Text

Cimarron Environmental Response Trust Facility Decommissioning Plan, Revision 2, Appendix M, RPP Div. 4, Part 3
	ML21076A459
Person / Time
Site:	07000925
Issue date:	02/26/2021
From:	; Environmental Properties Management, Enercon Services, Burns & McDonnell Engineering Co, Veolia Nuclear Solutions Federal Services
To:	; Office of Nuclear Material Safety and Safeguards, Cimarron Environmental Response Trust, NRC Region 4
Shared Package
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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 Potential Intake Calculation f~ ENERCON hcelltmce- Every proJect /:.very dO}' Uranium REV. 2 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 Potential Intake Calculation

~3 ENERCON Excellence- Every proJecr hcry day Uranium REV. 2 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 Potential Intake Calculation 2

~,~ ENERCON REV.

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.5 1E+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)

CALC NO. EPM028-CALC-001

~ ENERCON Sensitivity Analysis REV. 2 Excellence--Evt!t v 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-235 Uranium 9.7% 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

CALC NO. EPM028-CALC-001 0 ENERCON Excellence*-Every pro;ect. f.vP.ry day Sensitivity Analysis REV. 2 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 Dispersibilit y (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 REV. 2 Excellence-Every p ro1ect Every doy. CHECKLIST PAGE NO. 1 of 7 CHECKLIST ITEMS 1 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? 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?

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6. Is the calculation presented in a logical and orderly manner?

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7. Is there an existing calculation that should be revised or voided?

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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. ~

CALC NO. EPM017-CALC-001 ENERCON CALCULATION PREPARATION REV. 2 Excellence-- frery pro1ec1. Every doy. CHECKLIST PAGE NO. 2 of 7 CHECKLIST ITEMS 1 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?

~

Is the reason for performing and the end use of the calculation understood? ~

15.

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?

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20. Does the calculation otherwise support information found in the plant's design basis documentation? ~

21. If so, is this documented in the calculation?

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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?

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24. Are design inputs retrievable or have they been added as attachments?

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CALC NO. EPM017-CALC-001 ENERCON CALCULATION PREPARATION REV. 2 Excp//ence-- Every pro1ect. Every day. CHECKLIST PAGE NO. 3 of 7 CHECKLIST ITEMS 1 YES NO N/A

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.

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26. Are design inputs clearly distinguished from assumptions?

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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?

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31. Are input values reasonable and correctly applied?

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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?

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34. Were all applicable plant operating modes considered?

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ASSUMPTIONS

35. Are assumptions reasonable/appropriate to the objective? ~

36. Is adequate justification/basis for all assumptions provided?

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37. Are any engineering judgments used? ~

CALC NO. EPM017-CALC-001 ENERCON CALCULATION PREPARATION REV. 2 Excellence- Every pro_1ect. Every doy. CHECKLIST PAGE NO. 4 of 7 CHECKLIST ITEMS 1 YES NO N/A 38 . Are engineering judgments clearly identified as such?

Engineering judgement applied to factors used in potential intake calculation using NUREG-1400 methodology.

lXI

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?

lXI METHODOLOGY

40. Is the methodology used in the calculation described or implied in the plant's licensing basis? lXI

41. If the methodology used differs from that described in the plant's licensing basis, has the appropriate license document change notice been initiated? lXI

42. Is the methodology used consistent with the stated objective?

lXI

43. Is the methodology used appropriate when considering the quality classification of the calculation and intended use of the results? lXI BODY OF CALCULATION

44. Are equations used in the calculation consistent with recognized engineering practice and the plant's design and license basis? lXI

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. lXI

46. Are the mathematical operations performed properly and documented in a logical fashion? lXI 47 . Is the math performed correctly?

lXI

48. Have adjustment factors, uncertainties and empirical correlations used in the analysis been correctly applied? lXI

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 lXI affected by minor perturbations of variables.

CALC NO. EPM017-CALC-001 ENERCON CALCULATION PREPARATION REV. 2 Exceilence- Every proJect. Every day. CHECKLIST PAGE NO. 5 of 7 CHECKLIST ITEMS 1 YES NO N/A SOFTWARE/COMPUTER CODES

50. Are computer codes or software languages used in the preparation of the calculation?

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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?

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54. If applicable, does the computer model adequately consider actual plant conditions?

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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 ULTS AND CONCLUSIONS

60. Is adequate acceptance criteria specified?

No acceptance criteria required for this evaluation. ~

CALC NO. EPM017-CALC-001 ENERCON CALCULATION PREPARATION REV. 2 Exce!lence-- Every proJect. Every doy. CHECKLIST PAGE NO. 6 of 7 CHECKLIST ITEMS 1 YES NO N/A

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?

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69. Does the calculation contain any conceptual, unconfirmed or open assumptions requiring later confirmation? ~

70. If so, are they properly identified?

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DESIGN REVIEW

71. Have alternate calculation methods been used to verify calculation results?

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Note:

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".

CALC NO. EPM017-CALC-001 ENERCON CALCULATION PREPARATION REV. 2 Excellence- Every pro1ect. Every day CHECKLIST PAGE NO. 7 of 7 Originator:

Jay Maisler 12/12/2019 Print Name and Sign Date

~ Cimarron Environmental Response Trust

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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 Cimarron Environmental Client:

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 information, that require confirmation? (If YES, identify the assumptions.)

~

2 Does this calculation serve as an "Alternate Calculation"? (If YES, identify the ~

design verified calculation .)

Design Verified Calculation No.

3 Does this calculation supersede an existing Calculation? (If YES, identify the ~

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/,. ~r, l.* . Date: 12/21/2015

,,,,- -)1\

'---:1-

,,-- L--\;

I

~"--

Date: 12/23/2015 Design Reviewer: John Hawkinson *--

Approver: Jay Maisler, CHP

!Pl~ Date: 12/23/2015 CSP 3.03 Revision 1 Attachment A

CALC NO. EPM017-CALC-001 ENERCON CALCULATION REV. 0 Excellenn~-Every project Every doy. REVISION STATUS SHEET PAGE NO. 2 of 15 CALCULATION REVISION STATUS REVISION DATE DESCRIPTION 0 12/21/2015 Initial Issue PAGE REVISION STATUS PAGE NO. REVISION PAGE NO. REVISION APPENDIX/ATTACHMENT REVISION STATUS APPENDIX NO. NO.OF REVISION ATTACHMENT NO.OF REVISION PAGES NO. NO. PAGES NO.

CSP 3.03 Revision 1 Attachment B

CALCULATION TABLE OF CONTENTS I ENERCON TABLE OF CALC NO. EPM017-CALC-001 Excellence*-Every pro;ect. Every day. CONTENTS REV. 0 Section Page No.

1.0 Purpose and Scope

4 2.0 Summary of Results and Conclusions 4 3.0 References 4 4.0 Assumptions 4 5.0 Design Inputs 6 6.0 Methodology 7 7 .0 Calculations 10 8.0 Computer Software 15 List of Attachments # of pages MCNP6 Input 1 Email Correspondence 2 MCNP6 Output 58

CALC NO. EPM017-CALC-001 I ENERCON Dose Rate Near Uranium REV. 0 Exce!lence-frery proje<::t Every day. Treatment Train PAGE NO. 4 of 15

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, 4 th 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. EPM017-CALC-001 ENERCON Dose Rate Near Uranium REV. 0 Excellence-Every project. Every day. Treatment Train PAGE NO. 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.

CALC NO. EPM017-CALC-001 ENERCON Dose Rate Near Uranium REV. 0 fxcellence-- Every proJect. Every day Treatment Train PAGE NO. 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.

Vessel Diameter=48 in Volume=54.5 ft 3 The following properties are taken from Reference 3. 7.

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.

U234= 6.19 E+03 µCi/g U23s= 2.14 E+00 µCi/g U23a= 3.33 E-01 µCi/g 5.3 Material Definitions The following material definitions are taken from Reference 3.6.

CALC NO. EPM017-CALC-001 ENERCON Dose Rate Near Uranium REV. 0 Excellence-Every proJect. Every day. Treatment Train PAGE NO. 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

CALC NO. EPM017-CALC-001 ENERCON Dose Rate Near Uranium REV. 0 Excellence- Every project. Every day Treatment Train PAGE NO. 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.

CALC NO. EPM017-CALC-001 tl ENERCON Dose Rate Near Uranium REV. 0 l::xcellence- Every pro1ect. Every day. Treatment Train PAGE NO. 9 of 15 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 Detector F 15 I

(91.43 ,0,69.19745)

Y=O

~ ...

l

CALC NO. EPM017-CALC-001

.~ ENERCON Dose Rate Near Uranium REV. 0 Excellence--fvery project. Every day. Treatment Train PAGE NO. 10 of 15 Figure 6.2: Y-Plane of Modeled Geometry o *'

II:

>< : Z=138.3949 z

X Cross section of y-ptane @ 0cm Det ector F 15 (91.43000,0, 69.19745)

Cylindrical resin v essel centered at (0,0,0).

inner radius=60. 0075cm Outer radius=60.9600cm

- ~~~~~~:;;;;~~:;;;;;;~;;;;;;;;;;~~;:;.;;~ _- - - - - - - --Z=O 7.0 Calculation 7 .1 Source Development The activity of each isotope is found using the Equation 7.1.

Equation 7. 1

CALC NO. EPM017-CALC-001 I 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)

Au234 = 2.958 (g)

6190 (- g = 1.83

10 4 µCi Au235 = 491.177 (g)

2.140 ( -µCi) g = 1.05

10 3 µCi

µCi)

Au238 = 29094.873(g)

0.333 (- g = 9.69

10 3 µCi 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 Dose Rate Near Uranium REV. 0 txceflence--Every project. Every day Treatment Train PAGE NO. 12 of 15 Table 7.1: Gamma Emissions from Uranium source Activity Energy (MeV)

(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 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 Dose Rate Near Uranium REV. 0 Exceilence--Every projeer. Every day. Treatment Train 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 ri -

D - (2

clad) 2 48 in. -(2 *

! in. )

= 23.625 in Solving for hi; in 3 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 Dose Rate Near Uranium REV. 0 Excellence--- Every project. Every day. Treatment Train PAGE NO. 14 of 15 Figure 7.1 : Cell and Surface Cards from Input Deck C cell ls 10 2 - 0.485139 - 100 i mp, : p =l $Resi n (polystyrene) i nside vess el 50 1 10 100 i mp: p,=2 $ss 304 71 ayer 11 1 10110100 i mp: p=4 $55 304 vesse1 cl ad 30 0 - 300 101 imp,: p=B $Void 40 0 300 i mp: p,=0 $Bo nda ry c s ur faces 100 RCC O O 0.9525 0 0 136.4899 60.0075 $Interior cylinder of r e,sin vessel.

10 RCC O O 0.47625 0 0 136. 966,1 5 60.46375 $Layer used! for var i ance r eduction 101 RCC O O O O O 138. 3949 60 . 96, $out:er cyl inder of r es in vessel 102 s 91-43 0 69 .. 19745 20 $Detector 1 void 103 S 91 .4 3 243. 84 69. 19745 20 $Detector 2 void 300 RPP - 65 100 - 65 250 0 150 $Bmmdi ng Area 7 .2 .2 Source Definition 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 sou r 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 $c yli ndr i cal! source located i ns ide inner cyli nder s:n o 60.00 7 5 SI2 0.9525 137.4424 SI3 L. O.B .OB .013 .0532 .0664 .0727 .09 .0933 .105 $Discrete energy distdlbution based on ga a energies fro Microshielld

.1091 . 12 .121 4 . 1408 .14 38 .1633 .1827 .1657 .1904

.1949 .2021 .2053 . 2214 SP3 7_ U.2e 3.166e7 1.201e7 7. 990e5 3 .478e5 4.273e4 1.060e6 $Gamma emi ssi on frequency fro Microshielld

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 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%

CALC NO. EPM017-CALC-001 ENERCON Dose Rate Near Uranium REV. 0 Excellence-Every pro1ect. E.very day. Treatment Train 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 F15:p 91.43 0 69. 19745 10 $Poi nt: Detector , mid height: of vesse1

one foot away F25:p 91.43 243 . 84 69. 19745 10 $Poi nt. Det:e ct:or , mid' height of vessel . one foot: a\ri*ay, 96" offset:

C $equ i v a l ent: to dose. contribution frr l ag vessel!

FM15 L 5045072E:6 $Tallly mul!t:iplierr equi valem: t:o S l.l t i on of a ll l ga a iss ion f r equencies FM25 2. 2567608e7 $source scaled to one teek of buildup i n l ag vessel!

C c A~S:I 6.1. 1 - 1977 Garr. 1Fll t.1x t:o Dose conversion Factors . usi ng us uni ts c ( re.m/ hr ) / (phot:ons / c m2 - s )

dfO n i 1 IC 20 $seperat:es tal ly into e ne r gy bins , app*li es conversion factors a nd 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 Dose Rate Near Uranium REV. 0 ENERCON Excellence-Every project Eve1y day. Treatment Train PAGE NO. 1 of 1 Attachment A MCNP6 Input

Cimmarron Resi n Bed Dose Esti mation c ce11s 10 2 - 0 . 485139 -100 imp p=l $Resin ( pol ystyrene) i nsi de vessel 50 1 10 100 i mp p=2 $SS .304 layer 11 1 101 10 "100 imp p--4 $SS 304 vessel clad 30 0 -300 101 imp p=8 $Void 40 0 300 i ,mp p=O $BOlmd ary c sur faces 100 RCC O O 0 .. 952 5 0 0 136 . 4 899 60. 007 5 $Interior cy linder of r esi n v essel

3/ 8" (O . 9525orn) off of f l oor to accomodat:e vessel clad 10 RCC O O 0 . 47625 0 0 136. %615 60 . 4 837 5 $Layer used for var i ance reduction 101 RCC O O O O O 1.38. 3949 60. 96 $Outer cyl inder of r esi n vessel 102 s !U . 43 0 69.19745 20 $Detector 1 void 103 S 91 . 43 243 . 84 69 . 1974 5 20 $Detector 2 void 300 RPP -65 100 - 65 250 0 150 $Bou ndi ng Area 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 $SS 304 16000 - 0.000150 24000 - 0 .190000 25000 -0.010000 26000 - 0. 701730 28000 *- 0. 092500 M2 1000 - 0.077421 6000 - 0.922579 $Polystyr ene 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 $Cylindriical sour ce l ocated i nside i nne r cyl inder SU O 60 . 0075 SI2 0 . 95 2 5 137 . 4424 SI3 L 0 . 13 . 013 . OB . 0532 . 0664 . 0 727 . 09 . 093.3 .105 $Discrete e nergy distribution based on gamma ene rgi es from Microshiel d

.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 7 8e5 4 .273e4 1.060e6 $Gamma emission freq uen cy from Microshi e l d

1. 732e6 8 . 014e5 5. B27 e5 5. 827e4 2. 712e5 8. 547 e 4 4 . 0 79e6 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 $Poi nt Detector , mid height of vessel, one foot: away F25:p 91 . 43 243 . 84 69.19745 10 $Poi nt: Detector, mid height of vesse 1 , one foot: away, 96 " offset C $equi valent to dose contribution from l ag vessel FM15 l.504507 2 E8 $Tally multiplier eq ui valent: to s ummat i on of all gamma emission frequ encies FM25 2. 2567608e7 $Sou r ce scaled to one week of buildup i n lag vessel C

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 e nergy bins , appl ies conver sion factor s and s ums

CALC NO. EPM017-CALC-001 Dose Rate Near Uranium 3ENERCON l::xrellence-Every pro;ect. Every day Treatment Train REV. 0 PAGE NO. 1 of 2 Attachment B Email Correspondence Caleb T'rainor from: Jai-Kael LllJle,' < (luey@l::llJlrion.com >

Se nt:: lrn.m:: dla~*,, Decem be r 03, 2015 11():38 AM To: *ateb Trainor Cc: Cha rie.s- Beatty; jlu1:<@e nvpm.co1(1nt; Ja- Kaef. uey

Subject:

RE: <IE>::lERNAIL> RE= Resin Vessell Dime1111:;;ronc If yo u an: doiing dose caffc11Jlati,ons use the folJ,o-wi n g i n lie11.11 of sp ecific informati,on {w i,dh m av b e proprveta ry frnm A\f ,Nlfiec!ll hru.'t I nave not !ha,d ,a, chi:llnce to ch,e,clk}.

11"-JaH , uckn e:5,5- .:li/ ,,, as istlhewalltlhiclmes:s.for r i*o,11 ' ssta1111dardl36- iriK vessel at h as.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 su re 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 Ji ke1this was no1ta u iti,rnl efe men: 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-e l {*it,hich is 48-nn c:hes ~-

ai-llCae l From : 1Calle:b TH UlflltDII" [ a.vl:ttci:c.tra.r1rmir@ern en::rnn.com]

Se nt: .u irsd'rf/Y, Deir:em lhu~r Cl!:ll_, 2!015 7:00, Alf/J lfo: Jill- aen LIJle'j' <JIIJ'e*1t @.k.urii1 111.1rnm>

Subje ct: RE: <EX.T'ERlt*t AiL> E:: Resiill VesseE[)rmelfllsuons Thank

o,u for t h e informatio n, this. 1.s mu,c!h cfoser to *what Rn e,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 'e rtal. I -aissu *e e 48'*'

spading is. e,dg,e to e cllge,. or 9*6*" on center, rnrre ct? 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 ! *m atelf\-* a or~t 5a!lfet1f rnncern, t110.t dlose.

From: Ja,Kael u-ey IT , aalto: jlueyr@k:uriot11.com]

Sent: 'W e dn es.cfay , De ir:emlo er 012, 2iD15 11:22 PM lio: C-.a fe b iran1111on,1r <ctrainor@ enerrnn.mm>

Cc:: -rnalflles ~e att, <cbeatty@e111 enrnn.com>; ilux@emrpm.com : ai-!Kaeli 1Lue11,1< jlu:ey@ urr-on.il:om,;;,

Subjed: <EXTIERNAIL> , E.: Resin V ess el Di m e lll.sion.s Please fin d attsc ed t in e drswinig tlhat is the basi s for the ISM Vessels u sed en lthe desrgri. l e spacing h1=twee n tlile

'!l'essets is 48" from the G e ne al Assem y drawin_g (! can pro11ide tlhe sp1=d-frc refe re n ce ,, ,hen Bam back il!ll the office lfhurs.da ff ','OU do noiit a11e the full sell: ). This s,eparation is based on m eeti ngs h e-Id with E111 ercon a n d not a1spe,ci *c-Cited dloci.Jment. f mm a spacing standpoint it would b e better if this could be smaller. e:s p ecially for the BA Unit sin ce* i:s fft into an e-11dosure.

Ja-Kaiel From: Ca1tie-b Trainor [ maiilito: ctrarnor@en ercon .com]

Sent.: W edn esday, ecemb er 02,, 20 5 5:34.

CALC NO. EPM017-CALC-001 Dose Rate Near Uranium REV. 0 ENERCON txcellence-Every proJect. Every day. Treatment Train PAGE NO. 2 of 2 To: Ja-1Kael uey <j~ue:y@ku *,r:mu: o :..,.

Cc: C a-rles Beatty <cbeatty~enercon .com>~jlux@e111vpm.com

Subject:

Re:si VesseJ Dii e n1sion1s Jl'll supp rt fi dose ca lc:ufatrons llllff e es iin *1,1,esseis.* II a Fnt eedl o ft e ve5seli d ~, e nsio 1s, v essel m ate f11I,, ai d spad 1g etl'leelll t he. v esse ls. 1 n e dles ig rrn dlra1. i rllgs II ihiave so fair o ly- deita1nll 1J: e p1iip,~111,g. a111cll ot 'th e ve:S.sek Ca.111 yo u 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 Dose Rate Near Uranium REV. 0 Excellence-Every project. £very doy. Treatment Train PAGE NO. 1 of 58 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

+-------------------------------------------------------------+

CALC NO. EPM017-CALC-001 ENERCON Dose Rate Near Uranium REV. 0 Excellence- Every projecr. Every day. Treatment Train PAGE NO. 2 of 58 1 mcnp version 6 ld=05/08/13 12/15/15 16:46:08

- - - - probid = 12/15/15 16:46:08 i=cim.txt o=cim.out tasks 8 warning. Physics models disabled.

1- Cimmarron Resin Bed Dose Estimation 2- c Cells 3- 10 2 -0.485139 -100 imp:p=1 $Resin (poly 4- 50 1 10 100 imp:p=2 $SS 304 laye 5- 11 1 101 10 100 imp:p=4 $SS 304 vess 6- 30 0 -300 101 imp:p=8 $Void 7- 40 0 300 imp:p=0 $Boundary 8-9- c Surfaces 10- 100 RCC 0 0 0.9525 0 0 136.4899 60.0075 $1 nterior cy 11- 10 RCC 0 0 0.47625 0 0 136.96615 60.48375 $Layer used 12- 101 RCC 0 0 0 0 0 138.3949 60.96 $Outer cylin 13- 102 S 91.43 0 69.19745 20 $Detector 1 14- 103 S 91.43 243.84 69 .19745 20 $Detector 2 15- 300 RPP -65 100 -65 250 0 150 $Bounding Ar 16-17- c Data 18- Mode P 19- nps 10e6 20- C 21- c Material Definitions 22- M1 6000 -0.000400 14000 -0.005000 15000 -0.000230 $SS 304 23- 16000 -0.000150 24000 -0 .190000 25000 -0.010000 24- 26000 -0 .701730 28000 -0.092500 25- M2 1000 -0.077421 6000 -0 .922579 $Polystyrene 26- C 27- c Source Definition

CALC NO. EPM017-CALC-001 ENERCON Dose Rate Near Uranium REV. 0 Excellence- Every pro1~ct. Every doy. Treatment Train PAGE NO. 3 of 58 28- SDEF PAR=P axs=0 0 1 pos=0 0 0 rad=d1 ext=d2 erg=d3 cel=10 $Cylindrical 29- SI 1 0 60.0075 30- Sl2 0.9525 137.4424 31- Sl3 L 0.13 .013 .013 .0532 .0664 .0727 .09 .0933 .105 $Discrete en 32- .1091 .12 .1214 .1408 .1438 .1633 .1827 .1857 .1904 33- .1949 .2021 .2053 .2214 34- SP3 7.112e7 3.166e7 1.201 e7 7.990e5 3.478e5 4.273e4 1.060e6 $Gamma emiss 35- 1.732e6 8.014e5 5.827e5 5.827e4 2.712e5 8.547e4 4.079e6 36- 1.826e6 1.554e5 2.098e7 3.572e5 2.292e5 3.885e5 1.826e6 37- 3.885e4 38- C 39- c Tally Definition 40- F15:p 91.43 0 69.1974510 $Point Detec 41- F25:p 91.43 243.84 69.19745 10 $Point Detec 42- C $equivalent 43- FM15 1.5045072E8 $Tally multi 44- FM25 2.2567608e7 $Source seal 45- C 46- c ANSI 6.1.1-1977 Gamma Flux to Dose Conversion Factors, using US units 47- c (rem/hr)/(photons/cm2-s) 48- 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.

1cells print table 60 atom gram photon cell mat density density volume mass pieces importance

CALC NO. EPM017-CALC-001 Dose Rate Near Uranium REV. 0 ENERCON Excellenc,:- Every proJect. Every day. Treatment Train PAGE NO. 4 of 58 1 10 2 4.48803E-02 4.85139E-01 1.54405E+06 7.49079E+05 1 1.0000E+00 2 50 1 8.76841 E-02 8.00000E+00 3.00795E+04 2.40636E+05 1 2.0000E+00 3 11 1 8.76841E-02 8.00000E+00 4.15670E+04 3.32536E+05 1 4.0000E+00 4 30 0 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 0 8.0000E+00 5 40 0 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 0 0.0000E+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 .

minimum source weight= 1.0000E+00 maximum source weight= 1.0000E+00

Random Number Generator = 1*

Random Number Seed = 19073486328125 *

Random Number Multiplier= 19073486328125 *

Random Number Adder = 0*

Random Number Bits Used = 48 *

Random Number Stride = 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.

1cross-section tables print table 100 XSDIR used: C:\MCNP\MCNP _DATA/xsdir_mcnp6.1

CALC NO. EPM017-CALC-001 nENERCON Dose Rate Near Uranium REV. 0 Excellenc,:- Every projecr. tvery doy. Treatment Train PAGE NO. 5 of 58 table length tables from file xdata/mcplib84 1000.84p 1974 Update of MCPLIB04 Photon Compton Broadening Data For MCNP5 see LA-UR- 12-00018 01 /03/12 6000.84p 3228 Update of MCPLI 804 Photon Compton Broadening Data For MCNP5 see LA-UR- 12-00018 01 /03/12 14000.84p 4868 Update of MCPLIB04 Photon Compton Broadening Data For MCNP5 see LA-UR- 12-00018 01 /03/12 15000.84p 4574 Update of MCPLIB04 Photon Compton Broadening Data For MCNP5 see LA-UR- 12-00018 01 /03/12 16000.84p 4730 Update of MCPLIB04 Photon Compton Broadening Data For MCNP5 see LA-UR- 12-00018 01/03/12 24000.84p 5758 Update of MCPLIB04 Photon Compton Broadening Data For MCNP5 see LA-UR- 12-00018 01/03/12 25000.84p 5674 Update of MCPLIB04 Photon Compton Broadening Data For MCNP5 see LA-UR- 12-00018 01/03/12 26000.84p 5794 Update of MCPLIB04 Photon Compton Broadening Data For MCNP5 see LA-UR- 12-00018 01/03/12 28000.84p 5902 Update of MCPLIB04 Photon Compton Broadening Data For MCNP5 see LA-UR- 12-00018 01/03/12 total 42502 maximum photon energy set to 100.0 mev (maximum electron energy) tables from file xdata/el03 1000.03e 2329 6/6/98 6000. 03e 2333 6/6/98 14000.03e 2339 6/6/98 15000.03e 2339 6/6/98 -

16000.03e 2339 6/6/98 24000.03e 2345 6/6/98 25000.03e 2345 6/6/98 26000.03e 2345 6/6/98 28000.03e 2347 6/6/98 1particles and energy limits print table 101 particle maximum smallest largest always always cutoff particle table table use table use model

CALC NO. EPM017-CALC-001

._-. E N E R C O N Dose Rate Near Uranium REV. 0 Excellence- Every pro1ec1. Every doy. Treatment Train PAGE NO. 6 of 58 particle type energy energy maximum maximum below above 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 6 117 6 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 2 36 6 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 4 67 6 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 3 45 6 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 4 79 6 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 8 111 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc

CALC NO. EPM017-CALC-001 ENERCON Dose Rate Near Uranium REV. 0 Excellence--hery proJecl. Every day Treatment Train PAGE NO. 7 of 58 2 7.3518E-05 2.5000E-01 8.4093E+01 8.6295E-02 2.0433E+02 1.0000E+01 1.1394E-01 11 267347 4 66 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 1.6404E-03 1.0000E+00 2.5645E+02 2.3748E+00 4.8113E+01 1.0000E+01 1. 7341 E-01 10 275363 3 54 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 1.4661 E-03 2.5000E-01 6.2765E+01 5.1569E-01 3.1892E+01 1.0000E+01 1.1387E-01 11 289480 3 65 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 4. 7999E-04 2.5000E-01 4.1311 E+01 1.1433E+00 3.3039E+01 1.0000E+01 9.5904E-02 11 295930 3 60 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 5.3206E-03 2.5000E-01 1.4027E+02 7.2495E-02 3.1234E+01 1.0000E+01 1.8570E-01 11 313718 3 41 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 7.5842E-05 2.5000E-01 8.3107E+01 1.0047E-02 2.0776E+02 1.0000E+01 1.0709E-01 11 385577 4 71 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 1.4009E-04 2.5000E-01 2.5325E+02 4.0166E-01 2.1940E+02 1.0000E+01 1. 7177E-01 11 388463 5 65 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 4.8092E-04 2.5000E-01 1.5055E+01 1.2837E-01 3.3098E+01 1.0000E+01 1.1808E-01 11 397905 3 61 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 6.9698E-05 5.0000E-01 1.3953E+02 1.3767E+00 2.0052E+02 1.0000E+01 1.3000E-01 50 571314 2 42 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 5.6973E-04 2.5000E-01 7.3557E+01 1.4935E+00 3.3967E+01 1.0000E+01 9.3916E-02 11 573255 6 88 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 2.9775E-03 2.5000E-01 8.8545E+01 1.9940E-01 3.1134E+01 1.0000E+01 1.0968E-01 11 674671 13 254 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 3.4525E-03 2.5000E-01 1.1223E+02 1.9960E-01 3.2548E+01 1.0000E+01 1.3000E-01 11 717579 2 48 6

CALC NO. EPM017-CALC-001

,u ENERCON Dose Rate Near Uranium REV. 0 Excellence- Every pro1ect. Every doy. Treatment Train PAGE NO. 8 of 58 det t wg t psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 6.2456E-04 5.0000E-01 3.2244E+01 1.4263E+00 3.1413E+01 1.0000E+01 1.2246E-01 50 726168 3 45 6 det t wg t psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 1.6632E-04 1.0000E+00 2.2685E+02 1.6681 E+00 2.0234E+02 1.0000E+01 1.4318E-01 10 812481 3 60 6 det t wg t psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 5.3368E-04 1.0000E+00 8.8019E+01 2.6691 E+00 4.2655E+01 1.0000E+01 1.3000E-01 10 860193 1 13 6 det t wg t psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 8.1664E-05 2.5000E-01 1.1185E+02 2.6078E-01 2.0491 E+02 1.0000E+01 1.8570E-01 11 864981 1 21 6 det t wg t psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 1.5431 E-03 2.5000E-01 5.5340E+01 2.4316E-01 3.3450E+01 1.0000E+01 1.0500E-01 11 874440 6 101 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 5.2532E-04 2.5000E-01 1.5099E+01 4.8062E-02 3.3015E+01 1.0000E+01 1.3000E-01 11 911985 1 15 6 det t wg t psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 4.8100E-04 2.5000E-01 1.5132E+01 1.3574E-01 3.3059E+01 1.0000E+01 1.3000E-01 11 911985 2 23 6 det t wg t psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 1.5455E-03 2.5000E-01 7.6267E+01 5.5582E-01 3.3559E+01 1.0000E+01 9.8397E-02 11 959316 5 95 6 det t wg t psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 6.8770E-05 2.5000E-01 9.9724E+01 2.981 0E-01 2.0694E+02 1.0000E+01 1.2357E-01 11 991642 2 37 6 det t wg t psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 1.9707E-03 2.5000E-01 7.4492E+01 1.5406E-01 3.5907E+01 1.0000E+01 1.4937E-01 11 1035243 4 59 6 det t wg t psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 1.1657E-03 2.5000E-01 7.1482E+01 6.2134E-01 3.6204E+01 1.0000E+01 1.4937E-01 11 1035243 5 67 6

CALC NO. EPM017-CALC-001 ENERCON Dose Rate Near Uranium REV. 0 Excellence-Every pro1ect. tvery doy. Treatment Train PAGE NO. 9 of 58 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 6.7144E-04 5.0000E-01 6.2578E+01 1.6644E+00 3.7469E+01 1.0000E+01 1.4380E-01 50 1078642 5 86 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 9.4945E-05 2.5000E-011 .7751E+02 5.5729E-01 2.0641E+021.0000E+011.8018E-01 11 1087746 3 65 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 8.7006E-04 2.5000E-01 2.9759E+01 1.4314E-01 3.4342E+01 1.0000E+01 1.2527E-01 11 1111829 7 110 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 4. 7657E-04 2.5000E-01 2.9136E+01 7.0819E-01 3.4614E+01 1.0000E+01 1.2527E-01 11 1111829 9 129 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 1.4361 E-03 2.5000E-01 8.6140E+01 2.7980E-01 4.2475E+01 1.0000E+01 1.2024E-01 11 1169084 4 84 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 5.0758E-04 2.5000E-01 2.4111 E+01 2.5089E-01 3.8349E+01 1.0000E+01 1.1081 E-01 11 1204350 5 99 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 7.1728E-04 5.0000E-01 9.5580E+01 1.9686E+00 3.8483E+01 1.0000E+01 1.4930E-01 50 1232639 3 59 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 7.5601 E-05 5.0000E-01 1.0312E+02 9.9309E-01 2.0052E+02 1.0000E+01 1.3000E-01 50 1318369 1 17 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 5.6998E-04 2.5000E-01 4.5313E+01 9.8667E-01 3.4341 E+01 1.0000E+01 1.0458E-01 11 1385745 4 88 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 6.6728E-05 1.0000E+00 9.3301 E+01 1.6266E+00 2.0916E+02 1.0000E+01 1.6869E-01 10 1395745 3 70 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 5.5334E-04 2.5000E-01 1.5005E+01 8.8175E-02 3.1430E+01 1.0000E+01 1.3375E-01 11 1430896 3 46 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc

CALC NO. EPM017-CALC-001

.. ENERCON Dose Rate Near Uranium REV. 0 Excellence- Every proJecr. Every doy. Treatment Train PAGE NO. 10 of 58 1 1.0282E-03 5.0000E-01 5.9984E+01 1.4429E+00 3.3116E+01 1.0000E+01 1.3000E-01 50 1572051 6 108 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 6.6336E-05 2.5000E-01 8.0864E+01 1.8158E-01 2.0112E+02 1.0000E+01 1.0217E-01 11 1588704 4 85 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 5.0668E-04 2.5000E-01 2.5289E+01 5.6608E-01 3.3578E+01 1.0000E+01 1.7126E-01 11 1655950 7 102 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 6.3800E-04 2.5000E-01 2.5121 E+01 3.3871 E-01 3.3414E+01 1.0000E+01 1. 7126E-01 11 1655950 8 110 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 8.5434E-04 2.5000E-01 2.4413E+01 1.4079E-01 3.1427E+01 1.0000E+01 1.8570E-01 11 1664001 3 39 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 4.9346E-04 2.5000E-01 1.9930E+01 1.3594E-01 3. 7453E+01 1.0000E+01 1.8570E-01 11 1695063 1 20 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 1.1612E-03 5.0000E-01 1.2665E+02 1.8239E+00 3. 7428E+01 1.0000E+01 1.4380E-01 50 1771399 6 99 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 5.2350E-04 2.5000E-01 7.0521 E+01 1.5161 E+00 3.4306E+01 1.0000E+01 9.8239E-02 11 1782361 16 292 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 9.3573E-05 2.5000E-01 1.0677E+02 5.8288E-02 2.0695E+02 1.0000E+01 1.1075E-01 11 1800281 2 40 6 det t wgt psc amfp ddetx radius

erg cell nps nch p nrn ipsc 1 5.0019E-04 2.5000E-01 3.6268E+01 4.2032E-01 4.3531 E+01 1.0000E+01 1.2915E-01 11 1811526 13 236 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 5.2333E-04 2.5000E-01 2.9283E+01 2.1129E-01 4.2454E+01 1.0000E+01 1. 7037E-01 11 1833593 8 136 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 1.5870E-04 5.0000E-01 1.6024E+02 6.9714E-01 2.0004E+02 1.0000E+01 1.7501 E-01 50 1869062 2 38 6

CALC NO. EPM017-CALC-001 UENERCON Dose Rate Near Uranium REV. 0 Excellence--Every pro1ect. Every doy. Treatment Train PAGE NO. 11 of 58 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 7.5992E-04 2.5000E-01 4.3218E+01 7.8143E-01 3.2184E+01 1.0000E+01 1.0812E-01 11 1925119 4 58 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 9.3520E-04 2.5000E-01 3.2528E+01 9.9967E-02 3.5387E+01 1.0000E+01 1.3000E-01 11 1925442 2 26 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 1.5937E-04 2.5000E-01 2.2703E+02 3.1759E-01 2.0312E+02 1.0000E+01 1.8570E-01 11 1956285 8 105 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 4.7675E-04 5.0000E-01 2.4336E+01 1.2345E+00 3.4381 E+01 1.0000E+01 1.8570E-01 50 2159382 3 40 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 2.0617E-03 5.0000E-01 9.7782E+01 1.0548E+00 3.6255E+01 1.0000E+01 1.4656E-01 50 2166494 2 40 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 5.4699E-04 5.0000E-01 9.1756E+01 2.0320E+00 4.1829E+01 1.0000E+01 1.4091 E-01 50 2183252 5 80 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 6.1567E-04 2.5000E-01 5.8573E+01 1.0186E+OO 3.6971 E+01 1.0000E+01 9.2406E-02 11 2319969 7 124 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 1.2852E-03 2.5000E-01 1.3956E+02 7.2292E-01 4.5792E+01 1.0000E+01 1.8570E-01 11 2334214 2 44 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 1.1976E-03 5.0000E-01 5.3714E+01 1.2483E+00 3.2005E+01 1.0000E+01 1.2771 E-01 50 2355712 4 71 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 1.1893E-03 5.0000E-01 8.8997E+01 1.4704E+00 3.6995E+01 1.0000E+01 1.2044E-01 50 2443068 2 41 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 1.6740E-03 5.0000E-01 1.2254E+02 1.6349E+00 3.3701 E+01 1.0000E+01 1.3000E-01 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

CALC NO. EPM017-CALC-001

~-- ENERCON Dose Rate Near Uranium REV. 0 Excellence- Eve ry p roJen. Every doy. Treatment Train PAGE NO. 13 of 58 1 5.8600E-04 2.5000E-01 7.7180E+01 1.0494E+00 4.2836E+01 1.0000E+01 1.3000E-01 11 3134216 7 87 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 4.8181 E-04 2.5000E-01 3.0576E+01 2.9797E-01 4.3294E+01 1.0000E+01 1.3000E-01 11 3161023 1 15 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 5.4533E-04 2.5000E-01 4.4832E+01 1.0679E+00 3.3531 E+01 1.0000E+01 1.0656E-01 11 3185384 9 161 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 6.3824E-05 2.5000E-01 7.9431 E+01 1.8690E-01 2.0267E+02 1.0000E+01 1.3000E-01 11 3185455 3 35 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 5.9247E-04 2.5000E-01 3.7973E+01 6.9944E-01 3.5596E+01 1.0000E+01 1.2844E-01 11 3195092 2 36 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 8.7236E-04 2.5000E-01 5.6743E+01 7.8042E-01 3.4437E+01 1.0000E+01 1.3000E-01 11 3220944 11 193 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 5.7987E-04 2.5000E-01 6.0033E+01 1.0150E+00 3.8636E+01 1.0000E+01 1.2286E-01 11 3245009 2 36 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 4.6707E-04 5.0000E-01 3.4993E+01 1.3552E+00 3.9211 E+01 1.0000E+01 1.6379E-01 50 3276500 2 36 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 4.8260E-04 5.0000E-01 3.1520E+01 1.4794E+00 3.4406E+01 1.0000E+01 1.2549E-01 50 3347693 4 71 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 5.1747E-04 5.0000E-01 4.9909E+01 1.4486E+00 4.2460E+01 1.0000E+01 1.3669E-01 50 3357499 4 90 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 1.2658E-03 5.0000E-01 8.5492E+01 1.4898E+00 3.4807E+01 1.0000E+01 1.3000E-01 50 3361939 1 16 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 1.3289E-03 2.5000E-01 8.5079E+01 7.6544E-01 3.4421 E+01 1.0000E+01 1.3000E-01 11 3361939 5 57 6

CALC NO. EPM017-CALC-001 ENERCON Dose Rate Near Uranium REV. 0 Excellencr:- Every proJect. Every doy. Treatment Train PAGE NO. 14 of 58 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 1.1435E-03 2.5000E-01 7.2440E+01 4.1929E-01 4.0711 E+01 1.0000E+01 1.2771 E-01 11 3367095 2 34 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 8.5953E-04 5.0000E-01 8.8525E+01 2.0934E+00 3.1785E+01 1.0000E+01 1.0117E-01 50 3394891 2 41 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 7.4288E-05 5.0000E-01 9.8099E+01 9.3087E-01 2.0353E+02 1.0000E+01 1.8570E-01 50 3442182 2 39 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 1.3308E-03 2.5000E-01 1.2372E+02 8.8648E-01 3.9043E+01 1.0000E+01 1.5373E-01 11 3537462 12 232 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 5.0014E-04 2.5000E-01 3.3212E+01 2.3959E-01 4.5599E+01 1.0000E+01 1.3000E-01 11 3539926 2 27 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 5.3956E-04 5.0000E-01 2.1833E+01 1.1026E+OO 3.2697E+01 1.0000E+01 1.8570E-01 50 3545089 1 14 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 5.6292E-04 2.5000E-01 1.6586E+01 1.1803E-01 3.2278E+01 1.0000E+01 1.8283E-01 11 3650364 2 35 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 2.2950E-03 2.5000E-01 9.2796E+01 3.3100E-01 3.3992E+01 1.0000E+01 1.3000E-01 11 3650975 3 33 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 9. 7066E-05 1.0000E+00 2.6143E+02 2.2765E+00 2.0976E+02 1.0000E+01 1.3000E-01 10 3654321 1 16 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 1.1695E-03 2.5000E-01 5.1011 E+01 6.0644E-01 3.0763E+01 1.0000E+01 1.1012E-01 11 3848369 4 73 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 6.6962E-04 2.5000E-01 7.6065E+01 8.3818E-01 4.4213E+01 1.0000E+01 1.7413E-01 11 3905496 4 71 6

CALC NO. EPM017-CALC-001

'--ENERCON Dose Rate Near Uranium REV. 0 Excellence- hery proJec:t. Every day. Treatment Train PAGE NO. 15 of 58 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 9.6599E-05 2.5000E-01 1.1998E+02 1.0080E-01 2.1137E+02 1.0000E+01 1.8479E-01 11 3906556 2 32 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 6.7549E-05 2.5000E-01 9.7349E+01 2.9342E-01 2.0679E+02 1.0000E+01 1.3000E-01 11 3907053 6 109 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 7.7800E-05 2.5000E-01 1.0680E+02 3.0907E-01 2.0024E+02 1.0000E+01 1.0923E-01 11 3921665 7 112 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 8.6059E-04 1.0000E+00 4.1885E+01 1.6285E+00 3.8987E+01 1.0000E+01 1.8570E-01 10 3930467 1 13 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 3.2872E-03 2.5000E-01 2.5142E+02 7.6437E-01 3. 7643E+01 1.0000E+01 1.8570E-01 11 4059754 2 41 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 5.4959E-04 5.0000E-01 7.4183E+01 2.1380E+00 3.5585E+01 1.0000E+01 1.2589E-01 50 4079838 3 59 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 9.3644E-04 5.0000E-01 4.5728E+01 1.0991 E+00 3.5982E+01 1.0000E+01 1.8570E-01 50 4 156195 1 14 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 7.2649E-04 5.0000E-01 4.6224E+01 1.3520E+00 3.6194E+01 1.0000E+01 1.8570E-01 50 4 156195 5 69 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 1.3817E-03 2.5000E-01 5.9445E+01 3.0319E-01 3.5554E+01 1.0000E+01 9.3136E-02 11 4159952 6 103 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 2.0539E-03 5.0000E-01 1.1802E+02 1.2470E+00 3.6250E+01 1.0000E+01 1.3000E-01 50 4171884 1 16 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 5.3407E-04 5.0000E-01 4.4289E+01 1.3847E+00 4.0649E+01 1.0000E+01 1.3000E-01 50 4 182657 1 14 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc

CALC NO. EPM017-CALC-001 ENERCON Dose Rate Near Uranium REV. 0 Excellence- Eve ry pro1ec:r. Every doy. Treatment Train PAGE NO. 16 of 58 1 6.2597E-04 5.0000E-01 5.3306E+01 1.6796E+00 3.5545E+01 1.0000E+01 1.5492E-01 50 4265308 2 35 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 1.2845E-04 2.5000E-01 1.3873E+02 4.2095E-02 2.0298E+02 1.0000E+01 1.8570E-01 11 4310093 4 64 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 7.0270E-04 2.5000E-01 2.8470E+01 3.4209E-01 3.3838E+01 1.0000E+01 1.3000E-01 11 4328280 2 23 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 6.2254E-04 5.0000E-01 7.6286E+01 1.5238E+00 4.6095E+01 1.0000E+01 1.4380E-01 50 4354629 1 14 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 5.1419E-04 5.0000E-01 1.9935E+01 9.4154E-01 3.4688E+01 1.0000E+01 2.0530E-01 50 4398274 1 14 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 1.3410E-03 1.0000E+00 2.7016E+02 2.7793E+00 4.4615E+011.0000E+011.2317E-01 10 4535430 2 36 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 1.9512E-03 5.0000E-01 1.2248E+02 1.6198E+00 3.1444E+01 1.0000E+01 1.2842E-01 50 4573242 9 197 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 1.0099E-04 5.0000E-01 1.9850E+02 1.2931 E+00 2.0718E+02 1.0000E+01 1.8570E-01 50 4594708 2 24 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 6.2792E-04 5.0000E-01 4.3828E+01 1.4149E+00 3.6735E+01 1.0000E+01 1.1670E-01 50 4608539 2 41 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 4. 7662E-04 1.0000E+00 1.4555E+02 3.4950E+00 3.8406E+01 1.0000E+01 1.0012E-01 10 4613891 3 62 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 6. 7040E-04 5.0000E-01 4.4527E+01 1.4417E+00 3.5358E+01 1.0000E+01 1.3000E-01 50 4681007 5 52 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 7.3379E-05 1.0000E+00 7.0702E+01 1.2945E+00 2.0499E+02 1.0000E+01 1.8570E-01 10 4684360 1 16 6

CALC NO. EPM017-CALC-001 ENERCON Dose Rate Near Uranium REV. 0

!:xcellencr:-Every pro1ect. Every doy. Treatment Train PAGE NO. 17 of 58 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 1.0558E-03 2.5000E-01 4.6122E+01 2.6416E-01 3.6532E+01 1.0000E+01 1.3000E-01 11 4703340 2 32 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 1.5123E-03 2.5000E-01 8.6092E+01 8.4980E-01 3.1118E+01 1.0000E+01 1.3000E-01 11 4712733 2 23 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 1.7255E-03 2.5000E-01 8.5665E+01 7.1743E-01 3.1048E+01 1.0000E+01 1.3000E-01 11 4712733 7 97 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 2.9430E-03 2.5000E-01 1.1299E+02 2.5841 E-01 3.4348E+01 1.0000E+01 1.4855E-01 11 4764056 8 137 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 1 6.1087E-04 2.5000E-01 2.3456E+01 3.8734E-02 3.8338E+01 1.0000E+01 1.1820E-01 11 4768139 6 100 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 8.9505E-05 2.5000E-01 9.3860E+01 3.4463E-02 2.0078E+02 1.0000E+01 1.8570E-01 11 4879138 1 15 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 9.3422E-05 2.5000E-01 1.7357E+02 3.4902E-01 2.2835E+02 1.0000E+01 1.6992E-01 11 4985150 7 106 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 7.9443E-05 2.5000E-01 1.3739E+02 5.1180E-01 2.0309E+02 1.0000E+01 1.2469E-01 11 5166101 16 311 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 6.3427E-05 5.0000E-01 1.4501 E+02 1.3501 E+00 2.1716E+02 1.0000E+01 1.8570E-01 50 5240953 1 23 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 9.2058E-05 2.5000E-01 1.2053E+02 2.2794E-01 2.0366E+02 1.0000E+01 1.8570E-01 11 5309294 1 17 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 8.1922E-05 2.5000E-01 1.0587E+02 2.1140E-01 2.0402E+02 1.0000E+01 1.3000E-01 11 5507091 5 73 6

CALC NO. EPM017-CALC-001 Dose Rate Near Uranium REV. 0 ENERCON Excellem:e- Every proJee/. Every day. Treatment Train PAGE NO. 18 of 58 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 7.1386E-05 2.5000E-01 1.6026E+02 6.6252E-01 2.1460E+02 1.0000E+01 1.6330E-01 11 5607881 4 52 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 1.2320E-04 5.0000E-01 1.5423E+02 8.2608E-01 2.0883E+02 1.0000E+01 1.6773E-01 50 5742616 4 95 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 6.7748E-05 2.5000E-01 1.4851 E+02 6.1173E-01 2.1751E+021.0000E+01 1.6067E-01 11 5798661 6 98 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 1.4616E-04 5.0000E-01 2.5270E+02 1.1450E+00 2.0924E+02 1.0000E+01 1.8570E-01 50 5941969 1 15 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 6.3250E-05 5.0000E-01 1.0746E+02 1.1696E+00 2.0489E+02 1.0000E+01 1.5957E-01 50 6106548 3 63 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 7.7663E-05 2.5000E-01 1.1530E+02 3.6248E-01 2.0275E+02 1.0000E+01 1.3000E-01 11 6122751 3 40 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 8.2003E-05 5.0000E-01 8.5367E+01 6.7714E-012.0516E+021 .0000E+01 1.7525E-01 50 6128781 6 107 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 8.0096E-05 2.5000E-01 8.1642E+01 1.4839E-02 1.9990E+02 1.0000E+01 1.3000E-01 11 6301952 1 16 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 7. 7647E-05 2.5000E-01 1.1386E+02 2.1132E-01 2.1732E+02 1.0000E+01 1.6915E-01 11 6325708 2 44 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 8.0105E-05 2.5000E-01 9. 7521 E+01 9.2966E-02 2.1009E+02 1.0000E+01 1.2952E-01 11 6569431 8 143 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 6.3612E-05 5.0000E-01 9.4114E+01 1.0530E+00 2.0267E+02 1.0000E+01 1.3000E-01 50 6864922 1 15 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc

CALC NO. EPM017-CALC-001 Dose Rate Near Uranium REV. 0 ENERCON Treatment Train Excellence-Every pro;ect. Every doy.

PAGE NO. 19 of 58 2 8.5899E-05 2.5000E-01 9.9501 E+01 5.7195E-02 2.0863E+02 1.0000E+01 1.3000E-01 11 6957752 3 47 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 8.3686E-05 2.5000E-01 1.8246E+02 6.7611 E-01 2.1005E+02 1.0000E+01 1.8570E-01 11 6982788 1 22 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 1.4716E-04 5.0000E-01 1.8785E+02 8.4998E-01 2.0837E+02 1.0000E+01 1.4865E-01 50 7006398 5 97 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 8.07 44E-05 1.0000E+00 2.2806E+02 2.3206E+00 2.1012E+02 1.0000E+01 1.3000E-01 10 7015682 1 14 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 7.7876E-05 2.5000E-01 9.8330E+01 2.0527E-01 2.0228E+02 1.0000E+01 1.0346E-01 11 7071106 7 116 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 7.8800E-05 2.5000E-01 1.1116E+02 2.6310E-01 2.0772E+02 1.0000E+01 1.4380E-01 11 7237656 3 44 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 8.2322E-05 2.5000E-01 9.5347E+01 6.8997E-02 2.0739E+02 1.0000E+01 1.0388E-01 11 7430193 8 150 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 7.0185E-05 5.0000E-01 1.4111 E+02 1.3704E+00 2.0159E+02 1.0000E+01 1.2327E-01 50 7480406 3 46 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 1.9834E-04 5.0000E-01 2.8574E+02 9.6830E-01 2.0865E+02 1.0000E+01 2.021 0E-01 50 7980777 6 106 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 8.0021 E-05 2.5000E-01 1.0923E+02 2.7107E-01 2.0351 E+02 1.0000E+01 1.3000E-01 11 7983577 6 88 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 1.0526E-04 2.5000E-01 1.3134E+02 4.5678E-02 2.1778E+02 1.0000E+01 1.2624E-01 11 8224664 6 117 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 8.7746E-05 2.5000E-01 1.0136E+02 7.5749E-02 2.0642E+02 1.0000E+01 1.8570E-01 11 8660330 2 35 6

CALC NO. EPM017-CALC-001

.. ENERCON Dose Rate Near Uranium REV. 0 Exc:ellencl.'- fvery p rojec:r. Every doy Treatment Train PAGE NO. 20 of 58 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 8. 7664E-05 2.5000E-01 1.1636E+02 7.3317E-02 2.2154E+02 1.0000E+01 1.6760E-01 11 8932238 8 138 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 7.1299E-05 5.0000E-01 1.2433E+02 1.2120E+00 2.0321E+021.0000E+01 1.2898E-01 50 9142262 5 67 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 6.6424E-05 2.5000E-01 9.6398E+01 3.4061 E-01 2.0267E+02 1.0000E+01 1.0685E-01 11 9325623 14 248 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 7.6836E-05 2.5000E-01 9.5882E+01 2.1270E-01 2.0034E+02 1.0000E+01 1.0768E-01 11 9602391 10 167 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 1.0410E-04 2.5000E-01 1.4581 E+02 2.4234E-01 2.0913E+02 1.0000E+01 1.4970E-01 11 9649833 4 82 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 7.4218E-05 2.5000E-01 8.0648E+01 7.2804E-02 2.0050E+02 1.0000E+01 1.4349E-01 11 9681295 5 94 6 det t wgt psc amfp ddetx radius erg cell nps nch p nrn ipsc 2 6.6683E-05 5.0000E-01 1.1436E+02 1.1936E+00 2.0340E+02 1.0000E+01 1.3000E-01 50 9952165 1 16 6 1problem summary run terminated when 10000000 particle histories were done.

+ 12/15/15 16:50:13 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 1609553 4.0239E-02 5.5397E-03 nucl. interaction 0 0. 0. energy cutoff 0 0. 4.5751 E-06 particle decay 0 0. 0. time cutoff 0 0. 0.

weight window 0 0. 0. weight window 0 0. 0.

CALC NO. EPM017-CALC-001 ENERCON Dose Rate Near Uranium REV. 0 txcellence- Every pro1ect. Every day. Treatment Train PAGE NO. 21 of 58 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 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 Dose Rate Near Uranium REV. 0 Excellenci:- Every proJecc. Every ooy. Treatment Train PAGE NO. 22 of 58 number of histories processed by each thread 1312074 1201267 1259672 1299659 1294866 1282904 1264634 1084924 1photon 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) 1 10 10322059 10193584 50738870 5.0739E+00 8.3033E-02 8.3033E-02 1.0000E+00 1.1545E+01 2 50 9023654 8922895 13144162 6.5721E-01 1.1558E-01 1.1558E-01 1.0000E+00 4.3220E-01 3 11 6437568 6528077 9761147 2.4403E-01 1.2524E-01 1.2524E-01 1.0000E+00 4.8793E-01 4 30 1376517 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 1tally 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

CALC NO. EPM017-CALC-001

... ENERCON Dose Rate Near Uranium REV. 0 Excellence- Every pro1e,r. Every day. Treatment Train PAGE NO. 23 of 58 1.00000E+00 2782476 0.78225 4.22849E-08 0.11571 2.00000E+00 480224 0.85973 3. 02936E-08 0.18381 5.00000E+00 443038 0.93120 6.23896E-08 0.32405 1.00000E+01 215883 0.96603 6.75746E-08 0.47595 1.00000E+02 202626 0.99871 1.84876E-07 0.89153 1.00000E+03 2350 0.99909 2.79066E-08 0.95426 1.00000E+38 195 0.99913 2.03054E-08 0.99991 before dd roulette 5422 1.00000 4.07592E-11 1.00000 average tally per history = 4.44862E-07 largest score = 5.32061 E-03 (largest score)/(average tally)= 1.19601 E+04 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 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 Dose Rate Near Uranium REV. 0 fxcel lence-fvery proJect. Every ooy. Treatment Train PAGE NO. 24 of 58 tfc bin --mean-- ---------relative error--------- ----variance of the variance---- --figure of merit-- -pdf-behavior behavior value decrease decrease rate value decrease decrease rate value behavior slope 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: -----

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 1analysis 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 efficiency for the nonzero tallies = 0.3041 history number of largest tally = 313718 largest unnormalized history tally= 3.74298E-01 (largest tally)/(average tally) = 1.56455E+04 (largest tally)/(avg nonzero tally)= 4.75705E+03 (confidence interval shift)/mean = 0.0003 shifted confidence interval cente r = 2.39305E-05

CALC NO. EPM017-CALC-001

._-. E N E R C O N Dose Rate Near Uranium REV. 0 Excellence- Every proJecr. £very doy. Treatment Train 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 value at nps+1 value(nps+1 )/value(nps)-1.

mean 2.39237E-05 2.39611 E-05 0.001564 relative error 5.47129E-03 5.68168E-03 0.038452 variance of the variance 1.90457E-02 2.19879E-02 0.154486 shifted center 2.39305E-05 2.39314E-05 0.000038 figure of merit 1.41191 E+02 1.30928E+02 -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 1tally 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

CALC NO. EPM017-CALC-001 ENERCON Dose Rate Near Uranium REV. 0 Excellencr:-Every pro1ecr. Every day. Treatment Train PAGE NO. 26 of 58 1.00000E+00 4570832 0.75986 1.01499E-08 0.19169 2.00000E+00 976550 0.86165 8.59433E-09 0.33098 5.00000E+00 959927 0.96169 1.86191 E-08 0.63274 1.00000E+01 304493 0.99343 1.27090E-08 0.83871 1.00000E+02 55103 0.99917 6.01146E-09 0.93614 1.00000E+03 2382 0.99942 3.38705E-09 0.99104 1.00000E+38 61 0.99943 5.47142E-10 0.99990 before dd roulette 5491 1.00000 5.86511 E-12 1.00000 average tally per history= 6.17012E-08 largest score = 1.98339E-04 (largest score)/(average tally)= 3.21450E+03 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 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 Dose Rate Near Uranium REV. 0 Excellence- Every proJecr. Every doy. Treatment Train PAGE NO. 27 of 58 tfc bin --mean-- ---------relative error--------- ----variance of the variance---- --figure of merit-- -pdf-behavior behavior value decrease decrease rate value decrease decrease rate value behavior slope 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: -----

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 1analysis 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 efficiency for the nonzero tallies = 0.4079 history number of largest tally = 7980777 largest unnormalized history tally = 2.28189E-03 (largest tally)/(average tally) = 4.58726E+03 (largest tally)/(avg nonzero tally)= 1.87124E+03 (confidence interval shift)/mean = 0.0001 shifted confidence interval center = 4.97467E-07

CALC NO. EPM017-CALC-001 IU ENERCON Dose Rate Near Uranium REV. 0 Excellenc.:-Every proJect. Every day. Treatment Train 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 value at nps+1 value(nps+1 )/value(nps)-1.

mean 4.97439E-07 4.97668E-07 0.000459 relative error 2.40083E-03 2.44312E-03 0.017616 variance of the variance 4. 71546E-03 5.62879E-03 0.193689 shifted center 4. 97 467E-07 4.97470E-07 0.000006 figure of merit 7.33269E+02 7.08102E+02 -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 1status 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 10 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 10 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 10 statistical checks are only for the tally fluctuation chart bin and do not apply to other tally bins.

1tally 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 Dose Rate Near Uranium REV. 0 Excellenc~-Every proJect. Every day. Treatment Train PAGE NO. 29 of 58 1024000 2.4078E-05 0.0213 0.2766 2.2 110 4.9771 E-07 0.0075 0.0438 3.2 876 1536000 2.3929E-05 0.0160 0.1849 2.3 136 4.9688E-07 0.0059 0.0257 3.1 989 2048000 2.3935E-05 0.0128 0.1420 2.3 153 4.9847E-07 0.0056 0.0281 3.2 796 2560000 2.3867E-05 0.0111 0.1081 2.4 150 4.9707E-07 0.0049 0.0214 3.8 776 3072000 2.3783E-05 0.0100 0.0890 2.6 160 4.9589E-07 0.0044 0.0171 3.9 832 3584000 2.3846E-05 0.0094 0.0676 3.0 161 4.9585E-07 0.0040 0.0136 4.0 880 4096000 2.3883E-05 0.0088 0.0556 3.0 161 4.9676E-07 0.0037 0.0110 3.5 899 4608000 2.3874E-05 0.0082 0.0469 2.9 161 4.9657E-07 0.0035 0.0098 3.5 870 5120000 2.4010E-05 0.0081 0.0377 2.8 153 4.9693E-07 0.0034 0.0087 3.6 879 5632000 2.3975E-05 0.0076 0.0338 2.6 161 4.9764E-07 0.0032 0.0075 3.9 888 6144000 2.3969E-05 0.0072 0.0300 2.7 157 4.9766E-07 0.0031 0.0069 3.4 824 6656000 2.3965E-05 0.0068 0.0273 2.7 150 4.9714E-070.00300.0063 3.1 784 7168000 2.3940E-05 0.0065 0.0253 2.7 154 4.9817E-07 0.0029 0.0056 3.3 770 7680000 2.3942E-05 0.0063 0.0236 2.6 150 4.9818E-07 0.0028 0.0051 3.5 777 8192000 2.3982E-05 0.0061 0.0208 3.0 143 4.9807E-07 0.0027 0.0062 3.2 724 8704000 2.3969E-05 0.0059 0.0190 3.1 143 4.9799E-07 0.0026 0.0057 3.2 726 9216000 2.3925E-05 0.0056 0.0184 3.2 144 4.9759E-07 0.0025 0.0053 3.3 721 9728000 2.3939E-05 0.0056 0.0194 3.1 138 4.9753E-07 0.0024 0.0049 3.7 723 10000000 2.3924E-05 0.0055 0.0190 3.1 141 4.9744E-07 0.0024 0.0047 4.0 733 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

CALC NO. EPM017-CALC-001 ENERCON CALCULATION PREPARATION REV. 0 IJ Excellence-Every pro;ect. Every day CHECKLIST PAGE NO. 1 of 6 CHECKLIST ITEMS 1 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 ITEMS 1 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 ITEMS 1 YES NO NIA

25. If Attachments are used as design inputs or assumptions are the Attachments traceable and verifiable? rzI

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 the attachments properly referenced in the calculation? rzI

28. Are input sources (including industry codes and standards) appropriately selected and are they consistent with the quality classification and objective of the calculation? rzI

29. Are input sources (including industry codes and standards) consistent with the plant's design and license basis? rzI

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?

The Cimarron design is currently at 60% completion. rzI

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. EPM017-CALC-001 ENERCON CALCULATION PREPARATION REV. 0 Ex,ellence-Everv pro;ect. Every day. CHECKLIST PAGE NO. 4 of 6 CHECKLIST ITEMS 1 YES NO N/A

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?

~

CSP 3.03 Revision 1 Attachment C

CALC NO. EPM017-CALC-001 ENERCON CALCULATION PREPARATION REV. 0 Excellence-Eve ry pro;ect. Every day. CHECKLIST PAGE NO. 5 of 6 CHECKLIST ITEMS 1 YES NO N/A

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? ~

CSP 3.03 Revision 1 Attachment C

CALC NO. EPM017-CALC-001 ENERCON CALCULATION PREPARATION REV. 0 Excellence-Every pro;ect. Every day. CHECKLIST PAGE NO. 6 of 6 CHECKLIST ITEMS 1 YES NO N/A

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:

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 *.

Cal eb Tra inor c .,_

12/21/ 2015 Print Name and Sign Date CSP 3.03 Revision 1 Attachment C

ML21076A459

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