View source for NG-18-0090, Calculation No. NEE-323-CALC-002, Dose Rate Evaluation of Reactor Vessel Water Levels During Refueling for EAL Thresholds

{{Adams
| number = ML18212A236
| issue date = 12/12/2017
| title = Calculation No. NEE-323-CALC-002, Dose Rate Evaluation of Reactor Vessel Water Levels During Refueling for EAL Thresholds
| author name = 
| author affiliation = NextEra Energy Duane Arnold, LLC
| addressee name = 
| addressee affiliation = NRC/NRO
| docket = 05000331
| license number = DPR-049
| contact person = 
| case reference number = NG-18-0090
| document report number = NEE-323-CALC-002
| document type = Calculation
| page count = 37
}}

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{{#Wiki_filter:CALC NO. NEE-323-CALC-0 02
* ENERCON C A LCUL A T I ON COVER SHEET REV. 00 Excelk!nc e-Eve,y p rOjt!Ct. E very day. PAGE NO. 1 of 28 D o se Rate Evaluation of Reactor Vessel Client: Duane Arno l d Energy Center Title: Wate r Le v els During Refueling for EAL Thresho l ds Project Identifier:
NEE-323 Item Cover S h eet Items Yes No 1 Does this calculatio n contain any open assumptions , including prelim i nary D information , that requ ire confirmat i on? (I f YES , identify the assumptions
.) 2 Does this ca l cu l ation s e rve as an " Alternate Calculation
"? (If YES , identify the design D ve r ified calcu l ation.) Design Ve r ified Calculation No. --3 Does th i s calculation s u persede an ex i sting Calculat i on? (If YES , i dent i fy the design D ver i fied calculation
.) Superseded Calculation No. --Sco p e of R evision: In i tial Issue Revisio n Impact on Results: Initial Issue Study Calcu l ation D Final Ca l culation Safety-Re l ated D Non-Safet y-R elated (Print Name and Sign) Originato r: Jay Bhatt Date: 12/12/17 Design V erifier 1 (Re v iewer if NSR): Caleb Tra i nor Date: 12/12/17 Appr o ver: Aa r on Holloway Date: 12/1 2/17 Note 1: For n on-safety-rela t ed c alculation , d e s i gn verifica t ion can b e subst i t u ted by review.  
.. ENERCON CALCULATION CALC NO. NEE-323-CALC-002
* Exct:llence-Every projec t. Ev~ry day. REVISION STATUS SHEET REV. 00 CALCULATION REVISION STATUS REVISION DATE DESCRIPTION 00 12/12/17 Initial Issue PAGE REVISION STATUS PAGE NO. REVISION PAGE NO. REVISION All 00 APPENDIX/ATTACHMENT REVISION STATUS APPENDIX NO. NO.OF REVISION ATTACHMENT NO.OF REVISION PAGES NO. NO. PAGES NO. A 1 00 1 5 00 B 2 00 C 1 00 Page 2 of 28 ENERCON TABLE OF CONTENTS &cellence-Every project. E11ery day. Section 1.0 Purpose and Scope 2.0 Summary of Results and Conclusions 3.0 References 4.0 Assumptions 5.0 Design Inputs 6.0 Methodology 7.0 Calculations 8.0 Computer Software 9.0 Impact Assessment List of Appendices Appendix A -Electronic Fi l e Listing Appendix B -DAEAL.x l sx Sheets Appendix C -SCALE Input List o f A tt achme nt s Attachment 1 -Calculation Preparation Checklist Page 3 of 28 CALC NO. NEE-323-CALC-002 REV. 00 Page No. 4 4 5 6 8 13 14 27 28 #of P ages 1 2 1 # of P ages 5 ENERCON Dose Rate Evaluation of CALC NO. NEE-323-CALC-002 Reactor Vessel Water Levels.__ ___________ ___. During Refueling for EAL 00 REV. Thresholds Excellence
-Every proJ<<t. E v ery d ay. 1.0 Purpose and Scope The purpose of this calculation is to evaluate dose rates with water at the top of active fuel in the reactor vessel during cold shutdown or refueling operations in order to set Emergency Action Level (EAL) thresholds (RA2 , CS1, CG1) per NEI 99-01 [Reference 3.5]. The dose rates are calculated at the locations of the drywell monitors 9184A/B so that dose rate measurements by these devices can be correlated to the water level in the core, upon failure of other water level detection systems. This calculation is nonsafety-related as the results of the calculation do not affect the design basis or safety-related systems structures or components.
These results are best estimates based on as-built conditions and provide information to operators with respect to classifying an emergency, therefore no acceptance criteria is required.
2.0 Summary of Results and Conclusions The dose rates just prior to the core being uncovered (i.e. water at the top of the active fuel) are shown in the table below. Note that the results presented below are calculated dose rates and do not account for background radiation or any installed detector check sources. Model Description Head Off Head On 1 This value is off scale low. Table 1-Dose Rate at Top of Acti v e Fuel Drywell Monitor 9184A Reading hr 1.81 1.11 Drywell Monitor 9184B Reading hr 1.68 7.41 E-Ol 1 Page 4 of 28 Drywell Monitor (9184A/B)
Range R/hr 1 to 1 E+7 I to 1 E+7 Dose Rate Evaluation of CALC NO. NEE-323-CALC-002 Reactor Vessel Water Levels ,___ ___________
__, Exct!l~ce-Every proJt!Ct.
Every day. During Refueling for EAL 00 REV. Thresholds I ENERCON 3.0 References 3.1 " Standard Composition Library ," ORNL/NUREG/CSD-2N1/R6 , Volume 3 , Section M8 , March 2000 3.2 CGDG-SCALE
-6.1.2 , Rev 00 , Commercial Grade Dedication SCALE Version 6.1.2 3.3 CGDG-MCNP6-V1 
.0 , Rev 00 , Commercial Grade Dedication MCNP6 Version 1.0 3.4 ANSI/ANS 6.1.1-1977 , Neutron and Gamma Flux-To-Dose Conversion Factors 3.5 NEI 99-01, Rev. 6 , " Development of Emergency Action Levels for Non-Passive Reactors" 3.6 I.RIM-V115-01 , Rev. 10 , " Victoreen Model 876A Containment Radiation Monitor Calibration" 3.7 NUREG 1940 , " RASCAL 4: Descriptions of Models and Methods" 3.8 CAL-ROO-PUP
-008 , Rev. 03 , " Non-LOCA Radiological Consequence Dose with Alternate Sou r ce Term" 3.9 RFP 110 , Rev. 45, " Refueling Procedure-Reactor Pressure Vessel Disassembly" 3.10 Technical Specifications , Section 1.1 3.11 Technical Specifications , Section 4.2.1 3.12 NU REG 1754 , " A New Comparative Analysis of LWR Fuel Designs" 3.13 BECH-M009 , Rev. 14 , " Equipment Locations Reactor Building Section-GG" 3.14 BECH-C405 , Rev. 14 , " Reactor Building Floor Plan@ El. 757'-6"" 3.15 NG-17-0156 , Proprietary Data Transmittal to ENERCON 3.16 BECH-M405 , Sh 04 , Rev. 24 , " Instrument Points and Rack Locations Diagram Plans at Elevs 812'-0" & 833'-6"" 3.17 NG-88-0966 , " G.E. Fuel Damage Documentation/Dose Rate Calculations" 3.18 C003-029 , Rev. 0 , " Drywell Cylindrical Shell & Cone" 3.19VS-01-06 , Rev. 4 , " Top Head Assembly" 3.20 BECH-C511 , Rev. 5 , " Reactor Building RPV Ped Dev. Elev. & Sect's" 3.21 BECH-C514 , Rev. 1 , " Drywell Interior Biological Shield Wall Reinforcing Sections" 3.22 BECH-C-516 , Rev. 6 , " Drywell Interior Biological Shield Wall Plans El. 816'-3 Y<s" to El 779'-1 W"' 3.23 BECH-M405 , Sh 02 , Rev. 71, " Instrument Points & Lines Diagrams Plan at Elev 757'-6"" 3.24APED-B 2816-001 , Rev. 5 , " Outline Reactor Recirculating Pump" Page 5 of 28 ENERCON Excellenct!
-Every pfOJ<<t. E 11 ery day. Dose Rate Evaluation of CALC NO. NEE-323-CALC-002 Reactor Vessel Water Levels ,___ ____________ __. During Refueling for EAL Thresholds REV. 00 3.25 FSAR Section 4.3.2.1 , and Section 9.1 3.26 CAL-M98-058 , Rev. 1 , " ADS Accumulator Size Verification" 4.0 Assumptions 4.1 The core is homogenized based on the typical 1Ox10 fuel assembly dimensions , taking into account the fuel rods and space between. Any small variations in fuel parameters will have a negligible effect on containment dose rates. The cladding is modeled as Zircaloy 4 in lieu of ZIRLO; th i s is acceptable due to the similarity of the materials.
4.2 Any non-fuel hardware , including rod end plugs , is ignored in the active fuel region. This is acceptable since the primary self-shielding occurs in the fuel itself , and there may be some unknown streaming effects through the non-fuel hardware.
This homogenization takes into account the presence of water when calculating the isotopic weight fraction and homogenized density. For the case with the reactor vessel head in place , the region between the head and the active fuel region is homogenized based on the actual mass of the upper internals over the entire region. Homogenization of source regions and shields is acceptable due to the insignificant effects on the detector response given the model geometry.
4.3 The composition of the containment structure and components are based on the values in the SCALE standard composition library [Reference 3.1 ]. These material properties are commonly used in shielding applications , and are acceptable for modelling the structures and components used to determine the best estimate response at the detector locations. 4.4 The minimum period of decay after reactor shutdown before moving fuel is 60 hours [Reference 3.8, Section 4.3.8]. This calculation assumes a decay time of 50 hours to allow EAL thresholds to be determined for reactor vessel conditions that exist prior to the commencement of fuel movement which is representative of the applicable operating modes (cold shutdown , refueling).
This decay time is appropriate to produce best estimate results for both the head on and head off configurations.
4.5 The hardware in the upper internals region between the active fuel region , reactor recirculating pumps and reactor vessel head is assumed to be stainless steel type 304. While the actual composition of the hardware may vary slightly , small variations in the material will have a negligible effect on the dose rate response at the detectors.
4.6 It is assumed that the water below the active fuel region is liquid at a constant temperature.
Using a density of 0.9982 g/cm 3 is common in shielding Page 6 of 28  
.. ENERCON Excelk!nCt!
-Every proJec t E v ery day. Dose Rate Evaluation of CALC NO. NEE-323-CALC-002 Reactor Vessel Water Levelsf------------------i During Refueling for EAL Thresholds REV. 00 applications.
Any water above this region would be steam with little shielding value. 4.7 The source term is generated shortly after shutdown , therefore , the fuel gamma source term will predominate and the neutron-gamma and hardware activation can be neglected.
4.8 The high range detectors read out in roentgen per hour (R/h) which is a measurement of exposure rate , while the MCNP output is provided in mrem/h which is a measurement of the equivalent dose rate that represents the biological effects of ionizing radiation. It is assumed that 1 R is approximately 1000 mrem. This is acceptable as only the gamma source term is considered. 4.9 The roof of the Reactor Building is modeled as 0.5 inches of stainless steel. This will account for any scattering interactions that may contribute to the response at the detector.
The magnitude of the detector response due to scattering off of the roof will be small due to the geometry and amount of shielding in the model , and is therefore acceptable.
4.10 Automatic Depressurization System Accumulators 1 R003A/B/C located on the 775'-11 1'2" elevation are not included in the model. The size of the accumulators are 200 gallons [Reference 3.26]. This is relatively small compared to the geometry of the model, and the corresponding scatter interactions will not have a significant impact on the detector response.
Page 7 of 28 Dose Rate Evaluation of CALC NO. NEE-323-CALC-002 Reactor Vesse l Water Levels ,___ ____________ __. " ENERCON During Refueling for EAL 00 REV. Thresholds Excellenc~
-Evcry p r oj<<t Every day. 5.0 Design Inputs 5.1 Fuel Assembly Parameters The following fuel assembly parameters are used to homogenize the core in the MCNP model. They are based on typical fuel assembly values for 1Ox10 fuel. Table 2 -Design Input Fuel Assembly Parameters Parameters Fuel type # of Assemblies in Core # Fuel rods per assembly Pitch Density (% of theoretical)
Fuel pellet OD Fuel rod OD Clad thickness Active length 5.2 Model Dimensions Value lOxlO 368 92 0.5 1 95 0.33 6 0.395 0.026 144 Unit [in] [in] [in] [in] [in] Reference 3.25 3.11 3.12 3.12 3.12 3.12 3.12 3.12 3.12 The following elevations and dimensions are based on the associated drawings or other reference. Some parameters are estimated using drawing scales when exact dimensions are not provided.
Table 3 -Design Input Dimensions Dimension ft in cm Reference Pedestal inner radius 8 243.84 3.20 Pedestal outer radius 12 365.76 3.20 Reactor vessel inner diameter 185.375 470.85 3.15 Reactro vessel thickness 5 12.70 3.15 Drywell spherical portion radius 31.5 960.12 3.17 Figure 2 Concrete around drywell spherical 36 9 1120.14 3.14 portion(x and y directions radius) Drywell cylindrical portion radius 17 518.16 3.16 Drywell liner thickness 0.75 1.91 3.18 Concrete around drywell cylindri-22 9 693.42 3.16 cal portion (x and y directions)
Reactor Building (x and y direc-140 4267.20 3.14 tions) Reactor Building Roof Thickness 0.5 1.27 Assumption 4.9 Height of active fuel 144 365.76 3.12 Vessel Height 704.5 1789.43 3.15 Page 8 of 28 Dose Rate Evaluat i on of CALC NO. N EE-323-CALC-002 Reactor Vesse l Water Le v e l s 'I. ENERCON Exullence-Every proj<<r. E11ery day. During Refue l ing for EAL REV. 00 T hr es h olds Dimension ft in cm Reference Reactor vessel head thickness 3.9375 10.00 3.19 Distance from vessel O to bottom of 2 00.94 5 10.39 3.15 , 3.12 active fuel Bio shield inner radius 9 6.25 290.20 3.21 Bio shield outer radius 1 L 8.25 356.24 3.21 Reactor recirculating pump height 17 2 523.24 3.24 Reactor recirculating pump radius 2 9 83.82 3.24 Detector RE-9184A distance from 121.92 3 .23 [Scaled] origin (x plane) Detector RE-9184A distance from 13.33 406.29 3 .23 [Scaled] origin (y plane) Detector RE-9184B distance from 6 182.88 3 .23 [Scaled] origin (x plane) Detector RE-9184B distance from -1 2 -365.76 3.23 [Scaled] origin (y plane) Reactor Recirculating P u mp IP-12 365.76 3.23 [Scaled] 201A distance from origin (x plane) Reactor Recircu l at i ng Pump IP-12 365.76 3 .23 [Scaled] 201A distance from origin (y plane) Reactor Recirc u lat i ng Pump IP--12 -365.76 3 .23 [Scaled] 201B d i stance from origin (x plane) Reactor Recircu l ating Pump IP--12 -365.76 3.23 [Scaled] 201B distance from ori in lane Table 4 -Design Input Elevations 2 Dimension:
ft. in cm Reference Drywell Equator 766 0.5 0.00 3.13 Vessel 0 772 5.5 195.58 3.15 Bottom of pedestal elevation 742 9 -709.93 3.13 Top of cylindrica l portion of drywell 855 2711.45 3.13 concrete Top of Reactor Building 897 6 4006.85 3.13 Detector elevation 760 -184.15 3.17 Top of pedestal/
bottom of bio shield 770 10.5 147.32 3.20 Top of bio shie l d 816 3.25 1530.99 3.22 Reactor recirc ul atin 748 8.5 -528.32 3.13 2 All elevations listed in centimeters are relative to the equator of the drywe ll elevation of 766' 0.5" ence 3.13]. P age 9 of 28 ENERCON Excellencr:
-Evtry pro1~r. Every day. Dose Rate Evaluation of CALC NO. NEE-323-CALC-002 Reactor Vessel Water Levels1----------------i During Refueling for EAL Thresholds REV. 00 5.3 Core Isotopic Inventory Core isotopic activities in Ci/MWt are taken from Reference 3.7 Table 1-1. A tab l e of the input values is shown in Table 5, below. The activities in Ci are determined by multiplying by the rated thermal power of 1912 MWt taken from Reference 3.1 0. Table 5-Core Source Term Isotope Ci/MWt Ci Isotope Ci/MWt Ci Ba-139 4.74E+04 9.06E+07 Rh-105 2.81E+04 5.37E+07 Ba-140 4.76 E+04 9.10E+07 Ru-103 4.34E+04 8.30E+07 Ce-141 4.39E+04 8.39E+07 Ru-105 3.06E+04 5.85E+07 Ce-143 4.00E+04 7.65E+07 Ru-106 l.55E+04 2.96E+07 Ce-144 3.54E+04 6.77E+07 Sb-127 2.39E+03 4.57E+06 Cm-242 l.12E+03 2.14E+06 Sb-129 8.68E+03 l.66E+07 Cs-134 4.70E+03 8.99E+06 Sr-89 2.41E+04 4.61E+07 Cs-136 1.49E+03 2.85E+06 Sr-90 2.39E+03 4.5 7E+06 Cs-137 3.25E+03 6.21E+06 Sr-91 3.01E+04 5.76E+07 1-131 2.6 7 E+04 5.l 1 E+07 Sr-92 3.24E+04 6.19E+07 1-132 3.88E+04 7.42E+07 Tc-99m 4.37E+04 8.36E+07 1-133 5.42E+04 l.04E+08 Te-127 2.36E+03 4.51E+06 1-134 5.98E+04 l.14E+08 Te-127m 3.97E+02 7.59E+05 1-135 5.18E+04 9.90E+07 Te-129 8.26E+03 l .58E+07 Kr-83m 3.05E+03 5.83E+06 Te-129m l.68E+03 3.21E+06 Kr-85 2.78E+02 5.32E+05 Te-131m 5.41E+03 l .03E+07 Kr-85m 6. l 7 E+03 l.18E+07 Te-132 3.81E+04 7.28E+07 Kr-87 l .23E+04 2.35E+07 Xe-131m 3.65E+02 6.98E+05 Kr-88 1.70E+04 3.25E+07 Xe-133 5.43E+04 1.04E+08 La-140 4.91E+04 9.39E+07 Xe-133m l.72E+03 3.29E+06 La-141 4.33E+04 8.28E+07 Xe-135 l.42E+04 2.72E+07 La-142 4.21E+04 8.05E+07 Xe-135m l.15E+04 2.20E+07 Mo-99 5.30E+04 l.OI E+08 Xe-138 4.56E+04 8.72E+07 Nb-95 4.50E+04 8.60E+07 Y-90 2.45E+03 4.68E+06 Nd-147 1.75E+04 3.35E+07 Y-91 3.17E+04 6.06E+07 Np-239 5.69E+05 l.09 E+09 Y-92 3.26E+04 6.23E+07 Pr-143 3.96E+04 7.57E+07 Y-93 2.52E+04 4.82E+07 Pu-241 4.26E+03 8.15E+06 Zr-95 4.44E+04 8.49E+07 Rb-86 5.29E+Ol 1.0IE+OS Zr-97 4.23E+04 8.09E+07 Page 10 of 28  
---------Dose Rate Evaluation of CALC NO. NEE-323-CALC-002 Reactor Vessel Water Levels1------------------1 ENERCON Exce'1enct!
-Every proJ~t~ E v ery da y. During Refueling for EAL Thresholds 5.4 Material Compositions REV. 00 The following compositions used in the MCNP model are taken or developed from the SCALE standard composition library [Reference 3.1] and are shown in Table 6. Table 6 -Scale St anda rd Compositions used in MCNP Model Material Isotope Weight Fraction Zry-4 Zr 0.9823 (6.56 g/cm 3) Sn 0.0145 Cr 0.0010 Fe 0.0021 Hf 0.0001 U02 U-235 0.0348 (10.412 g/cm 3) U-238 0.8466 0 0.1186 Air C 0.0001 (1.21E-03 g/cm 3) N 0.7651 0 0.2348 Water H 0.1111 (0.9982 g/cm 3) 0 0.8889 SS-304 Fe 0.6838 (7 .94 g/cm 3) Cr 0.1900 Ni 0.0950 Mn 0.0200 Si 0.0100 C 0.0008 p 0.0004 Concrete 0 0.5320 (2.30 g/cm 3) Si 0.3370 [KENO Regular Ca 0.0440 Concrete Standard Al 0.0340 Mix] Na 0.0290 Fe 0.0140 H 0.0100 Carbon Steel C 0.0100 (7 .82 g/cm 3) Fe 0.9900 Page 11 of 28  
&deg;' ENERCON Excellen c e-Every p fO)K t. E~ery day. 5.5 Upper Internals Dose Rate Evaluation of CALC NO. NEE-323-CALC-002 Reactor Ve s se l Water Le v els 1------------------1 During Refueling for EAL Thresholds REV. 00 The following weights are used i n the MCNP model for t he regio n between the active fuel and the reactor vesse l head [Reference 3.9 , Appendix 8.9]:
* The w e i ght of stain l ess stee l for the mo i sture separat o r i s 83 , 00 0 lb s.
* The weight of stainless stee l for the steam dryer is 50,000 lbs. 5.6 The drywell (9184 A/B) and torus (9185 A/B) radiation monitor ranges (1 to 10 7 R/hr) are taken from Reference 3.6. 5.7 ANSI/A N S-1977 Flux to Dose Factors Flux to dose conversion factors are taken from ANSI/ANS-6
.1.1-1977 [Reference 3.4] and are shown in Table 7. T a bl e 7 -ANSl!ANS-6.1. 1-197 7 Flu x to D ose F a ctors Me V mr e m/hr/(y/cm 2/s) Me V mrem/hr/(y/cm 2/s) 0.01 3.9 6&#xa3;-0 3 0.8 1.6 8&#xa3;-0 3 0.03 5.82&#xa3;-0 4 1 1.98&#xa3;-0 3 ---0.05 2.9 0&#xa3;-04 2.2 3.4 2&#xa3;-0 3 ---~ 0.0 7 2.58&#xa3;-0 4 2.6 3.82&#xa3;-0 3 Page 12 of 28 ENERCON Excellena:
-Every proJ~l. Every day. 6.0 Methodology Dose Rate Evaluation of CALC NO. NEE-323-CALC-002 Reactor Vessel Water Levels ,___ ___________
_____. During Refueling for EAL Thresholds REV. 00 The reactor source terms are decayed to 50 hours with ORIGEN-S of the SCALE 6.1 code package , Reference 3.2. The results are used to bin design input isotope specific activities into energy dependent photon bins. These energy specific photon emission bins are used as input for the energy distribution described by the MCNP source definitions. The MCNP6 , Reference 3.3 , Monte Carlo transport code is used to determine the dose r ates via the flux to dose conversion factors in Table 7 , while accounting for shielding and particle transport.
The detailed engineering drawings are converted into MCNP surface and cell cards in the dimensions shown in Table 3 and Table 4. The radiation monitors of interest are modeled as point detectors to determine the expected dose rate for those detectors.
The dose rates are calculated for two reactor refueling conditions: 
: 1. With Head -the reactor is modeled with a 3.9375 inch carbon steel plate as indicated in Table 3 , which is additional attenuation between the source and detector.
The mass of the moisture separator and steam dryer is homogenized between the active fuel region and the vessel head. 2. Without head -the reactor is modeled with air between the active fuel zone and containment. 
: 3. A sensitivity case is run with a mirror surface at the top of the drywell to ensure the modeling of the drywell cap would not significantly affect the response at the detector locations due to scattering. Variance reduction is accomplished with a geometric importance map that is imposed on the homogenized core. In addition , cell based importance weighting and source biasing (see Section 7.5) are utilized to improve the variance reduction of the simple geometric scheme. A superimposed weight window mesh is utilized where necessary to improve variance.
The weight windows are iteratively generated using the MCNP weight windows generator card. All final dose rates presented in this calculation include weight windows variance reduction. Page 13 of 28 Excellencr
-Every proj<<r. E 11 ery day. Dose Rate Evaluation of CALC NO. NEE-323-CALC-002 Reactor Vessel Water Levels 1----------------1 During Refueling for EAL 00 Thresholds REV. I ENERCON 7 .0 Calculation 7.1 Source Terms The ORIGEN-S input deck , DAECEAL.inp , is provided in Appendix C. This input produces a simple case where the isotopic composition from Table 5 is decayed. The isotope is specified in the 73$$ card using the special identifier described in Section F7.6.2 of the ORIGEN-S manual , and the activity in curies is specified in the 74** card. The time steps for the decay are given on the 60** card in hours. Although multiple time steps are calculated , the source term with 50 hours decay time is used in this calculation to model the core shortly after shutdown. The output of the decay is given in terms of photons/s/Energy-Group , which is automatically normalized in the MCNP input. The results of this calculation are summarized below in Table 8. These values are used in the MCNP input source definition.
Table 8-Binned Total Core Source Term Energy Group Energy Boundaries (Me V) Photons/sec 1 0.01-0.05 2.028E+l9 2 0.05-0.1 6.572E+ 18 3 0.1-0.2 l.557E+ 19 4 0.2-0.3 9.672E+l8 5 0.3-0.4 3.5 82E+I8 6 0.4-0.6 7.837E+l8 7 0.6-0.8 1.373E+19 8 0.8-1 2.132E+l8 9 1-1.33 4.942E+17 10 1.33-1.66 3.5 79 E+l8 11 1.66-2 6.576E+l6 12 2-2.5 7.518E+l6 13 2.5-3 l.l 10 E+17 14 3-4 8.689E+l4 15 4-5 1.553E+10 16 5-6.5 2.568E+08 17 6.5-8 3.792E+07 18 8-10 8.041E+06 19 10-11 4.352E+05 totals 8.37E+ 19 Page 14 of 28 Excelk!na-frery project. Every day. Dose Rate Evaluation of CALC NO. NEE-323-CALC-002 Reactor Vessel Water Levels,__
___________ 
----< During Refueling for EAL 00 REV. Thresholds ENERCON 7.2 MCNP Model Core Homogenization The source term is given for the entire core , therefore, the self-shielding from the assemblies is an important part of the dose rate response.
For simplicity, the core is modeled as a three dimensional cylinder with a uniformly distributed spatial particle distribution.
The calculations for determining the mass of fuel , cladding and water for the core and the resulting density are shown below. The inputs are based on the dimensions in Table 2. Assembly Width= (Array Size -1) x pitch+ Rod OD = (10 -1)(0.Slin) 
+ 0.395in = 4.985 in Active Fuel Region Area= (Assembly Width)2 x Number of Assemblies in Core = ( 4.985in)2 x 368 = 9144.883 in 2 Active Fuel Equivalent Radius= jActive Fuel RegionArea;n 
= j9144.883 in 2/rr = 53.953 in Rod Volumeu 0 2 = rr(Pellet Radius)2 x Active Length= rr(0.168 in)2 (144 in) = 12.768 in 3 g cm 3 Rod Massuo = p x V = (10.412-) 
(12.7682 in 3) (2.54-.-) 
= 2178.54 g 2 CC Ln Number of Fuel Rods Assembly Massuo = Rod Mass x bl = (2178.54 g)(92) 2 Assem y = 200.43 kg (OD 2 ID 2) Clad Volume= rr 4-4 x Active Length [(0.395 in)2 (0.343 in)2] ( 3 = (rr) 4 -4 144 in) = 4.34 in g cm 3 Rod MaSS zry-4 = p x V = ( 6.56 cJ ( 4.34 in 3) ( 2.54 in) = 466.5 g Page 15 of 28 I ENERCON Excell~nce-Every projecr. Every day. Dose Rate Evaluation of CALC NO. NEE-323-CALC-002 Reactor Vessel Water Levels1------------------i During Refueling for EAL Thresholds REV. 00 Numbe r of Fuel Rods Assembly Masszry-4 = Rod Mass x A bl = (466.5g)(92) 
= 42.92 kg ssem y Assembly H 2 0 Volume = [(Assembly Width)2 -rr(Rod Radius)2 x Number of Fuel Rods] x Active length = [( 4.985 in)2 -(rr)(0.1975 in)2 (92)](144 in) = 1955 in 3 ( 9)(1955)( cm)3 Assemb ly MassH O = p x V = 0.9982-. 3 2.54-.-= 31.98 kg 2 cc m m Assembly Volume= Active length x (Assembly Width)2 = (144 in)(4.985 in)2 = 3578.4 in 3 . Total Mass 1000g/kg(200.43 
+ 42.92 + 31.98) kg Density= = 3 = 4.70 g/cc Volume 3578.4 in 3 ( 2.54 ~:;;J The corresponding isotopic composition for the homogenized active fuel region is calculated based on the compositions in Table 6. An example calculation for the mass fraction of U-235 is included below. Assembly Massuo Mass Fraction U235 = l 2 x weight fraction U235 Tota Mass 200*43 kg X 0.0348 = 0.0253 (200.43 + 42.92 + 31.98) kg The remaining calculations for the homogenization are done in the worksheet Compositions of the EXCEL workbook DAEAL.xlsx and are shown in Appendix B. The isotopic compositions are calculated with the water level above the top of the fuel. Note that the EXCEL workbook uses additional significant figures. Page 16 of 28 I ENERCON Excellenc~
-Every proj<<t~ Every day. ZAID N u mb e r 92235 92238 8016 40000 50000 24000 26000 72000 100 1 Do se Rate Eval u ation of CALC NO. NEE-323-CALC-00 2 Reacto r Vessel Water Level s~--------------< During Refueling fo r EAL Threshold s REV. 00 Tab l e 9 -H omo g enization o f A c ti ve F uel R eg i on A tom Ma s s Fraction Act i ve Fu e l Regio n Homoge ni zed U-235 0.0253 U-238 0.6163 0 0.1896 Zr 0.1531 Sn 0.0023 Cr 0.0002 Fe 0.0003 Hf 0.0000 H 0.0129 7.3 MCNP Model Upper Internals Homogenization For the case with the reactor vessel head i n place , the steam dryer and moisture separator region a r e modeled as a discr e te cylinde r with a uniformly distributed homogenized mate r ial to accoun t for the mass of stainless steel between the active fuel height and r eactor vessel head. The homogen i zation ac c ounts for the mass of metal from Section 5.5 (assumed stainless steel type 304 per Assumption 4.5) distributed evenly across t h e volume between th e active fuel heigh t (Z=1071.73 cm) and the head (Z=1985.01 cm). Mass Upper Internals= 
(830 00 lb+ 500 00 l b) ( 453.59 ~) = 6.033 x 1 0 7 g The mass is divided by the volume of the reg i on between the active fuel height and the r eactor vessel head to determine the density. Density U pper Internals 
= M ass Upper Internals 
+ V = 6.033 x 10 7 g + (913.28cm x (rr(235.43c m)2) = 0.379 !!_ cc 7.4 MCNP Model Geometry T he follow i ng MCNP model geometry is based on the conta i nment dimensions summarized in Table 3 and Table 4. The model only focuses on the pr i mary systems and componen t s that prov i de shielding or reflect i on from the core to the radiation monitors. These components i nclude the reactor vessel , recirculat i on pumps , pedestal, biological s hield and drywell. V I S E D plots of the mod e l geometry a r e provided i n Figures 1-3. The MCNP surf ace cards w ith the model dimensions (cm) are shown in Figure 4 , and the c ell cards are shown in F i g u r e 5 for the cases w i th no reactor vessel head. A VISED plot of t he model with the reactor vessel head is shown in Figu r e 6. Areas that are not of interest Page 17 of 2 8  
--~---------------Dose Rate Evaluation of CALC NO. NEE-323-CALC-002 Reactor Vessel Water Levels>--____________
__, ENERCON Excellence
-Evtry proJ<<t. E v ery day. During Refueling for EAL 00 REV. Thresholds are given an importance of zero (white areas) so MCNP will not track particles in locations that will not contribute to the detector response.
Figure 1 X-Z VISED Plot of Reactor Vessel (No Head) _. +-1 2.7 0 c m 1789.43 cm + 470.85cm Homogenized Core ---1,= Water Page 18 of 28 Air Reactor Vess el Biological Shield ENERCON Excelknce-Every proJ<<-t Every d ay. Dose Rate Evaluation of CALC NO. NEE-323-CALC-002 Reactor Vessel Water Levelsf---
-------------1 During Refueling for EAL Thresholds REV. 00 Figure 2 Vised Plot of Drywe/1 and Reactor Building 3 Pump Reactor Building Drywell Pedestal Radiation Monitor Pump 3 Radiation monitors are not on the same plane shown above. They are included for visualization purposes only. The VISED Plot was rotated around the Z axis until the Recirculating Pumps were visible. Page 19 of 28 Dose Rate Evaluation of CALC NO. NEE-323-CALC-002 .ii ENERCON Reactor Vessel Water Levels Excellena-Every pl'O)<<t. E"lery day. During Refueling for EAL REV. 00 Thresholds Fi gure 3 X-Y V ised Pl ot of D e t ec t o rs a nd R ea c tor Recircul a t i ng Pump s a t El e vation 760'-0" 4 4 Detectors are included fo r visualization pu r poses only. Page 20 of 28 Dose Rate Evaluation of CALC NO. NEE-323-CALC-002 Reactor Vessel Water Levels 1-----------------i ENERCON Excdl~nce-Every proj<<r. Every day. During Refueling for EAL Thresholds REV. 00 F i g u re 4 MCNP Model Surface C a rds 5 c surfaces 1 rec O O 705.97 0 0 365.76 137.045 2 rec O O 208.28 0 0 1776.73 235.4 3 3 rec O O 195.58 0 0 1789.43 248.13 4 rpp -1120.14 1120.14 -1120.14 1120.14 -1120.14 821.86 5 so 960.1 2 6 so 958.21 7 pz -709.93 8 rec O O -709.93 0 0 857.25 243.84 9 rec O O -709.93 0 0 857.25 365.76 81 rec O O 147.32 0 0 1383.67 290.20 91 re c O O 147.32 0 0 1383.67 356.24 82 rec 365.76 365.76 -528.32 0 0 523.24 83.82 92 rec -365.76 -365.76 -528.32 0 0 523.24 83.82 10 pz 195.58 11 pz 821.86 12 rec O O 821.86 0 0 13 rec O O 821.86 0 0 14 rpp -693.42 693.4 2 15 pz 1071. 73 16 pz 1985.01 17 rpp -4267.2 4267.2 18 rpp -4267.2 4267.2 19 pz 147.32 20 pz 1530.99 1889.59 518.16 1889.59 516.25 -693.42 693.4 2 -4 267.2 4267.2 -4267.2 42 67. 2 28 rec O O 1985.01 0 0 10.00 248.1 3 101 102 103 104 105 1 06 107 108 109 110 pz pz pz pz pz p z pz pz pz pz 742.546 779.122 815.698 852.274 888.85 925.246 962.002 998.578 1035.154 1071.7 3 821.86 2711.45 2711. 45 4006.85 4006.85 4008.12 $ Active Fuel Region $ Reactor Pressure Vessel Inner Surface $ Reactor Pressure Vesse l O uter Surface $ Concrete Spher port drywell outer $ Spher portion of drywell o ut er surface $ Spher portion of drywell liner surface $ Bottom of Pedestal E l evation $ Pedestal Inner Surface $ Pedestal Outer Surface $ Bio Shield Inner Surface $ Bio Shield Outer Sur fa ce $ Recirc Pump IP-201A $ Recirc Pump IP-201B $ Vessel 0 $ Transition Spherical to Cy lindri ca l $ cylin port drywell concrete surface $ cylin port drywell liner surface $ Concrete cylin port drywell outer $ Water Elevation Surface $ Top of RPV (head level) $ Reactor building above drywell $ Reactor building roof $ Top of Ped Elevation/Bottom Bio Sh i eld $ Top of Ped Elevation/Bottom Bio Shield $ Reactor Head 5 The surface card for the MCNP model without the r eactor vessel head does not have surface 28. Page 21 of 28 ENERCON Excellence
-Every pro ject. f y ery day. c ce ll s 101 1 -4.49 101 102 1 -4.49 -1 101 -102 103 1 -4.49 -1 102 -10 3 104 1 -4.49 -1 103 -104 105 1 -4.49 -1 104 -105 106 1 -4.49 -1 105 -1 06 107 1 -4.4 9 -1 106 -10 7 108 1 -4.49 -1 107 -108 109 1 -4.49 -1 108 -1 09 110 1 -4.4 9 -1 1 09 -110 2 2 -0.9982 1 15 3 3 -1. 21E-03 15 -2 4 4 -7.94 2 16 7 5 -2.3 5 -4 8 5 -2.3 -14 12 9 5 -2.3 -9 8 7 -1 9 91 5 -2.3 -91 8 1 19 -20 10 5 -2.3 7 11 3 -l.21 E-03 -8 12 3 -l.21 E-0 3 -6 7 -11 9 #18 #19 #9 1 13 3 -1. 21E-03 -1 3 3 #91 14 3 -1. 21E-03 -17 15 4 -7.9 4 2 -18 16 4 -7.94 6 11 17 4 -7.94 13 -1 2 18 4 -7.94 -82 19 4 -7.94 -92 999 0 1 #2 #3 #4 #7 #8 #9 #15 #16 #17 Dose Rate Evaluation of CALC NO. NEE-323-CALC-002 Reactor Vessel Water Levels1--
During Refueling for EAL Thresholds REV. 00 Figure 5 MCNP Model Cell Cards (No Head) imp:p=256 
$ Active Fuel Region imp:p=l28 
$ Active F uel Region imp: p=64 $ Active Fu e l Regio n imp:p=32 $ Active Fuel Region i mp: p=l6 $ Active Fuel Region imp:p=8 $ Active Fuel Region imp:p=4 $ Active Fuel Region imp: p=3 $ Active Fuel Region imp: p=2 $ Active Fuel Region imp: p=l $ Active Fue l Region imp:p=256 $ Water Region imp:p=256 $ Air Region inside vessel imp:p=256 $ RPV Shell imp: p=256 $ Concrete Surrounding RPV spher i cal imp:p=256 $ Concrete Surround i ng RPV cylindrical imp: p=256 $ Pedestal imp:p=2 56 $ Bio Shield imp:p=2 56 $ Concrete at bottom of pede sta l imp:p=256 
$ Inside Pedestal A ir 3 imp:p=256 $ Inside Spherical portion Air imp: p=256 $ Inside Cylindrica l portion Air imp: p=256 $ Reactor Building above drywell Air imp:p=256 $ Reactor Build Roof Stainless Steel imp:p=2 56 $ Containment Liner Spherical portion imp:p=256 $ Conta i nment Liner Cylin portion imp: p=256 $ Recirc Pump IP-201A imp:p=256 $ Recirc Pump IP-201B #10 #11 #12 #13 #14 #18 #19 #91 imp:p=O $ P r oblem Boundary Page 22 of 28 I ENERCON Excellence
-Every proj<<r. E v ery day. Dose Rate Evaluation of CALC NO. NEE-323-CALC-002 Reactor Vessel Water Levels1-----
-------------1 During Refueling for EAL Thresholds REV. 00 Figure 6 X-Z V SED Plot of Reactor Vessel (With Head) Reacto r Vessel Head Cell for the homogenization of the Upper Internals stainless steel 0.379 g/cm 3 7.5 MCNP Source Definition Homogen i zed Core The core source term is modeled as uniformly distributed throughout the homogenized core , and has an energy spectra based on the decayed core inventory (Section 7.1). Only the gamma source term is taken into account for this evaluation.
The source term is generated shortly after shutdown , therefore, the fuel gamma source term will predominate, and the neutron-gamma and hardware activation source terms can be neglected (Assumption 4.7). The source is defined on the MCNP sdef card using Page 23 of 28 Dose Rate Evaluation of CALC NO. NEE-323-CALC-002 Reactor Vessel Water Levels 1-----------------< ENERCON Excellenc e-Every pro j ec t. E v ery da y. During Refueling for EAL Thresholds REV. 00 distributions to define the particle location and energy. The radius of the core is defined with the rad parameter , which automatically creates a uniform distribution based on a cylindrical geometry.
The ext and axs parameters define the direction and distance of the cylinder axis. These parameters combined define the core where the particles can be born. The erg parameter defines the energy spectrum of source part i cles , and is based on the results of the ORIGEN-S calculation discussed previously.
This distribution is a histogram of energies represented by activities. These are automatically normalized by MCNP to create a probability distribution.
The total activity is preserved in the tally multiplier. The MCNP source definition cards are shown below in Figure 7. The sb card is a source biasing card , which in this case biases the particle generation to the lower end of the core. This is a variance reduction technique to improve the statistical certainty in the results. Figure 7 MCNP Sour ce D e finition C a rds sdef rad=dl ext=d2 axs=O O 1 erg=d8 sil 137.045 si2 h O 742.546 779.122 815.698 852.274 888.85 925.246 962.002 998.578 1035.154 1071.73 sp2 0 1 1 1 1 1 1 1 1 1 1 sb2 0 1 1 0.1 0.1 0.1 0.01 0.01 0.01 0.001 0.001 c Fuel Gamma Spectra ~Source Defin i tion Card -Radius= dl -Extent= d2 -Axis= +Z -Energy= d8 ~Core Radius Distribution 
~Core Axial Distribution 
~Actual Uniform Distribution 
~Biased to Bot Distribution si8 h l.OOOe-002 5.000e-002 l.OOOe-001 2.000e-001 3.000e-001 4.000e-001 ~Source Energy Groups 6.000e-001 8.000e-001 l.OOOe+OOO l.330e+OOO 1.660e+OOO 2.000e+OOO 2.500e+OOO 3.000e+OOO 4.000e+OOO 5.000e+OOO 6.500e+OOO 8.000e+OOO l.OOOe+OOl l.lOOe+OOl sp8 0.00E+OO 2.028E+l9 6.572E+l8 l.557E+l9 9.67 2 E+1 8 3.582E+1 8 7.837E+l8 
~Source Emission on Energy Basis l.373E+19 2.132E+18 4.94 2 E+1 7 3.579E+l 8 6.576E+1 6 7.518E+16 l.1 1 0E+l7 8.689E+14 l.553E+10 2.568E+08 3.79 2 E+07 8.041E+06 4.352E+05 Page 24 of 28 Dose Rate Evaluation of CALC NO. NEE-323-CALC-002 Reactor Vessel Water Levels1---------------; "'ENERCON ExceJlenc~Every proJe<:t.
Every day. During Refueling for EAL Thresholds 7.6 MCNP Tally Specification REV. 00 The tallies used in this evaluation are point detectors placed at approximate locations of radiation monitors RE-9184A , and RE-9184B.
Point detectors are chosen because they use quasi-deterministic dose calculations that will provide better results than surface or cell based tallies that require the particles to enter those regions. The inputs to this card are the coordinates of the dose points followed by an exclusion zone to reduce variance , as well as a multiplier card , which represents the total core activity in photons/sec.
The tally cards are shown in Figure 8. Figure 8 MCNP Tally Cards f5c RE-9184A, and 9184B f5:p -1 21.92 406.29 -184.15 20 182.88 -365.76 -1 84.15 20 fm5 8.370E+l9 f-Tally Comment Card f-Tally 5 (point detector) x y z exclusion f-Tally Multiplier (Total Activity)
In addition , the flux is multiplied by ANSI/ANS flux-dose conversion factors [Reference 3.4]. This is specified in MCNP using the de/df cards. These are shown in Figure 9. Figure 9 ANSl!ANS-6
.1.1-1977 Gamma Flux to Dose Conversion Factors C --------------------------------
---------------
-----------------
--C ANSI/ANS-6
.1.1-1977 c Gamma Flu x to Dose Conversion Factors c (mrem/hr)/(photons/cm2-s) C ------------
--------------------------
----------------------------
de0 .01 .03 .05 .07 .10 .15 .20 .25 .30 .35 .40 .45 .50 .55 .60 .65 .70 .80 1. 1. 4 1. 8 2.2 2.6 2.8 3.25 3.75 4.25 4.75 5. 5.25 5.75 6.25 6.7 5 7.5 9. 11. dfO 3.96E-03 5.82E-04 2.90E-04 2.58E-04 2.83E-04 3.79E-04 5.0lE-04 6.31E-04 7.59E-04 8.78E-04 9.85E-04 l.08E-03 l.17E-03 l.27E-03 l.36E-03 l.44E-03 l.52E-03 l.68E-03 l.98E-03 2.51E-03 2.99E-03 3.42E-03 3.82E-03 4.0lE-03 4.41E-03 4.83 E-03 5.23E-03 5.60E-03 5.80E-03 6.0lE-03 6.37E-03 6.74E-03 7. llE-03 7.66E-03 8.77E-03 1. 03E-02 Page 25 of 28 f-Energy Bins for Flux to Dos e Conversion f-Energy Dependent Flux Multiplier s
ENERCON Excellencr
-Every proJect. E v ery day. Dose Rate Evaluation of CALC NO. NEE-323-CALC-002 Reactor Vessel Water Levelsf---
--------------1 During Refueling for EAL Thresholds REV. 00 7.7 MCNP Material Cards The MCNP material cards are provided in Figure 9. These are based on the compositions described in Table 6 or calculated in Section 7.2. Figure 10 MCNP Material Cards ml 92235 -0.0253 $ Homogenized Active Fuel Region 92238 -0.6163 8016 -0.1896 40000 -0.1531 50000 -0.0023 24000 -0.0002 26000 -0.0003 1001 -0.0129 m2 1001 2 8016 1 $ Water m3 6012 -0.000126 $ Air 7014 -0.76508 8016 -0.234793 m4 6000 -0.0008 $ ss 304 14000 -0.01 15031 -0.00045 24000 -0.19 25055 -0.02 26000 -0.6 8375 28000 -0.095 m5 26000 -0.014 $ Reg-Concrete 1 001 -0.01 1 3027 -0.034 20000 -0.044 8016 -0.53 2 14000 -0. 337 11023 -0. 029 m6 6012 -0.01 $ Carbon Steel 26056 -0.99 Page 26 of 28 Dose Rate Evaluation of CALC NO. NEE-323-CALC-002 Reactor Vessel Water Levelsf----
-------------1 ENERCON Excellence
-Every project. E'ilery day. 7.8 Results During Refueling for EAL Thresholds REV. 00 The dose rates are provided in Table 10 for the water level at the top of the fuel assemblies.
The dose rate is slightly above the detectable response of 1 R/h (1 E+03 mrem/h) for the no head configuration , and below the detectable response for the configuration with the reactor vessel head in place for one of the detectors.
The sensitivity case shows that there is no significant impact due to reflection from the drywell cap. Table 10-Dose R ate Response (mremlh) Configuration Dose Rate 1 fsd 6 Dose Rate 2 fsd Tally F il e RE-9 184 A RE-9184B No Head l.8lE+03 10.81 % l.68 E+03 7.31% dOndm With Head l.11E+03 10.16% 7.41E+02 8.24% dOhgm With Head (Sen-l.07E+03 15.27% 7.67E+02 15.51% dOrdm sitivity Case} 8.0 Computer Software This calculation uses ORIGEN-S of the SCALE Version 6.1.2 code package [Reference 3.2] and MCNP Vers ion 6.1.0 [Reference 3.3] in accordance with CSP 3.09. 6 Fraction standard deviation. Page 27 of 28 ENERCON Excellence-Every projt!C t. E very day. 9.0 Impact Assessment Dose Rate Evaluation of CALC NO. NEE-323-CALC-002 Reactor Vessel Water Levels 1-----------------4 During Refueling for EAL Thresholds REV. 00 This calculation is based on " realistic" assumptions for the purpose of declaring EALs , rather than typical conservative 
" bounding" type design basis analyses.
The calculation results are intended to provide order of magnitude dose rates to assist Operations and Emergency Response personnel in determination of core uncovery in accordance with NEI 99-01 Rev. 6. Page 28 of 28
* ENERCON Excellenc~-Evt.ry project. E v ery day. Origen output: 07/26/2017 04: 1 9 P M MCNP output: Directory of \No h ead\ 08/16/2017 09:13 AM Directory of \With Head\ 08/16/2017 10:01 AM Directory of \sensitivity\
08/16/2017 03: 54 AM Appendix A Electronic File Listing 82 , 1 14 DAECEAL.OUT 327 , 680 dOnao 1 , 269 , 760 dOhgo 286 , 720 dOrdo Page 1 of 1 CALC NO. REV. N EE-323-CALC-002 00 1 2 3 4 5 6 7 8 9 10 11 12 1 3 14 15 16 17 1 8 19 20 21 22 23 24 25 26 27 28 29 30 3 1 A ENERCON fxcellence-Evtry p r oject. &#xa3;v ery doy. B C D :Material Isotope Weight Fraction Zr y-4 Zr 0.9823 {6.56 g/cm 3) Sn 0.0145 Cr 0.00 1 Fe 0.0021 Hf 0.0001 U0 2 U-235 0.034 8 U-23 8 0.8466 0 0.1186 Air C 0.0001 {l.21E-03 N 0.7651 g/c m 3) 0 0.234 8 Water H 0.1111 (0.998 2 g/cm 3) 0 0.8889 SS-304 Fe 0.6838 {7.94 g/cm 3) Cr 0.19 Ni 0.095 .Mn 0.02 Si 0.01 C 0.0008 p 0.0004 Concrete 0 0.532 (2.30 g/cm 3) Si 0.337 Ca 0.044 Al 0.034 Na 0.02 9 Fe 0.014 H 0.01 Carbon Steel C 0.01 (7.82 g/cm 3) Fe 0.99 Appendix B DA E AL.xl s x Shee ts E F G H Mas Reference Materials (KG) [1] U0 2 200.4 Zry-4 42.92 Water 31.98 [I] [I] [!] [!] [l] f l l Pa g e 1 o f 2 -CALC NO. REV. ZAIDNumber 92235 92238 8016 40000 50000 24000 26000 nooo 1001 K Atom U-235 U-238 0 Zr S n Cr Fe Hf H N EE-323-CALC-002 00 L Mass Fraction Active Fuel Region Homogenized 0.0253 0.6163 0.1896 0.1531 0.002 3 0.0002 0.0003 0.0000 0.0129 1.0000 1 2 I 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 A B Material Z ry-4 (6.5 6 g/cm 3) U 0 2 Air (l.l lE-0 3 g/cm 3) Wat e r (0.998 2 g/cm 3) SS-304 (7.9 4 g/cm 3) Concrete (2.30 g/cm 3) Carbon Steel (7.82 rzJ cm 3) ENERCON Exr:ellenc~-f.~ry projllt. &#xa3;v ery d(J<;. C D E Isotope Weight R eference Fraction Zr 0.98 2 3 [1) Sn 0.0 1 45 Cr 0.00 1 Fe 0.002 1 Hf 0.000 1 U-235 0.034 8 [1] U-238 0.8 46 6 0 0.1 18 6 C 0.0001 [1] N 0.765 1 0 0.234 8 H 0.111 1 [1] 0 0.8 8 89 Fe 0.6 8 3 8 [1] Cr 0.19 N i 0.0 9 5 Mn 0.02 S i 0.01 C 0.000 8 p 0.0004 0 0.532 fll Si 0.337 Ca 0.044 Al 0.034 Na 0.02 9 Fe 0.0 1 4 H 0.0 1 C 0.0 1 ri 1 Fe 0.9 9 F Appendix B DAEAL.xlsx Sheets G H Material Mass (KG) U 0 1 20 0.42 Zry-4 42.9 2 Water 3 1.98 Pag e 2 of 2 CALC NO. REV. K ZAID Numb e r Atom 92235 U-235 922 3 8 U-23 8 80 1 6 0 4 0000 Z r 50000 S n 24000 C r 26000 F e 72 0 0 0 Hf 1001 H NEE-323-CALC-002 00 L Mass Fraction Act i ve Fuel Region H omoge n ized =(H 3/SU M(H 3:H 5))*08 =(H 3/S UM(H 3:H5))*D9 =((H 3/(S UM(H3:H 5)))*0 1 0)+((H 5/(S UM(H3:H 5))))*015 =($H$4/S UM($H$3:$H$5))*D3 =($H$4/S UM($H$3:$H$5))*D4 =($H$4/S UM($H$3:$H$5))*D5 =($H$4/S UM($H$3:$H$5))*D6 =($H$4/S UM($H$3:$H$5))*D7 =(H 5/S UM(H3:H 5) )*D 14 =S UM(L3:lll) 
+
CALC J I ENERCON Appendix C NO. &cellt!nce-Every projllr. E v ery da y. SCAL E Input REV. =origens 0$$ all 71 e t BWR Source Term DAEC EAL Analysis 3$$ 21 1 1 a4 27 a16 4 a33 19 et 35$$ 0 t 54$$ a8 0 all 2 e 56$$ 0 6 a6 1 alO 0 a13 63 3 3 0 2 0 e 57** 0 a3 1-16 e 95$$ 0 t DAECEAL Ci Source Terms 60** 0 24 40 so 60 70 61** Srl-8 1+6 1+4 65$$ 'GRAM-ATOMS 3Z GRAMS 0 1 0 1 1 1 CURIES 1 0 0 1 0 1 1 1 1 WATTS-ALL 1 0 0 WATTS-GAMMA 3Z 3Z 3Z 1 1 1 81$$ 2 O 26 1 e 82$$ f 2 83** l.10E+07 l.OOE+07 2.S OE+06 2.00E+06 4.00E+OS 3.00E+OS 84** 2.00E+07 6.43E+06 l.OOE+OS 1. 70E+04 3.0SE+OO l.77E+OO 1 1 1 3Z 1 1 1 3Z 8.00E+06 6.SOE+06 5.00E+06 4.00E+06 1. 66E+06 l.33E+06 l.OOE+06 8.00E+OS 2.00E+OS l.OOE+OS 5.00E+04 1. OOE+04 3.00E+06 1. 85E+06 l.40E+06 9.00E+OS 3.00E+03 5.SOE+0 2 l.OOE+02 3.00E+Ol l.30E+OO l .13E+OO l.OOE+OO 8.00E-01 6Z 6Z 6Z 3.00E+06 6.00E+OS e 4.00E+OS l.OOE+Ol 4.00E-01 3.2SE-01 2.2S E-01 l.OOE-01 S.OOE-02 3.00E-02 l.OOE-02 1. OOE-05 e 73$$ 561390 561400 581410 581430 581440 962420 551340 551360 551370 531310 531320 531330 531340 531350 360831 360850 360851 360870 360880 571400 571410 571420 420990 410950 601470 932390 591430 942410 370860 451050 441030 441050 441060 511270 511290 380890 380900 380910 380920 430991 521270 521271 521290 52 1 29 1 521311 521320 541311 54 1 330 541331 541350 541351 54 1 380 390900 390910 390920 390930 400950 400970 74** 9.06E+07 9.10E+07 8.39E+07 7.65E+07 6.77E+07 2.14E+06 8.99E+06 2.85E+06 6.21E+06 5 .11 E+07 7.42E+07 1. 04E+08 l.14E+08 9.90E+07 5.83E+06 5.32E+OS l.18E+07 2.35E+07 3.25E+07 9.39E+07 8.28E+07 8.0SE+07 1. 01E+08 8.60E+07 3.35E+07 l.0 9E+09 7.57E+07 8.1SE+o6 l.OlE+OS S.3 7E+07 8.30E+07 5.85E+07 2.96E+07 4.57E+07 l.66E+07 4.61E+07 4.57E+06 S.76E+07 6.1 9E+07 8.36E+07 4.51E+06 7.59E+OS 1. 58E+07 3.21E+06 l.03E+07 7.28E+07 6.98E+OS l.04E+08 3.29E+06 2. 72E+07 2.20E+07 8. 72E+07 4.68E+07 6.06E+07 6.23E+07 4.82E+07 8.49E+07 8.09E+07 75$$ 3 3 3 3 3 2 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 2 3 2 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 t 56$$ fO t end Page 1 of 1 3 NEE-323-CALC-002 00 CALC NEE-323-CALC-002 Attachment 1 NO. ENERCON CALCULAT I ON PREPARATION bce llen ce-E v~ry project. (very day. CHECKLIST REV. 0 CHECKLIST ITEMS 1 YES NO N/A GENERAL REQUIREMENTS 
: 1. If the calculation is being performed to a client procedure , is the procedure being D D [81 used the latest revision? The Calcu l at i on is performed in accordance with ENERCON procedures. 2. Are the proper forms being used and are they the latest revision? 
[81 D D The Ca l culation is performed in accordance with ENERCON procedures. 
: 3. Have the appropriate client review forms/check l ists been completed?
D D [81 OAR will be performed after calculation submittal 
: 4. Are all pages properly identified with a calculation number , calculation revision and [81 D D page number consistent with the requirements of the client's procedure? 
: 5. Is all information legible and reproducible? 
[81 D D 6. Is the calculation presented in a logical and orderly manner? [81 D D 7. Is there an existing calculation that should be revised or voided? D [81 D There is no existing ca l cu l at i on that should be rev i sed or voided. 8. Is it possible to alter an existing calculation instead of preparing a new calculation for D [81 D this situation?
No existing calculation would be applicable. 9. I f an e x isting calculation is being used for design inputs , are the key design inputs , assumptions and engineering judgments used in that calculation valid and do they D D [81 apply to the calc u lation revision being performed. No existing calculation is used for design inputs 10. Is the format of the calculation consistent with applicable procedures and [81 D D expectations? 
: 11. Were design inpuUoutput documents proper l y updated to reference this ca l culation?
D D [81 There are no design output documents. 12. Can the calculation logic , methodology and presentation be properly understood 
[81 D D without referring back to the originator for clarification?
OBJECT I V E A ND S COPE 13. Does the calcu l ation provide a clear concise statement of the problem and objective 
[81 D D of the calculation? 
: 14. Does the calculation provide a clear statement of quality classifica t ion? [81 D D 15. Is the reason for performing and the end use of the calculation understood? 
[81 D D 16. Does the calculation provide the basis for information found in the plant's license D [81 D basis? This does not provide basis for license basis 17. If so , is this documented in the calculation?
D D [81 Page 1 of 5 CALC NEE-323-CALC-0 02 Attachment 1 NO. ENERCON CALCULAT I ON PREPARAT I ON &ce ll ence-E ve ry pr o ject. E very d ay. CHECKLIST REV. 0 CHECKLIST ITEMS 1 I YES I NO I N/A See above 18. Does the calcu l ation provide the basis for information found in the plant's design I D I D I basis documentation?
T his does not provide basis for design basis 19. I f so , is this documented in the calculation?
I D I D I See above 20. D oes the ca l cu l ation otherwise support information found in the p l ant's des i gn basis I D I I D d ocumentation?
This does not provide support for information found in design basis documentation 2 1. If so , is this documented in the calculation?
I D I D I See above 22. H as the appropriate design or l i cense basis documentation bee n rev i sed , or has the I D I D I change notice or change r equest documents be i ng prepared for subm i ttal? See above DES I G N IN PUTS I I I 23. Are design inputs clearly identified?
I I D I D 24. Are design i nputs retr i evable or h a v e they been added as attac h me n ts? I I D I D 25. If Attachments are used as design inputs or assumptions are the Attachments I I D I D traceable and ver i fiable? 26. Are design i nputs clearly distinguished from assumptions?
I I D I D 2 7. Does the calculation rely on Attac h ments for design inputs or assumptions?
I f yes , I I D I D are the attachments properly referenced in t h e ca l culation?
The Desig n Information Transmittal is included as an Attachment is proper l y referenced in the calcu l ation 28. Are input sources (including ind u stry codes and standards) appro p riately se l ected I I D I D and are they cons i stent with the quality classification and objecti v e of the calcu l ation? 2 9. Are in put sources (i nclud i ng i ndus t ry codes and standards) consistent wit h the p l ant's I I D I D design and l ice n se basis? 30. If applicable , do design i nputs adequately address actual plant conditions?
I I D I D 3 1. Are input values reasonable and correctly app li ed? I I D I D 32. A re design in p ut sources appro v ed? I I D I D The Design I nformation Transmittal co n t ai n s informatio n from a superseded calcu l atio n. 3 3. D oes the calcu l at i on reference the l atest re v is i on of the des i gn inp u t source? I I D I D The calculati o n uses information from a superseded ca l culat i on. This i n fo rmation is prov i ded in a Des i gn In formation Transm i tta l. 3 4. Were all applicab l e plant operating modes considered?
I I D I D ASS UMP T I O N S I I I P age 2 of 5 CALC NEE-323-CALC-00 2 Attachment 1 NO. ft' ENERCON CALCULAT I O N PREPARATION b c e lle nce-Ev e ry pr o je c t. Ev ery da y. CHECKLIST REV. 0 CHECKLIST ITEMS 1 YES NO N/A 35. Are assumptions reasonable/appropriate to the objective? 
[81 D D 3 6. Is adequate justification
/basis for a l l assumptio n s provided? 
[81 D D 3 7. Are any engineering judgments used? D [81 D Engineering judgement not used as design input. 3 8. Are engineer i ng judgments clear l y identified as such? D D [81 Engineering Judgement is not used as a des i gn input. 39. I f engineering judgments are uti l ized as design inputs , are they reasonable and can they be quantified or substantiated by reference to site or industry standards , D D [81 engineer i ng principles , physical laws or other appropriate criter i a? Engineering Judgement is not used as a design i nput. METHODOLOGY 
: 40. Is the methodology used in the calculation described or imp l ied in the plant's D D [81 licensing basis? The scope of calculation is outs i de of p l ant licensing basis 41. I f the methodo l ogy used differs from that described i n the plant's l icensing basis , has D D [81 t h e appropr i ate l icense document c h ange n o tice been initiated?
see above. 4 2. I s the methodology used consistent with the stated objective? 
[81 D D 43. Is the methodology used appropr i ate when cons i dering the qua l ity classificatio n of [81 D D t h e calculation a n d intended use of the r esults? BODY OF CALCULATIO N 44. Are equations used in the ca l culation consistent with recognized engineering practice [81 D D and the plant's design and license basis? 45. I s t h ere reasonab l e justification provided for the use of equations not in common D D [81 use? There are no uncommon equations used in the calculation. 46. Are the mathemat i cal op e rations performed properly and documented i n a l ogical [81 D D fashion? 47. I s the math performed correct l y? [81 D D 48. Have adjustment factors , uncerta in t i es and empirical correlat i ons used in the ana l ysis [81 D D bee n correctly applied? 49. H as proper c o nsideration been given to resu l ts that may be over l y sensitive to very [81 D D s m all changes in input? SOFTWAR E/COMP UT E R CODES 50. Are computer codes or software languages used in the preparat i on of the [81 D D ca l culation?
MCNP and Scale are u sed Page 3 of 5 CALC NEE-323-CALC-002 Attachment 1 NO. ENERCON CALCULAT I ON PREPARATION I CHECKLIST 
&ct lle nce-E ve ry pr o ject. E v ery day. REV. 0 CHECKLIST ITEMS 1 YES NO NIA 51. Have the requ i rements of CSP 3.09 for use of computer codes or software D D languages , inc l uding verification of accuracy and applicabi l ity been met? 52. Are the codes properly identified along with source vendor , organization , and revision D D level? 53. Is the computer code applicab l e for the ana l ysis being performed? D D 54. If applicable , does the computer model adequately consider actual plant conditions? D D 55. Are the inputs to the compu ter code clearly ident i fied and consistent with the inputs D D and assumptions documented in the calculation? 
: 56. Is the computer output clearly identified? D D 57. Does the computer output clear l y identify the appropriate units? D D 58. Are the computer outputs reasonable when compared to the inputs and what was D D expected? 
: 59. Was the computer output reviewed for ERROR or WARNING messages that could D D invalidate the resu l ts? RESULTS AND CONCL U S I ONS 60. I s adequate acceptance criteria specified?
D D There is no acceptance criteria as discussed in calc. 61. Are the stated acceptan ce criteria consistent with the purpose of the calculat i on , and D D intended use? See above 62. Are the stated acceptance cr i teria consistent w i th the plant's design basis , app l icable D D licensing commitments and industry codes , and standards?
See above 63. Do the calculation results and conclusions meet the stated acceptance criteria?
D D See above. 64. Are the results represent ed in the proper units with an appropriate tolerance, if D D applicable? 
: 65. Are the calculat i on results and conclusions reasonable when considered against the D D stated inputs and object ives? 66. I s sufficient conservatism appl i ed to the outputs and conclusions? D D Page 4 of 5 CALC NEE-323-CALC-002 Attachment 1 NO. ENERCON CALCULATION PREPARATION I CHECKLIST Exc, 1/e nc,-Ev e ,y P'*"* Every d oy. REV. 0 CHECKLIST ITEMS 1 YES NO N/A 67. Do the calculation results and conclusions affect any other calcu l ations? D D No other calculations are affected by this calculat i on. 68. If so , have the affected calculations been revised? D D No other calculat i ons are affected by th i s calculation. 69. Does the calculation conta i n any conceptual , unconfirmed or open assumptions D D requiring later confirmation?
There are no open assumptions requiring confirmation l ater. 7 0. If so , are they properly identified?
D D There are no open assumptions r equiring confirmation later. DESIGN REVIEW 71. Have alternate ca lcul ation methods been used to verify calculation results? D D No a Design Review was performed.
Note: 1. Where requ i red , provide clarification
/justification for answers to the questions in the space provided below each question.
An e x planation i s required for any questions answered as " No' or " N/A". Originator:
Jay Bhatt Print Name and Sign Date Page 5 of 5}}