Text

Letter to Branch Chief/Sflb Renewal Application for the Model 360 Series Transport Package Designs - USA/9371/B(U)-96
	ML18149A025
Person / Time
Site:	07109371
Issue date:	04/25/2018
From:	Podolak L; QSA Global
To:	; Spent Fuel Licensing Branch
	Garcia-Santos N
References
	Download: ML18149A025 (84)
	v • d • e

25 April 2018 Branch Chief Spent Fuel Licensing Branch U.S. Nuclear Regulatory Commission Office ofNuclear Material Safety and Safeguards Mailstop: 3WFN-14A44 11555 Rockville Pike One White Flint Rockville, MD 20852 QSA Global, Inc.

40 North Avenue Burlington, MA 01803 Telephone: (781) 272-2000 Toll Free: (800) 815-1383 Facsimile: (781) 359-9191 RE:

Renewal Application for the Model 360 Series Transport Package Designs - USN9371/B(U)-96

Dear Sir or Madam:

QSA Global, Inc. requests renewal of the certificate referenced above for the Model 360 Series Type B(U) containers. The current certificate expires on 31 January 2019. This renewal submission makes minor modifications to the Safety Analysis Report (SAR) related to administrative/corrective changes as applicable. These changes are documented in a Table describing the SAR changes and they have no significant impact on the package performance or continued compliance for Type B transport.

This submission is being provided as a full revision to the SAR at Revision 5. This submission contains proprietary documentation for which we request withholding from public disclosure under the provisions of 10 CFR

§2.390(a)(4). The attachments to this letter include Attachment 1 which is the affidavit required for proprietary documentation under §2.390; Attachment 2 which includes all submission documents covered by the proprietary request for withholding under the affidavit in Attachment 1; and Attachment 3 which includes all submission documents that can be released for public disclosure related to these packages. Should you have any additional questions or wish to discuss this submission after receipt please feel free to contact me.

Sincerely,

~O~

Lori Podolak Senior RNQA Specialist Regulatory Affairs/Quality Assurance Ph: (781) 505-8241 Fax: (781) 359-9191 Email: Lori.Podolak@qsa-global.com

Enclosures:

Affidavit Pursuant to §2.390 Proprietary documents Non-Proprietary documents S.~

Engineering Approval www.qsa-global.com 23,19/A, 2{)/(3 Date z~ Af'.e 2o18 Date

cc: Document Control Desk U.S. Nuclear Regulatory Commission 11555 Rockville Pike One White Flint Rockville, MD 20852 1,v,v w. q s a -

g I o b a Page2

.com Affidavit Pursuant to 10 CFR §2.390

AFFIDAVIT Pursuant to 10 CFR §2.390 I, Mike Fuller, Director Regulatory Affairs/Quality Assurance of QSA Global, Inc. hereby affirm and state:

1. I have been specifically delegated the function of reviewing the information sought to be withheld and am authorized to apply for its withholding on behalf of QSA Global, Inc.

2. QSA Global, Inc. is providing NRC with a detailed drawing (R36000 Rev G) and technical details, specifications and product related information as parts of the SAR Revision 5 for the Model 360 Series transport packages. These documents contain proprietary commercial information.

3. The information sought to be withheld pursuant to the provisions of 10 CFR §2.390(a)(4) are marked as follows in Attachment 2 of our application letter "Proprietary information submitted under 10 CFR §2.390 to be witltlteldfrom public disclosure under 10 CFR §2.390."

4. These documents should be held in confidence by the NRC per 10 CFR §2.390(a)(4) based on the following justifications:

a. This information is owned and been held in confidence by QSA Global, Inc.

b. This information is of a type that QSA Global, Inc. has determined should be held in confidence since its release for public disclosure could result in a loss of an existing or potential competitive advantage as follows:

1. The information reveals the distinguishing aspects of the design and the prevention of its use by QSA Global, Inc. competitors gives QSA Global, Inc. a competitive economic advantage.

11. The information, if used by a competitor, is likely to reduce the competitor's expenditure of resources or improve their advantage in design, quality and manufacture of a similar product.

c.

This information is being transmitted to the NRC voluntarily and in confidence for use in evaluation and approval of these package designs for Type B(U) transport certification.

d. This information is not available in public sources.

e.

Public disclosure of this information is likely to cause substantial harm to the competitive position of QSA Global, Inc. because of the reasons outlined below:

1. Similar products are manufactured and sold by competitors of QSA Global, Inc.

11. The development of this information by QSA Global, Inc., including test/evaluation documentation supporting these package designs, is the result of significant expenditure of staff effort and a considerable amount of money. It is our belief that a competitor would have to undertake similar effort and expense to generate equivalent information iii. In order to generate such information, a competitor would also require considerable time ( e.g.,

in excess of 1 year).

iv. If a competitor used this information and did not have to undertake the work required to generate this information, they are likely to have lower overall costs and so are likely to have an unfair economic advantage over QSA Global, Inc. in offering a similar product to the market.

5. QSA Global has spent considerable commercial and technical resources to design and build this innovative family of source changers that is unique in its ability to store and transport a wide range of industrial radiography sources that are used worldwide. Access to the technical information for this unique design would give a competitor an unfair advantage in expanding their domestic and international market without having to perform their own research and development of the market needs and the ideal configuration of the transport package to meet a wide variety of customer needs.

Accordingly, QSA Global, Inc. requests that the designated information be withheld from public disclosure pursuant to 10 CFR §2.390.

Executed on Z-:J /9/7/?.J:L 2.0lfd

~;d,~

Mike Fuller, Director Regulatory Affairs/Quality Assurance Subscribed and sworn to (or affirmed) before me on thi&:~J day of 4J2r, * /

, 2018 by Mike Fuller, proved to me on the basis of satisfactory evidence to be the person who appeared before me.

Signature vf&.£:ss~j {J)~

Seal My Commission Expires 2__ day of '--fvk1

, 20:J.D.

MELISSA J. WOLFE NOTARY PUBl.JC My commission expires July 3, 2 020 i

\\

Non-Proprietary Documents List of Affected Pages Revision Description for the Model 360 SAR from Rev 4 to Rev 5 SAR Revision 5:

Title page and contents pages pages 1-1 through 1-4 pages 1-11 through 1-16 page 1-18 including Drawing R360-USER Revision C page 2-28 pages 2-45 through 2-48 pages 2-51 & 2-52 page 3-1 pages 3-4 & 3-5 pages 4-1 & 4-2 pages 5-1 through 5-12 page 6-1 pages 7-1 through 7-6 pages 8-1 through 8-3 page 9-1

Revision 0, May 2013 Revision 1, July 2013 Revision 2, October 2013 Revision 3, November 2013 Revision 4, January 2015 Revision 5, April 2018 Safety Analysis Report for the Models 360 Series Transport Packages List of Affected Pages Original Submission.

Revised drawings R36000 and R360-User, reassessed pages submitted as proprietary under 10 CFR &2.390 Revised pages 2-1, 2-2, 2-32 and 5-10 thru 5-12 in response to NRC RAI letter dated 10/09/2013.

Revised pages 2-2 & 2-3 to clarify design criteria requirements under HAC testing.

Revised page 3-8 to correct revision references for 3.6.1 & 3.6.2 Revision to update regulatory references, make minor grammatical/typographical corrections, update details on source information and updates special form certificate revisions in Section 2.12.

Revision Description for the Model 360 SAR from Revision 4 to Revision 5 April 2018 Page 1 of2 Revision 5 to the 360 SAR includes minor modifications related to administrative/corrective changes as applicable. These changes are listed under the SAR Section in Revision 5 where the change occurs. These changes are made either for clarification/accuracy or detail changes pending NRC approval prior to implementation. As such they will have no impact on packages in transport until approved under an amendment Certificate of Compliance.

Section Reference Description Generic Format Correction of minor typographical errors within the SAR text.

Changes Updated reference to ISO 2919 from the 2008 version of this standard to the 2012 version. No significant changes occurred between the test criteria covered by these two version of the same performance standard.

1.1 & 2.1.2 Updated reference to IAEA from the 1996 edition to reflect the 2009 edition adopted under the current USA regulations.

Updated reference standard to the applicable Canadian Nuclear Safety Commission PTNS regulations SOR/2015-145.

1.2 Corrected the month reference for NUREG-1886 from "May" to "March" to accurately reflect the publication date for the NUREG document.

1.3.1 & 1.3.2 Removed the revision reference to the identifiers for these sections. Submitted revisions are identified on the drawings included and need not be duplicated in the section identifier.

2.1.4&9.l Section revised to reflect QSA Global acquisition of the assets and design authority for NTP Radioisotopes (Europe) SA - Belgium source chain assemblies. Previously the use of these designs by QSA Global was limited to source loading. However, after purchase of the design authority for these assemblies, QSA Global, Inc. now performs repairs/service of existing source chain assemblies, as well as new manufacture of these assemblies under our NRC and ISO approved Quality Assurance programs.

2.6.7 Added notation to identify criteria in IAEA TS-R-1 (2009 Edition) is equivalent to the originally evaluated 1996 edition of this standard.

2.12 Updated previous USDOT Special form certificate revisions and added two additional special form certifications to this section.

3.4.1.1 Corrected typographical error in reference to revision for Technical Report 225. This should be Revision 1 but Revision 4 of the SAR had specified Revision 2 in error.

3.4.1.2 Corrected typographical error in reference to revision for Technical Report 224. This should be Revision 1 but Revision 4 of the SAR had specified Revision 2 in error. Also corrected reference to Technical Report 225 which should have been Technical Report 224 in the 2"d paragraph of this section.

5.1.1 Corrected the grammar in the first sentence.

5.3.1 Corrected section reference for Technical Report 228 from 2.12 to 5.5. Also changed "obtain" to "obtained" in 2"d paragraph for grammatical accuracy. Added missing reference to section 5.5.3 for Microshield Version 9.06 calculations.

5.1.2, 5.3.1 & 5.3.2 Added reference to Microshield Version 9.06 for completeness.

5.4.1 Added reference to Microshield Version 9.06 calculations in Section 5.5.3 for completeness.

7.1.2.1.c. 5 Added "dust cap" to clarify the cover referred to in this section applies to the lock mechanism cover as identified on the drawings in Section 1.3. Change made for clarify.

7.4.2 & 7.5.1 Updated the DOT Emergency Response Handbook from the 2004 revision to the 2016 revision.

Safety Analysis Report QSA Global, Inc.

Models 360 Series Type B(U) - 96 Transport Package April 2018 Revision 5

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts Contents April 2018 - Revision 5 Page i SECTION 1-GENERAL INFORMATION......................................................................................................... 1-1 l. l INTRODUCTION............................................................................................................................................ 1-I

1. 2 PACKAGE D ESCRlPTlON............................................................................................................................... 1-1 1.2.1 Packaging.......................................................................................................................................... 1-3 1.2.1.1 Container Assembly....................................................................................................................................... 1-5 1.2.1.2 Cover Assembly.............................................................................................................................................. 1-6 1.2.1.3 ShieldAssembly.............................................................................................................................................. 1-7 1.2.1.4 Source Securing Mechanism........................................................................................................................ 1-10 1.2.1.5 Source Assemblies........................................................................................................................................ 1-12 1.2.2 Contents........................................................................................................................................... 1-14 1.2.3 Special Requirements/or Plutonium................................................................................................ 1-15 1.2.4 Operational Features....................................................................................................................... 1-15 1.3 APPENDIX.................................................................................................................................................. 1-15 1.3.1 Drawing R36000.............................................................................................................................. 1-17 1.3.2 Drawing R360-USER....................................................................................................................... 1-18 SECTION 2 - STRUCTURAL EVALUATION.................................................................................................... 2-1

2. I D ESCRlPT!ON OF STRUCTURAL D ESIGN........................................................................................................ 2-1 2.1.1 Discussion.......................................................................................................................................... 2-l 2.1.2 Design Criteria.................................................................................................................................. 2-1 2.1.3 Weight and Centers of Gravity.......................................................................................................... 2-3 2.1.4 Identification of Codes and Standards for Package Design.............................................................. 2-3 2.2 MATERIALS.................................................................................................................................................. 2-3 2.2. 1 Material Properties and Specifications............................................................................................. 2-3 2.2.2 Chemical, Galvanic or Other Reactions............................................................................................ 2-4

2. 2. 3 Effects of Radiation on Materials...................................................................................................... 2-5 2.3 FABRICATION AND EXAMINATION............................................................................................................... 2-5 2.3.1 Fabrication........................................................................................................................................ 2-5 2.3.2 Examination....................................................................................................................................... 2-5 2.4 GENERAL REQU IREMENTS FOR ALL PACKAGES........................................................................................... 2-5 2.4. I Minimum Package Size...................................................................................................................... 2-5 2.4.2 Tamper-Indicating Feature................................................................................................................ 2-6 2.4.3 Positive Closure................................................................................................................................. 2-6 2.5 LIFTING AND T IEDOWN STANDARDS FOR ALL PACKAGES........................................................................... 2-6

2. 5. 1 Lifting Devices................................................................................................................................... 2-6

2. 5.2 Tie-Down Devices.............................................................................................................................. 2-6 2.6 ORMAL CONDITIONS OF TRANSPORT......................................................................................................... 2-7

2. 6. 1 Heat................................................................................................................................................... 2-7

2. 6.1. 1 Summary of Pressures and Temperatures...................................................................................................... 2-7

2. 6. 1.2 Differential Thermal Expansion..................................................................................................................... 2-7 2.6.1.3 Stress Calculations......................................................................................................................................... 2-8

2. 6. 1.4 Comparison with A 1/owable Stresses............................................................................................................. 2-8 2.6.2 Cold.................................................................................................................................................. 2-8 2.6.3 Reduced External Pressure................................................................................................................ 2-8 2.6.4 Increased External Pressure.............................................................................................................. 2-9 2.6.5 Vibration............................................................................................................................................ 2-9 2.6.6 Water Spray...................................................................................................................................... 2-9

2. 6. 7 Free Drop.......................................................................................................................................... 2-9

2. 6. 7. 1 Bottom Surface Orientation.......................................................................................................................... 2-13 2.6.7.2 Shallow Angle/Slap Down Drop Orientation - Side Hit.............................................................................. 2-14

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts Apri l 2018 - Revision 5 P age ii 2.6. 7.3 Top Surface Drop Orientation................................................................................................................... 2-15 2.6. 7.4 Top Corner Drop Orientation...................................................................................................................... 2-17 2.6. 7.5 Normal Transport Drop Test Results Summary Evaluation......................................................................... 2-18

2. 6.8 Corner Drop.................................................................................................................................... 2-20 2.6.9 Compression or Stacking................................................................................................................. 2-20

2. 6. 10 Penetration.................................................................................................................................. 2-22 2. 7 HYPOTHETICAL ACCIDENT CONDITIONS.................................................................................................... 2-23

2. 7.1 Free Drop........................................................................................................................................ 2-23

2. 7. 1. l End Drop...................................................................................................................................................... 2-23

2. 7.1.2 Side Drop..................................................................................................................................................... 2-25

2. 7.1.3 Corner Drop................................................................................................................................................. 2-26

2. 7. 1.4 Oblique Drops.............................................................................................................................................. 2-27 2.7. 1.5 SummaryofResults...................................................................................................................................... 2-28

2. 7.2 Crush............................................................................................................................................... 2-29

2. 7. 3 Puncture........................................................................................................................................... 2-29

2. 7. 3. l End Drop Puncture Test............................................................................................................................... 2-29

2. 7.3.2 Corner Drop Puncture Test.......................................................................................................................... 2-31

2. 7.3.3 Oblique Drop Puncture Test........................................................................................................................ 2-32

2. 7. 3.4 Summary of Results...................................................................................................................................... 2-33

2. 7.4 Thermal............................................................................................................................................ 2-33

2. 7.4. l Summary of Pressures and Temperatures.................................................................................................... 2-33

2. 7. 4.2 Differential Thermal Expansion................................................................................................................... 2-33

2. 7.4.3 Stress Calculations....................................................................................................................................... 2-34

2. 7.4.4 Comparison of Allowable Stresses............................................................................................................... 2-34

2. 7.4.5 Additional Thermal Analysis........................................................................................................................ 2-34

2. 7.5 Immersion - Fissile Material......................................................................................................... 2-36

2. 7.6 Immersion - All Packages................................................................................................................ 2-36

2. 7. 7 Deep Water Immersion Test (for Type B Packages Containing More than 105 A2)........................ 2-36

2. 7. 8 Summary of Damage........................................................................................................................ 2-36 2.8 ACCIDENT CONDITIONS FOR AIR TRANSPORT OF P LUTONIUM OR PACKAGES WITH LARGE QUANTITIES OF RADIOACTIVITY................................................................................................................................................... 2-37 2.9 ACCIDENT CONDITIONS FOR FISSILE MATERIAL PACKAGES FOR AIR TRANSPORT.................................... 2-37 2.10 SPECLAL FORM...................................................................................................................................... 2-37 2.11 FUELRODS............................................................................................................................................ 2-37 2.12 APPEND[)(.............................................................................................................................................. 2-37 2.12.1 Test Plan 199 Revision 2 dated 3 May 2012............................................................................... 2-39

2. 12.2 Test Plan 199 Addendum Revision O (minus appendix) dated 15 June 2012.............................. 2-40

2. 12.3 Test Plan 199 Report #1 (minus Append C & D) dated 24 May 2013........................................ 2-41 2.12.4 Test Plan 199 Report #2 (minus Append C & D) dated 24 May 2013........................................ 2-42

2. 12. 5 Technical Report 226 Model 360 Series Transport Package lifting Analysis

2. 12.6 2.12.7 2.12.8 2.12.9 2.12.10 2.12. 11 2.12. 12 2.12.13

2. 12.14 dated 18 Dec 2012...................................................................................................................... 2-43 Technical Report 227 Model 360 Series Tie-Down Analysis Rev 1 dated 21 May 2013............ 2-44 USDOT Special Form Certificate USA/0335/S-96 Rev 12.......................................................... 2-45 USDOT Special Form Certificate USA/0392/S-96 Rev 12.......................................................... 2-46 USDOT Special Form Certificate USA/0502/S-96 Rev 1 /.......................................................... 2-47 USDOT Special Form Certificate USA/0790/S-96 Rev 1............................................................ 2-48 Test Plan 79 and Report Vultafoam Compression Test (minus Attachment B) dated 22 Oct 1998................................................................................................................................. 2-49 Technical Report No. 223 Profile Errors Induced by Changed Calibration Factors dated 16April 2013............................................................................................................................... 2-50 USDOT Special Form Certificate USA/0797/S-96 Rev 0............................................................ 2-51 USDOT Special Form Certificate USA/0805/S-96 Rev 0............................................................ 2-52 SECTION 3 - THERMAL EVALUATION.......................................................................................................... 3-1 3.1 D ESCRIPTION OF THERMAL D ESIGN............................................................................................................. 3-1

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts April 2018 - Revision 5 Page iii

3. 1.1 Design Features................................................................................................................................. 3-1

3. 1. 2 Decay Heat of Contents..................................................................................................................... 3-1 3.1.3 Summary Tables of Temperatures..................................................................................................... 3-2 3.1.4 Summary Tables of Maximum Pressures........................................................................................... 3-2 3.2 MATERlAL PROPERTIES AND COMPONENT SPEC!FICATIONS........................................................................ 3-2 3.2. 1 Material Properties............................................................................................................................ 3-2 3.2.2 Component Specifications.................................................................................................................. 3-4 3.3 GENERAL CONS!DERA TIONS........................................................................................................................ 3-4 3.3.1 Evaluation by Analysis....................................................................................................................... 3-4 3.3.2 Evaluation by Test............................................................................................................................. 3-4 3.4 THERMAL EVALUATION UNDER NORMAL CONDITIONS OF TRANSPORT....................................................... 3-4 3.4. 1 Heat and Cold.................................................................................................................................... 3-4 3.4.2 Temperatures Resulting in Maximum Thermal Stresses.................................................................... 3-5 3.4.3 Maximum Normal Operating Pressure.............................................................................................. 3-6 3.5 THERMAL EVALUATION UNDER HYPOTHETICAL ACCIDENT CONDITIONS.................................................... 3-6 3.5.1 Initial Conditions............................................................................................................................... 3-6 3.5.2 Fire Test Conditions.......................................................................................................................... 3-6 3.5.3 Maximum Temperatures and Pressure.............................................................................................. 3-7 3.5.4 Temperatures Resulting in Maximum Thermal Stresses.................................................................... 3-7 3.5.5 Fuel/Cladding Temperatures for Spent uclear Fuel....................................................................... 3-8 3.5.6 Accident Conditions for Fissile Material Packages for Air Transport.............................................. 3-8 3.6 APPENDIX.................................................................................................................................................... 3-8

3. 6. 1 Technical Report 224 Rev I Model 360 General Standards Thermal Analysis dated IO May 2013. 3-9 3.6.2 Technical Report 225 Rev I Model 360 NCT lnsolation Thermal Analysis dated JO May 2013..... 3-10 SECTION 4-CONTAINMENT............................................................................................................................ 4-1 4.1 D ESCRIPTION OF THE CONTAINMENT SYSTEM............................................................................................. 4-1 4.1. 1 Special Requirements for Damaged Spent Nuclear Fuel................................................................... 4-1 4.2 CONTAINM ENT UNDER NORMAL CONDITIONS OF TRANSPORT.................................................................... 4-1 4.3 CONTAINMENT UNDER HYPOTHETICAL ACC[DENT CONDITIONS................................................................. 4-1 4.4 LEAK.AGE RA TE TESTS FOR TYPE B PACKAGES........................................................................................... 4-1 4.6 APPENDIX.................................................................................................................................................... 4-2 SECTION 5-SHIELDING EVALUATION........................................................................................................ 5-1 5.1 D ESCRJPTION OF SHIELDING D ESIGN........................................................................................................... 5-l 5.1.1 Design Features................................................................................................................................. 5-1

5. 1. 2 Summary Table of Maximum Radiation l evels................................................................................. 5-1 5.2 SOURCE SPECIFICATION............................................................................................................................... 5-9 5.2.1 Gamma Source................................................................................................................................... 5-9 5.2.2 Neutron Source.................................................................................................................................. 5-9 5.3 SHIELDING MODEL....................................................................................................................................... 5-9 5.3. 1 Configuration of Source and Shielding.............................................................................................. 5-9 5.3.2 Material Properties.......................................................................................................................... 5-10 5.4 SHIELDING EVALUATION........................................................................................................................... 5-10

5. 4. 1 Methods........................................................................................................................................... 5-10 5.4.2 Input and Output Data..................................................................................................................... 5-11 5.4.3 Flux-to-Dose-Rate Conversion........................................................................................................ 5-12

5. 4. 4

&ternal Radiation Levels................................................................................................................ 5-12 5.5 APPENDIX.................................................................................................................................................. 5-12 5.5.1 Technical Report 228 Model 360 Shield Evaluation with Se75 & Yb/69 Revision O dated 1/9/13. 5-13 5.5.2 Technical Report 240 Model 360 Shield Capacity Evaluations dated 5/21/13 (Minus Append B-G)........................................................................................................................ 5-14 5.5.3 Additional Microshield Calculations for the 360-IOW Package to Determine Equivalent Shielding

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts Effectiveness for Se-7 5 and Yb-169...

April 2018 - Revision 5 Page iv

- - - - ************************************************************* ** ***************** 5-15 SECTION 6 - CRITICALITY EVALUATION.................................................................................................... 6-1 SECTION 7 - PACKAGE OPERA TIO NS........................................................................................................... 7-1 7.1 PACKAGE LOADING..................................................................................................................................... 7-1 7.1.1 PREPARATION FOR LOADING................................................................................................................... 7-1 7.1.1.1 Authorized Package Contents........................................................................................................................ 7-1 7.1.1.2 Packaging Maintenance and inspection Prior to Loading............................................................................. 7-2

7. 1.2 Loading of Contents........................................................................................................................... 7-2 7.1.2.1 General Pre-transportation Requirements..................................................................................................... 7-2 7.2 PACKAGE UNLOADING................................................................................................................................. 7-4 7.2. 1 Receipt of Package from Carrier....................................................................................................... 7-4 7.2. 2 Removal of Contents.......................................................................................................................... 7-5 7.3 PREPARATION OF EMPTY PACKAGE FOR TRANSPORT.................................................................................. 7-5 7.4 OTHER OPERATIONS.................................................................................................................................... 7-5

7. 4.1 Package Transportation By Consignor.............................................................................................. 7-5

7. 4. 2 Emergency Response......................................................................................................................... 7-6 7.5 APPENDIX.................................................................................................................................................... 7-6 SECTION 8-ACCEPTANCE TESTS AND MAINTENANCE PROGRAM................................................... 8-1 8.1 ACCEPTANCE TEST...................................................................................................................................... 8-1 8.1. 1 Visual Inspections and Measurements.............................................................................................. 8-1

8. 1.2 Weld Examinations............................................................................................................................ 8-1

8. 1. 3 Structural and Pressure Tests............................................................................................................ 8-1 8.1.4 Leakage Tests..................................................................................................................................... 8-2 8.1.5 Component and Material Tests.......................................................................................................... 8-2 8.1.6 Shielding Tests................................................................................................................................... 8-2

8. 1. 7 Thermal Tests..................................................................................................................................... 8-2 8.1.8 Miscellaneous Tests........................................................................................................................... 8-3 8.2 MAINTENANCE PROGRAM............................................................................................................................ 8-3 8.2. 1 Structural and Pressure Tests............................................................................................................ 8-3 8.2.2 Leakage Tests..................................................................................................................................... 8-3 8.2.3 Component and Material Tests.......................................................................................................... 8-3 8.2.4 Thermal Tests.................................................................................................................................... 8-3 8.2.5 Miscellaneous Tests........................................................................................................................... 8-3 8.3 APPENDIX.................................................................................................................................................... 8-3 SECTION 9 - QUALITY ASSURANCE.............................................................................................................. 9-1 9.1 U.S. QUALITY ASSURANCE PROGRAM REQUIREMENTS............................................................................... 9-1 9.2 CANADA QUALITY A SSURANCE PROGRAM REQUIREMENTS........................................................................ 9-1 9.3 APPENDIX.................................................................................................................................................... 9-1

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts List of Tables April 2018 - Revision 5 Page v TABLE 1.2A: MODEL 360 SERIES PACKAGE INFORMATION.............................................................................................. 1-2 TABLE 1.28: ISOTOPE INFORMATION PERMITTED IN MODEL 360 SERIES PACKAGES....................................................... 1-l 5 TABLE 2.2A: MECHANICAL PROPERTlES OF PRINCIPAL TRANSPORT PACKAGE MATERIALS............................................ 2-4 TABLE 2.6A: RADIONUCLIDE D ECAY ENERGY................................................................................................................. 2-7 TABLE 2.68:

SUMMARY

T EMPERATURES NORMAL TRANSPORT...................................................................................... 2-7 TABLE 2.6C. MODEL 360 TRANSPORT PACKAGE CONFIGURATIONS................................................................................. 2-10 TABLE 2.7A:

SUMMARY

TABLE OF TEMPERATURES........................................................................................................ 2-33 TABLE 2.78:

SUMMARY

TABLE OF MAxlMUM PRESSURES.............................................................................................. 2-33 TABLE 3. IA:

SUMMARY

TABLE OF T EMPERATURES......................................................................................................... 3-2 TABLE 3. 18:

SUMMARY

TABLE OF MAXIMUM PRESSURES............................................................................................... 3-2 TABLE 3.2A: MATERIAL OF COMPONENTS IMPORTANT TO SAFETY................................................................................ 3-2 TABLE 3.28: THERMAL PROPERTIES OF PRINCIPAL TRANSPORT PACKAGE MATERIALS................................................... 3-3 TABLE 5. l A: MODEL 360-1 OW lR-192

SUMMARY

TABLE OF EXTERNAL RADIATION LEVEL (NON-EXCLUSIVE USE) 1.. 5-1 TABLE 5.1 B: MODEL 360-1 OW lR-192

SUMMARY

TABLE OF EXTERNAL RADIATION LEVELS (EXCLUSIVE USE) 1*4......... 5-2 TABLE 5. IC: MODEL 360-2 lR-l 92

SUMMARY

TABLE OF EXTERNAL RADIATION LEVELS (NON-EXCLUSIVE USE) 1........ 5-2 TABLE 5.1 D: MODEL 360-2 lR-192

SUMMARY

TABLE OF EXTERNAL RADIATION L EVELS (EX LUSIVE USE) 1*4............... 5-3 TABLE 5.1 E: MODEL 360-4 IR-192

SUMMARY

TABLE OF EXTERNAL RADIATION L EVELS (NON-EXCLUSIVE USE) 1........ 5-3 TABLE 5.1 F: MODEL 360-4 lR-l 92

SUMMARY

TABLE OF EXTERNAL RADIATION L EVELS (EXCLUSIVE USE) 1*4............... 5-4 TABLE 5.1 G: MODEL 360-4 W lR-192

SUMMARY

TABLE OF EXTERNAL RADIA Tl ON LEVEL (NON-EXCLUSIVE USE) 1.... 5-4 TABLE 5. lH: MODEL 360-4 W lR-192

SUMMARY

TABLE OF EXTERNAL RA DIA T!ON LEVELS (EXCLUSIVE USE) 1*4........... 5-5 TABLE 5.11: MODEL 360- 10 IR-192

SUMMARY

TABLE OF EXTERNAL RADIA T!ON LEVELS (NON-EXCLUSIVE USE) 1....... 5-5 TABLE 5. lJ: MODEL 360-10 TR-192

SUMMARY

TABLE OF EXTERNAL RADIATION LEVELS (EXCLUSIVE USE) 1*4.............. 5-6 TABLE 5.1 K: MODEL 360-2 SE-75

SUMMARY

TABLE OF EXTERNAL RADIATION L EVELS (NON-EXCLUSIVE USE) 1......... 5-6 TABLE 5. lL: MODEL 360-4 SE-75

SUMMARY

TABLE OF EXTERNAL RADIATION LEVELS (NON-EXCLUSIVE USE) 1......... 5-6 TABLE 5.lM: MODEL360-4W SE-75

SUMMARY

TABLE OF EXTERNAL RADIATION LEVELS (NON-EXCLUSIVE USE) 1..... 5-7 TABLE 5.1 N: MODEL 360- 10 SE-75

SUMMARY

TABLE OF EXTERNAL RADIATION LEVELS (NON-EXCLUSIVE USE) 1....... 5-7 TABLE 5.10: MODEL 360-1 OW SE-75

SUMMARY

TABLE OF EXTERNAL RADIATION LEVELS (NON-EXCLUSIVE USE) 1... 5-7 TABLE 5. lP: MODEL 360-2 YB-169

SUMMARY

TABLE OF EXTERNAL RADIA T!ON LEVELS (NON-EXCLUSIVE USE) 1....... 5-8 TABLE 5.1 Q: MODEL 360-4 YB-169

SUMMARY

TABLE OF EXTERNAL RADIATION LEVELS (NON-EXCLUSIVE USE) 1...... 5-8 TABLE 5. lR: MODEL 360-4 W YB-169

SUMMARY

TABLE OF EXTERNAL RADIA T!ON LEVELS (NON-EXCLUSIVE USE) 1... 5-8 TABLE 5. l S: MODEL 360-10 YB-169

SUMMARY

TABLE OF EXTERNAL RADIATION LEVELS (NON-EXCLUSIVE USE) 1..... 5-9 TABLE 5.1 T: MODEL 360-1 OW YB-169

SUMMARY

TABLE OF EXTERNAL RADIATION LEVELS (NON-EXCLUSIVE USE) 1* 5-9 TABLE 7. lA: MODEL 360 SERlES PACKAGE INFORMATION.............................................................................................. 7-1

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts List of Figures April 2018 - Revision 5 Page vi FIGURE 1.2A: EXTERNAL VIEW OF MODELS 360 SERIES TRANSPORT PACKAGES..................................................... 1-l FIGURE 1.28: EXPLODED VLEW OF MODELS 360-lOW (TUNGSTEN SHIELDED)TRANSPORT PACKAGE.................... 1-3 FIGURE 1.2C: EXPLODED VIEW OF MODELS 360-10 (TUNGSTEN/DEPLETED URANIUM SHIELDED)TRANSPORT PACKAGE............................................................................................................................................................... 1-4 FIGURE 1.2D: MODELS 360 SERIES CONTAINER ASSEMBLY........................................................................................ 1-5 FIGURE 1.2E: MODELS 360 SERIES TRANSPORT PACKAGES-COVER ASSEMBLY CUTAWAY VIEW......................... 1-6 FIGURE 1.2F-CUTAWAY VIEW OF THE MODEL360-2 SHIELD ASSEMBLY................................................................. 1-8 FIGURE 1.2G-CUTAWAY VIEW OF THE MODEL360-4 SHIELD ASSEMBLY................................................................ 1-8 FIGURE 1.2H - CUTAWAY VIEW OF MODEL 360-4W SHIELD ASSEMBLY.................................................................... 1-9 FIGURE 1.2I-CUTAWAY VIEW OF THE MODEL360-10 SHIELD ASSEMBLY................................................................ 1-9 FIGURE 1.2J-CUTAWAY VIEW OF THE MODEL 360-lOW SHIELD ASSEMBLY........................................................... 1-10 FIGURE 1.2K-TYPICAL SOURCE SECURING MECHANISM (10 SOURCE CONFIGURATION SHOWN)........................... 1-11 FIGURE 1.2L: LOCK ASSEMBLY COMPO NE TS............................................................................................................. 1-11 FIGURE 1.2M: SOURCE LOADING POSITIO s-STEPPED CE TER SHIELD VERSIO s................................................ 1-12 FIGURE 1.2N: SOURCE LOADING POSITIONS-MODEL 360-10 & 360-lOW CENTER SHlELDS.................................. 1-13 FIGURE 1.3A SKETCH OF MODEL 360 SERIES PACKAGES IN THE TRANSPORT CO FIGURA TIO............................... 1-16 FIGURE 2.6A MAJOR SUB-ASSEMBLIES OF TYPICAL MODEL 360 SERIES PACKAGES................................................. 2-l l FIGURE 2.6B TUNGSTEN ONLY AND DUffUNGSTEN COMBINATION SHIELD UNIT COMPARISON.............................. 2-12 FIGURE 2.6C-1.2 M (4 FT) DROP 0RJE TATION TP199A............................................................................................ 2-13 FIGURE 2.6D -1.2 M ( 4 FT) DROP ORIENTATION TP199B............................................................................................ 2-14 FIGURE 2.6E - 1.2 M ( 4 FT) DROP ORIENT A TION TP199C............................................................................................ 2-15 FIGURE 2.6F-1.2 M (4 FT) DROP ORIENTATION TP199D............................................................................................ 2-17 FIGURE 2.6G - COVER SUPPORT POST DESIGN AND SHIELD PCN ADDITIONS.............................................................. 2-18 FIGURE 2.6H-EXPLODED VIEW SHIELD RETAINER DESIGN CHANGE........................................................................ 2-19 FIGURE 2.61-PARTIAL CUTAWAY SSM ASSEMBLY TUNGSTEN SHIELD DESIGN CHANGE........................................ 2-20 FIGURE 2.6J-COMPRESSION TEST IN PROGRESS FOR UNITS TP199A, TP199C & TP199D..................................... 2-21 FIGURE 2.7A-9 M (30 FT) DROP ORIENTATION TP199A............................................................................................. 2-24 FIGURE 2.7B - 9 M {30 FT) DROP 0RfENTATI0NTP199C............................................................................................. 2-25 FIGURE 2.7C-HORIZONTAL SIDE DROP ORIENTATION FOR THE MODEL 360 SERIES PACKAGE.............................. 2-26 FIGURE 2. 7D - 9 M (30 FT) DROP ORIENTATION TP199D............................................................................................. 2-27 FIGURE 2.7E-9 M (30 FT) DROP ORIENTATION TP199B............................................................................................. 2-28 FIGURE 2. 7F-RELATIVE SOURCE SHIELD STORAGE LOCATIONS (BOTTOM AND TOP PLACEMENT)........................ 2-30 FIGURE 5.lA. SAMPLE SURFACE CORRECTION FACTOR DISTANCE CRITERIA................................... 5-12

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts Section 1 - GENERAL INFORMATION 1.1 Introduction April 2018 - Revision 5 Page 1-1 All versions of the Models 360 Series are designed as transport packages and storage containers for Type B quantities of special form radioactive material. They conform to the Type B(U)-96 criteria for packaging in accordance 10 CFR 71, 49 CFR 173, the IAEA Regulations for the Safe Transport of Radioactive Material No. TS-R-1 (2009 Edition) and Canadian Nuclear Safety Commission (CNSC) PTNS Regulations SOR/2015-145. This submission is formatted in accordance with NUREG-1886 "Joint Canada - United States Guide for Approval of Type B(U) and Fissile Material Transportation Packages" dated March 2009.

1.2 Package Description These transport packages are a family of five package configurations that share a common structure, with some variations for capacity and shielding configuration. These packages are intended as Type B(U) transport containers and as radiography source changers. The Model 360 Series packages are comprised of the Models 360-2, 360-4, 360-4W, 360-10 and 360-lOW. Only tungsten shielding is used in two of the five Model 360 designs. The "W" in the container model indicates the configuration uses all tungsten shielding. The three other designs use a combination of tungsten and depleted uranium to provide shielding for the radiation sources.

These transport packages are constructed in accordance with drawing R36000. Note that this drawing is provided as a separate attachment to the application cover letter as it is considered proprietary and intended for use only by regulators in the review of the package design's compliance. An additional drawing, R360-User, contained in Appendix 1.3 is intended for use by users of the package for Type B(U) shipments. Drawing R360-User is not proprietary and is intended for reference on the Type B certificate.

I I

15.9 Inches (Ref)

(Height With Bolts I

I I

Optional Grip Brackets (2) ---

151nches(Ref)

(Length with Grips) 13.5 Inches (Ref) --""'

(Width/Diameter)

Figure 1.2a: External View of Models 360 Series Transport Packages

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts April 2018 - Revision 5 Page 1-2 Package 360-2 360-4 360-4W 360-10 360-lOW The external dimensions for all packages are the same. The packages are approximately 15 inches (38 cm) long, 13.5 inches (34 cm) wide and 15.9 inches (40 cm) tall. The length is controlled by the two protruding handling grips mounted near the cover.

All the Model 360 Series packages use the same cover, locks and base container configurations.

The base container can incorporate an optional set oflifting handles (sample handle configuration shown in Figure 1.2a). If used, the lifting capacity complies with regulatory requirements. Based on the shielding design, the individual models will vary on the construction of the shield assembly, the shield retainer and the number oflock assemblies or source securing mechanisms (SSM).

The weight of the Model 360 packages varies depending on the number of sources transported and the shield design. All Model 360 packages have their center of gravity located essentially at the geometric center. The handling and lifting provisions are located approximately an inch (2.54 cm) above the center of gravity. Additional details for these Packages are shown in Table 1.2a:

Table 1.2a: Model 360 Series Package Information Isotope Activity Form 1 Maximum Maximum Maximum Maximum Maximum Shield Source Package Content DU Weight Package Location Capacity2 Capacity2 Weight3 Weight Ir-192 Bottom 150 Ci 300 Ci4 0.3 lbs 40lbs 110 lbs Ir-192 Topor Special 135 Ci 270 Ci (138 grams)

(18 kg)

(50 kg)

Middle Form Se-75 Any Sources 5,000 Ci 5,000 Ci Yb-169 Any 5,000 Ci 5,000 Ci Ir-192 Bottom 150 Ci4 600 Ci4 0.6 lbs 55 lbs 130 lbs Ir-192 Top or Special 135 Ci 540 Ci (276 grams)

(25 kg)

(59 kg)

Middle Form Se-75 Any Sources 5,000 Ci 5,000 Ci Yb-169 Any 5,000 Ci 5,000 Ci Ir-192 Any Special 65 Ci 260 Ci 0.6 lbs 155 lbs Se-75 Any Form 5,000 Ci 5,000 Ci (276 grams)

NA (70.3 kg)

Yb-169 Any Sources 5,000 Ci 5,000 Ci lr-192 Any Special 150 Ci 1,500 Ci 1.5 lbs 80 lbs 170 lbs Se-75 Any Form 5,000 Ci 5,000 Ci (690 grams)

(36 kg)

(77 kg)

Yb-169 Any Sources 5,000 Ci 5,000 Ci Ir-192 Any Special 17 Ci 170 Ci 1.5 lbs NA 180 lbs Se-75 Any Form 5,000 Ci 5,000 Ci (690 grams)

(82 kg)

Yb-169 Any Sources 5,000 Ci 5,000 Ci 1Special Form is defined in 10 CFR 71, 49 CFR 173, and lAEA TS-R-1.

2Maximum activity for lr-192 is defined as output Curies as required in ANSI N432 and IO CFR 34.20 and in line with TS-R-1 and Rulemaking by the USNRC and USDOT published in the Federal Register on 26 January 2004.

3Maximum content weight includes the mass of the radioactive material and the source capsule handling assembly for a shipment containing the maximum number of source assemblies that can be transported per package design.

4The maximum package capacity may be reduced based on the number sources loaded in the Top or Middle shielded positions within the package.

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts 1.2.1 Packaging April 20 I 8 - Revision 5 Page 1-3 The following paragraphs describe the major components of the transport package including: the container assembly, shield assembly, shield retainer, source securing assembly, cover assembly and the source assemblies. There are two basic versions of the package design (e.g., designs with all tungsten shielding and designs with a combination of tungsten and depleted uranium shielding). See Figures 1.2b and 1.2c for package component identification.

I I

COVER ASSEMBLY SSM SCREWS (2 PER SSM)

I I I

f I

I I

SOURCE i ;

SECURING MECHANISM (SSM)

(10 SHOWN)

SHIEILO

~------MOUNTING BOLTS (4)

SHIELD ASSEMB.LY

-.......----(360*1 OW SHOWN PARTIALLY CUTAWAY)

SOURCE ASSEMBLY (424-9 SHOWN)

CONTAINER ASSEMBLY Figure 1.2b: Exploded View of Models 360-lOW (Tungsten Shielded)Transport Package

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts 1 I I

I I

1 1

t i I

I 1, I ;

CO*VER ASSEMBLY ss April 2018 - Revision 5 Page 1-4 SCREWS (2 PER SSM)

SOURCE SECURING MECHANISM (SSM)

(1 0 SHOWN)

SHIELD MOUNTING

...-----BOLTS (4)

SHIELD ASSEMBLY

, _.......__-~(360*10 SHOWN PARTIALLY CUTAWAY)

SOURCE ASSEMBLY (424-91 SHOWN)

CONTAINER ASSEMBLY Figure 1.2c: Exploded View of Models 360-10 (Tungsten/Depleted Uranium Shielded)Transport Package

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts April 2018 - Revision 5 Page 1-11 SOURCE SECURING

.,---IMECHANISM (10 SHOWN)

Figure 1.2k - Typical Source Securing Mechanism (10 Source Configuration Shown)

A9

_J CABLE SCREW WITH SPACER CABLE ASSEMBLY SECTION A9-A9 SOURCE SECURING MECHANISM ALL MODEL 360 PACKAGES Figure 1.21: Lock Assembly Components SLIDE GUIDE

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts April 2018 - Revision 5 Page 1-12 Each source securing mechanism incorporates a locking mechanism to secure the source inside the package and a source dust cap to further protect the end of the source assembly during transport and storage within the package. The source securing mechanisms may also incorporate an optional tungsten shield component (adaptor shield) to provide further shielding if necessary on the top side of the package. The use or non-use of the adaptor shield is determined at the time of package manufacture prior to its release for use as a Type B(U) transport package.

1.2.1.5 Source Assemblies The Models 360 Series Transport Packages are designed to transport special form capsules containing the isotopes listed in Table 1.2a. Depending on the source assembly transported, the source capsule can either be attached to a flexible steel wire or it can be incorporated into a segment of a source chain which forms the source assembly.

The source channels in the 360-2, 360-4 and 360-4 W shield designs are stepped to allow for the ability to secure varying length source assemblies within the shield by the lock assembly. Due to the length of the source assemblies, this will result in effectively three loading positions within each of these shield designs. Sources attached to flexible steel wires will locate the active material at the bottom of the tungsten shield. For sources incorporated into a component of a source chain, the active material will be located at one of two other distances above the bottom of the tungsten shield based on the outer diameter of the bottom link of the source chain (see Figure 1.2m).

Middle Loading Position Bottom Loading Position Figure 1.2m: Source Loading Positions - Stepped Center Shield Versions

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts April 2018 - Revision 5 Page 1-13 The source channels in the 360-10 and 360-1 OW shield designs are a single diameter which is large enough to allow both the flexible wire assemblies and the chain assemblies to be loaded in the bottom shield loading position. To secure the shorter chain assemblies in the package, a stainless steel jumper extension is attached to the chain assemblies to allow the assemblies to be locked in place by the source securing mechanisms while locating the source activity in the bottom of the shield.

Figure 1.2n: Source Loading Positions - Model 360-10 & 360-lOW Center Shields All source assemblies contain a special form source capsule as an integral part of the source assembly. The source assemblies are secured in place in the package by the source securing mechanisms assemblies described in Section 1.2.1.4 and, for the Models 360-10 and 360-lOW, by the jumper extensions.

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts 1.2.2 Contents April 2018 - Revision 5 Page 1-14 The Models 360 Series Transport Packages are designed to transport special form capsules containing the isotopes listed in Table 1.2a. Additional information for the contents is provided in Table 1.2b. The maximum decay heat for Ir-192 has been adjusted in Table 1.2b to account for content activity of the source. Actual content to output activity varies based on the capsule configuration as well as variations in isotope self-absorption. A factor of 2.3 was used for lr-192 to convert output activity to content activity as this factor reflects the worst case variation for Ir-192 sources transported in these packages.

Note:

Ir-192 of higher specific activity can be used, but this would produce sources with lower total mass of the contents. Se-75 and Yb-169 have lower densities than Ir-192 and will produce source capsules of lesser maximum weight than their Ir-192 counterparts.

Values listed in Table 1.2b are the maximum source assembly content masses per container configuration.

Maximum decay heat for these nuclides was calculated as follows:

(

Watt-sec)(

d/sec)

Decay Heat = (Ci)(KeV /decay) 1.602£ - 16 keV 3.7£10 Ci (For Ir-192 the decay heat is factored up by 2.3 to correct output Curies to content Curies in the above equation.)

The maximum decay heat per nuclide is based on the decay energy minus the energy of decay neutrinos since they do not interact with matter. The values for decay energy per disintegration w/o neutrinos was obtained from the Table of Radioactive Isotopes, Shirley, J. Wiley & Sons, Inc. 1986. The value used for Ir-192 was 1,029.32 keV. The value used for Se-75 was 406.23 keV. The value used for Yb-169 was 424.05 keV.

The maximum weight of the contents for the shield containers listed in Table 1.2a are calculated based on the package capacity, the lowest specific activity of lr-192 (200 Ci/gram) used in source production for these sources and the weight of the remaining source assembly components that comprise the heaviest source holder used for that isotope.

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts April 2018 - Revision 5 Page 1-15 Table 1.2b: Isotope Information Permitted in Model 360 Series Packages Identification Isotope Form Chemical/Physical Form Maximum Decay Heat1 lr-192 Metal 4 Watts Se-75 Special Form Sources Metal-Selenide Compound 12 Watts 360-2 Yb-169 Ceramic Pellet 13 Watts Ir-192 Metal 8 Watts Se-75 Special Form Sources Metal-Selenide Compound 12 Watts 360-4 Yb-169 Ceramic Pellet 13 Watts Ir-192 Metal 4 Watts Se-75 Special Form Sources Metal-Selenide Compound 12 Watts 360-4W Yb-169 Ceramic Pellet 13 Watts lr-192 Metal 21 Watts Se-75 Special Form Sources Metal-Selenide Compound 12 Watts 360-10 Yb-169 Ceramic Pellet 13 Watts lr-192 Metal 2 Watts Se-75 Special Form Sources Metal-Selenide Compound 12 Watts 360-lOW Yb-169 Ceramic Pellet 13 Watts 1Maximumdecay heat for Ir-192 is calculated by correcting the output activity to content activity. A factor of2.3 is used for Ir-192 to account for source capsule and self-absorption in this conversion. No corrections are made for Se-75 or Yb-169.

1.2.3 Special Requirements for Plutonium Not applicable. This package is not used for the transportation of plutonium.

1.2.4 Operational Features This package does not involve complex containment systems for source securement. The sources for these packages are all special form, welded capsules. The capsules are part of source assemblies which are held in place by source securing mechanisms after the source assemblies are inserted into the shield tube(s). The ends of the source assemblies are protected by shipping caps that attach to the source securing mechanism and lastly, the source securing mechanisms are further protected by a cover assembly during transport.

1.3 Appendix Figure 1.3a shows a sketch representative of the Model 360 Series transport packages as prepared for shipment. Externally, all packages are identical in size with the only variance being the identification information contained on the package labeling, and the use of optional grip brackets. Additional drawings of these transport packages are enclosed in this appendix.

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts 15.9 inches (Ref)

(Height with Bolts I

I a

April 2018 - Revision 5 Page 1-16 Optional Grip Brackets (2) 151nches(Ref)

(Length with Grips)

---~

13.5 inches (Ref)

(Width/Diameter)

Figure 1.3a Sketch of Model 360 Series Packages in the Transport Configuration

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts 1.3.2 Drawing R360-USER April 2018 - Revision 5 Page 1-18

UNLESS OlHERWISE SPECIFIED:

QSA GLOBAL 40 NORTH AVE, BURLINGTON, MA 01803 DESCRIPTIVE DRAWING TITLE MODEL 360 TRANSPORT PACKAGE R360-USER SIZE DWG. NO.

A REV C

SCALE: NONE SHEET 1 OF2 Security-Related Information Figure Withheld Under 10 CFR 2.390 ALL DIMENSIONS ARE INCHES, TOLERANCE +/-1/16

UNlESS OTHERWISE SPECIFIED:

40 NORTH AVE, BURLINGTON, MA 01803 DESCRIPTIVE DRAWING TITLE MODEL 360 TRANSPORT PACKAGE S

A I

ZE DWG.NO. R360-USER C

SCALE: NONE SHEET 2 OF 2 Security-Related Information Figure Withheld Under 10 CFR 2.390 ALL DIMENSIONS ARE INCHES, TOLERANCE +/-1/16 QSA GLOBAL

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts 2.12.13 US DOT Special Fonn Certificate USA/0797 /S-96 Rev 0 2.12.14 USDOT Special Fonn Certificate USA/0805/S-96 Rev 0 April 2018 - Revision 5 Page 2-38

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts 2.12. 7 USDOT Special Form Certificate USA/0335/S-96 Rev 12 April 2018 - Revision 5 Page 2-45

East Building, PHH-23 1200 New Jersey Ave, SE Washington, D.C. 20590 U.S. Department IAEA CERTIFICATE OF COMPETENT AUTHORITY of Transportation SPECI AL FORM RADIOACTIVE MATERIALS Pipeline and CERTIFICATE USA/0335/S-96, REVISION 12 Hazardous Materials Safety Administration This certifies that the sources described have been demonstrated t o meet t he regulatory requirements for special form radioactive material a s prescribed in the regulations of the International Atomic Energy Agency1 and the United States of America 2 for the transport of radioactive material.

1. Source Identificati on -

QSA Global, I nc. Model 875 Series.

2. Source with Description Cylindrical the outer capsule made of single or Type 304L double encaps ulations stainless steel and tungsten inert gas or laser welded.

Approximate outer dimensions a r e 6. 35 mm (0. 25 in. ) in diameter and either 19.05 mm (0. 75 in. ) or 24. 2 mm (0. 954 in. ) in length.

Inner capsules, when present, are made of stainless steel or titanium.

Construction of the outer capsule shall be in accordance with attached QSA Global,

Inc.

Drawing No. R875 OUTER, Rev. C.

Construction of any i nner capsule s hall be i n accordance with attached QSA Global, Inc. Drawing No.

R8 75 INNER, Rev. C, or QSA Global, Inc. Drawing No. R8 752 7-4 0, Rev.

A.

3. Radioactive Contents -

No more than either 14. 8 TBq

( 400 Ci) of I r idium-192 as a solid metal ; 8. 14 TBq (220 Ci) of Cobalt-60 as a solid metal ;

5. 56 TBq (150 Ci) of Sel enium-75 as an e ncapsulat e d solid metal ; 1. 11 TBq (30 Ci) of Cesium-137 as encapsulated CsC1 2 ;

1.85 TBq (50 Ci) of Thulium-170 as Tm20 3 ;

or 7. 4 TBq (200 Ci) of Ytterbium-169 as Yb 20 3.

1 "Regulati ons for the Safe Transport of Radioactive Material, 2012 Edition,

No. SSR-6 " published by the International Atomic Energy Agency (I AEA),

Vienna, Austria.

2 Title 49, Code of Federal Regulations, Parts 100-199, United States of America.

(- 2 -)

CERTIFICATE USA/0335/S-96, REVISION 12

4. Management System Activities Records of Management System activities required by Paragraph 306 of the IAEA regulations shall be maintained and made available to the authorized officials for at least three years after the last shipment authorized by this certificate.

Consignors in the United States exporting shipments under this certificate shall satisfy the requirements of Subpart H of 10 CFR 71.

5. Expiration Date This certifi cate expires on June 30, 2018.

Previous editions which have not reached their expiration date may continue to be used.

This certificate is issued in accordance with paragraph(s) 804 of the IAEA Regulations and Section 173.47 6 of Title 49 of the Code of Federal Regulations, in response to the September 6, 2017 petition by QSA Global, Inc., Burlington, MA, and in consideration of other information on file in this Office.

Certified By:

William Schoonover Associate Administrator for Hazardous Materials Safety Revision 12 - Issued to extend the expiration date.

September 28,

2017 (DATE)

DESCRIPTIVE DRAWING TITLE 875 SERIES SSDR OUTER CAPSULE SqE DWG. NO.

R875 OUTER A

SCALE:

NONE SHEET 1

or 1 REV C

Security-Related Information Figure Withheld Under 10 CFR 2.390

.4() NORTH AV£.. BURLINGTON, M-' 01803 DESCRIPTIVE DRAWING TITLE 875 SERIES INNER CAPSULE SIZE DWG. NO.

R875 INNER REV A

SCALE: NONE SHEET 1 OF 1 C _,

Security-Related Information Figure Withheld Under 10 CFR 2.390

Security-Related Information Figure Withheld Under 10 CFR 2.390 DESCRIPTIVE DRAWING TITLEX540N CAPSULE ASS EMBLY SIZE DWG. NO.

R 8 7 5 2 7 - 40 REV A

SCALE:

NONE SHEET 1

OF 1 A

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, lnc.

Burlington, Massachusetts 2.12.8 USDOT Special Form Certificate USA/0392/S-96 Rev 12 April 2018 - Revision 5 Page 2-46

U.S.Department IAEA CERTIFICATE OF COMPETENT AUTHORITY of Transportation SPECIAL FORM RADIOACTIVE MATERIALS Pipeline and CERTIFICATE USA/0392/S-96, REVISION 12 Hazardous Materials Safety Administration East Building, PHH-23 1200 New Jersey Ave, SE Washington, D.C. 20590 This certifies that the source described has been demonstrated to meet the regulatory requirements for special form radioactive material as prescribed in the regulations of the International Atomic Energy Agency1 and the United States of America2 for the transport of radioactive material.

1. Source Identification - QSA Global, Inc. Model 875 Capsule.

2. Source Description - Cylindrical single encapsulation made of Type 304 or 304L stainless steel and tungsten inert gas or laser welded.

Approximate exterior dimensions are 5.2 mm (0.205 in.) in diameter and 7. 84 mm

( 0. 309 in.)

in length.

Inside dimensions vary, but minimum wall thickness is 0.482 mm (0.019 in.).

Construction shall be in accordance with attached QSA Global, Inc.

Drawing No. R875 INNER, Rev. C.

3. Radioactive Contents -

No more than either 8.9 TBq (240.0 Ci) of Cobal t-60 or 14. 8 TBq

( 400. 0 Ci) of Iridium-192 in the form of metallic wafers or pellets.

4. Management System Activities Records of Management System activities required by Paragraph 306 of the IAEA regulations shall be maintained and made available to the authorized officials for at least three years after the last shipment authorized by this certificate.

Consignors in the United States exporting shipments under this certificate shall satisfy the requirements of Subpart H of 10 CFR 71.

5. Expiration Date This certificate expires on October 31, 2022.

Previous editions which have not reached their expiration date may continue to be used.

1 "Regulations for the Safe Transport of Radioactive Material, 2012 Edition, No. SSR-6" published by the International Atomic Energy Agency (IAEA),

Vienna, Austria.

2 Title 49, Code of Federal Regulations, Parts 100-199, United States of America.

(- 2 -)

CERTIFICATE USA/0392/S-96, REVISION 12 This certificate i s issued in accordance with paragraph(s) 804 of the IAEA Regulations and Section 173.476 of Title 49 of the Code of Federal Regulations, in response to the October 13, 2017 petiti on by QSA Global, Inc., Burlington, MA, and in consideration of other information on file in thi s Office.

Certified By:

William Schoonover Associate Administrator for Hazardous Materials Safety Revision 12 - Issued to extend the expiration date.

November 03,

2017 (DATE)

DESCRIPTIVE DRAWING TITLE 875 SERIES INNER CAPSULE SIZE DWG. NO.

R 8 7 5 1 N N ER REV A -------c SCALE: NONE SHEET 1 OF 1 Security-Related Information Figure Withheld Under 10 CFR 2.390

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts 2.12.9 USDOT Special Form Certificate USA/0502/S-96 Rev 11 April 2018 - Revision 5 Page 2-47

East Building, PHH-23 1200 New Jersey Ave, SE Washington, D.C. 20590 U.S. Department IAEA CERTIFICATE OF COMPETENT AUTHORITY SPECIAL FORM RADIOACTIVE MATERIALS of Transportation Pipeline and Hazardous Materials Safety Administration CERTIFICATE USA/0502/S-96, REVISION 11 This certifies that the sources described have been demonstrated to meet the regulatory requirements for special form radioactive material as prescribed in the regulations of the International Atomic Energy Agency1 and the United States of America 2 for the transport of radioactive material.

1. Source Identification QSA Global,

Inc.

Model Nos.

X54 (Manufactured before January 1, 1998),

X540 (Manufactured on or after February 17, 1981),

and X540/1 (Manufactured on or after September 27, 2000).

2. Source Description Tungsten inert gas or laser seal welded cyl indrical single or double encapsulations.

The outer encapsulation is made of titanium or stainless steel and the inner encapsulation, if used, is made of titanium, stainless steel,

or aluminum.

Approximate exterior dimensions are 5. 15 mm (0. 2 in. )

maximum diameter and 15. 15 mm (0. 6 in. ) in length (Model X54) ; and 5. 16 mm

( 0. 2 in. ) in diameter and 7. 65 mm

( 0. 3 in. )

in length (Models X540 and X540/1).

Construction shall be in accordance with attached Amer sham Drawing No. A10639,

Issue C (Model X54) or QSA Global Inc. Drawing No. R87527, Rev. H (Models X540 and X5 40/1).

3. Radioactive Contents -

No more than 17.0 TBq (459. 5 Ci) of Cobalt-60 (Model X54) ; or no more than either 20. 0 TBq (540. 5 Ci) of Cobalt-60,

17. 0 TBq (459. 5 Ci) of Iridium-192, or 5. 56 TBq (150. 3 Ci) of Selenium-75 (Models X540 and X540/1).

The Co-60, Ir-192, and Se-75 are in the form of a metal.

1 "Regulations for the Safe Transport of Radioactive Material, 2012 Edition,

No. SSR-6 " published by the International Atomic Energy Agency (IAEA),

Vienna, Austria.

2 Title 49, Code of Federal Regulations, Parts 100-199, United States of America.

(- 2 -)

CERTIFICATE USA/0502/S-96, REVISION 11 4. Management System Activities Records of Management System activities required by Paragraph 306 of the IAEA regulations shall be maintained and made available to the authorized officials for at least three years after the last shipment authorized by this certificate.

Consignors in the United States exporting shipments under this certificate shall satisfy the requirements of Subpart H of 10 CFR 71.

5. Expiration Date This certificate expires on June USA/0502/S-96 Revision 10 may be used until February 28,

other revisions are not authorized for use.

30,

2018.

2018. All This certificate is issued in accordance with paragraph(s) 804 of the IAEA Regulations and Section 173. 476 of Title 49 of the Code of Federal Regulations, in response to the December 4, 201 7 petition by QSA Global,

Inc., Burlington,

MA, and in consideration of other information on file in this Office.

Certified By :

William Schoonover Associate Administrator for Hazardous Materials Safety January 11, 2018 (DATE)

Revision 11 - Issued to update QSA Global Inc. Drawing No. R87527.

ACTUAL SIZE TOLERANCES MATERIAL RD.IOYE AU. BURRS APPROVAL TIIII - U _,. TIii * &al f1II -

--Ill-USED ON SHT. A3 SIZE

? A10639 SHT 1 OF SHTS 1 Security-Related Information Figure Withheld Under 10 CFR 2.390 GENERALNOTES SCALE:

Jc Jws1211 14,1.95 IM.A.

ld'J.J.£ !JP...Ll?.

I~.

I THIRD NfOI.E PffOJEC'llOH $--E;}-

10:1 I ISSUE I.. OD No. I DATE I DRAWN ll:i£a<ED T' N2PRCJYED I ~ APPROVED I MD111F1CA11011S INDIC.\\Tm av ISSUE.,o -----*--*---.. --11.c:. © Mmersham

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DESCRIPTIVE DRAWING TITLE X540 CAPSULE SERIES SIZE DWG. NO.

SCALE:

R87527 NONE SHEET 1

OF" REV H

Security-Related Information Figure Withheld Under 10 CFR 2.390

~~I *;

I 40 NORTH Al/f., BURLINGTON, MA 01803 A

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts 2.12.10 USDOT Special Form Certificate USA/0790/S-96 Rev 1 April 2018 - Revision 5 Page 2-48

U.S. Department East Building, PHH-23 1200 New Jersey Avenue Southeast of Transportation IAEA CERTIFICATE OF COMPETENT AUTHORITY Washington, D.C. 20590 Pipeline and Hazardous Materials Safety Administration SPECIAL FORM RADIOACTIVE MATERIALS CERTIFICATE USA/0790/S - 96, REVIS I ON 1 This certifies that the source described has been demonstrated to meet the regulatory requirements for special form radioactive material as prescribed in the regulations of the International Atomic Energy Agency 1 and the United St ates of America 2 for the transport of radioactive material.

1.

Source Identification -

QSA Global, Inc. Model X9099.

2.

Source Description - Cylindrical single encapsulation made of titanium and tungsten inert gas or laser seal welded.

Approximate outer dimensions are 4.83 mm (0.19 in.) in diameter and 10.92 mm (0.43 in.)

in length.

Construction shall be in accordance with attached QSA Global, Inc. Drawing No. RB00387-1, Rev. A.

3.

Radioactive Contents No more Ytterbium-169.

The Yb-169 is in compressed powder.

than

4. O the form of TBq (108.1 Ci) a ceramic pellet of or

4.

Quality Assurance -

Records of Quality Assurance activities required by Paragraph 310 of the IAEA regulations 1 shall be maintained and made available to the authori zed off i cials f or at least three years after the last shipment author i zed by this cer tificate. Consignors in the Uni ted States exporting shipments under t hi s certificate s hall satisfy the applicabl e requirements of Subpart Hof 10 CFR 71.

5.

Expiration Date - This certificate expires on June 30, 2022.

1 "Regulations for the Edi tion (Revised),

No.

I nternational Atomic Energy Saf e Transport of Radioactive Material, 1996 TS - R-1 (ST-1, Revised),"

published by the Agency(IAEA), Vienna, Austria.

2 Title 49, Code of Federal Regulations, Parts 100-199, United States of America.

---~

J

( -

2 - )

CERTIFICATE USA/0790/S-96, REVISION 1 This certificate is issued in accordance with paragraph 804 of the IAEA Regulations and Section 173.476 of Title 49 of the Code of Federal Regulations, in response to the June 15, 2017 petition by QSA Global, Inc.,

Burlington, MA, and in consideration of other information on file in this Office.

Certified By:

for Hazardous Materials Safety Revision 1 -

Issued to extend the expiration date.

Jun 23 2017 (DATE)

3 2

ITEM QTY ACTIVE MATERIAL PLUG, TAPERED CAPSULE, BOTTOM TITLE 40 NDRTH AVE, BURLINGTON, MA 01803 DESCRIPTIVE DRAWING ERF#

APPROVALS DATE TITLE X9099 CAPSULE ASSEMBLY 2782 Security-Related Information Figure Withheld Under 10 CFR 2.390 ALL DIMENSIONS ARE INCHES, TOLERANCE +/-1/16 TITANIUM ALLOY TITANIUM ALLOY MATERIAL REV A

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts 2.12.13 USDOT Special Form Certificate USA/0797 /S-96 Rev 0 April 2018 - Revision 5 Page 2-51

0 U.S. Department East Building, PHH-23 1200 New Jersey Avenue Southeast of Transportation IAEA CERTIFICATE OF COMPETENT AUTHORITY Washington, D.C. 20590 Pipeline and Hazardous Materials Safety Administration SPECIAL FORM RADIOACTIVE MATERIALS CERTIFICATE USA/0797/S-96, REVISION 0 This certifies that the source described has been demonstrated to meet the regulatory requirements for special form radioactive material as prescribed in the regulations of the International Atomic Energy Agency 1 and the United States of America 2 for the transport of radioactive material.

1.

2.

3.

4.

5.

Source Identification - QSA Global, Inc. Model X9102.

Source Description - Cylindrical single encapsulation made of titanium and tungsten inert gas or laser seal welded.

The radioactive material may be inside an inner assembly of either titanium, vanadium or zirconium alloys.

The capsule may also contain metallic spacers or springs to secure the radioactive material or inner assembly within the capsule.

Approximate outer dimensions are 4.83 mm (0.19 in.) in diameter and 6.86 mm (0.27 in.) in length.

Construction shall be in accordance with attached QSA Global, Inc.

Drawing No.

R87527-17-l, Rev. B.

Radioactive Contents - No more than 7.4 TBq (200 Ci) of Selenium-75.

The Se-75 is in the form of a

physically inert and stable metal-selenide compound.

Quality Assurance -

Records of Quality Assurance activities required by Paragraph 310 of the IAEA regulations 1 shall be maintained and made available to the authorized officials for at least three years after the last shipment authorized by this certificate.

Consignors in the United States exporting shipments under this certificate shall satisfy the applicable requirements of Subpart H of 10 CFR 71.

Expiration Date - This certificate expires on January 31, 2019.

1 "Regulations for the Edition (Revised),

No.

International Atomic Energy Safe Transport of Radioactive Material, 1996 TS-R-1 (ST-1, Revised),"

published by the Agency(IAEA), Vienna, Austria.

2 Title 49, Code of Federal Regulations, Parts 100-199, United States of America.

( -

2 - )

CERTIFICATE USA/0797/S-96, REVISION 0 This certificate is issued in accordance with paragraph 804 of the IAEA Regulations and Section 173.476 of Title 49 of the Code of Federal Regulations, in response to the October 19, 2013 petition by QSA Global, Inc., Burlington, MA, and in consideration of other information on file in this Office.

Certified By:

I

~

Dr. Magdy El-Sibaie

~~* Associate Administrator for Hazardous Materials Safety Revision O -

Original issue.

Jan 17 2014 (DATE)

t----.--....-----------------,.------------IUNLESSOTHERWISESPECIAED:

3 AR 2

ITEM QTY ACTIVE MATERIAL X9102 CAPSULE LID X9102 CAPSULE BODY TITLE ERF#

3005 TITANIUM ALLOY TITANIUM ALLOY MATERIAL AL DIMENSIONS ARE INCHES, TOLERANCE +/-1/16

. 40 NORTH AVE, BURLINGTON, MA 01803 DESCRIPTIVE DRAWING TITLE X9l02 CAPSULE ASSEMBLY Security-Related Information Figure Withheld Under 10 CFR 2.390 DWG. NO. R87527-17-1 REV B

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts 2.12.14 USDOT Special Form Certificate USA/0805/S-96 Rev 0 April 2018 - Revision 5 Page 2-52

0 U.S. Department East Building, PHH-23 1200 New Jersey Avenue Southeast of Transportation IAEA CERTIFICATE OF COMPETENT AUTHORITY Washington, D.C. 20590 Pipeline and Hazardous Materials Safety Administration SPECIAL FORM RADIOACTIVE MATERIALS CERTIFICATE USA/0805/S-96, REVISION 0 This certifies that the source described has been demonstrated to meet the regulatory requirements for special form radioactive material as prescribed in the regulations of the International Atomic Energy Agency 1 and the United States of America 2 for the transport of radi oactive material.

1.

Source Identification -

QSA Global, Inc. Model X9103.

2.

3.

4.

5.

Source Description Cylindrical single encapsulation made of 3 00 series stainless steel and tungsten inert gas or laser seal welded.

The radioactive material may be inside an inner assembly made of vanadium, titanium, titanium alloy, or zirconium alloy.

The capsule may also contain stainless steel,

titanium, titanium alloy, or vanadium spacers or springs to secure the radioactive material or inner assembly within the capsule.

Approximate outer dimensions are 6.86 mm (0.27 in.) in diameter and 26.92 mm (1.06 in. ) in length.

Construction shall be in accordance with attached QSA Global, Inc.

Drawing No. R90017-1, Rev. A.

Radioact ive Contents -

No more than 7.4 TBq (200 Ci) of Selenium-75.

The Se-75 is in the form of a

physically inert and stable metal-selenide compound.

Quality Assurance -

Records of Quality Assurance activities required by Paragraph 310 of the IAEA regulations 1 shall be maintained and made available to the authorized officials for at least three years after the last shipment authorized by this certificate. Consignors in the United States exporting shipments under this certificate shall satisfy the applicable requirements of Subpart Hof 10 CFR 71.

Expiration Date - This certificate expires on November 30, 2019.

1 "Regulations for the Edition (Revised),

No.

International Atomic Energy Safe Transport of Radioactive Material, 1996 TS - R-1 (ST-1, Revised),"

published by the Agency(IAEA), Vienna, Austria.

2 Title 49, Code of Federal Regulations, Parts 100-199, United States of America.

This certificate Regulations and Regulations, in Inc., Burlington, this Office.

Certified By:

( -

2 - )

CERTIFICATE USA/0805/S-96, REVISION 0 is issued in accordance with paragraph 804 of the IAEA Section 173.476 of Title 49 of the Code of Federal response to the October 24, 2014 petition by QSA Global, MA, and in consideration of other information on file in

~

Dr. Magdy El-Sibaie Dec 09 2014 (DATE)

~~, Associate Administrator for Hazardous Materials Safety Revision O -

Original issue.

4 3

2 ITEM QTY X9103 Se LINK BODY STAINLESS STEEL UNLESS OTHERWISE SPECIFIED:

X9103 Se LINK SHANK STAINLESS STEEL ALL DIMENSIONS ARE INCHES, TOLERANCE +/-1/16 ACTIVE CAPSULE/ TARGET INNER CAPSULE ASSEMBLY (OPTIONAL)

TITLE ERF#

MATERIAL APPROVALS 40 NORTH AVE, BURLINGTON, MA 01803 DESCRIPTIVE DRAWING DATE TITLE X9 l 03

-------- ---

1-1

>.JY_\\L_J'JOO crttt SIZE DWG. NO. R90017-1 s 0 cl-11 A SCALE: NONE SHEET 1 OF 1 3160 REV A

Security-Related Information-Figure Withheld per 10 CFR 2.390 I

U, *.,, II

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts Section 3 - THERMAL EVALUATION 3.1 Description of Thermal Design April 2018 - Revision 5 Page 3-1 The Model 360 Series transport packages are completely passive thermal devices having no mechanical cooling system or relief valves. All cooling of the transport package is through free convection and radiation. The maximum heat source is 1,500 Curies of 192lridium. The corresponding decay heat generation rate is approximately 21 Watts (See Section 2.6.1, "Heat").

3.1.1 Design Features The Model 360 Series transport packages are described in Section 1. Components important to safety and materials used in their construction are shown in Table 3.2a. All components important to safety are designed to retain sufficient mechanical and thermal properties at and within the temperature range of -40°C to +800°C. See Table 3.2b.

The package contents consist of 1921ridium, 75Selenium, or 169Ytterbium encapsulated within a welded capsule. The source capsules, located near the center of the shield and welded body, are typically crimped onto a source wire or contained within a source chain assembly which is secured by the lock slide of the source securing mechanism. (For the Model 360-10 and 360-1 OW containers, the source chain assemblies include a jumper extension which is secured by the lock slide of the source securing mechanism. A source securing mechanism is provided for every source assembly, which secures each source independently, and is attached by two screws to the top tungsten shield and top plate of the container assembly.

The large mass of the shield provides a substantial heat sink for decay heat dissipation through the shield assembly and the container. The heat absorbed in the shield is conducted out to the exterior surfaces of the package. The configurations using depleted uranium (DU) include a small amount of polyurethane foam which surrounds and partially insulates the shield within the body. The foam acts as a thermal and oxidizing barrier during high temperature conditions like the hypothetical accident fire test. The all tungsten shielded configurations will conduct heat directly to the container. The large surface area of the container's exterior enables heat to be transferred to the external environment by radiant and convective means.

3.1.2 Decay Heat of Contents The maximum decay heat load is 21 watts when the package contains the maximum quantity of radioactive contents - 1,500 curies of lridum-192. See Table 2.6a.

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts April 2018 - Revision 5 Page 3-4

4. Mi-Tech Metals Inc Data Sheet for HDl 7 with reference to ASTM-B777 Class 1.

5. Eugene A. Avallone and Theodore Baumeister III, Marks' Standard Handbook for Mechanical Engineers, Tenth Edition, New York, McGraw-Hill, 1996.

6. ASTM-B777 Class I.

7. Data from Depleted Uranium Casting Supplier.

3.2.2 Component Specifications All components are specified and described on the drawings included in the Section 1.3.

3.3 General Considerations 3.3.1 Evaluation by Analysis Evaluations by analysis are described in the section they apply to in this Safety Analysis Report or when applicable in the supportive documentation contained in Section 2.12.

3.3.2 Evaluation by Test Evaluations by direct testing are detailed in the supportive documentation contained in Section 2.12 or are described in the section they apply to in this Safety Analysis Report.

3.4 Thermal Evaluation under Normal Conditions of Transport 3.4.1 Heat and Cold 3.4.1.1 Insolation and Decay Heat Technical Report 225 Revision 1 (see Appendix 3.6.2) determines the maximum surface temperature produced by solar heating and decay heat generation of the Model 360 Series transport packages in accordance with 10 CFR 71.7l(c)(l) and IAEA TS-R-1. The maximum surface temperature is compared with the maximum operating temperatures of the package materials of construction.

The thermal evaluation in Technical Report 225 is modeled on the Model 360-10 package configuration. This configuration is used since this package produces the highest decay heat generation of all the Model 360 Style packages, and is therefore representative of the worst case temperature condition for any of the package designs.

The maximum surface temperature caused by the effects of solar input and content decay is 75.3°C located on the center of the package cover. This temperature is well below the maximum service temperature for the materials used in the Model 360 Series transport package components important to safety. This temperature constitutes the most onerous Normal Transport thermal condition. Based on the package materials of construction for components important to safety, this temperature will not be sufficient to adversely affect the containment or shielding integrity as it is well below the maximum service temperature for the materials. As such, the package complies with the requirements of this section.

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts 3.4.1.2 Still Air (shaded) Decay Heating April 2018 - Revision 5 Page 3-5 Technical Report 224 Revision 1 (see Appendix 3.6.1) calculates the maximum surface temperature of the Models 360 Series Transport Packages in the shade (i.e., no insolation effects), assuming an ambient temperature of 38°C (100°F), per 10 CFR 71.43(g).

The thermal evaluation in Technical Report 224 is modeled on the Model 360-10 package configuration. This configuration is used since this package produces the highest decay heat generation of all the Model 360 Style packages, and is therefore representative of the worst case temperature condition for any of the package designs. Thermal evaluations are performed for the Model 360-10 package in two conditions: (1) with the source array located at the lowest shield loading position and (2) with the source array located at the highest shield loading position. These two source loading positions will bound the shield array for all source loading positions.

The highest temperature on any accessible surface of the Model 360-10 transport package was 49.1 °C when transported with content producing the maximum decay heat in any shield position. The highest temperature was determined to be located on the underside of the container top plate outer edge. Based on the analysis in Technical Report 224 Revision 1, it is demonstrated that the surface temperature for any Model 360 transport package in still air at 38°C in the shade will not exceed 50°C.

3.4.1.3 Cold Materials in Table 3.2a are not adversely affected by an ambient air temperature of minus 40°C (-40°F) in still air and shade. These materials have not been found to be susceptible to brittle fracture when subjected to sub-zero temperatures. Based on this evaluation, the Model 360 transport packages will withstand the normal transport cold condition.

3.4.2 Temperatures Resulting in Maximum Thermal Stresses Since the top of the package sees the highest temperature differential due to the effects of solar heating, then the top cover weld seam is the primary area of concern on the package when considering maximum thermal stresses occurring during normal conditions of transport. A highly stressed, welded cover seam could potentially deform enough to cause rupture of the seam and compromise the effectiveness of the packaging.

3.4.2.1 Package Surface See Section 2.6.1.2 which demonstrates that the Model 360 Series transport packages will maintain their structural integrity and shielding effectiveness under the normal transport thermal stress conditions.

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts Section 4 - CONTAINMENT 4.1 Description of the Containment System April 2018 - Revision 5 Page 4-1 The primary containment system for the package is the welded radioactive source capsules.

These source capsules shall be qualified as Special Form radioactive material under 49 CFR 173 and IAEA TS-R-1. The special form source capsules are either attached to flexible handling wire or secured within a source chain assembly. The source wires and source chain assemblies are then maintained within the shielded configuration of the package by means of source securing mechanisms (SSM) after the source wire/assembly is inserted into the shield tube(s). (For source chain assemblies loaded into the Model 360-10 or 360-lOW packages, a jumper extension is attached to the source chain assemblies and this jumper is then secured in the SSM.)

4.1.1 Special Requirements for Damaged Spent Nuclear Fuel Not applicable. These packages do not transport spent nuclear fuel.

4.2 Containment Under Normal Conditions of Transport As demonstrated in Test Plan 199 Report # 1, the normal conditions of transport testing will not cause any breach of the source capsules contained in the package. Since the source capsules are the primary containment of the radioactive contents and no release from the source capsules occurred during testing, the Models 360 Series transport packages are determined to meet the requirements of this section.

4.3 Containment Under Hypothetical Accident Conditions As demonstrated in Test Plan 199 Report #2, after performance of the hypothetical accident conditions of transport testing, radiation levels at one meter from the surface of the package did not exceed 1 R/hr and again there was no breach of the source capsules contained in the package.

The Models 360 Series transport packages are determined to meet the requirements of this section.

4.4 Leakage Rate Tests for Type B Packages The primary containment for the radioactive material in the Models 360 Series Transport Packages is the radioactive source capsule. All source capsules authorized for Type B transport in the Models 360 Series are certified as special form radioactive material under 10 CFR Part 71, 49 CFR Part 173 and IAEA TS-R-1. After manufacture and again once every six months thereafter prior to transport, the source capsule is leak tested in accordance with IS09978: 1992(E) ( or more recent editions) to ensure that containment of the source does not allow release of more than 0.005 µCi ofradioactive material. These fabrication and periodic tests ensure that contamination release from the package does not exceed the regulatory limits.

Reference : ISO 9978: l 992(E) - Radiation Protection - Sealed Radioactive Sources - Leakage Test Methods.

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts 4.6 Appendix Not Applicable.

April 2018 - Revision 5 Page 4-2

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts Section 5 - SHIELDING EVALUATION 5.1 Description of Shielding Design 5.1.1 Design Features April 2018 - Revision 5 Page 5-1 The principal shielding in the Models 360 Series transport packages are either the tungsten shield assembly or the tungsten/depleted uranium shield assembly based on the model designation. Tungsten components are machined to the final shield dimensions. For shield assemblies that use depleted uranium (DU) components, the DU shielding is cast as one piece and is enclosed by stainless steel.

Dimensional information for the individual shield containers is contained in the shield drawings included in Section 1.3.

5.1.2 Summary Table of Maximum Radiation Levels Radiation levels shown in Tables 5.1 a and 5.1 b are for Ir-192 and are based on test specimens from Test Plan 199 Reports # I and #2. Radiation levels shown for Ir-192 in the other Model 360 Series packages are based on untested units (see Section 5.5.1.2). Due to similarities of construction, the maximum dose rates from the other Model 360 Series packages after testing will be essentially unchanged from those obtained on untested units. Radiation levels for the Model 360 Series packages containing Se-75 and Yb-169 are calculated using Microshield Version 7.01 (see Section 5.5.1.1) and Version 9.06. In all cases, the Model 360 Series transport packages will meet the NCT and HAC transport regulatory limits specified in 10 CFR 71.47 and 71.51.

Table 5.1 a: Model 360-IOW lr-192 Summary Table of External Radiation Levels (Non-Exclusive Use)1 360-lOW serial number TP199A - Reference Test Plan 199 Re ort #2 in Section 2.12 Normal Conditions of Packa e Surface mSv/h mrem/h Side Bottom Bottom 0.9 90 1.89 189 0.044 4.4 2 200 2 200 0.1 10 0.003 0.3 0.019 1.9 0.043 4.3 10 1000 10 1000 10 1000 1Table results are extrapolated to the package capacity of 170 Ci oflr-192 and incorporate surface correction factors. Survey Results are reported for sources located at the bottom of shield storage position which is the only loading position for the Model 360-1 OW package.

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts April 2018 - Revision 5 Page 5-2 Table 5.lb: Model 360-lOW Ir-192 Summary Table of External Radiation Levels (Exclusive Use)1*4 (360-lOW serial number TP199A-Reference Test Plan 199 Report #2 in Section 2.12)

Package (or Freight Container) Surface Normal Conditions mSv/h (mrem/h) of Transport Top Side Total (Gamma Only) 0.02 (2) 0.9 (90) 10 CFR 71.47(b) 10 (1000)2 10 (1000)2 Limit Vehicle Surface mSv/h (mrem/h)

Total (Gamma Onlv)

< 0.02 (2)

< 0.9 (90) 10 CFR 71.47(b) 2 (200) 2 (200)

Limit Hypothetical Accident Conditions Total (Gamma Only) 10 CFR 71.51(a)(2)Limit 1For packages transported by roadway, railway and sea.

2For packages in closed vehicles, otherwise, 2 (200).

3Confirmed at time of vehicle loading prior to shipment.

Bottom 1.89 (189) 10 (1000)2

< 1.89 (189) 2 (200) 2 Meters from Outer Vehicle Surface mSv/h (mrem/h' Top Side Bottom

< 0.001 (O. l)

< 0.019 (1.9)

< 0.044 (4.4) 0.1 (10) 0.1 (10) 0.1 (10)

Occupied Position mSv/h (mrem/hr)3

< 0.02 (2) 0.02 (2) 1 Meter from Package Surface mSv/h (mrem/hr) 0.003 (0.3) 0.019 (1.9) 0.043 (4.3) 10 (1000) 10(1000) 10 (1000) 4Table results are extrapolated to the package capacity and incorporate surface correction factors. Survey Results are reported for sources located at the bottom of shield storage position which is the only loading position for the Model 360-1 OW package.

Table 5.lc: Model 360-2 Ir-192 Summary Table of External Radiation Levels (Non-Exclusive User 360-2 serial number 360-2-B w/TP199E Container Ass - Reference Tech Re ort No. 240 in Section 2.12 Normal Conditions of Transport Total2 mrem/h 1 Meter from Packa e Surface mSv/h mrem/h To Side Bottom

<10 1000

<10 1000 10 1000 10 1000 10 1000 1 Survey Results for are reported for sources located at the bottom of shield storage position (B) and the top shield storage position (T). Table results are extrapolated to the package capacity of300 Ci oflr-192 for the (B) storage position and 270 Ci oflr-192 for the (T) storage position. All results incorporate surface correction factors. Survey results for sources located in the middle shield position will be conservatively bounded by the results of the top shield surveys.

2The highest dose rate from either survey position is reported in the "Total" column entries as representative of the worst case result for any source storage location (top, bottom or middle shield positions).

3Yalues shown for HAC transport are based on negligible dose rate change seen after testing performed on the Model 360-lOW transport packages in Test Plan 199 Report #2. Due to similarities of construction in the package designs, it is reasoned that the other Model 360 Series packages will never exceed the maximum radiation level limit in IO CFR 71.4 7(a)(2) under HA Cs.

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts April 2018 - Revision 5 Page 5-3 Table 5. ld: Model 360-2 lr-192 Summary Table of External Radiation Levels (Exclusive Use)1*4 360-2 serial number 360-2-B w/TPI99E Container Ass -Reference Tech Re ort No. 240 in Section 2.12 Normal Conditions of Transport Gamma Gamma Totals IO CFR 71.47 b Limit Gamma Gamma Totals H

Package (or Freight Container) Surface mSv/h mrem/h 1For packages transported by roadway, railway and sea.

2For packages in closed vehicles, otherwise, 2 (200).

3Confirmed at time of vehicle loading prior to shipment.

2 Meters from Outer Vehicle Surface mSv/h mrem/h 1 Meter from Packa e Surface mSv/h mrem/hr 4Survey Results for are reported for sources located at the bottom of sh ield storage position (B) and the top shield storage position (T). Table results are extrapolated to the package capacity of300 Ci oflr-192 for the (B) storage position and 270 Ci oflr-192 for the (T) storage position. All results incorporate surface correction factors. Survey results for sources located in the middle shield position will be conservatively bounded by the results of the top shield surveys.

5The highest dose rate from either survey position is reported in the "Total" column entries as representative of the worst case result for any source storage location (top, bottom or middle shield positions).

6Values shown for HAC transport are based on negligible dose rate change seen after testing performed on the Model 360-1 OW transport packages in Test Plan 199 Report #2. Due to similarities of construction in the package designs, it is reasoned that the other Model 360 Series packages will never exceed the maximum radiation level limit in 10 CFR 71.47(a)(2) under HACs.

Table 5.le: Model 360-4 Ir-192 Summary Table of External Radiation Levels (Non-Exclusive Use) 1 360-4 serial number 360-4-A w/TP199E Container Ass - Reference Tech Re ort No. 240 in Section 2.12 Normal Conditions of Transport Total2 H

mrem/h I Meter from Packa e Surface mSv/h mrem/h To Side Bottom

< 10 1000 10 1000 1Survey Results for are reported for sources located at the bottom of shield storage position (B) and the top shield storage position (T). Table results are extrapolated to the package capacity of 600 Ci of Ir-192 for the (B) storage position and 540 Ci of Ir-192 for the (T) storage position. All results incorporate surface correction factors. Survey results for sources located in the middle shield position will be conservatively bounded by the results of the top shield surveys.

2The highest dose rate from either survey position is reported in the "Total" column entries as representative of the worst case result for any source storage location (top, bottom or middle shield positions).

3Values shown for HAC transport are based on negligible dose rate change seen after testing performed on the Model 360-1 OW transport packages in Test Plan 199 Report #2. Due to similarities of construction i.n the package designs, it is reasoned that the other Model 360 Series packages will never exceed the maximum radiation level limit in IO CFR 71.4 7(a)(2) under HA Cs.

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts April 2018 - Revision 5 Page 5-4 Table 5. lf: Model 360-4 Ir-192 Summary Table of External Radiation Levels (Exclusive Use)1*4 (360-4 serial number 360-4-A w/TPl 99E Container Assy - Reference Tech Report No. 240 in Section 2.12)

Package (or Freight Container) Surface mSv/h Normal Conditions of (rnrem/h)

Transport Top Side Gamma ffi) 0.009 (0.9) 1.73 (173)

Gamma (T) 1.06 (106) 1.81 (181)

Totals 1.36 (136) 1.98 (198) 10 CFR 71.47(b) Limit 10 (1000)2 10 (1000)2 Vehicle Surface mSv/h (mrem/h)

Gamma ffi)

<0.009 (0.9)

<1.73 (173)

Gamma (T)

<1.06 (106)

<1.81 (181)

Totals

<l.36 (136)

<1.98 (198) 10 CFR 71.47(b) Limit 2 (200) 2 (200)

Hypothetical Accident Conditions6 Total (Gamma only Any Loading Position) 10 CFR 71.51(a)(2) Limit 1For packages transported by roadway, railway and sea.

2For packages in closed vehicles, otherwise, 2 (200).

3Confirmed at time of vehicle loading prior to shipment.

Bottom 1.27 (127) 0.26 (26) 1.53 (153) 10 (1000)2

<1.27 (127)

<0.26 (26)

<1.53 (153) 2 (200) 2 Meters from Outer Vehicle Surface mSv/h (rnrem/h)

Top Side Bottom

<0.004 (0.4)

<0.032 (3.2)

<0.028 (2.8)

<0.021 (2.1)

<0.034 (3.4)

<0.001 (1.0)

<0.021 (2.1)

<0.034 (3.4)

<0.028 (2.8) 0.1 (10) 0.1 (10) 0.1 (10)

Occupied Position mSv/h (mrem/hr)3

< 0.02 (2)

S 0.02 (2) 0.02 (2) 1 Meter from Package Surface mSv/h (mrem/hr)

<10 (1000)

<10 (1000) 10 (1000) 10 (1000) 10 (1000) 4Survey Results for are reported for sources located at the bottom of shield storage position (B) and the top shield storage position (T). Table results are extrapolated to the package capacity of 300 Ci of Ir-192 for the (B) storage position and 270 Ci of lr-192 for the (T) storage position. All results incorporate surface correction factors. Survey results for sources located in the middle shield position will be conservatively bounded by the results of the top shield surveys.

5The highest dose rate from either survey position is reported in the "Total" column entries as representative of the worst case result for any source storage location (top, bottom or middle shield positions).

6Values shown for HAC transport are based on negligible dose rate change seen after testing performed on the Model 360-IOW transport packages in Test Plan 199 Report #2. Due to similarities of construction in the package designs, it is reasoned that the other Model 360 Series packages will never exceed the maximum radiation level limit in IO CFR 71.47(a)(2) under HACs.

Table 5.lg: Model 360-4W Ir-192 Summary Table of External Radiation Levels (Non-Exclusive Use) 1 360-4W serial number 360-4W-A w/TP199E Container Ass - Reference Tech Re ort No. 240 in Section 2.12 Normal Conditions of Packa e Surface mSv/h mrem/h 1 Meter from Packa e Surface mSv/h rnrem/h Transport Side To Side Bottom GammaOnl B

1.15 115 0.003 0.3 0.021 2.1 0.041 4.1 GammaOnl T

1.64 164 0.007 0.7 0.026 2.6 0.013 1.3 Total2 1.64 164 0.007 0.7 0.026 2.6 0.041 4.1 10 CFR 71.47 a Limit 2 200 0.1 10 0.1 10 0.1 10 H

<10 1000

<10 1000 10 1000 LO 1000 10 1000

'Survey Results for are reported for sources located at the bottom of shield storage position (B) and the top shield storage position (T). Table results are extrapolated to the package capacity of260 Ci oflr-192 for the (B) and (T) storage positions. All results incorporate surface correction factors. Survey results for sources located in the middle shield position will be conservatively bounded by the results of the top shield surveys.

2The highest dose rate from either survey position is reported in the "Total" column entries as representative of the worst case result for any source storage location (top, bottom or middle shield positions).

3Values shown for HAC transport are based on negligible dose rate change seen after testing performed on the Model 360-IOW transport packages in Test Plan 199 Report #2. Due to similarities of construction in the package designs, it is reasoned that the other Model 360 Series packages will never exceed the maximum radiation level limit in 10 CFR 71.47(a)(2) under HACs.

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts April 2018 - Revision 5 Page 5-5 Table 5. lh: Model 360-4W Ir-192 Summary Table of External Radiation Levels (Exclusive Use)'-4 (360-4 W serial number 360-4 W-A w/TP 199E Container Assv - Reference Tech Report No. 240 in Section 2.12)

Package (or Freight Container) Surface mSv/h Normal Conditions of (mrem/h)

Transport Top Side Gammaffi) 0.06 (6) 1.15 (115)

Gamma(T) 0.30 (30) 1.64 (164)

Totals 0.30 (30) 1.64 (164) 10 CFR 71.47(b) Limit IO (1000)2 10 (1000)2 Vehicle Surface mSv/h (mrem/h)

Gamma(B)

<0.06 (6)

<1.15 (115)

Gamma (T)

<0.30 (30)

<1.64 (164)

Totals

<0.30 (30)

<1.64 (164) 10 CFR 7I.47<b) Limit 2 (200) 2 (200)

Hypothetical Accident Conditions6 Total (Gamma only Any Loading Position)

IO CFR 71.51(a)(2) Limit 1For packages transported by roadway, railway and sea.

2For packages in closed vehicles, otherwise, 2 (200).

3Confirmed at time of vehicle loading prior to shipment.

Bottom 1.89 (189) 0.35 (35) 1.89 (189) 10 (1000)2

<1.89 (189)

<0.35 (35)

<1.89 (189) 2 (200) 2 Meters from Outer Vehicle Surface mSv/h (mrem/h)

Top Side Bottom

<0.003 (0.3)

<0.021 (2.1)

<0.041 (4.1)

<0.007 (0.7)

<0.026 (2.6)

<0.013 (1.3)

<0.007 (0.7)

<0.026 (2.6)

<0.041 (4.1) 0.1 (10) 0.1 (10) 0.1 (10)

Occupied Position mSv/h (mrem/hr)3

'.S 0.02 (2)

< 0.02 (2)

< 0.02 (2) 0.02 (2) 1 Meter from Packa11:e Surface mSv/h (mrem/hr)

<IO (1000)

<10 (1000) 10 (1000) 10 (1000) 10 (1000) 4Survey Results for are reported for sources located at the bottom of shield storage position (B) and the top shield storage position (T). Table results are extrapolated to the package capacity of 260 Ci oflr-192 for the (8) and (T) storage positions. All results incorporate surface correction factors. Survey results for sources located in the middle shield position will be conservatively bounded by the results of the top shield surveys.

5The highest dose rate from either survey position is reported in the "Total" column entries as representative of the worst case result for any source storage location (top, bottom or middle shield positions).

6Values shown for HAC transport are based on negligible dose rate change seen after testing performed on the Model 360-1 OW transport packages in Test Piao 199 Report #2. Due to similarities of construction in the package designs, it is reasoned that the other Model 360 Series packages will never exceed the maximum radiation level limit in IO CFR 7 I.47(a)(2) under HA Cs.

Table 5.li: Model 360-10 Ir-192 Summary Table of External Radiation Levels (Non-Exclusive Use)1 360-10 serial number 360-10-C w/TPl 99E Container Ass - Reference Tech Re ort No. 240 in Section 2.12 Normal Conditions of Packa e Surface mSv/h mrem/h l Meter from Packa e Surface mSv/h mrem/h Side Bottom

<10 1000

<10 1000 10 1000 10 1000 10 1000 1Table results are extrapolated to the package capacity of 1,500 Ci of lr-192 and incorporate surface correction factors. Survey Results are reported for sources located at the bottom of shield storage position which is the only loading position for the Model 360-10 package.

2Values shown for HAC transport are based on negligible dose rate change seen after testing performed on the Model 360-1 OW transport packages in Test Plan 199 Report #2. Due to similarities of construction in the package designs, it is reasoned that the other Model 360 Series packages will never exceed the maximum radiation level limit in IO CFR 71.4 7(a)(2) under HA Cs.

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts April 2018 - Revision 5 Page 5-6 Table 5.lj: Model 360-10 Ir-192 Summary Table of External Radiation Levels (Exclusive Use)1*4 (360-10 serial number 360-10-C w/TPl 99E Container Assy - Reference Tech Report No. 240 in Section 2.12)

Package (or Freight Container) Surface Normal Conditions mSv/h (mrem/h) of Transport Too Side Total (Gamma Only) 0.19 (19) 1.08 (108) 10 CFR 71.47(b)

IO (1000)2 10 (1000)2 Limit Vehicle Surface mSv/h (mrem/h)

Total (Gamma Only)

<0.19 (19)

<1.08 (108) 10 CFR 71.47(b) 2 (200) 2 (200)

Limit Hypothetical Accident Conditions5 Total (Gamma Only) 10 CFR 71.51(a)(2) Limit 1For packages transported by roadway, railway and sea.

2For packages in closed vehicles, otherwise, 2 (200).

3Confinned at time of vehicle loading prior to shipment.

Bottom 1.77 (I 77) 10 (1000)2

<1.77 (177) 2 (200) 2 Meters from Outer Vehicle Surface mSv/h (mrem/h)

Top Side Bottom

<0.007 (0.7)

<0.022 (2.2)

<0.036 (3.6) 0.1 (10) 0.1 (10) 0.1 (10)

Occupied Position mSv/h (mrem/hr)3

'.S 0.02 (2) 0.02 (2) 1 Meter from Packaee Surface mSv/h (mrem/hr)

<10 (1000)

<10 (1000) 10 (1000) 10 (1000) 10 (1000) 4Table results are extrapolated to the package capacity and incorporate surface correction factors. Survey Results are reported for sources located at the bottom of shield storage position which is the only loading position for the Model 360-10 package.

5Values shown for RAC transport are based on negligible dose rate change seen after testing performed on the Model 360-IOW transport packages in Test Plan 199 Report #2. Due to similarities of construction in the package designs, it is reasoned that the other Model 360 Series packages will never exceed the maximum radiation level limit in 10 CFR 71.47(a)(2) under HACs.

Table 5.lk: Model 360-2 Se-75 Summary Table of External Radiation Levels (Non-Exclusive Use) 1 (Values Calculated Using Microshield Version 7.01 - Reference Tech Report No. 228 in Section 2.12)

Normal Conditions of Package Surface mSv/h mrem/h) 1 Meter from Package Surface mSv/h (mrem/h)

Transport Too Side Bottom Top Side Bottom Total (Gamma Only) l.56 (156) l.7E-4 8E-5 0.04 (4.0) 3E-6 (3E-4) lE-6 (lE-4)

(0.017)

(0.008) 10 CFR 71.47(a) Limit 2 (200) 2 (200) 2 (200) 0.1 (10) 0.1 (10) 0.1 (IO)

Hypothetical Accident Conditions2 Total (Gamma Only)

<10 (1000)

<IO (1000)

<10 (1000) 10 CFR 71.51(a)(2) Limit 10 (1000)

IO (1000)

'Table results above are extrapolated from Technical Report No. 228 to a maximum capacity of5,000 Ci ofSe-75. The calculated results in this table reflect the highest dose rate reading calculated for the package in any loading position (T), (M) or (B).

2Based on comparisons of radiation profiles for lr-192 after hypothetical accident testing, it is assessed that radiation levels from Se-75 will be essentially unchanged after undergoing the hypothetical accident condition testing. Based on comparison Se-75 results to Ir-192, Exclusive Use results for Se-75 will be no worse than those calculated for NCT.

Table 5.11: Model 360-4 Se-75 Summary Table of External Radiation Levels (Non-Exclusive Use) 1 Values Calculated Usin Microshield Version 7.0 I - Reference Tech Re ort No. 228 in Section 2.12 Normal Conditions of Transport Total (Gamma Only) 1.80 ( 180) 5E-5 0.005 2 200 2 200 mrem/h Bottom 5E-5 0.005 2 200 To Side Bottom 0.046 (4.6) lE-6 (lE-4) 8E-7 (8E-5) 0.1 10 0.1 10 0.1 10

<10 1000

<10 1000 IO 1000 10 1000

'Table results above are extrapolated from Technical Report No. 228 to a maximum capacity of 5,000 Ci of Se-75. The calculated results in this table reflect the highest dose rate reading calculated for the package in any loading position (T), (M) or (B).

2Based on comparisons of radiation profiles for Ir-192 after hypothetical accident testing, it is assessed that radiation levels from Se-75 will be essentially unchanged after undergoing the hypothetical accident condition testing. Based on comparison Se-75 results to lr-192, Exclusive Use results for Se-75 will be no worse than those calculated for NCT.

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts April 2018 - Revision 5 Page 5-7 Table 5.lm: Model 360-4W Se-75 Summary Table of External Radiation Levels (Non-Exclusive Use) 1 (Values Calculated Using Microshield Version 7.01 - Reference Tech Report No. 228 in Section 2.12)

Normal Conditions of Package Surface mSv/h mrem/h) 1 Meter from Package Surface mSv/h (mrem/h)

Transport Top Side Bottom Top Side Bottom Total (Gamma Only) 0.14 (14) 0.015 (1.5) 0.0045 0.0035 (0.35) 2.5E-4 (0.025) lE-4 (0.01)

(0.45) 10 CFR 71.47(a) Limit 2 (200) 2 (200) 2 (200) 0.1 (10) 0.1 (10) 0.1 (10)

Hypothetical Accident Conditions2 Total (Gamma Only)

<10 (1000)

<10 (1000) 10 CFR 71.5l(a)(2) Limit 10 (1000) 10 (1000) 10 (1000) 1Table results above are extrapolated from Technical Report No. 228 to a maximum capacity of 5,000 Ci ofSe-75. The calculated results in this table reflect the highest dose rate reading calculated for the package in any loading position (T), (M) or (8).

2Based on comparisons of radiation profiles for Ir-192 after hypothetical accident testing, it is assessed that radiation levels from Se-75 will be essentially unchanged after undergoing the hypothetical accident condition testing. Based on comparison Se-75 results to lr-192, Exclusive Use results for Se-75 will be no worse than those calculated for NCT.

Table 5.ln: Model 360-10 Se-75 Summary Table of External Radiation Levels (Non-Exclusive Use) 1 Values Calculated Usin Microshield Version 7.01 - Reference Tech Re ort No. 228 in Section 2.12 Normal Conditions of Packa e Surface mSv/h mrem/h Transport To Side Bottom To Side Bottom Total (Gamma Only) 0.835 4.5E-5 4.5E-5 0.0215 (2.15) 5E-7 (5E-5) 5E-7 (5E-5) 83.5 0.0045 0.0045 2 200 2 200 2 200 O.l 10 0.1 10 0.1 10

<10 1000

<10 1000 10 1000 10 1000 10 1000 1Table results above are extrapolated from Technical Report No. 228 to a maximum capacity of5,000 Ci ofSe-75.

2Based on comparisons of radiation profiles for Ir-1 92 after hypothetical accident testing, it is assessed that radiation levels from Se-75 will be essentially unchanged after undergoing the hypothetical accident condition testing. Based on comparison Se-75 results to Ir-192, Exclusive Use results for Se-75 will be no worse than those calculated for NCT.

Table 5.lo: Model 360-lOW Se-75 Summary Table of External Radiation Levels (Non-Exclusive Use) 1 (Values Calculated Using Microshield Version 7.01 - Reference Tech Report No. 228 in Section 2.12)

Normal Conditions of Package Surface mSv/h mrem/h) 1 Meter from Package Surface mSv/h (mrem/h)

Transport Top Side Bottom Top Side Bottom Total (Gamma Only) 0.485 0.065 (6.5) 0.0135 0.0125 (1.25) 0.001 (0.1) 2E-4 (0.02)

(48.5)

(1.35) 10 CFR 71.47(a) Limit 2 (200) 2 (200) 2 (200) 0.1 (10) 0.1 (10) 0.1 (10)

Hvoothetical Accident Conditions2 Total (Gamma Only)

<10 (1000)

<10 (1000) 10 CFR 71.5l(a)(2) Limit 10 (1000) 10 (1000) 10 (1000) 1Table results above are extrapolated from Technical Report No. 228 to a maximum capacity of 5,000 Ci ofSe-75.

2Based on comparisons of radiation profiles for Ir-192 after hypothetical accident testing, it is assessed that radiation levels from Se-75 will be essentially unchanged after undergoing the hypothetical accident condition testing. Based on comparison Se-75 results to Ir-1 92, Exclusive Use results for Se-75 will be no worse than those calculated for NCT.

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts April 2018 - Revision 5 Page 5-8 Table 5.lp: Model 360-2 Yb-169 Summary Table of External Radiation Levels (Non-Exclusive Use)'

Values Calculated Usin Microshield Version 7.01 - Reference Tech Re ort No. 228 in Section 2.12 Normal Conditions of Transport Total (Gamma Only) 0.003 (0.3) 1.5E-5 0.0015 2 200 2 200 mrem/h Bottom 2E-5 0.002 2 200 1 Meter from Packa e Surface mSv/h mrem/h To Side Bottom JE-4 (0.01) 3E-7 (3E-5) 3E-7 (3E-5) 0.1 10 0.1 10 0.1 10

<10 1000

<10 1000 10 1000 10 1000

'Table results above are extrapolated from Technical Report No. 228 to a maximum capacity of 5,000 Ci ofYb-169. The calculated results in this table reflect the highest dose rate reading calculated for the package in any loading position (T), (M) or (B).

2Based on comparisons of radiation profiles for Ir-192 after hypothetical accident testing, it is assessed that radiation levels from Yb-169 will be essentially unchanged after undergoing the hypothetical accident condition testing. Based on comparison Yb-169 results to Ir-192, Exclusive Use results for Yb-169 will be no worse than those calculated for NCT.

Table 5.1 q: Model 360-4 Yb-169 Summary Table of External Radiation Levels (Non-Exclusive Use)'

Values Calculated Usin Microshield Version 7.01 - Reference Tech Re ort No. 228 in Section 2.12 Normal Conditions of Transport Total (Gamma Only)

Packa e Surface mSv/h To Side 0.004 (0.4) l.5E-5 0.0015 2 200 2 200 mrem/h Bottom 2E-5 0.002 2 200 To Side Bottom lE-4 (0.01) 3E-7 (3E-5) 3E-7 (3E-5) 0.1 10 0.1 10 0.1 10

<10 1000 10 1000 1Table results above are extrapolated from Technical Report No. 228 to a maximum capacity of 5,000 Ci ofYb-169. The calculated results in this table reflect the highest dose rate reading calculated for the package in any loading position (T), (M) or (B).

2Based on comparisons of radiation profiles for lr-192 after hypothetical accident testing, it is assessed that radiation levels from Yb-169 will be essentially unchanged after undergoing the hypothetical accident condition testing. Based on comparison Yb-169 results to Ir-192, Exclusive Use results for Yb-169 will be no worse than those calculated for NCT.

Table 5.lr: Model 360-4W Yb-169 Summary Table of External Radiation Levels (Non-Exclusive Use)'

(Values Calculated Using Microshield Version 7.01 - Reference Tech Report No. 228 in Section 2.12)

Normal Conditions of Package Surface mSv/h (mrem/h) 1 Meter from Package Surface mSv/h (mrem/h)

Transport Top Side Bottom Top Side Bottom Total (Gamma Only) lE-4 (0.01) 2.5E-6 5E-7 (5E-5) 2E-6 (2E-4) 4.5E-8 ( 4.5E-6) lE-8 (JE-6)

(2.5E-4) 10 CFR 71.47(a) Limit 2 (200) 2 (200) 2 (200) 0.1 (10) 0.1 (10) 0.1 (10)

Hypothetical Accident Conditions2 Total (Gamma Only)

<10 (1000)

<10 (1000) 10 CFR 71.5J(a)(2) Limit 10 (1000) 10 (1000) 10 (1000) 1Table results above are extrapolated from Technical Report No. 228 to a maximum capacity of 5,000 Ci ofYb-169. The calculated results in this table reflect the highest dose rate reading calculated for the package in any loading position (1), (M) or (B).

2Based on comparisons of radiation profiles for lr-192 after hypothetical accident testing, it is assessed that radiation levels from Yb-169 will be essentially unchanged after undergoing the hypothetical accident condition testing. Based on comparison Yb-169 results to Ir-192, Exclusive Use results for Yb-169 will be no worse than those calculated for NCT.

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts April 2018 - Revision 5 Page 5-9 Table 5.ls: Model 360-10 Yb-169 Summary Table of External Radiation Levels (Non-Exclusive Use)'

(Values Calculated Using Microshield Version 7.01 - Reference Tech Report No. 228 in Section 2.12)

Normal Conditions of Package Surface mSv/h mrem/h) 1 Meter from Package Surface mSv/h (mrem/h)

Transport Top Side Bottom Top Side Bottom Total (Gamma Only) lE-4 (0.1) 2E-5 2E-5 3E-5 (0.003) 3E-7 (3E-5) 3E-7 (3E-5)

(0.002)

(0.002) 10 CFR 71.47(a) Limit 2 (200) 2 (200) 2 (200) 0.1 (10) 0.1 (] 0) 0.1 (10)

Hvvothetical Accident Conditions2 Total (Gamma Onlv)

<10 (1000)

<IO (1000) 10 CFR 71.5l(a)(2) Limit 10 (1000) 10 (1000) 10 (1000) 1Table results above are extrapolated from Technical Report No. 228 to a maximum capacity of 5,000 Ci ofYb-169.

2Based on comparisons of radiation profiles for Ir-192 after hypothetical accident testing, it is assessed that radiation levels from Yb-169 will be essentially unchanged after undergoing the hypothetical accident condition testing. Based on comparison Yb-169 results to Ir-192, Exclusive Use results for Yb-169 will be no worse than those calculated for NCT.

Table 5.lt: Model 360-lOW Yb-169 Summary Table of External Radiation Levels (Non-Exclusive Use)'

(Values Calculated Using Microshield Version 7.01 - Reference Tech Report No. 228 in Section 2.12)

Normal Conditions of Package Surface mSv/h ' mrem/h) 1 Meter from Package Surface mSv/h (mrem/h)

Transport Top Side Bottom Top Side Bottom Total (Gamma Only) 5E-5 2E-5 2E-6 (2E-4) l.5E-5 3E-7 (3E-5) 3.5E-8 (3.5E-6)

(0.005)

(0.002)

(0.0015) 10 CFR 71.47(a) Limit 2 (200) 2 (200) 2 (200) 0.1 (10) 0.1 (10) 0.1 (10)

Hvvothetical Accident Conditions2 Total (Gamma Only)

<10 (1000)

<10 (1000) 10 CFR 71.5 l(a)(2) Limit 10(1000) 10 (1000) 10 (1000) 1Table results above are extrapolated from Technical Report No. 228 to a maximum capacity of 5,000 Ci ofYb-169.

2Based on comparisons of radiation profiles for Ir-192 after hypothetical accident testing, it is assessed that radiation levels from Yb-169 will be essentially unchanged after undergoing the hypothetical accident condition testing. Based on comparison Yb-169 results to lr-192, Exclusive Use results for Yb-169 will be no worse than those calculated for NCT.

5.2 Source Specification 5.2.1 Gamma Source The gamma sources allowed for transport in the Models 360 Series are described in Sections 1.2.2 and 2.10.

5.2.2 Neutron Source Not Applicable. These packages are not used for the transportation of neutron emitting sources.

5.3 Shielding Model 5.3.1 Configuration of Source and Shielding Microshield, Version 7.01 and Version 9.06, were used to determine the loading capacity for isotopes other than lr-192 referenced in the tables in Section 5.1.2. Microshield calculations for Yb-169 and Se-75, based on conservative assumptions, and comparisons to Ir-192 survey measurements were used to verify shield capacity for these isotopes. (See Technical Report No. 228 in Section 5.5.) These results provided ratios to determine if the survey measurements after testing would disqualify use of any isotope. Since the testing results showed that an insignificant change had occurred in the radiation profiles, all isotopes were considered acceptable.

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts April 2018 - Revision 5 Page 5-10 Surface lm Additional Microshield calculations were performed using Microshield Version 9.06 (see Section 5.5.3).

These calculations evaluated the worst case package configuration for Ir-192 (Model 360-1 OW with sources located in the top loading position with the measurements taken on the package side), and compared that to the Se-75 and Yb-169 limits for the container. This shielding calculation was run for 1 Ci quantities of Ir-192, Se-75 and Yb-169. Based on those calculations, a ratio was obtained to determine the equivalent Se-75 and Yb-169 activities for the package based on the original Ir-192 package capacities.

1 Ci Activity Calculations for Side of 360-lOW Package (values w/build-up) lr-192 Se-75 Yb-169 mR/hr mrad/hr mR/hr mrad/hr mR/hr mrad/hr 5.llE+OO 4.46E+OO l.09E-02 9.SlE-03 2.32E-03 2.02E-03 8.53E-02 7.44E-02 l.82E-04 l.59E-04 3.87E-05 3.38E-05

[ Ratio per Ci to lr-1921 469 2,204 Max Se-75 & Yb-169 Capacities Based on lr-192 Capacity and Correction Factor lr-192 (based on side limits)

Se-75 Yb-169 Per Source (Ci)

Per Pkg (Ci)

Per Source (Ci)

Per Pkg (Ci)

Per Source (Ci)

Per Pkg (Ci) 17 170 7,971 79,708 37,463 374,631 For all Model 360 style packages, we have requested a maximum Se-75 and Yb-169 limit per source and per package of 5,000 Ci. Based on the above evaluation, when loaded in the worst case shielding configuration, these packages can effectively shield more than 1.59 times the activities requested in our application for Se-75 or Yb-169. We submit that any uncertainties associated with the Microshield shielding program calculations are insignificant in comparison to this buffer factor, and that these packages will easily shield the activities requested in our application.

5.3.2 Material Properties Not Applicable. A shielding model was not used as the primary justification for these packages.

Shieldingjustification was based on direct measurement using Ir-192. Additional radionuclides were justified based on photon emissions using Microshield, Version 7.01 and Version 9.06.

5.4 Shielding Evaluation 5.4.1 Methods Shielding justification for Ir-192 were based on direct measurement. See Test Plan Report 199 # 1 & #2 (see Section 2.12) for results of Ir-192 radiation surveys of the Model 360-1 OW transport packages after testing and Technical Report No. 240 (see Section 5.5.2) for Ir-192 profile results for the other Model 360 Series packages. Shieldingjustification for Ir-192 was based on direct measurement. Radiation shielding information for the package configuration containing Yb-169 or Se-75 were obtained by calculation using Microshield Version 7.01 in Technical Report No. 228 (see Section 5.5.1). Results of these Microshield calculations are shown in the tables in Section 5.1.2. Additional justification for use

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts April 2018 - Revision 5 Page5-ll of the Microshield calculations to support the capacity limits for Yb-169 and Se-75 is provided in Section 5.3.1 and Section 5.5.3.

5.4.2 Input and Output Data Radiation measurements included in this Section were adjusted to the maximum activity capacity for the package (e.g., activity correction factor) and the surface measurements were also adjusted to correct for off-set of the survey meter probe from the true surface of the package.

Activity correction factors (CF A) were obtained by using the following relationship:

Maximum Package Activity Capacity (Ac)

CF = ----------------

A Actual Profile Activity AP For Example if Ap = 270 Ci and Ac = 300 Ci, then CF = 300Ci = 1.1 A

270 Ci Therefore, all original surface and 1 meter profile measurements would be multiplied by a factor of 1.1 for a package profiled using 270 Ci and a package capacity of 300 Ci.

Radiation measurements at the surface of the container were also adjusted to compensate for the off-set of the survey meter probe from the true surface of the package. Surface correction factors (SCF) were obtained by using the following relationship:

SCF = d 2 where d1 and d2 are determined as shown in Figure 5.la.

d1 For Example if d1 = 6 inches and d2 = 6.5 inches then SCF = 6.5.inches = 1.0B 6 inches Therefore, in the example shown, all original surface profile measurements located along the side of the drum shown in Figure 5.a would also be multiplied by a factor of 1.08 to account for surface correction of the detector to the package. Different SCF's would be calculated for the any dimension of the container where the minimum distance from the center of the activity to the center of the radiation probe is different.

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts d2 April 2018 - Revision 5 Page 5-12 distance from activity center to surface of container.

distance from activity center to surface of container plus radius of the survey meter probe.

FIGURE 5.la. SAMPLE SURF ACE CORRECTION FACTOR DISTANCE CRITERIA The radiation profile data showed no increase in radiation dose after testing beyond normal measurement variations. All test specimens met the regulatory requirements.

5.4.3 Flux-to-Dose-Rate Conversion Not Applicable. Flux rates were not used to convert to dose rates in any shielding evaluations.

5.4.4 External Radiation Levels Radiation surveys for the Models 360 Series configurations showed maximum surface and 1 meter radiation levels from the transport packages within regulatory limits. Radiation surveys of Models 360 Series Transport Packages, after undergoing normal and accident condition transport testing, were also well within the regulatory limits.

5.5 Appendix 5.5.1 Technical Report 228 Model 360 Shield Evaluation with Se75 & Ybl69 Revision O dated 1/9/13 5.5.2 Technical Report 240 Model 360 Shield Capacity Evaluations dated 5/21/13 (Minus Append B-G).

5.5.3 Additional Microshield Calculations for the 360-1 OW Package to Determine Equivalent Shielding Effectiveness for Se-75 and Yb-169

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts Section 6 - CRITICALITY EVALUATION April 2018 - Revision 5 Page 6-1 All parts of this section are not applicable. The Models 360 Series Transport Packages are not used for shipment of Type B quantities of fissile material.

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts April 2018 - Revision 5 Page 7-1 Section 7 - Package Operations Operation of the Models 360 Series Transport Packages must be in accordance with the operating instructions supplied with the transport package, per 10 CFR 71.87 and 71.89.

7.1 Package Loading 7.1.1 Preparation for Loading The Model 360 Series transport packages must be loaded and closed in accordance with procedures that, at a minimum, include the requirements specified in this section. Shipment of Type B(U) quantities of radioactive material are authorized for sources specified in Section 7.1.1.1. Maintenance and inspection of these packages is in accordance with the requirements specified in Section 7.1.1.2.

7.1.1.1 Authorized Package Contents Table 7.la: Model 360 Series Package Information Package Isotope Activity Form' Maximum Maximum Maximum Maximum Maximum Shield Source Package Content DU Weight Package Location Capacity2 Capacity2 Weight3 Weight lr-192 Bottom 150 Ci 300 Ci4 0.3 lbs 40 lbs 110 lbs lr-192 Top or Special 135 Ci 270 Ci (138 grams)

(18 kg)

(50 kg) 360-2 Middle Form Se-75 Any Sources 5,000 Ci 5,000 Ci Yb-169 Any 5,000 Ci 5,000 Ci lr-192 Bottom 150 Ci4 600 Ci4 0.6 lbs 55 lbs 130 lbs Ir-192 Top or Special 135 Ci 540 Ci (276 grams)

(25 kg)

(59 kg) 360-4 Middle Form Se-75 Any Sources 5,000 Ci 5,000 Ci Yb-169 Any 5,000 Ci 5,000 Ci lr-192 Any Special 65 Ci 260 Ci 0.6 lbs 155 lbs Se-75 Any Form 5,000 Ci 5,000 Ci (276 grams)

NA (70.3 kg) 360-4W Yb-169 Any Sources 5,000 Ci 5,000 Ci Ir-192 Any Special 150 Ci 1,500 Ci 1.5 lbs 80 lbs 170 lbs Se-75 Any Form 5,000 Ci 5,000 Ci (690 grams)

(36 kg)

(77 kg) 360-10 Yb-169 Any Sources 5,000 Ci 5,000 Ci lr-192 Any Special 17 Ci 170 Ci 1.5 lbs NA 180 lbs Se-75 Any Form 5,000 Ci 5,000 Ci (690 grams)

(82 kg) 360-lOW Yb-169 Any Sources 5,000 Ci 5,000 Ci

'Special Form is defined in 10 CFR 71, 49 CFR 173, and lAEA TS-R-1.

2Maximum activity for lr-192 is defined as output Curies as required in ANSI N432 and IO CFR 34.20 and in line with TS-R-1 and Rulemaking by the USNRC and USDOT published in the Federal Register on 26 January 2004.

3Maximum content weight includes the mass of the radioactive material and the source capsule handling assembly for a shipment containing the maximum number of ource assemblies that can be transported per package design.

4The maximum package capacity may be reduced based on the number sources loaded in the Top or Middle shielded positions within the package.

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts 7.1.1.2 April 2018 - Revision 5 Page 7-2 Packaging Maintenance and Inspection Prior to Loading

a.

Ensure all markings are legible.

b.

Inspect the container for signs of significant degradation. Ensure all welds are intact, the container is free of heavy rust, cracks or damage to the steel housing which breaches the container.

c.

Assure all bolts and fasteners (hardware) required for assembly of the package and as specified on the drawings referenced on the Type B transport certificate are fit for use. Without removing any safety wired hardware by disassembly from the device, examine the visible external surfaces of the bolts/fasteners for any signs of fatigue cracking.

d.

The bolts/fasteners must be replaced if they are no longer fit for use (e.g.,

threads stripped, unable to fully thread, signs of cracking, etc). Assure the cover can be properly secured to the container base in accordance with the drawings referenced on the Type B transport certificate.

e.

Ensure the shipping caps over each source securing mechanism (SSM) can be installed. Assure the locking assemblies actuate freely when performing an operational test and that the lock slides and plunger locks engage and are functional.

f.

If the container fails any of the inspections in steps 7.1.1.2.a-e, remove the container from use until it can be brought into compliance with the Type B certificate.

NOTE:

All components, including fasteners, used on the Model 360 Series transport packages must be replaced by QSA Global, Inc. supplied or approved components. Contact QSA Global, Inc. if any damaged is identified during this inspection or if replacement components are needed to make a compliant Type B(U) shipment.

7.1.2 Loading of Contents NOTE:

These loading operations apply to "dry" loading only. The Model 360 Series transport packages are NOT approved for wet loading.

7.1.2.1 General Pre-transportation Requirements

a.

Ensure the contents are authorized for use in the package.

b. Ensure the package condition has been inspected in accordance with Section 7.1.1.2.

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts April 2018 - Revision 5 Page 7-3

c.

Ensure that the source(s) are secured into place in the storage positions in accordance with the following requirements. Compliance with the following requirements ensures that the sources are securely locked in position before shipment.

1. Removal and installation of radioactive material contained within the shield containers must be performed in a shielded cell/enclosure capable of holding the maximum isotope capacity of the container, or by using remote transfer operations for source holder assemblies.

Container loading can only be performed by persons specifically authorized under an NRC or Agreement State license (or as otherwise authorized by an International Regulatory Authority).

All necessary safety precautions and regulations must be observed to ensure safe transfer of the radioactive material.

2. Using remote handling techniques, load the source assemblies so that they are fully inserted into the source tubes with the active end of the source assembly inserted first.

3. Once the source is loaded, secure the source in place by sliding the lock slide over the assembly, depress the plunger lock on the source securing mechanism (SSM) and install the protective cap over the end of the source assembly. Ensure the key is removed from the plunger lock after the lock is engaged.

NOTE: When loading chain style source assemblies (e.g., TSI or TI-F) into the 360-10 or 360-lOW style containers ONLY, ensure that a jumper extension provided with the package by QSA Global, Inc. is attached to the source assembly connector before securing the source in the package by sliding the lock slide and depressing the lock on the SSM. (Jumper extensions are not required for loading of the 360-2, 360-4 or 360-4W containers)

If a jumper extension is not available at the time of source loading, contact QSA Global, Inc. before loading the source.

DO NOT load a chain source in a 360-10 or 360-lOW style container without using a QSA Global, Inc. provided jumper extension.

Failure to use the proper jumper extension or to load the source chains in these devices without a jumper extension at all will invalidate the package for shipment under the Type B(U) approval.

4. Repeat steps 7.1.2.1.c.2 and 3 if a source will be loaded in another source tube/lock assembly of the device.

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts April 2018 - Revision 5 Page 7-4

5. If additional sources will not be loaded into the package, ensure the lock assembly dust cap cover is installed and the plunger lock is depressed and the key removed. Once all sources are loaded into the transport package, attach the cover assembly to the container base by means of the four captive cover bolts.

7.1.3 Preparation for Transport 7.1.3. l Ensure that all conditions of the certificate of compliance are met including attachment of a tamper indicating seal wire as shown on the drawings referenced on the certificate of compliance.

7.1.3.2 Perform a contamination wipe of the outside surface of the package and ensure removable contamination does not exceed 0.0001 µCi when averaged over a wipe area of 300 cm2*

7.1.3.3 Survey all exterior surfaces of the package to assure that the radiation level does not exceed 200 mR/hr at the surface. Measure the radiation level at one meter from all exterior surfaces to assure that the radiation level is less than 10 mR/hr.

7.1.3.4 Ship the container according to the procedure for transporting radioactive material as established in 49 CFR 171-178.

NOTE:

The US Department of Transportation, in 49 CFR 173.22(c), requires each shipper of Type B quantities ofradioactive material to provide prior notification to the consignee of the dates of shipment and expected arrival.

7.2 Package Unloading 7.2.1 Receipt of Package from Carrier 7.2.1.1 The consignee of a transport package of radioactive material must make arrangements to receive the transport package when it is delivered. If the transport package is to be picked up at the carrier's terminal, 10 CFR 20.1906 requires that this be done expeditiously upon notification of its arrival.

7.2.1.2 Upon receipt of a transport package of radioactive material:

a.

Survey the transport package with a survey meter as soon as possible, preferably at the time of pick-up and no more than three hours after it was received during normal working hours. Radiation levels should not exceed 200 mR/hr at the surface of the transport package, nor 10 mR/hr at a distance of 1 meter from the surface.

b.

Record the actual radiation levels on the receiving report.

c. If the radiation levels exceed these limits, secure the container in a Restricted Area and notify the appropriate personnel in accordance with 10 CFR 20 or applicable Agreement State regulations.

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts April 2018 - Revision 5 Page 7-5

d.

Inspect the outer container for physical damage or leaking. If the package is damaged or leaking or it is suspected that the package may have leaked or been damaged or been tampered with in transit ( e.g., tamper indicating seal is not present or not intact), restrict access to the package. As soon as possible, contact the Radiation Safety Office to perform a full assessment of the package condition and take necessary follow-up actions.

e.

Record the radioisotope, activity, model number, and serial number of the source and the transport package model number and serial number.

7.2.2 Removal of Contents Transfer the package to a remote handling cell, or prepare the package for source transfer to an appropriate exposure device in accordance with the applicable exposure device operating manual and applicable licensing provisions for the user's facility related to radioactive material handling. Remove the sealed source assembly(ies) from the package and transfer to an alternate shielded storage location or container.

7.3 Preparation of Empty Package for Transport In the following instructions, an empty transport package refers to a Model 360 Series transport package without an active source assembly contained within the shielded container. To ship an empty transport package:

7.3.1.

Unload the container in accordance with Section 7.2.2.

7.3.2 Assure that the levels ofremovable radioactive contamination on the outside surface of the transport package does not exceed 4 Bq/cm2 (when averaged over 300 cm2).

7.3.3 Assure that the levels of removable radioactive contamination on the inside surface of the shield container does not exceed 400 Bq/cm2 (when averaged over 300 cm2).

7.3.4 When it is confirmed that the Model 360 Series transport package is empty, prepare the transport package for shipment and survey to ensure the external surface radiation level does not exceed 5 µSv/h.

NOTE: When transporting the Model 360-2, 360-4 or 360-10 transport packages, shipping documentation must reflect the depleted uranium shielding that will be present even if no radioactive source assemblies are to be transported in these containers. (This is not necessary for the Model 360-4 W and 360-1 OW transport packages as they are comprised of tungsten shielding only.)

7.4 Other Operations 7.4.1 Package Transportation By Consignor Persons transporting the Model 360 Series transport packages in their own conveyances should comply with the following:

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts April 2018 - Revision 5 Page 7-6 7.4.1. I For a conveyance and equipment used regularly for radioactive material transport, check to determine the level of contamination that may be present on these items.

This contamination check is suggested if the package shows signs of damage upon receipt or during transport, or if a leak test on the special form source transported in the package exceeds the allowable limit of 185 Bq.

7.4.1.2 If contamination above 4 Bq/cm2 (when averaged over 300 cm2) is detected on any part of a conveyance or equipment used regularly for radioactive material transport, or if a radiation level exceeding 5 µSv/h is detected on any conveyance or equipment surface, then remove the affected item from use until decontaminated or decayed to meets these limits.

7.4.2 Emergency Response In the event of a transport emergency or accident involving this package, follow the guidance contained in "201 6 Emergency Response Guidebook: A Guidebook for First Responders During the Initial Phase of a Dangerous Goods/Hazardous Materials Incident", or equivalent guidance documentation.

7.5 Appendix 7.5.1

Reference:

"201 6 Emergency Response Guidebook: A Guidebook for First Responders During the lnitial Phase of a Dangerous Goods/Hazardous Materials Incident"

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts April 2018 - Revision 5 Page 8-1 Section 8 - ACCEPTANCE TESTS AND MAINTENANCE PROGRAM 8.1 Acceptance Test 8.1.1 Visual Inspections and Measurements Each transport package component is inspected visually prior to shipment for compliance to the following criteria:

8.1.1.1 The transport package was assembled properly to the applicable drawing.

8.1.1.2 Evaluate each shield container for shielding integrity when used in the applicable Model 360 Series assembly to ensure the transport dose rate requirements are met when the container is loaded to capacity.

8. I.1.3 All fasteners as required by the applicable drawings are properly installed and secured.

8.1.1.4 The relevant labels are attached, contain the required information, and are marked in accordance with 10 CFR 20.1904, 10 CFR 40.13(c)(6)(i), 10 CFR 34, and 10 CFR 71 or equivalent Agreement State regulations.

Visual inspections and measurements will be performed in accordance with a USNRC approved Quality Assurance Program per the requirements of 10 CFR 71.101.

8.1.2 Weld Examinations Weld examinations will be performed in accordance with the applicable drawings requirements and in accordance with QSA Global, Inc.'s USNRC approved Quality Assurance Program No. 0040.

8.1.3 Structural and Pressure Tests Prior to first use as part of a Model 360 Series Transport Package, container structural conformance will be evaluated in accordance with the applicable drawings requirements and in accordance with QSA Global, Inc. 's USNRC approved Quality Assurance Program No. 0040. The containment system is not designed to require increased or decreased operating pressures to maintain containment during transport, therefore pressure tests of package components prior to first use is not required.

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts 8.1.4 Leakage Tests April 2018 - Revision 5 Page 8-2 The source capsules (primary containment) are wipe tested for leakage of radioactive contamination upon initial manufacture and every six months thereafter prior to transfer and/or shipment. The removable contamination must be less than 0.005 microcuries.

The source capsules will also be subjected to leak tests under ISO 9978:1992(E) (or more recent editions). The source capsules are not transported in the Model 360 Series packages if they fail any of these tests.

8.1.5 Component and Material Tests Component and material compliance is achieved in accordance with the requirements in QSA Global, Inc.'s USNRC approved Quality Assurance Program No. 0040.

8.1.6 Shielding Tests The radiation levels at the surface of the Model 360 Series transport packages and at I meter from the surface of these packages are evaluated prior to first transport. This survey, performed in a low background area, involves a slow scan survey of the entire package external surface area as well as one meter from the surface of the container.

This survey is used to identify any significant void volumes or shield porosity which could prevent the finished package from complying with the dose limits in 10 CFR 71.47.

This radiation profile is performed at the time of manufacture of the Model 360 Series containers. For 360 style package designs that have multiple loading positions (e.g., 360-2, 360-4 and 360-4 W) radiation profiles will be performed for sources loaded in both the bottom and the top loading positions to fully characterize the package shielding effectiveness.

Radiation profile surveys are made with the radiation detector housing in contact with the surface of the container and then also at one meter from the surface of the container. The maximum radiation levels, when extrapolated to the rated capacity of the transport package, cannot exceed 200 mR/hr at the surface, nor 10 mR/hr at 1 meter from the surface of the transport package.

Failure of the radiation profile tests for any Model 360 Series container will cause the rejection of the affected Model 360 Series package as a Type B container. Rejected packages, which do not comply with the construction requirements on the applicable drawings referenced on the Type B certificate, or that do not comply with the radiation profile requirements will not distributed as approved Type B(U) packages.

8.1.7 Thermal Tests Not applicable. The source content of the Model 360 Series packages will not adversely affect the package surface temperature, and therefore no additional testing is necessary to evaluate thermal properties of the packaging.

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts 8.1.8 Miscellaneous Tests Not applicable.

8.2 Maintenance Program 8.2.1 Structural and Pressure Tests April 20 I 8 - Revision 5 Page 8-3 Not applicable. Material certification is obtained for Safety Class A components used in the transport package prior to their initial use. Based on the construction of the design, no additional structural testing during the life of the package is necessary if the container shows no signs of defect when prepared for shipment in accordance with the requirements of Section 7 of the SAR. The Model 360 Series packaging systems are not designed to require increased or decreased operating pressures to maintain containment during transport, therefore pressure tests of package components prior to individual shipment is not required.

8.2.2 Leakage Tests As described in Section 8.1.4, "Leakage Tests," the radioactive source assembly is leak-tested at manufacture. In addition, the sources are leak tested in accordance with that Section at least once every six months thereafter if being transported to ensure that removable contamination is less than 0.005 microcuries.

8.2.3 Component and Material Tests The transport package components, including re-usable source chain assemblies intended for re-loading by QSA Global, Inc., are inspected for tightness of fasteners, proper seal wires, and general condition prior to each use as described in Section 7 of this SAR. No additional component or material testing is required prior to shipment.

8.2.4 Thermal Tests Not applicable. The source content of the Model 360 Series packages has no adverse affect on the package surface temperature and therefore no additional testing is necessary to evaluate thermal properties of the packaging prior to shipment.

8.2.5 Miscellaneous Tests Inspections and tests designed for secondary users of this transport package under the general license provisions of 10 CFR 71.17(b) are provided in Section 7.

8.3 Appendix Not applicable.

Safety Analysis Report for the Models 360 Series Transport Packages QSA Global, Inc.

Burlington, Massachusetts Section 9 - Quality Assurance 9.1 U.S. Quality Assurance Program Requirements April 2018 - Revision 5 Page 9-1 Almost all component fabrication (including assembly) is controlled under the QSA Global, Inc.

Quality Assurance Plan approved by the USNRC (approval number 0040) and ISO 9001. Since these packages are designed to transport source assemblies manufactured by QSA Global, lnc. as well as source assemblies which may have been manufactured by other source providers (e.g. the source wire chain assemblies), the manufacture of source assemblies by other source providers would be in compliance with those competitors Quality Assurance programs.

Until March 8, 2018, QSA Global, lnc. made no changes/repairs to competitor's source assemblies other than installing our own source capsules into their manufactured source assemblies. As of March 8, 2018, QSA Global, Inc. purchased the assets for the NTP Radioisotopes (Europe) SA - Belgium (aka NTP) competitor source assemblies. From that date forward, QSA Global, lnc. became the design authority for the NTP source chain assemblies which allows for full service/repair of existing source chain assemblies as well as component fabrication related to new manufacture of these source chain assemblies. All component fabrication (including assembly) for the NTP source chain assemblies became controlled under the QSA Global, Inc. Quality Assurance Plan approved by the USNRC and ISO as of March 8, 2018. For source assemblies not included under this NTP agreement, QSA Global, lnc. makes no changes/repairs to these competitor's source assemblies other than installing our own source capsules into their manufactured source assemblies.

9.2 Canada Quality Assurance Program Requirements Not applicable. This package is originally submitted for certification in the United States and complies with the criteria in Section 9.1.

9.3 Appendix Not applicable.

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