ML21037A014

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Alpha-Omega Services, Inc, Chapter 8, Acceptance Tests and Maintenance Program
ML21037A014
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Site: 07109316
Issue date: 01/31/2021
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Radioactive Material Transport Packaging System Safety Analysis Report 8-1 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 8 ACCEPTANCE TESTS AND MAINTENANCE PROGRAM This chapter describes the acceptance tests and maintenance program to be used for the AOS Transport Packaging System, required by 10 CFR 71, Subpart G [8.1]. The acceptance tests are prescribed to verify materials of construction, fabrication processes, and the transport packages design to adequately meet the regulations, while the maintenance program outlined in this chapter assures the packagings performance during its service life, in full compliance with this SAR.

General information related to the AOS Transport Packaging System given in the early chapters of this SAR. Refer to the drawings in Table 1-5, AOS Transport Packaging System Certification Drawing List -

All Models, for dimensions and materials of construction. Refer to Section 2.3, Fabrication and Examination, for applicable Codes and Standards for design, fabrication, and testing of the AOS Transport Packaging System.

8.1 ACCEPTANCE TESTS Table 8-1 presents a summary of the acceptance test program imposed on the AOS Transport Packaging System. The table is divided into two horizontal regions. The upper region of the table identifies the tests that are imposed to accept the material prior their use in the AOS Transport Packaging System. The lower region of the table identifies the tests that are imposed to verify the adequacy of the materials and/or components to meet their functionality. The vertical axis of the table identifies the type of test to be conducted, while the horizontal axis shows all AOS Transport Packaging System models. The information presented in this table is further detailed in the series of tables that follow. Additional details regarding the material specifications and specific test plans used during fabrication and maintenance follow in subsequent sections of this chapter.

8-2 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Table 8-1. Acceptance Test Matrix Test Type Model AOS-025A AOS-050A AOS-100A AOS-100B AOS-100A-S Acceptance Materials Metals

Foama

a. Formulation tests are conducted upon initial order or formulation change.

Sealb

b. Seal supplier to conduct independent material verification, per its Quality Assurance Program.

Welding Rods

Verification Design Features Foamc c.

Batch tests are conducted upon each batch required to fulfill each impact limiter. Pour tests are conducted upon each pour of every batch.

Containment during fabricationd

d. Pressure test at 150% design pressure 10 CFR 71.85(b) [8.1].

Thermale

e. Thermal test is conducted upon the first unit of each model fabricated. Refer to Subsection 8.1.7.

Mechanical Analytical procedure benchmarked by a Drop test of a transport package 165%-larger than the Model AOS-100A.

Refer to Appendix 2.12.6, Impact (Free-Drop) Test Report.

Containment at assemblyf f.

MSLD He Test at least 2.00E-09 Std atm cm3/sec sensitivity.

Shieldingg

g. Refer to Subsection 8.1.6.

Radioactive Material Transport Packaging System Safety Analysis Report 8-3 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 8.1.1 Visual Inspections and Measurements Visual examinations of all component surfaces, including welds and dimensional inspections, are conducted during packaging fabrication. These inspections, as well any other NDE inspections, are conducted according to approved written procedures. Their objectives are to identify harmful discontinuities or indications (such as overlaps, seams, cracks, porosity, crevices, and excessive oxidation), and to verify that the component or item critical dimensions are met, as specified in the certification drawings. (Refer to Table 1-5, AOS Transport Packaging System Certification Drawing List -

All Models, for a complete list.)

Visual and dimensional inspection results are recorded in accordance with the Purchasers approved Quality Assurance and Fabrication plan. Refer to Subsection 2.3.2, Examination, for additional details.

8.1.2 Weld Examinations All welds within the cask component and impact limiters are visually inspected and liquid-penetrant tested (root and final passes). Also, the weld within the containment boundary must be ultrasonically examined and liquid-penetrant tested. These inspections are conducted to ensure that no cracks, incomplete fusion, nor lack of penetration exist. Parts that do not meet the established criteria are repaired or replaced, in accordance with written procedures issued by the Fabricator and approved by AOS.

The Model AOS-025, AOS-050, and AOS-100 transport packages use an ASME Code corner type C weld.

This weld configuration is presented in Figure 4-2, Typical Corner Cask Cavity Shell Weld Joint Configuration - All Models.

8.1.3 Structural and Pressure Tests In addition to the test described in Subsection 8.1.2, the cask cavity is hydrostatically tested, to verify that the containment boundary can support the Design Pressure, per the requirements of NB6200, Subsection NB,Section III, of the ASME Code [8.2] and [8.3]. The Test Pressure is 1.5 times (1.5x) the Design Pressure. If this test were to fail, each component of the containment boundary must be evaluated and replaced, if necessary.

8-4 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 8.1.4 Leakage Tests The AOS Transport Packaging System casks entire containment boundary is leak-tested per Subsection 8.2.2(b), before its first use, and after its third use. The Periodic Leak test is to be performed in accordance with Subsection 8.2.2(b), every 12 months thereafter. The Leak test procedure shall meet the ANSI N14.5-2014 [8.4] standard. The test uses a mass spectrometer leak detector (MSLD) in an evacuated envelope, with back pressurization technique. This technique consists of creating a 1-atm pressure differential across the boundary, and evacuating outside surfaces of the boundary, at critical locations (such as penetrations and seal joints) with the MSLD. The evacuated gases are passed through the instruments spectrum portion to detect, quantitatively, the presence of gas, typically helium, used in the pressurization of the containment boundary. The criteria that is required to be met to establish the containment boundarys leak-tightness is 10-7 atm cm3/sec or less, based upon dry air at 25°C (32°F) and for a pressure differential of 1 atm. The MSLD instrument must be sensitive to at least a 10-9 atm cm3/sec reading.

Critical locations within the AOS Transport Packaging System are the cask lid seal joint, cask drain port, and cask vent port. These locations are tested by connecting the test probe to the test port that is located between the seals two (2) seal rings (in the case of the seal joint) and port cover areas, and then determining the leak rate. If the leak-tightness criterion, per Reference [8.4], is not met, the containment boundary is checked, damaged components1 (such as a seal or pipe plug) are replaced, and the unit is re-tested.

8.1.5 Component and Material Tests 8.1.5.1 Valve, Rupture Disks, and Fluid Transport Devices Not applicable. Component tests of valve, rupture disks, and/or fluid transport devices are not applicable, because these components do not exist in the AOS Transport Packaging System.

8.1.5.2 Materials Materials and testing requirements are denoted in Table 8-2 through Table 8-7. Materials are selected and tested in accordance with these specifications, following the approved Manufacturing and Fabrication Quality Assurance Plan when packages are manufactured or repaired.

With respect to FR-3700 series foam, Table 8-6 and Table 8-7 list the maximum value limits for acceptance of the foam formulation test results. These values include the +15% variation resulting from the manufacturing process.

Radioactive Material Transport Packaging System Safety Analysis Report 8-5 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Table 8-2. Type 304 and 316 Material Requirements Definition Requirements Test Frequency Remarks Base Specification Suffix W ASME SA-479/ASTM A 479 Type 304 Bar and Shapes Suffix W1 ASME SA-479/ASTM A 479 Type 316 Bar and Shapes Suffix X ASME SA-312/ASTM A 312, Grade TP 304 Pipe Suffix X1 ASME SA-312/ASTM A 312, Grade TP 316 Pipe Suffix Y ASME SA-182/ASTM A 182, Grade F 304 Forgings Suffix Y1 ASME SA-182/ASTM A 182, Grade F 316 Forgings Suffix Z ASME SA-240/ASTM A 240, Type 304 Plate, Sheet, and Strip Suffix Z1 ASME SA-240/ASTM A 240, Type 316 Plate, Sheet, and Strip Chemistry Modification C 0.050 (all suffixes)

Na One Chemical Analysis Required per Heat Heat Treatment Inventory Material - 1,040°C (1,900°F),

minimum, in accordance with the Base Specification.

New Wrought Material - 1,040 to 1,149°C (1,900 to 2,100°F) for 15 minutes/25 mm (15 minutes/1 in.) of thickness, but not less than 15 minutes.

All Materials - Alternate quenching methods require prior AOS approval.

One per Heat and Heat Treat Lot Certification Statement Descaling (Oxide Removal)

Pickling is conducted in accordance with Treatment Code A of ASTM A380.

Other descaling methods are permitted with prior AOS approval.

After final solution heat treatment Mechanical Tests Properties at Room Temperature, as required by the Base Specification.

One per Heat and Heat Treat Lot After final solution heat treatment Hardness Test Not to exceed Rockwell B90, per ASTM A370.

One per Heat and Heat Treat Lot After final solution heat treatment

8-6 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Sensitization Test ASTM A262 Practice A - Modified -

Material having ditching greater than 5%

is unacceptable. Can be waived by AOS for material not exposed to reactor water environments at elevated temperatures for extended periods of time.

Inventory Material -

10% of Supplied Pieces New Material -

One per Heat and Heat Treat Lot After final solution heat treatment Intergranular Attack Surface sample after pickling or if pickling is not used after final heat treatment -

IGA or pitting in excess of 0.025 mm (0.001 in.) deep is unacceptable.

Inventory Material -

10% of Supplied Pieces New Material -

One per Heat and Heat Treat Lot After final solution heat treatment and oxide removal (if applicable)

Non-Destructive Examination As required by the Base Specification and/or applicable ASME Section III requirements (References [8.2]

and [8.3]).

100%

a. Nitrogen can be added, as necessary (up to the limits of the Base Specification), to achieve mechanical properties.

Table 8-2. Type 304 and 316 Material Requirements (Continued)

Definition Requirements Test Frequency Remarks

Radioactive Material Transport Packaging System Safety Analysis Report 8-7 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Table 8-3. Bolting/Screw Material Requirements Definition Requirements Test Frequency Remarks Base Specification Suffix W ASME SA-193, Grade B6 UNS S41000 Screw materials Suffix Z ASME SB-637, UNS N07718 Bolting materials Chemistry Modification (Weight %)

No modification. Chemistry as required by the Base Specification.

One Chemical Analysis

Required, per Heat Heat Treatment As required by the ASME Specification.

One per Heat and Heat Treat Lot Certification Statement Mechanical Tests As required by the ASME Specification.

One per Heat and Heat Treat Lot After heat treatment, per ASME SA370 Hardness Test As required by the ASME Specification.

One per Heat and Heat Treat Lot After final heat treatment Sensitization Test Test not required.

Intergranular Attack (IGA)

Surface sample after pickling, or if pickling is not used, after final heat treatment. IGA or pitting in excess of 0.025 mm (0.001 in.) deep is unacceptable.

After Pickling AOS to approve sampling plan Weld Repair Weld repair is not permitted on bolting materials.

Non-Destructive Examination As required by Code, as a minimum.

100%

8-8 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Table 8-4. Casting Pipe/Casting Material Requirements (Type CPF-8, CF-8)

Definition Requirements Test Frequency Remarks Base Specification Suffix T ASME SA-451/ASTM A 451 Grade CPF8 Cast Pipe Suffix U ASME SA-351/ASTM A 351 Grade CF8 Casting Chemistry Modification As required by the ASME Specification.

One Chemical Analysis Required per Heat Ferrite Content Controlled within the allowable limits of the Base Specification, to produce a minimum ferrite content of 5%, as determined magnetically by Practice ASTM A800, S1.

One Analysis Required per Heat and Heat Treat Lot Ferrite to be measured on an actual casting, after final solution heat treatment Heat Treatment Solution Heat Treat at 1,066 to 1,149°C (1,950 to 2,100°F) for 15 minutes/25 mm (15 minutes/1 in.)

of thickness, but not less than 15 minutes, in accordance with the Base Specification.

One per Heat and Heat Treat Lot Certification Statement Mechanical Tests Properties at Room Temperature, as required by the Base Specification.

One per Heat and Heat Treat Lot After final solution heat treatment Hardness Test As required by the Base Specification.

One per Heat and Heat Treat Lot After final solution heat treatment Sensitization Test Not required.

Intergranular Attack (IGA)

Surface sample after pickling or if pickling is not used after final heat treatment. IGA or pitting in excess of 0.025 mm (0.001 in.)

deep is unacceptable.

Inventory Material - 10% of Supplied Pieces New Material -

One per Heat and Heat Treat Lot After final solution heat treatment and oxide removal (if applicable)

Non-Destructive Examination As required by the Base Specification, Radiography per NB-2575, and additional applicable requirements of ASME Section III (References [8.2] and [8.3]).

100%

Weld Repair Procedures require AOS approval prior to performance of the repair work.

Repairs to castings subsequent to solution annealing must be documented and submitted to AOS.

Buyer approval required for repair procedure

Radioactive Material Transport Packaging System Safety Analysis Report 8-9 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Cleaning/Surface Preparation Surfaces shall be visibly free of miscellaneous processing materials and essentially free of contaminants of concern, including chlorides, fluorides, sulfur, bromides, lead, mercury, and other low-melting-point metals. Water used for cleaning must meet the following requirements:

Final cleaning must be conducted with demineralized water, and can be conducted by the Fabricator.

All Materials Table 8-4. Casting Pipe/Casting Material Requirements (Type CPF-8, CF-8) (Continued)

Definition Requirements Test Frequency Remarks Attribute Potable Water Demineralized pH at 25°C (77°F) 5.5 to 8.0 5.5 to 8.0 Chlorine, ppm

< 35

< 1 Fluorine, ppm

< 10

< 1 Sulfide, ppm

< 1

< 1 Silica

< 0.05 ppm Conductivity µS/cm

< 3

8-10 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Table 8-5. LAST-A-FOAM FR-3700 Series Foams - Testing Program Type of Testa Test Description Applicable Reference Number of Samples Nominal Value Tolerance (of Nominal)

Sample size (in.)

Formulation

Density, pcf ASTM D1622-03 3

18, 8, and 11b Each +/-15%

Increment +/-10%

2 x 2 x 1 Static Crush

Strength, psic General Plastics Manufacturing
Company, TM-9704, Rev. K 3d Report Value Report Value 1 x 1 x 1 and 2 x 2 x 2 Flame Retardancy ASTM D1622-03 3

Burn length 6 in.

0.5 x 3 x 6+

Intumescence General Plastics Manufacturing

Company, 9952037-00 and TM-9704, Rev. K 2

50%

Minimum 2 x 2 x 2 Leachable Chlorides General Plastics Manufacturing

Company, GP-TM9510, Rev. B and EPA 300.0 1

1 ppm

< 1 ppm 2 x 2 x 2 Thermal Conductivity, Btu-in/(ft2-°F-h)

ASTM D1622-03 1

0.349 Each +/-15%

8.0 diameter x 1.0 L Specific Heat, Btu/lb-°F ASTM E1269-05 1

0.351 Each +/-20%

As Required Water Absorption ASTM E1269-05 3

0.05 lbs. of water per ft2 in 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> Not to exceed nominal 6 x 6 x 3 Chemical Composition 1 per formulation Report Value Report Value As Required

Radioactive Material Transport Packaging System Safety Analysis Report 8-11 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Batch

Density, pcf ASTM D1622-03 3

18, 8, and 11b Each +/-15%

Increment +/-10%

2 x 2 x 1 Static Crush

Strength, psie General Plastics Manufacturing
Company, TM-9704, Rev. K 3f General Plastics Manufacturing
Company, Technical Specification Increment +/-15%

2 x 2 x 1 Flame Retardancy 14CFR14.25.853 3

Burn length 6 in.

0.5 x 3 x 6+

Intumescence General Plastics Manufacturing

Company, 9952037-00 and GP-TM9510, Rev. B 3

50%

Minimum 2 x 2 x 2 Leachable Chlorides General Plastics Manufacturing

Company, GP-TM9510, Rev.

B & EPA 300.0 2

1 ppm

< 1 ppm 2 x 2 x 2 Pour Static Crush

Strength, psie General Plastics Manufacturing
Company, TM-9704, Rev. K 3f General Plastics Manufacturing
Company, Technical Specification Increment +/-15%

2 x 2 x 1

Density, pcf ASTM D1622-03 3

18, 8, and 11b Each +/-15%

Increment +/-10%

2 x 2 x 1

a. Formulation tests are conducted upon initial order or formulation change. Batch tests are conducted upon each batch required to fulfill each impact limiter. Pour tests are conducted upon each pour of every batch.
b. Density nominal values of 18, 8, and 11 pcf are associated with the Model AOS-025, AOS-050, and AOS-100, respectively.

c.

The foam manufacturer will perform the Static Crush Strength test. In addition, a dynamic test will be performed by an independent testing laboratory as part of the Dedication Process toward a safety Category A. The dynamic test shall be per ASTM D1621-10, and will follow the recommendation of this Standard, with the exception of the strain rate. The test will use a controlled dynamic strain rate of 60s-1. The values obtained from this test must be less than or equal to the corresponding values in Table 8-6 and Table 8-7.

d. Three (3) samples are tested at -40, 75, and 250°F, at strains of 10, 40, and 60% in each direction; Parallel to Direction of Rise and Perpendicular to Direction of Rise.
e. Strain Rate value for this test is approximately 0.14 in./min. Each sample shall meet the tolerance for the indicated test. In cases where multiple samples are taken, the indicated tolerance applies to the numerical average result of the samples. For example, the results of each Static Crush test must be +/-20% of the nominal value, and the average of the three samples must be +/-15% of the nominal value.

f.

Three (3) samples are tested at 75°F, at strains of 10, 40, and 60% in each direction; Parallel to Direction of Rise and Perpendicular to Direction of Rise.

Table 8-5. LAST-A-FOAM FR-3700 Series Foams - Testing Program (Continued)

Type of Testa Test Description Applicable Reference Number of Samples Nominal Value Tolerance (of Nominal)

Sample size (in.)

8-12 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Table 8-6. LAST-A-FOAM FR-3700 Series Foam Dynamic Crush Strength Limits, Parallel to Rise - All Models Temp Model AOS-025 AOS-050 AOS-100 at -28.9°C

(-20°F)

Stress (psi)

Strain (in/in)

Stress (psi)

Strain (in/in)

Stress (psi)

Strain (in/in) 2,556 0.1 608 0.1 994 0.1 2,459 0.2 616 0.2 930 0.2 2,558 0.3 630 0.3 964 0.3 2,840 0.4 660 0.4 1,028 0.4 3,411 0.5 750 0.5 1,195 0.5 0.6 974 0.6 1,542 0.6 0.65a

a. The 65% values have been included for the completeness of data from General Plastics publications (Reference [8.8]); however, in the testing program, the 65% strain rate test is not conducted.

1,260 0.65a 1,983 0.65a at 23.9°C (75°F)

Stress (psi)

Strain (in/in)

Stress (psi)

Strain (in/in)

Stress (psi)

Strain (in/in) 1,893 0.1 471 0.1 736 0.1 1,849 0.2 453 0.2 699 0.2 1,938 0.3 477 0.3 730 0.3 2,168 0.4 512 0.4 785 0.4 2,604 0.5 595 0.5 912 0.5 0.6 761 0.6 1,186 0.6 0.65a 977 0.65a 1,549 0.65a at 126.7°C (260°F)

Stress (psi)

Strain (in/in)

Stress (psi)

Strain (in/in)

Stress (psi)

Strain (in/in) 757 0.1 212 0.1 294 0.1 740 0.2 199 0.2 280 0.2 795 0.3 219 0.3 299 0.3 911 0.4 241 0.4 330 0.4 1,068 0.5 286 0.5 374 0.5 0.6 373 0.6 510 0.6 0.65a 479 0.65a 666 0.65a

Radioactive Material Transport Packaging System Safety Analysis Report 8-13 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Table 8-7. LAST-A-FOAM FR-3700 Series Foam Dynamic Crush Strength Limits, Perpendicular to Rise - All Models Temp Model AOS-025 AOS-050 AOS-100 at -28.9°C

(-20°F)

Stress (psi)

Strain (in/in)

Stress (psi)

Strain (in/in)

Stress (psi)

Strain (in/in) 2,632 0.1 586 0.1 913 0.1 2,559 0.2 598 0.2 894 0.2 2,628 0.3 642 0.3 928 0.3 2,935 0.4 660 0.4 1,013 0.4 3,432 0.5 748 0.5 1,169 0.5 0.6 1,012 0.6 1,528 0.6 0.65a

a. The 65% values have been included for the completeness of data from General Plastics publications (Reference [8.8]); however, in the testing program, the 65% strain rate test is not conducted.

1,341 0.65a 1,978 0.65a at 23.9°C (75°F)

Stress (psi)

Strain (in/in)

Stress (psi)

Strain (in/in)

Stress (psi)

Strain (in/in) 1,964 0.1 444 0.1 681 0.1 1,924 0.2 443 0.2 672 0.2 1,991 0.3 479 0.3 703 0.3 2,207 0.4 500 0.4 762 0.4 2,640 0.5 567 0.5 899 0.5 0.6 761 0.6 1,194 0.6 0.65a 1,001 0.65a 1,595 0.65a at 126.7°C (260°F)

Stress (psi)

Strain (in/in)

Stress (psi)

Strain (in/in)

Stress (psi)

Strain (in/in) 766 0.1 200 0.1 266 0.1 750 0.2 199 0.2 262 0.2 796 0.3 225 0.3 281 0.3 905 0.4 240 0.4 312 0.4 1,082 0.5 272 0.5 369 0.5 0.6 365 0.6 478 0.6 0.65a 480 0.65a 638 0.65a

8-14 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 8.1.5.3 Seal Testing The testing conducted upon the seal during its fabrication is based upon the manufacturers QA system requirements to produce a Safety Classification A Component [8.7].

8.1.5.4 Fabrication Table 8-8 summarizes the AOS Transport Packaging System Fabrication examination program.

8.1.6 Shielding Tests The AOS Transport Packaging System models use either tungsten alloy or carbon steel as their shielding material. Conducting a 100% UT examination, as well as dimensional and density checks of the shielding material, provide the necessary inspection processes for verifying the shielding attribute of these materials. As an optional additional test, prior to the first use of the transport package, a Co-60 source can also be used. The source is placed inside the cask cavity, and its outside surface is surveyed with a gamma detection instrument. The source strength must be high enough to generate an external reading consistent with the capability of the survey instrument. Equally spaced meridian and circumferential lines, along the vertical axis, divide the cask outside surface into approximately 10 x 10 cm (4 x 4 in.) squares.

Dose rate readings are taken over each corner and center of the square area created by these lines.

To verify the cask shielding material integrity, the measured dose rates should closely match the anticipated values from shielding/dose rate calculations, and large, unanticipated deviations should not exist between measurements.

Table 8-8. Fabrication Examination Program Summary Test Category Test Type Reference Test Description Component Adherence to Drawing Certification Drawings. Refer to Table 1-5, AOS Transport Packaging System Certification Drawing List - All Models.

Visual and Dimensional inspections.

Sub-assembly Assembly Pressure and Containment ASME Code,Section V, and applicable requirements of NB-6112,Section III, and ANSI N14.5, Section 7.3.

Pneumatic and Leakage test, per Reference [8.4].

Weldment NDE ASME Code,Section V, and applicable requirements of NX-5000,Section III.

Visual, Penetrant, and Ultrasonic tests (VT, PT, and UT, respectively).

Radioactive Material Transport Packaging System Safety Analysis Report 8-15 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 8.1.7 Thermal Tests The thermal test is conducted upon the AOS Transport Packaging Systems cask component, to verify that the casks temperature distribution is similar to the analytical models predicted temperature distribution.

Temperature variations are acceptable, as long as the test results are within 15% of the values predicted by the analytical model. The test is conducted upon the first unit produced of each AOS Transport Packaging System model (Models AOS-025, AOS-050, AOS-100A, AOS-100B, and AOS-100A-S). The new analytical models developed for this test must have the same component arrangement as that of the test prototype, to allow a direct comparison of results.

The selection of using only the transport packages cask component as the thermal test prototype is based upon its geometrical design and the materials used. The cask design consists of two concentric shells, creating an internal hollow space occupied by a series of rings or solid cylinder components. The shells are comprised of 300 series stainless steel material. The rings or solid cylinders are comprised of tungsten alloy or carbon steel. There are gaps and contact resistance areas created by the manufacturing and/or assembly of the cask components. The gaps can be occupied either by air or packed stainless steel wool.

Understanding the heat transfer characteristic across these boundaries is essential to the accuracy of the analytical model. Furthermore, the cask component houses the transport package contents and containment boundary. The heat transfer characteristic across the boundaries between the cask and inner surface of the impact limiter, outside surface of the impact limiter, and exposed cask section are, in general, well-defined. Therefore, these characteristics can be modeled with few problems in a general-purpose computer code, and are not required to be verified by testing.

The thermal test consists of concentrically placing an electrical heat source, equal to the AOS Transport Packaging System models maximum decay heat within its cask cavity. (Refer to Table 3-2, Contents Decay Heat - All Models.) Temperature-sensing devices are strategically placed (refer to Figure 8-1):

At various locations within the cask cavity On exterior surfaces of the cask In the environment surrounding the cask The packaging undergoing test is placed within a pit or closed room, to minimize outside effects that can be caused by the surrounding environment. The heat source is turned on, to a value equal to or greater than the decay heat value of the radioactive content proposed for the cask. Temperature data is recorded at a minimum interval of one (1) minute during the transient event, until the cask reaches a steady state and remains significantly unchanged for approximately one (1) hour. This completes the heating cycle.

Thereafter, the heat source is turned off, to allow the cask to cool down. The cool-down cycle is also recorded, as in the previous cycle.

Refer to Appendix 3.5.8, Heat Test Report - AOS-165A Prototype, for a detailed discussion and results of this test, when conducted upon a 165%-larger package version of the Model AOS-100A.

8-16 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 8-1. Typical Thermal Test Setup Notes:

The numbered red dots in Figure 8-1 represent thermocouple locations.

The cask lid plug component is removed, to allow the heater power wire to exit the cask body.

8.1.8 Miscellaneous Tests No additional tests, other than those described in this chapter, are conducted on the AOS Transport Packaging System prior to it being placed into service.

(15)

SK06059 (12.000 in. Minimum)

L (5)

(12) 0.250D 0.165L 0.500L 0.830L (13)

(6)

(3)

(16)

(10)

(9)

(11)

(14)

(4)

(7)

(8)

(2)

(1)

D 0.500D

Radioactive Material Transport Packaging System Safety Analysis Report 8-17 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 8.2 MAINTENANCE PROGRAM The cask maintenance program is described, in detail, in an Engineering Specification provided to all AOS Transport Packaging System users. This Specification shall implement the requirements established in this chapter. Packaging System operators can develop procedures of their own, to include site-specific requirements, if they remain within the Engineering Specification requirements.

Pre-shipment Inspections are conducted prior to each shipment. These inspections include visual checks of the packaging and any support structure(s) or device(s) required to properly assemble the transport package. They might also include pressurization of the cask cavity, which is part of the Leak test for Normal Form content. Additionally, more detailed inspections are conducted annually, or prior to being used after a storage period of more than one (1) year, as detailed in Subsection 8.2.2(b). Pre-shipment Leak tests are conducted only when shipping Normal Form material.

8.2.1 Structural and Pressure Tests The only periodic pressure test performed on the AOS Transport Packaging System is the Leak test detailed in Subsection 8.2.2(b).

8.2.2 Leakage Tests [8.4]

Prior to leak testing, the cask lid seal, sealing surfaces, cask lid attachment bolts, and seal attachment screws must be inspected for damage such as scratches, dents, dirt, and oil residue. Also, the female thread holes for the cask lid attachment bolts and seal attachment screws must be checked. After completing the inspection, and repairing or replacing any damaged components, the seal is installed on the cask lid groove by the four (4) seal attachment screws, as illustrated in Figure 8-2 for the cask lid metallic seal, which also shows the location of the leak-testing hole.

Note: Elastomeric O-Rings must be visually inspected for cuts, blemishes, debris, and/or permanent local deformation on the sealing surface. Damaged seals must be replaced. Elastomeric O-Rings must be replaced every 12 uses or once per year, whichever comes first.

a.

Pre-shipment Leak Testing Pre-shipment leak testing must be performed before each shipment, after the content is loaded and the containment system is assembled. Perform the test as described in Paragraph 7.1.3.3.

b.

Periodic Leak Testing Periodic leak testing must be performed annually, or prior to the transport package being used, after a storage period of more than one (1) year, or prior to returning to service after repairs (such as weld repair) and/or replacing containment components. The cask lid seal, vent and drain threaded pipe plugs, and the port plug conical seal must be leak-checked with a helium MSLD. This instrument has a sensitivity of < 1 x 10-9 ref-cm3/sec (helium). Conduct this test by pressurizing the cask cavity to one (1) atm pressure differential across the boundary to be tested (verified with a double pressure gauge), then use the MSLD to test all components of the containment boundary for leaks. If leakage greater than 2 x 10-7 ref-cm3/sec helium at standard conditions is detected, repair or replace the damaged component(s), then re-test for leakage, to the same criteria as previously tested.

Note: For shipments of Special Form material, a Periodic Leak Test is not necessary after replacement of an elastomeric cask lid seal, provided that a Periodic Leak Test has been performed on the casks containment system within the past 12 months.

8-18 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

Figure 8-2. Cask Lid Showing the Cask Lid Metallic Seal Installed -

Attachment by way of Four (4) Screws, and Leak-Testing Hole Hole Used for Leak Testing Cask Lid Metallic Seal Attachment Screws (4 places, evenly spaced around seal)

Radioactive Material Transport Packaging System Safety Analysis Report 8-19 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 8.2.3 Component and Material Tests The AOS Transport Packaging System does not have any auxiliary cooling systems nor other subsystems that require maintenance other than those mentioned herein.

8.2.4 Thermal Tests Thermal testing is conducted to verify the heat transfer characteristics of the AOS Transport Packaging Systems cask component, as described in Subsection 8.1.7. No additional maintenance-related tests are conducted, because the materials of construction are stable, and routine operating procedures monitor the integrity of the transport packages thermal performance.

8.2.5 Miscellaneous Tests No additional tests are conducted upon the AOS Transport Packaging System models other than those described within this chapter.

8-20 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316) 8.3 APPENDIX (NONE)

Radioactive Material Transport Packaging System Safety Analysis Report 8-21 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

8.4 REFERENCES

[8.1]

U.S. Nuclear Regulatory Commission (NRC), Title 10, Code of Federal Regulations, Part 71 (10 CFR 71), Packaging and Transportation of Radioactive Material.

[8.2]

American Society of Mechanical Engineers, ASME Boiler and Pressure Vessel Code,Section III, Division 1, 2004, No Addenda.

[8.3]

American Society of Mechanical Engineers, ASME Boiler and Pressure Vessel Code,Section III, Division 3, 2004, No Addenda.

[8.4]

American National Standards Institute, ANSI N14.5-2014, Radioactive Materials -

Leakage Tests on Packages for Shipment, June 19, 2014.

[8.5]

International Atomic Energy Agency (IAEA) Safety Standards Series No. TS-R-1 (IAEA TS-R-1), Regulations for the Safe Transport of Radioactive Material, 1996 Ed.

(as amended 2003).

[8.6]

U.S. Nuclear Regulatory Commission (NRC), Title 10, Code of Federal Regulations, Part 71 (10 CFR 71), Packaging and Transportation of Radioactive Material.

[8.7]

NUREG/CR-6407, Classification of Transportation Packaging and Dry Spent Fuel Storage System Components According to Importance to Safety, Idaho National Engineering Laboratory, Idaho Falls, Idaho, February, 1996.

[8.8]

General Plastics Manufacturing Company, Design Guide for Use of LAST-A-FOAM FR-3700 for Crash & Fire Protection of Radioactive Material Shipping Containers, Tacoma, WA, March, 1998 (revised October, 2003).

8-22 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J, January 31, 2021 (Docket No. 71-9316)

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