ML22055A629

Transmittal Letter: TRUPACT-II Package Application, Revision 25, Docket No. 71-9218, and Halfpact Package Application, Revision 8, Docket No. 71-9279 (Epids L-2021-LLA-0033 and L-2021-LLA-0034)

ML22055A629
Person / Time
Site:	07109218, 07109279
Issue date:	02/24/2022
From:	Sellmer T Nuclear Waste Partnership
To:	Document Control Desk, Office of Nuclear Material Safety and Safeguards
Shared Package
ML22055A628	List: ML22055A629 ML22055A632 ML22055A633
References
EPID L-2021-LLA-003, EPID L-2021-LLA-0033, TS:22:03009, UFC:5822.00
Download: ML22055A629 (25)

Text

TS:22:03009 UFC:5822.00 February 24, 2022 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:

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)

4. Letter from T. E. Sellmer to Document Control Desk dated October 6, 2021, 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)

5. Letter from T. E. Sellmer to Document Control Desk dated November 18, 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 (EPIDS L-2021-LLA-0033 and L-2021-LLA-0034)

6. E-mail from N. Garcia Santos to T. E. Sellmer dated December 9, 2021, subject: TRUPACT-II\HalfPACT - Telephone call Follow up Questions

7. E-mail from S. Burns to N. Garcia Santos dated January 28, 2022, subject: TRUPACT-II\HalfPACT - Telephone call Follow up Questions

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 through 5). This amendment includes revisions to Section 5.5.10 of P.O. Box 2078 z Carlsbad, New Mexico USA 88221-2078 Phone: (575) 234-7200 z Fax: (575) 234-7083

Document Control Desk TS:22:03009 the TRUPACT-II Safety Analysis Report (SAR), Chapter 8 of the HalfPACT SAR, and HalfPACT SAR Drawing Nos. 163-010, 163-011, and 163-013 in response to the questions provided in Reference 6, and consists of the following documents:

x TRUPACT-II 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.

The responses to the questions submitted in Reference 6 are provided in Attachment A (Reference 7). New changes to the documents are summarized in Attachment B and are indicated by right-bars in the margin of the documents (l). Right-bars in the margin of the documents (l) indicating technical changes made to the documents in the original submittal and the subsequent amendments of this application (References 2, 4, and 5) have also been retained with this submittal.

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, TODD SELLMER Digitally signed by TODD SELLMER (Affiliate)

(Affiliate) Date: 2022.02.24 09:43:25 -07'00' 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. Garcia Santos, USNRC B. H. White, USNRC P.O. Box 2078 z Carlsbad, New Mexico USA 88221-2078 Phone: (575) 234-7200 z Fax: (575) 234-7083

Document Control Desk TS:22:03009 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 Size Release Submittal File Name (MB) Level Type Publicly 001 Transmittal Letter - February 2022.pdf 3.2 EIE Available Publicly 002 TRUPACT-II SAR R25 - February 2022.pdf 38.5 EIE Available Publicly 003 HalfPACT SAR R8 - February 2022.pdf 43.1 EIE Available Publicly 004 CH-TRAMPAC R6 - February 2022.pdf 6.3 EIE Available 005 CH-TRU Payload Appendices R5 - February Publicly 50.9 EIE 2022.pdf Available P.O. Box 2078 z Carlsbad, New Mexico USA 88221-2078 Phone: (575) 234-7200 z Fax: (575) 234-7083

Attachment A - Responses to Follow-up Questions February 2022

1. Update the following information in TRUPACT-II SAR tables 5.4-12, 5.4-13 and 5.4-15 based upon the results of SCA-CAL-0005 (ADAMS Accession No. ML21279A188) to demonstrate compliance with the applicable regulatory limits in 10 CFR Part 71:

a. calculated dose rate (mrem/hr)

b. tally error

c. allowable activity (par/s) and

d. allowable activity (Ci)

Response

Table 5.4-16 in Section 5.4.5 of the TRUPACT-II Safety Analysis Report reports a maximum 0.8% increase for the NCT 2-meter dose rate for axial gaps of 1/2 inch at both ends of the sidewall lead column. For simplicity and conservatism, it is proposed to alternatively increase the activity limit administrative margin defined in Section 5.5.10 by 1% (from 10% to 11%) to account for the maximum lead gap in lieu of updating Tables 5.4-12, 5.4-13, and 5.4-15 for the SC-30G2, SC-30G3, and SC-55G2, respectively. Accordingly, Step 10 in Section 5.5.10 is revised to say:

10. For all payloads except the SC-30G2, SC-30G3, and SC-55G2, ensure that the combined sum of the sum of fractions for the gamma and the neutron source term is less than or equal to 0.90. For the SC-30G2, SC-30G3, and SC-55G2 payloads, ensure that the combined sum of the sum of fractions for the gamma and the neutron source term is less than or equal to 0.89.

2. Update the following information in TRUPACT-II SAR tables 5.5-16, 5.5-18 and 5.5-22 based upon the results of SCA-CAL-0005 (ADAMS Accession No. ML21279A188) to demonstrate compliance with the applicable regulatory limits in 10 CFR Part 71:

a. calculated dose rate (mrem/hr)

b. tally error and

c. allowable activity (/s)

Response

See response to No. 1, above. As for response No. 1, there is no need to revise Tables 5.5-16, 5.5-18, and 5.5-22 for the SC-30G2, SC-30G3, and SC-55G2, respectively, since the revised administrative margin for these containers is 11%,

and is included in the determination of acceptable activity in Step 10 of Section 5.5.10 of the TRUPACT-II Safety Analysis Report.

A-1

Attachment A - Responses to Follow-up Questions February 2022

3. Is the gamma scan performed on an assembled container or only on individual components?

Response

With reference to Figure 1, Figure 2, and Figure 3 for the SC-30G2, SC-30G3, and SC-55G2 shielded containers, respectively, the gamma scan process is performed on the container body without the base lead or outer base plates installed, and without the prototypic lid installed.

To simulate the presence of these components for ALARA purposes, a test base is used that has lead and steel plates of similar thicknesses and diameters as specified in the fabrication drawings, less sufficient sliding clearances to fit within the container body base for gamma scan testing. Similarly, the test lid is a prototypic lid, but also includes a center hole to allow access for the gamma scan tests radioactive source and a slightly reduced step diameter for sufficient clearance with the unfinished upper flange.

Upon successful completion of gamma scan testing, the base lead and steel plates are machined and installed in the body assembly and the filter shield plug and lid lead plate is machined and installed in the lid assembly.

A-2

Attachment A - Responses to Follow-up Questions February 2022 Figure 1 - SC-30G2 Gamma Scan Test Assembly Exploded View A-3

Attachment A - Responses to Follow-up Questions February 2022 Figure 2 - SC-30G3 Gamma Scan Test Assembly Exploded View A-4

Attachment A - Responses to Follow-up Questions February 2022 Figure 3 - SC-55G2 Gamma Scan Test Assembly Exploded View A-5

Attachment A - Responses to Follow-up Questions February 2022

4. Explain how the gamma scan will be used to measure the thickness of the lead shield in the corners of the shielded container. If the gamma scan is not used, explain how you ensure that the thickness of the lead in the corners of the shielded container are within the values shown in the licensing drawings.

Response

The current gamma scan process only evaluates shielding efficacy over the axial span of the payload cavity, a decision based on the deep overlap of the sidewall lead beyond the payload cavity preventing a significant increase in measured dose rate at the containers surface. Shielding efficacy is determined by a combination of container geometry, materials, and distance between the source and detector.

With reference to Figure 4, grid locations aligned with the payload cavity are scanned with the source axially aligned with the detector; the reject count rate (RCR; i.e., acceptance criterion) is based on a flat-block calibration measurement. The axial grid locations for the straight-shot measurements are as follows: 1.5 - 30.0 for the SC-30G2 and SC-30G3, and 1.5 - 36.0 for the SC-55G2.

Figure 4 - Example SC-30G3 Gamma Scan Test Configuration A-6

Attachment A - Responses to Follow-up Questions February 2022 For axial grid locations below and above the payload cavity, however, the gamma scan procedure will be revised to include measurements for shielding efficacy using the following steps:

a. Establish a source position above the bottom of the payload cavity that allows angled dose rate measurements beyond the payload cavity, including measuring for the presence of axial gaps in the sidewall lead. Figure 5, Figure 6, and Figure 7 for the SC-30G2, SC-30G3, and SC-55G2, respectively, show the detector in its lowest and highest grid positions for detecting the presence of axial gaps at the ends of the sidewall lead column. The detector in the three figures is assumed to have a relatively standard, 2-inch diameter scintillator face.

b. Create MCNP models of the prototypic gamma scan test configurations for the SC-30G2, SC-30G3, and SC-55G2 designs with minimum material conditions, i.e., minimum steel shell and sidewall lead thicknesses, including the presence of a 1/2-inch axial gap at both ends of the sidewall lead column. The model will include a test base and lid, as described in the previous response; both are reusable for gamma scan testing all units of that size.

c. Run the three MCNP models for a unit source strength of 60Co and 192Ir (the two most commonly used radionuclides for gamma scan testing) for a straight-through-the-wall baseline case, then for the slant-shot grid rows below and above the payload cavity. For example, with reference to Figure 5 for the SC-30G2, the below and above grid locations are -1.5, -3.0, 31.5, and 33.0. An RCR adjustment factor can be applied to these slant-shot grid rows by calculating the ratio of the slant-shot unit dose rate with the straight-through unit dose rate for each grid row.

Section 8.1.5 of the HalfPACT Safety Analysis Report will be revised to summarize the above process for slant-shot gamma scan testing beyond the payload cavities for the SC-30G2, SC-30G3, and SC-55G2 containers.

A-7

Attachment A - Responses to Follow-up Questions February 2022 Figure 5 - SC-30G2 Gamma Scan Grid Layout Beyond the Payload Cavity A-8

Attachment A - Responses to Follow-up Questions February 2022 Figure 6 - SC-30G3 Gamma Scan Grid Layout Beyond the Payload Cavity A-9

Attachment A - Responses to Follow-up Questions February 2022 Figure 7 - SC-55G2 Gamma Scan Grid Layout Beyond the Payload Cavity A-10

Attachment A - Responses to Follow-up Questions February 2022

5. Provide the maximum amount of the proposed content that can be shipped a single shielded container and per shipment considering the applicable regulatory limits in 10 CFR Part 71. Also, provide the calculation as part of your response.

Response

The maximum activity per shipment is provided in Section 5.5 of the TRUPACT-II Safety Analysis Report; the tables therein list activity limits based on a per package (payload) basis. More specifically, Section 5.5.10 of the TRUPACT-II Safety Analysis Report lists the applicable steps that are followed to ensure the shielded container payloads are in compliance with 10 CFR Part 71. Three examples of calculating the allowable activity are provided in Section 5.5.10.1 for various container types and concentrated/distributed sources (note the table references in Section 5.5.10.1 are incorrect and will be updated). The final step of Section 5.5.10 is to ensure that the combined sum of fractions for the gamma and the neutron source term is less than or equal to 0.90 for a package (with the exception of the SC-30G2, SC-30G3, and SC-55G2 containers where the combined sum of fractions for the gamma and the neutron source term is less than or equal to 0.89). As explained below, this sum of fractions of 0.90 (or 0.89, as appropriate) represents the maximum allowable activity for both a single container a well as the package.

For a shipment, up to three packages meeting the activity limits specified in Section 5.5 are allowed on a trailer.

One SC-30G3 can be shipped in a HalfPACT package; therefore, the activity limit for the package/container is determined using Tables 5.5-18 and 5.5-19 for gamma and neutron wastes, respectively, where the combined sum of fractions for the gamma and the neutron source term is less than or equal to 0.89.

Similarly, one SC-55G2 can be shipped in a HalfPACT package; therefore, the activity limit for the package/container is determined using Tables 5.5-22 and 5.5-23 for gamma and neutron wastes, respectively, where the combined sum of fractions for the gamma and the neutron source term is less than or equal to 0.89.

For the SC-30G2, where there are two containers per HalfPACT, the theoretical maximum activity limit for a shielded container is equal to the package activity limit, assuming one of the shielded containers in the HalfPACT package is empty. In reality, containers certified for shipment would never approach these limits due to other limiting factors, mainly the CH-TRAMPAC payload container surface dose rate requirement not exceeding 200 mrem/hr. The activity limit for the package/container is determined using Tables 5.5-16 and 5.5-17 for gamma and neutron wastes, respectively, where the combined sum of fractions for the gamma and the neutron source term is less than or equal to 0.89.

Finally, for the SC-55G1, where there are two containers per HalfPACT, the theoretical maximum activity limit for a shielded container is again equal to the package activity limit, assuming one of the shielded containers in the HalfPACT package is empty. As previously stated, containers certified for shipment would never approach these limits due to other limiting factors, mainly the CH-TRAMPAC payload container surface dose rate requirement not exceeding 200 mrem/hr. The A-11

Attachment A - Responses to Follow-up Questions February 2022 activity limit for the package/container is determined using Tables 5.5-20 and 5.5-21 for gamma and neutron wastes, respectively, where the combined sum of fractions for the gamma and the neutron source term is less than or equal to 0.90.

As an example calculation, assume a HalfPACT package payload consists of an SC-30G3 containing waste debris contaminated with 0.01 Ci of 252Cf and a 1.0-cm diameter by 1.5-cm long metal capsule containing 20 Ci of 60Co. Following the 10-step process delineated in Section 5.5.10 yields the following results:

1. The neutron radionuclide is 252Cf with a total activity of 0.005 Ci, and the gamma radionuclide is 60Co with a total activity of 20 Ci.

2. The neutron debris is distributed, but will be treated as concentrated to avoid having to show it meets the requirement of Case B. The gamma source is concentrated.

3. N/A; not a distributed gamma source, so source density is not applicable.

4. See Table 1 for a list of all discrete gamma energies and intensities.

5. See Table 1; the gamma source strength (/s) is determined as the product of the source activity (Ci), Intensity (%), and conversion factor (3.7E+10 /s/Ci).

Thus, for the 1.173237 MeV gamma energy, the source strength is (20 Ci) x (9.9974E+01% / 100) x (3.7E+10 /s/Ci) = 7.3981E+11 /s.

6. See Table 1; the allowable fraction is the ratio of the source strength to the allowable activity for each discrete gamma energy. The source strength is log-log interpolated from the allowable activities found in Table 5.5-18 for a concentrated gamma source. Thus, for the 1.173237 MeV gamma energy, the log-log interpolated allowable activity is 3.2487E+12 /s, and the corresponding allowable fraction is (7.3981E+11 /s) / (3.2487E+12 /s) = 2.28E-01.

7. See Table 1; the neutron source spectrum for 252Cf is found in Section 5.2.2.

8. See Table 1; the neutron source strength (n/s) is determined as the product of the source activity (Ci) and source strength (n/s/g) divided by the specific activity for 252Cf (536 Ci/g). Thus, for the 0.5 MeV neutron energy, the source strength is (0.01 Ci) x (1.8000E+11 n/s/g) / (536 Ci/g) = 3.3582E+06 n/s.

9. See Table 1; the allowable fraction is the ratio of the source strength to the allowable activity for each discrete neutron energy. The source strength is log-log interpolated from the allowable activities found in Table 5.5-19 for a concentrated neutron source. Thus, for the 0.5 MeV neutron energy, the log-log interpolated allowable activity is 3.7900E+08 n/s, and the corresponding allowable fraction is (3.3582E+06 n/s) / (3.7900E+08 n/s) = 8.86E-03.

10. See Table 1; the combined sum of the sum of fractions for the gamma and neutron source terms, 0.854, is less than or equal to 0.89; thus, the HalfPACT package is authorized for transport.

A-12

Attachment A - Responses to Follow-up Questions February 2022 Table 1 - Acceptable Activity Example for an SC-30G3 with 252Cf and 60Co Gamma Source Allowable Energy Strength Activity Allowable (MeV) Intensity (%) (/s) (/s) Fraction Comment 0.0434 1.4800E-02 0.0000E+00 0.0000E+00 0.00E+00 252 Cf; ignored: Energy < 0.15 MeV 0.1002 1.3000E-02 0.0000E+00 0.0000E+00 0.00E+00 252 Cf; ignored: Energy < 0.15 MeV 0.1545 5.0400E-04 0.0000E+00 1.7011E+24 0.00E+00 252 Cf; ignored: Intensity < 0.1%

0.34693 7.6000E-03 0.0000E+00 7.0957E+17 0.00E+00 60 Co; ignored: Intensity < 0.1%

0.82628 7.6000E-03 0.0000E+00 3.7353E+13 0.00E+00 60 Co; ignored: Intensity < 0.1%

1.173237 9.9974E+01 7.3981E+11 3.2487E+12 2.28E-01 60 Co 1.332501 9.9986E+01 7.3990E+11 1.7274E+12 4.28E-01 60 Co 2.15877 1.1100E-03 0.0000E+00 3.8681E+11 0.00E+00 60 Co; ignored: Intensity < 0.1%

2.505 2.0000E-06 0.0000E+00 2.8477E+11 0.00E+00 60 Co; ignored: Intensity < 0.1%

Total Gamma 6.56E-01 DCF has no effect due to screening Neutron Source Source Allowable Energy Strength Strength Activity Allowable (MeV) (n/s/g) (n/s) (n/s) Fraction Comment 0.5 1.8000E+11 3.3582E+06 3.7900E+08 8.86E-03 252 Cf 1 2.7100E+11 5.0560E+06 2.5500E+08 1.98E-02 252 Cf 2 5.3600E+11 1.0000E+07 1.8600E+08 5.38E-02 252 Cf 3 4.1000E+11 7.6493E+06 1.7652E+08 4.33E-02 252 Cf 4 2.7300E+11 5.0933E+06 1.7735E+08 2.87E-02 252 Cf 6 2.6600E+11 4.9627E+06 1.7076E+08 2.91E-02 252 Cf 8 8.5300E+10 1.5914E+06 1.5993E+08 9.95E-03 252 Cf 10 2.4400E+10 4.5522E+05 1.5200E+08 2.99E-03 252 Cf 15 8.3600E+09 1.5597E+05 1.0900E+08 1.43E-03 252 Cf Total Neutron 1.98E-01 DCF is not applicable to neutrons Total Gamma & Neutron 8.54E-01 Authorized for Transport, F 0.89 A-13

Attachment A - Responses to Follow-up Questions February 2022

6. During the phone call last week, the applicant mentioned that they performed a calculation assuming a 1/2 -in. gap of the lead shield. Using the 1/2 -in. gap of the lead shield, provide the allowable activity calculation using the applicable 10 CFR Part 71 dose\dose rate limit.

Response

The evaluation for the effect of axial sidewall lead gaps of up to 1/2 inch is provided in Section 5.4.5 of the TRUPACT-II Safety Analysis Report and in calculation SCA-CAL-0005 (ADAMS Accession No. ML21279A188). Allowable activity calculations that account for the calculated dose rate increases from Section 5.4.5 are discussed in the above responses.

A-14

ATTACHMENT B - Summary of Revisions Summary Pg.

TRUPACT-II SAR, Revision 25 B-2 HalfPACT SAR, Revision 8 B-3 SC-30G2 Shielded Container SAR Drawing, 163-010, Revision 1 B-4 SC-30G3 Shielded Container SAR Drawing, 163-011, Revision 1 B-5 SC-55G2 Shielded Container SAR Drawing, 163-013, Revision 1 B-6 CH-TRAMPAC, Revision 6 B-7 CH-TRU Payload Appendices, Revision 5 B-8 February 2022 B-1

ATTACHMENT B - Summary of Revisions TRUPACT-II SAR, Revision 25, February 2022 Section Page Change Description Justification General Revised header for date. Administrative change. No impact to safety basis.

5.5.10 5.5-50 Step 10 in Section 5.5.10 has been revised as As described in Attachment A, Response No. 1:

follows:

Table 5.4-16 in Section 5.4.5 of the TRUPACT-II

10. For all payloads except the SC-30G2, Safety Analysis Report (SAR) reports a maximum SC-30G3, and SC-55G2, ensure that the 0.8% increase for the NCT 2-meter dose rate for combined sum of the sum of fractions for the axial gaps of 1/2 inch at both ends of the sidewall gamma and the neutron source term is less than lead column. For simplicity and conservatism, the or equal to 0.90. For the SC-30G2, SC-30G3, activity limit administrative margin defined in and SC-55G2 payloads, ensure that the Section 5.5.10 is increased by 1% (from 10% to combined sum of the sum of fractions for the 11%) to account for the maximum lead gap in lieu gamma and the neutron source term is less than of updating Tables 5.4-12, 5.4-13, and 5.4-15 for or equal to 0.89. the SC-30G3, SC-30G3, and SC-55G2, respectively.

February 2022 B-2

ATTACHMENT B - Summary of Revisions HalfPACT SAR, Revision 8, February 2022 Section Page Change Description Justification General Revised header for date. Administrative change. No impact to safety basis.

8.1.5 8.1-18 thru Section 8.1.5 of the HalfPACT SAR has been The gamma scan procedure was revised to 8.1-22 revised to summarize the process for slant-shot include measurements for shielding efficacy for gamma scan testing beyond the payload cavities axial grid locations below and above the payload for the SC-30G2, SC-30G3, and SC-55G2 cavity as described in the Attachment A Response containers. No. 4.

February 2022 B-3

ATTACHMENT B - Summary of Revisions SC-30G2 Shielded Container SAR Drawing, 163-010, Revision 1 Sheet Zone Change Description Justification General Revised header to update revision number. Administrative change. No impact to safety basis.

1 B-2 Revised Flag Note 16 as follows: As described in Attachment A, Response No. 1:

Fit-up of shells to base and flange to ensure a Table 5.4-16 in Section 5.4.5 of the TRUPACT-II minimum lead cavity width of 1.40 in. at shell Safety Analysis Report reports a maximum 0.8%

ends. Form control over the length of the shells increase for the NCT 2-meter dose rate for axial shall be maintained and lead pour process gaps of 1/2 inch at both ends of the sidewall lead controls shall be employed to ensure that 1.31 in. column. The activity limit administrative margin of minimum lead thickness has been achieved defined in Section 5.5.10 is increased by 1% (from throughout the length of the payload cavity. Axial 10% to 11%) to account for the maximum lead gaps at the lower and/or upper end of the gap in the lead annulus.

sidewall lead column shall not exceed 1/2 in.

Process controls shall be verified through The SC-30G2 SAR drawing has been revised to statistical sampling and application of gamma address the potential gaps discussed in scans or other nondestructive test methods. Section 5.4.5 of the TRUPACT-II SAR.

2 B-7 Added the term Payload Cavity to Section C-C The term Payload Cavity has been added to the drawing to clarify the reference included in the revision of Flag Note 16. No impact to safety basis.

5 C-4 Added min to Inner Ring thickness Design clarification change. No impact to safety basis.

February 2022 B-4

ATTACHMENT B - Summary of Revisions SC-30G3 Shielded Container SAR Drawing, 163-011, Revision 1 Sheet Zone Change Description Justification General Revised header to update revision number. Administrative change. No impact to safety basis.

1 B-2 Revised Flag Note 16 as follows: As described in Attachment A, Response No. 1:

Fit-up of shells to base and flange to ensure a Table 5.4-16 in Section 5.4.5 of the TRUPACT-II minimum lead cavity width of 2.75 in. at shell Safety Analysis Report reports a maximum 0.8%

ends. Form control over the length of the shells increase for the NCT 2-meter dose rate for axial shall be maintained and lead pour process gaps of 1/2 inch at both ends of the sidewall lead controls shall be employed to ensure that 2.57 in. column. The activity limit administrative margin of minimum lead thickness has been achieved defined in Section 5.5.10 is increased by 1% (from throughout the length of the payload cavity. Axial 10% to 11%) to account for the maximum lead gaps at the lower and/or upper end of the gap in the lead annulus.

sidewall lead column shall not exceed 1/2 in. Process controls shall be verified through The SC-30G3 SAR drawing has been revised to statistical sampling and application of gamma address the potential gaps discussed in scans or other nondestructive test methods. Section 5.4.5 of the TRUPACT-II SAR.

2 B-7 Added the term Payload Cavity to Section B-B The term Payload Cavity has been added to the drawing to clarify the reference included in the revision of Flag Note 16. No impact to safety basis.

February 2022 B-5

ATTACHMENT B - Summary of Revisions SC-55G2 Shielded Container SAR Drawing, 163-013, Revision 1 Sheet Zone Change Description Justification General Revised header to update revision number. Administrative change. No impact to safety basis.

1 C-2 Revised Flag Note 12 as follows: As described in Attachment A, Response No. 1:

Fit-up of shells to base and flange to ensure a Table 5.4-16 in Section 5.4.5 of the TRUPACT-II minimum lead cavity width of 1.98 in. at shell SAR reports a maximum 0.8% increase for the ends. Form control over the length of the shells NCT 2-meter dose rate for axial gaps of 1/2 inch at shall be maintained and lead pour process both ends of the sidewall lead column. The controls shall be employed to ensure that 1.86 in. activity limit administrative margin defined in of minimum lead thickness has been achieved Section 5.5.10 is increased by 1% (from 10% to throughout the length of the payload cavity. Axial 11%) to account for the maximum lead gap in the gaps at the lower and/or upper end of the lead annulus.

sidewall lead column shall not exceed 1/2 in.

Process controls shall be verified through The SC-55G2 SAR drawing has been revised to statistical sampling and application of gamma address the potential gaps discussed in scans or other nondestructive test methods. Section 5.4.5 of the TRUPACT-II SAR.

2 B-7 Added the term Payload Cavity to Section B-B The term Payload Cavity has been added to the drawing to clarify the reference included in the revision of Flag Note 12. No impact to safety basis.

February 2022 B-6

ATTACHMENT B - Summary of Revisions CH-TRAMPAC, Revision 6, February 2022 Section Page Change Description Justification General Revised header for date. Administrative change. No impact to safety basis.

February 2022 B-7

ATTACHMENT B - Summary of Revisions CH-TRU Payload Appendices, Revision 5, February 2022 Section Page Change Description Justification General Revised header for date. Administrative change. No impact to safety basis.

February 2022 B-8