452 0.35 8 t 40 021 0t I 1992 3.81 021221 t992 KArs 3.50 442819674 0.339743 0912711988 3.50 l0/30/1988 LA01 3.80 38724 9166 0.35881102117/1990 3.80 03/1611990s012 3.84 29991 6745 0.374416 1010511996 3.841011911996 IA09 3.sl 34980 10769 0.357s83 091281r98s 3.sl 12108/1985 KAl0 3.49 41976 9166 0.3s6152 0211711990 3.49 0311611990 s021 3.36 25244 6745 0.374600 10i05/1996 3.36 10118/1996 NOl8 3.70 46097 7851 0.36s2210912511993 3.701010811993D006 2.94 30218 12849 0.371844 0l/18/1980 2.94 0411611980 NOl7 3.70 46040 78sl 0.3655720912511993 3.701010611993 c0l3 3.19 35491 13310 0.3704s7 l0lt5lr978 3.19 l2ll0ll978 D0t3 2.96 27 388 I 33 I 0 0.37 309 6 r0 I I 5 I 197 8 2.96 tzl l0 I r97 8 x032 4.20 40853 4212 0.371351 0911212003 4.20 0912612003NOr0 3.69 45018 78sl 0.3641480912511993 3.69 10/0811993M004 3.81 44063 8452 0.364480 0210111992 3.8r 02/2011992 LAt4 3.81 37633 9166 0.3s7s77 0211711990 3.81 0311211990 MOl5 3.78 42816 84s2 0.364179 0210111992 3.78 0212011992 LA22 3.8r 39441 9166 0.3s6620 021171t990 3.81 031161t990 AA13 3.9s 40983 2530 0.371086 0411912008 3.95 0510112008 s0l4 3.84 30136 6745 0.373490 1010511996 3.84 1012011996 R043 3.8s 41757 674s 0.3744861010511996 3.85 t0/19/1996T043 3.75 40304 4709 0.374848 0s10312002 3.75 0s11412002 M0 I 8 3.7 7 427 37 8452 0.365228 02101 I 1992 3.7 7 02/20 I 1992 w039 3.61 36777 5122 0.37 0320 03 1 1 s 1200 1 3.6 1 03 /30/2001 AA38 4.27 3s667 3tt8 0.372923 0910912006 4.27 09/18/2006s040 3.3s 48653 6201 0.373764 0410111998 3.35 0411811998 M0l6 3.78 42851 8452 0.364066 0210v1992 3.78 02120/1992 w0l2 4.22 34026 sl22 0.373723 03llsl200l 4.22 031291200r w008 4.21 33740 5122 0.374403 0311512001 4.2t 0312812001w002 4.2t 35242 5122 0.373639 0311512001 4.21 0312812001 x038 4.20 39499 4212 0.371612 0911212003 4.20 0912612003 w026 3.60 36963 sl22 0.371680 03/l s/2001 3.60 03129120014.A06 3.9s 39436 1968 0.371261 1110112009 3.95 tlllll2009 x033 4.20 44442 4212 0.371224 0911212003 4.20 0912212003 u037 4.25 44968 5122 0.374485 0311512001 4.2s 03/301200t uOl8 4.25 41632 5122 0.37s96s 03llsl200t 4.25 0313012001 u022 4.25 43474 sl22 0.375153 0311512001 4.25 031301200t w013 3.60 361 t7 5122 0.372101 0311512001 3.60 03130/2001T034 3.75 30276 4709 0.374068 0s10312002 3.75 05/14/2002 w019 3.60 3598s st22 0.372162 03ltsl200l 3.60 03/2812001 Ml08 3.80 45005 8452 0.347494 0210111992 3.80 02/20/1992R022 3.86 51611 6201 0.37391t 04/0U1998 3.86 04/1911998 w00l 4.21 3s313 st22 0.3741s8 031t512001 4.21 0312812001 p003 3.94 44413 7337 0.365514 021201199s 3.94 03/0411995 R038 3.86 42039 6745 0.373227 1010511996 3.86 t011911996 p002 3.94 44521 7337 0.36s478 0212011995 3.94 03104/199s u0t0 4.2s 49176 st22 0.375426 03ltsl200l 4.25 0312912001 uDfi 4.25 49116 5122 0.374654 0311512001 4.2s 0312912001 w006 4.2r 33783 5122 0.374393 03115/2001 4.21 0312812001 w009 4.22 33982 sr22 0.373943 0311512001 4.22 031301200t FC08514 Page21 of24 Revision 0 Attachment 10.2 w004 4.21 35515 5122 0.373605 03/l 512001 4.21 0313012001 w003 4.21 35413 5122 0.374050 03/l 512001 4.21 031281200r x029 4.20 39462 4212 0.371627 0911212003 4.20 0912612003 w02s 3.60 37489 5122 0.371536 0311512001 3.60 03/29/2001w035 3.6t 37147 st22 0.371672 0311512001 3.61 03130/2001 cctT 4.00 39856 t44s 0.386492 041091201I 3.70 04/2412011 y039 4.02 44386 3677 0.373374 0212612005 4.02 0311212005 u023 4.25 4348s sl22 0.375207 0311512001 4.25 03129/2001 Y023 3.9r 43429 1445 0.370496 041091201I 3.91 04122/2011 y02t 3.96 45045 3677 0.3724s3 0212612005 3.96 031121200s x004 3.51 35743 4212 0.370855 0911212003 3.51 0912212003 AA29 4.r9 442s61968 0.3709821110112009 4.19 rl1U2009 cc32 4.00 38806 1968 0.386s60 lll0l12009 3.70 llll0l2009 DD3s 4.00 31364 1445 0.386334 041091201I 3.87 04122/2011 DD27 4.00 33s98 1445 0.38s470 041091201I 4.03 0412412011 DD28 4.00 33383 t44s 0.385448 0410912011 4.03 04123/2011 DD36 4.00 314201445 0.386582 041091201I 3.87 04123/2011 DD26 4.00 33599 1445 0.385601 0410912011 4.03 04123/2011 DD33 4.003t421 l44s 0.3856010410912011 3.86 0412312011 DD34 4.00 3t364 1445 0.38s943 0410912011 3.86 04123/201r DD25 4.00 33382 l44s 0.385404 04109/201l 4.03 04123/20rrDD23 4.00 37730 1445 0.385458 04109/201I 4.03 04/2312011 wOl0 4.22 25180 5122 0.374483 0311512001 4.22 03128/200r x03t 4.20 40850 4212 0.371403 0911212003 4.20 0912612003 y032 4.05 5s233 1968 0.374404 rr/0v2009 4.0s ll/ty2009 2037 3.63 38817 2530 0.370810 04119/2008 3.63 04/30/2008 T004 4.16 40400 4709 0.374819 0s103/2002 4.16 051t2/2002 T024 4.t6 3361 1 4709 0.374862 0510312002 4.16 0s/14/2002T045 3.7s 40317 4709 0.374s4r 05/0312002 3.7s 0511412002 Y05l 4.0r 38643 3lL8 0.372947 0910912006 4.0r 09/1812006 s003 3.85 33847 6201 0.374s010410111998 3.8s 04/1811998 u0t9 4.25 4t646 st22 0.375562 0311512001 4.25 0312912001 Z023 3.68 422t9 3n8 0.372133 0910912006 3.68 0911712006 cc33 4.00 38806 1968 0.386388 11i01/2009 3.70lllll12009 R042 3.86 41705 6745 0.374397 1010511996 3.861011711996 AA28 4.19 44216 r968 0.370999 1y0y2009 4.19 tyt2l2009ROl0 3.8s 41710 6745 0.373368 r0/0s/1996 3.8s 1011811996 w007 4.22 2s146 st22 0.374s4s 0311512001 4.22 0312812001 x005 4.17 46151 4212 0.374389 09A2t2003 4.17 0912612003 T038 3.7s 34080 4709 0.37s069 0s/0312002 3.75 05113/2002 T002 4.16 40362 4709 0.374833 0s10312002 4.16 0slr2/2002 T0t8 4.ls 38433 4709 0.374022 05/0312002 4.r5 05/13/2002T022 4.16 33617 4709 0.374s00 0510312002 4.16 05/1412002 T04t 3.7s 40251 4709 0.374599 0510312002 3.7s 0s11312002 z0t7 3.68 42323 3tr8 0.372188 0910912006 3.68 0911812006 y0l5 3.96 44668 3tt8 0.372704 0910912006 3.96 09118/2006 cc20 4.00 38805 1968 0.386583 tu0t/2009 3.70lllll12009 cc30 4.00 38841 1968 0.386189 ty0v2009 3.70 tyty2009 cc2t 4.00 38807 1968 0.3864761U0U2009 3.70 tuty2009 y03s 4.03 445621968 0.373852 rv0y2009 4.03 rlll0/2009 BB2r 3.97 43289 1968 0.370703 n10U2009 3.97 tvt2l2009 NOl l 3.69 45105 7851 0.364556 0912s11993 3.69 10108/1993 w0 I 6 3.60 299 58 5122 0.37 0902 03 I l 5 1200 I 3.60 03 12812001R03s 3.8s 38s07 62010.374383 04/0U1998 3.85 041t911998 FC08514 Page22 ot 24 Revision 0 Attachment 10.2 xOl8 4.19 39272 42120.373107 0911212003 4.19 0912212003 x027 4.19 37659 4212 0.371665 0911212003 4.19 09122/20032028 3.63 3879t 2530 0.371260 0411912008 3.63 05/01/2008 T0t2 4.16 4r048 4709 0.3744910510312002 4.16 0511212002 cc44 4.00 439301445 0.385979 04109120113.87 0412412011 z}tt 3.43 35908 3677 037090s 02126/2005 3.43 031121200sT046 3.75 40267 4709 0.374804 0510312002 3.75 05113/2002 cc14 4.00 42941 1445 0.389029 04109120113.97 04/22/2011 y0l6 3.96 44661 3tr8 0.372598 0910912006 3.96 0911812006s008 3.84 46195 62010.373505 0410111998 3.84 0411911998 cc25 4.00 38798 1968 0.3866841110112009 3.70lllrll2009 p008 3.94 4514s 7337 0.366399 0212011995 3.94 03/041199s LA2l 3.80 391s9 9166 0.356142 0211711990 3.80 0311211990 y038 4.04 445681968 0.373796ItI0r12009 4.04 tt/tt12009 D03S 2.97 33748 12849 0.371767 0l/18/1980 2.97 0411611980 p007 3.94 4s I 8 I 7337 0.365958 021201 t995 3.94 03 /041 1995 A0l0 I .39 7913 14654 0.375172 0210811975 1.39 0411011975 x003 3.51 3s709 4212 0.370889 0911212003 3.sl 09126/2003T008 4.16 42817 4709 0.374958 0510312002 4.16 0511212002 y 012 3.7 4 47 084 3 l l 8 0.37 I 6 66 09 I 09 12006 3.7 4 09 I 17 12006 T0l l 4.ls 40971 4709 0.3742s8 0510312002 4.ls 0511212002 T02t 4.16 42706 4709 0.374298 0s10312002 4.16 0s11312002T032 3.7s 40662 4709 0.373932 0510312002 3.7s 0s11412002 x02t 4.19 44473 42120.37249409112/2003 4.19 0912212003 y046 4.00 38s32 3118 0.373095 09109/2006 4.00 09/1712006w034 3.6t 3703s st22 0.372161 03llsl200l 3.61 03/3012001 u026 4.25 44339 sr22 0.3749t6 03ltsl200l 4.25 03/3012001 cc23 4.00 38840 1968 0.3865l0 lll0y2009 3.70 ll/tl12009 Mr09 3.80 39535 sl22 0.348423 0311512001 3.80 03/28/2001 p00l 3.94 45060 7337 0.365284 0212011995 3.94 03/0411995 LAI l 3.81 38033 8452 0.357631 0210111992 3.81 021201t992 w01r 4.222s423 st22 0.374700 0311512001 4.22 0313012001 x035 4.20 40864 4212 0.371248 0911212003 4.20 09123/2003 T039 3.76 34107 4709 0.374903 0s10312002 3.76 0s11412002 T036 3.76 40681 4709 0.373682 0510312002 3.76 0511412002 T003 4.17 40558 4709 0.374607 05103/2002 4.tT0sll2l2002 T0l5 4.15 42777 4709 0.374362 05/03/2002 4.15 0511412002 T0l3 4.16 38480 4709 0.374115 05/0312002 4.16 0s11412002 2002 3.44 3s732 3677 0.37ts04 02126/2005 3.44 0311212005 T0t7 4.15 38499 4709 0.374068 05/0312002 4.r5 05114/2002 z0t0 3.42 35872 3677 0.370750 0212612005 3.42 03112/2005 T023 4.15 4273s 4709 0.374196 05/03/2002 4.15 05/13/2002 cc28 4.00 38797 r968 0.386363 1U0U2009 3.70llll0/2009E020 3.03 2644212849 0.3642s2 01/18/1980 3.03 0411611980 w005 4.22 2s 48s 5 122 0.37 45 t 4 03 I t s 12001 4.22 03 I 29 1200 t x0t4 4.19 39355 4212 0.3728s6 09/1212003 4.19 0912312003 T040 3.76 34086 4709 0.3750rr 05/0312002 3.76 0s/1412002 T035 3.7s 40626 4709 0.373606 05/03/2002 3.75 0s/13/2002T00s 4.16 40575 4709 0.374573 0s10312002 4.16 0511212002 cc4l 4.00 43961 t44s 0.386436 04109/201I 3.87 04123120rt u003 0.27 10492 5122 0.375000 03llsl200l 0.27 03130/2001 x030 4.20 44486 4212 0.371314 0911212003 4.20 09123/2003 AA33 4.31 440721445 0.373074 0410912011 4.31 0412312011u044 4.2s 42780 st22 0.37s243 03ltsl200t 4.25 0312812001FC08514 Page 23 of 24 Revision 0 x008 4.17 4ss6s 4212 0.374060 osnztzoo3 4.17 ogtfiiffilto, x0t7 4.19 39317 42t2 0373200 0911212003 4.19 09/22/2003 T0l6 4.16 42780 4709 0.374405 0510312002 4.16 0511412002 T009 4.16 41055 4709 0.374362 0s/0312002 4.16 0511212002 T010 4.15 410s7 4709 0.373866 0510312002 4.15 0511212002 Mr24 3.80 46307 5122 0.346642 03llsl200l 3.80 0312812001G007 3.02 39051 11344 0.363922 0310211984 3.02 06/1811984 x0t2 4.17 45529 4212 0.373906 0911212003 4.17 0912212003 y0s0 4.00 38740 3l l8 0.373284 0910912006 4.00 09/1812006 T006 4.17 42678 4709 0.374810 0s10312002 4.17 05112/2002 x007 4.17 46203 42120.375047 0911212003 4.17 09122/2003 T00t 4.16 434t8 4709 0.374752 0s10312002 4.16 0s11212002 T007 4.16 43447 4709 0.375100 0s10312002 4.t6 0511212002T037 3.75 30252 4709 0.374306 0510312002 3.75 0511412002 T020 4.16 33594 4709 0.37437s 0510312002 4.16 0511412002 y048 4.01 38671 3l r 8 0.373 r5s 0910912006 4.01 09/19/2006T030 3.76 30273 4709 0.374048 0510312002 3.76 0511412002 x020 4.19 39383 4212 0.373203 0911212003 4.19 0912612003 pl 05 3.60 37316 785 I 0.349722 0912511993 3.60 10/0811993 x006 4.r7 46136 4212 0.375608 0911212003 4.17 09123/2003 x011 4.17 46286 4212 0.374388 0911212003 4.17 09126/2003 x001 3.51 35800 42120.37091609/1212003 3.51 09123/2003 x037 4.20 39451 4212 0.371730 0911212003 4.20 09123/2003 x022 4.19 44526 4212 0.372499 09/12/2003 4.19 0912312003FC08514 Page 24 ol 24 Revision 0 FC08514 Page 1 of 10Aftachment 10.3 oRNL/TM-2005139 Version 6.1 Sect. Dl Reactor and Nuclear Systems Division ORIGEN.ARP: AUTOMATIC RAPID PROCESSING FOR SPENT FUEL DEPLETION,DECAY, AND SOURCE TERM AIIALYSN I. C. Gauld S. M. Bowman J. E. Horwedel'Date Published: June 20l l Prepared for the Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 under Interagency Agreement DOE 1886-T487-08NRC JCN No. J5609 Prepared by OAK RIDGE NATIONAL LABORATORY Oak Ridge, Tennessee 37831-6170 managedby UT-Battelle, LLC for the U.S. DEPARTMENT OF ENERGYunder contract DE-AC05 - 00OR227 25" Formerly with Oak Ridge National Laboratory. Revision 0 FC08514 Page 2 of 10 Aftachment 10.3 ABSTRACT ORIGEN-ARP is a SCALE depletion analysis sequence used to perform point-depletion calculations with the ORIGEN-S code using problem-dependent cross sections. Problem-dependent cross-section libraries are generated using the ARP (Automatic Rapid Processing) module using an interpolation algorithm that operates on pre-generated libraries created for a range of fuel properties and operating conditions. Methods are provided in SCALE to generate these libraries using one-, two-, and three-dimensional transport codes. The interpolation of cross sections for uranium-based fuels may be performed for thevariables burnup, enrichment, and water density. An option is also available to interpolate cross sections for mixed-oxide (MOX) fuels using the variables bumup, plutonium content, plutonium isotopic vector, and water moderator density. Interpolation may also be performed for flux-based calculations usingneutron fluence as the interpolation parameter. An important feature of the sequence is the OrigenArp Windows graphical user interface. Written in Visual C++, OrigenArp greatly facilitates the creation of input files for the ARP and ORIGEN-S codes with toolbars, forms, and online help to assist the user.OrigenArp interacts directly with the SCALE code system to execute the input files in the requiredsequence, and executes a post-processor to extract desired quantities. An interactive plotting program is also provided for rapid display and analysis ofrequested data.Revision 0 FC085't4 Page 3 of 10 Attachment 10.3 CONTENTS page LIST OF FIGURES ............vii LIST OF TABLES.... ...........ix ACKNOWLEDGMENTS ................. .......................... xi Dl .1 . INTRODUCTION .......... .... Dl.l.l D1.2. WINDOWS GRAPHICAL INTERFACE....,......... ....D1.2,1 D1.2.1 EXPRESS FORM......... .........D1.2.1 D1.2.2 DETAILED FORMS...... .......D1.2.3 DI.3. ARP METHODOLOGY .....D1.3.1 Dl.3.t ARP INPUT DESCRIPTION.............. ...... Dl.3.4 DI.4. ORIGEN-ARP SAMPLE PROBLEMS .D1.4.1 D1.4.1 SAMPLE PROBLEM l: PWRDEMONSTRATION .D1.4.1 Dl.4.2 SAMPLE PROBLEM 2: H.B. ROBINSON FUEL SAMPLE N-9C-D.............Dl.4.3 DI.4.3 SAMPLE PROBLEM 3: COOPERBWRASSEMBLY C2205 .....D1.4.7 Dt.4.4 SAMPLE PROBLEM 4: TURKEY POINT PWR ASSEMBLY D-I5 ............. Dl.4.1 I Dl.4.5 SAMPLEPROBLEM5: CANDUNATURALURANIUMFUEL D1.4.14 Dl.4.6 SAMPLEPROBLEM6: OECDMOXBENCHMARK..... D7.4.17 D1.5. REFERENCES.............. .....D1.s.1 DI.A. ARP CROSS-SECTION LIBRARIES ..DI.A.l D1.A.I DESCRIPTION OF ORIGEN-ARP LIBRARIES IN SCALE....... . DI.A.I Dl.A.2 HOW TO GENERATE CROSS-SECTION LIBRARIES........... ... DI.A.9 Dl.A.3 REFERENCES.............. ....D1.A.16 Dl.B. UTILTTY PROGRAMS................. ........ Dl.B.lDI.B.I PRISM DI.B.I DI.B.z ARPLIB DI.B.8 D1.B.3 XSECLIST. .... DI.B.I I Revision 0 FC085'14 Page 4 of 10 Attachment 10.3 LIST OF FIGURES Figure Page Dl.2.l. The Origen Express form display for UO2 fuel............. D1.2.2 D1.2.2. The Origen Express form display for MOX fue1............. Dl.2.3 D1.2.3. The detailed compositions form display........ ..........D1.2.4 D1.2.4. The case data form display for an irradiation case. .D1.2.5 DL.2.5. The case data form display for a decay case. ........... Dl.2.6 D1.2.6. The plot setup form display. D1.2.7 Dl .3.1 . Effective absorption cross section as a function of bumup for the 2a0Pu isotope D1 .3.1 Dl.3.2. Effective absorption cross section as a function of enrichment. ................. ....D1.3.2 D1.3.3. Effective absorption cross section as a function of water-moderator density. D1.3.3 Dl.3.4. Examples of ARPDATA.TXT entries......... .......... Dl.3.11 D1.4.1. Simple demonstration problem input listing D1.4.2 Dl-4.2. H. B. Robinson assembly B05, Pellet N-9C input listing.......... .. DI.4.5 D1.4.3. Cooper BWR input listing. D1.4.9 D1.4.4. Turkey Point PWR input listing. .......D1.4.12 D1.4.5. CANDU reactor input listing. D1.4.15 D1.4.6. OECD MOX benchmark input. ......... D1.4.18 Dl .4.7 . Actinide results for the OECD Phase IV-B RG MOX assembly benchmark. . Dl .4.20 D1.4.8. Fission product results for the OECD Phase IV-B RG MOX assembly benchmark.. ....... Dl.4.20 Dl.A.1. TRITON input example used to generate ORIGEN-ARP cross-section libraries............ Dl.A.1 I Dl.B.1. PRISM input example to generate TRITON input files. .............D1.B.3 D1.B.2. Generic TRITON input template for PRISM ...........D1.B.4 D1.B.3. ARPLIB example input to reduce size of ORIGEN-ARP cross-section libraries.............D1.B.10 D1.B.4. XSECLIST input examp1e................. Dl.B.l3 Dl.B.s. XSECLIST listing of 2a0Pu data. ........... ................D1.B.14 Revision 0 FC08514 Page 5 of 10 Attachment 10.3 LIST OF TABLES Table Page D1.3.1. Input description for uranium fuels........... D1.3.5 D1.3.2. Input description for MOX fuels ......... D1.3.6 D1.3.3. Input description for activation problems..... D1.3.7 DI.3.4. ARPDATA.TXT file description for uranium fuel types.... ........ Dl.3.8 Dl.3.5. ARPDATA.TXT file description for MOX fuel types.... Dl.3.9 DI.3.6. ARPDATA.TXT file description for activation types........ ....... Dl.3.10 D1.4.1. Data for simple ORIGEN-ARP demonstration problem... Dl.4.1 DL.4.2. Data for H. B. Robinson Assembly B05, Pellet N-9C-D................ D1.4.4 D1.4.3. Data for Cooper BWR assembly C2205 D1.4.8 D1.4.4. Data for Turkey Point 3 PWR assembly D-15 ...... Dl.4.l I D1.4.5. Data for CANDU 685 GJ/kgU Bruce 'A' case ............ Dl.4.l4 Dl.A.l. Summary of ORIGEN-ARP 1ibraries................ ..... D1.A.2 Dl.A.z. PWR fuel design and operating data......... D1.A.3 Dl.A.3. BWR fuel design and operating data.......... Dl.A.4 Dl.A.4. MOX fuel assembly design and operating data.......... D1.A.6 Dl.A.5. Non-LWR reactor fuel and operating data............ . Dl.A.7 Dl.A.6. VVER-440 fuel design and operating data.......... ... Dl.A.8 Dl.A.7. Cross section positions and burnup values created in the example................. Dl.A.l5 Dl.B.l. PRISM input description............. ........D1.B.2 Dl.B.2. ARPLIB input description............. ......D1.B.9 Dl.B.3. XSECLIST input description............. ...................D1.8.12 Revision 0 FC08514 Page 6 of 10 Attachment'10.3 ACKNOWLEDGMENTSThe authors thank S. B. Ludwig for his support in earlier stages of this work. The authors are grateful for the technical advice received from B. L. Broadhead, M.D. DeHart, N. M. Greene, O. W. Hermann, C. V. Parks, L. M. Petrie, and J. C. Ryman. The authors thank Germina Ilas and Georgeta Radulescu for reviewing the manual and Willena Carter forthe preparation of the manuscript.Revision 0 FC08514 Page 7 of 10 Attachment 10.3 Water Density (S/cm')Figure D1.3.3. Effective absorption cross section as a function of water-moderator density.Mixed-oxide (MOX) fuel contains a mixture of plutonium and uranium oxide. Interpolation is performed using the total plutonium content in the heavy metal, the plutonium isotopic vector (Pu vector) thatdefines the relative concentrations of the Pu isotopes, and water-moderator density. The variation of the absorption cross sections is observed to be near linear as a function of Pu content. Interpolation on the Pu vector is more complex than the uranium enrichment for UO2 fuel since the vector is composed of five different isotopes: "tPu, "'Pu, 'ooPu, 2o'Pu, and 2a2Pu. Furthermore, the elements in the vector aredependent on one another and can therefore not be evaluated independently ofone another since the entire vector must sum to 100%u The scheme developed for the Pu vector was based on an evaluation of a large database of plutonium compositions for actual MOX fuel assemblies (European origin). One might expect that the variations of 23nPu and all other Pu isotopes in the vector would need to be parameterized.However, an evaluation of the MOX fuel database indicated that there is a strong correlation between 23ePu and the other isotopes in the vector that permits the cross sections for the MOX fuel to be determined to sufficient accuracy using only the 23ePu concentration. The cross sections for 238Pu, 240Pu, 2arPu, and "'Pu are based. only on the 23ePu concentration using empirical relationships derived from a second-order least-squares regression analysis of the MOX fuel vector database. Studies conducted usingadditional Pu isotopes, instead of just "'Pu to perform the cross-section interpolation, yielded similar interpolation accuracy. Therefore, cross-section interpolation for the MOX Pu vector is currently performed using 23ePu only. The cross-section error in this interpolation approach was generally found to be less than l%o. The MOX interpolation methods and libraries are described in greater detail in Ref. 2.Cross-section interpolation in ARP is performed using the Lagrangian method. The interpolation solver was implemented from the function YLAG first developed at Oak Ridge National Laboratory [Ref. 3].()d L.cl ,.o o t)*r)a u, m o tr (J tr o B o ta s (., a 19 H Revision 0 Attachment'10.3FC08514 Page 8 of 10 FC08514 Page 57 o't 327 D1.A.t Dl.A. ARP CROSS.SECTION LIBRARIES DESCRIPTION OF ORIGEN-ARP LIBRARIES IN SCALE The ARP code creates bumup-dependent ORIGEN-S cross-section libraries by interpolating over basic cross-section libraries generated in advance using reactor physics transport methods. The basic cross-section libraries distributed in SCALE include many classes of commercial power reactor designs and a range of fuel assembly designs. Cross sections for the pressurized water reactor (PWR), boiling light water reactor (BWR), and VVER fuels have been generated using the two-dimensional lattice physics code NEWT (Sect. F21) as applied in the TRITON depletion analysis module (Sect. T1). Most other cross-section libraries were generated using the one-dimensional XSDRNPM transport code (Sect. F3) as applied in the SAS2 depletion analysis sequence which is no longer supported in SCALE.Cross-section libraries suitable for use with ORIGEN-ARP are available in SCALE for the followingreactor and fuel assembly designs: o BWR 7x7,8x8-4,8x8-1,9x9-8, 9x9-9,10x10-9, lOxl0-8, SVEA-64 and SVEA-I00 o PWR 7 4x14, 1 5 x I 5, l6x 16, 17 xl7 o CANDU reactor (28- and 37-element bundle designs)o Magnox graphite reactor o Advanced Gas-Cooled Reactor (AGR). WER 440 and VVER 1000 o RBMK. MOX BWR 8x8-2,9x9-7,9x9-9, 10x10-9 o MOX PWR l4xl4, 15x15, l6x76,17xl1,18xl8 All of the libraries distributed with SCALE were developed using ENDF/B-V-based cross section libraries and SCALE modules with the exception of the CANDU pressurized heavy water reactor fuellibraries, which obtained from the RSICC code package DLC-210, contributed by Atomic Enerry of Canada Limited. The CANDU libraries were generated by the WIMS lattice code using ENDF/B-V cross sections. The libraries for MOX, Magnox, and AGR fuels were generated using the one-dimension depletion analysis module SAS2 in SCALE 5. All other libraries for BWR and PWR low-enriched uranium (LELD fuel assemblies were generated with the two-dimension depletion analysis module TRITON in SCALE 5.1. The assembly design and the identifier for each library are summarized in Table D1.A.l.The libraries for BWR and RBMK assembly designs all include variable coolant density. Table Dl.A.1lists the number of cross-section files associated with each individual assembly design; this number is a product of the number of enrichments and the number of coolant density values. Unless otherwise noted in Table Dl.A.l, the PWR and BWR LEU libraries were generated for six enrichment values: 1.5, 2.0,3.0, 4.0, 5.0, and 6.0 wt yo23tlJ. The cross sections are represented at eleven bumup values in the range from 0 to 72,000 MWdiMTU. The fuel assembly designations used for many of the BWR designs includethe iiasic lattice type, followed optionally by the number of empty (non fuel) lattice positions. Forexample, the 9x9-9 designation refers to the Atrium design with a 9x9 assembly lattice with 9 non-fuel (water) locations. In general, multiple libraries were developed for a particular BWR lattice type only when the configuration of the water sites was judged to have a significant neutronic effect on the cross sections. The non-proprietary design data used to generate these libraries are listed in Tables Dl.A.2-Table D1.A.6. The tables include the fuel lattice type, the fuel vendor (where design information is specific to a vendor design), the assembly model, basic fuel design and reactor operating data, and the Revision 0 Attachment 10.3FC08514 Page 9 of 10FC08514 Page 58 of 327 range of the variable parameters associated with the libraries (e.g., enrichment range, burnup range, etc.). A more detailed description of the data for these libraries can be found in separate reports that are listed inthe tables." LEU: Low-enriched uranium D Mox: Mi*ed-oxide Table Dl.A.1. Summary of ORIGEN-ARP librariesReactor type Assembly design description Library name No. ofcross-section liles PWRLEU4 Westinghouse CE l4x 14 Westinghouse CE l6x 16 Westinghouse l4x14 Siemens 14x14 Westinghouse 15x15 Westinghouse 17x17 Westinshouse 17xl7 OFA cel4xl4 cel6xl6 w14xl4 s14x14 w15x15 w17xl7 wl7xl7 ofa 6 6 6 6 6 6 6 BWRLEU GE7x7GE 8x8 ABB 8x8 GE 9x9 GE 10x10 ATRIUM.9 ATRIUM.IO SVEA-64 SVEA-IOO ge7x7-0 ge8x8-4 abb8x8-l ge9x9-7 gel0xl0-8 atrium9-9 atriuml0-9
svea64-l sveal00-0 30 30 30 30 30 30 30 30 30PWR MOX6 4xl4 5x l5 6x 16 7x17 8x 18 mox14xl4moxl 5xl 5 mox16x16 moxlTxlT moxl8xl8 5 5 5 5 5 BWR MOX 8x8 9x9-l ATRIUM 9x9-9 l0x l0 mox8x8 mox9x9-1 mox9x9-9 moxlOxl0 60 60 60 60 VVER VVER-440 fl at enrichment l.6yo, 2.4o/o, 3.6oh VVER-440 profiled enrichment, average 3.82o/o VVER-440 profiled enrichment, average 4.25o/o VVER-440 profiled enrichment, average 4.38Yo VVER-IOOO wer440(3.6) wer440(3.82) wer440(4.25) wer440(4.38) werl000 3 I I I 6RBMKRBMK 1000, enrichments 1.8 to2.2wtYo rbmk l8 CANDU28-element bundle design 37-element bundle design candu2Se candu3Te I I Magnox Magnox graphite reactor (Calder Hall design)magnox I AGR Advance gas cooled reactor agr I Revision 0 FC08514 Page 10 of 10 Attachment 10.3 Table D1.A.2. PWR fuel design and operating data Assembly lattice Model CE'l4xl4 CE*14 xl4 Siemens w'l4x14 W l5xl5 CE l6xl6 CE\\ST Enrichments (wt % 23sU)Maximum burnup (MWd/kgU)No. rods per assembly No. water holes Rod pitch (cm)Assembly pitch (cm)Fuel rod data Fuel density (g/"*')Pellet diameter (cm)Clad material Clad inner diameter (cm)Clad outer diameter (cm)Fuel temperature (K)Clad temperature (K)Guide tube data Inner radius (cm)Outer radius (cm)Guide tube material Moderator dataAverage density (g/c-')Average boron concentration (ppm)Moderator temperature (K)References 1.5-6 72 236 5 1.285 20.78 10.41 0.8255 (Zircaloy-Zi 0.8433 (0.9703 (1000 620 1.143 (1.2446 (Zircaloy-4 Zi 0.7100 (650 600 1.5-6 72 176 5 t.473 20.78 rc.4f 0.9680 Zircaloy-4 0.9850 1 .l 180 873 620 1.314 1.416 Zircaloy-4 0.7332 331 570 1.5--6 72 180 t6 1.430 20.12 9.742 0.925 Zircaloy-4 0.930 1.071 859 605 0.6413 0.6845 Zircaloy-4 0.7283 450 572 1.5-6 72 179 l7 1.412 19.77 10.41 0.9294 Zircaloy-2 0.9483 1.07t9 923 595 0.6413 0.6485 Zircaloy-2 0.7264 653 573.4 1.5-6 72 204 2t 1.430 21.45 10.41 0.9294 Zircaloy-2 0.9484 1.0719 923 595 0.6502 0.6934 Zircaloy-2 0.7135 653 579 A.5. A.6. A.7 A.1 A.5. A.6" A.7. A.8 4.2.4.5.4.7 A.5. A.6" A.7 A.5." CE: Combustion Engineering 6 W: Westinghouse" OFA = Optimized Fuel Assembly r' Equal to 957o theoretical density Revision 0 Gamma DDl Sub Batch Gamma photons/sec/bas ORIGEN2 Group ORIGEN grp maxgamma MeV Attachment 10.4.1.A boundaries FC08514 Page 1 19 18 t7 16 15 t4 13 L2 LL 10 9 8 7 6 5 4 3 2 L 0.02 20000 0.03 30000 0.045 45000 0.07 70000 0.1 100000 0.15 1s0000 0.3 300000 0.45 450000 0.7 700000 1 1000000 1.5 1500000 2 2000000 2.s 2s00000 3 3000000 4 4000000 6 5000000 8 8000000 11 11000000 1 0.00E+00 2 2.00E-02 3 3.00E-02 4 4.50E-02 5 7.00E-02 5 1.00E-01 7 1.50E-01 8 3.00E-01 9 4.50E-01 10 7.00E-01 LL 1.00E+00 LZ 1.50E+00 13 2.00E+00 L4 2.50E+00 15 3.00E+00 15 4.00E+00 L7 6.00E+00 18 8.00E+00 totals 0 Output Group mev 2.OOE-02 3.00E-02 4.50E-02 7.00E-02 1.00E-01 1.50E-01 3.00E-01 4.50E-01 7.00E-01 1.00E+00 1.50E+00 2.00E+00 2.50E+00 3.00E+00 4.00E+00 6.00E+00 8.00E+00 1.10E+01 1E-03 y 3.42E+L7 5.25E+16 5.48E+16 3.37E+16 4.53E+15 1.81E+17 L.35E+L7 3.63E+16 1.18E+17 9.47E+16 2.3LE+L6 2.18E+16 2.18E+15 7.92E+L4 3.55E+13 L,57E+L2 5.05E+05 5.81E+05 1.14E+18 3E-03 y 2.54E+L7 4.01E+16 4.43E+L6 2.58E+16 3.74E+t6 L.48E+L7 L.O4E+L7 2.93E+16 8.84E+15 7.55E+16 1.20E+15 1.87E+16 1.33E+15 6.72E+L4 5.38E+12 2.13E+10 5.05E+06 5.81E+05 8.90E+17 2E-02y 5.77E+L6 L.42E+L6 1.90E+16 1.04E+16 1.25E+16 2.88E+16 1.53E+15 L,2LE+L6 4.23E+Lo 4.48E+15 3.88E+15 1.23E+16 8.11E+14 4.54E+14 3.68E+12 4.35E+07 5.01E+06 5.75E+05 2.86E+L7 Revision 0 Gamma DDl Sub Batch 7E-O2v 0.2 y Attachment 10.4.1.A FC08514 Page 2 3.45E+15 7.88E+15 1.00E+16 5.94E+15 5.03E+15 1.10E+16 4.47E+Ls 4.51E+15 2.72E+L6 3.35E+15 1.75E+15 4.67E+Ls 3.97E+L4 L.72E+L4 1.51E+12 4.27E+07 4.92E+06 5.66E+05 L,5LE+T7 2.28E+L6 5.01E+15 5.50E+15 3.98E+15 2.97E+Ls 5.69E+15 2.84E+15 1.54E+15 1.60E+15 2.LZE+!G 7.83E+L4 3.30E+14 1.24E+L4 1.09E+13 2.49E+LL 4.O5E+07 4.58E+06 5.38E+05 8.89E+16 o.7 v 1.39E+16 3.00E+15 3.30E+15 2.52E+L5 1.90E+15 2.63E+15 1.82E+15 9.48E+14 9.82E+15 5.94E+15 5.49E+14 5.88E+13 6.96E+13 L.46E+L2 1.33E+11 3.54E+07 4.198+06 4.82E+05 4.75E+16 1.5 v 7.72E+L5 1.58E+15 1.85E+15 1.40E+15 1.05E+15 1.38E+15 1.00E+15 5.29E+L4 7.30E+15 2.74E+L5 3.738+14 3.23E+13 3.42E+L3 8.23E+11 7.52E+LO 3.27E+O7 3.77E+OG 4.33E+05 2.71E+15Twelve Assemblies 9.27E+15 2.01E+16 2-23E+L6 1.68E+16 L.26E+L6 1.55E+15 L.zoE+to 5.35E+15 8.76E+16 3.29E+16 4.47E+Ls 3.87E+14 4.toE+L4 9.87E+L2 9.02E+11 3.93E+08 4.52E+07 5.20E+06 3.25E+77 Revision 0 Gamma DD2 Sub Batch Gamma photons/sec/bas ORIGEN2 Group ORIGEN grp max gamma ev Attachment 10.4.1.A boundaries mev FC08s14Page 3 1E-02 y L.43E+17 2.43E+L6 2.90E+15 1.61E+16 2.32E+L6 7.68E+16 4.90E+15 1.94E+16 5.57E+LG 5.50E+16 6.32E+15 1.58E+16 1.02E+15 5.85E+14 4.56E+12 3.96E+07 4.56E+06 5.25E+05 5.16E+17 3E-03 y 2.57E+L7 3.90E+15 4.31E+16 2.49E+16 3.64E+16 L,44E+L7 L.0lE+L7 2.85E+16 8.58E+15 7.33E+16 1.15E+15 1.83E+16 1.27E+!5 6.55E+14 5.25E+Lz 2.09E+10 4.57E+06 5.25E+05 8.55E+17 190 18 0.02 L7 0.03 0.045 0.07 0.1 0.15 0.3 0.45 0.7 1 1.5 0 Output Group 16 15 L4 13 L2 11 10 9 8 20000 30000 45000 70000 100000 150000 300000 450000 700000 1000000 1s00000 2000000 2500000 3000000 4000000 5000000 8000000 11000000 1 0.00E+00 2.0OE-O2 2 2.00E-02 3.00E-02 3 3.00E-02 4.50E-02 4 4.50E-O2 7.00E-O2 5 7.00E-02 1.00E-01 5 1.00E-01 1.50E-01 7 1.s0E-01 3.00E-01 8 3.00E-01 4.50E-01 9 4.50E-01 7.00E-01 10 7.00E-01 1.00E+00\L 1.00E+00 1.50E+00 LZ 1.50E+00 2.00E+00 13 2.00E+00 2.50E+00 L4 2.50E+00 3.00E+00 15 3.00E+00 4.00E+00 15 4.00E+00 6.00E+00 t7 6.00E+00 8.00E+00 18 8.00E+00 1.10E+01 totals 1E-03 y 3.32E+L7 5.11E+15 5.33E+16 3.27E+LG 4.50E+16 1.75E+L7 L.32E+L7 3.53E+15 t.L4E+L7 9.19E+15 2.248+L6 2.L3E+LG 2.09E+15 7.72E+L4 3.47E+L3 L.54E+tz 4.57E+O6 5.26E+05 1.11E+18 72 6 2.s 53 44 36 2 1 8 LL Revision 0 Gamma DD2 Sub Batch 3E-02 y 0.1y Attachment 10.4.1.A FC08514 Page 4 5.55E+16 t.22E+L6 1.66E+15 9.04E+15 1.03E+16 2.L9E+L6 t.L7E+L6 1.02E+16 3.79E+15 4.13E+16 3.21E+15 1.08E+16 7.04E+L4 4.00E+14 3.25E+L2 3.93E+07 4.53E+06 5.20E+05 2.42E+L7 2.98E+LG 6.75E+15 8.19E+15 5.09E+15 4.04E+15 9.20E+15 3.71E+15 3.10E+15 2.29E+t6 2.95E+16 1.30E+15 2.76E+75 2.80E+14 1.01E+14 9.50E+11 3.83E+07 4.4LE+OG 5.07E+05 1.27E+17 0.5 v 1.57E+16 3.39E+15 3.71E+15 2.82E+15 2.L3E+15 3.08E+15 2.04E+15 1.06E+15 1.04E+15 9.76E+15 5.72E+14 6.55E+13 7.84E+t3 L.62E+L2 L.44E+LL 3.39E+07 3.90E+06 4.49E+05 5.48E+15 1.5 v 7.45E+15 1.62E+15 1.80E+15 1.36E+15 1.02E+15 1.33E+15 9.70E+14 5.L2E+L4 5.93E+15 2.58E+15 3.54E+14 3.11E+13 3.33E+13 7.94E+11 7.25E+10 2.92E+{7 3.37E+05 3.87E+05 2.60E+16 Five Assemblies 3.73E+16 8.11E+15 8.99E+15 6.78E+15 5.08E+15 5.57E+15 4.85E+15 2.56E+15 3.45E+15 L.29E+LG L.77E+Ls 1.55E+14 1.67E+L4 3.97E+Lz 3.63E+11 1.46E+08 1.68E+07 1.94E+06 1.30E+17 Revision 0 Gamma DD3 Sub Batch Gamma photons/sec/ba, ORI6EN2 Group ORIGEN grp max gamma MeV 190 0 Output Group 0.02 0.03 0.045 0.07 0.1 0.15 0.3 0.45 0.7 1 1.5 2 2.5 3 4 5 8 11 Attachment 10.4.1.A boundaries FC08514 Page 5 18 L7 16 15 L4 13 L2 IL 10 9 8 7 6 5 4 3 2 1 20000 30000 45000 70000 100000 150000 300000 4s0000 700000 1000000 1500000 2000000 2500000 3000000 4000000 6000000 8000000 11000000 1 0.00E+00 2 2.OOE-O?3 3.00E-02 4 4.50E-O2 5 7.00E-02 5 1.00E-01 7 1.50E-01 8 3.00E-01 9 4.50E-01 10 7.00E-01 11 1.00E+00 tZ 1.50E+00 13 2.00E+00 L4 2.50E+00 15 3.00E+00 15 4.00E+00 L7 5.00E+00 18 8.00E+00 totals mev 2.O0E-O2 3.00E-02 4.50E-02 7.00E-02 1.00E-01 1.50E-01 3.00E-01 4.50E-01 7.00E-01 1.00E+00 1.50E+00 2.00E+00 2.50E+00 3.00E+00 4.00E+00 6.00E+00 8.00E+00 1.10E+01 1E-03 y 3.13E+17 4.99E+16 5.32E+16 3.17E+16 4.30E+16 1.66E+17 L.27E+L7 3.46E+16 1.13E+17 9.15E+16 2.L3E+L5 2.19E+16 1.91E+15 8.08E+14 3.74E+L3 1.85E+12 1.61E+05 1.85E+05 1.07E+L8 3E-03 y 2.4LE+L7 3.80E+16 4.28E+L6 2.38E+16 3.48E+16 1.36E+17 9.68E+16 2.80E+16 8.29E+L5 7.36E+16 9.94E+15 1.88E+16 9.96E+14 6.81E+14 5.43E+72 2.52E+10 1.51E+06 1.85E+05 8.28E+L7 1E-02 y 1.35E+17 2.38E+15 2.89E+16 1.53E+16 2.23E+t6 7.33E+16 4.65E+16 L.92E+L6 5.30E+16 5.57E+15 5.00E+15 L.64E+L6 7.8LE+L4 6.11E+14 4.82E+L2 1.39E+07 1.60E+06 1.84E+05 4.96E+L7 Revision 0 Gamma DD3 Sub Batch 3E-02 y 0.1y 0.3 y Attachment 10.4.1.A 1.5 v 5.59E+15 1.43E+15 1.61E+15 1.20E+15 9.07E+14 1.25E+15 8.62E+14 4.53E+14 4.81E+15 1.69E+15 2.47E+L4 2.61E+13 3.34E+13 5.29E+11 5.58E+10 8.40E+05 9.58E+05 1.11E+05 2.11E+16 Four Assemblies 2.53E+15 5.72E+L5 5.45E+15 4.81E+15 3.53E+15 4.98E+15 3.45E+15 1.81E+15 L.92E+16 6.74E+15 9.89E+14 1.04E+14 1.34E+14 2.52E+12 2.27E+!L 3.36E+07 3.87E+05 4.45E+05 8.44E+76 FC08514 Page 6 5.41E+L6 1.20E+16 1.55E+16 8.68E+15 9.96E+15 2.18E+16 L.L2E+L6 1.028+16 3.40E+16 4.2tE+L6 2.34E+L5 L.L2E+L5 5.31E+14 4.L9E+L4 3.36E+12 1.38E+07 1.58E+06 1.82E+05 2.35E+L7 2.90E+16 6.56E+15 8.11E+15 4.93E+15 3.91E+15 9.39E+15 3.57E+15 3.04E+15 L.92E+16 3.02E+16 9.18E+14 2.84E+15 2.25E+L4 1.06E+14 9.48E+11 L.32E+O7 1.51E+05 1.74E+O5 1.22E+77 1.86E+16 4.03E+15 4.55E+15 3.28E+15 2.45E+L5 4.40E+15 2.33E+15 1.21E+15 9.88E+15 1.63E+15 4.87E+14 1.18E+14 9.76E+13 3.40E+12 1.44E+LL 1.18E+07 1.36E+06 1.56E+05 6.78E+16 1.0 v 9.38E+15 2.03E+15 2.29E+L5 1.71E+15 1.30E+15 1.83E+15 L-24E+L5 6.44E+t4 5.67E+15 2.85E+15 3.15E+14 3.75E+13 5.13E+13 8.88E+11 7.99E+10 9.20E+05 1.06E+05 L.22E+O5 2.94E+L6 Revision 0 Gamma EEl Sub Batch Gamma photons/sec/basi: ORIGEN2 Group ORIGEN grp max gamma MeV Attachment 10.4.1.A boundaries mev FC08514Page 7 LE-O2v t.43E+L7 2.45E+L6 2.94E+75 1.53E+15 2.34E+t6 7.67E+15 4.89E+16 1.96E+15 5.58E+15 5.61E+16 6.15E+15 L.62E+L5 9.83E+14 5.99E+14 4.76E+L2 3.33E+07 3.83E+05 4.41E+05 5.19E+17 1E-03 y 3.31E+17 5.14E+16 5.41E+15 3.30E+15 4.51E+16 L.75E+L7 1.33E+17 3.56E+15 L,L6E+L7 9.33E+16 2.25E+L6 2.L7E+tG 2.09E+15 7,9LE+L4 3.58E+13 L.64E+72 3.84E+05 4.42E+05 1.11E+18 3E-03 y 2.55E+L7 3.93E+16 4.37E+L6 2.52E+L6 3.65E+16 L,43E+L7 1.01E+17 2.88E+16 8.54E+15 7.46E+tG L.L4E+L6 1.86E+16 L.22E+15 6.70E+14 5.36E+12 2.23E+LO 3.84E+05 4.42E+O5 8.66E+17 19 18 L7 16 15 L4 13 L2 11 0 0.02 0.03 0.045 0.07 0.1 0.15 0.3 0.45 8 11 2.00E-02 3.00E-02 4.50E-02 7.00E-02 1.00E-01 1.50E-01 3.00E-01 4.50E-01 7.00E-01 1.00E+00 1.50E+00 2.00E+00 2.50E+00 3.00E+00 4.00E+00 6.00E+00 8.00E+00 1.10E+01 0 Output Group 30000 2 45000 3 70000 4 100000 5 1s0000 5 300000 7 4s0000 8 700000 9 1000000 10 1s00000 LL 2000000 L2 2s00000 13 3000000 t4 4000000 15 6000000 16 8000000 t7 11000000 18 0.00E+00 2.00E-02 3.00E-02 4.50E-02 7.00E-02 1.00E-01 1.50E-01 3.00E-01 4.50E-01 7.00E-01 1.00E+00 1.50E+00 2.00E+00 2.50E+00 3.00E+00 4.00E+00 5.00E+00 8.00E+00 totals 20000 10 0.7 91 8 1.5 72 6 2.5 53 44 36 2 1 Revision 0 Gamma EEl Sub Batch 3E-02 y 0.1y Attachment 10.4.1.A 1.5 y 0.3 v 1.98E+16 4.31E+15 4.78E+15 3.50E+15 2.62E+L5 4.50E+15 2.50E+15 1.30E+15 L.27E+LG 1.69E+16 6.38E+14 L.27E+14 1.00E+14 3.67E+Lz 1.73E+11 2.97E+07 3.42E+06 3.94E+05 7.37E+LG 16 Assemblies L.t9E+17 2.58E+16 2.88E+16 2.16E+16 L.62E+t6 2.15E+15 1.54E+16 8.14E+15 1.05E+17 3.93E+16 5.43E+15 4.89E+14 5.43E+14 1.23E+13 L.l2E+L2 3.80E+08 4.37E+07 5.03E+06 4.08E+17 FC08514 Page 8 1.0 y 5.62E+L6 L.24E+L6 1.59E+15 9.15E+15 1.04E+16 2.22E+L6 L.LlE+Lo 1.04E+16 3.77E+L6 4.22E+L6 3.08E+15 1.10E+16 6.76E+L4 4.10E+14 3.32E+12 3.30E+07 3.80E+06 4.37E+05 2.44E+L7 3.02E+15 6.83E+15 8.33E+15 5.15E+15 4.09E+15 9.40E+15 3.75E+15 3.14E+15 2.25E+L6 3.03E+15 t.Z4E+L5 2.82E+L5 2.72E+14 1.04E+14 9.63E+11 3.20E+O7 3.69E+05 4.24E+05 L.28E+L7 1.04E+15 2.25E+L5 2.50E+15 1.90E+15 1.43E+15 1.95E+15 L.37E+Ls 7.L5E+L4 7.80E+15 3.74E+L5 4.26E+L4 4.35E+13 5.20E+13 1.08E+12 9.82E+10 2.52E+O7 2.91E+05 3.34E+05 3.46E+16 7.428+t5 1.61E+15 1.80E+15 1.35E+15 1.01E+15 1.:l4E+15 9.55E+14 5.09E+14 5.54E+15 2.468+15 3.39E+14 3.05E+13 3.40E+13 7.67E+tL 6.99E+10 2.37E+O7 2.73E+05 3.14E+05 2.55E+16 Revision 0 Gamma EE2 Sub Batch Gamma photons/sec/basi ORIGEN2 Group ORIGEN grp max gamma MeV 0 0 Output Group 0.02 20000 0.03 30000 0.045 45000 0.07 70000 0.1 100000 0.15 150000 0.3 300000 0.45 450000 o.7 700000 1 1000000 1.5 1500000 2 2000000 2.s 2s00000 3 3000000 4 4000000 6 5000000 8 8000000 11 11000000 19 18 L7 16 15 L4 13 L2 11 10 9 8 7 5 5 4 3 2 1 Attachment 10.4.1.A boundaries mev FC08514 Page 9 1.3 v 7.65E+15 1.65E+15 1.87E+15 1.40E+15 1.05E+15 1.44E+15 1.00E+15 5.26E+L4 5.67E+Ls 2.76E+L5 2.98E+14 3.08E+13 3.86E+13 7.50E+LL 6.78E+10 L.24E+07 L.42E+OG 1.64E+05 2.48E+15 o.2v 2.04E+L6 4.45E+15 5.04E+15 3.57E+15 2.67E+Ls 5.08E+15 2.54E+15 1.348+15 1.19E+15 1.90E+15 5.69E+14 2.LLE+L4 1.08E+14 6.79E+L2 1.82E+U L.67E+O7 1.92E+06 2.20E+05 7.69E+16 1.0 v 9.58E+15 2.09E+15 2.35E+15 L.77E+Ls 1.34E+15 1.87E+15 1.28E+15 5.65E+14 6.34E+15 3.12E+15 3.50E+14 3.92E+13 5.14E+13 9.43E+11 8.51E+10 1.31E+07 1.51E+06 1.73E+05 3.09E+16 1 0.00E+00 2 2.00E-02 3 3.00E-02 4 4.50E-02 5 7.O0E-02 6 1.00E-01 7 1.50E-01 8 3.00E-01 9 4.50E-01 10 7.00E-01 LL 1.00E+00 L2 1.50E+00 13 2.00E+00 L4 2.50E+00 15 3.00E+00 16 4.00E+00 L7 5.00E+00 18 8.00E+00 totals 2.OOE-O2 3.00E-02 4.50E-02 7.00E-02 1.00E-01 1.50E-01 3.00E-01 4.50E-01 7.00E-01 1.00E+00 1.50E+00 2.00E+00 2.50E+00 3.00E+00 4.00E+00 6.00E+00 8.00E+00 1.10E+01 Revision 0 Gamma EE2 Sub Batch l.s y Attachment 10.4.1.A FC08514 Page 10 5.84E+15 1.49E+15 1.67E+15 1.25E+15 9.388+14 L.27E+Ls 8.93E+14 4.59E+14 5.39E+15 1.92E+15 2.768+14 2.74E+13 3.358+13 5.688+11 5.05E+10 l.2,,E+O7 1.39E+05 1.60E+05 2.25E+16 12 Assemblles 8.21E+15 1.78E+16 2.00E+16 1.50E+16 1.13E+15 1.53E+16 1.07E+16 5.63E+15 6.46E+16 2.318+15 3.31E+15 3.28E+14 4.O2E+L4 8.02E+L2 7.26E+LL 1.45E+08 L.67E+07 1.92E+05 2.7OE+L7 Revision 0 Gamma EE3 Sub Batch Gammaphotons/sec/basis ORIGEN2Group ORIGEN grp maxgamma MeV Attachment 10.4.1.A 1E-03 y 3.10E+17 4.93E+15 5.26E+16 3.14E+15 4.26E+16 1.65E+17 L.26E+L7 3.43E+15 t.tlE+L7 9.05E+15 2.LLE+L6 2.L6E+L6 1.90E+15 7.98E+14 3.59E+13 L.82E+L2 1.65E+06 1.90E+05 1.05E+18 FC08514Page 11 3E-03 y 2.39E+L7 3.75E+16 4.24E+16 2.35E+15 3.44E+L5 L.35E+L7 9.58E+15 2.77E+LG 8.2LE+L6 7.27E+L6 9.87E+15 1.86E+16 9.91E+14 6.73E+L4 5.36E+12 2.48E+10 1.55E+06 1.90E+05 8.2OE+L7 19 18 t7 15 15 L4 13 L2 LL 10 9 8 7 5 5 4 3 2 L 0 0 Output Group0.02 20000 10.03 30000 2 0.045 45000 30.07 70000 40.1 100000 s 0.15 150000 60.3 300000 7 0.45 450000 8 0.7 700000 91 1000000 101.5 1500000 LL2 2000000 L22.5 2500000 13 3 3000000 L44 4000000 155 6000000 168 8000000 L711 11000000 18 boundaries 0.00E+00 2.O0E-02 3.00E-02 4.50E-02 7.00E-02 1.00E-01 1.50E-01 3.00E-01 4.50E-01 7.00E-01 1.00E+00 1.50E+00 2.00E+00 2.50E+00 3.00E+00 4.00E+00 5.00E+00 8.00E+00 totals 2.00E-02 3.00E-02 4.50E-02 7.O0E-O2 1.00E-01 1.50E-01 3.00E-01 4.50E-01 7.00E-01 1.00E+00 1.50E+00 2.00E+00 2.50E+00 3.00E+00 4.00E+00 6.00E+00 8.00E+00 1.10E+01 Revision 0 Gamma EE3 Sub Batch 1E-02 y 3E-02 y 1.34E+17 2.35E+16 2.85E+16 1.52E+16 2,2LE+L6 7.26E+LG 4.51E+16 1.90E+15 5.25E+16 5.51E+16 4.98E+15 L.52E+LG 7.78E+t4 5.04E+14 4.76E+12 1.43E+O7 1.65E+06 1.89E+05 4.9LE+L7 Attachment 10.4.1.A 1.0 y o.1v 0.3 v 2.88E+16 6.50E+15 8.04E+15 4.88E+15 3.87E+15 9.28E+15 3.54E+15 3.01E+15 1.91E+16 2.99E+16 9.19E+14 2.81E+15 2.25E+L4 1.04E+14 9.38E+11 1.35E+07 1.56E+06 1.79E+05 l.2LE+L7 5.36E+15 1.19E+16 1.64E+16 8.61E+15 9.85E+15 2.15E+15 1.11E+15 1.01E+16 3.38E+16 4.16E+16 2.34E+L5 1.10E+16 5.29E+L4 4.L4E+L4 3.32E+L2 L.4LE+07 1.63E+06 1.87E+05 2.33E+L7 1.85E+16 4.00E+15 4.51E+15 3.25E+15 2.44E+15 4.36E+15 2.32E+15 t.2OE+15 9.88E+15 1.62E+16 4.88E+14 t,L7E+L4 9.67E+13 3.37E+Lz L,44E+LL L.22E+07 1.40E+06 1.61E+05 6.73E+tG 9.33E+15 2.O2E+L5 2.28E+L5 1.71E+15 1.29E+15 1.82E+15 1.23E+15 6.4LE+L4 5.70E+15 2.86E+15 3.17E+L4 3.74E+L3 5.09E+13 8.87E+11 7.98E+10 9.51E+06 1.10E+05 1.26E+05 2.93E+16 6.55E+15 1.42E+15 1.61E+15 1.20E+15 9.02E+14 1.24E+15 8.588+14 4.51E+14 4.83E+15 1.70E+15 2.4J,E+t4 2.60E+13 3.31E+13 5.28E+11 5.58E+10 8.59E+06 1.00E+06 1.15E+05 2.11E+15 FC08514 Page t2 Four Assemblie 2.62E+L6 5.70E+15 6.42E+L5 4.79E+L5 3.61E+15 4.94E+15 3.43E+15 1.80E+15 1.93E+16 6.78E+15 9.93E+14 L.04E+L4 L.32E+L4 2.51E+tz 2.27E+LL 3.48E+07 4.00E+06 4.60E+05 8.43E+16 1.5 v Revision 0 Gamma EE3 Sub Batch ts Attachment 10.4.1.A FC08514 Page 13 Revision 0 Gamma FFl Sub Batch Gamma photons/sec/ba: ORIGEN2 Group ORIGEN grp maxgamma MeV 0 0.02 0.03 0.045 0.07 0.1 0.15 0.3 0.45 0.7 1 1.5 Attachment 10.4.1.A boundaries mev FC08514Page 14 19 18 L7 15 15 L4 13 L2 11 10 9 8 72 5 2.5 53 20000 30000 45000 70000 100000 150000 300000 450000 700000 1000000 1500000 2000000 2500000 3000000 4000000 5000000 8000000 11000000 0 Output Group o.1v 2.87E+L6 5.45E+15 8.06E+15 4.85E+15 3.85E+15 9.40E+15 3.50E+15 2.99E+15 L.79E+t6 3.06E+15 8.07E+L4 2.84E+L5 2.O7E+t4 1.05E+14 9.34E+11 8.81E+06 1.01E+05 1.17E+05 1.20E+L7 1.0 v 8.99E+15 1.94E+15 2.22E+L5 1.64E+15 1.25E+15 1.79E+15 1.18E+15 5.13E+14 5.09E+15 2.66E+15 2.8LE+14 3.47E+L3 5.11E+13 7.78E+LL 5.94E+10 5.72E+O6 5.58E+05 7.57E+O4 2.77E+L6 1.1y 8.45E+15 1.82E+15 2.09E+15 1.54E+15 L,L7E+Ls 1.68E+15 1.11E+15 5.76E+L4 4.94E+15 2.32E+t5 2.69E+L4 3.26E+13 4.76E+L3 7-34E+LL 6.56E+10 5.59E+06 5.43E+05 7.39E+04 2.60E+15 1 0.00E+00 2.00E-02 2 2.00E-02 3.00E-02 3 3.00E-02 4.50E-02 4 4.50E-O2 7.OOE-OZ 5 7.00E-02 1.00E-01 5 1.00E-01 1.50E-01 7 1.50E-01 3.00E-01 8 3.00E-01 4.50E-01 9 4.50E-01 7.00E-01 10 7.00E-01 1.00E+00 11 1.00E+00 1.50E+00 72 1.50E+00 2.00E+00 13 2.00E+00 2.50E+00 14 2.50E+00 3.00E+00 15 3.00E+00 4.00E+00 16 4.00E+00 5.00E+00 t7 6.00E+00 8.00E+00 18 8.00E+00 1.10E+01 totals 4 6 8 Ll 4 3 2 t Revision 0 Gamma FFl Sub Batch r.2y t.2y Attachment 10.4.1.A 1.5 v 6.29E+15 1.35E+15 1.56E+15 1.15E+15 8.57E+14 1.21E+15 8.20E+14 4.29E+L4 4.32E+L5 1.498+15 2.2OE+L4 2.4OE+13 3.32E+13 5.50E+11 4.94E+10 5.11E+06 5.88E+05 6.77E+O4 1.988+16 Eight Assemblies 5.04E+15 1.09E+16 1.25E+16 9.18E+15 5.94E+15 9.71E+15 6.56E+15 3.43E+15 3.45E+16 1.20E+15 1.76E+15 1.92E+!4 2.66E+14 4.4OE+12 3.95E+11 4.09E+07 4.7LE+06 5.41E+05 1.58E+17 FC08514Page 15 7.94E+L5 L.7LE+Ls 1.96E+15 1.45E+15 1.10E+15 1.57E+15 1.04E+15 5.42E+L4 4.80E+15 2.06E+15 2.58E+L4 3.06E+13 4.42E+L3 5.93E+11 6.19E+10 5.47E+06 6.29E+05 7.24E+04 2.45E+L6 7.48E+L5 1.52E+15 1.85E+15 1.37E+15 1.04E+15 L.47E+15 9.81E+14 5.11E+14 4.67E+LS 1.87E+15 2.48E+L4 2.88E+13 4.t2E+t3 5.54E+11 5.85E+10 5.35E+05 6.17E+05 7.10E+04 2.32E+L6 1.3 v 7.O7E+L5 1.53E+15 1.75E+15 1.29E+15 9.78E+L4 1.38E+15 9.26E+14 4.83E+14 4.55E+15 L.72E+t5 2.38E+14 2.72E+13 3.84E+13 5.19E+11 5.54E+10 5.27E+06 6.07E+05 6.98E+04 2.20E+L5 1.4 v 6.66E+15 1.44E+15 1.65E+15 L.22E+ts 9.19E+14 1.29E+15 8.70E+14 4.54E+!4 4.43E+15 1.59E+15 2.28E+L4 2.55E+13 3.57E+13 5.83E+u 5.22E+LO 5.19E+06 5.97E+05 6.87E+04 2.08E+15 Revision 0 Gamma FF2 Sub Batch Gamma photons/sec/basi ORtGEN2 Group ORIGEN grp max gamma MeV 0 0.02 0.03 0.045 0.07 0.1 0.15 0.3 0.45 o.7 L 1.5 1 0.00E+00 2.00E-02 2 2.00E-02 3.00E-02 3 3.00E-02 4.s0E-02 4 4.50E-02 7.00E-O2 5 7.00E-02 1.00E-01 5 1.00E-01 1.50E-01 7 1.50E-01 3.00E-01 8 3.00E-01 4.50E-01 9 4.50E-01 7.00E-01 10 7.00E-01 1.00E+00 IL 1.00E+00 1.50E+00 L2 1.50E+00 2.00E+00 13 2.00E+00 2.50E+00 L4 2.50E+00 3.00E+00 15 3.00E+00 4.00E+00 16 4.00E+00 6.00E+00 L7 5.00E+00 8.00E+00 18 8.00E+00 1.10E+01 totals 19 18 L7 15 15 L4 13 L2 11 10 9 8 0 Output Group Attachment 10.4.1.A boundaries mev FC08514Page 16 L.2y 8.09E+15 1.75E+15 2.00E+15 1.48E+15 1.12E+15 1.59E+15 1.05E+15 5.53E+14 5.07E+15 2.18E+15 2.73E+L4 3.15E+13 4.44E+L3 7.24E+Lt 6.49E+10 6.74E+06 7.75E+O5 8.93E+04 2.52E+!6 o.1v 2.88E+16 6.49E+15 8.08E+15 4.88E+15 3.87E+15 9.38E+15 3.53E+15 3.01E+15 1.84E+16 3.04E+16 8.52E+14 2.83E+15 2.L4E+L4 1.06E+14 9.35E+11 1.05E+07 1.21E+06 1.39E+05 L.21E+77 1.1y 8.60E+15 1.86E+15 2.L2E+L5 1.57E+15 1.19E+15 1.69E+15 1.13E+15 5.88E+14 5.22E+15 2.45E+15 2.85E+14 3.35E+13 4.77E+L3 7.67E+LL 6.87E+10 6.88E+06 7.91E+05 9.10E+04 2.68E+16 72 6 2.5 53 44 36 28 111 20000 30000 4s000 70000 100000 150000 300000 450000 700000 1000000 1500000 2000000 2s00000 3000000 4000000 5000000 8000000 11000000 Revision 0 Gamma FF2 Sub Batch t.ZV 1.3 y 7.63E+15 7.20E+L5 1.65E+15 1.56E+15 1.88E+15 1.78E+15 1.39E+15 1.31E+15 1.06E+15 9.94E+L4 1.49E+15 1.39E+15 1.ggE+15 9.42E+14 5.2LE+L4 4.92E+L4 4.94E+15 4.81E+15 1.98E+15 1.82E+15 2.62E+14 2.52E+L4 2.97E+L3 2.79E+L3 4.13E+13 3,84E+13 6.84E+11 6.45E+11 6.14E+10 5.80E+10 6.62E+06 5.52E+06 7.62E+05 7.50E+05 8.17E+O4 8.63E+04 2.39E+16 2.26E+L5 Attachment 10.4.1.A FC08514 Page t7 L.4y 6.79E+15 L.47E+L5 1.68E+15 t.24E+t5 9.37E+t4 1.31E+15 8.88E+14 4.64E+L4 4.69E+15 1.70E+15 2.42E+14 2.53E+13 3.58E+13 5.09E+11 5.48E+10 5.42E+05 7.39E+05 8.50E+04 2.15E+15 1.5 y 5.42E+15 1.39E+15 1.59E+15 1.17E+15 8.84E+14 1.23E+15 8.37E+L4 4.38E+14 4.57E+15 1.598+15 2.33E+t4 2.478+L3 3.33E+13 5.758+11 5.17E+10 5.338+05 7.29E+05 8.39E+04 2.048+16 Eight Assemblies 5.14E+16 1.11E+16 L.27E+16 9.37E+15 7-O7E+75 9.82E+15 6.70E+15 3.50E+15 3.66E+16 1.28E+15 1.86E+15 1.98E+14 2.66E+14 4.60E+L2 4.L4E+!L 5.07E+07 5.83E+05 6.71E+05 L.63E+17Revision 0 Gamma FF3 Sub Batch Gammaphotons/sec/basis ORlGEN2Group ORIGEN grp maxgamma MeV 190 15 0.07 L4 0.1 0.15 0.3 0.45 0.7 1 1.5 72 5 2.5 53 44 36 28 111 1 0.00E+00 2 2.00E-02 3 3.00E-02 4 4.50E-02 5 7.00E-02 5 1.00E-01 7 1.50E-01 8 3.00E-01 9 4.50E-01 10 7.00E-01 LL 1.00E+00 L2 1.50E+00 13 2.00E+00 L4 2.50E+00 15 3.00E+00 16 4.00E+00 L7 6.00E+00 18 8.00E+00 totals FC08514 Page 18 1.1y 8.79E+15 1.90E+15 2.15E+15 1.61E+15 L.22E+L5 t.7LE+15 1.16E+15 6.03E+14 5.62E+15 2.59E+15 3.07E+14 3.51E+13 4.74E+L3 8.29E+11 7.45E+L0 9.55E+05 1.10E+05 1.27E+05 2.77E+L6 Attachment 10.4.1.A boundaries0 Output Group o.1v 18 t7 t6 0.02 0.03 0.045 20000 30000 4s000 70000 100000 150000 300000 450000 700000 1000000 1500000 2000000 2s00000 3000000 4000000 6000000 8000000 11000000 2.00E-02 3.00E-02 4.50E-02 7.OOE-02 1.00E-01 1.50E-01 3.00E-01 4.50E-01 7.00E-01 1.00E+00 1.50E+00 2.00E+00 2.50E+00 3.00E+00 4.00E+00 5.00E+00 8.00E+00 1.10E+01 2.88E+16 5.50E+15 8.04E+15 4.89E+15 3.88E+15 9.28E+15 3.54E+15 3.00E+15 1.91E+16 2.99E+L6 9.24E+L4 2.80E+15 2.25E+L4 L.04E+L4 9.33E+11 1.39E+07 1.60E+06 1.83E+05 L.2LE+L7 13 t2 11 10 9 8 Revision 0 Gamma FF3 Sub Batch t.ZV L.2y 8.27E+L5 7.80E+15 1.79E+15 1.69E+15 2.02E+L5 1.91E+15 1.51E+15 1.43E+15 1.14E+15 1.08E+15 1.50E+15 1.50E+15 1.09E+15 1.02E+15 5.58E+14 5.35E+14 5.45E+15 5.31E+15 2.33E+15 2.13E+15 2.95E+L4 2.83E+L4 3.30E+13 3.10E+13 4.4LE+L3 4.11E+13 7.82E+tL 7.39E+LL 7.05E+10 6.55E+10 9.40E+05 9.26E+06 1.08E+05 1.07E+06 1.25E+05 1.23E+05 2.62E+L6 2.48E+L6 Attachment 10.4.L.A t.4y 1.5 y 6.95E+15 6.58E+15 1.51E+15 1.43E+15 L.7TE+L5 1.61E+15 L.27E+L5 1.20E+15 9.58E+14 9.04E+14 1.32E+15 1.24E+15 9.10E+14 8.59E+14 4.77E+L4 4.51E+14 5.04E+15 4.91E+15 1.84E+15 1.74E+15 2.62E+L4 2.52E+L4 2.75E+L3 2.59E+13 3.56E+13 3.31E+13 6.58E+11 6.22E+lL 5.94E+10 5.62E+10 9.01E+06 8.90E+05 1.04E+06 1.03E+06 1.19E+05 1.18E+05 2.23E+16 2.LZE+LG FC08514Page 19 1.3 v 7.38E+15 1.60E+15 1.81E+15 1.35E+15 1.02E+15 1.41E+15 9.67E+14 5.06E+14 5.18E+15 L.97E+75 2.73E+14 2.93E+13 3.83E+13 6.99E+11 5.30E+10 9.13E+05 1.05E+06 1.21E+05 2.35E+16 lSAssemblies 1.05E+17 2.28E+L6 2.58E+16 1.92E+16 1.45E+15 1.98E+15 1.37E+16 7.2LE+15 7.86E+16 2.78E+76 4.03E+15 4.15E+14 5.30E+14 9.95E+12 8.98E+11 1.42E+08 L.64E+07 1.89E+06 3.40E+17 Revision 0 Gamma FF4 Sub Batch Gamma photons/sec/basi ORIGEN2 Group ORIGEN grp max gamma MeV Attachment 10.4.1.4 boundaries mev FC08s14 Page 20 l.2y 8.19E+15 t.77E+Ls 2.00E+15 1.50E+15 1.13E+15 1.59E+15 1.08E+15 5.63E+14 5.28E+15 2.26E+15 2.87E+14 3.27E+L3 4.39E+13 7.78E+1L 7.01E+10 8.71E+06 1.00E+05 1.15E+05 2.57E+Lo o.1v 2.87E+L6 6.47E+Ls 8.01E+15 4.86E+15 3.86E+15 9.26E+15 3.52E+15 2.99E+15 1.89E+16 2.98E+16 9.02E+14 2.80E+15 2.22E+L4 L.04E+L4 9.33E+11 L.29E+07 1.49E+05 1.71E+05 L.20E+L7 1.1v 8.70E+15 1.88E+15 2.13E+15 1.59E+15 L.2LE+L5 1.59E+15 1.15E+15 5.98E+14 5.44E+75 2.52E+15 2.99E+14 3.48E+13 4.72E+t3 8.24E+tL 7.42E+10 8.86E+06 1.02E+05 1.17E+05 2.73E+16 19 18 t7 16 15 L4 13 L2 11 10 9 8 7 6 5 4 3 2 1 0 Output Group 0.02 20000 0.03 30000 0.045 45000 0.07 70000 0.1 100000 0.15 150000 0.3 300000 0.45 450000 0.7 700000 1 1000000 1.s 1s00000 2 2000000 2.5 2500000 3 3000000 4 4000000 6 5000000 8 8000000 LL 11000000 1 0.00E+00 2.00E-02 2 2.00E-02 3.00E-02 3 3.00E-02 4.50E-02 4 4.50E-02 7.OOE-OZ 5 7.00E-02 1.00E-01 6 1.00E-01 1.50E-01 7 1.50E-01 3.00E-01 8 3.00E-01 4.50E-01 9 4.50E-01 7.00E-01 10 7.00E-01 1.00E+00 lL 1.00E+00 1.50E+00 L2 1.508+00 2.00E+00 13 2.00E+00 2.50E+00 L4 2.50E+00 3.00E+00 15 3.00E+00 4.00E+00 16 4.00E+00 6.008+00 L7 5.00E+00 8.00E+00 18 8.00E+00 1.10E+01 totals Revision 0 Gamma FF4 Sub Batch L.2y 1.3 y 7.728+15 7.30E+15 1.67E+15 1.58E+15 1.89E+15 1.79E+15 1.41E+15 1.33E+15 1.07E+15 1.01E+15 1.49E+15 1.40E+15 1.02E+15 9.59E+14 5.31E+14 5.02E+14 5.14E+15 5.01E+15 2.05E+15 1.90E+15 2.75E+L4 2.55E+L4 3.08E+13 2.90E+13 4.09E+13 3.82E+13 7.35E+11 6.95E+11 6.62E+10 6.27E+LO 8.57E+06 8.45E+06 9.87E+05 9.74E+O5 1.14E+05 1.12E+05 2.43E+LG 2.3LE+L6 Attachment 10.4.1.A FC08514 Page 21 r.4v 5.88E+15 1.49E+15 1.58E+15 1.26E+15 9.48E+L4 1.31E+15 9.01E+14 4.73E+L4 4.87E+Ls L.778+L5 2.54E+t4 2.73E+13 3.54E+13 6.55E+11 5.91E+10 8.34E+06 9.60E+05 1.10E+05 2.19E+15 1.5 v 5.50E+15 1.41E+15 1.59E+15 1.19E+15 8.95E+14 1.23E+15 8.50E+14 4.46E+14 4.75E+15 1.67E+15 2.44E+t4 2.57E+L3 3.30E+13 6.18E+11 5.58E+10 8.24E+05 9.49E+05 1.09E+05 2.08E+15 Eight Assemblies 5.20E+16 1.13E+16 L.27E+L6 9.50E+15 7.15E+15 9.83E+15 6.80E+15 3.57E+15 3.80E+16 1.34E+15 1.95E+15 2.05E+14 2.64E+t4 4.95E+12 4.47E+LL 6.59E+07 7.59E+06 8.73E+05 1.67E+L7 Gamma GG1Sub Batch Gamma photons/sec/basi ORIGEN2 Group OR]GEN grp max gamma MeV Attachment 10.4.1.A boundaries mev FC08514 Page22 1.0 v 6.43E+15 1.38E+15 1.64E+15 t.t7E+Ls 9.03E+14 1.39E+15 8.44E+L4 4.32E+L4 2.23E+L5 1.66E+15 1.30E+14 2.26E+L3 4.23E+L3 4.22E+Ll 3.64E+10 3.62E+05 4.76E+04 4.78E+03 1.83E+16 3E-O2y 4.76E+15 1.09E+16 1.56E+16 7.33E+15 8.90E+15 2.01E+15 9.57E+15 9.70E+15 2.68E+16 4.30E+16 1.20E+15 1.15E+16 3.L7E+t4 4.37E+14 3.42E+12 8.56E+05 9.83E+04 1.13E+04 2.L3E+L7 o.1y 2.50E+15 5.61E+15 7.22E+t5 4.!4E+L5 3.30E+15 8.87E+15 2.94E+15 2.58E+15 L.29E+16 3.10E+16 4.07E+14 2.89E+15 L.47E+74 1.09E+14 9.03E+11 7.91E+05 9.09E+04 1.04E+04 L.07E+L7 1900 Output Group 18 L7 15 15 t4 13 L2 11 10 9 8 7 5 5 4 4 4000000 3 5 6000000 2 8 80000001 11 11000000 1 0.00E+00 2.00E-02 2 2.OOE-O2 3.00E-02 3 3.00E-02 4.50E-02 4 4.50E-02 7.O0E-02 5 7.00E-02 1.00E-01 6 1.00E-01 1.50E-01 7 1.50E-01 3.00E-01 8 3.00E-01 4.50E-01 9 4.50E-01 7.00E-01 10 7.00E-01 1.00E+00 11 1.00E+00 1.50E+00 t2 1.50E+00 2.00E+00 13 2.00E+00 2.50E+00 L4 2.50E+00 3.00E+00 15 3.00E+00 4.00E+00 16 4.00E+00 5.00E+00 L7 6.00E+00 8.00E+00 18 8.00E+00 1.10E+01 totals o.02 20000 0.03 30000 0.045 4s000 0.07 70000 0.1 100000 0.15 150000 0.3 300000 0.45 4s0000 o.7 700000 1 1000000 1.5 1500000 2 2000000 2.5 2500000 3 3000000 Revision 0 Gamma GGl Sub Batch 1.1y t.Zy Attachment 10.4.1.A t.4y 1.5 y FC08514 Page 23 Eight Assemblies 3.48E+15 7.48E+15 8.87E+15 6.36E+15 4.87E+15 7.31E+15 4.56E+15 2.36E+15 L.49E+LG 4.83E+15 7.69E+14 7.22E+L4 2.L9E+L4 2.38E+12 2.07E+LL 2.27E+06 2.61E+05 2.99E+04 9.75E+L6 6.00E+15 1.29E+15 1.53E+15 1.10E+15 8.43E+L4 1.29E+15 7.88E+14 4.04E+L4 2.15E+15 1.33E+15 t.24E+L4 2.11E+13 3.93E+13 3.98E+11 3.44E+10 3.44E+05 3.96E+04 4.55E+03 1.59E+16 5.51E+15 1.20E+15 1.43E+15 1.03E+15 7.88E+14 1.20E+15 7.37E+L4 3.79E+14 2.09E+15 1.09E+15 L.L1E+L4 1.98E+13 3.66E+13 3.75E+11 3.25E+10 3.29E+05 3.78E+04 4.35E+03 1.57E+15 t.2v 5.25E+15 1.13E+15 1.34E+15 9.61E+14 7.38E+L4 L.t2E+L5 5.90E+14 3.55E+14 2.03E+15 9.t4E+L4 L.L2E+L4 1.85E+13 3.40E+13 3.54E+11 3.07E+10 3.15E+05 3.63E+04 4.17E+03 L.47E+L6 4.93E+15 1.06E+15 1.26E+15 9.01E+14 6.92E+14 1.05E+15 6.47E+L4 3.34E+L4 1.97E+I5 7.8LE+L4 1.06E+14 L.74E+L3 3.16E+13 3.34E+11 2.90E+10 3.03E+05 3.49E+O4 4.01E+03 1.38E+16 4.63E+15 9.94E+L4 1.18E+15 8.46E+14 6.49E+14 9.77E+L4 5.O7E+t4 3.13E+14 t.92E+L5 6.80E+14 1.01E+14 1.63E+13 2.94E+L3 3.15E+11 2.74E+L0 2.93E+05 3.37E+04 3.87E+03 1.29E+tG 4.35E+15 9.368+14 1.11E+15 7.95E+14 5.09E+14 9.148+14 5.70E+14 2.95E+14 1.87E+15 5.ME+14 9.61E+13 1.53E+13 2.73E+L3 2.98E+11 2.598+10 2.83E+05 3.268+(N 3.74E+03 L.22E+16 1.3 v Revision 0 Gamma GG2 Sub Batch Gamma photons/sec/basis ORIGEN2 Group ORIGEN grp max gamma MeV 190 18 0.02 L7 0.03 16 0.0450 OutputGroup Attachment 10.4.1.A boundaries mev FC08514 Page 24 L.2y 5.58E+15 1.20E+15 L.42E+L5 1.02E+15 7.84E+L4 1.19E+15 7.34E+L4 3.77E+L4 2.08E+15 1.10E+15 I.t7E+t4 1.97E+13 3.63E+13 3.77E+LL 3.25E+10 3.19E+05 3.56E+04 4.21E+03 1.57E+16 o.1v 2.49E+16 5.58E+15 7.19E+15 4.12E+Ls 3.28E+15 8.84E+15 2.92E+L5 2.67E+Ls 1.29E+15 3.09E+16 4.05E+14 2.88E+15 L.46E+L4 1.09E+14 8.99E+11 7.87E+O5 9.04E+04 1.04E+04 l.o7E+L7 1.1v 5.97E+15 1.28E+15 1.52E+15 1.09E+15 8.39E+14 1.28E+15 7.85E+L4 4.03E+14 2.t4E+t5 1.35E+15 L.23E+L4 2.7LE+L3 3.91E+13 3.99E+11 3.45E+10 3.34E+05 3.84E+04 4.41E+03 1.68E+16 0.07 0.1 0.15 0.3 0.45 0.7 91 8 1.5 72 5 2.s 53 44 36 28 LLL 20000 30000 45000 2500000 3000000 4000000 0.00E+00 2.00E-02 3.00E-02 4.50E-02 7.OOE-OZ 1.00E-01 1.50E-01 3.00E-01 4.50E-01 7.00E-01 1.00E+00 1.50E+00 2.00E+00 2.50E+00 3.00E+00 4.00E+00 5.00E+00 8.00E+00 totals 2.O0E-02 3.00E-02 4.50E-02 7.O0E-02 1.00E-01 1.50E-01 3.00E-01 4.50E-01 7.00E-01 1.00E+00 1.50E+00 2.00E+00 2.50E+00 3.00E+00 4.00E+00 6.00E+00 8.00E+00 1.10E+01 1 2 3 15 L4 13 t2 IL 10 70000 4 100000 s 150000 6 300000 7 450000 8 700000 9 1000000 10 1500000 11 2000000 L2 13 L4 15 6000000 16 8000000 L7 11000000 18 Revision 0 Gamma GG2 Sub Batch t.Zy 1.3 y 5.23E+15 4.92E+L5 1.12E+15 1.06E+15 1.33E+15 1.25E+15 9.55E+14 8.99E+14 7.34E+L4 5.90E+14 1.11E+15 1.04E+15 6.87E+t4 6.46E+L4 3.54E+14 3.33E+14 2.O2E+L5 1.95E+15 9.15E+14 7.85E+L4 1.11E+14 1.06E+14 1.85E+13 L.74E+L3 3.38E+13 3.15E+13 3.55E+11 3.35E+11 3.08E+10 2.92E+LO 3.05E+05 2.93E+05 3.50E+04 3.37E+04 4.03E+03 3.87E+03 1.46E+16 1.37E+16 Attachment 10.4.1.A FC08514 Page 25 L.4y 4.61E+15 9.89E+14 1.17E+15 8.42E+L4 6.46E+L4 9.72E+L4 5.04E+14 3.L2E+L4 1.91E+15 6.79E+L4 1.01E+14 1.52E+13 2.92E+L3 3.15E+11 2.75E+L0 2.82E+05 3.24E+04 3.72E+O3 1.29E+16 1.5 v 4.33E+15 9.318+14 1.10E+15 7,9LE+14 6.05E+14 9.08E+14 5.67E+14 2.93E+!4 1.85E+15 5.03E+14 9.57E+13 1.52E+13 2.728+L3 2.98E+U 2.50E+10 2.72E+05 3.13E+04 3.50E+03 1.21E+16 Eight Assemblies 3.46E+16 7.45E+L5 8.82E+15 6.33E+15 4.85E+15 7.27E+L5 4.54E+15 2.35E+15 1.48E+16 4.82E+15 7.65E+L4 L.22E+L4 2.L7E+L4 2.39E+L2 2.08E+1L 2.18E+06 2.50E+05 2.88E+04 9.70E+16 Revision 0 Gamma Sub Batch GG3 Gamma photons/sec/basi ORIGEN2 Group ORIGEN grp max gamma MeV 0 0.02 0.03 Attachment 10.4.1.A boundaries mev 19 18 L7 0 Output Group o.1v 2.57E+16 5.79E+15 7.35E+15 4.29E+L5 3.41E+15 8.89E+15 3.05E+15 2.74E+Ls L.43E+LG 3.00E+15 5.04E+14 2.82E+!5 L.62E+74 1.06E+14 9.00E+11 1.94E+06 2.23E+05 2.57E+04 1.09E+17 1.1v 5.58E+15 L.44E+t5 1.68E+15 L.22E+L5 9.35E+14 1.39E+15 8.82E+L4 4.56E+L4 2.79E+L5 1.53E+15 1.59E+14 2.47E+L3 4.15E+13 5.20E+11 4.58E+10 9.48E+05 1.09E+05 1.25E+04 1.92E+16 FC08514 Page 26 L.2v 6.25E+15 1.35E+15 1.57E+15 1.15E+15 8.77E+L4 1.30E+15 8.26E+L4 4.27E+14 2.70E+15 1.28E+15 1.52E+t4 2.32E+L3 3.85E+13 4.91E+11 4.32E+L0 9.13E+05 1.05E+05 L.2LE+04 L.79E+L6 13 t2 11 10 16 0.045 15 0.07 L4 0.1 0.15 0.3 0.45 o.7 91 8 1.5 72 6 2.5 53 44 36 28 111 20000 30000 45000 70000 100000 150000 300000 450000 700000 1000000 1s00000 2000000 2s00000 3000000 4000000 6000000 8000000 11000000 1 0.00E+00 2 2.OOE-O2 3 3.00E-02 4 4.50E-02 5 7.00E-02 6 1.00E-01 7 1.50E-01 8 3.00E-01 9 4.50E-01 10 7.00E-01 tL 1.00E+00 12 1.50E+00 L3 2.00E+00 14 2.50E+00 15 3.00E+00 15 4.00E+00 L7 6.00E+00 18 8.00E+00 totals 2.00E-02 3.00E-02 4.50E-02 7.00E-02 1.00E-01 1.50E-01 3.00E-01 4.50E-01 7.00E-01 1.00E+00 1.50E+00 2.00E+00 2.50E+00 3.00E+00 4.00E+00 5.00E+00 8.00E+00 1.10E+01 Revision 0 Gamma Sub Batch GG3 t.Zy 1.3 y 5.87E+15 5.53E+15 1.26E+15 1.19E+15 1.47E+L5 1.39E+15 1.08E+15 1.01E+15 8.22E+L4 7.73E+L4 1.21E+15 1.14E+15 7.75E+L4 7.29E+L4 4.0LE+L4 3.78E+L4 2.62E+L5 2.55E+15 1.10E+15 9.7LE+L4 1.45E+14 1.38E+14 2.18E+13 2.05E+13 3.59E+13 3.35E+13 4.63E+11 4.38E+11 4.09E+10 3.87E+10 8.83E+05 8.57E+05 1.02E+05 9.85E+04 L.L7E+O4 1.13E+04 1.68E+16 1.59E+15 Attachment 10.4.1.A FC08514 Page27 t.4y 5.18E+15 1.12E+15 1.30E+15 9.50E+14 7.24E+L4 1.06E+15 5.83E+14 3.55E+14 2.48E+15 8.62E+t4 1.32E+L4 1.92E+13 3.11E+13 4.13E+11 3.65E+10 8.31E+05 9.56E+04 1.10E+04 1.49E+15 1.5 y 4.88E+l5 1.05E+15 l.z2E+L5 8.93E+14 6.81E+14 9.928+L4 5.42E+L4 3.34E+14 2.41E+15 7.83E+14 L.26E+14 1.80E+13 2.89E+13 3.89E+11 3.45E+10 8.10E+05 9.32E+04 1.07E+04 1.41E+15 24 Assemblies L.L7E+t7 2.53E+16 2.94E+16 2.L48+15 1.53E+15 2.38E+16 1.54E+16 8.02E+15 5.78E+15 1.88E+16 3.01E+15 4.3?E+t4 6.94E+14 9.35E+12 8.27E+tL 1.94E+O7 2.24E+O6 2.57E+05 3.37E+77 Revision 0 Gamma Total Core Offload Attachment 10.4.1.A FC08s14Page 28 Assembly Sub Batch Core OffloadDD1 DDz DD3 EE1 Enerry Output Group 1 2 3 4 5 6 7 8 9 10 LL L2 13 L4 15 16 L7 18 Total 9.27E+L6 2.01E+16 2.23E+L6 1.68E+16 L.26E+L6 1.65E+16 1.20E+16 6.35E+15 8.76E+16 3.29E+16 4.47E+Ls 3.87E+14 4.10E+14 9.87E+12 9.OZE+!L 3.93E+08 4.52E+O7 5.20E+06 3.25E+L7 3.73E+16 8.11E+15 8.99E+15 6.78E+15 5.08E+15 6.67E+15 4.85E+15 2.56E+15 3.45E+15 1.29E+L6 t.77E+t5 1.56E+14 1.57E+14 3.97E+!2 3.63E+11 1.46E+08 1.58E+07 1.94E+05 1.30E+17 2.63E+L6 5.72E+15 6.45E+15 4.81E+15 3.63E+15 4.98E+15 3.45E+15 1.81E+15 L.92E+L6 6.74E+L5 9.89E+14 1.04E+14 L.34E+t4 2.52E+12 2_27E+tL 3.36E+07 3.87E+06 4.45E+05 8.44E+15 L.L9E+L7 2.58E+16 2.88E+15 2.16E+L6 L.62E+L5 2.15E+16 1.54E+15 8.14E+15 t.05E+L7 3.93E+16 5.43E+15 4.89E+14 5.43E+14 1.23E+13 t.L2E+L2 3.80E+08 4.37E+O7 5.03E+06 4.08E+L7 EE2 8.21E+16 1.78E+16 2.00E+16 1.50E+16 1.13E+16 1.53E+16 L.O7E+L6 5.63E+15 6.45E+16 2.31E+16 3.31E+15 3.28E+14 4.OZE+14 8.02E+12 7.26E+7L 1.45E+08 L.67E+07 1.92E+05 2.70E+17 EE3 2.62E+L6 5.70E+15 6.42E+t5 4.79E+L5 3.61E+15 4.94E+t5 3.43E+15 1.80E+15 1.93E+16 6.78E+15 9.93E+14 1.04E+14 1.328+14 2.51E+72 2.27E+tl 3.48E+07 4.00E+06 4.60E+05 8.43E+16 FFl 5.04E+16 1.09E+16 1.25E+15 9.18E+15 5.94E+15 9.71E+15 5.55E+15 3.43E+15 3.46E+16 1.20E+15 1.76E+15 L.92E+L4 2.66E+L4 4.40E+L2 3.95E+11 4.09E+07 4.7LE+06 5.41E+05 1.58E+17 FFz 5.14E+16 1.11E+15 L.27E+16 9.37E+15 7.O7E+L5 9.82E+15 5.70E+15 3.50E+15 3.66E+15 1.28E+16 1.85E+15 1.98E+14 2.65E+L4 4.60E+L2 4.14E+11 5.07E+07 5.83E+06 6.71E+05 1.63E+17 Revision 0 Gamma Total Core Offload Attachment 10.4.1.A FC08514 Page29 FF3 1.05E+17 2.28E+16 2.58E+15 L.92E+L6 1.45E+16 1.98E+16 1.37E+15 7.2tE+L5 7.86E+16 2.78E+L6 4.03E+15 4.15E+14 5.30E+14 9.95E+12 8.988+11 L.42E+08 L.64E+O7 1.89E+06 3.40E+17 FF4 5.20E+15 1.13E+15 L.27E+15 9.50E+15 7.L5E+L5 9.83E+15 5.80E+15 3,57E+15 3.80E+16 1.34E+16 1.95E+15 2.06E+t4 2.64E+L4 4.95E+L2 4.47E+LL 5.59E+07 7.59E+05 8.73E+05 L.57E+L7 GG1 3.48E+15 7.48E+15 8.87E+15 5.35E+15 4.87E+15 7.31E+15 4.56E+15 2.36E+15 1.49E+15 4.83E+15 7.69E+14 L.22E+L4 2.L9E+L4 2.38E+L2 2.O7E+LL 2.27E+05 2.51E+05 2.99E+04 9.75E+16 GG2 3.45E+15 7.45E+t5 8.82E+15 6.33E+15 4.85E+15 7.27E+L5 4.54E+L5 2.35E+15 1.48E+16 4.82E+t5 7.65E+L4 L.22E+L4 2.L7E+L4 2.39E+L2 2.08E+11 2.18E+06 2.50E+05 2.88E+04 9.70E+15 GG3 L.L7E+L7 2.53E+16 2.94E+L6 2.L4E+L6 1.63E+15 2.38E+15 1.54E+15 8.02E+15 5.78E+15 1.88E+15 3.01E+15 4.32E+L4 5.94E+14 9.35E+12 8.27E+LL L.94E+07 2.24E+OG 2.57E+05 3.37E+t7 Tota! for Core Offload at 18 months 8.29E+17 1.80E+17 2.O4E+17 1.51E+17 l.L4E+t7 1.57E+t7 1.08E+17 5.67E+16 6.O7E+17 2.LGE+17 3.UE+16 3.258+15 4.24E+t5 7.72E+13 5.96E+12 1.46E+09 1.68E+08 1.93E+07 2.66E+18 Revision 0 Gamma DDl Sub Batch Formulas Gamma photons/sec/bas ORIGEN grp 19 18 t7 15 15 L4 13 L2 11 10 9 8 7 6 5 4 3 2 1 maxgamma MeV 0 0.02 0.03 0.045 0.07 0.1 0.15 0.3 0.45 0.7 t 1.5 2 2.5 3 4 6 8 11 Attachment 10.4.1.8 ORIGEN2 Group 0=84*1000fiX) =85*10fl)000 =B6*1000000 =B7*10fi)000 =88*10fi)000 =89*1000000 =810*1000000 =811*10fi)000 =B12*10000O0 =813*1000000 =814*10fi)fi)0 =B15*1000fi)0 =B15*1000000 =817*1000000 =818*1000fi)0 =819*1000000 =B20*1000000 =821*1000000 Output Group L 2 3 4 5 6 7 8 9 10 11 L2 13 t4 15 16 t7 18 FC08s14Page 1Revision 0 Gamma DDl Sub Batch Formulas boundaries 0 0.02 0.03 0.045 0.07 0.1 0.15 0.3 0.45 0.7 1 1.5 2 2.5 3 4 6 8 totals Attachment 10.4.1.8 1E-03 y 3E-03 y 342000000000000000 264200000000000000 52520000000000000 40070000000000000 s4830000000000000 44310000000000000 33710000000000000 25770000000000000 46320000000000000 37430000000000000 181100000000000000 147700000000000000 136000000000000000 104200000000000000 36280000000000000 29320000000000000 117700000000000000 88350000000000000 94710000000000000 75500000000000000 23140000000000000 11990000000000000 21830000000000000 18740000000000000 2175000000000000 1329000000000000 792100000000000 671500000000000 35490000000000 5384000000000 1555000000000 5050000 580700 21270000000
50s1000 5808001143000000000000000 889600000000000000 FC08514 Page2 mev 0.02 0.03 0.045 0.07 0.1 0.15 0.3 0.45 o.7 1 1.5 2 2.5 3 4 6 8 L7 Revision 0 Gamma DDl Sub Batch Formulas 2E-O2y 67730000000000000 14230000000000000 19040000000000000 10410000000000000 12500000000000000 28800000000000000 16270000000000000
12080000000000000 42270000000000000 44750000000000000 3881000000000000 12260000000000000 811400000000000 454300000000000 3678000000000 43s30000 5011000 576200 285500000000000000 7E-02v 344s0000000000000
7884000000000000 10010000000000000 5938000000000000
5029000000000000 11020000000000000 4473000000000000 4514000000000000 27240000000000000 33500000000000000 1747000000000000 4673000000000000 397400000000000 172100000000000
1s07000000000 42730000 4919000 555700 151000000000000000 Attachment 10.4.1.8 0.2 v 22820000000000000 s006000000000000
5600000000000000 3976000000000000
2970000000000000 s58s000000000000 2838000000000000 1544000000000000 15970000000000000 21230000000000000
782800000000000
329900000000000 124400000000000
10940000000000 248500000000 40640000 4679000 538100 88890000000000000 0.7 v 13910000000000000 3003000000000000 3302000000000000 2523000000000000 1902000000000000 2631000000000000 1824000000000000 948400000000000 9822000000000000 6936000000000000 s49200000000000
58770000000000 69590000000000 1451000000000
132600000000 36410000 4193000 482300 47480000000000000 1.5 v 7721000(n0(x)0000 1579000000(x)0000 1851000000000000 1402000000000000 10s0000000000000 1376000000000000 1003000000000000 529100000000000 2742000000000000
372700000000000
32280000000000 34200000000000
822900000000
75190000000 32710000 3768000 433400 27110000000000000 FC08514 Page 3 Revision 0 Gamma DDl Sub Batch Formulas Attachment 10.4.1.8 FC08514 Page 4 Twelve Assemblies =12*M4=12*M5=12*M5=t2*M7=12*M8=12rM9=12*M10=12*M11=L2*MtZ=12*M13=12tM14=12*M15=12*M15=72*ML7=12*M18=12*M19=12*M20=t2*M2L =L2*M22 Revision 0 Gamma DD2 Sub Batch Formulas Gamma photons/sec/basi ORIGEN grp 19 18 t7 L6 15 L4 13 L2 TL 10 9 8 7 6 5 4 3 2 7 max gamma MeV 0 0.02 0.03 0.045 0.07 0.1 0.15 0.3 0.45 o.7 1 1.5 2 2-5 3 4 6 8 11 Attachment 10.4.1.8 ORIGEN2 Group ev 0=84*10000fi) =85*1000000 =85r1000000 =87*1fi)0000 =88*1fl)0000
=89*1000000 =B10*10fi)fi)0 =B11*1fi)0000 =812*1000000 =813*1000000 =814*1ffX)000 =815*1fi)0000 =815*1fi)fi)00 =817*1000000 =B18*1fi)fi)00
=819*100fi)fi)
=820*1fi)fl)00 =821*1000000 Output Group 1 2 3 4 5 6 7 8 9 10 LL L2 13 t4 15 15 L7 18 FC08514 Page 5Revision 0 Gamma DD2 Sub Batch Formulas boundaries 0 0.02 0.03 0.045 0.07 0.1 0.15 0.3 0.45 o.7 1 1.5 2 2.5 3 4 6 8 totals Attachment 10.4.1.8 1E-03 y FC08514Page 6 mev 0.02 0.03 0.045 o.o7 0.1 0.15 0.3 0.45 0.7 L 1.5 2 2.5 3 4 6 8 11 3E-03 y 332200000000000000 2s5700000000000000 51050000000000000 38970000000000000 s3310000000000000 43080000000000000 32560000000000000 24940000000000000 4s000000000000000 36370000000000000 175300000000000000 143700000000000000 132400000000000000 101400000000000000 3s310000000000000 28530000000000000 114400000000000000 85770000000000000 91880000000000000 73290000000000000 22350000000000000 11490000000000000 21250000000000000 18250000000000000 2092000000000000 1256000000000000 772200000000000 554500000000000 34570000000000 5247000000000 1s37000000000 4s72000 20890000000 4573000 525800 5258001111000000000000000 864s00000000000000 Revision 0 Gamma DDz Sub Batch Formulas s84500000000000 4555000000000 39640000 3252000000000 39310000 Attachment 10.4.1.B 0.1y 0.5 y 950200000000 38260000 143600000000 33900000 3904000 794200000000 72540000000 29230000 3366000 FC08514 PageT 1E-02 y 3E-02 y 1.5 v 143000000000000000 55630000000000000 29800000000000000 15680000000000000 7460000000000000 24250000000000000 12200000000000000 5749000000000000 3386000000000000 1622000000@@00 28980000000000000 15500000000000000 8193000000000000 3713000000000000 1798000000000000 16120000000000000 9044000000000000 s089000000000000 2824000000000000 1355000@0@0000 23230000000000000 10250000000000000 4043000000000000 2125000000000000 1015000000000000 76780000000000000 21930000000000000 9195000000000000 3079000000000000 1333000000@q)00 49030000000000000 11660000000000000 3714000000000000 2037000000000000 970100000000000 19410000000000000 10230000000000000 3096000000000000 1055000000000000 511900000000000 s5570000000000000 37870000000000000 22890000000000000 10370000000000000 5925000000000000 55040000000000000 41300000000000000 29640000000000000 9763000000000000 2583000000000000 5319000000000000 3212000000000000 1299000000000000 571900000000000 353500000000000 15820000000000000 10770000000000000 2759000000000000 65530000000000 31140000000000 1023000000000000 704200000000000 279900000000000 78420000000000 33300000000000 399s00000000000 101000000000000 1616000000000 4552000 4s2s000 4405000 524600 520400 505500 449000 387200 515200000000000000 241800000000000000 126900000000000000 54750000000000000 25990000000000000 Revision 0 Gamma DD2 Sub Batch Formulas Five Assemblies =5*M4=5*M5 =5*M5=5*M7=5*M8=5*M9=5*M10=5*M11=5*M12=5*M13=5*M14=5*M15=5*M15=5*M17=5*M18=5*M19=5*M20=5*M21=5*M22 Attachment 1-0.4.1.B FC08514 Page 8 Revision 0 Gamma DD3 Sub Batch Formulas Gamma photons/sec/bas ORIGEN grp 19 18 L7 16 15 L4 13 L2 11 10 9 8 7 5 5 4 3 2 1 maxgamma MeV 0 0.02 0.03 0.045 0.o7 0.1 0.15 0.3 0.45 o.7 1 1.5 2 2.5 3 4 6 8 11 Attachment 10.4.1.B ORIGEN2 Group 0=84*100fiX)0 =85*1000000 =86*1000000 =87*1000000 =88*1000fi)0 =89*100fi[0 =B10*100fi)fi) =B11*1000000 =B12*1000000 =813*1000000 =B14*100fi)fi) =B15*10fl)fi)0 =B15*1000000 =B17*1000000 =B18*1000000 =819*1000000
=820*1fi)0fi)0 =821*1fi)0fi)0 Output Group 1 2 3 4 5 5 7 8 9 10 11 L2 13 t4 15 16 L7 18 FC08514 Page 9Revision 0 Gamma DD3 Sub Batch Formulas boundaries 0 0.02 0.03 0.045 0.07 0.1 0.15 0.3 0.45 o.7 1 1.5 2 2.5 3 4 6 8 totals Attachment 10.4.1.B 1E-03 y FC08514 Page 10 mev 0.02 0.03 0.045 0.o7 0.1 0.15 0.3 0.45 0.7 1 1,5 2 2.5 3 4 6 8 11 3E-03 y 312600000000000000 241000000000000000 49850000000000000 38000000000000000 53170000000000000 42810000000000000 31590000000000000 23830000000000000 42960000000000000 34760000000000000 165400000000000000 135800000000000000 127300000000000000 96750000000000000 34500000000000000 27970000000000000 112600000000000000 82930000000000000 91520000000000000 73550000000000000 21280000000000000 9939000000000000 21880000000000000 18790000000000000 1914000000000000 995700000000000 807700000000000 681100000000000 37360000000000 5428000000000 1851000000000 1608000 25180000000 1608000 184800 1848001059000000000000000 827900000000000000Revision 0 Gamma DD3 Sub Batch Formulas 1E-02 y 135400000000000000 23780000000000000 288s0000000000000 15330000000000000 22340000000000000 73250000000000000 46490000000000000 19220000000000000 s3010000000000000 55720000000000000 s004000000000000 15350000000000000 780800000000000 511400000000000 4822000000000 13930000 1502000 184100 496100000000000000 3E-02 y 54100000000000000 12030000000000000 16600000000000000 8684000000000000
9960000000000000 21760000000000000 11160000000000000 10240000000000000 34010000000000000 42100000000000000 2338000000000000 11160000000000000 s30600000000000 418900000000000 3362000000000 13750000 1581000 181800 23s100000000000000 Attachment 10.4.1.8 0.1y 0.3 y 29040000000000000 18500000000000000 5558000000000000 4029000000000000 8113000000000000 4545000000000000 492s000000000000 3278000000000000 3908000000000000 24s7000000000000 9385000000000000 4399000000000000 3558000000000000 2333000000000000 303s000000000000 120s000000000000 19150000000000000 9875000000000000 30200000000000000 16330000000000000 917500000000000 487300000000000 2840000000000000 117600000000000 226300000000000 97640000000000 105500000000000 3399000000000 947800000000 13150000 1514000 L74L00 143800000000 11790000 1357000 156100 122000000000000000 57760000000000000 FC08514Page 11 1.0 v 9378000000000000 2025000000000000
2290000000000000 1714000000000000
1300000000000000 1833000000000000 1238000000000000 644300000000000
5670000000000000 2862000000000000 315700000000000 37520000000000
51340000000000 888000000000 79860000000 9204000 1060000 121900 29360000000000000 Revision 0 Gamma DD3 Sub Batch Formulas 1.5 v 5s87m0000000000 1430fl)0(x10000000 16!l(x)0000000000 90570000000(x,00 12450000000m000 85200000000m00 45250flD000m00 2472000fitfixno0
260700m0fixD0 33/roflxxto(xxrco 6288(xXXnfi)o s68fiXXtO000 8403fi'o 967600 111300 211fiXto0000000000 Attachment 10.4.1.B FourAssemblies =4*N4=4*N5 =4*N5=4*N7=4*N8=4*N9=4*N10=4*N11=4*N12=4*N13=4*N14=4*N15 =4*N16=4*N17=4*N18=4*N19=4*N20=4*N21=4*N22 FC08514Page 12 Revision 0 Gamma EEl Sub Batch Formulas Gam ma photons/sec/basir ORIGEN grp 19 18 t7 15 15 L4 13 L2 LL 10 9 I 7 6 5 4 3 2 1 max gamma MeV 0 o.o2 0.03 0.045 0.o7 0.1 0.15 0.3 0.45 0.7 1 1.5 2 2.5 3 4 6 8 11 Attachment 10.4.1.B ORIGEN2 Group 0=84*1000000 =B5*1000000 =86*10fi)000 =B7*1000000 =88*1000000 =89*1000000 =B10*1000000 =811*1000000 =B12*1000000 =813*100fi)00 =B14*1000000
=815*100fi)00 =B15*10000fi) =817*1000000
=818*1000000
=819*1000000 =820*1000000 =821*1000000 Output Group 1 2 3 4 5 6 7 8 9 10 11 L2 13 L4 15 15 L7 18 FC08514Page 13Revision 0 Gamma EEl Sub Batch Formulas boundaries 0 0.02 0.03 0.045 0.07 0.1 0.15 0.3 0.45 o.7 1 1.5 2 2.5 3 4 6 8 totals Attachment 10.4.1.B 1E-03 y 331000000000000000
51430000000000000 s4140000000000000 33030000000000000 45120000000000000 175400000000000000 132s00000000000000 35580000000000000 115700000000000000 93260000000000000 22500000000000000
21590000000000000
2085000000000000
791200000000000 35820000000000 1538000000000 3844000 442000 1114000000000000000 3E-03 y 255700000000000000
39250000000000000 43720000000000000 25160000000000000
35490000000000000 143100000000000000 101300000000000000 28750000000000000 85440000000000000 74s70000000000000 11350000000000000 18630000000000000 1223000000000000 659800000000000 5362000000000
22270000000
3844000 442000 866300000000000000 FC08514 Page 14 mev 0.02 0.03 0.045 0.07 0.1 0.15 0.3 0.45 0.7 1 1.5 2 2.5 3 4 6 8 11 Revision 0 Gamma EEl Sub Batch Formulas 1E-02 y 142900000000000000 24480000000000000 29440000000000000 16280000000000000 23380000000000000 76700000000000000 48920000000000000 19530000000000000 55750000000000000 55140000000000000 5154000000000000 16170000000000000 983200000000000 599000000000000 4760000000000 33320000 3834000 440900 s18600000000000000 3E-02 y 55230000000000000 12360000000000000 15890000000000000 91s9000000000000 10370000000000000 22220000000000000 11730000000000000 10390000000000000 376s0000000000000 42210000000000000 3083000000000000 11020000000000000 575700000000000 409800000000000 3324000000000 33020000 3800000 437000 244400000000000000 Attachment 10.4.1.B o.1v 30180000000000000 6826000000000000 8325000000000000 5148000000000000 4088000000000000 9399000000000000
3751000000000000 3135000000000000 22490000000000000 30310000000000000 1242000000000000 2818000000000000
272300000000000 103500000000000 963200000000
32040000 3688000 424L00 128100000000000000 0.3 v 19830000000000000 4307000000000000 4779000000000000 3499000000000000 2517000000000000 4504000000000000 2501000000000000 1301000000000000 12570000000000000 16850000000000000 637700000000000 127400000000000 100200000000000 3566000000000 173000000000 29730000 3423000 393600 73730000000000000 FC08514Page 15 Revision 0 Gamma EEl Sub Batch Formulas 1.0 v 10400000000000000 2251000000000000 2503000000000000 1897000000000000 1431000000000000 1947000000000000
1368000000000000 715400000000000 7799000000000000 3735000000000000 425800000000000 43530000000000 52030000000000 1082000000000 98220000000 25240000 2906000 334300 34s70000000000000 Attachment 10.4.1.B FC08514 Page 16 1.5 y 1514000000000000 1797000000000000 13s0000000000000
1012000000000000 96s300000000000 508500000000000 5544000000000000 339100000000000 30540000000000
33960000000000
756700000000
69870000000 23730000 2734000 31rt400 15 Assemblies =16*N4=15*N5 =16*N5=16*N7=16*N8=16*N9=16*N10 =15*N11=16*N12 =16*N13=15*N14=16*N15 =16*N16=16*N17=16*N18 =16*N19 =15*N20=15*N21=16*N22 Revision 0 Gamma EE2 Sub Batch Formulas Gamma photons/sec/basi ORIGEN grp 19 18 L7 15 15 t4 13 t2 11 10 9 8 7 6 5 4 3 2 1 tmaxgamma MeV 0 o.02 0.03 0.045 0.07 0.1 0.15 0.3 0.45 0.7 1 1.5 2 2.5 3 4 6 8 11 Attachment 10.4.1.B ORIGEN2 Group 0=84*1ff)0000 =85*1fi)0000 =85*1G)0000 =87*1000000 =88*lfi)fi)fi) =89*1000000 =B10*1000fi)0 =B11*1000fi)0 =812+10fi)000 =813*1000000 =B14*1000000 =815*1000000 =B15*1000000 =B17*1000000 =B18*1000000 =819*1000000 =B20*1000000
=821*1000000 Output Group 1 2 3 4 5 6 7 8 9 10 11 L2 13 L4 15 16 t7 18 FC08514Page L7Revision 0 Gamma EE2 Sub Batch Formulas boundaries 0 0.o2 0.03 0.045 0.07 0.1 0.15 0.3 0.45 o.7 1 1.5 2 2.5 3 4 6 8 totals Attachment 10.4.1.8 0.2 y 20440000000000000 44s2000000000000 s037000000000000
3574000000000000 2573000000000000 5083000000000000
2s40000000000000 1343000000000000 11920000000000000 18980000000000000 569200000000000 211100000000000 107800000000000 6789000000000 181900000000 16650000 1916000 220300 75940000000000000 1.0 v 9582000000000000
2092000000000000 2353000000000000 1768000000000000
1338000000000000 1865000000000000 1275000000000000 554900000000000
5338000000000000
3124000000000000 349500000000000
39240000000000
51410000000000 943100000000
85090000000 13090000 1507000 173300 30940000000000000 FC08514 Page 18 mev 0.02 0.03 0.045 0.07 0.1 0.15 0.3 0.45 0.7 1 1.5 2 2.5 3 4 6 8 11 Revision 0 Gamma EE2 Sub Batch Formulas 1.3 v 7649000000000000 1659000000000000 1865000000000000 1396000000000000
1053000000000000 1442000000000000 1003000000000000 525500000000000 5670000000000000
2153000000000000
297800000000000 30820000000000
38630000000000 749500000000
57810000000 12350000 1423000 163600 24790000000000000 Attachment 10.4.1.B FC08514Page 19 1.5 v 58410(X)000000000 1486000000000000 1570000000000000 1247000000000000 938400000000000 1273000000000000 892800000000000 469200000000000 1922000000000000 275800000000000 27350000000000
33480000000000 558000000000
60520000000 12080000 1391000 150000 12 Assemblies =L2*14=12*J5=L2*JG=L2*J7=12*J8=L2*19=L2*lLO=L2*)tL=L2*Jl2=12*J13=L2*JL4=L2*JtS=L2*JL6=t2*JL7=12*JLB =12*JL9 =12*J2O=12*)2t=L2*J22 Revision 0 Gamma EE3 Sub Batch Formulas Gamma photons/sec/basis ORIGEN grp 19 18 t7 16 15 14 13 L2 11 10 9 8 7 6 5 4 3 2 1 Attachment 10.4.1.B FC08514 Page 20maxgamma MeV 0 0.02 0.03 0.045 0.07 0.1 0.15 0.3 0.45 o.7 1 1.5 2 2.5 3 4 6 8 11 ORIGEN2 Group 0=84*1000000 =85*1000000 =86*1000000 =B7*1000000 =88*100fl)00 =B9*1fi)0000 =810*1000fi)0 =811*1000000 =B12*1000fi)0 =813r1000000 =814*1000000 =B15*1000000 =B16*1000000 =B17*1000000
=B18*1000000
=819*1000000 =820*1000000 =821*1000000 Output Group 1 2 3 4 5 5 7 8 9 10 11 t2 13 74 15 16 t7 18Revision 0 Gamma EE3 Sub Batch Formulas boundaries 0 0.02 0.03 0.045 0.07 0.1 0.15 0.3 0.45 0.7 1 1.5 2 2.5 3 4 6 8 totals Attachment 10.4.1.B FC08514 Page 21 3E-03 y 238900000000000000 37620000000000000 423s0000000000000 23500000000000000 34430000000000000 134600000000000000 95840000000000000 27680000000000000 82140000000000000 72730000000000000 9859000000000000 18550000000000000 990800000000000
572700000000000 5363000000000
24790000000 1654000 190100 819900000000000000 mev 0.02 0.03 0.045 0.07 0.1 0.15 0.3 0.45 0.7 1 1.5 2 2.5 3 4 5 8 11 1E-03 y 309800000000000000 49340000000000000 52600000000000000 31380000000000000 42ss0000000000000 154900000000000000
126100000000000000 34250000000000000 111400000000000000 90510000000000000
21070000000000000
21520000000000000 1895000000000000 797500000000000
36870000000000 1822000000000 1554000 190100 1058000000000000000 Revision 0 Gamma EE3 Sub Batch Formulas 1E-02 y 134200000000000000 23s40000000000000 28540000000000000 15190000000000000 22120000000000000 72560000000000000 45060000000000000 19020000000000000 s2s70000000000000 55090000000000000 4983000000000000 16170000000000000 777500000000000 603800000000000 4764000000000 14330000 1648000 189400 491400000000000000 Attachment 10.4.1.B FC08514 Page22 3E-02 y 53590000000000000 11910000000000000 16430000000000000 8605000000000000 9853000000000000 21530000000000000 11060000000000000 10140000000000000 33780000000000000 41620000000000000 2336000000000000 11030000000000000 528700000000000 413800000000000 3322000000000 14140000 L627000 187100 232800000000000000 o.1v 28780000000000000
6500000000000000 8035000000000000 4882000000000000 3874000000000000
9283000000000000 3s38000000000000 3007000000000000 19090000000000000 29850000000000000 918900000000000 2807000000000000
225100000000000 104300000000000 937900000000 13550000 1559000 L79200 120900000000000000 0.3 v 18450000000000000 4000000000000000 4508000000000000 3254000000000000 2439000000000000 43s7000000000000 2316000000000000 1197000000000000 9883000000000000 16150000000000000 488000000000000 116700000000000 96720000000000 3373000000000 143500000000
12150000 1398000 160800 67290000000000000 Revision 0 Gamma EE3 Sub Batch Formulas 1.0 y 9329000000000000 2015000000000000 2275000000000000 1705000000000000 1293000000000000 1819000000000000 1231000000000000 640900000000000 5698000000000000
2862000000000000 316800000000000 37390000000000 50850000000000 887400000000 79840000000 9510000 1095000 125900 29270000000000000 1.5 v 14240(x)000000000 1506000000000000 11970@000000000 902300000000000 1235000000000000 8s7900000000000 450500000000000 4832000000000000 1696000000000000 25990000000000
33090000000000 628300000000 55790000000 8690000 1001000 115100 21070000000000000 Attachment 10.4.1.B FC08514 Page 23 Four Assemblies =4*N4=4*N5=4*N5=4*N7=4*N8 =4*N9=4*N10=4*N11=4*N12=4*N13=4*N14 =4*N15=4*N15=4*N17=4*N18=4*N19=4*N20=4*N21 =4*N22 Revision 0 Gamma FFl Sub Batch Formulas Gamma photons/sec/basi ORIGEN grp 19 18 t7 L6 15 L4 13 L2 11 10 9 8 7 5 5 4 3 2 1 max gamma MeV 0 0.02 0.03 0.045 0.07 0.1 0.15 0.3 0.45 0.7 1 1.5 2 2.5 3 4 6 8 11 Attachment 10.4.1.B ORIGEN2 Group 0=84*1000000 =85*1000000 =86*1000000 =87*1000000 =B8*1000000
=89*1000000 =810*1000000 =B11*1000000
=812*100fi)00 =813*1000000 =814*1000000 =815*1000000 =816*1000000 =817*1000000 =B18*1000000 =819*1000000 =820*1000000 =821*1000000 Output Group 1 2 3 4 5 5 7 8 9 10 LL L2 13 L4 15 16 t7 18 FC08514 Page24 Revision 0 Gamma FFl Sub Batch Formulas boundaries 0 o.02 0.03 0.045 0.07 0.1 0.15 0.3 0.45 o.7 L 1.5 2 2.5 3 4 6 8 totals Attachment 10.4.1.B o.1y FC08514 Page 25 mev 0.02 0.03 0.045 0.07 0.1 0,15 0.3 0.45 0.7 L 1.5 2 2.5 3 4 6 8 11 1.0 v 28690000000000000 8992000000000000 64s3000000000000 1938000000000000 8054000000000000 2221000000000000 4854000000000000 1642000000000000 3850000000000000 1248000000000000 9401000000000000 1794000000000000 3503000000000000 1182000000000000 2994000000000000 512700000000000 17900000000000000 s085000000000000 30550000000000000 2655000000000000 807000000000000 281200000000000 2842000000000000 34670000000000 207300000000000 51110000000000 105100000000000 777700000000 934200000000 8814000 1014000 116500 69400000000 57L7000 558100 75580 120200000000000000 27740000000000000 Revision 0 Gamma FFl Sub Batch Formulas 1.1y t.2y Attachment 10.4.1.8 L.2y 7482000000000000 1617000000000000 1851000000000000 1367000000000000 1035000000000000 1470000000000000 980900000000000 510900000000000 4570000000000000 1867000000000000 247700000000000 28800000000000 41180000000000 554100000000
58530000000 5363000 6L7400 71000 23170000000000000 FC08514 Page26 t.4v 6661000000000000 1442000000000000 1549000000000000 1216000000000000 919400000000000 1293000000000000 870100000000000 454300000000000 4431000000000000 1592000000000000 228300000000000 2s490000000000
35650000000000 582800000000 52240000000 5185000 s96900 58550 20820000000000000 1.3 v 7072000000000000 1529000000000000
1750000000000000 1291000000000000 978000000000000 1382000000000000 925700000000000 482800000000000
4552000000000000 1719000000000000 238100000000000
27150000000000 38430000000000 618900000000 55420000000 5272000 607000 59810 21990000000000000 8445000000000000 1821000000000000 2087000000000000 1s43000000000000 1172000000000000 1677000000000000 1109000000000000 s76200000000000 4937000000000000 2319000000000000
269300000000000 32580000000000 47s60000000000 734100000000 6ss70000000 5585000 543000 73940 26040000000000000 7941000000000000 1714000000000000 1964000000000000 14s1000000000000 1101000000000000 1s69000000000000 1042000000000000 542200000000000 4798000000000000 2063000000000000
258100000000000
30610000000000 44240000000000
592800000000 61940000000 5467000 629400 72380 24520000000000000 Revision 0 Gamma FFl Sub Batch Formulas 1.5 y 1558m000fix)0fir0 11t8m0fixxxl0(X)0 8672fiXn000(xn0 12!tm00000(xxD0 8204flXxt000m00
4289(xxno00m00
4321m0UD0fiXD0 1494(x)OflDom000 2195m0fiD0fl)00
2400fi,ofixxxxlo 3319m0flx)0flr0 5502(x)0fit000 4936m0fiXtO 5109n0 588200 57650 197g(xxnoofiXxxno Attachment 10.4.1.8 Eight Assemblies =8*N4=8*N5=8*N6=8*N7=8*N8=8*N9=8*Nt0=8*N11=8*N12=8*N13=8*N14=8*N15=8*N16=8*N17=8*N18=8*N19=8*N20=8*N21=8*N22 FCO8514 PageZTRevision 0 Gamma FF2 Sub Batch Formulas Gamma photonsAec/basi ORIGEN grp 19 18 t7 16 15 t4 13 t2 11 10 9 8 7 6 5 4 3 2 1 tmaxgamma MeV 0 0.02 0.03 0.045 0.07 0.1 0.15 0.3 0.45 o.7 1 1.5 2 2.5 3 4 5 8 11 Attachment 10.4.1.8 ORIGEN2 Group 0=84*10fi)000 =85*1000000 =85*10fi)000 =87*10ff)000 =88*1000000 =89*10fl)000 =810*100fi)00 =B11*1000000 =B12*1fi)0000 =813*1000000 =814*1000fi)0 =815*1000000 =815*1000000 =B17*1000000 =818*1000000 =B19*1000000
=B20*1000000 =821*1000000 Output Group 1 2 3 4 5 6 7 8 9 10 11 L2 13 L4 15 16 L7 18 FC08514 Page 28 Revision 0}}