Text

Transmittal Letter: Response to Request for Additional Information for Revision 25 of the TRUPACT-II Shipping Package Application, Docket No.71-9218,and Revision 8 of the Halfpact Shipping Package Application, Docket No.71-9279
	ML21279A181
Person / Time
Site:	07109218, 07109279
Issue date:	10/06/2021
From:	Sellmer T; Nuclear Waste Partnership
To:	; Document Control Desk, Office of Nuclear Material Safety and Safeguards
Shared Package
ML21279A180	List: ML21279A181; ML21279A184; ML21279A187; ML21279A190;
References
	L-2021-LLA-0033, L-2021-LLA-0034, TS:21:03024, UFC:5822.00
	Download: ML21279A181 (93)
	v • d • e

P.O. Box 2078 z Carlsbad, New Mexico USA 88221-2078 Phone: (575) 234-7200 z Fax: (575) 234-7083 TS:21:03024 UFC:5822.00 October 6, 2021 ATTN: Document Control Desk Director, Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Subject:

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION FOR REVISION 25 OF THE TRUPACT-II SHIPPING PACKAGE APPLICATION, DOCKET NO. 71-9218, AND REVISION 8 OF THE HalfPACT SHIPPING PACKAGE APPLICATION, DOCKET NO. 71-9279 (EPIDS L-2021-LLA-0033 AND L-2021-LLA-0034)

References;

1. Letter from T. E. Sellmer to Document Control Desk dated February 23, 2021, subject: Revision 25 of the TRUPACT-II Shipping Package Application, Docket No. 71-9218, and Revision 8 of the HalfPACT Shipping Package Application, Docket No. 71-9279

2. Letter from T. E. Sellmer to Document Control Desk dated June 24, 2021, subject: Amendment to Revision 25 of the TRUPACT-II Shipping Package Application, Docket No. 71-9218, and Revision 8 of the HalfPACT Shipping Package Application, Docket No. 71-9279 (EPIDs L-2021-LLA-0033 AND L-2021-LLA-0034)

3. Letter from N. Garcia Santos to T. E. Sellmer dated August 11, 2021, subject: Application for the Model Nos. TRUPACT-II and HALFPACT Transport Packages - Request for Additional Information (EPIDS L-2021-LLA-0033 AND L-2021-LLA-0034)

Dear Sir or Madam:

Nuclear Waste Partnership LLC, on behalf of the U.S. Department of Energy (DOE), hereby submits an amendment to Revision 25 of the application for a Certificate of Compliance (CoC) for the TRUPACT-II Packaging, U.S. Nuclear Regulatory Commission (NRC) Docket No.

71-9218, and Revision 8 to the application for a CoC for the HalfPACT Packaging, NRC Docket No. 71-9279 (References 1 and 2). This amendment is in response to the Request for Additional Information (Reference 3) and consists of the following documents:

x TRUPACT-II Safety Analysis Report (SAR), Revision 25 x

HalfPACT SAR, Revision 8 x

Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC), Revision 6 x

CH-TRU Payload Appendices, Revision 5.

x HPT-REP-0001, Revision 1 x

SCA-CAL-0005, Revision 0

Document Control Desk TS:21:03003 P.O. Box 2078 z Carlsbad, New Mexico USA 88221-2078 Phone: (575) 234-7200 z Fax: (575) 234-7083 Individual responses to the RAI are provided in Attachment A. All technical changes added in response to the RAI are indicated by right-bars in the margin of the documents (l) and are summarized in Attachment B. Right-bars in the margin of the documents (l) indicating technical changes made to the documents in the original submittal and amendment of this application also have been retained. Revised report HPT-REP-0001 R1 and new calculation SCA-CAL-0005 R0 are provided as discussed in the Attachment A RAI responses.

This submission contains files, one or more of which contains hyperlinks to other files or to Internet websites. These hyperlinks are either inoperable or are not essential to the use of the filing. Any material referenced by hyperlinks to Internet websites that was essential for use of this filing has been submitted as part of the filing. Any material referenced by a hyperlink to another file that was essential for the use of this filing has either been included by reference or submitted as part of this filing.

To facilitate implementation, it is requested that the current package CoCs be valid for use one year from the date of issuance of the revised CoCs.

If you have any questions regarding this submittal, please contact Scott Burns of my staff at (575) 706-7920.

Sincerely, T. E. Sellmer, Manager Packaging and Information Systems TES:clm cc: D. Foreman, CBFO K. E. Princen, CBFO D. Smith, CBFO D. L. Standiford, CBFO M. Toothman, CBFO J. A. Walker, CBFO J. Shuler, EM-4.24 J. Shenk, EM-4.24 L. F. Gelder, SRRC N. Santos Garcia, USNRC B. H. White, USNRC TODD SELLMER (Affiliate)

Digitally signed by TODD SELLMER (Affiliate)

Date: 2021.10.06 07:32:33 -06'00'

Document Control Desk TS:21:03003 P.O. Box 2078 z Carlsbad, New Mexico USA 88221-2078 Phone: (575) 234-7200 z Fax: (575) 234-7083 The following table summarizes the components of this submittal. No deviations occur from the NRC-prescribed PDF formatting for the submitted files. Please contact Ms. C. L. Morrison at (505) 350-3693 or cindy.morrison@wipp.ws to resolve any discrepancies in this submittal.

File Name File Size (MB)

Release Level Submittal Type 001 Transmittal Letter - October 2021.pdf 1.2 Publicly Available EIE 002 TRUPACT-II SAR R25 - October 2021.pdf 38.5 Publicly Available EIE 003 HalfPACT SAR R8 - October 2021.pdf 40.3 Publicly Available EIE 004 CH-TRAMPAC R6 - October 2021.pdf 6.2 Publicly Available EIE 005 CH-TRU Payload Appendices R5 - October 2021.pdf 50.8 Publicly Available EIE 006 HPT-REP-0001 R1 86.8 Publicly Available EIE 007 SCA-CAL-0005 R0 15.1 Publicly Available EIE

ATTACHMENT A - Responses to RAI October 2021 A-1 Responses to NRC Request for Additional Information (RAI) on Revision 25 of the TRUPACT-II Safety Analysis Report (SAR), Revision 8 of the HalfPACT SAR, Revision 6 of the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC), and Revision 5 of the CH-TRU Payload Appendices STRUCTURAL EVALUATION (St)

RAI-St-1 Pertaining to SC-30G2, SC-30G3, SC-55G1, and SC-55G2, the application states that the SC-30G1 was previously approved based on 4-foot (4-ft) drop tests for normal conditions of transport (NCT) and 30-foot (30-ft) drop tests for hypothetical accident condition (HAC). Provide the following information:

a. Clarify whether the 4-ft drop test was conducted on the SC-55G1 version under NCT. If tests were performed, provide the test results. If the 4-ft drop test was not performed, demonstrate that the SC-55G1 shielded canister meets the 4-ft drop NCT requirement (e.g., show that the 4-ft drop test performed on other shielded canister bounds the SC-55G1 shielded canister or perform the test and provide the results).

The report HPT-REP-0001, Regulatory Hypothetical accident Condition Type B testing for the HalfPACT Shielded Container Payload, Revision 0, page 2, states that 4-ft drop tests were performed for all four new versions of the shielded canisters. On page 2, the report states that the 4-ft drop test and the 30-ft drop test were conducted for the SC-30G3 and the SC-55G1 versions of the canisters for HAC, but other sections of the report (e.g., page 30) do not state that a 4-ft drop test was conducted.

Similarly, the report CH-TRU on page 4.9-5 does not state that a 4-ft drop test was conducted for SC55G1.

b. Clarify whether the SC-30G2 was only tested for the 4-ft drop test. Justify why the 4-ft drop tests are an adequate means to demonstrate acceptability of the HAC 30-ft drop tests for the package with the new contents.

It appears that in the discussion in the report HPT-REP-0001, Section 7.1.4, SC-30G2 and SC-55G2 Evaluation, states that the 4-ft drop test was credited to demonstrate acceptable performance of the 30-ft drop test for HAC. However, on Section 5.1.1, SC-30G2 Payload Assembly vs. SC-55G1 Payload Assembly, it appears to state that no testing was performed on the SC-30G2 shielded canister.

c. Clarify what is intended by the term informally in the report HPT-REP-0001 excerpt. If the term informally means that the accelerometer was not calibrated or otherwise qualified for testing, then justify why the comparison of the test results is valid.

ATTACHMENT A - Responses to RAI October 2021 A-2 In the report, HPT-REP-0001Section 7.1.1, SC-30G3 Impact Acceleration Comparison, the applicant stated that the SC-30G3 will be used for direct comparison of 30-ft protected versus 4-ft unprotected bottom and side drops. Informally [bolded for emphasis], an information only uniaxial accelerometer was installed on SC-30G3 18TU-04 (the test unit used for Type B HAC drop testing).

Revision 8 of the application for the HalfPACT package references report CH-TRU, Payload Appendices, Revision 5, and the CH-TRU report references Report HPT-REP-0001. In these reports, the applicant discusses the methodology to qualify the shielded canisters included as part of the amendment request. The applicant refers in various instances to a 4-ft drop test performed for NCT (e.g., Type A tests) that is used to support the qualification of canisters. The applicant also discusses the 30-ft drop tests for HAC (e.g., Type B package tests).

The staff needs this information to determine compliance with the requirements in Title 10 of the Code of Federal Regulations Section 71.71(c)

[10 CFR 71.71(c)] and 10 CFR 71.73(c).

Response

Drop test report HPT-REP-0001, Rev. 0, submitted on February 23, 2021 as attachment 008 used to develop the RAIs has been revised to Rev. 1. The responses below where referenced (RAI-St-1 and RAI-Sh-8) are based on the updated HPT-REP-0001, Rev. 1, attached in the RAI response submittal.

As discussed in Section 1.2 of drop test report HPT-REP-0001, Rev. 1, both DOT-7A Type A 4-foot drop tests and Type B HAC 30-foot drop tests were performed for the previously approved SC-30G1. The DOT-7A Type A 4-foot free drop tests were performed to meet the requirements of 49 CFR

§173.465(c). For clarification, these are 4-foot drops of bare (unprotected) shielded containers that are not inside a HalfPACT package with its protective internal dunnage, and not the requisite NCT 3-foot package drops that are performed on the TRUPACT-II and HalfPACT packages per 10 CFR

§71.71(c).

a. DOT-7A Type A 4-foot bare (unprotected) free drop tests were performed on all four shielded container designs to meet the requirements of 49 CFR

§173.465(c). The HPT-REP-0001 example text (pages 2 and 30) cited by RAI-St-1(a) pertains to the HAC Type B 30-foot package drops. The bare (unprotected) DOT-7A Type A 4-foot drop test results for the SC-55G1 are presented in Section 6.1.2 of HPT-REP-0001, Rev. 1.

b. The SC-30G2 and SC-55G2 were only tested for the bare (unprotected)

DOT-7A Type A 4-foot drops. HAC Type B 30-foot drop tests were only performed for the SC-30G3 and SC-55G1 designs because the SC-30G3 and SC-55G1 payload assemblies, and associated packaging dunnage components, are more damaging to the ICV structure than the SC-55G2

ATTACHMENT A - Responses to RAI October 2021 A-3 and SC-30G2 designs, respectively. Justification for performing the HAC Type B 30-foot drop tests for these bounding designs is provided in Section 5.1 of HPT-REP-0001. For convenience, Table 1 summarizes the tested configurations for the four shielded container designs, and has been added to Section 1.2 of HPT-REP-0001, Rev. 1, for clarity.

Table 1 - Summary of Shielded Container Type A and Type B Testing Shielded Container Test Unit 18-TUXX1 Drop Test SC-30G2 SC-30G3 SC-55G1 SC-55G2 Type A - 4' CG Over Corner 01 03 06 09 Type A - 4' Flat Bottom End 01 03 09 Type A - 4' Near-Vertical Lid 02 05 06 10 Type A - 4' Flat Side 02 05 10 Type B - 30' Flat Bottom End 04 07 & 08 Type B - 30' Flat Side 04 07 & 08

1.

XX defines the test unit number, e.g., 18-TU01, 18-TU02, etc.

The basis for acceptance of the SC-30G2 and SC-55G2 designs is that physical damage to shielded containers caused by the DOT-7A Type A 4-foot bare drop tests is worse than physical damage to shielded containers caused by HAC Type B 30-foot protected (by foam-filled dunnage) drop tests within the HalfPACT package assembly. Comparison of physical damage to the tested shielded containers from the original SC-30G1 tests as well from the new SC-30G3 and SC-55G1 tests validate this assertion. Therefore, demonstrating that the SC-30G2 and SC-55G2 designs successfully passed the bounding DOT-7A Type A 4-foot drop tests of bare shielded containers ensures that they would also pass the HAC Type B 30-foot drop tests of protected shielded containers within the HalfPACT package. The HAC Type B 30-foot drops demonstrated that the foam-filled dunnage within the bounding payload assembly configurations protected the ICV from internal damage due to the shielded containers.

c. The term informally was intended to denote the use of a currently uncertified accelerometer (i.e., the accelerometers certification was expired, and certifying agencies were not available last summer due to COVID-19 closures). The data collected from the use of the uniaxial accelerometer is not the basis for regulatory compliance. The accelerometer data provides additional evidence that corroborates the documented post-test inspections confirming there was no loss of confinement of fluorescein dye from the payloads and the visual comparison of physical damage to shielded containers subject to bare DOT-7A Type A 4-foot drops and those subject to dunnage-protected HAC 30-foot drops. Section 7.0 of HPT-REP-0001, Rev. 1, has been revised to clarify the use of this information. Accelerometer data supports

ATTACHMENT A - Responses to RAI October 2021 A-4 what was observed from drop testing, i.e., that bare 4-foot drops were more damaging to the shielded containers than dunnage-protected 30-foot drops.

SHIELDING EVALUATION (Sh)

RAI-Sh-1 Clarify, with justifications, how the uncertainties in the source intensity, source term geometric distribution, and the density correction factors (DFCs) were considered in the calculations of the dose rates and revise the allowable contents as necessary to meet the dose rate limits.

Sections 5.5.6, 5.5.7, 5.5.8, and 5.5.9 of Revision 25 of the TRUPACT-II application provide information on the allowable source intensity, source term geometric distribution, and the DFCs. However, it is not clear whether the uncertainties in these parameters have been considered in determining the maximum allowable activity for each of the containers with the targeted dose rate limit.

The staff needs this information to determine compliance with the requirements in 10 CFR 71.47.

Response

All calculations used to determine activity limits and density correction factors (DCF) are based on an adjusted dose rate (Da) that is equal to the Monte Carlo N-Particle (MCNP) calculated dose rate (Dc) plus the tally error (E), i.e.,

one standard deviation, as follows:

a c

D D (1 E)

=

+

To account for uncertainties in the payload activity assay evaluation, Section 3.3.1.1 of the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC) includes the following requirement:

Each payload shall be acceptable for shipment only if the determined activity plus the error (i.e., one standard deviation) meets the specific limit as determined by the procedure provided in Section 5.5.10 of the TRUPACT-II SAR.

With reference to Section 5.5.10 of the TRUPACT-II SAR, the default payload configuration from a shielding standpoint conservatively assumes a point source. If, however, a waste form can be shown to meet the requirements for distributed throughout from NUREG-1608, then the activity limits for the distributed source model, in conjunction with the appropriate DCF for gamma-emitting radionuclides, may be used; neutron bearing wastes do not utilize a DCF for distributed source models. Uncertainties in the calculated DCFs were considered by conservatively implementing a DCF curve-fit utilizing the minimum DCFs calculated over a range of gamma energies as a function of

ATTACHMENT A - Responses to RAI October 2021 A-5 source density that utilizes zirconium as a conservative basis for self-shielding material in the distributed source region.

To account for other uncertainties in source intensity and/or source term geometric distribution, Section 5.5.10 of the TRUPACT-II SAR and correspondingly Section 3.3.2.1 of the CH-TRAMPAC apply a 10%

administrative margin to the calculated activity limit, where the combined sum of partial fractions for the gamma and neutron source terms present in the package must be less than or equal to 0.9.

RAI-Sh-2 Provide the maximum size of the solid-large objects, for each of the categories of the contents as specified in Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC) (ADAMS Accession No. ML21054A054) Revision 6, (ADAMS Accession No. ML21054A054) and clarify which shielding analyses supports the large objects.

CH-TRAMPAC, Revision 6, Table 2.9-49, Table 2.9-53, Table 2.9-57, and Table 2.9-61 identifies three forms of authorized contents for the SC-30G2, SC-55G1, and SC-55G1 containers. The three forms include the following:

1. solids, any particle size (e.g., fine powder or inorganic particulates),

2. large particle size (e.g., sand, concrete, or debris), and

3. large objects (e.g., metal cans containing waste).

However, it is not clear how to distinguish what constitutes a large object and particle of any size. Also, it is not clear how these definitions of the sizes of the particles or objects are related to the shielding models of distributed or concentrated sources in the package.

The staff needs this information to determine compliance with the requirements in 10 CFR 71.33(b)(3), 10 CFR 71.47, and 10 CFR 71.51.

Response

Table 2.9-41, Table 2.9-49, Table 2.9-53, Table 2.9-57, and Table 2.9-61 of the CH-TRAMPAC identify material content forms authorized for transport within each of the five shielded container designs (i.e., the currently licensed SC-30G1, and the new SC-30G2, SC-30G3, SC-55G1, and SC-55G2, respectively). Each waste form must be accordingly loaded within a 30-gallon or 55-gallon waste drum.

The term particle size is used comparatively in CH-TRAMPAC Section 2.9 to broadly differentiate physical forms as powder/particulate (as present in sludge or solidified waste) or debris; it is not quantitative. The first waste form, solids, any particle size, generically refers to relatively uniform solid waste material such as fine powders, ash, oxides, and cements. The second

ATTACHMENT A - Responses to RAI October 2021 A-6 waste form, large particle size, generically refers to non-uniform waste material such as sands, concrete, and random-sized debris. Finally, the third waste form, large objects, generically refers to waste material packed within inner metal containers, and may be as large as the 30-gallon or 55-gallon waste drums cavity allows. However, as shown in the subsequent paragraph, the precise waste form is generally unimportant from a shielding evaluation standpoint.

Material content forms from Section 2.9 of CH-TRAMPAC are not used in the determination of source term distribution or related in any way to shielding model inputs.

With reference to Section 5.5.10 of the TRUPACT-II SAR, the default payload configuration from a shielding standpoint conservatively assumes a point source; thus, the physical waste form becomes unimportant because source self-shielding is not relevant for gamma-emitting radionuclides, and the container materials of construction make them essentially transparent to neutron-emitting radionuclides. If a payload of containers can be shown to meet the requirements for distributed throughout from NUREG-1608, then the activity limits for the distributed source model, in conjunction with the appropriate density correction factor (DCF) for gamma-emitting radionuclides, may be used.

RAI-Sh-3 Explain why the density correction factors (DCFs) for SC-30G3 and SC-55G1 are identical.

The application shows that the equations for the self-shielding factor DCFs of the SC-30G3 and SC-55G1 are identical. Specifically, the application presents these polynomial equations as:

DCFSC-30G3 = 0.0051*3 - 0.0987*2 + 0.8030* + 0.2342, DCFSC-55G1 = 0.0051*3 - 0.0987*2 + 0.8030* + 0.2342 However, it is not clear why they behave the same since these two containers have different shielding designs and source term limits as shown in Tables 5.5-18 to 5.5-21.

The staff needs this information to determine compliance with the requirements of 10 CFR 71.47 and 10 CFR 71.51.

Response

As identified by RAI-Sh-3, the DCF equation for the SC-55G1 was incorrect in the application. Section 5.5.8 of the TRUPACT-II SAR has been revised to present the following corrected DCF equation for the SC-55G1.

DCFSC-55G1 = 0.0024*3 - 0.0668*2 + 0.7557* + 0.2630

ATTACHMENT A - Responses to RAI October 2021 A-7 RAI-Sh-4 Add the steps listed in Section 5.5.10 to the Chapter 7 of the safety analysis report (SAR) as part of the instructions for determining the allowable contents.

Section 5.5.10, Determination of Acceptable Activity, of the TRUPACT-II SAR provides a list of the steps for determining the allowable quantity of the wastes based on their radioactive characteristics. These steps/instructions form the basis for determining the maximum allowable contents and should be part of the loading instructions.

The staff needs this information to determine compliance with the requirements in 10 CFR 71.33(b)(1), 10 CFR 71.43(f), 10 CFR 71.47, 10 CFR 71.51, and 10 CFR 71.87(a).

Response

The TRUPACT-II and HalfPACT Certificates of Compliance as well as Section 7.1.4 of the TRUPACT-II and HalfPACT SARs specify the use of the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC) for determining allowable contents. Section 3.3.1.1 of the CH-TRAMPAC includes the following requirement:

Each payload shall be acceptable for shipment only if the determined activity plus the error (i.e., one standard deviation) meets the specific limit as determined by the procedure provided in Section 5.5.10 of the TRUPACT-II SAR.

Chapter 7 of the TRUPACT-II and HalfPACT SARs - the procedural instructions for operational loading of a payload assembly into a packaging -

specifies that a payload configuration has been properly prepared per the requirements of CH-TRAMPAC. Prior to assembling a payload for loading into a package, Section 6.2.2 of CH-TRAMPAC requires a Transportation Certification Official to comply with Section 3.3 of CH-TRAMPAC. As discussed above, Section 3.3.1.1 of CH-TRAMPAC requires compliance determination as described in Section 5.5.10 of the TRUPACT-II SAR.

Therefore, the steps listed in Section 5.5.10 of the TRUPACT-II SAR are included in Chapter 7 of the SARs because Chapter 7 requires compliance with CH-TRAMPAC.

RAI-Sh-5 Demonstrate there are no significant secondary gammas or neutrons from the package or provide control measures to ensure that there will be no significant (n, gamma) or (gamma, n) reactions in the TRU wastes.

Page 5.3-27 of the TRUPACT-II application states the following:

Combined photon/neutron mode evaluations were not employed for the neutron analyses as multiple test runs demonstrated that the gamma dose rate due to the interaction of neutrons in the shielding materials contributes a statistically insignificant (<1%) change in the dose rate as compared to the neutron dose rate.

ATTACHMENT A - Responses to RAI October 2021 A-8 However, it is not clear what the multiple runs were referred to. If the term run is related to the MCNP model calculation, the secondary gammas or neutrons in the TRU contents would not be captured in the analyses because the definition of the material in the sample MCNP input, as provided in the application, for the content does not include the TRU isotopes as defined in the Department of Energys Environmental Impact Statements (DOE 2016).

The (n, gamma) and (gamma, n) reactions in the TRU wastes are well understood physical phenomena (McNair, 2019). The MCNP models can only capture the secondary gamma and neutrons when the material compositions for the TRU contents are explicitly defined in the material cards.

The staff needs this information to determine compliance with the requirements in 10 CFR 71.47 and 10 CFR 71.51.

References:

1. Department of Energy, Final Environmental Impact Statement for the Disposal of Greater-Than-Class C (GTCC) Low-Level Radioactive Waste and GTCC-Like Waste (DOE/EIS-0375), Department of Energy, January 2016.

2. Carson R McNair, Characterization techniques for TRU waste from the Analytical Laboratory Hot Cells at Idaho National Laboratory, Idaho National Laboratory, March 2019.

Response

As correctly stated in RAI-Sh-5, the determination that secondary gamma production from neutrons is statistically insignificant relates only to neutron interaction with the materials of construction for the shielded containers proper. It is asserted that any dose rate increases due to secondary gamma production from neutron interaction with waste material contents is concurrently associated with a more dominant effect of neutron attenuation due to self-shielding (which is not credited for neutrons in either concentrated or distributed waste form activity limits). This assertion was again tested and affirmed via a supplemental series of calculations described below.

To increase neutron capture and corresponding secondary gamma production, the entire shielded container payload cavity was filled with polyethylene with a density of 0.94 g/cc. The SC-30G3 and SC-55G1, which are associated with the greatest and least gamma shielding, respectively, were modeled to encompass the four new shielded container designs.

Two MCNP analyses were run for the SC-30G3 and for the SC-55G1, i.e., NCT and HAC with a concentrated 252Cf neutron source. With the exception of placing polyethylene in the payload cavities and adding photon measurement for the tally regions, the MCNP models are identical to those used to develop Tables 5.4-13 (SC-30G3) and 5.4-14 (SC-55G1) of the TRUPACT-II SAR. For

ATTACHMENT A - Responses to RAI October 2021 A-9 completeness, the MCNP output files for the four runs are provided in Attachment RAI-Sh-5, and summarized below in Tables 2 and 3 below.

Self-shielding plays a major role in reducing dose rates such that the activity limits calculated in Tables 2 and 3 are significantly greater than the activity limits determined in Tables 5.4-13 and 5.4-14 of the TRUPACT-II SAR for the SC-30G3 and SC-55G1, respectively. Thus, the presence of a material within the shielded containers payload cavity that could stimulate secondary gamma production also serves to provide self-shielding for the neutron source. In summary, accounting for waste material from a neutron to secondary gamma production perspective results in far less restrictive activity limits than what is presented in the SAR.

Table 2 - SC-30G3 NCT & HAC Activity Limits with a Polyethylene Payload Particle Type Source Strength (par/s/Ci)

Calculated Dose Rate (mrem/hr /

par/s)

Tally Error Adjusted Dose Rate (mrem/hr /

par/s)

Percent of Total Dose Rate Allowable Dose Rate (mrem/hr)

Allowable Activity (n/s)

Activity Limit (Ci)

NCT - HalfPACT Package Side Surface Neutron 3.8322E+09 5.68E-09 0.8%

5.73E-09 95.6%

191.2 3.34E+10 8.716 Gamma 7.3991E+10 2.62E-10 0.9%

2.64E-10 4.4%

8.8 Total 5.99E-09 100.0%

200.0 NCT - 2 Meters from HalfPACT Package Side Surface Neutron 3.8322E+09 7.15E-10 1.0%

7.22E-10 95.8%

9.6 1.33E+10 3.471 Gamma 7.3991E+10 3.12E-11 1.0%

3.15E-11 4.2%

0.4 Total 7.54E-10 100.0%

10.0 HAC - 1 Meter from HalfPACT Package Side Surface Neutron 3.8322E+09 5.55E-07 0.2%

5.56E-07 99.4%

994.2 1.79E+09 0.467 Gamma 7.3991E+10 3.24E-09 0.6%

3.26E-09 0.6%

5.8 Total 5.59E-07 100.0%

1,000.0 Table 3 - SC-55G1 NCT & HAC Activity Limits with a Polyethylene Payload Particle Type Source Strength (par/s/Ci)

Calculated Dose Rate (mrem/hr /

par/s)

Tally Error Adjusted Dose Rate (mrem/hr /

par/s)

Percent of Total Dose Rate Allowable Dose Rate (mrem/hr)

Allowable Activity (n/s)

Activity Limit (Ci)

NCT - HalfPACT Package Side Surface Neutron 3.8322E+09 5.75E-09 0.8%

5.80E-09 76.8%

153.6 2.65E+10 6.915 Gamma 7.3991E+10 1.75E-09 0.2%

1.75E-09 23.2%

46.4 Total 7.55E-09 100.0%

200.0 NCT - 2 Meters from HalfPACT Package Side Surface Neutron 3.8322E+09 5.14E-10 1.2%

5.20E-10 73.4%

7.3 1.41E+10 3.679 Gamma 7.3991E+10 1.87E-10 0.3%

1.88E-10 26.6%

2.7 Total 7.08E-10 100.0%

10.0 HAC - 1 Meter from HalfPACT Package Side Surface Neutron 3.8322E+09 3.83E-07 0.3%

3.84E-07 98.6%

986.4 2.57E+09 0.671 Gamma 7.3991E+10 5.28E-09 0.4%

5.30E-09 1.4%

13.6 Total 3.89E-07 100.0%

1,000.0

ATTACHMENT A - Responses to RAI October 2021 A-10 RAI-Sh-6 Clarify whether the uncertainties associated with the source term calculation and the statistical uncertainty associated with the dose rate calculation have been included in the final dose rates. If they are not, include the uncertainties associated with these calculations and demonstrate that the package meets the regulatory requirements.

The applicant used computer code SOURCES-4A to calculate the specific activity of each of the nuclides provided in the document CH-TRAMPAC.

However, it is not clear what are the uncertainties, if any, associated with the source term calculations of the transuranic wastes using the SOURCES-4A computer code. The uncertainties of the source term calculations should include, as a minimum, how the transuranic wastes were produced, i.e.,

irradiation parameters, such as fluxes and spectra, cooling time, and the uncertainties of these parameters.

The applicant developed a scheme to calculate the allowable activity for the SC-30G1 and the four new containers. The scheme determines the maximum allowable contents by dividing the targeted dose rate by the calculated dose rate per curie of each nuclide in the wastes. Table 5.1-8 to Table 5.1-11 of Revision 25 of the TRUPACT-II application provide the targeted maximum dose rates for the Half-PACT packaging system containing the payloads for the four new containers (SC-30G2, SC-30G3, SC-55G1, and SC-55G2) and Table 5.1-7 provides the revised neutron dose rate for neutron sources for the SC-30G1 container. The dose rates in these tables show that the maximum dose rate is less than one percent (e.g., 9.99 mrem/hr vs. 10 mrem/hr for the SC-30G2 container) within the regulatory limits of 10 CFR 71.47, which is 10 mrem/hr. In addition, the data provided in Table 5.4-12, Table 5.4-13, Table 5.4-14, and Table 5.4-15 show that the statistical errors of the Monte Carlo method used in the shielding analyses are in 0.1% to 0.3% for packages under NCT. Based on the MCNP manual, the error associated tally of MCNP calculation is a percentage of the mean value, thus, 0.3%

9.99 =

0.02997. Considering the statistical error, the actual dose rate could be as high as 9.99+0.02997=10.01997 mrem/hr, which exceeds the regulatory dose rate limit of 10 mrem/hr.

The staff needs this information to determine compliance with the requirements in 10 CFR 71.47.

Response

The response to RAI-Sh-1 addresses uncertainties associated with source term calculation and the statistical uncertainty associated with the dose rate calculations that are used to determine activity limits.

Per Section 5.2.2 of the TRUPACT-II SAR, the SOURCES-4A computer code was used to generate the neutron source energy spectrum that was used for neutron shielding calculations, and not the specific activities of radionuclides; specific activities are taken from Table 3.1-2 of the CH-TRAMPAC.

ATTACHMENT A - Responses to RAI October 2021 A-11 As stated earlier, all MCNP shielding calculation results that are used to determine activity limits and density correction factors are based on an adjusted dose rate (Da) that is equal to the calculated dose rate (Dc) plus the tally error (E), i.e., one standard deviation, as follows:

a c

D D (1 E)

=

+

Thus, the tally error is already taken into account for developing the activity limits and is not additive to the dose rates provided in Tables 5.1-8 through 5.1-11 of the TRUPACT-II SAR.

RAI-Sh-7 Justify the assumption for maximizing the distance to the detector for the shielding model for the package under NCT.

On page 5.3-1, the first paragraph the TRUPACT-II SAR states the following:

NCT assumptions maximize the distance from the source(s) to the nearest detector whereas HAC assumptions minimize the distance from the source(s) to the nearest detector.

The staff understands the assumption for modeling of the package under HAC. However, it does not understand why the applicant tried to maximize the distance between the source and the detector in the NCT model. This assumption may not be conservative even if the source is homogeneously distributed in the waste.

The staff needs this information to determine compliance with the requirements in 10 CFR 71.47.

Response

To maximize the distance from the source to the shielded containers surface in all radial directions, the source is located at the shielded containers axial centerline. Given the nature of CH-TRU waste, the expected distribution of waste is such that the average source activity occurs near the center of the payload container. Any potential deviation from its center is captured within the 10% administrative margin that is used to restrict activity limits.

A response to a similar RAI was provided in March 2013 (Letter from T.E. Sellmer to Document Control Desk, dated March 27, 2013, subject:

Response to Second Request for Additional Information for Revision 23 of the TRUPACT-II Shipping Package Application, Docket No. 71-9218, TAC No. L24643, and Revision 6 of the HalfPACT Shipping Package Application, Docket NO. 71-9279, TAC NO. L24642). Since the same approved methodology is being implemented for the four new shielded container designs, the previous RAI 5.1 response is still valid.

The calculated allowable activity is administratively reduced 10% to address the potential for reconfiguration of source material within shielded containers

ATTACHMENT A - Responses to RAI October 2021 A-12 under NCT where the combined sum of partial fractions for gamma and neutron source terms are required to be less than or equal to 0.9. As shown below, potential reconfiguration of the source material in the shielded containers under NCT is highly improbable and will not cause a significant change in the limiting package dose rate values. Other potential sources of dose rate increase under NCT are not applicable for shielded containers due to test results indicating no damage to the payload container under those conditions.

DOE TRU waste packaging guidance and site-specific waste acceptance criteria direct the preparation of CH-TRU waste payload containers to ensure safe and compliant ALARA payload container dose rates during characterization activities, intra-site transport operations, generator site storage, Type B package loading and transport processes, and WIPP repository disposal sequences. By definition, a CH-TRU waste payload container surface dose rate cannot exceed 200 mrem/hr. The CH-TRAMPAC and the WIPP Land Withdrawal Act (Public Law 102-579) impose this payload container surface dose rate requirement. The absence of CH-TRU payload containers exceeding the payload container surface dose rate requirement when surveyed after receipt at WIPP is a strong indicator that dose rate changes during handling and shipment, even at the payload container level, are insignificant. This indicator is important because any change in the payload container surface dose rate translates into a much smaller corresponding change in the limiting 2-meter package dose rate.

Using distance attenuation for the SC-55G1 configuration as an example, where the dose rate is directly proportional to the inverse square of the distance, the limiting dose rate of 10 mrem/hr at a distance 2 meters from the HalfPACT package surface containing two SC-55G1s with initially centered point sources that are unrealistically moved the full radial distance to the SC-55G1s inner shell surface would only increase to (126.781/114.281)2 x 10 = 12.3 mrem/hr (see Figure 1). Similarly, the limiting dose rate of 10 mrem/hr at a distance 2 meters from the HalfPACT package surface containing one SC-55G2 with an initially centered point source that is unrealistically moved the full radial distance to the SC-55G2s inner shell surface would only increase to (125.928/113.448)2 x 10 = 12.3 mrem/hr (see Figure 2).

Any substantial concentration of sources resulting from movement during transport would be readily observable during receipt inspection of the package, and none has been noted in thousands of CH-TRU waste shipments within the TRUPACT-II and HalfPACT packages.

ATTACHMENT A - Responses to RAI October 2021 A-13 FIGURE 1 - HalfPACT Package with Two SC-55G1s; Shifted Point Source FIGURE 2 - HalfPACT Package with One SC-55G2; Shifted Point Source Regardless, the occurrence of shielded containers having initially centered sources with full source reconfiguration to the worst possible location under NCT is not considered a credible scenario. Given the nature of CH-TRU waste, the expected distribution of waste is such that the average source activity occurs near the center of the payload container. Any potential deviation from its center is captured within the 10% administrative margin that is used to restrict activity limits.

ATTACHMENT A - Responses to RAI October 2021 A-14 RAI-Sh-8 Either demonstrate that lead slump does not occur or provide an analysis of the effect of lead slump on the dose rate at one meter for the damaged package.

In the document titled CH-TRU Payload Appendices, Revision 5, the applicant stated in the application that no lead slump occurred by examining the lead layer of the testing unit. However, staff does not find the justification for not evaluating lead slump in the application. The staff notes that lead slump under impact is an unavoidable natural phenomenon and will occur in accordance with the basic physics (G. C. Mok, 1989, Tan, et al, 2017) unless the package is designed such that the shielded containers inside the overpack do not experience any significant impact (g-load) under the drop tests required in 10 CFR 71.73(c)(1), which states the following:

Free Drop. A free drop of the specimen through a distance of 9 m (30 ft) onto a flat, essentially unyielding, horizontal surface, striking the surface in a position for which maximum damage is expected.

The staff notes that Figure 4.10 SC-55G2 18TU-10 Cut AM-AN Near Mid-Span shows visible deformation of the lead layer in the middle section of the test unit. The staff also notes that the picture in Figure 7-20 of the document, with document identification number HPT-REP-0001, seems to show a void gap at the top end of the lead shield after drop test. These gaps are probable evidence that there will be a loss of lead shield resulting from lead slump. In fact, the gap created by lead slump can be calculated by the differential contraction of the lead layer and the steel shells. If there is not sufficient data to prove lead slump will never occur for this package under HAC, a shielding analysis should be provided assuming there is lead slump under HAC, as predicted using the method in the Cask Designers Guide (ORNL, 1970) document. The analysis should also account for any void between the top of the lead shielding and the outer cask top flange resulting from package fabrication. Using analyses for a few radionuclide contents (e.g., Co-60), the applicant may demonstrate that the dose rates for the puncture HAC configuration bound those for the lead slump configuration. In addition, the publication from Sandia National Laboratory, Dose Estimates in a Loss of Lead Shielding Truck Accident, clearly indicate that lead slump is a credible condition for transportation package under HAC.

The staff needs this information to determine compliance with the requirements in 10 CFR 71.51.

References:

1. Lawrence Livermore National Laboratory. G. C. Mok, et al., The Analysis of Lead Slump Effects in Shipping Casks for Radioactive Materials, March 1989.

ATTACHMENT A - Responses to RAI October 2021 A-15

2. Tan, Z., Bernal, S.A., and Provis, J.L., Reproducible mini-slump test procedure for measuring the yield stress of cementitious pastes, Mater Struct Vol. 50, PP 235, 2017.

3. Oak Ridge National Laboratory. Cask Designers Guide, A Guide for the Design, Fabrication, and Operation of Shipping Casks for Nuclear Applications, February 1970.

4. Matthew L. Dennis, Ruth F. Weiner, Douglas M. Osborn, and Terence J.

Heames, Dose estimates in a loss of lead shielding truck accident, Sandia National Laboratory, August 2009.

Response

With reference to Figure 7-43 in drop test report HPT-REP-0001, Rev. 1 (Figure 4.10-18 in CH-TRU Payload Appendices), the last paragraph of Section 7.1.3.2 clarifies that the visible deformation at mid-length of SC-55G2 18TU-10 occurred because of a side drop strike on the test riggings lifting shackle, not because of lead slump. Therefore, the damage shown in Figure 7-43 at mid-length and Figure 7-34 (not Figure 7-20) at the upper flange end are unrelated.

Axial voids at the ends of the sidewall lead column are shown in HPT-REP-0001, Rev. 1, Figures 6-51 and 6-53 for SC-30G3 18TU-04 that was used for 30-foot HAC drop testing in two orientations (a flat end drop and a flat side drop); Figures 7-18, 7-20, and 7-23 for SC-30G2 18TU-02 that was used for 4-foot Type A drop testing in two orientations (a 10º near-vertical top-down drop and horizontal side drop); and Figure 7-34 for SC-55G2 18TU-09 that was used for bare (unprotected) 4-foot Type A drop testing in two orientations (a center-of-gravity over bottom corner drop and a bottom-down vertical end drop). All axial voids are identified as cold-shuts that occurred during the lead pour process. The reasons for this conclusion are summarized below:

1. SC-30G3 18TU-04: The axial void depicted in Figures 6-51 and 6-53 only occurred at the upper step; no void occurred at the lower step. If lead slump had occurred, a void would have been present at both upper and lower steps.

2. SC-30G2 18TU-02: The axial void depicted in Figures 7-18, 7-20, and 7-23 occurred on the second SC-30G2 test unit that was subjected to a 10º near-vertical top-down drop and horizontal side drop. In comparison, SC-30G2 18TU-01 that was subjected to a flat end drop and center-of-gravity-over-corner drop showed no axial void at either end (see Figures 7-13 through 7-16). If lead slump had occurred, SC-30G2 18TU-01 would have exhibited an axial void greater than that observed in SC-30G2 18TU-02.

ATTACHMENT A - Responses to RAI October 2021 A-16

3. SC-55G2 18TU-09: The axial void depicted in Figure 7-34 occurred on the first SC-55G2 test unit that was subjected to a center-of-gravity over bottom corner drop followed by a flat end drop. The flat end drop should have produced an axisymmetric axial void, yet Figure 7-36 at a cut position 180º from the void shown in Figure 7-34 shows no evidence of lead movement.

Considering all test units, both Type B and Type A, the maximum measured axial void that occurred due to cold-shuts was 0.318 inches observed in SC-55G2 18TU-09. To address the effect of axial voids, the SC-30G2, SC-30G3, and SC-55G2 shielding models were modified to include an identical axial gap at both ends of the sidewall lead column; stepped ends included the gap at both steps. This evaluation is included in SCA-CAL-0005, Effect of Axial Gaps in the SC-30G2, SC30G3, and SC-55G2 Lead Sidewalls and the results are summarized in new Section 5.4.5, Evaluation for Axial Gaps in the Sidewall Lead, of the TRUPACT-II SAR. These models were evaluated for both NCT and HAC.

This evaluation demonstrated that axial gaps as great as 1/2-inch at either the upper or lower end of the sidewall lead column result in a maximum NCT dose rate increase of only 1.01x and a maximum HAC dose rate increase of 1.17x, both associated with the SC-30G2 design (see Table 5.4-16 of the TRUPACT-II SAR). Table 5.4-12 of the TRUPACT-II SAR for the SC-30G2 shows that the HAC activity limit is 9.73x greater than the NCT activity limit.

Similarly, Tables 5-4-13 and 5.4-15 of the TRUPACT-II SAR show HAC and NCT activity limit ratios of 3.35x and 4.10x for the SC-30G3 and SC-55G2 designs, respectively. Therefore, the reported increases in HAC dose rates due to 1/2-inch axial gaps are inconsequential because the NCT 2-meter dose rate bounds the activity limits for all shielded container designs.

RAI-Sh-9 Show that the MCNP gamma shielding analysis model for the HalfPACT containing the SC-30G3 container properly converged.

The applicant provided the input file for the MCNP model for the HalfPACT containing the SC-30G3 container. The input model indicates that the applicant set a cut-off computing time of 1200 minutes. However, it is not clear how this cut-off time was determined and whether it can assure a proper convergence of the calculations. One method of showing convergence is providing an output file for the package under NCT. Also, clarify whether the calculations were made on a multiprocessor computer cluster or single processor. For the CTME card, the MCNP 6.2 users manual (LA-UR-17-29981, Los Alamos National Laboratory, 2017) explicitly points out that it is highly recommended that the NPS card (Section 3.3.7.1.1) should be used to limit the run time for multiprocessor cluster computers.

The staff needs this information to determine compliance with the requirements in 10 CFR 71.47 and 10 CFR 71.51(a)(2).

ATTACHMENT A - Responses to RAI October 2021 A-17

Response

While convergence may be used to terminate MCNP calculations for a criticality analysis, it is not applicable for a shielding analysis. A shielding evaluation relies on the results of MCNPs ten statistical checks for determining a problems validity. A users model can attain a solution from MCNP that can pass all ten statistical checks, yet have a high tally error (i.e.,

statistical uncertainty) because a low number of particle histories were evaluated. To reduce the tally error, the user must run a greater number of particle histories, but doing so increases the probability that one or more poorly-behaved particles will cause one or more of the ten statistical checks to fail.

An MCNP run is terminated based on one of two possible methods:

1) controlling computer processor time using the CTME card, or 2) controlling total quantity of particles using the NPS card. Because LANL never corrected MCNP when multi-threading was implemented, computer processor time is semi-arbitrary when running a multi-threading evaluation; hence, the reason the NPS card is recommended, but not required, for use in that situation.

Regardless of the method employed to perform an MCNP evaluation and determine the runs cut-off point, however, it is still the responsibility of the user to evaluate results carefully to determine whether sufficient particles have been evaluated to produce an accurate solution.

Although the CTME card was employed for all runs, and all runs were performed using a multi-threading computer, the evaluation goal was to run for sufficient time (i.e., number of particles) to achieve a tally error under one percent. For the SC-30G3 example given, time was increased to 1,200 minutes using a trial-and-error process until the 1% tally error goal was achieved. As such, running with the NPS card would not have changed the reported results because the value on the NPS card would have been increased until the same answer with the same tally error goal was achieved.

RAI-Sh-10 Confirm that pre-shipment radiation survey is not relied upon for demonstrating that the package design will meet the regulatory requirement of 10 CFR 71.51(a)(1) and revise the SAR as necessary.

On page 5.3-1, the first paragraph the TRUPACT-II SAR states:

Any significant deviation from the NCT configuration assumption is precluded through the use of pre-shipment radiological surveys of the package to validate that the source(s) are reasonably distributed within the package.

This statement seems to indicate that assurance of compliance with the regulatory requirement of 10 CFR 71.51(a)(1),, no significant increase in external surface radiation levels, and no substantial reduction in the effectiveness of the packaging;.. relies on pre-shipment dose rate measurement. It is not clear how this pre-shipment measurement can assure that the package meets the regulatory requirements of no significant increase

ATTACHMENT A - Responses to RAI October 2021 A-18 in external surface radiation levels even before a shipment has been made.

A pre-shipment dose rate measurement can only assure that the package is fabricated and loaded as designed. It cannot tell any information on the potential source terms reconfiguration or relocation under NCT. Only design analysis can provide such an assurance.

In addition, as explained in Regulatory Issue Summary 2013-04, Content Specification and Shielding Evaluations for Type B Transportation Packages, pre-shipment dose rate measurement is a requirement of 10 CFR 71.87, Routine determinations. Per 10 CFR 71.35(a), an application for a CoC must include a demonstration that the package satisfies the standards in Subpart E which includes requirements in 10 CFR 71.51.

The staff needs this information to determine compliance with the requirements in 10 CFR 71.35 and 10 CFR 71.51.

Response

For clarity, Section 5.3.1 of the TRUPACT-II SAR has been revised to delete the last two sentences.

Assurance that the NCT regulatory requirement of 10 CFR §71.51(a)(1) has been met is accomplished via the shielding analyses presented in Chapter 5 of the TRUPACT-II SAR. The responses to RAI-Sh-1 and RAI-Sh-6 address uncertainties in the payload activity assay evaluation. The 10%

administrative margin that is applied to the calculated activity limit, where the combined sum of partial fractions for the gamma and neutron source terms present in the package must be less than or equal to 0.9, accounts for all other uncertainties.

ATTACHMENT A - Responses to RAI October 2021 A-19 Attachment RAI-Sh MCNP Output Files

1. SC-30G3 NCT Model with 252Cf - Polyethylene with Secondary Gammas Code Name & Version = MCNP_6.20, 6.2.0

_/ _/ _/_/_/ _/ _/ _/_/_/ _/_/_/

_/_/ _/_/ _/ _/_/ _/ _/ _/ _/

_/ _/ _/ _/ _/ _/ _/ _/_/_/ _/_/_/

_/ _/ _/ _/ _/_/ _/ _/ _/

_/ _/ _/_/_/ _/ _/ _/ _/_/

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

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

1mcnp version 6 ld=02/20/18 08/29/21 09:02:49

- - - - probid = 08/29/21 09:02:49 i=NCT_HP_SC-30G3_252Cf_0.i name=NCT_HP_SC-30G3_252Cf_0. tasks 24 warning. universe map (print table 128) disabled.

comment. Physics models disabled.

1-title HP/SC-30G3 with a Concentrated 252Cf Neutron Source - NCT 2-c 3-c Universe Fill Boundary 4-c 5-1 0 -107 108 -109 fill=1 $Shielded Container 6-imp:n=1 imp:p=1 trcl=1 7-c 8-c Payload Cell $Material Density 100%

9-c 10- 2 1 -0.9400 -1 2 -3 $Payload 11-imp:n=1 imp:p=1 u=1 12-c 13-c Shielded Container Cells $Material Density 100%

14-c 15-3 2 -7.8526 -11 12 -13 -14 $Lower Flange Steel 16- ((11 :13 :-15 :-16) 17- (11 :16 :-17 :-18) 18- (11 :18 :-19 :-20) 19- (11 :20 :-21 :-22) 20- (-12 :26 :27) 21- (23 :24 :-27))

22-imp:n=1 imp:p=1 u=1 23-4 3 -11.3500 -23 -24 25 $Lower Flange Upper Lead 24-imp:n=1 imp:p=1 u=1 25-5 3 -11.3500 -26 -27 28 $Lower Flange Lower Lead 26-imp:n=1 imp:p=1 u=1 27-6 2 -7.8526 (12 -26 -31): $Lower Flange Base Steel 28- (-29 31 -32) 29-imp:n=1 imp:p=1 u=1 30- 7 2 -7.8526 16 33 -34 -45 $Inner Shell Steel 31-imp:n=1 imp:p=1 u=1 32-8 3 -11.3500 (-16 17 18 -35): $Sidewall Lead 33- (16 34 -35 -40):

34- (-18 19 20 -35):

ATTACHMENT A - Responses to RAI October 2021 A-20 35- (34 40 -43 -45) 36-imp:n=1 imp:p=1 u=1 37-9 2 -7.8526 22 36 -37 -45 $Outer Shell Steel 38-imp:n=1 imp:p=1 u=1 39-10 2 -7.8526 ((38 -39 -41 45): $Upper Flange Steel 40- (40 43 -44 -45))

41- ((-38 :41 :42))

42-imp:n=1 imp:p=1 u=1 43-11 2 -7.8526 -49 50 -51 -52 $Lid Steel 44- ((39 :41 :-50 :-80) 45- (-41 :63 :-64 :65) 46- (-50 :51 :-65 :83) 47- (51 :-57 :58 :-59) 48- (-53 :54 :-55 :59))

49-imp:n=1 imp:p=1 u=1 50- 12 2 -7.8526 -50 -80 82 83 $Lid Ring Steel 51- (80 :-81 :-83 :-84) 52-imp:n=1 imp:p=1 u=1 53-13 2 -7.8526 -81 86 -87 -89 $Lid Base Steel 54- (81 :-83 :87 :-88) 55-imp:n=1 imp:p=1 u=1 56-14 3 -11.3500 -50 -82 85 $Lid Plate Lead 57-imp:n=1 imp:p=1 u=1 58-15 3 -11.3500 53 -54 55 -56 $Lid Ring Lead 59-imp:n=1 imp:p=1 u=1 60- 16 2 -7.8526 59 60 -61 -62 $Lid Ring Cover Plate Steel 61-imp:n=1 imp:p=1 u=1 62-c 63-c Cavity (Void) Cells 64-c 65-17 1 -0.9400 ((13 -33 -86): $Payload Cavity 66- (-13 15 16 -33):

67- (-33 86 89):

68- (-33 81 84 -89):

69- (-33 -45 80 -84):

70- (-38 42 45 80):

71- (-41 -42 80))

72- (1 :-2 :3) 73-imp:n=1 imp:p=1 u=1 74-18 0 -23 -25 27 $Lower Flange Upper Lead 75-imp:n=1 imp:p=1 u=1 $ Axial Cavity 76-19 0 (-26 -28 29 31): $Lower Flange Lower Lead 77- (-28 -29 32) $ Axial/Radial Cavity 78-imp:n=1 imp:p=1 u=1 79-20 0 (-20 21 22 -36): $Sidewall Lead Outer Radial Gap 80- (20 35 -36 -40):

81- (-36 40 44 -45) 82-imp:n=1 imp:p=1 u=1 83-21 0 41 -63 64 -65 $Lid Gasket Recess Cavity 84-imp:n=1 imp:p=1 u=1 85-22 0 53 -54 56 -59 $Lid Lead Ring Axial Cavity 86-imp:n=1 imp:p=1 u=1 87-23 0 (-82 83 -87 88): $Lid Lead Plate Axial Cavity 88- (-82 -85 87) 89-imp:n=1 imp:p=1 u=1 90- 24 0 ((11 :-12 :14 :22) $Exterior Void 91- (-22 :37 :45) 92- (-45 :49 :51 :52)):

93- ((12 -29 -30):

94- (-51 57 -58 62):

95- (57 59 -60 -62):

96- (-58 59 61 -62))

97-imp:n=1 imp:p=1 u=1 98-c 99-c HalfPACT Package Cells $Material Density 100%

100- c 101-201 4 -8.0128 (201 -202 204 -205): $HalfPACT ICV/OCV Steel Structure 102- (-202 203 -204):

103- (-202 205 -206) 104-imp:n=1 imp:p=1 105-202 5 -0.1322 (202 203 -206 -211): $HalfPACT OCA Polyurethane Foam 106- (-203 -211 214):

107- (206 -211 -215) 108-imp:n=1 imp:p=1 109-203 4 -8.0128 (211 -212 214 -215): $HalfPACT OCA Steel Structure 110- (-212 213 -214):

111- (-212 215 -216) 112-imp:n=1 imp:p=1 113-c 114-c HalfPACT Package Void Cells 115-c

ATTACHMENT A - Responses to RAI October 2021 A-21 116-204 0 -201 204 -205 $HalfPACT ICV Interior Void 117- #1 118-imp:n=1 imp:p=1 119-205 0 ((-999 212 213 -216): $HalfPACT OCA Exterior Void 120- (-999 -213):

121- (-999 216))

122- (-301 :302:-305 :306) 123- (-303 :304:-305 :306) 124-imp:n=1 imp:p=1 125-c 126-c HalfPACT Package Surface and 2-meter Tally Cells 127-c 128-301 0 301 -302 305 -306 $Package Side Middle @ Surface 129-imp:n=1 imp:p=1 130- 302 0 303 -304 305 -306 $Package Side Middle @ 2-meters 131-imp:n=1 imp:p=1 132-c 133-c World Cell 134-c 135-999 0 999 136-imp:n=0 imp:p=0 137-138-c 139-c Payload Surfaces 140- c 141-1 cz 1.27000 $Radius 142-2 pz 51.07305 $Plane, Bottom 143-3 pz 53.61305 $Plane, Top 144-c 145-c Shielded Container Lower Flange Surfaces 146-c 147-11 cz 35.56000 $Radius, Outer 148-12 pz 0.00000 $Plane, Lower Flange Bottom 149-13 pz 14.60500 $Plane, Lower Flange Top 150- 14 kz -35.24250 1.00000 1 $Chamfer, Bottom Outer Corner 151-15 cz 25.79370 $Radius, Inner Shell Step 152-16 pz 13.97000 $Plane, Inner Shell Step 153-17 cz 27.19070 $Radius, Inner Lead Step 154-18 kz 10.47452 192.3724 -1 $Cone, Inner Lead Step Vertex 155-19 cz 31.43250 $Radius, Outer Lead Step 156-20 pz 5.08000 $Plane, Outer Lead Step 157-21 cz 34.23920 $Radius, Outer Shell Step 158-22 pz 4.44500 $Plane, Outer Shell Step 159-23 cz 25.40000 $Radius, Upper Lead Plate Recess 160- 24 pz 10.18540 $Plane, Upper Lead Plate Recess 161-25 pz 5.74040 $Plane, Upper Lead Plate Bottom 162-26 cz 29.21000 $Radius, Lower Lead Plate Recess 163-27 pz 5.71500 $Plane, Lower Lead Plate Recess 164-28 pz 3.81000 $Plane, Lower Lead Plate Bottom 165-29 cz 29.07030 $Radius, Base Plate 166-30 pz 0.00000 $Plane, Base Plate Bottom 167-31 pz 2.54000 $Plane, Base Plate Weld Elevation 168-32 pz 3.81000 $Plane, Base Plate Top 169-c 170- c Shielded Container Sidewall Inner Shell Surfaces 171-c 172-33 cz 25.92070 $Radius, Inner 173-34 cz 27.19070 $Radius, Outer 174-c 175-c Shielded Container Sidewall Lead Shell Surface 176-c 177-35 cz 34.17570 $Radius, Outer 178-c 179-c Shielded Container Sidewall Outer Shell Surfaces 180- c 181-36 cz 34.29000 $Radius, Inner 182-37 cz 35.56000 $Radius, Outer 183-c 184-c Shielded Container Upper Flange Surfaces 185-c 186-38 cz 25.72385 $Radius, Inner 187-39 cz 35.56000 $Radius, Outer 188-40 pz 97.15500 $Plane, Upper Flange Bottom 189-41 pz 101.91750 $Plane, Upper Flange Top 190- 42 kz 30.60680 0.13247 1 $Chamfer, Top Inner Corner 191-43 cz 27.24150 $Radius, Inner Shell Step 192-44 cz 34.23920 $Radius, Outer Shell Step 193-45 pz 97.79000 $Plane, Shell Step Top 194-c 195-c Shielded Container Lid Surfaces 196-c

ATTACHMENT A - Responses to RAI October 2021 A-22 197-49 cz 35.56000 $Radius, Lid Outer 198-50 pz 100.34270 $Plane, Lid Bottom 199-51 pz 107.32770 $Plane, Lid Top 200- 52 kz 142.57020 1.00000 -1 $Chamfer, Top Outside Corner 201-53 cz 22.54250 $Radius, Lead Ring Recess Inner 202-54 cz 29.84500 $Radius, Lead Ring Recess Outer 203-55 pz 104.91470 $Plane, Lead Ring Recess Bottom 204-56 pz 106.81970 $Plane, Lead Ring Top 205-57 cz 22.22500 $Radius, Lead Ring Cover Recess Inner 206-58 cz 30.16250 $Radius, Lead Ring Cover Recess Outer 207-59 pz 106.84510 $Plane, Lead Ring Cover Recess Bottom 208-60 cz 22.27580 $Radius, Lead Ring Cover Inner 209-61 cz 30.11170 $Radius, Lead Ring Cover Outer 210- 62 pz 107.29976 $Plane, Lead Ring Cover Top 211-63 cz 28.57500 $Radius, Gasket Recess Outer 212-64 cz 26.33980 $Radius, Gasket Recess Inner 213-65 pz 102.23500 $Plane, Gasket Recess Top 214-c 215-c Shielded Container Lid Ring Surfaces 216-c 217-80 cz 25.66035 $Radius, Outer Upper 218-81 cz 25.52700 $Radius, Outer Lower 219-82 cz 24.13000 $Radius, Inner 220- 83 pz 93.28150 $Plane, Bottom 221-84 kz 26.24737 0.13247 1 $Cone, Outer Radius Transition 222-85 pz 94.62770 $Plane, Lead Plate Bottom 223-c 224-c Shielded Container Lid Base Surfaces 225-c 226-86 pz 90.08110 $Plane, Bottom 227-87 pz 94.52610 $Plane, Top 228-88 cz 24.06650 $Radius, Lid Ring Step 229-89 kz 20.58124 0.13247 1 $Chamfer, Bottom Outside Corner 230- c 231-c Shielded Container Universe Fill Boundary Surfaces 232-c 233-107 cz 35.56001 $Radius, Fill Boundary 234-108 pz -0.00001 $Plane, Fill Boundary Bottom 235-109 pz 107.32771 $Plane, Fill Boundary Top 236-c 237-c HalfPACT Package ICV/OCV Surfaces 238-c 239-201 cz 92.23375 $Radius, Shell Inner 240- 202 cz 93.34500 $Radius, Shell Outer 241-203 pz 22.86000 $Plane, Lower Head Bottom 242-204 pz 24.13000 $Plane, Lower Head Top 243-205 pz 198.12000 $Plane, Upper Head Bottom 244-206 pz 199.39000 $Plane, Upper Head Top 245-c 246-c HalfPACT Package OCA Surfaces 247-c 248-211 cz 118.74500 $Radius, Shell Inner 249-212 cz 119.38000 $Radius, Shell Outer 250- 213 pz 0.00000 $Plane, Lower Head Bottom 251-214 pz 0.63500 $Plane, Lower Head Top 252-215 pz 229.23500 $Plane, Upper Head Bottom 253-216 pz 229.87000 $Plane, Upper Head Top 254-c 255-c HalfPACT Package Tally Surfaces 256-c 257-301 cz 119.38000 $Radius, Inner (at Surface) 258-302 cz 119.48000 $Radius, Outer (at Surface) 259-303 cz 319.38000 $Radius, Inner (at 2.000-Meters) 260- 304 cz 319.48000 $Radius, Outer (at 2.001-Meters) 261-305 pz 108.58500 $Plane, Bottom Elevation 262-306 pz 113.66500 $Plane, Top Elevation 263-c 264-c World Surface (Problem Boundary) 265-c 266-999 sz 114.93500 400 267-268-c 269-c Physics Cards 270- c 271-mode n p comment. photonuclear physics may be needed (phys:p).

272-c 273-c Material Cards 274-c 275-m1 1001.84C -0.143704 $Payload (Polyethylene) 276-1002.84C -0.000033 6000.84C -0.856263

ATTACHMENT A - Responses to RAI October 2021 A-23 277-plib = 84P 278-c 279-m2 26054.84C -0.058450 $Carbon Steel 280- 26056.84C -0.917540 26057.84C -0.021190 26058.84C -0.002820 281-plib = 84P 282-c 283-m3 82204.84C -0.014000 $Lead 284-82206.84C -0.241000 82207.84C -0.221000 82208.84C -0.524000 285-plib = 84P 286-c 287-m4 14028.84C -0.009222 $Stainless Steel (ASTM A240, Type 304) 288-14029.84C -0.000469 14030.84C -0.000309 24050.84C -0.008256 289-24052.84C -0.159199 24053.84C -0.018052 24054.84C -0.004494 290- 25055.84C -0.020000 26054.84C -0.039746 26056.84C -0.623927 291-26057.84C -0.014409 26058.84C -0.001918 28058.84C -0.068077 292-28060.84C -0.026223 28061.84C -0.001140 28062.84C -0.003635 293-28064.84C -0.000926 294-plib = 84P 295-c 296-m5 1001.84C -0.069992 $Urethane Foam 297-1002.84C -0.000008 6000.84C -0.600000 7014.84C -0.079709 298-7015.84C -0.000291 8016.84C -0.239417 8017.84C -0.000091 299-14028.84C -0.009222 14029.84C -0.000469 14030.84C -0.000309 300- plib = 84P 301-c 302-c Specify Universe Transformations 303-c 304- *tr1 -53.66386 0.00000 111.12500 305- -90 90 0 90 0 90 0 90 -90 306-c 307-c Specify Explicit Analysis for Weight Windows Evaluation 308-c 309-cut:n 2j 0 310- cut:p 2j 0 311-c 312-c Source Cards 313-c 314-sdef par=1 axs=1 0 0 erg=d1 pos=d2 rad=d3 ext=d4 315-sc1 Concentrated 252Cf Neutron Source 316-si1 L 0.100000 0.500000 1.000000 2.000000 3.000000 317-4.000000 6.000000 8.000000 10.000000 15.000000 318-sp1 0.00E+00 1.80E+11 2.71E+11 5.36E+11 4.10E+11 319-2.73E+11 2.66E+11 8.53E+10 2.44E+10 8.36E+09 320- si2 L -1.32080 0.00000 111.12500 321-sp2 1 322-si3 0.00000 1.27000 323-sp3 -21 1 324-si4 -1.27000 1.27000 325-sp4 -21 0 0 326-c 327-c Package Tally Cards 328-c 329-f4:n 301 330- fc4 Package Surface Neutron Dose Rate (mrem/hr) @ Z = 111.12500 331-sd4 381.20362 332-f14:n 302 333-fc14 2-M from Package Surface Neutron Dose Rate (mrem/hr) @ Z = 111.12500 334-sd14 1019.57524 335-f24:p 301 336-fc24 Package Surface Gamma Dose Rate (mrem/hr) @ Z = 111.12500 337-sd24 381.20362 338-f34:p 302 339-fc34 2-M from Package Surface Gamma Dose Rate (mrem/hr) @ Z = 111.12500 340- sd34 1019.57524 341-c 342-c ANSI/ANS-6.1.1-1977 Neutron Flux-to-Dose Rate Factor Cards 343-c 344-de0 2.50E-08 1.00E-07 1.00E-06 1.00E-05 1.00E-04 $Energy (Mev) 345-1.00E-03 1.00E-02 1.00E-01 5.00E-01 1.00E+00 346-2.50E+00 5.00E+00 7.00E+00 1.00E+01 1.40E+01 347-2.00E+01 348-df0 3.67E-03 3.67E-03 4.46E-03 4.54E-03 4.18E-03 $Factor (mrem/hr) 349-3.76E-03 3.56E-03 2.17E-02 9.26E-02 1.32E-01 350- 1.25E-01 1.56E-01 1.47E-01 1.47E-01 2.08E-01 351-2.27E-01 352-c 353-c ANSI/ANS-6.1.1-1977 Gamma Flux-to-Dose Rate Factor Cards 354-c 355-de24 0.01 0.03 0.05 0.07 0.10 $Energy (Mev) 356- 0.15 0.20 0.25 0.30 0.35 357- 0.40 0.45 0.50 0.55 0.60

ATTACHMENT A - Responses to RAI October 2021 A-24 358- 0.65 0.70 0.80 1.00 1.40 359-1.80 2.20 2.60 2.80 3.25 360- 3.75 4.25 4.75 5.00 5.25 361-5.75 6.25 6.75 7.50 9.00 362-11.00 13.00 15.00 363-df24 3.96E-03 5.82E-04 2.90E-04 2.58E-04 2.83E-04 $Factor (mrem/hr) 364-3.79E-04 5.01E-04 6.31E-04 7.59E-04 8.78E-04 365-9.85E-04 1.08E-03 1.17E-03 1.27E-03 1.36E-03 366-1.44E-03 1.52E-03 1.68E-03 1.98E-03 2.51E-03 367-2.99E-03 3.42E-03 3.82E-03 4.01E-03 4.41E-03 368-4.83E-03 5.23E-03 5.60E-03 5.80E-03 6.01E-03 369-6.37E-03 6.74E-03 7.11E-03 7.66E-03 8.77E-03 370- 1.03E-02 1.18E-02 1.33E-02 371-de34 0.01 0.03 0.05 0.07 0.10 $Energy (Mev) 372- 0.15 0.20 0.25 0.30 0.35 373- 0.40 0.45 0.50 0.55 0.60 374- 0.65 0.70 0.80 1.00 1.40 375-1.80 2.20 2.60 2.80 3.25 376-3.75 4.25 4.75 5.00 5.25 377-5.75 6.25 6.75 7.50 9.00 378-11.00 13.00 15.00 379-df34 3.96E-03 5.82E-04 2.90E-04 2.58E-04 2.83E-04 $Factor (mrem/hr) 380- 3.79E-04 5.01E-04 6.31E-04 7.59E-04 8.78E-04 381-9.85E-04 1.08E-03 1.17E-03 1.27E-03 1.36E-03 382-1.44E-03 1.52E-03 1.68E-03 1.98E-03 2.51E-03 383-2.99E-03 3.42E-03 3.82E-03 4.01E-03 4.41E-03 384-4.83E-03 5.23E-03 5.60E-03 5.80E-03 6.01E-03 385-6.37E-03 6.74E-03 7.11E-03 7.66E-03 8.77E-03 386-1.03E-02 1.18E-02 1.33E-02 387-c 388-c Runtime and Print Cards 389-c 390- prdmp j j 1 2 391-ctme 1200

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. total nubar used if fissionable isotopes are present.

surface 11 and surface 37 are the same. 37 will be deleted.

surface 11 and surface 39 are the same. 39 will be deleted.

surface 11 and surface 49 are the same. 49 will be deleted.

surface 12 and surface 30 are the same. 30 will be deleted.

surface 12 and surface 213 are the same. 213 will be deleted.

surface 17 and surface 34 are the same. 34 will be deleted.

surface 21 and surface 44 are the same. 44 will be deleted.

surface 28 and surface 32 are the same. 32 will be deleted.

surface 212 and surface 301 are the same. 301 will be deleted.

comment. 9 surfaces were deleted for being the same as others.

warning. 1 materials had unnormalized fractions. print table 40.

warning. 1 cells appear to consist of more than one piece.

1cells print table 60 atom gram neutron photon photon wt cell mat density density volume mass pieces importance importance generation 1 1 0 0.00000E+00 0.00000E+00 4.26369E+05 0.00000E+00 1 1.0000E+00 1.0000E+00 -1.000E+00 2 2 1 1.21080E-01 9.40000E-01 1.28704E+01 1.20981E+01 1 1.0000E+00 1.0000E+00 -1.000E+00 3 3 2 8.46854E-02 7.85260E+00 2.01423E+04 1.58169E+05 1 1.0000E+00 1.0000E+00 -1.000E+00 4 4 3 3.29855E-02 1.13500E+01 9.00926E+03 1.02255E+05 1 1.0000E+00 1.0000E+00 -1.000E+00 5 5 3 3.29855E-02 1.13500E+01 5.10632E+03 5.79567E+04 1 1.0000E+00 1.0000E+00 -1.000E+00 6 6 2 8.46854E-02 7.85260E+00 1.01802E+04 7.99407E+04 1 1.0000E+00 1.0000E+00 -1.000E+00

ATTACHMENT A - Responses to RAI October 2021 A-25 7 7 2 8.46854E-02 7.85260E+00 1.77619E+04 1.39477E+05 1 1.0000E+00 1.0000E+00 -1.000E+00 8 8 3 3.29855E-02 1.13500E+01 1.21436E+05 1.37829E+06 1 1.0000E+00 1.0000E+00 -1.000E+00 9 9 2 8.46854E-02 7.85260E+00 2.60142E+04 2.04279E+05 1 1.0000E+00 1.0000E+00 -1.000E+00 10 10 2 8.46854E-02 7.85260E+00 8.66283E+03 6.80257E+04 1 1.0000E+00 1.0000E+00 -1.000E+00 11 11 2 8.46854E-02 7.85260E+00 2.16660E+04 1.70134E+05 1 1.0000E+00 1.0000E+00 -1.000E+00 12 12 2 8.46854E-02 7.85260E+00 1.61985E+03 1.27201E+04 1 1.0000E+00 1.0000E+00 -1.000E+00 13 13 2 8.46854E-02 7.85260E+00 8.80459E+03 6.91389E+04 1 1.0000E+00 1.0000E+00 -1.000E+00 14 14 3 3.29855E-02 1.13500E+01 1.04540E+04 1.18652E+05 1 1.0000E+00 1.0000E+00 -1.000E+00 15 15 3 3.29855E-02 1.13500E+01 2.28952E+03 2.59860E+04 1 1.0000E+00 1.0000E+00 -1.000E+00 16 16 2 8.46854E-02 7.85260E+00 5.86345E+02 4.60433E+03 1 1.0000E+00 1.0000E+00 -1.000E+00 17 17 1 1.21080E-01 9.40000E-01 1.59844E+05 1.50253E+05 1 1.0000E+00 1.0000E+00 -1.000E+00 18 18 0 0.00000E+00 0.00000E+00 5.14815E+01 0.00000E+00 1 1.0000E+00 1.0000E+00 -1.000E+00 19 19 0 0.00000E+00 0.00000E+00 3.24842E+01 0.00000E+00 1 1.0000E+00 1.0000E+00 -1.000E+00 20 20 0 0.00000E+00 0.00000E+00 2.27755E+03 0.00000E+00 1 1.0000E+00 1.0000E+00 -1.000E+00 21 21 0 0.00000E+00 0.00000E+00 1.22433E+02 0.00000E+00 1 1.0000E+00 1.0000E+00 -1.000E+00 22 22 0 0.00000E+00 0.00000E+00 3.05269E+01 0.00000E+00 1 1.0000E+00 1.0000E+00 -1.000E+00 23 23 0 0.00000E+00 0.00000E+00 1.97815E+02 0.00000E+00 1 1.0000E+00 1.0000E+00 -1.000E+00 24 24 0 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 0 1.0000E+00 1.0000E+00 -1.000E+00 25 201 4 8.80954E-02 8.01280E+00 1.82252E+05 1.46035E+06 1 1.0000E+00 1.0000E+00 -1.000E+00 26 202 5 1.11868E-02 1.32200E-01 5.29418E+06 6.99890E+05 1 1.0000E+00 1.0000E+00 -1.000E+00 27 203 4 8.80954E-02 8.01280E+00 1.65455E+05 1.32576E+06 1 1.0000E+00 1.0000E+00 -1.000E+00 28 204 0 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 0 1.0000E+00 1.0000E+00 -1.000E+00 29 205 0 0.00000E+00 0.00000E+00 2.57789E+08 0.00000E+00 2 1.0000E+00 1.0000E+00 -1.000E+00 30 301 0 0.00000E+00 0.00000E+00 3.81204E+02 0.00000E+00 1 1.0000E+00 1.0000E+00 -1.000E+00 31 302 0 0.00000E+00 0.00000E+00 1.01958E+03 0.00000E+00 1 1.0000E+00 1.0000E+00 -1.000E+00 32 999 0 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 0 0.0000E+00 0.0000E+00 -1.000E+00 total 2.64285E+08 6.22590E+06 minimum source weight = 1.0000E+00 maximum source weight = 1.0000E+00 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.

3 warning messages so far.

1cross-section tables print table 100 XSDIR used: C:\\MCNP\\MCNP_DATA/xsdir_mcnp6.2 table length tables from file xdata/endf71x/H/1001.714nc 1001.84c 15325 H1 ENDF71x (jlconlin) Ref. see jlconlin (ref 09/10/2012 10:00:53) mat 125 12/17/12 Energy range: 1.00000E-11 to 2.00000E+01 MeV.

particle-production data for deuterons being expunged from 1001.84c temperature = 2.1543E-07 adjusted to 2.5300E-08 tables from file xdata/endf71x/H/1002.714nc 1002.84c 7283 H2 ENDF71x (jlconlin) Ref. see jlconlin (ref 09/10/2012 10:00:53) mat 128 12/17/12 Energy range: 1.00000E-11 to 1.50000E+02 MeV.

particle-production data for protons being expunged from 1002.84c particle-production data for tritons being expunged from 1002.84c temperature = 2.1543E-07 adjusted to 2.5300E-08 tables from file xdata/endf71x/C/6000.714nc 6000.84c 55343 C0 ENDF71x (jlconlin) Ref. see jlconlin (ref 09/10/2012 10:00:53) mat 600 12/20/12 Energy range: 1.00000E-11 to 1.50000E+02 MeV.

particle-production data for protons being expunged from 6000.84c particle-production data for deuterons being expunged from 6000.84c particle-production data for alphas being expunged from 6000.84c temperature = 2.1543E-07 adjusted to 2.5300E-08 tables from file xdata/endf71x/N/7014.714nc 7014.84c 102640 N14 ENDF71x (jlconlin) Ref. see jlconlin (ref 09/10/2012 10:00:53) mat 725 12/16/12 Energy range: 1.00000E-11 to 1.50000E+02 MeV.

particle-production data for protons being expunged from 7014.84c particle-production data for deuterons being expunged from 7014.84c particle-production data for alphas being expunged from 7014.84c temperature = 2.1543E-07 adjusted to 2.5300E-08 tables from file xdata/endf71x/N/7015.714nc 7015.84c 28412 N15 ENDF71x (jlconlin) Ref. see jlconlin (ref 09/10/2012 10:00:53) mat 728 12/16/12 Energy range: 1.00000E-11 to 2.00000E+01 MeV.

temperature = 2.1543E-07 adjusted to 2.5300E-08

ATTACHMENT A - Responses to RAI October 2021 A-26 tables from file xdata/endf71x/O/8016.714nc 8016.84c 264772 O16 ENDF71x (jlconlin) Ref. see jlconlin (ref 09/10/2012 10:00:53) mat 825 12/13/12 Energy range: 1.00000E-11 to 1.50000E+02 MeV.

particle-production data for protons being expunged from 8016.84c particle-production data for deuterons being expunged from 8016.84c particle-production data for tritons being expunged from 8016.84c particle-production data for alphas being expunged from 8016.84c temperature = 2.1543E-07 adjusted to 2.5300E-08 tables from file xdata/endf71x/O/8017.714nc 8017.84c 4921 O17 ENDF71x (jlconlin) Ref. see jlconlin (ref 09/10/2012 10:00:53) mat 828 12/13/12 Energy range: 1.00000E-11 to 2.00000E+01 MeV.

temperature = 2.1543E-07 adjusted to 2.5300E-08 warning. 8017.84c lacks gamma-ray production cross sections.

tables from file xdata/endf71x/Si/14028.714nc 14028.84c 169896 Si28 ENDF71x (jlconlin) Ref. see jlconlin (ref 09/10/2012 10:00:53) mat1425 12/14/12 Energy range: 1.00000E-11 to 1.50000E+02 MeV.

particle-production data for protons being expunged from 14028.84c particle-production data for deuterons being expunged from 14028.84c particle-production data for tritons being expunged from 14028.84c particle-production data for alphas being expunged from 14028.84c temperature = 2.1543E-07 adjusted to 2.5300E-08 tables from file xdata/endf71x/Si/14029.714nc 14029.84c 158834 Si29 ENDF71x (jlconlin) Ref. see jlconlin (ref 09/10/2012 10:00:53) mat1428 12/14/12 Energy range: 1.00000E-11 to 1.50000E+02 MeV.

particle-production data for protons being expunged from 14029.84c particle-production data for deuterons being expunged from 14029.84c particle-production data for tritons being expunged from 14029.84c particle-production data for alphas being expunged from 14029.84c temperature = 2.1543E-07 adjusted to 2.5300E-08 tables from file xdata/endf71x/Si/14030.714nc 14030.84c 130018 Si30 ENDF71x (jlconlin) Ref. see jlconlin (ref 09/10/2012 10:00:53) mat1431 12/16/12 Energy range: 1.00000E-11 to 1.50000E+02 MeV.

particle-production data for protons being expunged from 14030.84c particle-production data for deuterons being expunged from 14030.84c particle-production data for tritons being expunged from 14030.84c particle-production data for alphas being expunged from 14030.84c temperature = 2.1543E-07 adjusted to 2.5300E-08 tables from file xdata/endf71x/Cr/24050.714nc 24050.84c 291186 Cr50 ENDF71x (jlconlin) Ref. see jlconlin (ref 09/10/2012 10:00:53) mat2425 12/13/12 Energy range: 1.00000E-11 to 1.50000E+02 MeV.

particle-production data for protons being expunged from 24050.84c particle-production data for deuterons being expunged from 24050.84c particle-production data for tritons being expunged from 24050.84c particle-production data for alphas being expunged from 24050.84c temperature = 2.1543E-07 adjusted to 2.5300E-08 tables from file xdata/endf71x/Cr/24052.714nc 24052.84c 310582 Cr52 ENDF71x (jlconlin) Ref. see jlconlin (ref 09/10/2012 10:00:53) mat2431 12/13/12 Energy range: 1.00000E-11 to 1.50000E+02 MeV.

particle-production data for protons being expunged from 24052.84c particle-production data for deuterons being expunged from 24052.84c particle-production data for tritons being expunged from 24052.84c particle-production data for alphas being expunged from 24052.84c temperature = 2.1543E-07 adjusted to 2.5300E-08 tables from file xdata/endf71x/Cr/24053.714nc 24053.84c 254692 Cr53 ENDF71x (jlconlin) Ref. see jlconlin (ref 09/10/2012 10:00:53) mat2434 12/13/12 Energy range: 1.00000E-11 to 1.50000E+02 MeV.

particle-production data for protons being expunged from 24053.84c particle-production data for deuterons being expunged from 24053.84c particle-production data for tritons being expunged from 24053.84c particle-production data for alphas being expunged from 24053.84c temperature = 2.1543E-07 adjusted to 2.5300E-08 tables from file xdata/endf71x/Cr/24054.714nc

ATTACHMENT A - Responses to RAI October 2021 A-27 24054.84c 190185 Cr54 ENDF71x (jlconlin) Ref. see jlconlin (ref 09/10/2012 10:00:53) mat2437 12/13/12 Energy range: 1.00000E-11 to 1.50000E+02 MeV.

particle-production data for protons being expunged from 24054.84c particle-production data for deuterons being expunged from 24054.84c particle-production data for tritons being expunged from 24054.84c particle-production data for alphas being expunged from 24054.84c temperature = 2.1543E-07 adjusted to 2.5300E-08 tables from file xdata/endf71x/Mn/25055.714nc 25055.84c 455909 Mn55 ENDF71x (jlconlin) Ref. see jlconlin (ref 09/10/2012 10:00:53) mat2525 12/18/12 Energy range: 1.00000E-11 to 6.00000E+01 MeV.

particle-production data for protons being expunged from 25055.84c particle-production data for deuterons being expunged from 25055.84c particle-production data for tritons being expunged from 25055.84c particle-production data for helions being expunged from 25055.84c particle-production data for alphas being expunged from 25055.84c probability tables used from 1.2500E-01 to 1.0000E+00 mev.

temperature = 2.1543E-07 adjusted to 2.5300E-08 tables from file xdata/endf71x/Fe/26054.714nc 26054.84c 217705 Fe54 ENDF71x (jlconlin) Ref. see jlconlin (ref 09/10/2012 10:00:53) mat2625 12/22/12 Energy range: 1.00000E-11 to 1.50000E+02 MeV.

particle-production data for protons being expunged from 26054.84c particle-production data for deuterons being expunged from 26054.84c particle-production data for tritons being expunged from 26054.84c particle-production data for alphas being expunged from 26054.84c temperature = 2.1543E-07 adjusted to 2.5300E-08 tables from file xdata/endf71x/Fe/26056.714nc 26056.84c 352429 Fe56 ENDF71x (jlconlin) Ref. see jlconlin (ref 09/10/2012 10:00:53) mat2631 12/22/12 Energy range: 1.00000E-11 to 1.50000E+02 MeV.

particle-production data for protons being expunged from 26056.84c particle-production data for deuterons being expunged from 26056.84c particle-production data for tritons being expunged from 26056.84c particle-production data for alphas being expunged from 26056.84c temperature = 2.1543E-07 adjusted to 2.5300E-08 tables from file xdata/endf71x/Fe/26057.714nc 26057.84c 241212 Fe57 ENDF71x (jlconlin) Ref. see jlconlin (ref 09/10/2012 10:00:53) mat2634 12/22/12 Energy range: 1.00000E-11 to 1.50000E+02 MeV.

particle-production data for protons being expunged from 26057.84c particle-production data for deuterons being expunged from 26057.84c particle-production data for tritons being expunged from 26057.84c particle-production data for alphas being expunged from 26057.84c temperature = 2.1543E-07 adjusted to 2.5300E-08 tables from file xdata/endf71x/Fe/26058.714nc 26058.84c 135502 Fe58 ENDF71x (jlconlin) Ref. see jlconlin (ref 09/10/2012 10:00:53) mat2637 12/22/12 Energy range: 1.00000E-11 to 2.00000E+01 MeV.

particle-production data for protons being expunged from 26058.84c particle-production data for alphas being expunged from 26058.84c temperature = 2.1543E-07 adjusted to 2.5300E-08 tables from file xdata/endf71x/Ni/28058.714nc 28058.84c 420627 Ni58 ENDF71x (jlconlin) Ref. see jlconlin (ref 09/10/2012 10:00:53) mat2825 12/15/12 Energy range: 1.00000E-11 to 1.50000E+02 MeV.

particle-production data for protons being expunged from 28058.84c particle-production data for deuterons being expunged from 28058.84c particle-production data for tritons being expunged from 28058.84c particle-production data for alphas being expunged from 28058.84c temperature = 2.1543E-07 adjusted to 2.5300E-08 tables from file xdata/endf71x/Ni/28060.714nc 28060.84c 344192 Ni60 ENDF71x (jlconlin) Ref. see jlconlin (ref 09/10/2012 10:00:53) mat2831 12/17/12 Energy range: 1.00000E-11 to 1.50000E+02 MeV.

particle-production data for protons being expunged from 28060.84c particle-production data for deuterons being expunged from 28060.84c particle-production data for tritons being expunged from 28060.84c particle-production data for alphas being expunged from 28060.84c temperature = 2.1543E-07 adjusted to 2.5300E-08 tables from file xdata/endf71x/Ni/28061.714nc 28061.84c 190713 Ni61 ENDF71x (jlconlin) Ref. see jlconlin (ref 09/10/2012 10:00:53) mat2834 12/13/12

ATTACHMENT A - Responses to RAI October 2021 A-28 Energy range: 1.00000E-11 to 1.50000E+02 MeV.

particle-production data for protons being expunged from 28061.84c particle-production data for deuterons being expunged from 28061.84c particle-production data for tritons being expunged from 28061.84c particle-production data for alphas being expunged from 28061.84c temperature = 2.1543E-07 adjusted to 2.5300E-08 tables from file xdata/endf71x/Ni/28062.714nc 28062.84c 169202 Ni62 ENDF71x (jlconlin) Ref. see jlconlin (ref 09/10/2012 10:00:53) mat2837 12/17/12 Energy range: 1.00000E-11 to 1.50000E+02 MeV.

particle-production data for protons being expunged from 28062.84c particle-production data for deuterons being expunged from 28062.84c particle-production data for tritons being expunged from 28062.84c particle-production data for alphas being expunged from 28062.84c probability tables used from 6.0000E-01 to 1.0000E+00 mev.

temperature = 2.1543E-07 adjusted to 2.5300E-08 tables from file xdata/endf71x/Ni/28064.714nc 28064.84c 152759 Ni64 ENDF71x (jlconlin) Ref. see jlconlin (ref 09/10/2012 10:00:53) mat2843 12/17/12 Energy range: 1.00000E-11 to 1.50000E+02 MeV.

particle-production data for protons being expunged from 28064.84c particle-production data for deuterons being expunged from 28064.84c particle-production data for tritons being expunged from 28064.84c particle-production data for alphas being expunged from 28064.84c temperature = 2.1543E-07 adjusted to 2.5300E-08 tables from file xdata/endf71x/Pb/82204.714nc 82204.84c 392627 Pb204 ENDF71x (jlconlin) Ref. see jlconlin (ref 09/10/2012 10:00:53) mat8225 12/22/12 Energy range: 1.00000E-11 to 2.00000E+02 MeV.

particle-production data for protons being expunged from 82204.84c particle-production data for deuterons being expunged from 82204.84c particle-production data for tritons being expunged from 82204.84c particle-production data for helions being expunged from 82204.84c particle-production data for alphas being expunged from 82204.84c temperature = 2.1543E-07 adjusted to 2.5300E-08 tables from file xdata/endf71x/Pb/82206.714nc 82206.84c 801388 Pb206 ENDF71x (jlconlin) Ref. see jlconlin (ref 09/10/2012 10:00:53) mat8231 12/22/12 Energy range: 1.00000E-11 to 2.00000E+02 MeV.

particle-production data for protons being expunged from 82206.84c particle-production data for deuterons being expunged from 82206.84c particle-production data for tritons being expunged from 82206.84c particle-production data for helions being expunged from 82206.84c particle-production data for alphas being expunged from 82206.84c temperature = 2.1543E-07 adjusted to 2.5300E-08 tables from file xdata/endf71x/Pb/82207.714nc 82207.84c 353707 Pb207 ENDF71x (jlconlin) Ref. see jlconlin (ref 09/10/2012 10:00:53) mat8234 12/22/12 Energy range: 1.00000E-11 to 2.00000E+02 MeV.

particle-production data for protons being expunged from 82207.84c particle-production data for deuterons being expunged from 82207.84c particle-production data for tritons being expunged from 82207.84c particle-production data for helions being expunged from 82207.84c particle-production data for alphas being expunged from 82207.84c temperature = 2.1543E-07 adjusted to 2.5300E-08 tables from file xdata/endf71x/Pb/82208.714nc 82208.84c 317905 Pb208 ENDF71x (jlconlin) Ref. see jlconlin (ref 09/10/2012 10:00:53) mat8237 12/22/12 Energy range: 1.00000E-11 to 1.50000E+02 MeV.

particle-production data for protons being expunged from 82208.84c particle-production data for deuterons being expunged from 82208.84c particle-production data for tritons being expunged from 82208.84c particle-production data for alphas being expunged from 82208.84c temperature = 2.1543E-07 adjusted to 2.5300E-08 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 Energy range: 1.00000E-03 to 1.00000E+05 MeV.

6000.84p 3228 Update of MCPLIB04 Photon Compton Broadening Data For MCNP5 see LA-UR-12-00018 01/03/12 Energy range: 1.00000E-03 to 1.00000E+05 MeV.

7000.84p 3270 Update of MCPLIB04 Photon Compton Broadening Data For MCNP5 see LA-UR-12-00018 01/03/12 Energy range: 1.00000E-03 to 1.00000E+05 MeV.

8000.84p 3348 Update of MCPLIB04 Photon Compton Broadening Data For MCNP5 see LA-UR-12-00018 01/03/12 Energy range: 1.00000E-03 to 1.00000E+05 MeV.

ATTACHMENT A - Responses to RAI October 2021 A-29 14000.84p 4868 Update of MCPLIB04 Photon Compton Broadening Data For MCNP5 see LA-UR-12-00018 01/03/12 Energy range: 1.00000E-03 to 1.00000E+05 MeV.

24000.84p 5758 Update of MCPLIB04 Photon Compton Broadening Data For MCNP5 see LA-UR-12-00018 01/03/12 Energy range: 1.00000E-03 to 1.00000E+05 MeV.

25000.84p 5674 Update of MCPLIB04 Photon Compton Broadening Data For MCNP5 see LA-UR-12-00018 01/03/12 Energy range: 1.00000E-03 to 1.00000E+05 MeV.

26000.84p 5794 Update of MCPLIB04 Photon Compton Broadening Data For MCNP5 see LA-UR-12-00018 01/03/12 Energy range: 1.00000E-03 to 1.00000E+05 MeV.

28000.84p 5902 Update of MCPLIB04 Photon Compton Broadening Data For MCNP5 see LA-UR-12-00018 01/03/12 Energy range: 1.00000E-03 to 1.00000E+05 MeV.

82000.84p 10086 Update of MCPLIB04 Photon Compton Broadening Data For MCNP5 see LA-UR-12-00018 01/03/12 Energy range: 1.00000E-03 to 1.00000E+05 MeV.

total 6579868 comment. 28 cross sections modified by free gas thermal treatment.

maximum photon energy set to 100.0 mev (maximum electron energy) tables from file xdata/el03 1000.03e 2329 6/6/98 Energy range: 1.00000E-03 to 1.00000E+03 MeV.

6000.03e 2333 6/6/98 Energy range: 1.00000E-03 to 1.00000E+03 MeV.

7000.03e 2333 6/6/98 Energy range: 1.00000E-03 to 1.00000E+03 MeV.

8000.03e 2333 6/6/98 Energy range: 1.00000E-03 to 1.00000E+03 MeV.

14000.03e 2339 6/6/98 Energy range: 1.00000E-03 to 1.00000E+03 MeV.

24000.03e 2345 6/6/98 Energy range: 1.00000E-03 to 1.00000E+03 MeV.

25000.03e 2345 6/6/98 Energy range: 1.00000E-03 to 1.00000E+03 MeV.

26000.03e 2345 6/6/98 Energy range: 1.00000E-03 to 1.00000E+03 MeV.

28000.03e 2347 6/6/98 Energy range: 1.00000E-03 to 1.00000E+03 MeV.

82000.03e 2373 6/6/98 Energy range: 1.00000E-03 to 1.00000E+03 MeV.

1particles and energy limits print table 101 particle maximum smallest largest always always cutoff particle table table use table use model particle type energy energy maximum maximum below above 1 n neutron 0.0000E+00 1.0000E+36 2.0000E+01 2.0000E+02 1.0000E+36 1.0000E+36 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 2 has been set to a conductor.

warning. material 3 has been set to a conductor.

warning. material 4 has been set to a conductor.

comment. setting up hash-based fast table search for xsec tables

=====> Set up arrays for hash-based fast table search for xsec data number of hash bins = 8192 min hash table energy = 1.00000E-11 max hash table energy = 2.00000E+02 nuclide ne emin emax ave_bins min_bins max_bins 1001.84c 590 1.00000E-11 2.00000E+01 0.1 0.0 1.0 1002.84c 583 1.00000E-11 1.50000E+02 0.1 0.0 2.0 6000.84c 1328 1.00000E-11 1.50000E+02 0.2 0.0 9.0 7014.84c 1826 1.00000E-11 1.50000E+02 0.2 0.0 20.0 7015.84c 939 1.00000E-11 2.00000E+01 0.1 0.0 6.0 8016.84c 2961 1.00000E-11 1.50000E+02 0.4 0.0 30.0 8017.84c 620 1.00000E-11 2.00000E+01 0.1 0.0 2.0 14028.84c 8019 1.00000E-11 1.50000E+02 1.0 0.0 115.0 14029.84c 4979 1.00000E-11 1.50000E+02 0.6 0.0 85.0 14030.84c 6089 1.00000E-11 1.50000E+02 0.7 0.0 89.0 24050.84c 29758 1.00000E-11 1.50000E+02 3.6 0.0 176.0 24052.84c 30705 1.00000E-11 1.50000E+02 3.7 0.0 214.0 24053.84c 21659 1.00000E-11 1.50000E+02 2.6 0.0 114.0

ATTACHMENT A - Responses to RAI October 2021 A-30 24054.84c 14261 1.00000E-11 1.50000E+02 1.7 0.0 155.0 25055.84c 11703 1.00000E-11 6.00000E+01 1.4 0.0 87.0 26054.84c 18775 1.00000E-11 1.50000E+02 2.3 0.0 156.0 26056.84c 26742 1.00000E-11 1.50000E+02 3.3 0.0 164.0 26057.84c 15731 1.00000E-11 1.50000E+02 1.9 0.0 175.0 26058.84c 10972 1.00000E-11 2.00000E+01 1.3 0.0 106.0 28058.84c 43443 1.00000E-11 1.50000E+02 5.3 0.0 285.0 28060.84c 33910 1.00000E-11 1.50000E+02 4.1 0.0 177.0 28061.84c 11091 1.00000E-11 1.50000E+02 1.4 0.0 96.0 28062.84c 11345 1.00000E-11 1.50000E+02 1.4 0.0 134.0 28064.84c 10310 1.00000E-11 1.50000E+02 1.3 0.0 276.0 82204.84c 11175 1.00000E-11 2.00000E+02 1.4 0.0 108.0 82206.84c 33882 1.00000E-11 2.00000E+02 4.1 0.0 256.0 82207.84c 11334 1.00000E-11 2.00000E+02 1.4 0.0 111.0 82208.84c 7220 1.00000E-11 1.50000E+02 0.9 0.0 112.0 dump no. 1 on file NCT_HP_SC-30G3_252Cf_0.r nps = 0 coll = 0 ctm = 0.00 nrn = 0 7 warning messages so far.

1problem summary run terminated when it had used 1200 minutes of computer time.

+ 08/29/21 09:52:54

=====> 205.55 M histories/hr (based on wall-clock time in mcrun) title HP/SC-30G3 with a Concentrated 252Cf Neutron Source - NCT probid = 08/29/21 09:02:49 neutron creation tracks weight energy neutron loss tracks weight energy (per source particle) (per source particle) source 171447570 1.0000E+00 3.1175E+00 escape 2218146 1.2938E-02 1.7473E-02 nucl. interaction 0 0. 0. energy cutoff 0 0. 0.

particle decay 0 0. 0. time cutoff 0 0. 0.

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

cell importance 0 0. 0. cell importance 0 0. 0.

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.

upscattering 0 0. 1.2297E-06 downscattering 0 0. 3.0708E+00 photonuclear 0 0. 0. capture 169294122 9.8744E-01 2.5583E-02 (n,xn) 129394 7.5471E-04 1.0222E-03 loss to (n,xn) 64696 3.7735E-04 4.6355E-03 prompt fission 0 0. 0. loss to fission 0 0. 0.

delayed fission 0 0. 0. nucl. interaction 0 0. 0.

prompt photofis 0 0. 0. particle decay 0 0. 0.

tabular boundary 0 0. 0. tabular boundary 0 0. 0.

tabular sampling 0 0. 0. elastic scatter 0 0. 0.

total 171576964 1.0008E+00 3.1185E+00 total 171576964 1.0008E+00 3.1185E+00 number of neutrons banked 64698 average time of (shakes) cutoffs neutron tracks per source particle 1.0008E+00 escape 2.0373E+04 tco 1.0000E+33 neutron collisions per source particle 1.2235E+02 capture 1.6753E+04 eco 0.0000E+00 total neutron collisions 20975978939 capture or escape 1.6800E+04 wc1 0.0000E+00 net multiplication 1.0004E+00 0.0000 any termination 1.6794E+04 wc2 0.0000E+00 photon creation tracks weight energy photon loss tracks weight energy (per source particle) (per source particle) source 0 0. 0. escape 2628755 1.5987E-02 2.8402E-02 nucl. interaction 0 0. 0. energy cutoff 11 6.8289E-08 2.4878E-04 particle decay 0 0. 0. time cutoff 0 0. 0.

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

cell importance 0 0. 0. cell importance 0 0. 0.

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 177752852 1.0395E+00 2.4178E+00 compton scatter 0 0. 1.9557E+00 bremsstrahlung 200339191 1.1722E+00 6.8769E-02 capture 564406502 3.3013E+00 4.2040E-01 p-annihilation 22175546 1.2986E-01 6.6359E-02 pair production 11087773 6.4929E-02 1.9237E-01 photonuclear 0 0. 0. photonuclear abs 0 0. 0.

ATTACHMENT A - Responses to RAI October 2021 A-31 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 153987535 9.0089E-01 4.2572E-02 2nd fluorescence 23867917 1.3965E-01 1.5735E-03 cerenkov 0 0. 0.

(gamma,xgamma) 0 0. 0.

tabular sampling 0 0. 0.

prompt photofis 0 0. 0.

total 578123041 3.3822E+00 2.5971E+00 total 578123041 3.3822E+00 2.5971E+00 number of photons banked 424135495 average time of (shakes) cutoffs photon tracks per source particle 3.3720E+00 escape 2.9777E+04 tco 1.0000E+33 photon collisions per source particle 1.0689E+01 capture 1.1985E+04 eco 1.0000E-03 total photon collisions 1832625563 capture or escape 1.2070E+04 wc1 0.0000E+00 any termination 1.2169E+04 wc2 0.0000E+00 computer time so far in this run 1201.19 minutes maximum number ever in bank 36 computer time in mcrun 1200.92 minutes bank overflows to backup file 0 source particles per minute 1.4276E+05 random numbers generated 420792660560 most random numbers used was 44705 in history 41959132 range of sampled source weights = 1.0000E+00 to 1.0000E+00 number of histories processed by each thread 7111511 7128881 7129558 7163609 7171458 7169343 7132174 7127869 7152665 7134414 7151424 7161679 7187632 7133190 7167871 7170197 7167598 7152356 7153966 7099399 7140547 7113408 7067195 7159626 1neutron 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 1 0 0 0 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 2 2 198133649 171447340 160035752 9.3344E-01 2.2084E-03 2.3253E+00 1.0000E+00 3.0950E+00 3 3 434888 213847 1319064 7.6937E-03 8.0301E-04 1.0050E+00 1.0000E+00 4.2307E+00 4 4 145243 77873 292410 1.7055E-03 2.4369E-03 1.0701E+00 1.0000E+00 4.2895E+00 5 5 127385 67644 118004 6.8828E-04 2.8420E-03 9.4328E-01 1.0000E+00 4.3012E+00 6 6 101097 72199 276431 1.6123E-03 2.8107E-03 8.6943E-01 1.0000E+00 4.9968E+00 7 7 14769462 7314174 22951209 1.3387E-01 2.2312E-04 8.0674E-01 1.0000E+00 2.7209E+00 8 8 8607744 5274740 34178538 1.9935E-01 3.3188E-04 8.8166E-01 1.0000E+00 3.7758E+00 9 9 4725019 3556812 5755947 3.3573E-02 6.2911E-04 1.0707E+00 1.0000E+00 3.7016E+00 10 10 94390 61268 249834 1.4572E-03 2.2166E-03 7.0206E-01 1.0000E+00 4.9979E+00 11 11 152941 95232 549418 3.2046E-03 2.9508E-03 7.4214E-01 1.0000E+00 5.3276E+00 12 12 66353 38500 72463 4.2265E-04 2.3313E-03 8.4294E-01 1.0000E+00 4.7190E+00 13 13 305339 164633 994059 5.7980E-03 6.3864E-04 1.0600E+00 1.0000E+00 3.9470E+00 14 14 138863 72349 345998 2.0181E-03 2.5808E-03 1.0088E+00 1.0000E+00 4.2553E+00 15 15 33030 24369 27468 1.6021E-04 1.6313E-03 6.0280E-01 1.0000E+00 4.0499E+00 16 16 27497 22717 11833 6.9018E-05 9.3338E-04 5.4818E-01 1.0000E+00 4.5738E+00 17 17 202892850 171421599 20716256087 1.2083E+02 6.9990E-05 4.4758E-01 1.0000E+00 9.5472E-01 18 18 107976 54555 0 0.0000E+00 2.6158E-03 9.8994E-01 1.0000E+00 0.0000E+00 19 19 6859 5547 0 0.0000E+00 3.4267E-03 7.3205E-01 1.0000E+00 0.0000E+00 20 20 5669593 3553671 0 0.0000E+00 4.3367E-04 9.4065E-01 1.0000E+00 0.0000E+00 21 21 12801 9535 0 0.0000E+00 4.9722E-03 6.8307E-01 1.0000E+00 0.0000E+00 22 22 24214 18552 0 0.0000E+00 1.1603E-03 5.7148E-01 1.0000E+00 0.0000E+00 23 23 153514 69573 0 0.0000E+00 2.3613E-03 1.1061E+00 1.0000E+00 0.0000E+00 24 24 3616573 3023203 0 0.0000E+00 5.7887E-04 5.0208E-01 1.0000E+00 0.0000E+00 25 201 6085358 3024714 7308145 4.2626E-02 6.0129E-04 7.8211E-01 1.0000E+00 2.6453E+00 26 202 4351129 2800586 23399829 1.3648E-01 3.4088E-04 6.9574E-01 1.0000E+00 1.5881E+01 27 203 2812747 2428292 1836450 1.0711E-02 6.7767E-04 9.4032E-01 1.0000E+00 2.6264E+00 28 204 5021934 3024251 0 0.0000E+00 7.3924E-04 1.0096E+00 1.0000E+00 0.0000E+00 29 205 2236980 2218146 0 0.0000E+00 1.1779E-03 1.2852E+00 1.0000E+00 0.0000E+00 30 301 39100 39100 0 0.0000E+00 9.8804E-04 1.0633E+00 1.0000E+00 0.0000E+00 31 302 18393 18393 0 0.0000E+00 9.9483E-04 1.1731E+00 1.0000E+00 0.0000E+00 total 460912921 380213414 20975978939 1.2235E+02 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 1 0 0 0 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 2 2 2948644 3779326 436308 2.5450E-03 1.8669E+00 1.8669E+00 1.0000E+00 1.9081E+01 3 3 12905043 15687878 43060382 2.5137E-01 9.9250E-01 9.9250E-01 1.0009E+00 1.8220E+00 4 4 2470775 6829420 12709919 7.4270E-02 1.3924E+00 1.3924E+00 1.0017E+00 1.3409E+00 5 5 301646 718601 1194220 7.0099E-03 1.4225E+00 1.4225E+00 1.0054E+00 1.3624E+00 6 6 114796 194468 491318 2.9061E-03 1.1693E+00 1.1693E+00 1.0128E+00 1.9379E+00 7 7 150210736 161269954 240405104 1.4034E+00 1.1485E+00 1.1485E+00 1.0010E+00 1.9332E+00 8 8 82746569 270845782 513589535 3.0050E+00 1.4961E+00 1.4961E+00 1.0028E+00 1.3986E+00

ATTACHMENT A - Responses to RAI October 2021 A-32 9 9 2590123 4498478 5157380 3.0484E-02 1.6210E+00 1.6210E+00 1.0121E+00 2.2182E+00 10 10 253385 353901 976300 5.7272E-03 1.0730E+00 1.0730E+00 1.0053E+00 1.8871E+00 11 11 229226 374990 1132686 6.6857E-03 1.0969E+00 1.0969E+00 1.0111E+00 1.8614E+00 12 12 609477 652299 1081364 6.3154E-03 9.9201E-01 9.9201E-01 1.0013E+00 1.8524E+00 13 13 12130203 14776858 39342827 2.2963E-01 9.8369E-01 9.8369E-01 1.0007E+00 1.8094E+00 14 14 2322841 6581530 12432876 7.2665E-02 1.3941E+00 1.3941E+00 1.0018E+00 1.3411E+00 15 15 36295 83125 138042 8.2038E-04 1.5113E+00 1.5113E+00 1.0173E+00 1.2340E+00 16 16 13805 16067 9353 5.7268E-05 1.5651E+00 1.5651E+00 1.0452E+00 2.0634E+00 17 17 27644010 189516876 947524648 5.5282E+00 9.9928E-01 9.9928E-01 1.0003E+00 1.3126E+01 18 18 203293 198688 0 0.0000E+00 1.4293E+00 1.4293E+00 1.0041E+00 0.0000E+00 19 19 8177 7448 0 0.0000E+00 1.1690E+00 1.1690E+00 1.0081E+00 0.0000E+00 20 20 3304874 2966609 0 0.0000E+00 1.6304E+00 1.6304E+00 1.0115E+00 0.0000E+00 21 21 32724 29352 0 0.0000E+00 1.0027E+00 1.0027E+00 1.0039E+00 0.0000E+00 22 22 11691 10893 0 0.0000E+00 1.5821E+00 1.5821E+00 1.0419E+00 0.0000E+00 23 23 2513390 2379166 0 0.0000E+00 1.0778E+00 1.0778E+00 1.0010E+00 0.0000E+00 24 24 2791707 2689575 0 0.0000E+00 1.5598E+00 1.5598E+00 1.0599E+00 0.0000E+00 25 201 4047942 5056171 7983354 4.8988E-02 1.6275E+00 1.6275E+00 1.0511E+00 2.0098E+00 26 202 3583293 3320205 1885027 1.1510E-02 1.4544E+00 1.4544E+00 1.0475E+00 1.1616E+02 27 203 3180937 3651603 3074920 1.8850E-02 1.5817E+00 1.5817E+00 1.0496E+00 1.9935E+00 28 204 3731514 3231746 0 0.0000E+00 1.5592E+00 1.5592E+00 1.0327E+00 0.0000E+00 29 205 2649542 2628755 0 0.0000E+00 1.7605E+00 1.7605E+00 1.0441E+00 0.0000E+00 30 301 45822 45822 0 0.0000E+00 1.7723E+00 1.7723E+00 1.0478E+00 0.0000E+00 31 302 20332 20332 0 0.0000E+00 1.7486E+00 1.7486E+00 1.0471E+00 0.0000E+00 total 323652812 702415918 1832625563 1.0706E+01 1summary of photons produced in neutron collisions in the tabular range production by cell of photons created with energies above local photon energy cutoffs cell number of weight per energy per avg photon mev/gm per weight/neut energy/neut photons source neut source neut energy source neut collision collision 1 1 0 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 2 2 913424 5.32772E-03 1.61699E-02 3.03505E+00 1.33656E-03 5.70762E-03 1.73229E-02 3 3 204043 1.21350E-03 3.92881E-03 3.23759E+00 2.48393E-08 1.57727E-01 5.10654E-01 4 4 22626 1.46897E-04 1.79979E-04 1.22521E+00 1.76010E-09 8.61293E-02 1.05526E-01 5 5 7603 4.91958E-05 6.00596E-05 1.22083E+00 1.03628E-09 7.14764E-02 8.72604E-02 6 6 25875 1.54650E-04 3.74729E-04 2.42308E+00 4.68759E-09 9.59168E-02 2.32414E-01 7 7 4842344 2.85857E-02 1.13600E-01 3.97403E+00 8.14474E-07 2.13537E-01 8.48605E-01 8 8 2401312 1.53410E-02 2.11210E-02 1.37677E+00 1.53240E-08 7.69541E-02 1.05948E-01 9 9 1043625 6.17422E-03 2.08328E-02 3.37416E+00 1.01982E-07 1.83906E-01 6.20529E-01 10 10 19830 1.18263E-04 3.12908E-04 2.64585E+00 4.59984E-09 8.11578E-02 2.14732E-01 11 11 43556 2.60141E-04 6.29503E-04 2.41985E+00 3.70004E-09 8.11778E-02 1.96438E-01 12 12 6699 4.01448E-05 9.98461E-05 2.48715E+00 7.84950E-09 9.49827E-02 2.36236E-01 13 13 170500 1.01332E-03 3.41471E-03 3.36982E+00 4.93891E-08 1.74770E-01 5.88943E-01 14 14 24881 1.61778E-04 2.02119E-04 1.24936E+00 1.70346E-09 8.01637E-02 1.00153E-01 15 15 962 6.17579E-06 7.41154E-06 1.20010E+00 2.85212E-10 3.85476E-02 4.62608E-02 16 16 1047 6.20955E-06 2.17363E-05 3.50047E+00 4.72085E-09 8.99697E-02 3.14936E-01 17 17 166604224 9.71750E-01 2.20504E+00 2.26914E+00 1.46755E-05 8.04220E-03 1.82489E-02 18 18 0 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 19 19 0 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 20 20 0 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 21 21 0 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 22 22 0 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 23 23 0 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 24 24 0 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 25 201 1043192 6.80803E-03 2.41630E-02 3.54919E+00 1.65460E-08 1.59715E-01 5.66859E-01 26 202 97096 5.66338E-04 1.45003E-03 2.56036E+00 2.07179E-09 4.14949E-03 1.06242E-02 27 203 280002 1.82082E-03 6.22352E-03 3.41798E+00 4.69431E-09 1.69988E-01 5.81016E-01 28 204 0 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 29 205 0 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 30 301 0 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 31 302 0 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 32 999 0 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 total 177752841 1.03954E+00 2.41783E+00 2.32586E+00 1energy distribution of photons produced in neutron collisions in the tabular range all sampled photons from neutron collisions in the tabular range, without regard to energy cutoffs energy number of number cum number weight of weight cum weight interval photons frequency distribution photons frequency distribution 20.000 6 3.37547E-08 3.37547E-08 4.00680E-08 3.85438E-08 3.85438E-08 15.000 45 2.53160E-07 2.86915E-07 2.74434E-07 2.63994E-07 3.02538E-07 10.000 2187 1.23036E-05 1.25905E-05 1.50398E-05 1.44677E-05 1.47702E-05 9.000 118890 6.68850E-04 6.81441E-04 7.12815E-04 6.85699E-04 7.00470E-04 8.000 100988 5.68137E-04 1.24958E-03 6.87854E-04 6.61688E-04 1.36216E-03 7.000 1840912 1.03566E-02 1.16062E-02 1.07971E-02 1.03864E-02 1.17485E-02 6.000 429486 2.41620E-03 1.40224E-02 2.60062E-03 2.50169E-03 1.42502E-02 5.000 439717 2.47375E-03 1.64961E-02 2.66847E-03 2.56696E-03 1.68172E-02

ATTACHMENT A - Responses to RAI October 2021 A-33 4.000 4067251 2.28815E-02 3.93776E-02 2.38383E-02 2.29315E-02 3.97487E-02 3.000 831880 4.67998E-03 4.40576E-02 5.01769E-03 4.82681E-03 4.45755E-02 2.000 164447507 9.25147E-01 9.69205E-01 9.59503E-01 9.23003E-01 9.67579E-01 1.000 1923435 1.08208E-02 9.80025E-01 1.17020E-02 1.12568E-02 9.78836E-01 0.500 2600383 1.46292E-02 9.94655E-01 1.61286E-02 1.55151E-02 9.94351E-01 0.100 830449 4.67193E-03 9.99327E-01 5.09152E-03 4.89784E-03 9.99248E-01 0.010 100569 5.65780E-04 9.99892E-01 6.60859E-04 6.35720E-04 9.99884E-01 0.000 19147 1.07717E-04 1.00000E+00 1.20422E-04 1.15842E-04 1.00000E+00

<-------- energy interval containing the global photon energy cutoff, 1.000E-03 MeV total 177752852 1.00000E+00 1.03954E+00 1.00000E+00 warning. 11 photons from neutron collisions were created below a local photon energy cutoff and were not followed.

1tally 4 nps = 171447570

+ Package Surface Neutron Dose Rate (mrem/hr) @ Z = 111.12500 tally type 4 track length estimate of particle flux.

particle(s): neutrons this tally is modified by dose function DE4 and DF4.

volumes cell: 301 3.81204E+02 cell 301 5.68309E-09 0.0082

=======================================================================================================================

results of 10 statistical checks for the estimated answer for the tally fluctuation chart (tfc) bin of tally 4 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 <0.10 yes 1/sqrt(nps) <0.10 yes 1/nps constant random >3.00 observed random 0.01 yes yes 0.00 yes yes constant random 6.23 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): 5.6373E-09 to 5.7301E-09; 5.5909E-09 to 5.7766E-09; 5.5444E-09 to 5.8230E-09 estimated symmetric confidence interval(1,2,3 sigma): 5.6367E-09 to 5.7295E-09; 5.5902E-09 to 5.7759E-09; 5.5438E-09 to 5.8224E-09 1analysis of the results in the tally fluctuation chart bin (tfc) for tally 4 with nps = 171447570 print table 160 normed average tally per history = 5.68309E-09 unnormed average tally per history = 2.16642E-06 estimated tally relative error = 0.0082 estimated variance of the variance = 0.0017 relative error from zero tallies = 0.0051 relative error from nonzero scores = 0.0064 number of nonzero history tallies = 39087 efficiency for the nonzero tallies = 0.0002 history number of largest tally = 47078243 largest unnormalized history tally = 3.73827E-01 (largest tally)/(average tally) = 1.72556E+05 (largest tally)/(avg nonzero tally)= 3.93396E+01 (confidence interval shift)/mean = 0.0001 shifted confidence interval center = 5.68371E-09 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 5.68309E-09 5.68881E-09 0.001006 relative error 8.16920E-03 8.22268E-03 0.006548 variance of the variance 1.70279E-03 1.87581E-03 0.101605 shifted center 5.68371E-09 5.68375E-09 0.000006 figure of merit 1.24775E+01 1.23157E+01 -0.012968 the estimated inverse power slope of the 200 largest tallies starting at 6.41056E-02 is 6.2335 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 = (1.428E+05)*( 9.349E-03)**2 = (1.428E+05)*(8.740E-05) = 1.248E+01 1tally 14 nps = 171447570

ATTACHMENT A - Responses to RAI October 2021 A-34

+ 2-M from Package Surface Neutron Dose Rate (mrem/hr) @ Z = 111.12500 tally type 4 track length estimate of particle flux.

particle(s): neutrons this tally is modified by dose function DE14 and DF14.

volumes cell: 302 1.01958E+03 cell 302 7.14939E-10 0.0099

=======================================================================================================================

results of 10 statistical checks for the estimated answer for the tally fluctuation chart (tfc) bin of tally 14 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 <0.10 yes 1/sqrt(nps) <0.10 yes 1/nps constant random >3.00 observed random 0.01 yes yes 0.00 yes yes constant random 10.00 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): 7.0789E-10 to 7.2206E-10; 7.0081E-10 to 7.2914E-10; 6.9373E-10 to 7.3623E-10 estimated symmetric confidence interval(1,2,3 sigma): 7.0786E-10 to 7.2202E-10; 7.0077E-10 to 7.2910E-10; 6.9369E-10 to 7.3619E-10 1analysis of the results in the tally fluctuation chart bin (tfc) for tally 14 with nps = 171447570 print table 160 normed average tally per history = 7.14939E-10 unnormed average tally per history = 7.28934E-07 estimated tally relative error = 0.0099 estimated variance of the variance = 0.0001 relative error from zero tallies = 0.0074 relative error from nonzero scores = 0.0066 number of nonzero history tallies = 18389 efficiency for the nonzero tallies = 0.0001 history number of largest tally = 160886395 largest unnormalized history tally = 2.35213E-02 (largest tally)/(average tally) = 3.22681E+04 (largest tally)/(avg nonzero tally)= 3.46099E+00 (confidence interval shift)/mean = 0.0001 shifted confidence interval center = 7.14977E-10 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 7.14939E-10 7.15074E-10 0.000188 relative error 9.90682E-03 9.90675E-03 -0.000008 variance of the variance 1.20396E-04 1.20440E-04 0.000360 shifted center 7.14977E-10 7.14977E-10 0.000000 figure of merit 8.48433E+00 8.48446E+00 0.000016 the estimated slope of the 198 largest tallies starting at 1.61949E-02 appears to be decreasing at least exponentially.

the empirical history score probability density function appears to be increasing at the largest history scores:

please examine. see print table 161.

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 = (1.428E+05)*( 7.709E-03)**2 = (1.428E+05)*(5.943E-05) = 8.484E+00 1tally 24 nps = 171447570

+ Package Surface Gamma Dose Rate (mrem/hr) @ Z = 111.12500 tally type 4 track length estimate of particle flux.

particle(s): photons this tally is modified by dose function DE24 and DF24.

volumes cell: 301 3.81204E+02 cell 301 2.62073E-10 0.0085

=======================================================================================================================

ATTACHMENT A - Responses to RAI October 2021 A-35 results of 10 statistical checks for the estimated answer for the tally fluctuation chart (tfc) bin of tally 24 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 <0.10 yes 1/sqrt(nps) <0.10 yes 1/nps constant random >3.00 observed random 0.01 yes yes 0.00 yes yes constant random 4.56 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): 2.5990E-10 to 2.6434E-10; 2.5768E-10 to 2.6656E-10; 2.5546E-10 to 2.6878E-10 estimated symmetric confidence interval(1,2,3 sigma): 2.5985E-10 to 2.6429E-10; 2.5763E-10 to 2.6651E-10; 2.5541E-10 to 2.6873E-10 1analysis of the results in the tally fluctuation chart bin (tfc) for tally 24 with nps = 171447570 print table 160 normed average tally per history = 2.62073E-10 unnormed average tally per history = 9.99030E-08 estimated tally relative error = 0.0085 estimated variance of the variance = 0.0038 relative error from zero tallies = 0.0047 relative error from nonzero scores = 0.0070 number of nonzero history tallies = 44645 efficiency for the nonzero tallies = 0.0003 history number of largest tally = 56671873 largest unnormalized history tally = 2.66690E-02 (largest tally)/(average tally) = 2.66949E+05 (largest tally)/(avg nonzero tally)= 6.95137E+01 (confidence interval shift)/mean = 0.0002 shifted confidence interval center = 2.62116E-10 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 2.62073E-10 2.62481E-10 0.001557 relative error 8.46907E-03 8.59762E-03 0.015179 variance of the variance 3.81789E-03 4.64129E-03 0.215670 shifted center 2.62116E-10 2.62122E-10 0.000020 figure of merit 1.16095E+01 1.12650E+01 -0.029681 the estimated inverse power slope of the 200 largest tallies starting at 3.19323E-03 is 4.5605 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 = (1.428E+05)*( 9.018E-03)**2 = (1.428E+05)*(8.132E-05) = 1.161E+01 1tally 34 nps = 171447570

+ 2-M from Package Surface Gamma Dose Rate (mrem/hr) @ Z = 111.12500 tally type 4 track length estimate of particle flux.

particle(s): photons this tally is modified by dose function DE34 and DF34.

volumes cell: 302 1.01958E+03 cell 302 3.11558E-11 0.0095

=======================================================================================================================

results of 10 statistical checks for the estimated answer for the tally fluctuation chart (tfc) bin of tally 34 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 <0.10 yes 1/sqrt(nps) <0.10 yes 1/nps constant random >3.00 observed random 0.01 yes yes 0.00 yes yes constant random 10.00 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.

ATTACHMENT A - Responses to RAI October 2021 A-36

estimated confidence intervals: -----

estimated asymmetric confidence interval(1,2,3 sigma): 3.0860E-11 to 3.1455E-11; 3.0563E-11 to 3.1753E-11; 3.0266E-11 to 3.2050E-11 estimated symmetric confidence interval(1,2,3 sigma): 3.0858E-11 to 3.1453E-11; 3.0561E-11 to 3.1751E-11; 3.0263E-11 to 3.2048E-11 1analysis of the results in the tally fluctuation chart bin (tfc) for tally 34 with nps = 171447570 print table 160 normed average tally per history = 3.11558E-11 unnormed average tally per history = 3.17657E-08 estimated tally relative error = 0.0095 estimated variance of the variance = 0.0003 relative error from zero tallies = 0.0070 relative error from nonzero scores = 0.0065 number of nonzero history tallies = 20228 efficiency for the nonzero tallies = 0.0001 history number of largest tally = 141742412 largest unnormalized history tally = 1.99122E-03 (largest tally)/(average tally) = 6.26847E+04 (largest tally)/(avg nonzero tally)= 7.39577E+00 (confidence interval shift)/mean = 0.0001 shifted confidence interval center = 3.11579E-11 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 3.11558E-11 3.11672E-11 0.000366 relative error 9.54731E-03 9.55082E-03 0.000367 variance of the variance 2.69260E-04 2.70617E-04 0.005037 shifted center 3.11579E-11 3.11579E-11 0.000000 figure of merit 9.13532E+00 9.12861E+00 -0.000734 the estimated slope of the 200 largest tallies starting at 1.14935E-03 appears to be decreasing at least exponentially.

the empirical history score probability density function appears to be increasing at the largest history scores:

please examine. see print table 161.

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 = (1.428E+05)*( 7.999E-03)**2 = (1.428E+05)*(6.399E-05) = 9.135E+00 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 4 passed the 10 statistical checks for the tally fluctuation chart bin result passed all bin error check: 1 tally bins all have relative errors less than 0.10 with no zero bins 14 passed the 10 statistical checks for the tally fluctuation chart bin result passed all bin error check: 1 tally bins all have relative errors less than 0.10 with no zero bins 24 passed the 10 statistical checks for the tally fluctuation chart bin result passed all bin error check: 1 tally bins all have relative errors less than 0.10 with no zero bins 34 passed the 10 statistical checks for the tally fluctuation chart bin result passed all bin error check: 1 tally bins all have relative errors less than 0.10 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 4 tally 14 tally 24 nps mean error vov slope fom mean error vov slope fom mean error vov slope fom 16384000 5.9170E-09 0.0265 0.0142 2.7 12 7.4784E-10 0.0313 0.0012 2.4 9.0E+00 2.5732E-10 0.0261 0.0194 3.0 13 32768000 5.8371E-09 0.0180 0.0056 3.7 13 7.3031E-10 0.0224 0.0006 2.3 8.7E+00 2.5931E-10 0.0197 0.0172 2.8 11 49152000 5.8140E-09 0.0155 0.0062 3.8 12 7.2340E-10 0.0184 0.0004 2.1 8.6E+00 2.6214E-10 0.0163 0.0133 2.5 11 65536000 5.8045E-09 0.0134 0.0045 3.1 12 7.1340E-10 0.0160 0.0003 2.0 8.5E+00 2.6326E-10 0.0145 0.0141 2.7 10 81920000 5.7419E-09 0.0120 0.0035 3.2 12 7.1880E-10 0.0143 0.0003 2.1 8.5E+00 2.6244E-10 0.0126 0.0103 3.2 11 98304000 5.7412E-09 0.0109 0.0028 4.3 12 7.1736E-10 0.0131 0.0002 2.2 8.5E+00 2.6052E-10 0.0114 0.0079 3.6 11 114688000 5.7437E-09 0.0101 0.0024 5.8 12 7.1261E-10 0.0121 0.0002 2.6 8.5E+00 2.6185E-10 0.0106 0.0069 3.5 11 131072000 5.7188E-09 0.0093 0.0020 6.1 13 7.1480E-10 0.0113 0.0002 10.0 8.5E+00 2.6196E-10 0.0098 0.0057 3.6 11 147456000 5.6975E-09 0.0088 0.0018 6.7 13 7.1275E-10 0.0107 0.0001 10.0 8.5E+00 2.6231E-10 0.0092 0.0047 3.8 11 163840000 5.6938E-09 0.0084 0.0018 5.7 12 7.1530E-10 0.0101 0.0001 10.0 8.5E+00 2.6166E-10 0.0087 0.0040 4.4 12 171447570 5.6831E-09 0.0082 0.0017 6.2 12 7.1494E-10 0.0099 0.0001 10.0 8.5E+00 2.6207E-10 0.0085 0.0038 4.6 12 tally 34 nps mean error vov slope fom 16384000 3.0563E-11 0.0308 0.0029 2.3 9.2E+00 32768000 3.0828E-11 0.0222 0.0015 2.2 8.9E+00 49152000 3.1033E-11 0.0180 0.0010 3.6 9.0E+00 65536000 3.0838E-11 0.0156 0.0007 10.0 9.0E+00 81920000 3.0875E-11 0.0139 0.0006 10.0 9.0E+00 98304000 3.0942E-11 0.0127 0.0005 10.0 9.1E+00

ATTACHMENT A - Responses to RAI October 2021 A-37 114688000 3.1228E-11 0.0117 0.0004 10.0 9.1E+00 131072000 3.1171E-11 0.0109 0.0003 10.0 9.1E+00 147456000 3.1194E-11 0.0103 0.0003 10.0 9.2E+00 163840000 3.1136E-11 0.0098 0.0003 10.0 9.1E+00 171447570 3.1156E-11 0.0095 0.0003 10.0 9.1E+00 dump no. 2 on file NCT_HP_SC-30G3_252Cf_0.r nps = 171447570 coll = 22808604502 ctm = 1200.92 nrn = 420792660560 tally data written to file NCT_HP_SC-30G3_252Cf_0.m 8 warning messages so far.

run terminated when it had used 1200 minutes of computer time.

computer time = 1201.20 minutes mcnp version 6 02/20/18 08/29/21 09:52:54 probid = 08/29/21 09:02:49

2. SC-30G3 HAC Model with 252Cf - Polyethylene with Secondary Gammas Code Name & Version = MCNP_6.20, 6.2.0