ML15223A428

From kanterella
Jump to navigation Jump to search
E-mail OP-100, Rev. 4 Safety Analysis Report(Partial)
ML15223A428
Person / Time
Site: 07109185
Issue date: 08/06/2015
From: William Allen
Office of Nuclear Material Safety and Safeguards
To: Debose M
Spent Fuel Licensing Branch
References
OP-100, Rev. 4
Download: ML15223A428 (34)
v • d • e


Text

DeBose, Michelle From: DeBose, Michelle Sent: Thursday, August 06, 2015 2:05 PM To: DeBose, Michelle

Subject:

FW: FW: Here the rest of it...

Attachments: OP-100 SAR Rev 4 pg 57 - end.pdf; 665S (Second SAR Submittal).doc From: Allen, William Sent: Thursday, August 06, 2015 12:22 PM To: DeBose, Michelle

Subject:

FW: FW: Here the rest of it...

can you get the attached PDF of a partial SAR into ADAMS? I've attached a 6655 for the submittal. Let me know if you have any questions. Chris From: Mike Rose [1]

Sent: Monday, August 03, 2015 2:02 PM To: Allen, William

Subject:

[ExternalSender] FW: Here the rest of it...

Mr. Allen, The rest of the story.

If you have any questions or concerns please do not hesitate to contact me at the information below.

Regards, Mike Rose QAM/ARSO 14320 Wicks Blvd San Leandro, CA 94577 510-352-6767 ph 510-352-6772 fax www.IR100.com From: Ron M[2]

Sent: Monday, August 03, 2015 10:38 AM To: Mike Rose

Subject:

Here the rest of it...

a

INC OP-I100 Package SAR Docket No. 71 -91 85 Revision 4, 6/2015 Figure 2.12.1-23 - CTU-3 Puncture Drop Test No. 8: Damage to Drum Shell 57

INC OP-I100 Package SAR Docket No. 71 -91 85 Revision 4, 6/2015 Figure 2.1 2.1 CTU-3 Thermal Test No. 11 Just Prior to Insertion Into Oven 58

INC OP-I100 Package SAR Docket No. 71 -91 85 Revision 4, 6/2015 Figure 2.12.1 CTU-3 Thermal Test No. 11 Immediately Upon Removal from Oven Figure 2.12.1 CTU-3 Post-Test Disassembly: Damaged Lock Box Dust Cap 59

INC OP-I100 Package SAR Docket No. 71 -91 85 Revision 4, 6/2015 Figure 2.12.1 CTU-3 Post-Test Disassembly: Damaged ,Safety Plug Figure 2.1 2.1 CTU-3 Post-Test Disassembly: Illustrating Polyurethane Foam Char 60

INC OP-I100 Package SAR Docket No. 71 -91 85 Revision 4, 6/2015 Figure 2.12.1-29 - CTU-3 Post-Test Disassembly: Interior Cavity with Foam Debris Removed Figure 2.12.1 CTU-3 Post-Test Disassembly: DU Support Bracket/Welds and Copper Shims 61

INC OP-I100 Package SAR Docket No. 71 -91 85 Revision 4, 6/2015 Figure 2.12.1 CTU-3 Post-Test Disassembly: DU Support Bracket/Melds and Copper Shims 62

INC OP-I100 Package SAR Docket No. 71 -91 85 Revision 4, 612015 Figure 2.12.1-32 - CTU-4 Free Drop Test No. 6: CC Over Closure Bolt 63

INC OP-I100 Package SAR Docket No. 71 -91 85 Revision 4, 6/2015 Figure 2.12.1-33 - CTU-4 Free Drop Test No. 6: Overall Damage View 64

INC OP-I100 Package SAR Docket No. 71 -91 85 Revision 4, 6/2015 Figure 2.12.1-34 - CTU-4 Puncture Drop Test No. 10 Setup 65

INC OP-I100 Package SAR Docket No. 71 -91 85 Revision 4, 6/2015 Figure 2.12.1-35 - CTU-4 Puncture Drop Test No. 10 Immediately Prior to Impact 66

INC OP-I100 Package SAR Docket No. 71 -91 85 Revision 4, 6/2015 Figure 2.12.1 CTU-4 Puncture Drop Test No. 10: Damage to Drum Shell Due to Lock Box Figure 2.12.1 CTU-4 Post-Test Disassembly: Condition of Plywood Support Structure 67

INC OP-IO00 Package SAR Docket No. 71 -91 85 Revision 4, 6/2015 Figure 2.12.1 CTU-.4 Post-Test Disassembly: Condition of Handle 68

INC OP-I100 Package SAR Docket Revision -9185 No. 4,716/2015 3.0 THERMAL EVALUATION This chapter establishes the compliance of the OP-lO0 package transporting a payload of up to 120 Ci (4.44 TBq) of Ir-192 or Se-75 in special form with the thermal requirements of 10 CFR §718 3.1 Description of Thermal Design 3.1.1 Design Features The OP-lO0 package and the IR-100/IR-50 devices do not contain any specific thermal design features. The thermal performance of the package is demonstrated by test. Therefore, this section does not apply.

3.1.2 Content's Decay Heat The OP-100 package may contain up to 120 Ci (4.44 TBq) of lr-192 or Se-75 in special form.

The radiol~ytic decay heat of Ir- 192 is 7.03 x 10. W/Ci 9. The radiolytic decay heat of Se-75 is 2.41 x 10- W/Ci 9 . Since the radiolytic decay heat of lr-192 is greater than the radiolytic decay heat of Se-75, the heatload of the Ir-192 payload bounds the Se-75 payload. Therefore, the maximum decay heat load for the package is therefore 0.84 W (2.87 Btu/hr), which is negligible.

3.1.3 Summary Tables of Temperatures The maximum surface temperature of the OP-100 package is 136.9 0F, as documented in Appendix 3.6.1, Determinationof Maximum Surface Temperaturefor OP-IQO0 Package, in full sunlight.

3.1.4 Summary Tables of Maximum Pressures The containment of the OP-100 package is provided by the special form payload. Gas can freely move from thle internal cavity to the environment during all phases of operation. Therefore, there are no internal pressures to be determined, since the OP-100 package does not contain any pressure boundaries.

3.2 Material Properties and Component Specifications 3.2.1 Material Properties The OP-100 packaging is constructed of a 10-gallon carbon steel drum, with a 20-gauge (0.0359 inch) thick body and lid. The drum lid is attached to the body with a 12-gauge (0.105 inch) thick 8Title 10, Code of Federal Regulations, Part 71 (10 CFR 71 ), Packagingand Transportationof Radioactive Material, 1-1-15 Edition.

90ORIG EN-S Decay Data Librar, and Half-Life Un~certainties, 0. W. Hermann, P. R. Daniel, and J. C. Ryman, Oak Ridge National Laboratory, ORNL/TM- 13624, September 1998.

69

INC OP-I100 Package SAR Docket No. 71 -91 85 Revision 4, 6/2015 carbon steel closure ring, which is secured with a 5/8-inch x 4 inch hex bolt and nut. A plywood support structure positions the device in the center of the drum cavity.

The IR-100 Exposure Device and the IR-50 Source Changer are constructed of a 12-gauge (0.105 inch) thick stainless steel outer skin surrounding polyurethane foam and a depleted uranium gamma shield. Since the structural integrity of the package is established by testing, the only pertinent temperature limits on the components is established by their melting temperatures for the fire based Hypothetical Accident Condition (HAC). The melting temperatures for uranium and stainless steel are 2,071 0 F and 2,800 0F, respectively.

The payload was qualified per Qualification of Special Form Radioactive Material, in 10 CFR §71.75(b)(4).

3.2.2 Component Specifications The OP-100 package does not contain any component or material that is important to the thermal performance of the package. The two primary structural materials are austenitic stainless steel and the DU shield. As noted in Section 2.1.2.2.1, Brittle Fracture,both materials have been tested to temperatures below -20 0 F with no loss of structural or shielding capability.

3.3 Thermal Evaluation under Normal Conditions of Transport This section presents the thermal evaluation of the OP-lO0 package under the normal conditions of transport (NCT) per 10 CFR §7 1.71.

3.3.1 Heat and Cold Since the total decay heat load of the OP-100 package is less than 1 W (3 Btu/hr), a detailed analysis of the package and internals is unnecessary. The peak internal temperatures will very closely match those on the surface of the package.

Per 10 CFR §71.71(c)(1), the worst-case high temperature conditions for the package consist of an ambient temperature of 100 0 F and maximum insolation. Under those conditions, the worst case surface temperature for the OP-100 package woiuld be 137 °F, as documented in Appendix 3.6.

Given the negligible decay heat, the maximum temperature for all surfaces of the OP-lO0 package in shade with an ambient temperature of 100 0 F (560 °R) is 100 °F (560 °R). This temperature is below the maximum acceptable surface temperature of 122 °F for non-exclusive use shipments as stipulated in 10 CFR §71.43(g). Similarly, the package temperature will be equal to ambient under the low temperature conditions of-20 °F and -40 °F.

3.3.2 Maximum Normal Operating Pressure This section does not apply, since the OP-100 package does not contain any pressure boundaries.

Therefore, there is no maximum normal operating pressure (MNOP) for the OP-lO00 package.

The containment of the OP-lO0 package is provided by the special form payload. Gas can freely move from the internal cavity to the environment during all phases of operation. Therefore, determination of internal pressures is not required.

70

INC OP-I100 Package SAR Docket No. 71 -91 85 Revision 4, 6/2015 3.3.3 Maximum Thermal Stresses Due to the small size of the package and thle negligible decay heat load, the thermal stresses within the package are negligible.

3.3.4 Evaluation of Package Performance for Normal Conditions of Transport As discussed in the previous sections, all of the temperatures that may be experienced by the OP-100 package during normal conditions of transport are within acceptable limits.

3.4 Thermal Evaluation under Hypothetical Accident Conditions The performance of the OP-100 package under Hypothetical Accident Conditions (HAC) was determined via testing in accordance with 10 CFR §71 .73. Additional details are provided in the following sections.

3.4.1 Initial Conditions A previously free and puncture dropped OP-100 certification test unit (CTU) package was placed into an oven and exposed to a forced convective environment that resulted in the average surface temperature of the package to at least 1,475 °F.

3.4.2 Fire Test Conditions Following the introduction of air and indication of the package surface at a minimum of 1,475 °F, thle package wvas maintained in the oven for 30 minutes. During the 30-minute test, the surface temperature varied between 1,470 0F and 1,627 °F. During heat-up, burning of the combustible materials was observed. Following the 30-minute test, the package was removed from the oven and allowed to cool in air.

A post-test examination of the package indicated that the both the plywood support structure and the polyurethane foam were completely consumed by the fire, adding its combustion energy to that of the forced convection from the oven. The depleted uranium shielding, and the outer skin of the package were not compromised or appreciably oxidized. Additionally, the peak temperatures recorded in the test were well below the melting temperatures of both stainless steel (2,800 0 F) and uranium (2,071 °F).

A post-test radiation survey conducted subsequent to the fire test indicated little, if any, degradation in shielding capability.

The special form qualification of the payload certifies that it could withstand the fire test without degradation.

3.4.3 Maximum Temperatures and Pressures Based the thermal tests performed on the OP-lO0 package, none of the components exceeds its temperature limit as described in Section 3.2.1, Material Properties. Specifically, the maximum recorded package temperatures fall more than 500 °F below the melting point of steel and uranium. Additionally, the special form payload does not exceed the temperatures for the special form certification tests.

71

INC OP-I100 Package SAR Docket No. 71 -91 85 Revision 4, 6/2015 The containment of the OP-lO0 package is provided by the special form payload. Gas can freely move from thle internal cavity to the environment during all phases of operation, so determination of internal pressures is not required.

This verifies that the OP-lO0 package satisfies the HAC thermal requirements set forth by 10 CFR §71.73(c)(4).

3.4.4 Maximum Thermal Stresses The effects of HAC thermal stresses were addressed by the fire test. No damage due to thermal stresses was found during post-test examination of the OP-lO0 CTU and the payload devices.

3.4.5 Accident Conditions for Fissile Material Packages for Air transport This section does not apply, since the OP-1OG package does not contain fissile material.

72

INC OP-I100 Package SAR Docket No. 71-91 85 Revision 4, 6/2015 3.5 Appendix 3.5.1 Determination of Maximum Surface Temperature for OP-I100 Package 73

ILP T EC ackgig ecnology, Inc.

Prepared Paul F. Stevens */**Date (9 [Z/?SI Revision 0~

Reviewed Phil W. Noss J***Date (,6/0 *,Page

  • ' 1 of 7 Approved Gary L. Clark 4: & -, Date
  • Project 98005 Title _Surface Temperature Calculation for INC OP-i!00 Package TABLE OF CONTENTS 1.0 OBJECTIVE................................................ .............................. 2

2.0 REFERENCES

....................................................................... .... 2 3.0 CALCULATION ASSUMPTIONS...................................................... 2 4.0 MATERIAL PROPERTIES ............................................................. 3 5.0 THERMAL LOADS ...................................................................... 3 6.0 ANALYTICAL CALCULATIONS ....................................................... 4 7.0

SUMMARY

OF RESULTS ............................................................. 7 REVISION LOG

,Revision!**.. .te*!'*.. . .!I:..i .tem Revised * . . .. ".*....., . .Reason~fOrRevision * .*.: .,** : * %.*.:

______ 1. I.

Packaging Technology, Inc., 4507-D Pacific Hwy East, Tacoma WA 98424-2633, 2*(253)922-1450 *(253)922-1445

PacTec Calculation Sheet Prepared Paul F. Stevens *)*z Date (o1,* /9." RevisionQ_

Reviewed Phil W. Noss //J'U4V Date 4.'"23/ ? Page 2_..of 7 Approved Gary L. Clark .. * *Date gt).e* Project 98005 Title Surface Temperature Calculation for INC OP-100 Package 1.0 OBJECTIVE The purpose of this calculation is to determine the peak surface temperatures on the Industrial Nuclear Company OP-I100 Package due to solar radiation per the regulations of 10 CFR 71.71(c)(I).

2.0 REFERENCES

I) Code of Federal Regulations, Title 10, Part 71, Packaging and Transportation of Radioactive Materials, 1/1/98.

2) EngineeringHeat Transfer, James R. Welty, John Wiley and Sons Publishing, New York, 1974.
3) Industrial Nuclear Company, OP-10O0 Package, Drawing OP- 100-1.
4) Handbook of Heat Transfer, Warren M. Rohsenow and James P. Hartnett, McGraw Hill Book Company, New York, 1973.
5) Principlesof Heat Transfer, Frank Kreith, Harper and Row Publishers, New York, 1973.

3.0 CALCULATION ASSUMPTIONS

  • Conductance along the carbon steel outer skin of the package is conservatively assumed to be negligible.
  • Solar radiation is assumed to be at a constant value that is 1/12th of the maximum solar radiation value as prescribed by 10 CFR 71 .71 (c)(l1) (Reference 1).
  • Ambient temperature is assumed to be at a constant temperature of I100°F (560 0 R) per Reference 1.
  • All surfaces, excepting the base, of the OP-100, experience turbulent natural convection.
  • Decay heat from OP- 100 payload is assumed to be negligible.

Packaging Technology, Inc., 4507-D Pacific Highway East, Tacoma WA 98424-2633, *(253)922-1450 *(f253)922-1445

PacTec Calculation Sheet Prepared Paul F. Stevens

  • Date CG{7*/99 Revision 0 Revewd PilW.Nos Dte / /-

Reviewed___PhilW.__Noss______/__ Date 6,/2/ IY Page _1_ of 7_

Approved Gary L. Clark ,,'- Date 4l2&*jfLProject 98005 Title Surface Temperature Calculation for INC OP-i100 Package 4.0 MATERIAL PROPERTIES Since conduction is conservatively neglected for the purposes of this calculation, the only pertinent material properties are the ernissivity and sOlar absorptivity of the paint on the exterior surface of the package.

Per Reference 3, the package may be painted yellow, or the lid and bottom of the package may be painted white, and its walls black. From Reference 4, page 3-22, the emissivity for white, silicone based paint, 8 whi~e, is 0.75, while its solar absorptivity, c~wt, is 0.26.

From the same source, the emissivity of black enamel paint, 6 black, is 0.84, and its absorptivity, Xblck, is 0.93. From Reference 5, page 237, the radiation properties of yellow paint are commensurate with those of white paint. Therefore, a drum with the white/black paint scheme will be the controlling case, as it will absorb more solar radiation and have higher temperatures than an all yellow drum.

Conductivity and kinematic viscosity of air affect convective heat transfer from the OP-100. These material properties are addressed by using simplified heat transfer equations for air as documented in Section 6.0.

5.0 THERMAL LOADS Since the decay heat source term of the OP-100 is negligible, the only pertinent thermal load is solar radiation (insolation). Per 10 CFR 71.71(c)(1) (Reference 1), the maximum insolation is as follows:

SufceOiettinTotal Insolation for 12 Average Heat Flux Hour Period (gcal/cm 2) (Btu/hr-ft2 )

Flat, horizontal (not base) 800 245.7 Flat, horizontal (base) 0 0.0 Flat, non-horizontal 200 61.4 Curved 400 122.9 PackagingTechnology, Inc., 4507-D Pacific Highway East, Tacoma WA 98424-2633, 2(253)922-1450 [J(253)922-1445

PacTec Calculation Sheet Prepared Paul F. Stevens i%§. Date /ZifL 99Revision()

Reviewed Phil W. Noss ,4i.)t. Date &/2*/* s" Page 4 of 7 Approved Gary L, Clark *.,*Date F/28 roject 98005 Title Surface Temperature Calculation for INC OP-100 Package 6.0 ANALYTICAL CALCULATIONS The simplified dimensions of the OP-100 used in the analytical calculations are shown in the figure below and are derived from Reference 3.

Wk' Vi-1 C So~iv* I; *-.*

.......... .)

2_--'..*-222--:L'*i P.,L .c ]--*<r, J* it LL

--5212 _-ii_-

-*---\---*'J/i' k)"

1 7..%"

-H2 _--_

  • .Z-_22*2.:ZZ-%-.I*;I ]

1.4." LI .19 "--

Determining the surface temperature of the OP- 100 in the shade with an ambient temperature of 100 0F (560 °R) in accordance with 10 CFR 71.43(g) (Reference 1), which stipulates a maximum accessible surface temperature of 122 0F for non-exclusive use shipments, is a trivial exercise. Without a significant decay heat load, the OP-100 will have a surface temperature of 100 °F (560 °F), and thereby meets the requirements of 10 CFR 7 1.43(g).

Packaging Technology, Inc., 4507-D Pacific H-fighway East, Tacoma WA 98424-2633, 'd(253)922-1450 *J(253)922-1445

PacTec Calculation Sheet Prepared Paul F. Stevens I* Date _______ Revision 0 Reviewed Phil W. Noss //.//JDate _______Page _5 of 7 Approved Gary L. Clark *"t**Date *Z?*2Project

-- 98005 Title Surface Tem~erature Calculation for INC OP-i100 Package The temperature for the curved, horizontal and vertical surfaces with maximum insolation

  • can be found by solving the following heat balance equation for each of the three geometries:

=Q rad,,

,,,io,, + Qe,,,vec~ijon where Qsoiar = Insolation value for the particular geometry. Cfaso

  • Area Qradiation = ay " suriface "Area- (T4sufface - T4*m~bjioj), a = 0.1714 x 10-8 Btu/hr-ft 2 -°R4 Qoeton= h *Area(T,,,rfce - Tainbient), h = free convection heat transfer coefficient From Reference 2, pp. 252-3, the general form of h at one atmosphere and moderate temperatures is:

Where a, b and L vary based on surface geometry, orientation and whether the free convection is turbulent or laminar. Since turbulent free convection is less efficient, it is conservatively assumed for this analysis that all surfaces on the OP- 100 will experience turbulent natural convection. The values for a, b and L for each orientation is presented below:

Simplified Turbulent Free Convection Equation Coefficients Flat Vertical Flat Horizontal Curved A 0.19 0.22 0.18 B 1/3 1/3 1/3 L 1.0 1.0 1.0 h=_________ 0.19AT 11 3 0.22AT"/3 0.18ATI/ 3 Packaging Technology, Inc., 4507-D Pacific Highway East, Tacoma WA 98424-26331 E(253)922-1450 *(253)922-1445

PacTec Calculation Sheet Prepared Paul F. Stevens 1/i Date cffj~g, Revision()

Reviewed Phil W. Noss ,Act*l) Date Pag 6 of 7 Approved Gary. L. Clark ,,*,**_' Date -

-- R*.Poet98005 Title Surface Temperature Calculation for INC OP-i100 Package For a unit area, the energy balance equations for each of the orientation is:

Flat Horizontal (non base)

Q,,,t,,r =245. 7 . 0 .2 6 =6 3 9. Bu hr 9 4 Q,,,jai,,v,, = O. 1714 x10-. *0.75. (T1,4,jce - 560 ) = 1.29 x 10- .(T,:,jac - 560 )

Tsurface = 596.9 °R or 136.9 °F Vertical Qxo~urhr Qr adiair,,

9

=0. 1714x10-s

  • 0.84. ( ,,f,,.e -5604 )=1.44x 10- *(T f,,ce*. 560 4 )
  • QCO,,,,CjI,,= 0.19 *(T~.,,,rja, --560)I/3 "(TL.,rjace -560)=0.19 *(T,,,¢de -560)4/3 Turface = 593.3 °R or 133.3 0F Curved All curved surfaces of the OP-0O0 are vertically oriented, and are addressed in the above vertical surface section.

Packaging Technology, Inc., 4507-D Pacific Highway East, Tacoma WA 98424-2633, 2(253)922-1450 *j(253)922-1445

PacTec Calculation Sheet Prepared Paul F. Stevens /, Date

  • 4('i I Revision()..

Reviewed Phil W. NOSS //Dae*///?Pae 7o Approved Gary L. Clark ,.-6-4*-* Date c_2vdf*"Project 98005 Title Surface Temperature Calculation for INC OP-1 00 Package 7.0

SUMMARY

OF RESULTS The maximum temperature for all surfaces of the OP-I100 in shade and an ambient temperature of 100 0 F (560 0R) is 100 0 F (560 0 R), which satisfies the requirements of 10 CFR 71.43(g). Under peak insolation, the maximum predicted surface temperature of the sides of the OP-100 would be 133.3 0 F (593.3 0 R), and the maximum predicted temperature of the top of the OP-1O0 is 136.9 °F (596.9 0R).

Packaging Technology, Inc., 4507-D Pacific Highway East, Tacoma WA 98424-2633, 2(253)922-1450 *(253)922-1445

INC OP-I100 Package SAR Docket No. 71 -91 85 Revision 4, 6/2015 4.0 CONTAINMENT The OP-100 package is designed as a means of confinement for a special form Ir-192 or Se-75 source capsule. Containment of radioactive material is provided by the special form construction of the payload. The sour-ce capsules and their respective special form certification are as follows:

Manufacture Model Number Certification Number A USA/0297/S-96 Industrial Nuclear Co., Inc.

791 USA/0393/S-96 SucPrdcin&VSe Source Capsule* USA/0785/S-96 Equipment Co., Inc.

  • Note: Source capsule is limited to a maximum of 120 Ci of Se-75 material.

Since the OP-100 packaging does not provide containment, subsequent sections of this chapter are not applicable.

78

INC OP-I100 Package SAR Docket No. 71 -91 85 Revision 4, 6/2015 5.0 SHIELDING EVALUATION This section demonstrates the shielding capability of the 1R-100 package design for the authorized special form contents. The shielding evaluation is demonstrated via prototypic testing in lieu of an analytical evaluation.

5.1 Description of Shielding Design 5.1.1 Design Features The OP-l00 package overpacks the IR-100 and IR-50 devices. Both the 1R-100 and IR-50 devices are a welded structure that contains a depleted uranium (DU) gamma shield, which surrounds a titanium S-tube. A stainless steel special form capsule, which contains either 120 Ci (4.44 TBq) oflIr-192 or Se-75 isotope, is inserted into thle S-tube via a pigtail assembly. The radioactive source is positioned at the center of the DU gamma shield to provide the maximum attenuation of the gamma radiation.

5.1.2 Summary Table of Maximum Radiation Levels Table 5-1 provides the maximum measured external radiation levels for either an IR-I00 or IR-50 device with the maximum payload content (120 Ci (4.44 TBq) lr-192) for a non-exclusive use shipment. Note that the values were measured for devices outside of the OP-100 package.

Table 5-1 - Maximum Measured External Radiation Levels. (Non-Exclusive Use)

Normal Conditions of Transport Hypothetical Accident Conditions Package 10 CFR §71.47(a) 10 CFR §71.51(c)(2)

Measurement Measured1 Limit Measured Limit Location mrem/hr (mSv/hr) mrem/hr (m~v/hr) mrem/hr (mSv/hr) mrem/hr (m~v/hr)

Surface 165 (1.65) 200 (2) N/A N/A 1 Meter from 1.6 (0.016) 10 (0.1) 1.9 (0.019) 1000 (10)

Surface __________ __________ __________ _________

5.2 Source Specification 5.2.1 Gamma Source The radioactive content of the OP-100 package is limited to 120 Ci (4.44 TBq) of h'-192 or~ Se-75 isotopes. As shown in Table 5-2, Ir-192 results in a higher unit dose than Se-75 per curie of activity. In addition, the photon energies of lr-1 92 are higher than for Se-75 (0.280 MeV average).

Therefore, the Ir-192 payload will bound the Se-75 payload for the 120 Ci (4.44 TBq) content.

Since actual lr-192 special form capsules are utilized to determine the acceptance of the DU gamma shielding, the tabulation of gamma decay source strengths for the special form capsules is not required for the OP- 100 package.

5.2.2 Neutron Source This section does not apply, since the OP-100 package does not contain fissile material.

79

INC OP-I100 Package SAR Docket No. 71 -9185 Revision 4, 6/2015 Table 5-2 - Sp*ecific Gamma Ray Constants for Iridium and Selenium IsotopesII Specific Gamma Ray Constant Radionuclide (R-m 2/hr-Ci)

Iridium- 192 0.460 Selenium-75 0.203 5.3 Shielding Model The shielding capability of the OP-100 package design is demonstrated by physical tests of prototypic packages. Therefore, no analytical shielding model of the package is performed.

5.4 Shielding Evaluation 5.4.1 Methods The method utilized to demonstrate the shielding performance of the OP-100 package is via prototypic testing utilizing an IR-100 or IR-50 device with a special form capsule containing radioactive lr-192 material.

5.4.2 Input and Output Data This section does not apply, since the shielding performance of the OP-l00 package is not performed analytically.

5.4.3 Flux-to-Dose-Rate Conversions This section does not apply, since the shielding performance of the OP-lO0 package is not performed analytically.

5.4.4 External Radiation Levels Following the specified tests of a prototypic package with a 120 C i (4.44 TBq) of Ir-192 payload per 2.6, Normal Conditions of Transport, and 2.7, Hypothetical Accident Conditions, the maximum radiation level measured on the surface and at i-meter of the IR-100 or IR-50 device is 165 mrem/hr (1 .65 mSv/hr) and 1.9 mrem/hr (0.019 mSv/hr), respectively. As noted in Table 5-I, these levels are well below the regulatory limits of 10 CFR §71.47(a) and 10 CFR §71.51(a)(2).

"Exposure Rate Constants and Lead Shielding Values for Over 1,100 Radionuclides", David S. Snmith and Michael G. Stabin, Department of Radiology and Radiological Sciences, Vanderbilt University, Nashville, TN, Health Physics Society Journal, March 2012 issue.

80

INC OP-I100 Package SAR Docket No. 71 -91 85 Revision 4, 6/2015

6.0 CRITICALITY EVALUATION

The OP-100 package does not transport fissile material; therefore, this section does not apply.

81

INC OP-I100 Package SAR Docket No. 71-91 85 Revision 4, 6/2015 7.0 PACKAGE OPERATIONS 7.1 Package Loading This section delineates the procedures for loading a payload into the OP-100 packaging.

Hereafter, reference to specific OP-lO0 packaging components may be found in Appendix 1.3.1, General Arrangement Drawings, OP-iO00 Package.

7.1.1 Preparation of the OP-100 Package for Loading

1) Visually inspect the OP-lO0 package for damage and/or missing parts.
2) Visually inspect the device (i.e., IR-l00 or IR-50) to be loaded into the OP-lO0 package.
3) Loosen and remove the closure ring bolt from the closure ring.
4) Remove the closure ring and the drum lid from the drum body.
5) Remove the two unsecured plywood cross members that allow an JR-t00 or an IR-50 device to be positioned within the plywood support structure.
6) Remove the Safety Plug and the dust cover (IR-100) or the dust caps (IR-50). Check the threads for wear or damage.
7) Inspect the Lock Box for damage or missing set screws. Replace any damaged or missing set screwvs.
8) PriOr to loading an active Ir- 192 or Se-75 source into anl IR- 100 or IR-50, insert a dummy source pigtail and functionally test the automatic locking device to ensure that all components are operating properly. The IR-100 and JR-5O locking devices shall be checked prior to each use.
9) Pull (retract) the dummy pigtail. The Safety Latch Plate will pop-up and lock the dummy source in the stored position. Rotate the key to the locked position and remove thle key.
10) Insert the key into the lock, retract (pull) the dummy source pigtail and rotate the key to the unlocked position. Manually depressed the Safety Latch Plate to the operate position and remove the dummy source pigtail.

7.1.2 Loading the Special Form Payload into the IR-100/IR-50 I) Place the special form h'-192 or Se-75 source pigtail assembly into a source changer.

2) Connect the drive cable housing and the guide tube to the IR-100 device.
3) Crank the drive cable out through the guide tube and connect it to the lr-192 or Se-75 source pigtail assembly. Connect the guide tube to the JR-5O device.
4) Unlock the JR-SO device and retract the lr-192 or Se-75 source pigtail assembly into the IR-100 device.
5) Survey the package to ensure that the source is in the stored position. Rotate key to locked position and remove the key.

82

INC OP-I100 Package SAR Docket No. 71 -91 85 Revision 4, 6/2015

6) Disconnect drive cable and install the Safety Plug and dust cap (IR-100) or the dust caps (IR-S0).
7) Install the Ir-192 or Se-75 source identification plate on the top of the IR-l00 device.
8) When transported in an IR-50 device, attach the Ir-192 or Se-75 source identification plate to the tamper seal wire of the IR-50 device for transfer with the Ir-192 or Se-75 source to an IR-100 device.

7.1.3 Preparation for Transport

1) Install the two tamper-indicating seals (security wire/lead seals). For the IR-l00 device, one tamper-indicating seal is located at the lock assembly; and the second is located at the Safety Plug. For the IR-50 device, the safety seals are located on each Lock Box and has a lock key attached.
2) Load the IR-100 or IR-50 device into the plywood support structure. Replace the two unsecured plywood cross members in their proper positions.
3) Replace drum lid.
4) Replace the closure ring and then the 5/8-inch x 4 inch closure ring hex bolt. As the hex bolt is tightened, ensure that the closure ring is fully seated around the circumference of the drum. Tighten the closure ring bolt to a snug tight condition.
5) Install the hex nut and tighten to a snug tight condition.
6) Install a tamper-indicating seal (security wire/lead seal) through the hex bolt.
7) Monitor external radiation per the guidelines of 49 CFR §173.441 12
8) Determine the shielding transport index for the loaded package per the guidelines of 49 CFR § 173.403.
9) Load the OP-l00 package onto the transport vehicle.
10) Complete all necessary shipping papers inl accordance with Subpart C of 49 CFR 172's.

1I) OP- 100 package marking shall be in accordance with 10 CFR §71 .85(c) and Subpart D of 49 CFR 172. Package labeling shall be in accordance with Subpart E of 49 CFR 172.

Packaging placarding shall be in accordance with Subpart F of 49 CFR 172.

7.2 Package Unloading This section delineates the procedures for unloading a payload into the OP-100 packaging.

Hereafter, reference to specific OP-100 package components may be found in Appendix 1.3.1, General Arrangement Drawings, OP-100 Package.

1-2Title 49, Code of Federal Regulations, Part 173 (49 CFR 173), Shippers-Gener'alRequirementsfor Shipments and Packagings, 10-1 -14 Edition.

'3 Title 49, Code of Federal Regulations, Part 172 (49 CFR 172), Hazardous M'aterials Tables and Hazardous Communications Regulations, 10-1 -14 Edition.

83

INC OP-I100 Package SAR Docket No. 71 -91 85 Revision 4, 6/2015 7.2.1 Receipt of Package from Carrier I) Remove the OP-l00 package from the transport vehicle.

2) Monitor the external radiation to ensure that the OP-100 package was not damaged during shipment. if Radiation readings or surface radioactive contamination levels exceed allowable limits contact the Radiation Safety Officer for instructions.

7.2.2 Removal of Contents from the OP-I100 Package I) Remove the tamper indicating wire seal. If tamper indicating seal is missing or broken, call Radiation Safety Officer for instructions. The RSO will investigate the incident before proceeding.

2) Remove the hex nut, closure ring hex bolt, the closure ring, and lid.
3) Remove the two unsecured plywood cross members and remove the device (i.e., IR-100 oi?

JR-SO device).

4) Remove the Safety Plug and the dust cap (JR-I 00) or the dust caps (JR-5O).
5) Connect the drive cable housing and the guide tube to the package. Connect the guide tube to a source changer.
6) Unlock the IR-l00 and IR-5O devices and extend the lr-192 or Se-75 source pigtail assembly into the IR-50 device.
7) Secure the Ir-192 or Se-75 source pigtail assembly in the IR-5O device, lock, and remove the key.
8) Disconnect the drive cable from the JR-5O device and retract it.
9) Disconnect the guide tube from the IR-50 and the IR-1 00 devices. Install the dust caps onl the IR-50 device, and the Safety Plug and dust cap on the IR-100 device. Remove the source identification from the IR-I00 device and install it on the JR-SO device.

7.2.3 Final Package Preparations for Transport of Unloaded OP-I100 Package

1) Complete all required shipping papers in accordance with Subpart C of 49 CFR 172.
2) OP-10O package marking shall be in accordance with 10 CFR §71.85(c) and Subpart D of 49 CFR 172. Package labeling shall be in accordance with Subpart E of 49 CFR 172.

Packaging placarding shall be in accordance with Subpart F of 49 CFR 172.

7.3 Preparation of an Empty Package for Transport Previously used and empty OP-100 packages shall be prepared and transported per the requirements of 49 CFR § 173.426, Subpart 1.

84

INC OP-I100 Package SAR Docket No. 71 -9185 Revision 4, 6/2015 8.0 ACCEPTANCE TESTS AND MAINTENANCE PROGRAM 8.1 Acceptance Tests Per the requirements of 10 CFR §71.85(c), this section discusses the inspections and tests to be performed prior to first use of the OP- 100 package.

8.1.1 Visual Inspections and Measurements All OP-100 package materials of construction and welds shall be examined in accordance with the requirements delineated on the drawings in Appendix 1.3.1, GeneralArrangement Drawings, per the requirements of 10 CFR §71.85(a).

8.1.2 Weld Examinations All welds on the IR-I00 and JR-SO devices shall be examined in accordance with the requirements delineated on the drawings in Appendix 1.3.1, General Arrangement Drawings, per the requirements of 10 CFR §71.85(a).

8.1.3 Structural and Pressure Tests The OP-lO0 package does not contain any lifting/tie-down devices or pressure boundaries that require load testing.

8.1.4 Leakage Tests The OP-10O package does not contain any seals or containment boundaries thlat require testing.

8.1.5 Component and Material Tests The OP-100 package does not contain any additional components or materials that require acceptance testing.

8.1.6 Shielding Tests A radiation profile is performed on each depleted uranium (DU) shield prior to being used in the fabrication of an IR-100 or IR-50 device. These measured survey results are ratioed upward to determine the expected radiation levels for the maximum authorize source strength of 120 Ci.

Any radiation profile of a DU shield which results in a dose rate that exceeds the requirements of 49 CFR § 173.441 with the maximum authorized payload shall not be utilized in thle manufacture of an IR-100 or JR-SO device.

8.1.7 Thermal Tests The OP-lO0 package does not contain any thermal features or systems that require testing.

Therefore, this section does not apply.

85

INC OP-I100 Package SAR Docket No. 71 -91 85 Revision 4, 6/2015 8.1.8 Miscellaneous Tests There are no additional acceptance tests required for thle OP- 10O0 packaging.

8.2 Maintenance Program This section describes the maintenance program used to ensure continued performance of the OP-l100 package.

8.2.1 Structural and Pressure Tests Thle OP-100 package does not contain any lifting/tie-down devices or pressure boundaries that require load testing.

8.2.2 Leakage Tests The OP-100 package does not contain any seals or containment boundaries that require testing.

8.2.3 Component and Material Tests 8.2.3.1 Fasteners All threaded components shall be inspected quarterly for deformed or stripped threads.

Damaged components shall be repaired or replaced prior to further use.

8.2.3.2 Lock Assembly Prior to each use, inspect the lock assembly for restrained motion. Any motion or operational impairing shall be corrected prior to fulrther use.

8.2.4 Thermal Tests No thermal tests are necessary to ensure continued performance of the OP-IlO0 packaging.

8.2.5 Miscellaneous Tests - Shielding Prior to each shipment, a radiation survey is performed to ensure that thle radiation dose levels do not exceed the requirements of 49 CFR § 173.441. This survey confirms that the DU shield has maintained its shielding function.

86

Retrieved from "https://kanterella.com/w/index.php?title=ML15223A428&oldid=2510992"