ML21118A962

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Alpha-Omega Services, Inc., Request to Amend Certificate of Compliance 9316
ML21118A962
Person / Time
Site: 07109316
Issue date: 04/28/2021
From: Hedger T
Alpha-Omega Services
To: Pierre Saverot
Document Control Desk, Office of Nuclear Material Safety and Safeguards
References
1-042021-015, EPID L-2021-LLA-0071, FM9006
Download: ML21118A962 (32)


Text

9156RoseStreetP.O.Box789Bell"ower,California,U.S.A90706 CustomerService(800)3467894(562)8040604Fax:(562)8040610 www.alphaomegaserv.com April 28, 2021 U.S. Nuclear Regulatory Commission Attn: Document Control Desk / Mr. Pierre Saverot - STLB Director, Division of Fuel Management - DFM Office of Nuclear Material Safety and Safeguards - NMSS 11555 Rockville Pike One White Flint North Rockville, MD 20852

SUBJECT:

AOS REQUEST TO AMEND CERTIFICATE OF COMPLIANCE 9316 USNRC

Reference:

EPID L-2021-LLA-0071, Docket No. 71-9316 AOS

Reference:

FM9006.1-042021-015 Mr. Saverot:

Alpha-Omega Services, Inc. (AOS) would like to request the amendment of Certificate of Compliance No. 9316.

Our amendment request includes several minor changes, as described below.

1.

Expand the justification of the radiation resistance of elastomeric seals in Section 2.2.3 Effects of Radiation on Materials. The revised justification relates specifically to the elastomeric cask lid seals.

2.

Revise the pressure evaluation under NCT to include the slight pressure due to backfilling with Helium after leak testing. The new evaluation does not change the Design Pressure and therefore does not change the analyses that evaluate the effects of pressure inside the cask. This change affects pages in Chapters 1, 2, 3 and 4.

3.

Revise Chapter 7, Package Operations and Chapter 8, Acceptance Tests and Maintenance Program to make some clarifications. The changes relate to leak testing and vacuum drying and are associated with our recent Part 71.95 report - being submitted concurrent with this request.

Attached for your review are the revised pages from SAR FM9054 Revision J-1 and the assiocated list of changes.

Best Regards, Troy Hedger, President Alpha-Omega Services, Inc.

Attachments:

SAR AOS-FM9054 Rev J-1 (21 pages)

List of Changes to SAR AOS-FM9054 (10 pages)

AOS-FM9054 Rev. J-1, April 20, 2021 (Docket No. 71-9316)

Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages Prepared by Alpha-Omega Services, Inc.

Bellflower, CA

J January 31, 2021 Consolidation of Revisions H - H7 (Revision I intentionally skipped)

Subsection 1.2.2 and Section 7.1 - Clarified that the shoring materials are structural Paragraphs 2.5.3.1.2 through 2.5.3.1.4 - Calculations revised to correct minor errors and typos Subsection 2.6.7 - Removed stale note created in Revision H-5 Figures 3-18 through 3 Replaced thermal transient plots for AOS Model-025 fire condition Figure 4 Changed port cover torque requirement Chapter 9 - Updated with current requirements, approval letter, and certificate Updated ANSI N14.5 references to 2014 edition Applied miscellaneous corrections (table of changes included with cover page of the submittal)

J-1 April 20, 2021 Revised Subsection 1.2.2 (added discussion related to cask loading temperature and backfilling pressure)

Revised Subsection 2.2.3 (expanded discussion related effects of radiation),

Paragraph 2.6.1.1 (revised initial conditions for NCT pressure calculations),

Table 2-31 and Table 2-54 (omitted footnotes b and c, respectively; updated calculated pressures); added new Reference [2.35]

Revised Subsection 3.2.2 (update calculated NCT pressures and elaborate on initial conditions and mechanisms that can increase internal cask pressure)

Revised Table 4-6 and Table 4-7 (omitted footnotes b and c, respectively; revised pressure calculations based on updated initial conditions)

Revised Paragraph 7.1.3.1 (revised instructions for wet-loading cask),

Figure 7-4 (updated to reflect current equipment), and Paragraph 7.1.3.3 (revised leak testing procedure)

Revised Table 8-1 footnote (clarified test procedure sensitivity),

Subsection 8.1.4 (revised fabrication leak testing requirements), Section 8.2 (removed statement regarding pre-shipment leak testing because this belongs in Chapter 7), Subsection 8.2.2 (updated leak testing requirements)

Revision Date Description of Changes

Radioactive Material Transport Packaging System Safety Analysis Report 1-13 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J-1, April 20, 2021 (Docket No. 71-9316)

Radioactive contents are limited by the external radiation levels specified in 10 CFR 71.47 and 71.51 [1.1],

and 49 CFR 173.441 [1.3]. Exclusive-Use mode of shipment is required whenever the radiation dose rates of the package exceed the external radiation standards in 10 CFR 71.47(a) [1.1] for non-exclusive use shipment. For Models AOS-100A and AOS-100A-S, when shipped as exclusive use, the activity limits for each isotope are specified in Table 1-2b.

There are no materials added to the package for the purpose of neutron absorption nor moderation.

Radiation shields (that is, liners, axial shielding plates, and/or cavity spacer plates) are required in certain cases, as stipulated in Table 1-2, Table 1-2a, and Table 1-2b.

The construction materials of the AOS Transport Packaging System and their proposed contents are compatible with one another; no chemical nor galvanic reactions are expected to occur, including the generation of combustible gas.

The transport packages shall be loaded under ambient atmospheric pressure and temperature conditions. The cask may have a slight internal pressure due to backfilling with air or an inert gas and internal heating of the enclosed gases can increase the pressure. The cask is normally loaded at room temperature; however, for evaluating the temperature contribution to the pressurization of the cask cavity, the loading temperature will be conservatively assumed to be 50°F. The pressure inside the containment boundary is evaluated in Subsection 4.2.2.

The maximum gross weight of the AOS Transport Packaging System, including contents, is listed in Table 1-1.

The maximum decay heats, listed in Table 1-2, Table 1-2a, and Table 1-2b, are calculated using the constants presented in Chapter 5, Shielding Evaluation.

Radioactive Material Transport Packaging System Safety Analysis Report 2-37 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J-1, April 20, 2021 (Docket No. 71-9316)

The casks fabrication process excludes any moisture (electrolyte) from being present within the cask.

During shipment (jointed unit), the cavity must be dry, regardless of how it was loaded. If the cavity was loaded in water, the cavity must be vacuum-dried. Following this procedure eliminates the presence of the electrolyte, one of the factors for galvanic interaction. Refer to Paragraph 7.1.3.1, Securing the Cask Lid, for the vacuum drying procedure.

Possible galvanic interaction is eliminated by controlling the potential difference for both permanent and temporary dissimilar metal joints, and by preventing the presence of an electrolyte, during fabrication and shipment.

2.2.3 Effects of Radiation on Materials The AOS Transport Packaging Systems cask component is comprised of the following construction materials:

300 series stainless steel (SS300), tungsten alloy or low carbon steel alloy for the cask body, cask lid, and cask lid plug components Nickel alloy for the cask lid attachment bolts Silver, nickel-chromium alloy, and stainless steel for the cask lid metallic seal Silicone material for the O-Rings used in the cask lid elastomeric seal and port cover Of these materials, the one most affected by radiation is the silicone material. The port cover O-Ring components are not a part of the containment boundary and are used only to seal the port cover to prevent debris from entering the port plug area. Furthermore, these items are visually inspected for damage, deterioration, and wear, and are replaced as needed.

The cask lid elastomeric seal is part of the containment boundary and is exposed to gamma radiation that can cause compression set. The expected maximum dose rate in the cask lid seal region is 1 rad/hr.

After one year of continuous use, this would result in a total dose of 1 x 104 rad. However, at a dose of 1 x 106 rads, the radiation effect on elastomers is minor. It is not until the radiation is delivered in doses within the range of 1 x 107 rad that radiation is a concern for O-Ring compounds (Reference [2.35]).

Therefore, radiation is not a concern because the cask lid elastomeric seals are replaced after every 12 uses or annually, whichever comes first.

The impact limiters are constructed of 300 series stainless steel and polyurethane foam materials. The effect of radiation upon the stainless steel material is minimal. Also, according the manufacturers data for the polyurethane foam (Reference [2.13]), its material does not incur any physical property changes when subjected to a maximum cumulative dose of 2 x 108 rads. Therefore, the impact limiters are not affected by radiation.

Radioactive Material Transport Packaging System Safety Analysis Report 2-75 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J-1, April 20, 2021 (Docket No. 71-9316) 2.6.1.1 Summary of Pressures and Temperatures Table 2-30 presents the maximum temperatures, throughout the transport package, resulting from Normal conditions of transport. The structural analyses are applied to the temperature field generated by the thermal analysis, to determine the thermal stresses.

Table 2-31 presents the pressure corresponding to the maximum temperature for each transport package model. These pressure values are based on air occupying the cavity volume. To calculate these pressures, the initial temperature is conservatively assumed to be 50°F and the initial pressure is assumed to be 4.5 psig, which is the maximum pressure to which the cavity will be backfilled after vacuum drying as per Paragraph 7.1.3.1. These pressures do not exceed the design pressure, which is also listed in Table 2-31. Therefore, the transport package can withstand pressures and temperatures in excess of those encountered in Normal conditions of transport.

Pressure-related Load Cases 201 through 204 are analyzed by the 2D cask model. Pressure is applied to the models inside cask cavity wall or cask outside surface. The LIBRA LE -4a loading function is used to apply pressure loads. This function generates nodal forces in 2D models due to surface tractions along edge nodal lines. The nodal lines are defined by terminal nodes.

a. The LIBRA programs LE feature defines several types of edge and surface loadings. The first entry is a negative integer that distinguishes the type of loading. The types of loadings and nodal specifications are listed below, with former record types in parentheses.

Options Available when Applying the LE Command Type General loading on nodes specified by numbering sequence.

Type General loading on arc defined by control points (LE1).

Type Surface pressure on arc defined by control points (LEP).

Type Linearly varying pressure on line specified by end nodes.

Type Linearly varying harmonic pressure on 3D model generated from a 2D model.

Further Details for Types -4 and -5 Type This command generates nodal loads corresponding to linearly varying surface tractions along a line on a 2D model. The line is specified by the two (2) terminal nodes, and loads are applied to all nodes within a specified distance of the line. The linearly varying pressure is specified by the terminal values.

Type This command generates nodal loads corresponding to surface tractions over a 3D model generated from an axisymmetric (2D) model. The tractions may vary linearly along a radial line, and circumferentially as a Fourier harmonic. The loaded nodes are identified by specifying the two (2) terminal nodes on the zero meridian. The linearly varying pressure is specified by the corresponding terminal values on the zero meridian.

2-76 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J-1, April 20, 2021 (Docket No. 71-9316)

Table 2-30. Temperature Summary of Normal Conditions of Transport - All Models Package Component Maximum Temperatures, by Model AOS-025A AOS-050A AOS-100A AOS-100A-S AOS-100B

°C

°F

°C

°F

°C

°F

°C

°F Cask Cavity 125 257 147 296 155 312 156 312 Shielding Material 124 256 142 288 148 298 148 298 Cask Lid Seal Area 124 255 141 286 145 293 145 293 Cask Vent Port 124 255 140 284 143 290 143 290 Cask Drain Port 124 255 141 286 144 291 144 291 Test Port 124 255 141 286 145 293 145 293 Cask Vent Port Pipe Plug 124 255 140 285 143 290 143 290 Cask Drain Port Pipe Plug 124 255 141 286 144 292 144 292 Cask Vent Port Conical Seal 124 255 141 286 145 293 145 293 Cask Drain Port Conical Seal 124 255 142 288 147 296 147 297 Cask Outside Surface 124 256 142 287 146 295 146 295 Impact Limiter, Foam Materials 94 202 117 242 111 231 111 231 Accessible Outside Surface 48 119 45 113 41 106 41 106 Table 2-31. Maximum Cask Cavity Pressure Due to Normal Conditions of Transport - All Models Model Temperature Pressurea

a. Pressure calculation is based upon the ideal gas law illustrated in Table 4-6, Maximum Cask Cavity Pressure Due to Normal Conditions of Transport - All Models, footnote a.

Design Pressure

°C

°F kPa psia kPa psia AOS-025A 125 257 186 27 207 30 AOS-050A 147 296 196 28 414 60 AOS-100A AOS-100A-S 155 312 200 29 1,930 280 AOS-100B 156 312 200 29 1,930 280

2-148 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J-1, April 20, 2021 (Docket No. 71-9316)

Table 2-53. Temperature Summary of Fire Condition - All Models Component Maximum Temperatures, by Model AOS-025A AOS-050A AOS-100A AOS-100A-S AOS-100B

°C

°F

°C

°F

°C

°F

°C

°F Cask Cavity 136 277 259 499 246 476 241 467 Shielding Material 135 276 262 504 246 475 242 467 Cask Lid Seal Area 134 274 223 434 207 404 204 399 Cask Vent Port 134 274 225 437 208 407 206 403 Cask Drain Port 135 276 227 440 210 410 207 405 Test Port 134 274 223 433 206 402 203 397 Cask Vent Port Pipe Plug 134 274 225 437 209 407 206 402 Cask Drain Port Pipe Plug 135 276 227 441 211 411 208 406 Cask Vent Port Conical Seal 134 274 224 435 207 405 205 400 Cask Drain Port Conical Seal 135 276 224 436 208 407 206 402 Cask Outside Surface 145 294 414 777 463 866 463 866 Table 2-54. Maximum Cask Cavity Pressure Due to Fire Condition - All Models Model Temperaturea

a. Temperature listed is the maximum value obtained throughout the Fire event.

Pressureb

b. Pressure calculation is based upon the ideal gas law illustrated in Table 4-6, Maximum Cask Cavity Pressure Due to Normal Conditions of Transport - All Models, footnote a.

Design Pressure

°C

°F kPa psia kPa psia AOS-025A 136 277 191 28 207 30 AOS-050A 259 499 249 36 414 60 AOS-100A AOS-100A-S 246 476 243 35 1,930 280 AOS-100B 241 467 241 35 1,930 280

2-986 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J-1, April 20, 2021 (Docket No. 71-9316)

[2.19]

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).

[2.20]

Communication from ATI Firth Sterling to Alpha-Omega Services, Inc., and GE Energy.

[2.21]

Parker O-Ring Division, Evaluation of Parker Compound S1224-70 to ASTM D2000 7GE705 A19 B37 EA14 EO16 E036 F19 G11 Compound Data Sheet, Kentucky, June 19, 1996.

[2.22]

Fitzroy, Nancy D., Ed., Heat Transfer Data Book, General Electric Company, New York, November, 1970 Edition, Section G502.5, p. 7.

[2.23]

Touloukian, Y. S., Thermophysical Properties of Matter, Metallic Elements and Alloys, 1971.

[2.24]

Fischer, L. E. and W. Lai, NUREG/CR-3854, Fabrication Criteria for Shipping Containers, Lawrence Livermore Laboratory, Prepared for U.S. Nuclear Regulatory Commission (NRC),

Livermore, California, March, 1985.

[2.25]

Monroe, R. E, H. H. Woo, and R. G. Sears, NUREG/CR-3019, Recommended Welding Criteria For Use in the Fabrication of Shipping Containers for Radioactive Materials, Lawrence Livermore Laboratory, Prepared for U.S. Nuclear Regulatory Commission (NRC), Livermore, California, March, 1984.

[2.26]

American Society of Mechanical Engineers, ASME Boiler and Pressure Vessel Code,Section III, Division 1, Subsections NB, NF, and NG, 2004 Ed., No Addendum.

[2.27]

ASTM International, ASTM F1145 - 05(2011), Standard Specification for Turnbuckles, Swaged, Welded, Forged, Table 3, West Conshohocken, PA, 2011.

[2.28]

Shigley, Joseph E., Mechanical Engineering Design, Chapter 6, The Design of Screws, Fasteners, and Connections, McGraw Hill, Inc., 3rd Edition, 1977.

[2.29]

American Society of Mechanical Engineers, ASME Boiler and Pressure Vessel Code,Section VIII, Division 1, 2004 Ed., No Addendum.

[2.30]

U.S. Nuclear Regulatory Commission (NRC), Regulatory Guide 7.11, Fracture Toughness Criteria of Base Material for Ferritic Steel Shipping Cask Containment Vessels with a Maximum Wall Thickness of 4 Inches (0.1 m), 1991.

[2.31]

Holman, W.R, and R.T. Langland, NUREG/CR-1815, Recommendations for Protecting Against Failure by Brittle Fracture in Ferritic Steel Shipping Containers Up to Four Inches Thick, Lawrence Livermore National Laboratory, Prepared for U.S. Nuclear Regulatory Commission (NRC), June 15, 1981.

[2.32]

McConnell, J. W. Jr., A. L. Ayers, Jr., and M. J. Tyacke, NUREG/CR-6407, Classification of Transportation Packaging and Dry Spent Fuel Storage System Components According to Importance to Safety, Idaho National Engineering Laboratory, Prepared for U.S. Nuclear Regulatory Commission (NRC), Idaho Falls, Idaho, February, 1996.

[2.33]

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

[2.34]

ANSYS, Inc. ANSYS documentation release 15.0, November, 2013.

[2.35]

Parker Hannifin Corporation, Parker O-Ring Handbook, ORD 5700, 2018.

Radioactive Material Transport Packaging System Safety Analysis Report 3-21 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J-1, April 20, 2021 (Docket No. 71-9316) 3.3.2 Maximum Normal Operating Pressure The maximum operating pressure, based upon steady state temperatures for Normal conditions of transport are 27 psia, 28 psia, and 29 psia for Models AOS-025, AOS-050, and AOS-100, respectively.

The calculation is applied by using the Ideal Gas Law, a relationship of temperature and pressure. The volume parameter does not enter into the calculation, because it is constant. Refer to Table 4-6, Maximum Cask Cavity Pressure Due to Normal Conditions of Transport - All Models, for pressure calculation details.

The AOS Transport Packaging System can be loaded dry or wet; however, if loaded wet, the cask cavity must be vacuum-dried to remove all water or other moisture and then backfilled with dry air or inert gas to a maximum pressure of 4.5 psig in accordance with Paragraph 7.1.3.1. None of the contents undergo alpha decay in any appreciable amount, nor do they contain neutron emitters or boron systems, that could generate helium gas.

3.3.3 Thermal Finite Element Model The thermal evaluation of the AOS Transport Packaging System is conducted using the thermal analysis modulus of the LIBRA computer program, MAIN12. This heat conduction solution determines both steady-state and transient temperature fields. For transient thermal problems, the user can control the integration scheme by specifying the integration parameter. A zero (0) value for this parameter provides an explicit integration scheme; while between zero (0) and one (1) provide implicit schemes. A value of one (1) is used in the evaluation, corresponding to a backward difference integration technique. Temperature-dependent properties are either incorporated into an algorithm or implemented by a user-written subroutine. In this evaluation, the temperature-dependent properties are provided by an algorithm, and are shown in Subsection 3.2.1, Material Properties.

The thick stainless steel cask outer shell, which comprises the bulk of the cask, defines the outside dimensions of the cask. The cask cavity is defined by the cask cavity shell, which is secured to the cask outer shell. The cask lid plug shell is secured by the cask lid and cask cavity shell. Four-node quadrilateral conduction elements are used to model the cask outer shell, cask cavity shell, and cask lid plug shell. Also, the bottom plate and cask lid are modeled with four-node quadrilateral conduction elements. Figure 3-1 shows the analytical model used in the evaluation of Normal conditions of transport. Refer to Appendix 3.5.4.2 and Appendix 3.5.4.3 for descriptions of the analytical model used in this evaluation.

The side tungsten alloy or carbon steel shielding is encapsulated by the cask outer shell and cask cavity shell. The vertical wall between the shielding and cask outer shell is packed with stainless steel wool on one side, and between the shielding and cask cavity shell, an air gap exists on the other. At the top and bottom horizontal surfaces, existing gaps within the cask cavity shell are filled with stainless steel shim plates. Two-node conduction elements are used in the model for the surface contact resistance and conduction through the stainless steel wool. Other surface interfaces, between cask components, are assembled with zero (0) gap, and are modeled with two-node conduction elements that have pressure surface-contact resistance properties.

The analytical FEA methodology and model are validated by a thermal test, the details of which are provided in Appendix 3.5.7.

4-30 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J-1, April 20, 2021 (Docket No. 71-9316) 4.2.3 Containment Criterion The AOS Transport Packaging System containments are designed, and verified by Leak test, to meet the leak-tight criteria established in Reference [4.4], for the transportation of activated material in Normal form.

Table 4-6. Maximum Cask Cavity Pressure Due to Normal Conditions of Transport - All Models Model Temperature (T)

Pressure (P)a

a. Pressure calculation is based upon the ideal gas law:

Design Pressure

°C

°F kPa psia kPa psia AOS-025A 125 257 186 27 207 30 AOS-050A 147 296 196 28 414 60 AOS-100A AOS-100A-S 155 312 200 29 1,930 280 AOS-100B 156 312 200 29 1,930 280 Table 4-7. Maximum Cask Cavity Pressure Due to Fire Condition - All Models Model Temperaturea

a. Temperature listed is the maximum value obtained throughout the Fire event.

Pressureb

b. Pressure calculation is based upon the ideal gas law illustrated in Table 4-6, footnote a.

Design Pressure

°C

°F kPa psia kPa psia AOS-025A 136 277 191 28 207 30 AOS-050A 259 499 249 36 414 60 AOS-100A AOS-100A-S 246 476 243 35 1,930 280 AOS-100B 241 467 241 35 1,930 280 P1 V1 T1

=

P2 V2 T2 P1 T1

=

P2 T2

=>

Initial Conditions Assumed to be an ambient temperature of 50°F and a pressure of 4.5 psig corresponding to the cask cavity being backfilled with helium in accordance with Paragraph 7.1.3.1.

P1 = 14.7 + 4.5 psig = 19.2 psia T1 = 50°F Final Condition P2 = ?

T2 = 257°F P2 = x 19.2 = 26.99 psia (257 + 460)

(50 + 460)

7-10 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J-1, April 20, 2021 (Docket No. 71-9316) 7.1.3 Preparation for Transport 7.1.3.1 Securing the Cask Lid To secure the cask lid, in preparation for transport:

Note: Torque sequence is stamped on top surface of the cask lid, about the bolt location.

a.

Torque the cask lid attachment bolts (refer to Table 7-2), using one of the two conditions listed below.

1.

If the cask was dry loaded - Torque the cask lid attachment bolts in a crisscross pattern, with a final pass all the way around, to ensure even seal compression after the elastomeric seal has been visually inspected and installed, -or-a new metallic seal has been installed.

2.

If the cask was wet loaded - To torque the cask lid attachment bolts:

a.

Install the cask lid and a minimum of at least five (5) bolts in the cask lid, as the cask breaks the waters surface. Note that this step may be skipped with the approval of Radiation Protection.

b.

Drain the cask over the pool area. After the water has drained from the cask, move the cask to the decontamination pad.

c.

Remove the bolts (previously installed for the transfer) and cask lid.

d.

Dry the sealing surfaces and the bolt threaded holes.

e.

Install the cask lid elastomeric seal after it has been visually inspected, -or-a new cask lid metallic seal onto the cask lid, then re-install the bolts and torque the cask lid attachment bolts in a crisscross pattern, with a final pass all the way around, to ensure even seal compression.

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

Radioactive Material Transport Packaging System Safety Analysis Report 7-10a for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J-1, April 20, 2021 (Docket No. 71-9316) f.

Flush the cask cavity with dry air or nitrogen, to displace any remaining water within the cavity.

g.

Vacuum-dry the cavity until the cask cavity pressure is 1 torr or less and then isolate the vacuum source. The pressure within the cask cavity must remain at or below 3 torr for at least 30 minutes. Gas discharged from the vacuum pump should be filtered to prevent airborne release of radioactive material that might be present within the gas stream. After completing this operation, fill the cask cavity with dry air, helium, or other inert gas, to 2.5 psig +/-2.0 psig.

h.

Figure 7-4 illustrates a typical vacuum drying system and its basic components.

These components include a vacuum pump, pressure gauge, connectors, and valves.

b.

Install the cask drain port plugs, cask vent port plugs, and covers, as applicable. Prior to installation, completely remove all previous thread sealant from the pipe plugs, if not already done. Apply pipe thread sealant on the plug thread areas. If using Loctite Thread Seal Tape No. 39904, wrap the threads with three (3) full turns of tape. Three (3) full turns are necessary to ensure a leak-tight seal of the port plugs.

7-10b Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J-1, April 20, 2021 (Docket No. 71-9316)

THIS PAGE INTENTIONALLY LEFT BLANK

Radioactive Material Transport Packaging System Safety Analysis Report 7-11 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J-1, April 20, 2021 (Docket No. 71-9316)

Figure 7-4 illustrates a typical Leak testing setup (vacuum drying system and its basic components) that can be used for all AOS Radioactive Material Transport Packaging System models (Models AOS-025A, AOS-050A, AOS-100A, AOS-100B, and AOS-100A-S).

Figure 7-4. Typical Vacuum Drying System Setup and Equipment Table 7-2. Cask Lid Attachment Bolt Size and Preload Torque - All Modelsa

a. Refer to Table 1-5, AOS Transport Packaging System Certification Drawing List - All Models.

Model Function Bolt Size / ASME and ANSI Standards Preload Torque N-m ft-lb AOS-025 Cask Lid Attachment Bolt 3/8-16 UNC-2A / ASME SB-637, UNS N07718 47 35 AOS-050 Cask Lid Attachment Bolt 1/2-13 UNC-2A / ASME SB-637, UNS N07718 85 62.5 AOS-100 Cask Lid Attachment Bolt 7/8-9 UNC-2A / ASME SB-637, UNS N07718 678 500

+HOLXP Vacuum +ose Vacuum 'rying $ssembly HEPA

)ilter $ssHPEOy Vacuum *auge

9alve (VGV-1)

Cask 9ent

9alve (CVV-1)

Vacuum

/eak

'etector Helium

/eak

'etector

&DVN

&DYLW\\

Drain Port HEPA

)LOWHU$VVHPEO\\

Helium 9ent 9alve(HVV-1) 3UHVVXUH 5HJXODWRU Quick

&onnector Vent Line Helium Backfill $ssembly 1/4" +ose Helium Supply Valve (HSV-1)

Quick

&onnector Vent Port Test Port Vacuum 3ump Pressure Gauge

7-12 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J-1, April 20, 2021 (Docket No. 71-9316) 7.1.3.2 Removing the Cask from the Loading Area To remove the cask from the loading area, in preparation for transport:

a.

Carefully measure the cask radiation levels, while removing the cask from the storage basin or cell area.

b.

Decontaminate the cask to a level consistent with IAEA TS-R-1, Paragraph 508, 10 CFR 71.87(i), and 49 CFR 173.443 (References [7.1], [7.2], and [7.3], respectively).

7.1.3.3 Pre-Shipment Leak Testing To verify that the transport packages containment system is properly assembled for shipment, perform one of the following Pre-Shipment Leak tests - Test A1, A2 or B - depending on the content and cask lid seal type. Tests A1 and A2 are minimum requirements for shipments that contain Special Form contents.

Test B is the minimum test required for shipments that contain Normal Form content. However, Test B can be performed in lieu of Tests A1 or A2.

Notes:

A Periodic or Maintenance Leak test performed on a loaded cask in accordance with Subsection 8.2.2 may be acceptable as a Pre-Shipment Leak test, provided that the test meets or exceeds the requirements for Pre-Shipment Leak testing described below.

When the Model AOS-100A-S is used, both cask lid seals must be leak tested.

Test A1 - Gas Pressure Rise: For Special Form Contents (Tests: Cask Lid(s), Vent and Drain Ports)

To perform a pre-shipment verification of the elastomeric lid seal:

a.

Perform the test by evacuating the space between the cask lid seals elastomeric O-Ring seals, -or-the cavities outside the cask vent and drain ports, and then measuring the pressure rise.

Notes:

The cask vent port and cask drain port need to be leak tested only if the ports have been opened since they were last tested.

The Gas Pressure Rise Leak test is performed using a test manifold, isolation valve, vacuum gauge, and vacuum pump. Use the test apparatus described in the test procedure or equivalent.

b.

Connect the test manifold to the test port. Evacuate the test volume to the required level.

and then close the isolation valve.

c.

Disconnect the vacuum pump and then wait for the prescribed test time. After the test time, the acceptance criterion is a pressure rise that corresponds to no detectable leakage.

Radioactive Material Transport Packaging System Safety Analysis Report 7-13 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J-1, April 20, 2021 (Docket No. 71-9316)

Test A2 - Gas Pressure Drop: For Special Form Contents (Tests: Cask Lid(s), Vent and Drain Ports)

To perform a pre-shipment verification of the elastomeric lid seal:

a.

Perform the test by pressurizing the space between the cask lid seals elastomeric O-Ring seals, -or-the cavities outside the cask vent and drain ports, and then measuring the pressure drop.

Notes:

The cask vent port and cask drain port need to be leak tested only if the ports have been opened since they were last tested.

The Gas Pressure Drop Leak test is performed using a test manifold, isolation valve, pressure gauge, and pressure supply. Use the test apparatus described in the test procedure or equivalent.

b.

Connect the test manifold to the test port. Evacuate the test volume to the required level.

and then close the isolation valve.

c.

Disconnect the pressure supply and then wait for the prescribed test time. After the test time, the acceptance criterion is a pressure drop that corresponds to no detectable leakage.

Test B - Tracer Gas: For Normal Form Contents (Tests: Lid (Cask Lid Seal), Vent and Drain Ports)

To leak test the containment system:

a.

The cask lid seal, and vent and drain threaded pipe plugs must be leak-tested in accordance with ANSI N14.5-2014 [7.8]. The acceptance criteria is 1 x 10-7 ref-cm3/sec air at an upstream pressure of a minimum of 1 atmosphere and downstream pressure of 0.01 atmosphere absolute or less. The test procedure sensitivity must be one-half of the reference air leakage rate (i.e., 5 x 10-8 ref-cm3/sec of air) or less.

8-2 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J-1, April 20, 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 Helium test procedure sensitivity of at least 5 x 10-8 ref-cm3/sec.

Shieldingg

g. Refer to Subsection 8.1.6.

8-4 Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J-1, April 20, 2021 (Docket No. 71-9316) 8.1.4 Leakage Tests The containment system, which includes the cask cavity, cask lid, welds, port plug assembly, seals, and penetrations, is leak tested during fabrication in accordance with ANSI N14.5-2014 [8.4]. The acceptance criteria is 1 x 10-7 ref-cm3/sec of air at an upstream pressure of 1 atmosphere and downstream pressure of 0.01 atmosphere absolute or less. The test procedure sensitivity must be one-half of the reference air leakage rate (i.e., 5 x 10-8 ref-cm3/sec of air) or less.

Note: Casks manufactured prior to April 2016 were leak tested in accordance with the 1997 edition of ANSI N14.5.

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 8-17 for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J-1, April 20, 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).

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 prior to the transport packages first use, after its third use, annually, and/or prior to the transport package being used after a storage period of more than one (1) year. The cask lid seal, vent and drain threaded pipe plugs, and the port plug conical seal must be leak-tested in accordance with ANSI N14.5-2014 [8.4]. The acceptance criteria is 1 x 10-7 ref-cm3/sec air at an upstream pressure of 1 atmosphere and downstream pressure of 0.01 atmosphere absolute or less. The test procedure sensitivity must be one-half of the reference air leakage rate (i.e., 5 x 10-8 ref-cm3/sec of air) or less.

8-17a Radioactive Material Transport Packaging System Safety Analysis Report for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J-1, April 20, 2021 (Docket No. 71-9316) c.

Maintenance Leak Testing Maintenance leak testing is performed to confirm that maintenance, repair, and/or replacement of components has not degraded containment system performance. The portion of the containment system affected by the maintenance, repair and/or component replacement must be leak-tested in accordance with ANSI N14.5-2014 [8.4]. The acceptance criteria is 1 x 10-7 ref-cm3/sec air at an upstream pressure of 1 atmosphere and downstream pressure of 0.01 atmosphere absolute or less. The test procedure sensitivity must be one-half of the reference air leakage rate (i.e., 5 x 10-8 ref-cm3/sec of air) or less.

Notes:

For shipments of Special Form material, a Maintenance Leak test is not necessary after replacement of a cask lid elastomeric seal, provided that a Periodic Leak test has been performed on the casks containment system within the past 12 months and a Pre-Shipment Leak test is performed in accordance with Paragraph 7.1.3.3.

Periodic and Maintenance Leak testing on casks prior to April 2016 may have been performed in accordance with the 1997 edition of ANSI N14.5.

Radioactive Material Transport Packaging System Safety Analysis Report 8-17b for Model AOS-025, AOS-050, and AOS-100 Transport Packages, Rev. J-1, April 20, 2021 (Docket No. 71-9316)

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Rev.J,January31,2021

Rev.J1,April20,2021

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constraints,SARpagefootersmight/mightnotincludearevisionbar

indicatingthischange.Additionally,therevisionbarmightspan

bothlinesofthefooter.)

iv

RevisionHistory

J1

-

-

x RevisedSubsection1.2.2(addeddiscussionrelatedtocask

loadingtemperatureandbackfillingpressure)

x RevisedSubsection2.2.3(expandeddiscussionrelatedeffects

ofradiation),Paragraph2.6.1.1(revisedinitialconditionsfor

NCTpressurecalculations),Table231andTable254(omitted

footnotesbandc,respectively;updatedcalculatedpressures);

addednewReference[2.35]

x RevisedSubsection3.2.2(updatecalculatedNCTpressuresand

elaborateoninitialconditionsandmechanismsthatcan

increaseinternalcaskpressure)

x RevisedTable46andTable47(omittedfootnotesbandc,

respectively;revisedpressurecalculationsbasedonupdated

initialconditions)

x RevisedParagraph7.1.3.1(revisedinstructionsforwetloading

cask),Figure74(updatedtoreflectcurrentequipment),and

Paragraph7.1.3.3(revisedleaktestingprocedure)

x RevisedTable81footnote(clarifiedtestprocedure

sensitivity),Subsection8.1.4(revisedfabricationleaktesting

requirements),Section8.2(removedstatementregardingpre shipmentleaktestingbecausethisbelongsinChapter7),

Subsection8.2.2(updatedleaktestingrequirements)

Chapter1

113

1.2.2

4

2+

Thecontainmentboundarywillnotnormallybe

pressurized;however,internalheatingoftheenclosed

gasescanincreasethepressure.

Thecaskmayhaveaslightinternalpressureduetobackfillingwith

airoraninertgasandinternalheatingoftheenclosedgasescan

increasethepressure.Thecaskisnormallyloadedatroom

temperature;however,forevaluatingthetemperaturecontribution

tothepressurizationofthecaskcavity,theloadingtemperaturewill

beconservativelyassumedtobe50°F.Thepressureinsidethe

containmentboundaryisevaluatedinSubsection4.2.2.



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237

2.2.3

2

All

Ofallthesematerials,theonemostaffectedby

radiationisthesiliconematerial.However,theseport

coverORingcomponentsarereplacedaftereachuse,

thuseliminatingthecumulativeeffectofradiation.

Ofthesematerials,theonemostaffectedbyradiationisthesilicone

material.TheportcoverORingcomponentsarenotapartofthe

containmentboundaryandareusedonlytosealtheportcoverto

preventdebrisfromenteringtheportplugarea.Furthermore,these

itemsarevisuallyinspectedfordamage,deterioration,andwear,

andarereplacedasneeded.

237

2.2.3

3(new)

-

-

<Addednewparagraph.>

Thecasklidelastomericsealispartofthecontainmentboundary

andisexposedtogammaradiationthatcancausecompressionset.

Theexpectedmaximumdoserateinthecasklidsealregionis1

rad/hr.Afteroneyearofcontinuoususe,thiswouldresultinatotal

doseof1x104rad.However,atadoseof1x106rads,theradiation

effectonelastomersisminor.Itisnotuntiltheradiationis

deliveredindoseswithintherangeof1x107radthatradiationisa

concernforORingcompounds(Reference[2.35]).Therefore,

radiationisnotaconcernbecausethecasklidelastomericsealsare

replacedafterevery12usesorannually,whichevercomesfirst.

275

2.6.1.1

2

2

Thispressurevalueisbaseduponairat100%relative

humidityoccupyingtheentirecavityvolume.

Thesepressurevaluesarebasedonairoccupyingthecavityvolume.

Tocalculatethesepressures,theinitialtemperatureis

conservativelyassumedtobe50°Fandtheinitialpressureis

assumedtobe4.5psig,whichisthemaximumpressuretowhich

thecavitywillbebackfilledaftervacuumdryingasperParagraph

7.1.3.1.

276

Table231

Pressure

columns

(columns45)

Allmodel

rows

AOS025A:135kPa,20psia

AOS050A:142kPa,21psia

AOS100A/100AS:145kPa,21psia

AOS100B:145kPa,21psia

AOS025A:186kPa,27psia

AOS050A:196kPa,28psia

AOS100A/100AS:200kPa,29psia

AOS100B:200kPa,29psia

276

Table231

DesignPressure

columnheading

andfootnote

-

DesignPressureb

b.ModelAOS100transportpackage-Pressurevalue

isbaseduponprojectedoperatingconditions.

<Omittedfootnoteb.>

2148

Table254

Pressure

columns

(columns45)

Allmodel

rows

AOS025A:139kPa,20psia

AOS050A:181kPa,26psia

AOS100A/100AS:177kPa,26psia

AOS100B:175kPa,25psia

AOS025A:191kPa,28psia

AOS050A:249kPa,36psia

AOS100A/100AS:243kPa,35psia

AOS100B:241kPa,35psia

2148

Table254

DesignPressure

columnheading

andfootnote

-

DesignPressurec

b.ModelAOS100transportpackage-Pressurevalue

isbaseduponprojectedoperatingconditions.

<Omittedfootnotec.>



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2.13

[2.35]

-

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<Addednewreference.>

ParkerHannifinCorporation,ParkerORingHandbook,

ORD5700,2018.

Chapter3

321

3.3.2

1

2

20psia,21psia,and21psia

27psia,28psia,and29psia

321

3.3.2

2

All

TheAOSTransportPackagingSystemcanbeloadeddry

orwet;however,ifloadedwet,thecaskcavitymustbe

vacuumdriedtoremoveallwaterorothermoisture.

Subsequently,onlytherelativehumidityintheloading

environmentistrappedwithinthecavity.Noneofthe

contentsundergoalphadecayinanyappreciable

amount,neitherneutronemittersnorboronsystems,

thatcouldgenerateheliumgas.

TheAOSTransportPackagingSystemcanbeloadeddryorwet;

however,ifloadedwet,thecaskcavitymustbevacuumdriedto

removeallwaterorothermoistureandthenbackfilledwithdryair

orinertgastoamaximumpressureof4.5psiginaccordancewith

Paragraph7.1.3.1.Noneofthecontentsundergoalphadecayinany

appreciableamount,nordotheycontainneutronemittersorboron

systems,thatcouldgenerateheliumgas.

Chapter4

430

Table46

Pressure

columns

(columns45)

Allmodel

rows

AOS025A:135kPa,20psia

AOS050A:142kPa,21psia

AOS100A/100AS:145kPa,21psia

AOS100B:145kPa,21psia

AOS025A:186kPa,27psia

AOS050A:196kPa,28psia

AOS100A/100AS:200kPa,29psia

AOS100B:200kPa,29psia

430

Table46

DesignPressure

columnheading

andfootnote

-

DesignPressureb

b.ModelAOS100transportpackage-Pressurevalue

isbaseduponprojectedoperatingconditions.

<Omittedfootnoteb.>

430

Table46

Footnotea

Initial

andFinal

Condition relatedtext

P1 = 14.7 psia T1 = 78°F Initial Condition P2 = ?

T2 = 257°F Final Condition P2 =

  • 14.7 = 19.59 psia (257 + 460)

(78 + 460)



Initial Conditions Assumed to be an ambient temperature of 50°F and a pressure of 4.5 psig corresponding to the cask cavity being backfilled with helium in accordance with Paragraph 7.1.3.1.

P1 = 14.7 + 4.5 psig = 19.2 psia T1 = 50°F Final Condition P2 = ?

T2 = 257°F P2 = x 19.2 = 26.99 psia (257 + 460)

(50 + 460)



430

Table47

Pressure

columns

(columns45)

Allmodel

rows

AOS025A:139kPa,20psia

AOS050A:181kPa,26psia

AOS100A/100AS:177kPa,26psia

AOS100B:175kPa,25psia

AOS025A:191kPa,28psia

AOS050A:249kPa,36psia

AOS100A/100AS:243kPa,35psia

AOS100B:241kPa,35psia



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Table47

DesignPressure

columnheading

andfootnote

















-

DesignPressurec

b.ModelAOS100transportpackage-Pressurevalue

isbaseduponprojectedoperatingconditions.

<Omittedfootnotec.>

Chapters5and6-Nochanges

Chapter7

710

7.1.3.1

a.2

a.2.a

All

2.Ifthecaskwaswetloaded-Totorquethecasklid

attachmentbolts,ifthecaskwaswetloaded:

a.Installaminimumofatleastfive(5)boltsinthe

casklid,asthecaskbreaksthewaterssurface.

2.Ifthecaskwaswetloaded-Totorquethecasklidattachment

bolts:

a.Installthecasklidandaminimumofat

leastfive(5)boltsinthecasklid,asthecaskbreaksthewaters

surface.Notethatthisstepmaybeskippedwiththeapproval

ofRadiationProtection.

710

7.1.3.1

e

Notes(new)

-

Note:ForshipmentsofSpecialFormmaterial,aMaintenanceLeak

testisnotnecessaryafterreplacingacasklidelastomericseal,

providedthataPeriodicLeaktesthasbeenperformedonthecasks

containmentsystemwithinthepast12months.

710a

710b

(new)

7.1.3.1

-

-

-

<Movedstepfandremainingcontentfrompage710to

page710a.Page710bisblank.>

710a

(new)

7.1.3.1

g

All

Vacuumdrythecavityuntilthecaskcavitypressureis

1torrorless.

Thevacuumsourcemustbeisolatedafterthepressure

is1torrorless.Thepressurewithinthecaskcavitymust

remainatorbelow1torr,foratleast30minutes.Gas

dischargedfromthevacuumpumpshouldbefiltered,to

preventairbornereleaseofradioactivematerialthat

mightbepresentwithinthegasstream.After

completingthisoperation,fillthecaskcavitywith

helium,to2psig+/-0.5psig.

Vacuumdrythecavityuntilthecaskcavitypressureis1torrorless

andthenisolatethevacuumsource.Thepressurewithinthecask

cavitymustremainatorbelow3torrforatleast30minutes.Gas

dischargedfromthevacuumpumpshouldbefilteredtoprevent

airbornereleaseofradioactivematerialthatmightbepresent

withinthegasstream.Aftercompletingthisoperation,fillthecask

cavitywithdryair,helium,orotherinertgas,to2.5psig+/-2.0psig.



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7.1.3.1

h

All

Figure74illustratesatypicalvacuumdryingsystemand

itsbasiccomponents.Thesecomponentsincludean

ultrafinevacuumpump,vacuumpressuregauge,

cryogenicwatertrap,vacuumconnectors,andvalves.

Ifthevacuumpumpusedinthisprocedureisequipped

withagasballastdevice,turnoffthedeviceduringthe

caskcavityvacuumdryingoperation.Thegasballast

deviceisusedtodryanymoisturethatmightbetrapped

withinthevacuumpumpoil.Ifitisnecessarytoremove

watervaporfromthepumpoilduringthevacuum

dryingoperation,isolatethesystem.Turnonthegas

ballastdeviceuntilthewatervaporisremovedfromthe

oil,turnoffthegasballast,thenplacethesystemback

online.

Figure74illustratesatypicalvacuumdryingsystemanditsbasic

components.Thesecomponentsincludeavacuumpump,pressure

gauge,connectors,andvalves.

711

Figure74

-

-



<Replacedfigure.>





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7.1.3.3

1andNote

All

Toverifythatthecontainmentsystemofthetransport

packageisproperlyassembledforshipment,perform

oneofthefollowingPreShipmentLeaktests-TestA1,

A2orB-dependingonthecasklidsealtype.

Note:WhentheModelAOS100ASisused,bothcasklid

sealsmustbeleaktested.

Toverifythatthetransportpackagescontainmentsystemis

properlyassembledforshipment,performoneofthefollowingPre ShipmentLeaktests-TestA1,A2orB-dependingonthecontent

andcasklidsealtype.TestsA1andA2areminimumrequirements

forshipmentsthatcontainSpecialFormcontents.TestBisthe

minimumtestrequiredforshipmentsthatcontainNormalForm

content.However,TestBcanbeperformedinlieuofTestsA1

orA2.

Notes:APeriodicorMaintenanceLeaktestperformedonaloaded

caskinaccordancewithSubsection8.2.2maybeacceptableasa

PreShipmentLeaktest,providedthatthetestmeetsorexceedsthe

requirementsforPreShipmentLeaktestingdescribedbelow.



WhentheModelAOS100ASisused,bothcasklidsealsmustbe

leaktested.

712

7.1.3.3

TestA1

Heading

TestA1-GasPressureRise:WhenUsingElastomeric

CaskLidSealsforSpecialFormContents(Tests:Cask

Lid(s),VentandDrainPorts)

TestA1-GasPressureRise:ForSpecialFormContents

(Tests:CaskLid(s),VentandDrainPorts)

712

7.1.3.3

TestA1

Notes

Note:Thecaskventportandcaskdrainportneedtobe

leaktestedonlyiftheportshavebeenopenedsince

theywerelasttested.

Note:Thegaspressureriseleaktestisperformedusing

atestmanifold,isolationvalve,vacuumgauge,and

vacuumpump.Useonlythetestapparatusdescribedin

thetestprocedure.

Notes:Thecaskventportandcaskdrainportneedtobeleaktested

onlyiftheportshavebeenopenedsincetheywerelasttested.



TheGasPressureRiseLeaktestisperformedusingatestmanifold,

isolationvalve,vacuumgauge,andvacuumpump.Usethetest

apparatusdescribedinthetestprocedureorequivalent.

712

7.1.3.3

TestA1

Stepc

Disconnectthevacuumpumpandthenwaitforthe

prescribedholdtime.Aftertheholdtime,the

acceptancecriterionisapressurerisethatislessthanor

equalto0.1psig.

Disconnectthevacuumpumpandthenwaitfortheprescribedtest

time.Afterthetesttime,theacceptancecriterionisapressurerise

thatcorrespondstonodetectableleakage.

713

7.1.3.3

TestA2

Heading

TestA2-GasPressureDrop:WhenUsingElastomeric

CaskLidSealsforSpecialFormContents(Tests:Cask

Lid(s),VentandDrainPorts)

TestA2-GasPressureDrop:ForSpecialFormContents

(Tests:CaskLid(s),VentandDrainPorts)

713

7.1.3.3

TestA2

Notes

Note:Thecaskventportandcaskdrainportneedtobe

leaktestedonlyiftheportshavebeenopenedsince

theywerelasttested.

Note:Thegaspressuredropleaktestisperformedusing

atestmanifold,isolationvalve,pressuregauge,and

pump.Useonlythetestapparatusdescribedinthetest

procedure.

Notes:Thecaskventportandcaskdrainportneedtobeleaktested

onlyiftheportshavebeenopenedsincetheywerelasttested.



TheGasPressureDropLeaktestisperformedusingatestmanifold,

isolationvalve,pressuregauge,andpressuresupply.Usethetest

apparatusdescribedinthetestprocedureorequivalent.



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7.1.3.3

TestA2

Stepc

Disconnectthepressuresupplyandthenwaitforthe

prescribedtesttime.Aftertheholdtime,theacceptance

criterionisapressurerisethatislessthanorequalto

0.1psig.

Disconnectthepressuresupplyandthenwaitfortheprescribed

testtime.Afterthetesttime,theacceptancecriterionisapressure

dropthatcorrespondstonodetectableleakage.

713

7.1.3.3

TestB

Heading

TestB-TracerGasWhenUsingMetallicCaskLidSeal

forNormalorSpecialFormContents(Tests:Lid(CaskLid

Seal),VentandDrainPorts)

TestB-TracerGas:ForNormalFormContents

(Tests:Lid(CaskLidSeal),VentandDrainPorts)

713

7.1.3.3

TestB

Allstepsand

Note

a.

Performaleaktestofthecasklidseal,drain

threadedpipeplugs,andventthreadedpipeplugs,

withathermalconductivitysensinginstrumentor

massspectrometerdevicewithasensitivityofat

least1.0x108refcm3/sec.

b.

Setupthetestinstrumentinaccordancewith

writtenproceduresandtheinstrument

manufacturersguidance.

Note:LeakTestcriteriaforleakratesmustmeetthe

requirementofReference[7.8].

c.

Evacuatethecaskcavityandthenbackfillthecask

cavitywithheliumtoapressureofatleastone(1)

atmosphere.

d.

Withtheinstrumentselectedinstepacalibrated

withacalibrationstandardwithintherangeof

1.0x108to5.0x107refcm3/sec,checkthe

followingforindicationsofleakage:

x Packagecontainmentwiththetestinstrument,

throughthetestport

x VolumebetweenthedoubleCcrosssections

x Aroundthethreadedjointareaofthedrain

andventthreadedpipeplugs

e.

Ifleakagegreaterthan1x107refcm3/sec,

correctedforthenatureofthetracergasand

temperatureconditionatthetimeofthetest,

isdetected,repairorreplacethedamaged

component(s),andthenretestforindications

ofleakage.

a.

Thecasklidseal,andventanddrainthreadedpipeplugsmust

beleaktestedinaccordancewithANSIN14.52014[7.8].The

acceptancecriteriais1x107refcm3/secairatanupstream

pressureofaminimumof1atmosphereanddownstream

pressureof0.01atmosphereabsoluteorless.Thetest

proceduresensitivitymustbeonehalfofthereferenceair

leakagerate(i.e.,5x108refcm3/secofair)orless.

Chapter8

82

Table81

Footnotef

1

MSLDHeTestatleast2.00E09Stdatmcm3/sec

sensitivity.

MSLDHeliumtestproceduresensitivityofatleast

5x108refcm3/sec.



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8.1.4

12

All

TheAOSTransportPackagingSystemcasksentire

containmentboundaryisleaktestedperSubsection

8.2.2(b),beforeitsfirstuse,andafteritsthirduse.The

PeriodicLeaktestistobeperformedinaccordancewith

Subsection8.2.2(b),every12monthsthereafter.The

LeaktestprocedureshallmeettheANSIN14.52014

[8.4]standard.Thetestusesamassspectrometerleak

detector(MSLD)inanevacuatedenvelope,withback

pressurizationtechnique.Thistechniqueconsistsof

creatinga1atmpressuredifferentialacrossthe

boundary,andevacuatingoutsidesurfacesofthe

boundary,atcriticallocations(suchaspenetrationsand

sealjoints)withtheMSLD.Theevacuatedgasesare

passedthroughtheinstrumentsspectrumportionto

detect,quantitatively,thepresenceofgas,typically

helium,usedinthepressurizationofthecontainment

boundary.Thecriteriathatisrequiredtobemetto

establishthecontainmentboundarysleaktightnessis

107atmcm3/secorless,basedupondryairat25°C

(32°F)andforapressuredifferentialof1atm.

TheMSLDinstrumentmustbesensitivetoatleast

a109atmcm3/secreading.

CriticallocationswithintheAOSTransportPackaging

Systemarethecasklidsealjoint,caskdrainport,and

caskventport.Theselocationsaretestedbyconnecting

thetestprobetothetestportthatislocatedbetween

thesealstwo(2)sealrings(inthecaseofthesealjoint)

andportcoverareas,andthendeterminingtheleak

rate.Iftheleaktightnesscriterion,perReference[8.4],

isnotmet,thecontainmentboundaryischecked,

damagedcomponents1(suchasasealorpipeplug)are

replaced,andtheunitisretested.

Thecontainmentsystem,whichincludesthecaskcavity,casklid,

welds,portplugassembly,seals,andpenetrations,isleaktested

duringfabricationinaccordancewithANSIN14.52014[8.4].The

acceptancecriteriais1x107refcm3/secofairatanupstream

pressureof1atmosphereanddownstreampressureof0.01

atmosphereabsoluteorless.Thetestproceduresensitivitymustbe

onehalfofthereferenceairleakagerate(i.e.,5x108refcm3/sec

ofair)orless.

Note:CasksmanufacturedpriortoApril2016wereleaktestedin

accordancewiththe1997editionofANSIN14.5.

817

8.2

2

56

asdetailedinSubsection8.2.2(b).Preshipment

LeaktestsareconductedonlywhenshippingNormal

Formmaterial.

asdetailedinSubsection8.2.2(b).



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8.2.2

b

2

Periodicleaktestingmustbeperformedannually,or

priortothetransportpackagebeingused,aftera

storageperiodofmorethanone(1)year,orpriorto

returningtoserviceafterrepairs(suchasweldrepair)

and/orreplacingcontainmentcomponents.Thecasklid

seal,ventanddrainthreadedpipeplugs,andtheport

plugconicalsealmustbeleakcheckedwitha

heliumMSLD.Thisinstrumenthasasensitivityof

<1x109refcm3/sec(helium).Conductthistestby

pressurizingthecaskcavitytoone(1)atmpressure

differentialacrosstheboundarytobetested(verified

withadoublepressuregauge),thenusetheMSLDto

testallcomponentsofthecontainmentboundaryfor

leaks.Ifleakagegreaterthan2x107refcm3/sechelium

atstandardconditionsisdetected,repairorreplacethe

damagedcomponent(s),thenretestforleakage,tothe

samecriteriaaspreviouslytested.

Periodicleaktestingmustbeperformedpriortothetransport

packagesfirstuse,afteritsthirduse,annually,and/orpriortothe

transportpackagebeingusedafterastorageperiodofmorethan

one(1)year.Thecasklidseal,ventanddrainthreadedpipeplugs,

andtheportplugconicalsealmustbeleaktestedinaccordance

withANSIN14.52014[8.4].Theacceptancecriteriais1x107ref cm3/secairatanupstreampressureof1atmosphereand

downstreampressureof0.01atmosphereabsoluteorless.Thetest

proceduresensitivitymustbeonehalfofthereferenceairleakage

rate(i.e.,5x108refcm3/secofair)orless.

817a

(new)

8.2.2

c

-

-

c.

MaintenanceLeakTesting

Maintenanceleaktestingisperformedtoconfirmthat

maintenance,repair,and/orreplacementofcomponentshasnot

degradedcontainmentsystemperformance.Theportionofthe

containmentsystemaffectedbythemaintenance,repairand/or

componentreplacementmustbeleaktestedinaccordance

withANSIN14.52014[8.4].Theacceptancecriteriais

1x107refcm3/secairatanupstreampressureof1atmosphere

anddownstreampressureof0.01atmosphereabsoluteorless.The

testproceduresensitivitymustbeonehalfofthereferenceair

leakagerate(i.e.,5x108refcm3/secofair)orless.



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817a

(new)

8.2.2

Note

All

Note:ForshipmentsofSpecialFormmaterial,aPeriodic

LeakTestisnotnecessaryafterreplacementofan

elastomericcasklidseal,providedthataPeriodicLeak

Testhasbeenperformedonthecaskscontainment

systemwithinthepast12months.

<MovedNotefrompage817,andthenrewroteastwonotes.>

Notes:ForshipmentsofSpecialFormmaterial,aMaintenanceLeak

testisnotnecessaryafterreplacementofacasklidelastomeric

seal,providedthataPeriodicLeaktesthasbeenperformedonthe

caskscontainmentsystemwithinthepast12monthsandaPre ShipmentLeaktestisperformedinaccordancewithParagraph

7.1.3.3.



PeriodicandMaintenanceLeaktestingoncaskspriortoApril2016

mayhavebeenperformedinaccordancewiththe1997editionof

ANSIN14.5.

817b

(new)

8.2.2

-

-

-

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