ML21076A459
Text
CALC NO.
EPM028-CALC-001 ENERCON Potential Intake Calculation REV.
2 Excellence-Every pro;ect. Every day.
PAGE NO.
12 of 13
- U-234:
0.17% ALI
- U-235:
0.01% ALI
- Th-231:
<0.01% ALI
- U-238:
0.02% ALI
- Th-234:
<0.01% ALI
- Pa-234m:
<0.01% ALI
CALC NO.
EPM028-CALC-001 ENERCON Potential Intake Calculation REV.
2 Excellence-Every pro;ect. Every day PAGE NO.
13 of 13 8.0 Computer Software A Microsoft Excel spreadsheet was used to perform calculations discussed in this calculation.
CALC NO.
EPM028-CALC-001 f~ ENERCON Potential Intake Calculation REV.
2 hcelltmce-Every proJect /:.very dO}'
Uranium PAGE NO.
1 of 2 Attachment A - Potential Intake Calculation - Uranium EPM028-CALC-001 Assumptions More realistic calculation Specific Activity (5%
2.70E-06 Ci/g SA (1.5%)
l.00E-06 Ci/g enrich.)
Max GW concentration 5000 pCi/L 5.00E-06
µCi/ml Oral Intake ALI l.00E+0l
µCi Consumption for 2% ALI 40.00 L
Consumption for 1 ALI 2000.00 L
Spent resin loading Site limit for U-235 1200 g
Max U235 500 g
Total U assume 5%
2.40E+04 g
U(l.5%)
3.33E+04 g
NUREG-1400 Methodology Total activity per resin 6.48E-02 Ci 6.48E+04
µCi 3.33E-02 Ci 3.33E+04
µCi bed Total activity (Q) (12 7.78E-01 Ci 7.78E+05
µCi 4.00E-01 Ci 4.00E+05
µCi bed/y)
Is Q > 1E+04 ALI?
7.78E+04 YES 4.00E+04 YES
CALC NO.
EPM028-CALC-001
~3 ENERCON Potential Intake Calculation REV.
2 Excellence-Every proJecr hcry day Uranium PAGE NO.
2 of 2 Potential Intake (Ip)
Ip= Q x lE-06 x R x C xD Total activity (Q) (12 7.78E+0S
µCi 4.00E+0S
µCi bed/y)
Release Fraction (R) 0.01 Nonvolatile Powder 0.01 Nonvolatile Powder Confinement Factor (C) 0.1 Well-ventilated Glovebox would be 0.1 Well-ventilated hood 0.01 hood Dispersibility (D) 0.1 Moist resin 0.1 Moist resin Potential Intake (IP) 7.78E-05
µCi 4.00E-05
µCi
%ALI 0.19%
0.10%
Chemical Intake Potential Intake (Ip) 7.78E-05
µCi 4.00E-05
µCi Mass intake per year 2.88E-05 g
2.88E-02 mg 4.00E-05 g
4.00E-02 mg Limit per week 10 mg 10 mg Percentage of weekly 0.3%
0.4%
mass limit Drinking 3000
µg/L 3000
µg/L Volume per week 3.33E+00 L
3.33E+00 L
CALC NO.
EPM028-CALC-001
~,~ ENERCON Potential Intake Calculation REV.
2 l:xceilence-Every proJect. t.'Very day Tc-99 PAGE NO.
1 of 2 Attachment B - Potential Intake Calculation - Tc-99 EPM028-CALC-001 Assumptions Groundwater activity 582 pCi/L Groundwater flow 130 gpm Groundwater vol/year 6.83E+07 gallons Coversion 3.785 L/g NUREG-1400 Methodology Tc-99 Activty/y l.51E+ll pCi l.51E+05
µCi ALI 7.00E+02
µCi Is Q > 1E+04 ALI?
2.15E+02 NO Potential Intake (Ip)
Ip= Q x lE-06 x R x C x D Release Fraction (R) 1 No credit taken Confinement Factor (C) 1 No credit taken Dispersibility (D) 0.1 Moist resin and bio-solids Potential Intake (Ip) l.51E-02
µCi
%ALI 0.22%
CALC NO.
EPM028-CALC-001 (0 ENERCON Potential Intake Calculation REV.
2 Excellcna**-Every oroJ~cr Every aoy Tc-99 PAGE NO.
2 of 2 Oral Intake Groundwater activity 582 pCi/L Oral ALI 4.00E+03
µCi Consumption for 2% ALI l.37E+0S L
Consumption for 1 ALI 6.87E+06 L
Consumption per day 3.77E+02 L/day for 365 days/y (2%)
Consumption per day l.88E+04 L/ day for 365 days/y (ALI)
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EPM028-CALC-001
~ ENERCON Sensitivity Analysis REV.
2 Excellence--Evt!tv proJ<!Ct. fvt'ry aa; PAGE NO.
1 of 2 Sensitivity Analysis - 5% enrichment Assumptions 6.48E-02 Ci Total Li-activity in one spent resin bed Activity % of U-234 in 87.1%
U-234 Uranium Activity % of U-235 in 3.3%
U-238 Activity % of U-238 in Uranium 5.64E-02 Ci U-234 ALI 4.00E-02
µCi 2.12E-03 Ci U-235 ALI 4.00E-02
µCi 2.12E-03 Ci Th-231 ALI 6.00E+03
µCi 6.26E-03 Ci U-238 ALI 4.00E-02
µCi 6.26E-03 Ci Th-234 ALI 2.00E+02
µCi 6.26E-03 Ci Pa-234m ALI 7.00E+03
µCi U-234 U-235 Th-231 U-238 Th-234 Pa-234m Total activity per resin bed
µCi 5.64E+04 2.12E+03 2.12E+03 6.26E+03 6.26E+03 6.26E+03 Total activity (Q) (12 bed/y)
µCi 6.77E+05 2.55E+04 2.55E+04 7.52E+04 7.52E+04 7.52E+04 Q/ALI 1.69E+07 6.37E+05 4.24E+00 1.88E+06 3.76E+02 1.07E+0l Is Q > 1E+04 ALI?
YES YES NO YES NO NO
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EPM028-CALC-001 0 ENERCON Sensitivity Analysis REV.
2 Excellence*-Every pro;ect. f.vP.ry day PAGE NO.
2 of 2 Potential Intake (Ip= Q x lE-06 x Rx C x D)
Total activity (Q) (12 bed/y)
µCi 6.77E+0S 2.SSE+04 2.SSE+04 2.SSE+04 7.52E+04 7.52E+04 7.52E+04 Nonvolatile Release Fraction (R)
Powder 0.01 0.01 0.01 0.01 0.01 0.01 0.01 Well-ventilated Confinement Factor (C) hood 0.1 0.1 0.1 0.1 0.1 0.1 0.1 Dispersibility (D)
Moist resin 0.1 0.1 0.1 0.1 0.1 0.1
- 0. 1 Potential Intake (Ip)
µCi 6.77E-05 2.SSE-06 2.SSE-06 2.SSE-06 7.52E-06 7.52E-06 7.52E-06 Fraction of ALI 1.69E-03 6.37E-05 4.24E-10 1.27E-03 1.88E-04 3.76E-08 1.07E-09 Percent ALI 0.17%
0.01%
0.00%
0.13%
0.02%
0.00%
0.00%
Activity Fraction Determination Enrichment Activity Fraction DOE-STD-1036-2009 Ex. 3a Specific Activity U-234 2.30E+08 Bq/g 0.05%
87.06%
DOE-STD-1036-2009 Ex. 3a U-235 79312 Bq/g 5.00%
3.27%
DOE-STD-1036-2009 Ex. 3a U-238 12329 Bq/g 94.95%
9.67%
CALC NO.
EPM017-CALC-001 ENERCON CALCULATION PREPARATION CHECKLIST REV.
Excellence-Every pro1ect Every doy.
PAGE NO.
CHECKLIST ITEMS1 GENERAL REQUIREMENTS
- 1.
If the calculation is being performed to a client procedure, is the procedure being used the latest revision?
Client procedure is not used in this calculation. ENERCON QA procedures used throughout this project.
- 2.
Are the proper forms being used and are they the latest revision? Same format matching EPM017-CALC-001 was used for internal consistency
- 3.
Have the appropriate client review forms/checklists been completed?
Client procedure is not used in this calculation. ENERCON QA procedures used throughout this project.
- 4.
Are all pages properly identified with a calculation number, calculation revision and page number consistent with the requirements of the client's procedure?
Client procedure is not used in this calculation. ENERCON QA procedures used throughout this project.
- 5.
Is all information legible and reproducible?
- 6.
Is the calculation presented in a logical and orderly manner?
- 7.
Is there an existing calculation that should be revised or voided?
- 8.
Is it possible to alter an existing calculation instead of preparing a new calculation for this situation?
No current ENERCON calculations exist that are similar to this calculation.
- 9.
If an existing calculation is being used for design inputs, are the key design inputs, assumptions and engineering judgments used in that calculation valid and do they apply to the calculation revision being performed.
- 10.
Is the format of the calculation consistent with applicable procedures and expectations?
- 11.
Were design input/output documents properly updated to reference this calculation?
No ENERCON design inputs or outputs are affected by this calculation.
2 1 of 7 YES NO N/A
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CHECKLIST ITEMS1
- 12.
Can the calculation logic, methodology and presentation be properly understood without referring back to the originator for clarification?
OBJECTIVE AND SCOPE
- 13.
Does the calculation provide a clear concise statement of the problem and objective of the calculation?
- 14.
Does the calculation provide a clear statement of quality classification?
- 15.
Is the reason for performing and the end use of the calculation understood?
- 16.
Does the calculation provide the basis for information found in the plant's license basis?
This calculation applies to a remediation site. No work performed in this calculation is applicable to a licensing basis.
- 17.
If so, is this documented in the calculation?
- 18.
Does the calculation provide the basis for information found in the plant's design basis documentation?
- 19.
If so, is this documented in the calculation?
- 20.
Does the calculation otherwise support information found in the plant's design basis documentation?
- 21.
If so, is this documented in the calculation?
- 22.
Has the appropriate design or license basis documentation been revised, or has the change notice or change request documents being prepared for submittal?
DESIGN INPUTS
- 23.
Are design inputs clearly identified?
- 24.
Are design inputs retrievable or have they been added as attachments?
EPM017-CALC-001 2
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CALC NO.
ENERCON CALCULATION PREPARATION CHECKLIST REV.
Excp//ence--Every pro1ect. Every day.
PAGE NO.
CHECKLIST ITEMS1
- 25.
If Attachments are used as design inputs or assumptions are the Attachments traceable and verifiable? MS Excel spreadsheet was used to perform the calculation. All equations are provided in the calculation.
- 26.
Are design inputs clearly distinguished from assumptions?
DESIGN INPUTS (Continued)
- 27.
Does the calculation rely on Attachments for design inputs or assumptions? If yes, are the attachments properly referenced in the calculation?
- 28.
Are input sources (including industry codes and standards) appropriately selected and are they consistent with the quality classification and objective of the calculation?
- 29.
Are input sources (including industry codes and standards) consistent with the plant's design and license basis?
- 30.
If applicable, do design inputs adequately address actual plant conditions?
- 31.
Are input values reasonable and correctly applied?
- 32.
Are design input sources approved?
The Cimarron design is currently at 60% completion.
- 33.
Does the calculation reference the latest revision of the design input source?
- 34.
Were all applicable plant operating modes considered?
ASSUMPTIONS
- 35.
Are assumptions reasonable/appropriate to the objective?
- 36.
Is adequate justification/basis for all assumptions provided?
- 37.
Are any engineering judgments used?
EPM017-CALC-001 2
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CALC NO.
ENERCON Excellence-Every pro_1ect. Every doy.
CALCULATION PREPARATION CHECKLIST REV.
PAGE NO.
CHECKLIST ITEMS1
- 38.
Are engineering judgments clearly identified as such?
Engineering judgement applied to factors used in potential intake calculation using NUREG-1400 methodology.
- 39.
If engineering judgments are utilized as design inputs, are they reasonable and can they be quantified or substantiated by reference to site or industry standards, engineering principles, physical laws or other appropriate criteria?
METHODOLOGY
- 40.
Is the methodology used in the calculation described or implied in the plant's licensing basis?
- 41.
If the methodology used differs from that described in the plant's licensing basis, has the appropriate license document change notice been initiated?
- 42.
Is the methodology used consistent with the stated objective?
- 43.
Is the methodology used appropriate when considering the quality classification of the calculation and intended use of the results?
BODY OF CALCULATION
- 44.
Are equations used in the calculation consistent with recognized engineering practice and the plant's design and license basis?
- 45.
Is there reasonable justification provided for the use of equations not in common use?
Equations applied in this evaluation are in common use in the industry.
- 46.
Are the mathematical operations performed properly and documented in a logical fashion?
- 47.
Is the math performed correctly?
- 48.
Have adjustment factors, uncertainties and empirical correlations used in the analysis been correctly applied?
- 49.
Has proper consideration been given to results that may be overly sensitive to very small changes in input?
Results generated by calculations performed in this evaluation are not significantly affected by minor perturbations of variables.
EPM017-CALC-001 2
4 of 7 YES NO N/A lXI lXI lXI lXI lXI lXI lXI lXI lXI lXI lXI lXI
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ENERCON Exceilence-Every proJect. Every day.
CALCULATION PREPARATION CHECKLIST REV.
PAGE NO.
CHECKLIST ITEMS1 SOFTWARE/COMPUTER CODES
- 50.
Are computer codes or software languages used in the preparation of the calculation?
- 51.
Have the requirements of CSP 3.09 for use of computer codes or software languages, including verification of accuracy and applicability been met?
SOFTWARE/COMPUTER CODES (Continued)
- 52.
Are the codes properly identified along with source vendor, organization, and revision level?
- 53.
Is the computer code applicable for the analysis being performed?
- 54.
If applicable, does the computer model adequately consider actual plant conditions?
- 55.
Are the inputs to the computer code clearly identified and consistent with the inputs and assumptions documented in the calculation?
- 56.
Is the computer output clearly identified?
- 57.
Does the computer output clearly identify the appropriate units?
The output units are not identified in the output document. Tallies have been modified through multipliers and dose response functions. This process has been adequately documented within this calculation.
- 58.
Are the computer outputs reasonable when compared to the inputs and what was expected?
Only basic functions and operations in Microsoft Excel 2013 were applied in this calculation.
- 59.
Was the computer output reviewed for ERROR or WARNING messages that could invalidate the results?
RES UL TS AND CONCLUSIONS
- 60.
Is adequate acceptance criteria specified?
No acceptance criteria required for this evaluation.
EPM017-CALC-001 2
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CHECKLIST ITEMS1
- 61.
Are the stated acceptance criteria consistent with the purpose of the calculation, and intended use?
- 62.
Are the stated acceptance criteria consistent with the plant's design basis, applicable licensing commitments and industry codes, and standards?
- 63.
Do the calculation results and conclusions meet the stated acceptance criteria?
- 64.
Are the results represented in the proper units with an appropriate tolerance, if applicable?
- 65.
Are the calculation results and conclusions reasonable when considered against the stated inputs and objectives?
- 66.
Is sufficient conservatism applied to the outputs and conclusions?
- 67.
Do the calculation results and conclusions affect any other calculations?
No ENERCON calculations are affected by this evaluation.
- 68.
If so, have the affected calculations been revised?
- 69.
Does the calculation contain any conceptual, unconfirmed or open assumptions requiring later confirmation?
- 70.
If so, are they properly identified?
DESIGN REVIEW
- 71.
Have alternate calculation methods been used to verify calculation results?
Note:
EPM017-CALC-001 2
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- 1. Where required, provide clarification/justification for answers to the questions in the space provided below each question. An explanation is required for any questions answered as "No' or "N/A".
ENERCON Excellence-Every pro1ect. Every day Originator:
CALCULATION PREPARATION CHECKLIST Jay Maisler Print Name and Sign CALC NO.
EPM017-CALC-001 REV.
2 PAGE NO.
7 of 7 12/12/2019 Date
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Cimarron Environmental Response Trust environmenta Radiation Protection Plan properties management. LLC Document No. RPP-001 Rev. 4 Effective date:
Appendix B Page B-1 APPENDIX B DOSE RA TE NEAR URANIUM TREATMENT TRAIN (EPM017-CALC-001)
CALC NO.
EPM017-CALC-001 ENERCON CALCULATION COVER SHEET REV.
0 Excelfence--Every projecr. Every day.
PAGE NO.
1 of 15 Client:
Cimarron Environmental
Title:
Dose Rate Near Uranium Treatment Train Response Trust Project Identifier:
EPM017 Item Cover Sheet Items Yes No 1
Does this calculation contain any open assumptions, including preliminary
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information, that require confirmation? (If YES, identify the assumptions.)
2 Does this calculation serve as an "Alternate Calculation"? (If YES, identify the
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design verified calculation.)
Design Verified Calculation No.
3 Does this calculation supersede an existing Calculation? (If YES, identify the
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design verified calculation.)
Superseded Calculation No.
Scope of Revision:
Initial Issue Revision Impact on Results:
Initial Issue Study Calculation Final Calculation ~
Safety-Related Non-Safety-Related ~
(Print Name and Sign)
Originator: Caleb Trainor 1/
Date:
12/21/2015
'.. _.;_,,.~r, l.*.
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Date:
12/23/2015 Design Reviewer: John Hawkinson Approver: Jay Maisler, CHP
!Pl~
Date:
12/23/2015 CSP 3.03 Revision 1 Attachment A
ENERCON Excellenn~-Every project Every doy.
REVISION 0
PAGE NO.
CALC NO.
EPM017-CALC-001 CALCULATION REVISION STATUS SHEET REV.
PAGE NO.
CALCULATION REVISION STATUS DATE 12/21/2015 PAGE REVISION STATUS REVISION PAGE NO.
DESCRIPTION Initial Issue 0
2 of 15 REVISION APPENDIX/ATTACHMENT REVISION STATUS APPENDIX NO.
NO.OF PAGES REVISION NO.
ATTACHMENT NO.
NO.OF PAGES REVISION NO.
CSP 3.03 Revision 1 Attachment B
CALCULATION TABLE OF CONTENTS I
ENERCON Excellence*-Every pro;ect. Every day.
Section
1.0 Purpose and Scope
TABLE OF CONTENTS 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 List of Attachments MCNP6 Input Email Correspondence MCNP6 Output CALC NO.
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1.0 Purpose and Scope
The purpose of this calculation is to determine the radiation level surrounding a resin vessel array used to extract uranium contamination from groundwater at the Cimarron Site, hereby referred to as a uranium treatment train. The results of this calculation represent the highest anticipated dose rate an individual would be subject to while in the close vicinity of a uranium treatment train.
2.0 Summary of Results and Conclusions The highest anticipated dose rate in the vicinity of a uranium treatment train is calculated to be 0.024 mrem/hr.
3.0 References 3.1 MCNP6-1.0, Revision 00, MCNP6 Version 1.0 Acceptance Report, November 2014 3.2 LA-CP-13-000634, MCNP6 User's Manual, Version 1.0, May 2013 3.3 MicroShield 6.20 3.4 DTS-WPS-M-3100, AVANTech Drawing, '48" Process Vessel', Rev B, January 10, 2000 3.5 Vessel Use and U235 Accum Calc_DRAFT _ 16Oct15.xlsx, Vessel loading analysis provided as an Excel spreadsheet 3.6 PNNL-15870, Rev. 1, Compendium of Material Composition Data for Radiation Transport Modeling, March 4, 2011 3.7 Email correspondence with Kurian representative (attached) 3.8 BA 1 Isotopic Data for Enercon.xlsx, Isotopic abundance of Uranium source provided as an Excel spreadsheet 3.9 NUREG/BR-0150, Vol. 1, Rev. 4, RTM-96 Response Technical Manual, March 1996 3.10 Introduction to Health Physics, 4th ed., Herman Cember and Thomas E. Johnson, McGraw-Hill, 2009.
4.0 Assumptions 4.1 The resin vessel is approximated as a perfect right circular cylinder, maintaining the actual volume and clad thickness of the vessel. This is a minor simplification made for modeling purposes and is insignificant to the final dose rate.
4.2 The resin vessel is modeled as stainless steel 304. At the time of this calculation, the vessel was known to be composed of stainless steel, but the specific alloy was
CALC NO.
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5 of 15 unknown. Stainless steel 304 was chosen as it is a popular alloy for nuclear vessels. The specific alloy of stainless steel has insignificant impact on shielding.
4.3 The mass of uranium assumed to be present in the resin vessels is based off of a draft calculation provided for this study. The calculation is performed in Excel spreadsheet "Vessel Use and U235 Accum Calc_DRAFT _ 16Oct15.xlsx" (Reference 3.5). From this calculation, the largest expected mass accumulation of uranium is 24,055 g of uranium at Burial Area 1 (BA 1) after the first full loading. The theoretical capacity of the resin used for the calculation is 29,589.01 grams.
The vessel loading calculations use an enrichment of 2% by weight. This value was chosen as a conservative bound for the actual 1.66% enrichment in order to remain conservative with respect to materials controls. The resin loading is not dependent on enrichment and the input values used in this calculation are not affected by this assumption.
4.4 The lead vessel is modeled assuming it is completely full to its theoretical capacity, ready to be removed and replaced with the lag vessel. The lag vessel is assumed to accumulate one week's worth of uranium, due to a one week period between sampling intervals. The accumulation in the first week of loading in the lead vessel is used to define one week's worth of accumulation. This is conservative as the uranium loading rate decreases with time; as the concentration of contaminants in the fluid passed through the vessels decreases, the resin removes a lower volume of uranium. The polishing vessel is assumed to provide negligible dose rate contribution due to the significant distance and low accumulation of uranium.
4.5 The uranium is assumed to be evenly distributed through the resin vessel.
4.6 The DOWEX-1 resin is approximated as polystyrene. For shielding purposes, this media is roughly equivalent. The mass of resin used is provided in Reference 3.5.
The resin is assumed to fill the vessel and is homogenized, while maintaining mass, for modeling purposes.
4.7 The shielding provided by the vessel clad and resin are modeled. The shielding which would be provided by the water and additional piping inside the vessel has been omitted. Miscellaneous piping and structures outside the vessels are also omitted. The lack of additional shielding provides a conservative estimate, which results in a higher estimation of dose rate.
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6 of 15 4.8 All alpha and beta particles are shielded by the 3/8 inch stainless steel walls of the resin vessel and do not contribute to the final dose rate.
4.9 The spontaneous fission rate for the uranium isotopes is sufficiently low (3.5 n/s per kg U-234, 0.31 n/s per kg U-235 and 7.0 n/s per kg U-238) that the neutron dose rate can be disregarded.
5.0 Design Inputs 5.1 Resin Vessel Properties The following properties are taken from Reference 3.4.
The following properties are taken from Reference 3. 7.
Vessel Diameter=48 in Volume=54.5 ft3 Vessel Clad=3/8 in Vessel Spacing=48 in (96 in on center) 5.2 Source Characteristics The following source characteristics are taken from Reference 3.5 Media Capacity=39.52 g U/kg Media Mass used=748.7 kg The following isotopic abundances by mass percent are taken from Reference 3.8.
U234= 0.01 U23s=
1.66 U23a= 98.33 The following specific activities are taken from Table E-4 of Reference 3.9.
5.3 Material Definitions U234= 6.19 E+03 µCi/g U23s= 2.14 E+00 µCi/g U23a= 3.33 E-01 µCi/g The following material definitions are taken from Reference 3.6.
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7 of 15 Table 5.1: Composition of Polystyrene (Density homogenized to 0.485139 glee)
Nuclide Weight Fraction Hydrogen 0.077421 Carbon 0.922579 Table 5.2: Composition of Stainless Steel 304 (Density of 8.0 glee)
Nuclide Weight Fraction Carbon 0.000400 Silicon 0.005000 Phosphorus 0.000230 Sulphur 0.000150 Chromium 0.190000 Manganese 0.010000 Iron 0.701730 Nickel 0.092500 5.4 Resin Vessel Loading The first week's loading of the resin vessel is 3,706 grams of uranium. After the first full loading, the vessel contains 24,055 grams of uranium. These values are taken from Reference 3.5.
6.0 Methodology 6.1 Source Term The activity by isotope is determined using the mass abundance of each isotope from Reference 3.8 and applying the specific activities from Reference 3.9. These activities are entered into MicroShield 6.20 (Reference 3.3) to produce a list of gamma emission energies and activity in photons per second. These energies correspond to the energy bins defined in the MCNP6 (Reference 3.2) source term distribution. The activity in photons per second correspond to the energy distribution probabilities defined in the MCNP6 source term.
6.2 Shielding Evaluation The MCNP6 code is used to model the resin vessel and cylindrical source term inside the vessel. The interior of the vessel is modeled as homogenized polystyrene. Outside of the vessel is comprised of dry air, characteristic of near sea level. Two point detectors used, one located mid height of the vessel, 12 inches (30.48 cm) from the outer surface of the vessel and another located 96 inches
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8 of 15 (283.84 cm) offset laterally. The first detector represents the dose rate contribution from the modeled vessel (the lead vessel), the second detector represents the dose rate contribution from the lag vessel. Figures 6.1 and 6.2 are representative of the MCNP6 input.
tl ENERCON l::xcellence-Every pro1ect. Every day.
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Figure 6.1: Z-plane of Modeled Geometry L
Cross section of z-plane
@ 69.19745cm Detector F25............ *
(91.43,243.84, 69.19745)
Cylindrical resin vessel centered at (0,0,0).
Inner radius =600075cm Outer radius=60.9600cm 0 uter Clad layer
\\
lnner\\..C.,.laddl!lla!!y!!er~ !!f~
I I
I I
Y=O
... ------------- - - -- -- - ----.-* ~ ----------------........ -...... -...... -...
Detector F 15 (91.43,0,69.19745) l 0
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10 of 15 Figure 6.2: Y-Plane of Modeled Geometry o
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Cylindrical resin vessel centered at (0,0,0).
inner radius=60. 0075cm Outer radius=60.9600cm Z=138.3949 z
X Cross section of y-ptane @ 0cm Detector F 15 (91.43000,0, 69.19745)
Z=O
-~~~~~~:;;;;~~:;;;;;;~;;;;;;;;;;~~;:;.;;~ _ -- -- - ---- -----*---------
7.0 Calculation 7.1 Source Development The activity of each isotope is found using the Equation 7.1.
Equation 7. 1
I CALC NO.
EPM017-CALC-001 ENERCON Dose Rate Near Uranium REV.
0 Excellence--Every pro1ect. /:.very day Treatment Train PAGE NO.
11 of 15 Where Ai is equal to activity of each isotope, in µCi, Ui is the mass of uranium isotope i, and SA is equal to the specific activity of uranium isotope i.
The mass of each isotope in a full resin vessel is found using Equation 7.2.
U;(g) = Media capacity (Uk~))* Media mass (kg)* w; Equation 7. 2 Where Wi represents the isotopes abundance by weight percent. Solving for the three isotopes;
( U(g))
U234(g) = 39.52 ~
- 748.7 (kg)* 0.0001 = 2.958 g U234
( U(g))
U235 (g) = 39.52 ~
- 748.7 (kg)* 0.0166 = 491.177 g U235 U238(g) = 39.52 (\\~))
- 748.7 (kg)* 0.9833 = 29094.873 g U238 Using these values, and the specific activities defined in Design Input 5.2, Equation 7.1 is solved for the three isotopes;
( µCi)
Au
= 2.958 (g)
- 6190 -
= 1.83
- 104 µCi 234 g
( µCi)
Au
= 491.177 (g)
- 2.140 -
= 1.05
- 103 µCi 235 g
( µCi)
Au = 29094.873(g)
- 0.333 -
= 9.69
- 10 3 µCi 238 g
With the activities determined, MicroShield 6.20 is used to define gamma emission energies and emission frequencies. The MicroShield output is listed in Table 7.1.
CALC NO.
EPM017-CALC-001 ENERCON txceflence--Every project. Every day Dose Rate Near Uranium Treatment Train REV.
PAGE NO.
Table 7.1: Gamma Emissions from Uranium source Energy (MeV)
Activity (Photons/sec) 0.013 7.112E+07 0.013 3.166E+07 0.013 1.201 E+07 0.0532 7.990E+05 0.0664 3.478E+05 0.0727 4.273E+04 0.09 1.060E+06 0.0933 1.732E+06 0.105 8.014E+05 0.1091 5.827E+05 0.12 5.827E+04 0.1214 2.712E+05 0.1408 8.547E+04 0.1438 4.079E+06 0.1633 1.826E+06 0.1827 1.554E+05 0.1857 2.098E+07 0.1904 3.572E+05 0.1949 2.292E+05 0.2021 3.885E+05 0.2053 1.826E+06 0.2214 3.885E+04 7.2 MCNP6 Input Development 7.2.1 Geometry Specifications 0
12 of 15 The only resin vessel modeled is the lead vessel. Since the lead vessel accumulates the most uranium, the area of interest is directly in front of the lead vessel. A detector is placed halfway up the vessel, 12 inches (30.48 cm) from the outer surface of the vessel. To model the dose rate contribution from the lag vessel, a second detector is placed at the same height, offset laterally by 96 inches (283.84 cm). The inner and outer clad layers represent the vessel clad, seperated into two layers for variance reduction purposes.
CALC NO.
EPM017-CALC-001 ENERCON Exceilence--Every pro jeer. Every day.
Dose Rate Near Uranium Treatment Train REV.
0 PAGE NO.
13 of 15 The geometry between the modeled vessel and the second detector is equivalent to the geometry between the lag vessel and the dose rate point of interest. The second detector tally will be scaled accordingly to represent the source term which would be present in the lag vessel.
The lead vessel is modeled using two concentric right circular cylinders with a separation of 3/8 inches around the top, sides, and bottom. The dimensions of the interior cylinder are calculated, preserving the defined vessel volume and diameter.
Vol= hi* rrr/
Equation 7. 4 Where; Vol = 54.5 f t 3 D - (2
- clad) 48 in. -(2 * ! in. )
r -
- ------ = 23.625 in i-2 2
Solving for hi; in3 54.5 ft 3
- 1728 ft3 hi = 3.14159 * (23.625 in) 2 = 53*7362 m The clad thickness is accounted for in the dimensions for the outer cylinder in the following equations.
h0 = hi + 2
- Clad
= 53.7362 in+ 2
- 3/8 in= 54.4862 in
= 23.625 in+ 3/ 8 in= 24 in For variance reduction purposes, a third right circular cylinder is included.
This cylinder divides the vessel clad into two equal layers, shown as the "inner clad layer" and "outer clad layer" in Figures 6.1 and 6.2. The following excerpt from the MCNP6 input deck shows the cell and surface cards which define the geometry described above.
CALC NO.
EPM017-CALC-001
. ENERCON Excellence--- Every project. Every day.
Dose Rate Near Uranium Treatment Train REV.
0 PAGE NO.
14 of 15 Figure 7.1 : Cell and Surface Cards from Input Deck C cell ls 10 2 - 0.485139 - 100 50 1 10 100 11 1 10110100 30 0 - 300 101 40 0 300 c s ur faces i mp, : p=l i mp: p,=2 i mp: p=4 imp,: p=B i mp: p,=0 100 RCC O O 0.9525 0 0 136.4899 60.0075 10 RCC O O 0.47625 0 0 136. 966,15 60.46375 101 RCC O O O O O 138. 3949 60. 96, 102 s 91-43 0 69.. 19745 20 103 S 91.4 3 243. 84 69. 19745 20 300 RPP - 65 100 - 65 250 0 150 7.2.2 Source Definition
$Resi n (polystyrene) i nside vessel
$ss 304 71 ayer
$55 304 vesse 1 cl ad
$Void
$Bo ndary
$Interior cylinder of r e,sin vessel.
$Layer used! for vari ance r eduction
$out:er cylinder of r esin vessel
$Detector 1 void
$Detector 2 void
$Bmmdi ng Area The source is defined as a photon source, evenly distributed within a right circular cylinder equivalent to the interior cylinder of the resin vessel. The values in Table 7.1 are used to define the energy and probability of gamma particles in this area. The terms axs, pas, rad, and ext define the vector, base position, radius and height of the source term respectively.
Figure 7.2: Source Definition from Input Deck c sour ce [)efinit:ion SDEIF IPA.R.= IP axs=O O 1 pos=O O O rad=dtll. ex"E:=d2 erg= c.13 cel =10 s:n o 60.007 5
$cylindr i cal! source located i ns ide inner cyli nder SI2 0.9525 137.4424 SI3 L. O.B.OB.013.0532.0664.0727.09.0933.105
.1091. 12.1214. 1408.1438.1633.1827.1657.1904
.1949.2021.2053. 2214
$Discrete energy distdlbution based on ga a energies fro Microshielld SP3 7_ U.2e 3.166e7 1.201e7 7. 990e5 3.478e5 4.273e4 1.060e6
- 1. 732e6 8.014e5 5. 827e5 5. 827e4 2. 712e5 8. 54 7e.4 4. 079e6 1.S26e6 1.554e5 2.098e7 3. 572e5 2.292e5 3.885e5 1.826e6 3.885e4 7.2.3 Tally Definitions
$Gamma emi ssi on frequency fro Microshielld Two tallies are used to find the total dose rate. The first tally is located mid height and one foot away from the modeled lead resin vessel. The second tally is located in the equivalent position on the lag resin vessel (not modeled). Using these tallies, the total dose rate is equal to the summation of the first and second tally.
A tally multiplier of 1.504 E+08 is applied to the first tally. This value is equal to the summation of column 2 of Table 7.1 and scales the results to the source strength. A tally multiplier of 2.568 E+07 is applied to the second tally.
This is approximately 15% of the source strength used for the first tally. This tally represents the dose rate contribution of the lag vessel, acting as the primary resin vessel for one week's time per Assumption 4.4. A ratio of 15%
ENERCON Excellence-Every pro1ect. E.very day.
Dose Rate Near Uranium Treatment Train CALC NO.
EPM017-CALC-001 REV.
0 PAGE NO.
15 of 15 is equivalent to the ratio of the first weeks vessel loading compared to a fully loaded vessel. The values from Design Input 5.4 are used to determine this ratio.
An MCNP6 dose response function is also applied to all tallies. This function sorts the tallies into energy bins, applies dose conversion factors from ANSI 6.1.1-1977, and sums all the bins. Due to the tally multiplier and dose function, the output of the tallies is in rem per hour. Figure 7.3 shows the tally definitions from the input deck.
Figure 7.3: Tally Definitions from Input Deck c Ta1liy oefi nit:ion
$Poi nt: Detector, mid height: of vesse 1
- one foot away F15:p 91.43 0 69. 19745 10 F25:p 91.43 243. 84 69. 19745 10 C
FM15 L 5045072E:6 FM25 2. 2567608e7 C
$Point. Det:ect:or, mid' height of vessel. one foot: a\\ri*ay, 96" offset:
$equi va l ent: to dose. contribution frr l ag vessel!
$Tallly mul!t:iplierr equi valem: t:o S l.l t i on of all l ga a
ission f r equencies
$source scaled to one teek of buildup i n l ag vessel!
c A~S:I 6.1. 1 - 1977 Garr.
1Fll t.1x t:o Dose conversion Factors. using us uni ts c
( re.m/ hr ) / (phot:ons / cm2-s )
dfO n i 1 IC 20
$seperat:es tal ly into ener gy bins, app*lies conversion factors and s ums 7.3 Dose Rates The estimated dose rates present near the uranium treatment train are presented in Table 7.2.
Table 7.2: Dose Rate Tank Contribution Equivalent Tally Dose Rate (rem/hr)
Lead tank F15 2.392 E-05 Lag tank F25 4.974 E-07 Total Dose Rate 2.442 E-05 (.02442 mrem/hr) 8.0 Computer Software MCNP6 is used for shielding analysis in this calculation. It is verified and validated for use (Reference 3.1 ).
MicroShield 6.20 is used for calculating gamma emission energies and frequencies.
CALC NO.
EPM017-CALC-001 ENERCON Excellence-Every project Eve1y day.
Dose Rate Near Uranium Treatment Train REV.
0 Attachment A MCNP6 Input
- Cimmarron Resi n Bed c ce11s 10 2 - 0. 485139 -100 50 1 10 100 11 1 101 10 "100 30 0 -300 101 40 0 300 c surfaces Dose Estimation imp p=l i mp p=2 imp p--4 imp p=8 i,mp p=O 100 RCC O O 0.. 952 5 0 0 136. 4 899 60. 007 5 10 RCC O O 0. 47625 0 0 136. %615 60. 4 837 5 101 RCC O O O O O 1.38. 3949 60. 96 102 s !U. 43 0 69.19745 20 103 S 91. 43 243. 84 69. 1974 5 20 300 RPP -65 100 - 65 250 0 150 c Dat:a Mode P nps 10e6 C
c Mat:eri al Def i nit:i ons Ml 6000 - 0.000400 14000 -0.005000 15000 -0.000230 16000 - 0.000150 24000 - 0.190000 25000 -0.010000 26000 - 0. 701730 28000 *- 0. 092500 M2 1000 - 0.077421 6000 - 0.922579 C
c source Def i nition SDEF PAR=P axs=O O 1 pos=O O O rad=dl ext=d2 erg=d.3 cel=10 SU O 60. 0075 SI2 0. 952 5 137. 4424 SI3 L 0. 13. 013. OB. 0532. 0664. 0727. 09. 093.3.105
.1091.12.1214. 1408. 1438.16.33. 1827. 1857. 1904
.1949. 2021. 2053. 2214 SP3 7.U2e7 3. 166e7 1.201e7 7.990e5 3. 4 78e5 4.273e4 1.060e6
- 1. 732e6 8. 014e5 5. B27e5 5. 827e4 2. 712e5 8. 547e4 4. 079e6 1.826e6 1.554e5 2. 098e7 3. 572e5 2.292e5 3.885@5 1. 826e6 3.885e4 C
C Tally Definition F15:p 91.43 0 69.19745 10 F25:p 91. 43 243. 84 69.19745 10 C
FM15 l.5045072E8 FM25 2. 2567608e7 C
PAGE NO.
$Resin (pol ystyrene) i nsi de vessel
$SS.304 layer
$SS 304 vessel clad
$Void
$BOlmdary 1 of 1
$Interior cylinder of r esi n vessel
- 3/ 8" (O. 9525orn) off of f l oor to accomodat:e vessel clad
$Layer used for vari ance reduction
$Outer cyl inder of r esi n vessel
$Detector 1 void
$Detector 2 void
$Boundi ng Area
$SS 304
$Polystyr ene
$Cylindriical sour ce l ocated i nside i nner cyl inder
$Discrete energy distribution based on gamma energi es from Microshiel d
$Gamma emission frequen cy from Microshi el d
$Poi nt Detector, mid height of vessel, one foot: away
$Poi nt: Detector, mid height of vesse 1, one foot: away, 96 " offset
$equi valent to dose contribution from l ag vessel
$Tally multiplier equi valent: to s ummati on of all gamma emission frequ encies
$Sour ce scaled to one week of buildup i n lag vessel c
ANSI 6.1.1-1977 Gamma Fl ux to Dose conversion Factors, using us units c
(rem/ hr) / (phot:ons/ om2-s) dfO I U 1 IC 20
$Seper ates tal l1y i nto energy bins, appl ies conver sion factor s and s ums
CALC NO.
EPM017-CALC-001 3ENERCON Dose Rate Near Uranium REV.
l::xrellence-Every pro;ect. Every day Treatment Train PAGE NO.
Attachment B Email Correspondence Caleb T'rainor from:
Sent::
To:
Cc:
Subject:
Jai-Kael LllJle,' <(luey@l::llJlrion.com >
lrn.m::dla~*,, December 03, 2015 11():38 AM
- ateb Trainor Charie.s-Beatty; jlu1:<@envpm.co1(1nt; Ja-Kaef. uey RE: <IE>::lERNAIL> RE= Resin Vessell Dime1111:;;ronc If you an: doiing dose caffc11Jlati,ons use the folJ,o-wing in lie11.11 of sp ecific informati,on {w i,dh m av b e proprvetary frnm A\\f,Nlfiec!ll hru.'t I nave not !ha,d,a, chi:llnce to ch,e,clk}.
11"-JaH, uckne:5,5-.:li/,,,
as istlhewalltlhiclmes:s.for ri*o,11'ssta1111dardl36-iriK vessel at has.asfimnfiair*,*;rorlting presSJU1ire. t i:s. possubffe.!he.AVANilfech ~'.l1aU
- ick:ne:s:.s. rtS thi,dker :s-0 vm.ir d1C1se c;akulai1tion 'l.l'JHI b e boundirng. IF*Dr d,o,se p11.11rposes a d alpha, lflltlJt sure if the Huner maiter"al wulfi a e m'l.Jlch o a differe1n11i::e un *~*,r:iii.u1r ca rnla1tuon.
Sp;acing: 0\\lliG-i?i; 1 0 ns the drawing th,arlt ~
ought lnaid! the separntion di.sll:.imce on it. ltillo s Jike1this was no1ta u iti,rnl efemen: to have *Ol"I the drawrn,g~ h01a1,i1e,.ter, a.se,d on the s,c:ale the nstaJrllce i.s.-edlge-to-edge ais the gap looks to ibe e same i:liS th-e ISM Vess-el {*it,hich is 48-nnc:hes ~-
- ai-llCael From : 1Calle:b T H UlflltDII" [
a.vl:ttci:c.tra.r1rmir@ernen::rnn.com]
Sent:
.uirsd'rf/Y, Deir:em lhu~r Cl!:ll_, 2!015 7:00, Alf/J lf o: Jill-aen LIJle'j' <JI IIJ'e*1t @.k.urii1 111.1rnm>
Subject:
RE: <EX.T'ERlt*t AiL> E:: Resiill VesseE [)rmelfllsuons Thank
- o,u for t he information, this. 1.s mu,c!h cfoser to *what R ne,ed_ I aim stfll lefhvith a fe* i qll.llesltions howe11etr. Outerr dilann-eter is. listed bufi: 11J1 u er diametteir; a liner [s al:5,0 mentioned but again lfl10 thidkness oir ma 'ertal. I -aissu *e e 48'*'
spading is. e,dg,e to ecllge,. or 9*6*" on center, rnrrect? It wm ae e;asy fo,r me to @k11Jla,te dose or,an\\¥ o er spacing 110,u gi'lt*e me. bLlt a d1ange ij111 sipar:n111g i:s. 1J.J! *matelf\\-* a or~t 5a!lfet1f rnncern, t110.t dlose.
From: Ja,Kael u-ey IT, aalto:jlueyr@k:uriot11.com]
Sent: 'Wedn es.cfay, Deir:emloer 012, 2iD15 11:22 PM lio: C-.afeb iran1111on,1r <ctrainor@enerrnn.mm>
Cc:: -rnalflles ~eatt, <cbeatty@e111enrnn.com>; ilux@emrpm.com: ai-!Kaeli 1Lue11,1 <jlu:ey@ urr-on.il:om,;;,
Subjed: <EXTIERNAIL>, E.: Resin Vessel Dim e lll.sion.s Please find attsc ed t ine drswinig tlhat is the basis for the ISM Vessels used en lthe desrgri. l e spacing h1=tween tlile
'!l'essets is 48" from the Gene al Assem y drawin_g (! can pro11ide tlhe sp1=d-frc reference,,,hen B am back il!ll the office lfhurs.da ff ','OU do noiit a11e the full sell:). This s,eparation is based on m eetings he-Id with E111ercon and not a1 spe,ci *c-Cited dloci.Jment. f mm a spacing standpoint it would b e better if this could be smaller. e:specially for the BA Unit sin ce* i:s fft into an e-11dosure.
Ja-Kaiel From: Ca1tie-b Trainor [maiilito:ctrarnor@enercon.com]
Sent.: Wednesday, ecember 02,, 20 5 5:34.
0 1 of 2
ENERCON txcellence-Every proJect. Every day.
To: Ja-1Kael uey <j~ue:y@ku *,r:mu:o Dose Rate Near Uranium Treatment Train Cc: C a-rles Beatty <cbeatty~enercon.com>~ jlux@e111vpm.com
Subject:
Re:si VesseJ Dii en1sion1s CALC NO.
EPM017-CALC-001 REV.
0 PAGE NO.
2 of 2 Jl'll supp rt fi dose ca lc:ufatrons llllff e esiin *1,1,esseis.* II a Fnt eedl oft e ve5seli d~, ensio 1s, v essel m ate f11I,, ai d spad 1g etl'leelll the. vessels. 1n e dlesigrrn dlra1. i rllgs II ihiave so fair o ly-deita1nll 1J: e p1iip,~111,g. a111cll ot 'th e ve:S.sek Ca.111 you he lp m e geit ai rDldl of 'this, frn:fo,irnt1tatron?'
Ca leb T@blf'IOr Emerrge ncy' IP'rre pa red ess Erngun1eer (ci) (81!..3~ 962-:ll llJQi e:rt. 2tUl7
CALC NO.
EPM017-CALC-001
... ENERCON Excellence-Every project. £very doy.
Dose Rate Near Uranium Treatment Train REV.
PAGE NO.
Attachment C MCNP6 Output Code Name & Version = MCNP6, 1.0
_/
_I
_/_/ _/_/
_I _I _/
_I
_/
_/
_I
_/_/_/
_I
_/
I
_/_/_/
_/
_I
_/_/
- I
_/ _/ _/
_/
_/_/
_I
_/
_/_/_/
I
_/_/_/
_/_/_/
_/
_/
_/_/_/
_I
_/
_I I
_/_/
+-------------------------------------------------------+
Copyright 2008. Los Alamos National Security, LLC. All rights reserved.
I This material was produced under U.S. Government contract I
DE-AC52-06NA25396 for Los Alamos National Laboratory, which is operated by Los Alamos National Security, LLC, for the U.S.
I Department of Energy. The Government is granted for itself and others acting on its behalf a paid-up, nonexclusive, irrevocable I worldwide license in this material to reproduce, prepare derivative I works, and perform publicly and display publicly. Beginning five I (5) years after 2008, subject to additional five-year worldwide I
renewals, the Government is granted for itself and others acting on I its behalf a paid-up, nonexclusive, irrevocable worldwide license I in this material to reproduce, prepare derivative works, distribute I copies to the public, perform publicly and display publicly, and to I permit others to do so. NEITHER THE UNITED STATES NOR THE UNITED I STATES DEPARTMENT OF ENERGY, NOR LOS ALAMOS NATIONAL SECURITY, LLC, I NOR ANY OF THEIR EMPLOYEES, MAKES ANY WARRANTY, EXPRESS OR IMPLIED, I OR ASSUMES ANY LEGAL LIABILITY OR RESPONSIBILITY FOR THE ACCURACY, I COMPLETENESS, OR USEFULNESS OF ANY INFORMATION, APPARATUS, PRODUCT, I OR PROCESS DISCLOSED, OR REPRESENTS THAT ITS USE WOULD NOT INFRINGE I PRIVATELY OWNED RIGHTS.
I
+-------------------------------------------------------------+
0 1 of 58
ENERCON Excellence-Every projecr. Every day.
1 mcnp version 6 ld=05/08/13 Dose Rate Near Uranium Treatment Train 12/15/15 16:46:08 CALC NO.
EPM017-CALC-001 REV.
0 PAGE NO.
2 of 58 probid = 12/15/15 16:46:08 i=cim.txt o=cim.out tasks 8 warning.
1-2-
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-Physics models disabled.
Cimmarron Resin Bed Dose Estimation c Cells 10 2 -0.485139 -100 50 1 10 100 11 1 101 10 100 30 0 -300 101 40 0 300 c Surfaces imp:p=1 imp:p=2 imp:p=4 imp:p=8 imp:p=0 100 RCC 0 0 0.9525 0 0 136.4899 60.0075 10 RCC 0 0 0.47625 0 0 136.96615 60.48375 101 RCC 0 0 0 0 0 138.3949 60.96 102 S 91.43 0 69.19745 20 103 S 91.43 243.84 69.19745 20 300 RPP -65 100 -65 250 0 150 c Data Mode P nps 10e6 C
c Material Definitions
$Resin (poly
$SS 304 laye
$SS 304 vess
$Void
$Boundary
$1 nterior cy
$Layer used
$Outer cylin
$Detector 1
$Detector 2
$Bounding Ar M1 6000 -0.000400 14000 -0.005000 15000 -0.000230
$SS 304 16000 -0.000150 24000 -0.190000 25000 -0.010000 26000 -0. 701730 28000 -0.092500 M2 1000 -0.077421 6000 -0.922579
$Polystyrene C
c Source Definition
CALC NO.
EPM017-CALC-001 ENERCON Excellence-Every pro1~ct. Every doy.
Dose Rate Near Uranium Treatment Train REV.
PAGE NO.
28-29-30-31-32-33-34-35-36-37-38-39-40-41-42-43-44-45-46-47-48-SDEF PAR=P axs=0 0 1 pos=0 0 0 rad=d1 ext=d2 erg=d3 cel=10
$Cylindrical SI 1 0 60.0075 Sl2 0.9525 137.4424 Sl3 L 0.13.013.013.0532.0664.0727.09.0933.105
$Discrete en
.1091.12.1214.1408.1438.1633.1827.1857.1904
.1949.2021.2053.2214 SP3 7.112e7 3.166e7 1.201 e7 7.990e5 3.478e5 4.273e4 1.060e6
$Gamma emiss 1.732e6 8.014e5 5.827e5 5.827e4 2.712e5 8.547e4 4.079e6 1.826e6 1.554e5 2.098e7 3.572e5 2.292e5 3.885e5 1.826e6 3.885e4 C
c Tally Definition F15:p 91.43 0 69.1974510 F25:p 91.43 243.84 69.19745 10 C
FM15 1.5045072E8 FM25 2.2567608e7 C
$Point Detec
$Point Detec
$equivalent
$Tally multi
$Source seal c ANSI 6.1.1-1977 Gamma Flux to Dose Conversion Factors, using US units c (rem/hr)/(photons/cm2-s) dfO IU 1 IC 20
$Seperates t surface 100.2 and surface 10.2 are the same.
10.2 will be deleted.
surface 101.3 and surface 300.6 are the same.
300.6 will be deleted.
comment.
2 surfaces were deleted for being the same as others.
warning.
1 materials had unnormalized fractions. print table 40.
1 cells print table 60 atom gram photon cell mat density density volume mass pieces importance 0
3 of 58
CALC NO.
EPM017-CALC-001 ENERCON Excellenc,:-
Every proJect. Every day.
Dose Rate Near Uranium Treatment Train REV.
PAGE NO.
1 2
3 4
5 10 50 11 30 40 2 4.48803E-02 4.85139E-01 1.54405E+06 7.49079E+05 1 8.76841 E-02 8.00000E+00 3.00795E+04 2.40636E+05 1 8.76841E-02 8.00000E+00 4.15670E+04 3.32536E+05 0 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 0 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 total 1.61570E+06 1.32225E+06 warning. surface 102.0 is not used for anything.
warning. surface 103.0 is not used for anything.
1 1.0000E+00 1 2.0000E+00 1 4.0000E+00 0 8.0000E+00 0 0.0000E+00 minimum source weight= 1.0000E+00 maximum source weight= 1.0000E+00
- Random Number Generator =
- Random Number Seed
=
- Random Number Multiplier=
- Random Number Adder
=
- Random Number Bits Used =
- Random Number Stride
=
1
- 19073486328125
- 19073486328125
- 0*
48
- 152917*
comment. threading will be used when possible in portions of mcnp6.
comment. threading will be used for n/p/e table physics.
comment. threading will generally not be used for model physics.
4 warning messages so far.
1 cross-section tables XSDIR used: C:\\MCNP\\MCNP _DATA/xsdir_mcnp6.1 print table 100 0
4 of 58
CALC NO.
EPM017-CALC-001 nENERCON Excellenc,:-
Every projecr. tvery doy.
table length tables from file xdata/mcplib84 Dose Rate Near Uranium Treatment Train REV.
PAGE NO.
1000.84p 1974 Update of MCPLIB04 Photon Compton Broadening Data For MCNP5 see LA-UR-12-00018 6000.84p 3228 Update of MCPLI 804 Photon Compton Broadening Data For MCNP5 see LA-UR-12-00018 14000.84p 4868 Update of MCPLIB04 Photon Compton Broadening Data For MCNP5 see LA-UR-12-00018 15000.84p 4574 Update of MCPLIB04 Photon Compton Broadening Data For MCNP5 see LA-UR-12-00018 16000.84p 4730 Update of MCPLIB04 Photon Compton Broadening Data For MCNP5 see LA-UR-12-00018 24000.84p 5758 Update of MCPLIB04 Photon Compton Broadening Data For MCNP5 see LA-UR-12-00018 25000.84p 5674 Update of MCPLIB04 Photon Compton Broadening Data For MCNP5 see LA-UR-12-00018 26000.84p 5794 Update of MCPLIB04 Photon Compton Broadening Data For MCNP5 see LA-UR-12-00018 28000.84p 5902 Update of MCPLIB04 Photon Compton Broadening Data For MCNP5 see LA-UR-12-00018 total 42502 maximum photon energy set to 100.0 mev (maximum electron energy) tables from file xdata/el03 1000.03e 2329 6000. 03e 2333 14000.03e 2339 15000.03e 2339 16000.03e 2339 24000.03e 2345 25000.03e 2345 26000.03e 2345 28000.03e 2347 1 particles and energy limits 6/6/98 6/6/98 6/6/98 6/6/98 -
6/6/98 6/6/98 6/6/98 6/6/98 6/6/98 print table 101 particle maximum smallest largest always always cutoff particle table table use table use model 0
5 of 58 01 /03/12 01 /03/12 01 /03/12 01 /03/12 01/03/12 01/03/12 01/03/12 01/03/12 01/03/12
CALC NO.
EPM017-CALC-001
._-. E N E R C O N Excellence-Every pro1ec1. Every doy.
particle type energy energy maximum Dose Rate Near Uranium Treatment Train maximum below above REV.
PAGE NO.
2 p photon 1.0000E-03 1.0000E+02 1.0000E+05 1.0000E+05 1.0000E+36 1.0000E+36 3 e electron 1.0000E-03 1.0000E+02 1.0000E+02 1.0000E+02 1.0000E+36 1.0000E+36 warning. material 1 has been set to a conductor.
dump no.
1 on file runtpe nps =
0 coll=
0 ctm =
0.00 nrn =
0 5 warning messages so far.
det t
wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 4.2865E-04 2.5000E-01 1.4603E+01 3.0014E-01 3.1687E+01 1.0000E+01 1.0341 E-01 11 29113 det t
wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 4.6727E-04 2.5000E-01 2.9341 E+01 6.9818E-01 3.5255E+01 1.0000E+01 1.0449E-01 11 37886 det t
wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 4.3285E-04 2.5000E-01 2.9375E+01 7.7426E-01 3.5284E+01 1.0000E+01 1.0449E-01 11 37886 det t
wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 7.1396E-04 2.5000E-01 2.9074E+01 3. 7427E-01 3.3383E+01 1.0000E+01 1.8570E-01 11 99391 det t
wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 5.0577E-04 2.5000E-01 7.5862E+01 1.0924E+00 4.4741 E+01 1.0000E+01 1.3005E-01 11 202920 det t
wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 5.2451 E-04 2.5000E-01 1.8136E+01 4.9620E-02 3.6183E+01 1.0000E+01 1.3000E-01 11 266011 det t
wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 0
6 of 58 6
117 6
2 36 6
4 67 6
3 45 6
4 79 6
8 111 6
ENERCON Excellence--hery proJecl. Every day Dose Rate Near Uranium Treatment Train 2 7.3518E-05 2.5000E-01 8.4093E+01 8.6295E-02 2.0433E+02 1.0000E+01 1.1394E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 1.6404E-03 1.0000E+00 2.5645E+02 2.3748E+00 4.8113E+01 1.0000E+01 1. 7341 E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 1.4661 E-03 2.5000E-01 6.2765E+01 5.1569E-01 3.1892E+01 1.0000E+01 1.1387E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 4. 7999E-04 2.5000E-01 4.1311 E+01 1.1433E+00 3.3039E+01 1.0000E+01 9.5904E-02 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 5.3206E-03 2.5000E-01 1.4027E+02 7.2495E-02 3.1234E+01 1.0000E+01 1.8570E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 7.5842E-05 2.5000E-01 8.3107E+01 1.0047E-02 2.0776E+02 1.0000E+01 1.0709E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 1.4009E-04 2.5000E-01 2.5325E+02 4.0166E-01 2.1940E+02 1.0000E+01 1. 7177E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 4.8092E-04 2.5000E-01 1.5055E+01 1.2837E-01 3.3098E+01 1.0000E+01 1.1808E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 6.9698E-05 5.0000E-01 1.3953E+02 1.3767E+00 2.0052E+02 1.0000E+01 1.3000E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 5.6973E-04 2.5000E-01 7.3557E+01 1.4935E+00 3.3967E+01 1.0000E+01 9.3916E-02 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 2.9775E-03 2.5000E-01 8.8545E+01 1.9940E-01 3.1134E+01 1.0000E+01 1.0968E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 3.4525E-03 2.5000E-01 1.1223E+02 1.9960E-01 3.2548E+01 1.0000E+01 1.3000E-01 CALC NO.
EPM017-CALC-001 REV.
0 PAGE NO.
7 of 58 11 267347 4
66 6
nrn ipsc 10 275363 3
54 6
nrn ipsc 11 289480 3
65 6
nrn ipsc 11 295930 3
60 6
nrn ipsc 11 313718 3
41 6
nrn ipsc 11 385577 4
71 6
nrn ipsc 11 388463 5
65 6
nrn ipsc 11 397905 3
61 6
nrn ipsc 50 571314 2
42 6
nrn ipsc 11 573255 6
88 6
nrn ipsc 11 674671 13 254 6
nrn ipsc 11 717579 2
48 6
,u ENERCON Excellence-Every pro1ect. Every doy.
det t
wgt psc amfp ddetx Dose Rate Near Uranium Treatment Train radius erg cell nps nch p 1 6.2456E-04 5.0000E-01 3.2244E+01 1.4263E+00 3.1413E+01 1.0000E+01 1.2246E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 1.6632E-04 1.0000E+00 2.2685E+02 1.6681 E+00 2.0234E+02 1.0000E+01 1.4318E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 5.3368E-04 1.0000E+00 8.8019E+01 2.6691 E+00 4.2655E+01 1.0000E+01 1.3000E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 8.1664E-05 2.5000E-01 1.1185E+02 2.6078E-01 2.0491 E+02 1.0000E+01 1.8570E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 1.5431 E-03 2.5000E-01 5.5340E+01 2.4316E-01 3.3450E+01 1.0000E+01 1.0500E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 5.2532E-04 2.5000E-01 1.5099E+01 4.8062E-02 3.3015E+01 1.0000E+01 1.3000E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 4.8100E-04 2.5000E-01 1.5132E+01 1.3574E-01 3.3059E+01 1.0000E+01 1.3000E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 1.5455E-03 2.5000E-01 7.6267E+01 5.5582E-01 3.3559E+01 1.0000E+01 9.8397E-02 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 6.8770E-05 2.5000E-01 9.9724E+01 2.981 0E-01 2.0694E+02 1.0000E+01 1.2357E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 1.9707E-03 2.5000E-01 7.4492E+01 1.5406E-01 3.5907E+01 1.0000E+01 1.4937E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 1.1657E-03 2.5000E-01 7.1482E+01 6.2134E-01 3.6204E+01 1.0000E+01 1.4937E-01 CALC NO.
EPM017-CALC-001 REV.
0 PAGE NO.
8 of 58 nrn ipsc 50 726168 3
45 6
nrn ipsc 10 812481 3
60 6
nrn ipsc 10 860193 1
13 6
nrn ipsc 11 864981 1
21 6
nrn ipsc 11 874440 6
101 6
nrn ipsc 11 911985 1
15 6
nrn ipsc 11 911985 2
23 6
nrn ipsc 11 959316 5
95 6
nrn ipsc 11 991642 2
37 6
nrn ipsc 11 1035243 4
59 6
nrn ipsc 11 1035243 5
67 6
ENERCON Excellence-Every pro1ect. tvery doy.
det t
wgt psc amfp ddetx Dose Rate Near Uranium Treatment Train radius erg cell nps nch p 1 6.7144E-04 5.0000E-01 6.2578E+01 1.6644E+00 3.7469E+01 1.0000E+01 1.4380E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 9.4945E-05 2.5000E-011.7751E+02 5.5729E-01 2.0641E+021.0000E+011.8018E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 8.7006E-04 2.5000E-01 2.9759E+01 1.4314E-01 3.4342E+01 1.0000E+01 1.2527E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 4. 7657E-04 2.5000E-01 2.9136E+01 7.0819E-01 3.4614E+01 1.0000E+01 1.2527E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 1.4361 E-03 2.5000E-01 8.6140E+01 2.7980E-01 4.2475E+01 1.0000E+01 1.2024E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 5.0758E-04 2.5000E-01 2.4111 E+01 2.5089E-01 3.8349E+01 1.0000E+01 1.1081 E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 7.1728E-04 5.0000E-01 9.5580E+01 1.9686E+00 3.8483E+01 1.0000E+01 1.4930E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 7.5601 E-05 5.0000E-01 1.0312E+02 9.9309E-01 2.0052E+02 1.0000E+01 1.3000E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 5.6998E-04 2.5000E-01 4.5313E+01 9.8667E-01 3.4341 E+01 1.0000E+01 1.0458E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 6.6728E-05 1.0000E+00 9.3301 E+01 1.6266E+00 2.0916E+02 1.0000E+01 1.6869E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 5.5334E-04 2.5000E-01 1.5005E+01 8.8175E-02 3.1430E+01 1.0000E+01 1.3375E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p CALC NO.
EPM017-CALC-001 REV.
0 PAGE NO.
9 of 58 nrn ipsc 50 1078642 5
86 6
nrn ipsc 11 1087746 3
65 6
nrn ipsc 11 1111829 7
110 6
nrn ipsc 11 1111829 9
129 6
nrn ipsc 11 1169084 4
84 6
nrn ipsc 11 1204350 5
99 6
nrn ipsc 50 1232639 3
59 6
nrn ipsc 50 1318369 1
17 6
nrn ipsc 11 1385745 4
88 6
nrn ipsc 10 1395745 3
70 6
nrn ipsc 11 1430896 3
46 6
nrn ipsc
.. ENERCON Excellence-Every proJecr. Every doy.
Dose Rate Near Uranium Treatment Train 1 1.0282E-03 5.0000E-01 5.9984E+01 1.4429E+00 3.3116E+01 1.0000E+01 1.3000E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 6.6336E-05 2.5000E-01 8.0864E+01 1.8158E-01 2.0112E+02 1.0000E+01 1.0217E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 5.0668E-04 2.5000E-01 2.5289E+01 5.6608E-01 3.3578E+01 1.0000E+01 1.7126E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 6.3800E-04 2.5000E-01 2.5121 E+01 3.3871 E-01 3.3414E+01 1.0000E+01 1. 7126E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 8.5434E-04 2.5000E-01 2.4413E+01 1.4079E-01 3.1427E+01 1.0000E+01 1.8570E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 4.9346E-04 2.5000E-01 1.9930E+01 1.3594E-01 3. 7453E+01 1.0000E+01 1.8570E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 1.1612E-03 5.0000E-01 1.2665E+02 1.8239E+00 3. 7428E+01 1.0000E+01 1.4380E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 5.2350E-04 2.5000E-01 7.0521 E+01 1.5161 E+00 3.4306E+01 1.0000E+01 9.8239E-02 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 9.3573E-05 2.5000E-01 1.0677E+02 5.8288E-02 2.0695E+02 1.0000E+01 1.1075E-01 det t
wgt psc amfp ddetx radius
- erg cell nps nch p 1 5.0019E-04 2.5000E-01 3.6268E+01 4.2032E-01 4.3531 E+01 1.0000E+01 1.2915E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 5.2333E-04 2.5000E-01 2.9283E+01 2.1129E-01 4.2454E+01 1.0000E+01 1. 7037E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 1.5870E-04 5.0000E-01 1.6024E+02 6.9714E-01 2.0004E+02 1.0000E+01 1.7501 E-01 CALC NO.
EPM017-CALC-001 REV.
0 PAGE NO.
10 of 58 50 1572051 6
108 6
nrn ipsc 11 1588704 4
85 6
nrn ipsc 11 1655950 7
102 6
nrn ipsc 11 1655950 8
110 6
nrn ipsc 11 1664001 3
39 6
nrn ipsc 11 1695063 1
20 6
nrn ipsc 50 1771399 6
99 6
nrn ipsc 11 1782361 16 292 6
nrn ipsc 11 1800281 2
40 6
nrn ipsc 11 1811526 13 236 6
nrn ipsc 11 1833593 8
136 6
nrn ipsc 50 1869062 2
38 6
UENERCON Excellence--Every pro1ect. Every doy.
det t
wgt psc amfp ddetx Dose Rate Near Uranium Treatment Train radius erg cell nps nch p 1 7.5992E-04 2.5000E-01 4.3218E+01 7.8143E-01 3.2184E+01 1.0000E+01 1.0812E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 9.3520E-04 2.5000E-01 3.2528E+01 9.9967E-02 3.5387E+01 1.0000E+01 1.3000E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 1.5937E-04 2.5000E-01 2.2703E+02 3.1759E-01 2.0312E+02 1.0000E+01 1.8570E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 4.7675E-04 5.0000E-01 2.4336E+01 1.2345E+00 3.4381 E+01 1.0000E+01 1.8570E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 2.0617E-03 5.0000E-01 9.7782E+01 1.0548E+00 3.6255E+01 1.0000E+01 1.4656E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 5.4699E-04 5.0000E-01 9.1756E+01 2.0320E+00 4.1829E+01 1.0000E+01 1.4091 E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 6.1567E-04 2.5000E-01 5.8573E+01 1.0186E+OO 3.6971 E+01 1.0000E+01 9.2406E-02 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 1.2852E-03 2.5000E-01 1.3956E+02 7.2292E-01 4.5792E+01 1.0000E+01 1.8570E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 1.1976E-03 5.0000E-01 5.3714E+01 1.2483E+00 3.2005E+01 1.0000E+01 1.2771 E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 1.1893E-03 5.0000E-01 8.8997E+01 1.4704E+00 3.6995E+01 1.0000E+01 1.2044E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 1.6740E-03 5.0000E-01 1.2254E+02 1.6349E+00 3.3701 E+01 1.0000E+01 1.3000E-01 CALC NO.
EPM017-CALC-001 REV.
0 PAGE NO.
11 of 58 nrn ipsc 11 1925119 4
58 6
nrn ipsc 11 1925442 2
26 6
nrn ipsc 11 1956285 8
105 6
nrn ipsc 50 2159382 3
40 6
nrn ipsc 50 2166494 2
40 6
nrn ipsc 50 2183252 5
80 6
nrn ipsc 11 2319969 7
124 6
nrn ipsc 11 2334214 2
44 6
nrn ipsc 50 2355712 4
71 6
nrn ipsc 50 2443068 2
41 6
nrn ipsc 50 2452650 5
92 6
CALC NO.
EPM017-CALC-001
~ ENERCON Dose Rate Near Uranium REV.
0 Excellencr:- Every proJecr. Every day.
Treatment Train PAGE NO.
12 of 58 det t
wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 6.1736E-05 2.5000E-01 1.1410E+02 5.3949E-01 2.0706E+02 1.0000E+01 1.4751 E-01 11 2497606 13 209 6
det t
wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 8.9798E-04 2.5000E-01 6.1676E+01 8.2533E-01 3.4601 E+01 1.0000E+01 1.3000E-01 11 2556120 2
46 6
det t
wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 5.2836E-04 2.5000E-01 1.9075E+01 1.7225E-01 3.4773E+01 1.0000E+01 1.1794E-01 11 2577928 3
55 6
det t
wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 3.2627E-03 5.0000E-01 1.9452E+02 9.4308E-01 4.2983E+01 1.0000E+01 1. 7960E-01 50 2625505 4
60 6
det t
wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 5.3011 E-04 2.5000E-01 6. 7960E+01 7.7162E-01 4.8559E+01 1.0000E+01 1.4380E-01 11 2647549 7
90 6
det t
wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 8.0678E-05 5.0000E-01 1.8015E+02 1.4568E+00 2.034 7E+02 1.0000E+01 1.4380E-01 50 2729735 2
25 6
det t
wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 5.1116E-04 5.0000E-01 4.2447E+01 1.5137E+00 3.8136E+01 1.0000E+01 1.3000E-01 50 2780623 5
82 6
det t
wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 6.2670E-04 2.5000E-01 2.0365E+01 2.5639E-01 3.1631 E+01 1.0000E+01 1.3000E-01 11 2878562 2
24 6
det t
wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 6.87 41 E-04 2.5000E-01 9.0621 E+01 9.0706E-01 4.6017E+01 1.0000E+01 1.4380E-01 11 2942792 11 207 6
det t
wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 3.2928E-03 2.5000E-01 1.1130E+02 2.9941 E-01 3.157 4E+01 1.0000E+01 1. 7372E-01 11 3091738 2
39 6
det t
wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 6.2637E-04 2.5000E-01 2.9437E+01 5.2772E-01 3.3214E+01 1.0000E+01 1.3000E-01 11 3116909 6
102 6
det t
wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc
~-- ENERCON Excellence-Every proJen. Every doy.
Dose Rate Near Uranium Treatment Train 1 5.8600E-04 2.5000E-01 7.7180E+01 1.0494E+00 4.2836E+01 1.0000E+01 1.3000E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 4.8181 E-04 2.5000E-01 3.0576E+01 2.9797E-01 4.3294E+01 1.0000E+01 1.3000E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 5.4533E-04 2.5000E-01 4.4832E+01 1.0679E+00 3.3531 E+01 1.0000E+01 1.0656E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 6.3824E-05 2.5000E-01 7.9431 E+01 1.8690E-01 2.0267E+02 1.0000E+01 1.3000E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 5.9247E-04 2.5000E-01 3.7973E+01 6.9944E-01 3.5596E+01 1.0000E+01 1.2844E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 8.7236E-04 2.5000E-01 5.6743E+01 7.8042E-01 3.4437E+01 1.0000E+01 1.3000E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 5.7987E-04 2.5000E-01 6.0033E+01 1.0150E+00 3.8636E+01 1.0000E+01 1.2286E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 4.6707E-04 5.0000E-01 3.4993E+01 1.3552E+00 3.9211 E+01 1.0000E+01 1.6379E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 4.8260E-04 5.0000E-01 3.1520E+01 1.4794E+00 3.4406E+01 1.0000E+01 1.2549E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 5.1747E-04 5.0000E-01 4.9909E+01 1.4486E+00 4.2460E+01 1.0000E+01 1.3669E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 1.2658E-03 5.0000E-01 8.5492E+01 1.4898E+00 3.4807E+01 1.0000E+01 1.3000E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 1.3289E-03 2.5000E-01 8.5079E+01 7.6544E-01 3.4421 E+01 1.0000E+01 1.3000E-01 CALC NO.
EPM017-CALC-001 REV.
0 PAGE NO.
13 of 58 11 3134216 7
87 6
nrn ipsc 11 3161023 1
15 6
nrn ipsc 11 3185384 9
161 6
nrn ipsc 11 3185455 3
35 6
nrn ipsc 11 3195092 2
36 6
nrn ipsc 11 3220944 11 193 6
nrn ipsc 11 3245009 2
36 6
nrn ipsc 50 3276500 2
36 6
nrn ipsc 50 3347693 4
71 6
nrn ipsc 50 3357499 4
90 6
nrn ipsc 50 3361939 1
16 6
nrn ipsc 11 3361939 5
57 6
ENERCON Excellencr:- Every proJect. Every doy.
det t
wgt psc amfp ddetx Dose Rate Near Uranium Treatment Train radius erg cell nps nch p 1 1.1435E-03 2.5000E-01 7.2440E+01 4.1929E-01 4.0711 E+01 1.0000E+01 1.2771 E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 8.5953E-04 5.0000E-01 8.8525E+01 2.0934E+00 3.1785E+01 1.0000E+01 1.0117E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 7.4288E-05 5.0000E-01 9.8099E+01 9.3087E-01 2.0353E+02 1.0000E+01 1.8570E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 1.3308E-03 2.5000E-01 1.2372E+02 8.8648E-01 3.9043E+01 1.0000E+01 1.5373E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 5.0014E-04 2.5000E-01 3.3212E+01 2.3959E-01 4.5599E+01 1.0000E+01 1.3000E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 5.3956E-04 5.0000E-01 2.1833E+01 1.1026E+OO 3.2697E+01 1.0000E+01 1.8570E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 5.6292E-04 2.5000E-01 1.6586E+01 1.1803E-01 3.2278E+01 1.0000E+01 1.8283E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 2.2950E-03 2.5000E-01 9.2796E+01 3.3100E-01 3.3992E+01 1.0000E+01 1.3000E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 9. 7066E-05 1.0000E+00 2.6143E+02 2.2765E+00 2.0976E+02 1.0000E+01 1.3000E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 1.1695E-03 2.5000E-01 5.1011 E+01 6.0644E-01 3.0763E+01 1.0000E+01 1.1012E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 6.6962E-04 2.5000E-01 7.6065E+01 8.3818E-01 4.4213E+01 1.0000E+01 1. 7413E-01 CALC NO.
EPM017-CALC-001 REV.
0 PAGE NO.
14 of 58 nrn ipsc 11 3367095 2
34 6
nrn ipsc 50 3394891 2
41 6
nrn ipsc 50 3442182 2
39 6
nrn ipsc 11 3537462 12 232 6
nrn ipsc 11 3539926 2
27 6
nrn ipsc 50 3545089 1
14 6
nrn ipsc 11 3650364 2
35 6
nrn ipsc 11 3650975 3
33 6
nrn ipsc 10 3654321 1
16 6
nrn ipsc 11 3848369 4
73 6
nrn ipsc 11 3905496 4
71 6
'--ENERCON Excellence-hery proJec:t. Every day.
det t
wgt psc amfp ddetx Dose Rate Near Uranium Treatment Train radius erg cell nps nch p 2 9.6599E-05 2.5000E-01 1.1998E+02 1.0080E-01 2.1137E+02 1.0000E+01 1.8479E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 6.7549E-05 2.5000E-01 9.7349E+01 2.9342E-01 2.0679E+02 1.0000E+01 1.3000E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 7.7800E-05 2.5000E-01 1.0680E+02 3.0907E-01 2.0024E+02 1.0000E+01 1.0923E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 8.6059E-04 1.0000E+00 4.1885E+01 1.6285E+00 3.8987E+01 1.0000E+01 1.8570E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 3.2872E-03 2.5000E-01 2.5142E+02 7.6437E-01 3. 7643E+01 1.0000E+01 1.8570E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 5.4959E-04 5.0000E-01 7.4183E+01 2.1380E+00 3.5585E+01 1.0000E+01 1.2589E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 9.3644E-04 5.0000E-01 4.5728E+01 1.0991 E+00 3.5982E+01 1.0000E+01 1.8570E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 7.2649E-04 5.0000E-01 4.6224E+01 1.3520E+00 3.6194E+01 1.0000E+01 1.8570E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 1.3817E-03 2.5000E-01 5.9445E+01 3.0319E-01 3.5554E+01 1.0000E+01 9.3136E-02 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 2.0539E-03 5.0000E-01 1.1802E+02 1.2470E+00 3.6250E+01 1.0000E+01 1.3000E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 5.3407E-04 5.0000E-01 4.4289E+01 1.3847E+00 4.0649E+01 1.0000E+01 1.3000E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p CALC NO.
EPM017-CALC-001 REV.
0 PAGE NO.
15 of 58 nrn ipsc 11 3906556 2
32 6
nrn ipsc 11 3907053 6
109 6
nrn ipsc 11 3921665 7
112 6
nrn ipsc 10 3930467 1
13 6
nrn ipsc 11 4059754 2
41 6
nrn ipsc 50 4079838 3
59 6
nrn ipsc 50 4156195 1
14 6
nrn ipsc 50 4156195 5
69 6
nrn ipsc 11 4159952 6
103 6
nrn ipsc 50 4171884 1
16 6
nrn ipsc 50 4182657 1
14 6
nrn ipsc
ENERCON Excellence-Every pro1ec:r. Every doy.
Dose Rate Near Uranium Treatment Train 1 6.2597E-04 5.0000E-01 5.3306E+01 1.6796E+00 3.5545E+01 1.0000E+01 1.5492E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 1.2845E-04 2.5000E-01 1.3873E+02 4.2095E-02 2.0298E+02 1.0000E+01 1.8570E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 7.0270E-04 2.5000E-01 2.8470E+01 3.4209E-01 3.3838E+01 1.0000E+01 1.3000E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 6.2254E-04 5.0000E-01 7.6286E+01 1.5238E+00 4.6095E+01 1.0000E+01 1.4380E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 5.1419E-04 5.0000E-01 1.9935E+01 9.4154E-01 3.4688E+01 1.0000E+01 2.0530E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 1.3410E-03 1.0000E+00 2.7016E+02 2.7793E+00 4.4615E+011.0000E+011.2317E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 1.9512E-03 5.0000E-01 1.2248E+02 1.6198E+00 3.1444E+01 1.0000E+01 1.2842E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 1.0099E-04 5.0000E-01 1.9850E+02 1.2931 E+00 2.0718E+02 1.0000E+01 1.8570E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 6.2792E-04 5.0000E-01 4.3828E+01 1.4149E+00 3.6735E+01 1.0000E+01 1.1670E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 4. 7662E-04 1.0000E+00 1.4555E+02 3.4950E+00 3.8406E+01 1.0000E+01 1.0012E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 6. 7040E-04 5.0000E-01 4.4527E+01 1.4417E+00 3.5358E+01 1.0000E+01 1.3000E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 7.3379E-05 1.0000E+00 7.0702E+01 1.2945E+00 2.0499E+02 1.0000E+01 1.8570E-01 CALC NO.
EPM017-CALC-001 REV.
0 PAGE NO.
16 of 58 50 4265308 2
35 6
nrn ipsc 11 4310093 4
64 6
nrn ipsc 11 4328280 2
23 6
nrn ipsc 50 4354629 1
14 6
nrn ipsc 50 4398274 1
14 6
nrn ipsc 10 4535430 2
36 6
nrn ipsc 50 4573242 9
197 6
nrn ipsc 50 4594708 2
24 6
nrn ipsc 50 4608539 2
41 6
nrn ipsc 10 4613891 3
62 6
nrn ipsc 50 4681007 5
52 6
nrn ipsc 10 4684360 1
16 6
ENERCON
!:xcellencr:-Every pro1ect. Every doy.
det t
wgt psc amfp ddetx Dose Rate Near Uranium Treatment Train radius erg cell nps nch p 1 1.0558E-03 2.5000E-01 4.6122E+01 2.6416E-01 3.6532E+01 1.0000E+01 1.3000E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 1.5123E-03 2.5000E-01 8.6092E+01 8.4980E-01 3.1118E+01 1.0000E+01 1.3000E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 1.7255E-03 2.5000E-01 8.5665E+01 7.1743E-01 3.1048E+01 1.0000E+01 1.3000E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 2.9430E-03 2.5000E-01 1.1299E+02 2.5841 E-01 3.4348E+01 1.0000E+01 1.4855E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 1 6.1087E-04 2.5000E-01 2.3456E+01 3.8734E-02 3.8338E+01 1.0000E+01 1.1820E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 8.9505E-05 2.5000E-01 9.3860E+01 3.4463E-02 2.0078E+02 1.0000E+01 1.8570E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 9.3422E-05 2.5000E-01 1.7357E+02 3.4902E-01 2.2835E+02 1.0000E+01 1.6992E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 7.9443E-05 2.5000E-01 1.3739E+02 5.1180E-01 2.0309E+02 1.0000E+01 1.2469E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 6.3427E-05 5.0000E-01 1.4501 E+02 1.3501 E+00 2.1716E+02 1.0000E+01 1.8570E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 9.2058E-05 2.5000E-01 1.2053E+02 2.2794E-01 2.0366E+02 1.0000E+01 1.8570E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 8.1922E-05 2.5000E-01 1.0587E+02 2.1140E-01 2.0402E+02 1.0000E+01 1.3000E-01 CALC NO.
EPM017-CALC-001 REV.
0 PAGE NO.
17 of 58 nrn ipsc 11 4703340 2
32 6
nrn ipsc 11 4712733 2
23 6
nrn ipsc 11 4712733 7
97 6
nrn ipsc 11 4764056 8
137 6
nrn ipsc 11 4768139 6
100 6
nrn ipsc 11 4879138 1
15 6
nrn ipsc 11 4985150 7
106 6
nrn ipsc 11 5166101 16 311 6
nrn ipsc 50 5240953 1
23 6
nrn ipsc 11 5309294 1
17 6
nrn ipsc 11 5507091 5
73 6
ENERCON Excellem:e-Every pro Jee/. Every day.
det t
wgt psc amfp ddetx Dose Rate Near Uranium Treatment Train radius erg cell nps nch p 2 7.1386E-05 2.5000E-01 1.6026E+02 6.6252E-01 2.1460E+02 1.0000E+01 1.6330E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 1.2320E-04 5.0000E-01 1.5423E+02 8.2608E-01 2.0883E+02 1.0000E+01 1.6773E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 6.7748E-05 2.5000E-01 1.4851 E+02 6.1173E-01 2.1751E+021.0000E+01 1.6067E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 1.4616E-04 5.0000E-01 2.5270E+02 1.1450E+00 2.0924E+02 1.0000E+01 1.8570E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 6.3250E-05 5.0000E-01 1.0746E+02 1.1696E+00 2.0489E+02 1.0000E+01 1.5957E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 7. 7663E-05 2.5000E-01 1.1530E+02 3.6248E-01 2.0275E+02 1.0000E+01 1.3000E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 8.2003E-05 5.0000E-01 8.5367E+01 6.7714E-012.0516E+021.0000E+01 1.7525E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 8.0096E-05 2.5000E-01 8.1642E+01 1.4839E-02 1.9990E+02 1.0000E+01 1.3000E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 7. 7647E-05 2.5000E-01 1.1386E+02 2.1132E-01 2.1732E+02 1.0000E+01 1.6915E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 8.0105E-05 2.5000E-01 9. 7521 E+01 9.2966E-02 2.1009E+02 1.0000E+01 1.2952E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 6.3612E-05 5.0000E-01 9.4114E+01 1.0530E+00 2.0267E+02 1.0000E+01 1.3000E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p CALC NO.
EPM017-CALC-001 REV.
0 PAGE NO.
18 of 58 nrn ipsc 11 5607881 4
52 6
nrn ipsc 50 5742616 4
95 6
nrn ipsc 11 5798661 6
98 6
nrn ipsc 50 5941969 1
15 6
nrn ipsc 50 6106548 3
63 6
nrn ipsc 11 6122751 3
40 6
nrn ipsc 50 6128781 6
107 6
nrn ipsc 11 6301952 1
16 6
nrn ipsc 11 6325708 2
44 6
nrn ipsc 11 6569431 8
143 6
nrn ipsc 50 6864922 1
15 6
nrn ipsc
ENERCON Excellence-Every pro;ect. Every doy.
Dose Rate Near Uranium Treatment Train 2 8.5899E-05 2.5000E-01 9.9501 E+01 5.7195E-02 2.0863E+02 1.0000E+01 1.3000E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 8.3686E-05 2.5000E-01 1.8246E+02 6.7611 E-01 2.1005E+02 1.0000E+01 1.8570E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 1.4716E-04 5.0000E-01 1.8785E+02 8.4998E-01 2.0837E+02 1.0000E+01 1.4865E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 8.07 44E-05 1.0000E+00 2.2806E+02 2.3206E+00 2.1012E+02 1.0000E+01 1.3000E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 7.7876E-05 2.5000E-01 9.8330E+01 2.0527E-01 2.0228E+02 1.0000E+01 1.0346E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 7.8800E-05 2.5000E-01 1.1116E+02 2.6310E-01 2.0772E+02 1.0000E+01 1.4380E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 8.2322E-05 2.5000E-01 9.5347E+01 6.8997E-02 2.0739E+02 1.0000E+01 1.0388E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 7.0185E-05 5.0000E-01 1.4111 E+02 1.3704E+00 2.0159E+02 1.0000E+01 1.2327E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 1.9834E-04 5.0000E-01 2.8574E+02 9.6830E-01 2.0865E+02 1.0000E+01 2.021 0E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 8.0021 E-05 2.5000E-01 1.0923E+02 2.7107E-01 2.0351 E+02 1.0000E+01 1.3000E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 1.0526E-04 2.5000E-01 1.3134E+02 4.5678E-02 2.1778E+02 1.0000E+01 1.2624E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 8.7746E-05 2.5000E-01 1.0136E+02 7.5749E-02 2.0642E+02 1.0000E+01 1.8570E-01 CALC NO.
EPM017-CALC-001 REV.
0 PAGE NO.
19 of 58 11 6957752 3
47 6
nrn ipsc 11 6982788 1
22 6
nrn ipsc 50 7006398 5
97 6
nrn ipsc 10 7015682 1
14 6
nrn ipsc 11 7071106 7
116 6
nrn ipsc 11 7237656 3
44 6
nrn ipsc 11 7430193 8
150 6
nrn ipsc 50 7480406 3
46 6
nrn ipsc 50 7980777 6
106 6
nrn ipsc 11 7983577 6
88 6
nrn ipsc 11 8224664 6
117 6
nrn ipsc 11 8660330 2
35 6
CALC NO.
EPM017-CALC-001
.. ENERCON Exc:ellencl.'-
fvery projec:r. Every doy det t
wgt psc amfp ddetx Dose Rate Near Uranium Treatment Train radius erg cell nps nch p 2 8. 7664E-05 2.5000E-01 1.1636E+02 7.3317E-02 2.2154E+02 1.0000E+01 1.6760E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 7.1299E-05 5.0000E-01 1.2433E+02 1.2120E+00 2.0321E+021.0000E+01 1.2898E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 6.6424E-05 2.5000E-01 9.6398E+01 3.4061 E-01 2.0267E+02 1.0000E+01 1.0685E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 7.6836E-05 2.5000E-01 9.5882E+01 2.1270E-01 2.0034E+02 1.0000E+01 1.0768E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 1.0410E-04 2.5000E-01 1.4581 E+02 2.4234E-01 2.0913E+02 1.0000E+01 1.4970E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 7.4218E-05 2.5000E-01 8.0648E+01 7.2804E-02 2.0050E+02 1.0000E+01 1.4349E-01 det t
wgt psc amfp ddetx radius erg cell nps nch p 2 6.6683E-05 5.0000E-01 1.1436E+02 1.1936E+00 2.0340E+02 1.0000E+01 1.3000E-01 1 problem summary run terminated when 10000000 particle histories were done.
+
12/15/15 16:50:13 REV.
PAGE NO.
nrn ipsc 11 8932238 8
nrn ipsc 50 9142262 5
nrn ipsc 11 9325623 14 nrn ipsc 11 9602391 10 nrn ipsc 11 9649833 4
nrn ipsc 11 9681295 5
nrn ipsc 50 9952165 1
Cimmarron Resin Bed Dose Estimation probid = 12/15/15 16:46:08 photon creation tracks weight energy photon loss tracks weight energy (per source particle)
(per source particle) source 10000000 1.0000E+00 1.0453E-01 escape nucl. interaction 0
- 0.
- 0.
energy cutoff 0
- 0.
1609553 4.0239E-02 5.5397E-03 4.5751 E-06 particle decay 0
- 0.
- 0.
time cutoff 0
- 0.
- 0.
weight window 0
- 0.
- 0.
weight window 0
- 0.
- 0.
0 20 of 58 138 6
67 6
248 6
167 6
82 6
94 6
16 6
CALC NO.
EPM017-CALC-001 ENERCON txcellence-Every pro1ect. Every day.
Dose Rate Near Uranium Treatment Train REV.
PAGE NO.
cell importance 8402371 2.0823E-02 1.8945E-03 cell importance 557774 2.0827E-02 1.8943E-03 weight cutoff 0
- 0.
- 0.
weight cutoff 0
- 0.
- 0.
e or t importance 0
- 0.
- 0.
e or t importance 0
- 0.
- 0.
dxtran 0
- 0.
- 0.
dxtran 0
- 0.
- 0.
forced collisions 0
- 0.
- 0.
forced collisions 0
- 0.
- 0.
exp. transform 0
- 0.
- 0.
exp. transform 0
- 0.
- 0.
from neutrons 0
- 0.
- 0.
compton scatter 0
- 0.
5.0425E-02 bremsstrahlung 289865 1.2283E-02 1.1847E-04 capture 20289522 1.1232E+00 4.9640E-02 p-annihilation 0
- 0.
- 0.
pair production 0
- 0.
- 0.
photonuclear 0
- 0.
- 0.
photonuclear abs 0
- 0.
- 0.
electron x-rays 0
- 0.
- 0.
loss to photofis 0
- 0.
- 0.
compton fluores 0
- 0.
- 0.
muon capt fluores 0
- 0.
- 0.
1st fluorescence 3764613 1.5121 E-01 9.6138E-04 2nd fluorescence 0
- 0.
- 0.
(gamma,xgamma) 0
- 0.
- 0.
tabular sampling 0
- 0.
- 0.
prompt photofis 0
- 0.
- 0.
total 22456849 1.1843E+00 1.0750E-01 total 22456849 1.1843E+00 1.0750E-01 number of photons banked 7207156 average time of (shakes) cutoffs photon tracks per source particle 2.2457E+00 escape 2.1082E-01 tco 1.0000E+33 photon collisions per source particle 7.3644E+00 capture 1.5924E-01 eco 1.0000E-03 total photon collisions 73644179 capture or escape 1.6103E-01 wc1 -5.0000E-01 any termination 1.6002E-01 wc2 -2.5000E-01 computer time so far in this run 236. 73 minutes maximum number ever in bank 5
computer time in mcrun 236.60 minutes bank overflows to backup file 0
source particles per minute 4.2266E+04 0
21 of 58 random numbers generated 1463531465 most random numbers used was 1114 in history 3631177 range of sampled source weights= 1.0000E+00 to 1.0000E+00 source efficiency= 1.0000 in cell 10
CALC NO.
EPM017-CALC-001 ENERCON Excellenci:-
Every proJecc. Every ooy.
Dose Rate Near Uranium Treatment Train REV.
PAGE NO.
number of histories processed by each thread 1312074 1201267 1259672 1299659 1294866 1282904 1264634 1084924 1 photon activity in each cell print table 126 tracks population collisions collisions number flux average average cell entering
- weight weighted weighted track weight track mfp (per history) energy energy (relative)
(cm) 0 22 of 58 1
2 3
4 10 10322059 50 9023654 11 6437568 10193584 8922895 6528077 1376517 50738870 5.0739E+00 8.3033E-02 8.3033E-02 1.0000E+00 1.1545E+01 13144162 6.5721E-01 1.1558E-01 1.1558E-01 1.0000E+00 4.3220E-01 9761147 2.4403E-01 1.2524E-01 1.2524E-01 1.0000E+00 4.8793E-01 30 1376517 0
0.0000E+00 1.3735E-01 1.3735E-01 2.0000E+00 0.0000E+00 total 27159798 27021073 73644179 5.9751 E+00 1 tally 15 nps =
10000000 tally type 5 particle flux at a point detector.
particle(s): photons this tally is modified by standard dose function 1.
this tally is all multiplied by 1.50451 E+08 detector located at x,y,z = 9.14300E+01 0.00000E+00 6.91975E+01 2.39237E-05 0.0055 detector located at x,y,z = 9.14300E+01 0.00000E+00 6.91975E+01 uncollided photon flux 7.28378E-06 0.0018 detector score diagnostics cumulative tally cumulative fraction of per fraction of times average score transmissions transmissions history total tally 1.00000E-01 2066474 0.33337 9.19114E-09 0.02066
... ENERCON Excellence-Every pro1e,r. Every day.
Dose Rate Near Uranium Treatment Train 1.00000E+00 2.00000E+00 5.00000E+00 1.00000E+01 1.00000E+02 1.00000E+03 1.00000E+38 before dd roulette 2782476 480224 443038 215883 202626 2350 195 5422 0.78225 0.85973 0.93120 0.96603 0.99871 0.99909 0.99913 1.00000 4.22849E-08
- 3. 02936E-08 6.23896E-08 6.75746E-08 1.84876E-07 2.79066E-08 2.03054E-08 4.07592E-11 0.11571 0.18381 0.32405 0.47595 0.89153 0.95426 0.99991 1.00000 average tally per history = 4.44862E-07 (largest score)/(average tally)= 1.19601 E+04 largest score = 5.32061 E-03 nps of largest score=
313718 score contributions by cell cell misses hits tally per history weight per hit 1
10 50103740 5496658 2.24457E-07 4.08352E-07 2
50 6049166 355174 8.06515E-08 2.27076E-06 3
11 5057541 346856 1.39754E-07 4.02916E-06 total 61210447 6198688 4.44862E-07 7.17672E-07 score misses russian roulette on pd 0
psc=0.
975368 russian roulette in transmission 56695829 underflow in transmission 3539250 hit a zero-importance cell 0
energy cutoff 0
CALC NO.
EPM017-CALC-001 REV.
0 PAGE NO.
23 of 58 results of 10 statistical checks for the estimated answer for the tally fluctuation chart (tfc) bin of tally 15
CALC NO.
EPM017-CALC-001 ENERCON fxcellence-fvery proJect. Every ooy.
tfc bin
--mean--
relative error---------
Dose Rate Near Uranium Treatment Train
variance of the variance----
REV.
PAGE NO.
--figure of merit--
-pdf-behavior behavior value decrease decrease rate value decrease decrease rate value behavior desired random
<0.05 yes 1/sqrt(nps)
<0.10 yes 1/nps constant random
>3.00 observed random 0.01 yes yes 0.02 yes yes constant random 3.12 passed?
yes yes yes yes yes yes yes yes yes yes this tally meets the statistical criteria used to form confidence intervals: check the tally fluctuation chart to verify.
the results in other bins associated with this tally may not meet these statistical criteria.
estimated confidence intervals: -----
0 24 of 58 slope estimated asymmetric confidence interval(1,2,3 sigma): 2.3800E-05 to 2.4061 E-05; 2.3669E-05 to 2.4192E-05; 2.3538E-05 to 2.4323E-05 estimated symmetric confidence interval(1,2,3 sigma): 2.3793E-05 to 2.4055E-05; 2.3662E-05 to 2.4185E-05; 2.3531 E-05 to 2.4316E-05 1 analysis of the results in the tally fluctuation chart bin (tfc) for tally 15 with nps =
10000000 print table 160 normed average tally per history = 2.39237E-05 unnormed average tally per history = 2.39237E-05 estimated tally relative error
0.0055 estimated variance of the variance = 0.0190 relative error from zero tallies = 0.0005 relative error from nonzero scores = 0.0055 number of nonzero history tallies
3040522 history number of largest tally =
313718 (largest tally)/(average tally) = 1.56455E+04 (confidence interval shift)/mean = 0.0003 efficiency for the nonzero tallies = 0.3041 largest unnormalized history tally= 3.74298E-01 (largest tally)/(avg nonzero tally)= 4. 75705E+03 shifted confidence interval center = 2.39305E-05
CALC NO.
EPM017-CALC-001
._-. E N E R C O N Excellence-Every proJecr. £very doy.
Dose Rate Near Uranium Treatment Train REV.
0 PAGE NO.
25 of 58 if the largest history score sampled so far were to occur on the next history, the tfc bin quantities would change as follows:
estimated quantities value at nps mean 2.39237E-05 relative error 5.47129E-03 variance of the variance 1.90457E-02 shifted center 2.39305E-05 figure of merit 1.41191 E+02 value at nps+1 2.39611 E-05 5.68168E-03 2.19879E-02 2.39314E-05 1.30928E+02 value(nps+1 )/value(nps)-1.
0.001564 0.038452 0.154486 0.000038
-0.072686 the estimated inverse power slope of the 200 largest tallies starting at 2.58402E-02 is 3.1203 the history score probability density function appears to have an unsampled region at the largest history scores:
please examine. see print table 161.
tom= (histories/minute)*(f(x) signal-to-noise ratio)**2 = (4.227E+04)*( 5.780E-02)**2 = (4.227E+04)*(3.341 E-03) = 1.412E+02 1 tally 25 nps =
10000000 tally type 5 particle flux at a point detector.
particle(s): photons this tally is modified by standard dose function 1.
this tally is all multiplied by 2.25676E+07 detector located at x,y,z = 9.14300E+01 2.43840E+02 6.91975E+01 4.97439E-07 0.0024 detector located at x,y,z = 9.14300E+01 2.43840E+02 6.91975E+01 uncollided photon flux 1.65726E-07 0.0010 detector score diagnostics cumulative tally cumulative fraction of per fraction of times average score transmissions transmissions history total tally 1.00000E-01 2719757 0.2834 7 1.67735E-09 0.02719
1.00000E+00 2.00000E+00 5.00000E+00 1.00000E+01 1.00000E+02 1.00000E+03 1.00000E+38 before dd roulette ENERCON Excellencr:-Every pro1ecr. Every day.
4570832 976550 959927 304493 55103 2382 61 5491 0.75986 0.86165 0.96169 0.99343 0.99917 0.99942 0.99943 1.00000 Dose Rate Near Uranium Treatment Train 1.01499E-08 8.59433E-09 1.86191 E-08 1.27090E-08 6.01146E-09 3.38705E-09 5.47142E-10 5.86511 E-12 0.19169 0.33098 0.63274 0.83871 0.93614 0.99104 0.99990 1.00000 average tally per history= 6.17012E-08 (largest score)/(average tally)= 3.21450E+03 largest score = 1.98339E-04 nps of largest score =
7980777 score contributions by cell cell misses hits tally per history weight per hit 1
10 47440116 8160282 3.45288E-08 4.23132E-08 2
50 5631580 772760 1.10836E-08 1.43429E-07 3
11 4742843 661554 1.60889E-08 2.43198E-07 total 57814539 9594596 6.17012E-08 6.43083E-08 score misses russian roulette on pd 0
psc=0.
855422 russian roulette in transmission 53023942 underflow in transmission 3935175 hit a zero-importance cell 0
energy cutoff 0
CALC NO.
EPM017-CALC-001 REV.
0 PAGE NO.
26 of 58 results of 10 statistical checks for the estimated answer for the tally fluctuation chart (tfc) bin of tally 25
CALC NO.
EPM017-CALC-001 ENERCON Excellence-Every proJecr. Every doy.
tfc bin
--mean--
relative error---------
Dose Rate Near Uranium Treatment Train
variance of the variance----
REV.
PAGE NO.
--figure of merit--
-pdf-behavior behavior value decrease decrease rate value decrease decrease rate value behavior desired random
<0.05 yes 1/sqrt(nps)
<0.10 yes 1/nps constant random
>3.00 observed random 0.00 yes yes 0.00 yes yes constant random 4.00 passed?
yes yes yes yes yes yes yes yes yes yes this tally meets the statistical criteria used to form confidence intervals: check the tally fluctuation chart to verify.
the results in other bins associated with this tally may not meet these statistical criteria.
estimated confidence intervals: -----
0 27 of 58 slope estimated asymmetric confidence interval(1,2,3 sigma): 4.9627E-07 to 4.9866E-07; 4.9508E-07 to 4.9986E-07; 4.9388E-07 to 5.0105E-07 estimated symmetric confidence interval(1,2,3 sigma): 4.9625E-07 to 4.9863E-07; 4.9505E-07 to 4.9983E-07; 4.9386E-07 to 5.0102E-07 1 analysis of the results in the tally fluctuation chart bin (tfc) for tally 25 with nps =
10000000 print table 160 normed average tally per history = 4.97439E-07 unnormed average tally per history = 4.97439E-07 estimated tally relative error
0.0024 estimated variance of the variance = 0.0047 relative error from zero tallies = 0.0004 relative error from nonzero scores = 0.0024 number of nonzero history tallies
4079202 history number of largest tally =
7980777 (largest tally)/(average tally) = 4.58726E+03 (confidence interval shift)/mean = 0.0001 efficiency for the nonzero tallies = 0.4079 largest unnormalized history tally = 2.28189E-03 (largest tally)/(avg nonzero tally)= 1.87124E+03 shifted confidence interval center = 4.97467E-07
CALC NO.
EPM017-CALC-001 IU ENERCON Excellenc.:-Every proJect. Every day.
Dose Rate Near Uranium Treatment Train REV.
0 PAGE NO.
28 of 58 if the largest history score sampled so far were to occur on the next history, the tfc bin quantities would change as follows:
estimated quantities value at nps mean 4.97439E-07 relative error 2.40083E-03 variance of the variance
- 4. 71546E-03 shifted center
- 4. 97 467E-07 figure of merit 7.33269E+02 value at nps+1 4.97668E-07 2.44312E-03 5.62879E-03 4.97470E-07 7.08102E+02 value(nps+1 )/value(nps)-1.
0.000459 0.017616 0.193689 0.000006
-0.034322 the estimated inverse power slope of the 200 largest tallies starting at 2.97193E-04 is 4.0044 the large score tail of the empirical history score probability density function appears to have no unsampled regions.
fom = (histories/minute)*(f(x) signal-to-noise ratio)**2 = (4.227E+04 )*( 1.317E-01 )**2 = (4.227E+04 )*(1. 735E-02) = 7.333E+02 1 status of the statistical checks used to form confidence intervals for the mean for each tally bin tally result of statistical checks for the tfc bin (the first check not passed is listed) and error magnitude check for all bins 15 passed the 1 0 statistical checks for the tally fluctuation chart bin result passed all bin error check:
2 tally bins all have relative errors less than 0.05 with no zero bins 25 passed the 1 0 statistical checks for the tally fluctuation chart bin result passed all bin error check:
2 tally bins all have relative errors less than 0.05 with no zero bins the 1 0 statistical checks are only for the tally fluctuation chart bin and do not apply to other tally bins.
1 tally fluctuation charts tally 15 tally 25 nps mean error vov slope fom mean error vov slope fom 512000 2.4094E-05 0.0352 0.5579 2.2 83 4.9978E-07 0.0102 0.1024 3.3 988
CALC NO.
EPM017-CALC-001 ENERCON Excellenc~-Every proJect. Every day.
1024000 2.4078E-05 0.0213 0.2766 2.2 1536000 2.3929E-05 0.0160 0.1849 2.3 2048000 2.3935E-05 0.0128 0.1420 2.3 2560000 2.3867E-05 0.0111 0.1081 2.4 3072000 2.3783E-05 0.0100 0.0890 2.6 3584000 2.3846E-05 0.0094 0.0676 3.0 4096000 2.3883E-05 0.0088 0.0556 3.0 4608000 2.3874E-05 0.0082 0.0469 2.9 5120000 2.4010E-05 0.0081 0.0377 2.8 5632000 2.3975E-05 0.0076 0.0338 2.6 6144000 2.3969E-05 0.0072 0.0300 2.7 6656000 2.3965E-05 0.0068 0.0273 2.7 7168000 2.3940E-05 0.0065 0.0253 2.7 7680000 2.3942E-05 0.0063 0.0236 2.6 8192000 2.3982E-05 0.0061 0.0208 3.0 8704000 2.3969E-05 0.0059 0.0190 3.1 9216000 2.3925E-05 0.0056 0.0184 3.2 9728000 2.3939E-05 0.0056 0.0194 3.1 10000000 2.3924E-05 0.0055 0.0190 3.1 Dose Rate Near Uranium Treatment Train 110 4.9771 E-07 0.0075 0.0438 3.2 876 136 4.9688E-07 0.0059 0.0257 3.1 989 153 4.9847E-07 0.0056 0.0281 3.2 796 150 4.9707E-07 0.0049 0.0214 3.8 776 160 4.9589E-07 0.0044 0.0171 3.9 832 161 4.9585E-07 0.0040 0.0136 4.0 880 161 4.9676E-07 0.0037 0.0110 3.5 899 161 4.9657E-07 0.0035 0.0098 3.5 870 153 4.9693E-07 0.0034 0.0087 3.6 879 161 4.9764E-07 0.0032 0.0075 3.9 888 157 4.9766E-07 0.0031 0.0069 3.4 824 150 4.9714E-070.00300.0063 3.1 784 154 4.9817E-07 0.0029 0.0056 3.3 770 150 4.9818E-07 0.0028 0.0051 3.5 777 143 4.9807E-07 0.0027 0.0062 3.2 724 143 4.9799E-07 0.0026 0.0057 3.2 726 144 4.9759E-07 0.0025 0.0053 3.3 721 138 4.9753E-07 0.0024 0.0049 3.7 723 141 4.9744E-07 0.0024 0.0047 4.0 733 REV.
PAGE NO.
dump no.
2 on file runtpe nps =
10000000 coll =
73644179 ctm =
236.60 nrn =
1463531465 5 warning messages so far.
run terminated when 10000000 particle histories were done.
computer time= 236.73 minutes mcnp version 6 05/08/13 12/15/15 16:50:13 probid = 12/15/15 16:46:08 0
29 of 58
CALC NO.
EPM017-CALC-001 ENERCON CALCULATION PREPARATION REV.
0 IJ CHECKLIST Excellence-Every pro;ect. Every day PAGE NO.
1 of 6 CHECKLIST ITEMS1 YES NO N/A GENERAL REQUIREMENTS
- 1.
If the calculation is being performed to a client procedure, is the procedure being used the latest revision?
Client procedure is not used in this calculation. ENERCON QA procedures used
~
throughout this project.
- 2.
Are the proper forms being used and are they the latest revision?
~
- 3.
Have the appropriate client review forms/checklists been completed?
Client procedure is not used in this calculation. ENERCON QA procedures used
~
throughout this project.
- 4.
Are all pages properly identified with a calculation number, calculation revision and page number consistent with the requirements of the client's procedure?
Client procedure is not used in this calculation. ENERCON QA procedures used
~
throughout this project.
- 5.
Is all information legible and reproducible?
~
- 6.
Is the calculation presented in a logical and orderly manner?
~
- 7.
Is there an existing calculation that should be revised or voided?
~
- 8.
Is it possible to alter an existing calculation instead of preparing a new calculation for this situation?
~
No current ENERCON calculations exist that are similar to this calculation.
- 9.
If an existing calculation is being used for design inputs, are the key design inputs, assumptions and engineering judgments used in that calculation valid and do they
~
apply to the calculation revision being performed.
- 10.
Is the format of the calculation consistent with applicable procedures and expectations?
~
11.
Were design input/output documents properly updated to reference this calculation?
No ENERCON design inputs or outputs are affected by this calculation.
~
CSP 3.03 Revision 1 Attachment C
CALC NO.
EPM017-CALC-001
- J ENERCON CALCULATION PREPARATION REV.
0 Excellence-Every pro;ect. Every day.
CHECKLIST PAGE NO.
2 of 6 CHECKLIST ITEMS1 YES NO N/A
- 12.
Can the calculation logic, methodology and presentation be properly understood
~
without referring back to the originator for clarification?
OBJECTIVE AND SCOPE
- 13.
Does the calculation provide a clear concise statement of the problem and objective of
~
the calculation?
- 14.
Does the calculation provide a clear statement of quality classification?
~
- 15.
Is the reason for performing and the end use of the calculation understood?
~
- 16.
Does the calculation provide the basis for information found in the plant's license basis?
This calculation applies to a remediation site. No work performed in this calculation is
~
applicable to a licensing basis.
- 17.
If so, is this documented in the calculation?
~
- 18.
Does the calculation provide the basis for information found in the plant's design basis
~
documentation?
- 19.
If so, is this documented in the calculation?
~
- 20.
Does the calculation otherwise support information found in the plant's design basis
~
documentation?
- 21.
If so, is this documented in the calculation?
~
- 22.
Has the appropriate design or license basis documentation been revised, or has the
~
change notice or change request documents being prepared for submittal?
DESIGN INPUTS
- 23.
Are design inputs clearly identified?
~
- 24.
Are design inputs retrievable or have they been added as attachments?
~
CSP 3.03 Revision 1 Attachment C
CALC NO.
EPM017-CALC-001
- I ENERCON CALCULATION PREPARATION REV.
0 Excellence-Every pro;ect. Every day.
CHECKLIST PAGE NO.
3 of 6 CHECKLIST ITEMS1 YES NO NIA
- 25.
If Attachments are used as design inputs or assumptions are the Attachments traceable rzI and verifiable?
- 26.
Are design inputs clearly distinguished from assumptions?
rzI DESIGN INPUTS (Continued)
- 27.
Does the calculation rely on Attachments for design inputs or assumptions? If yes, are rzI the attachments properly referenced in the calculation?
- 28.
Are input sources (including industry codes and standards) appropriately selected and rzI are they consistent with the quality classification and objective of the calculation?
- 29.
Are input sources (including industry codes and standards) consistent with the plant's rzI design and license basis?
- 30.
If applicable, do design inputs adequately address actual plant conditions?
rzI
- 31.
Are input values reasonable and correctly applied?
rzI
- 32.
Are design input sources approved?
rzI The Cimarron design is currently at 60% completion.
- 33.
Does the calculation reference the latest revision of the design input source?
rzI
- 34.
Were all applicable plant operating modes considered?
rzI ASSUMPTIONS
- 35.
Are assumptions reasonable/appropriate to the objective?
rzI
- 36.
Is adequate justification/basis for all assumptions provided?
rzI
- 37.
Are any engineering judgments used?
rzI
- 38.
Are engineering judgments clearly identified as such?
No engineering judgments were applied in this evaluation.
rzI CSP 3.03 Revision 1 Attachment C
CALC NO.
ENERCON CALCULATION PREPARATION CHECKLIST REV.
Ex,ellence-Everv pro;ect. Every day.
PAGE NO.
CHECKLIST ITEMS1
- 39.
If engineering judgments are utilized as design inputs, are they reasonable and can they be quantified or substantiated by reference to site or industry standards, engineering principles, physical laws or other appropriate criteria?
METHODOLOGY
- 40.
Is the methodology used in the calculation described or implied in the plant's licensing basis?
- 41.
If the methodology used differs from that described in the plant's licensing basis, has the appropriate license document change notice been initiated?
- 42.
Is the methodology used consistent with the stated objective?
- 43.
Is the methodology used appropriate when considering the quality classification of the calculation and intended use of the results?
BODY OF CALCULATION
- 44.
Are equations used in the calculation consistent with recognized engineering practice and the plant's design and license basis?
- 45.
Is there reasonable justification provided for the use of equations not in common use?
Equations applied in this evaluation are in common use in the industry.
- 46.
Are the mathematical operations performed properly and documented in a logical fashion?
- 47.
Is the math performed correctly?
- 48.
Have adjustment factors, uncertainties and empirical correlations used in the analysis been correctly applied?
- 49.
Has proper consideration been given to results that may be overly sensitive to very small changes in input?
Results generated by calculations performed in this evaluation are not significantly affected by minor perturbations of variables.
SOFTWARE/COMPUTER CODES
- 50.
Are computer codes or software languages used in the preparation of the calculation?
EPM017-CALC-001 0
4 of 6 YES NO N/A
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~
~
~
~
~
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~
~
~
~
CSP 3.03 Revision 1 Attachment C
CALC NO.
ENERCON Excellence-Every pro;ect. Every day.
CALCULATION PREPARATION CHECKLIST REV.
PAGE NO.
CHECKLIST ITEMS1
- 51.
Have the requirements of CSP 3.09 for use of computer codes or software languages, including verification of accuracy and applicability been met?
SOFTWARE/COMPUTER CODES (Continued)
- 52.
Are the codes properly identified along with source vendor, organization, and revision level?
- 53.
Is the computer code applicable for the analysis being performed?
- 54.
If applicable, does the computer model adequately consider actual plant conditions?
- 55.
Are the inputs to the computer code clearly identified and consistent with the inputs and assumptions documented in the calculation?
- 56.
Is the computer output clearly identified?
- 57.
Does the computer output clearly identify the appropriate units?
The output units are not identified in the output document. Tallies have been modified through multipliers and dose response functions. This process has been adequately documented within this calculation.
- 58.
Are the computer outputs reasonable when compared to the inputs and what was expected?
Only basic functions and operations in Microsoft Excel 2013 were applied in this calculation.
- 59.
Was the computer output reviewed for ERROR or WARNING messages that could invalidate the results?
While warning messages exist, they do not impact the results.
RESULTS AND CONCLUSIONS
- 60.
Is adequate acceptance criteria specified?
No acceptance criteria required for this evaluation.
- 61.
Are the stated acceptance criteria consistent with the purpose of the calculation, and intended use?
EPM017-CALC-001 0
5 of 6 YES NO N/A
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~
~
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CSP 3.03 Revision 1 Attachment C
CALC NO.
ENERCON CALCULATION PREPARATION CHECKLIST REV.
Excellence-Every pro;ect. Every day.
PAGE NO.
CHECKLIST ITEMS1
- 62.
Are the stated acceptance criteria consistent with the plant's design basis, applicable licensing commitments and industry codes, and standards?
- 63.
Do the calculation results and conclusions meet the stated acceptance criteria?
- 64.
Are the results represented in the proper units with an appropriate tolerance, if applicable?
- 65.
Are the calculation results and conclusions reasonable when considered against the stated inputs and objectives?
- 66.
Is sufficient conservatism applied to the outputs and conclusions?
- 67.
Do the calculation results and conclusions affect any other calculations?
No ENERCON calculations are affected by this evaluation.
- 68.
If so, have the affected calculations been revised?
- 69.
Does the calculation contain any conceptual, unconfirmed or open assumptions requiring later confirmation?
- 70.
If so, are they properly identified?
DESIGN REVIEW
- 71.
Have alternate calculation methods been used to verify calculation results?
Note:
EPM017-CALC-001 0
6 of 6 YES NO N/A
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- 1. Where required, provide clarification/justification for answers to the questions in the space provided below each question. An explanation is required for any questions answered as "No' or "N/A".
Originator:
- 1
- 1
/
/.
/ fl-,$) L *.
Caleb Trainor c
Print Name and Sign 12/21/ 2015 Date CSP 3.03 Revision 1 Attachment C