ML24169A142
| ML24169A142 | |
| Person / Time | |
|---|---|
| Site: | 07109315 |
| Issue date: | 02/01/2024 |
| From: | Consolidated Nuclear Security |
| To: | Office of Nuclear Material Safety and Safeguards |
| Shared Package | |
| ML24169A140 | List: |
| References | |
| EPID L-2022-LRM-0064 | |
| Download: ML24169A142 (1) | |
Text
Pre-Application Presentation Safety Analysis Report, Y-12 National Security Complex, Model ES-3100 Package with Bulk HEU Contents Y/LF-717, Rev. 5, Page Change 1, June 16, 2022 (Y/LF-717 001 05, Draft-Issued for Approval)
Docket 23-v34 -9315 NNSA NPO l February 01, 2024
Reactor Material Supply & Disposition Programs Consolidated Nuclear Security, LLC
1 Changes in the ES-3100 NRC SAR General overview of changes incorporated in Rev. 5, Page Change 1
Revised SAR format for consistency with U.S. Nuclear Regulatory Commission (NRC) Regulatory Guide 7.9, Rev. 2
Use of new thermal insulating and impact limiting material (Packcrete) as equivalent to Kaolite
Periodic maintenance interval extended from 1 to 2 years for ethylene propylene diene monomer (EPDM) O-rings
Addition of new contents requested by end users
Updated references to reflect current regulatory requirements
Use of more current shielding software for internal analyses of the ES-3100
Removed reference documents from chapter appendices and created separate volume
2 Changes to the ES-3100 NRC SAR Kaolite and Packcrete
Kaolite is the thermal insulating and impact limiting material used in all ES-3100 packagings originally manufactured
The vermiculite used in the original formula is no longer commercially available
Y-12 developed Packcrete as an equivalent to Kaolite to fabricate new ES -3100 packagings
Packcrete is still a mixture of Portland cement and vermiculite but with different vermiculite specification
Numerous material properties evaluated to confirm equivalency of Packcrete to Kaolite 1600
The U.S. Department of Energy (DOE) Packaging Certification Program (PCP)approved Packcrete as equivalent to Kaolite in 2021 (DOE CoC 9315, Rev. 18)
Packcrete is being used in 200 new ES-3100 packagings fabricated at Wagstaff Applied Technologies (Spokane, WA)
3 Changes to the ES-3100 NRC SAR EPDM O-ring maintenance interval
The periodic maintenance interval for leakage testing of the ES-3100 containment vessel was based on American National Standards Institute (ANSI) N14.5-1997 (i.e., within 12 months prior to shipment)
In 2019, DOE approved a periodic maintenance interval of 24 months in DOE CoC 9315, Rev. 16, based on the justification provided by Y-12 and the guidance in ANSI N14.5 -2014
The 2-year periodic maintenance interval is included in the DOE PCP approved ES -3100 SARP (SP-PKG-801940 -A001, Safety Analysis Report For Packaging, Y-12 National Security Complex, Model ES-3100 Package with Bulk HEU Contents )
Substantial cost savings
Improved availability rate of ES-3100 packagings within Y -12
4 Changes to the ES-3100 NRC SAR Additional contents added
Tristructural-isotropic (TRISO) micro fuel particles
Added uranium compounds [UC, U 2C3, or UC2 (TRISO)] to Table 1.3 with supporting analyses
235U assay 93.17%
Typically in a solid crystalline or granular form
Finished TRISO fuel particle: kernel of UOX (or UC or UCO) coated with 4 layers of 3isotropic materials:
porous buffer layer of carbon dense inner layer of pyrolytic carbon (PyC) ceramic layer of SiC (to retain fission products at elevated temps and to give structural integrity to TRISO particle) dense outer layer of PyC.
Bounding TRISO calculation models consists of uranium carbide (UC) homogeneously mixed with water inside of the CV, modeled with the uranium enriched at 100% 235U.
Mass loading limits for TRISO in the NRC SAR (2 kg TRISO, 1.903 kg 235U)
500 grams of polyethylene is also homogeneously mixed with the UC and water
5 Changes to the ES-3100 NRC SAR Additional contents added
Tristructural-isotropic (TRISO) micro fuel particles (cont.)
Authorized Content for TRISO :
6 Changes to the ES-3100 NRC SAR Additional contents added (cont.)
Increased the transuranic impurity allowance for the highly enriched uranium (HEU) metal and alloy contents transported by ground from 40 to 800 g/gU
Clarified the behavior of uranyl nitrate crystals upon exposure to elevated temperatures
Clarified that bagging may be polyethylene, nylon, or Teflon
7 Changes to the ES-3100 NRC SAR Chapter 1. General Information
Added uranium compounds [UC, U2C3, or UC2 (TRISO)] to Table 1.3 with supporting analyses
Increased the transuranic impurity allowance for the HEU metal and alloy contents transported by ground from 40 to 800 g/gU
Clarified the behavior of uranyl nitrate crystals upon exposure to elevated temperatures
Clarified that bagging may be polyethylene, nylon, or Teflon.
8 Changes to the ES-3100 NRC SAR Chapter 2. Structural Evaluation; Chapter 3. Thermal Evaluation; and Chapter 4. Containment
Incorporated the requirements of NRC Regulatory Guide 7.9, Rev. 2
Evaluated the additional use of unirradiated research reactor fuel elements and compounds and uranium carbide compounds Added rod, plates, and tubes to the chemical and physical forms of material for transport
Addressed additional void volume requirements for containment vessel arrangements with closed convenience cans with diameters >10.8 cm (>4.25 in.)
A void volume at least 43 in.3 must be provided for gas expansion and offgassing of material at temperatures associated with normal conditions of transport (NCT) or hypothetical accident conditions (HAC)
If a closed convenience can has a hole (0.125 in. minimum diameter) in the lid, the void volume inside that convenience can may be used to meet this void volume requirement
Clarified that bagging may be polyethylene, nylon, or Teflon If Teflon bottles are used for shipping, the allowable offgassing material limit is increased from 500 to 1490 g.
Increased transuranic maximum concentration from 40 to 800 g/gU (except for 237Np) for ground transportation, which increased maximum evaluated decay heat from 0.4 to 5 W 9
Changes to the ES-3100 NRC SAR Chapter 2. Structural Evaluation; Chapter 3. Thermal Evaluation; and Chapter 4. Containment (cont.)
Added Packcrete as a substitute for Kaolite for thermal insulating and impact limiting material using material properties in RP 802282-0002, Packcrete Material Properties
10 Changes to the ES-3100 NRC SAR Chapter 2. Structural Evaluation; Chapter 3. Thermal Evaluation; and Chapter 4. Containment (cont.)
Added Packcrete as a substitute for Kaolite for thermal insulating and impact limiting material using material properties in RP 802282-0002, Packcrete Material Properties
11 Changes to the ES-3100 NRC SAR Chapter 2. Structural Evaluation; Chapter 3. Thermal Evaluation; and Chapter 4. Containment (cont.)
Added Packcrete as a substitute for Kaolite for thermal insulating and impact limiting material using material properties in RP 802282-0002, Packcrete Material Properties
Revised thermal analysis for NCT due to increase in decay heat Revised thermal stress evaluation for NCT Revised American Society of Mechanical Engineers Boiler and Pressure Vessel code calculation for containment vessel due to increased NCT temperatures and maximum normal operating pressure inside containment vessel
Revised all stress calculations for various environment conditions stipulated by 10 CFR 71.71 Removed older versions from SAR Included new analyses in DAC instead of appendices
Revised chemical, galvanic or other reactions section to discuss uranyl nitrate crystals and Teflon bottle use.
Added effects of radiation on the O-ring material Increased O-ring periodic maintenance interval from 1 to 2 years supported by testing documented in RP 801580-0022, ES-3100 Containment Vessel (CV) O -rings Life Extension Testing
12 Changes to the ES-3100 NRC SAR Chapter 2. Structural Evaluation; Chapter 3. Thermal Evaluation; and Chapter 4. Containment (cont.)
Incorporated the following criteria and guidance because some contents may be transported by air International Atomic Energy Agency (IAEA) SSR-6, para. 621, states: Packages containing radioactive material, to be transported by air, shall be capable of withstanding, without loss or dispersal of radioactive contents from the containment system, an internal pressure that produces a pressure differential of not less than the maximum normal operating pressure plus 95 kPa.
In order to also comply with 49 CFR 173.410(i)(2), the range of temperature evaluated will be from 40 to 55°C (ambient temperature)
According to IAEA SSG-26, para. 621.3, the evaluation at an ambient temperature of 55° C does not consider the solar radiation input; however, self-heating of the package is taken into account
Incorporated new decay heat load and applied solar insolation prior to and following thermal testing in HAC thermal analysis in accordance with 10 CFR 71.73 c (4)
Revised all stress calculations for various environment conditions stipulated by 10 CFR 71.73
Revised regulatory leakage rate criteria for this package to reflect increases in temperature and pressure during both NCT and HAC due to the revised decay heat load, the incorporation of solar insolation during thermal testing, and air transport requirements
13 Changes to the ES-3100 NRC SAR Chapter 5. Shielding Evaluation
Used detailed vs simplified geometry model
Used MCNP code vs MORSE code (not supported by Oak Ridge National Laboratory now)
Added side dose rates for different HEU metal source configurations (Table 5.7)
Included graphical presentation of dose rates (using Java Mesh File Viewer from SCALE 6.1 package)
Added Packcrete vs Kaolite dose rate comparison (Appendix 5.5.3)
Added O-ring dose rate calculations
14 Changes to the ES-3100 NRC SAR Chapter 5. Shielding Evaluation
ES-3100 packaging detailed model
15 Changes to the ES-3100 NRC SAR Chapter 5. Shielding Evaluation
Sample calculation model of the ES-3100 shipping package for NCT with cylindrical hemi-shell source configuration shown in yellow (sectional x-z and x-y views)
16 Changes to the ES-3100 NRC SAR Chapter 5. Shielding Evaluation
Sample photon dose rate contours for the cylinder at the top of CV configuration (x-z plane)
17 Changes to the ES-3100 NRC SAR Chapter 5. Shielding Evaluation
Added Packcrete as the new thermal insulating and impact limiting material
Performed comparative dose rates at the surface and 1 m from the surface
For all source configurations for NCT and HAC cases
Minor statistical differences are observed (Appendix 5.5.3)
Therefore, Packcrete can be used as the impact limiting and thermal insulating material
18 Changes to the ES-3100 NRC SAR Chapter 6. Criticality Evaluation
Added uranium compounds [UC, U2C3, or UC2 (TRISO)] with supporting analyses
Performed parametric studies for mass for UC, U 2C3, and UC2
19 Changes to the ES-3100 NRC SAR Chapter 6. Criticality Evaluation (cont.)
Tristructural-isotropic (TRISO) micro fuel particles (cont.)
Results for uranium carbide compounds (TRISO fuel) in the CV and ES -3100 packaging calculation models
- UC content and 500 g polyethylene, flooded containment vessel, single reflected package
235U Sat. CV case name UCx(g)(g)H2O H2O h/x keff keff+2 (g) (g) 5cvcrpuct11_1_10 10,000 9,514 4,259 4,663 26.24 0.91168 0.00161 0.91491 5cvcrpuct11_1_9 9,000 8,563 3,833 5,163 29.38 0.90134 0.00158 0.90450 5cvcrpuct11_1_8 8,000 7,612 3,407 5,662 33.30 0.89789 0.00126 0.90041 5cvcrpuct11_1_7 7,000 6,660 2,981 6,161 38.34 0.88176 0.00129 0.88435 5cvcrpuct11_1_6 6,000 5,709 2,555 6,660 45.07 0.86805 0.00174 0.87154 5cvcrpuct11_1_5 5,000 4,757 2,129 7,159 54.49 0.84990 0.00147 0.85284 5cvcrpuct11_1_4 4,000 3,806 1,704 7,658 68.61 0.82598 0.00192 0.82982 5cvcrpuct11_1_3 3,000 2,854 1,278 8,157 92.15 0.78650 0.00210 0.79070 5cvcrpuct11_1_2 2,000 1,903 852 8,656 139.22 0.73220 0.00137 0.73494 5cvcrpuct11_1_1 1,000 952 426 9,155 280.42 0.64502 0.00133 0.64769
20 Changes to the ES-3100 NRC SAR Chapter 6. Criticality Evaluation (cont.)
Tristructural-isotropic (TRISO) micro fuel particles (cont.)
Results for uranium carbide compounds (TRISO fuel) in the CV and ES -3100 packaging calculation models
- UC content with 500 g polyethylene, flooded containment vessel, flooded package, reflected
UC 235U S at. CV cas e n ame x H2O H2O h /x kef f kef f+2 (g ) (g ) (g ) (g )
5 n c s r p u ct11 _1_ 10_1 5 10,000 9,514 4,259 4,663 26.24 0.81163 0.00116 0.81395 5 n c s r p u ct11 _1_ 9_15 9,000 8,563 3,833 5,163 29.38 0.80769 0.00145 0.81060 5 n c s r p u ct11 _1_ 8_15 8,000 7,612 3,407 5,662 33.30 0.79915 0.00170 0.80254 5 n c s r p u ct11 _1_ 7_15 7,000 6,660 2,981 6,161 38.34 0.78922 0.00142 0.79207 5 n c s r p u ct11 _1_ 6_15 6,000 5,709 2,555 6,660 45.07 0.77601 0.00157 0.77915 5 n c s r p u ct11 _1_ 5_15 5,000 4,757 2,129 7,159 54.49 0.75825 0.00153 0.76130 5 n c s r p u ct11 _1_ 4_15 4,000 3,806 1,704 7,658 68.61 0.73808 0.00130 0.74068 5 n c s r p u ct11 _1_ 3_15 3,000 2,854 1,278 8,157 92.15 0.70280 0.00142 0.70564 S at. CV cas e n ame UCx 235U H O H O h /x k k +2 (g ) (g ) 2 2 mo ifr ef f ef f (g ) (g )
5 n c s r p u ct11 _1_ 2_15 2,000 1,903 852 8,656 139.22 1.0E+00 0.65451 0.00136 0.65724 5 n c s r p u ct11 _1_ 2_8 2,000 1,903 852 2,597 56.11 3.0E-01 0.62741 0.00153 0.63046 5 n c s r p u ct11 _1_ 2_6 2,000 1,903 852 866 32.37 1.0E-01 0.61746 0.00123 0.61991 5 n c s r p u ct11 _1_ 2_5 2,000 1,903 852 87 21.68 1.0E-02 0.61244 0.00119 0.61482 5 n c s r p u ct11 _1_ 2_4 2,000 1,903 852 9 20.61 1.0E-03 0.61168 0.00122 0.61413 5 n c s r p u ct11 _1_ 2_3 2,000 1,903 852 1 20.51 1.0E-04 0.61271 0.00127 0.61524 5 n c s r p u ct11 _1_ 2_2 2,000 1,903 852 0 20.50 1.0E-05 0.61238 0.00127 0.61493 5 n c s r p u ct11 _1_ 2_1 2,000 1,903 852 0 20.50 1.0E-20 0.61350 0.00158 0.61667 5 n c s r p u ct11 _1_ 1_15 1,000 952 426 9,155 280.42 1.0E+00 0.57240 0.00136 0.57511 21
Changes to the ES-3100 NRC SAR Chapter 6. Criticality Evaluation (cont.)
Tristructural-isotropic (TRISO) micro fuel particles (cont.)
Infinite array package calcs for bulk saturated UC compound in fully flooded CV and homogeneously mixing UC compound throughout flooded CV. Results found below:
Results for uranium carbide compounds (TRISO fuel) in the CV and ES -3100 packaging calculation models UC 235U S at. CV cas e n ame (g )x (g ) H2O H2O h /x mo ifr kef f kef f+2 (g ) (g )
UC c o n t en t, 500 g p o ly, flo o d e d c o n t a inme n t v e s se l, in fin it e a r r a y o f p a c k a g e s 5 n c i a p u ct1 1_ 1_9_ 3 9,000 8,563 3,833 5,163 29.38 1.0E-04 0.90795 0.00136 0.9106 5 n c i a p u ct1 1_ 1_8_ 3 8,000 7,612 3,407 5,662 33.30 1.0E-04 0.89136 0.00139 0.8941 5 n c i a p u ct1 1_ 1_7_ 3 7,000 6,660 2,981 6,161 38.34 1.0E-04 0.87019 0.00131 0.8728 5 n c i a p u ct1 1_ 1_6_ 3 6,000 5,709 2,555 6,660 45.07 1.0E-04 0.84331 0.00140 0.8461 5 n c i a p u ct1 1_ 1_5_ 3 5,000 4,757 2,129 7,159 54.49 1.0E-04 0.81542 0.00127 0.8179 5 n c i a p u ct1 1_ 1_4_ 3 4,000 3,806 1,704 7,658 68.61 1.0E-04 0.78005 0.00139 0.7828 5 n c i a p u ct1 1_ 1_3_ 3 3,000 2,854 1,278 8,157 92.15 1.0E-04 0.73291 0.00130 0.7355 5 n c i a p u ct1 1_ 1_2_ 3 2,000 1,903 852 8,656 139.22 1.0E-04 0.67136 0.00129 0.6739 5 n c i a p u ct1 1_ 1_1_ 3 1,000 952 426 9,155 280.42 1.0E-04 0.57485 0.00114 0.5771 UC c o n t en t, 500 g p o ly, d is p e r s e d in flo o d e d c o nt a in me nt v e s se l, in fin it e a r r a y o f p a c k a g e s 5 n c i a d p u ct1 1_1_ 9_1 5_3 9,000 8,563 8,995 29.38 1.0E-04 1.02430 0.00136 1.0270 5 n c i a d p u ct1 1_1_ 8_1 5_3 8,000 7,612 9,069 33.30 1.0E-04 1.01560 0.00151 1.0186 5 n c i a d p u ct1 1_1_ 7_1 5_3 7,000 6,660 9,142 38.34 1.0E-04 1.00614 0.00147 1.0090 5 n c i a d p u ct1 1_1_ 6_1 5_3 6,000 5,709 9,215 45.07 1.0E-04 0.99808 0.00135 1.0007 5 n c i a d p u ct1 1_1_ 5_1 5_3 5,000 4,757 9,288 54.49 1.0E-04 0.98482 0.00115 0.9871 5 n c i a d p u ct1 1_1_ 4_1 5_3 4,000 3,806 9,362 68.61 1.0E-04 0.96658 0.00121 0.9689 5 n c i a d p u ct1 1_1_ 3_1 5_3 3,000 2,854 9,435 92.15 1.0E-04 0.94085 0.00131 0.9434 5 nciadpuct 1 1 _1_ 2_1 5_3 2,000 1,903 9,508 139.22 1.0E-04 0.89104 0.00175 0.8945 5 n c i a d p u ct1 1_1_ 1_1 5_3 1,000 952 9,581 280.42 1.0E-04 0.78231 0.00129 0.7848 22
Changes to the ES-3100 NRC SAR Chapter 6. Criticality Evaluation (cont.)
Added new thermal insulating and impact limiting material (Packcrete), shown as equivalent to Kaolite Performed parametric studies varying the density and water content that show Kaolite bounds Packcrete In the calculations for a single package, the maximum amount of water in both Kaolite and Packcrete was modeled. This value of water is the amount of water mixed with the dry constituent prior to baking as in the original Kaolite calculations. The maximum amount of water in Kaolite is more reactive in single package calculations than in array calculations as shown in the original Kaolite calculations.
Note that the original Kaolite input decks were rerun using a newer version of SCALE, the same version used for Packcrete.
Co mp arativ e Ca lc u la t io n s K a o lit e v s Pa c k c r e t e fo r S in g le Pa c k a g e M a ximu m A mo u n t o f W a t e r in K a o lit e a n d Pa c k c r e t e O r ig in a l K a o lit e Packcrete
(* p )
D e s c r ip t io n Cas e Name kef f + 2 kef f + 2 Slug s, no s pa cer s, 18, 277 g 235U ns cr5s t 11_1_1_15 0. 88510 0. 88727 B r oken met a l, no s pa cer s, 100% enr ichment, 35, 142 g 235U ncs rbmt 11_36_1_5 0. 80799 0. 81753 C ylinders (3. 24 < d 4. 25 in. ), no s pa cers, 17 kg 235U ncs rcyct 11_17_1_15 0. 89674 0. 89755 H E U pr oduc t ox ide, no s pa c e r s, 2 4 kg U O2 ncs rpdoxt 11_1_3_24 0. 80888 0. 80936 Squa r e ba r s (l, w 2. 29), no s pa c e r s, 36 kg 235U ncs rs qt 11_36_1_15 0. 86569 0. 86544 T hree 5" t a ll T R I GA fuel per ca n, 921 g 235U ncs rt rig a _1_15_15 0. 49314 0. 49477
23 Changes to the ES-3100 NRC SAR Chapter 6. Criticality Evaluation (cont.)
Added new thermal insulating and impact limiting material (Packcrete), shown as equivalent to Kaolite Packcrete modeled with minimum amount of water from the samples documented in RP 802282-0002-000- 02, the keff + 2 is lower than original Kaolite cases minimum amount of water from the Packcrete samples is significantly higher than Kaolite samples Additional water reduces the interaction between ES-3100 packages For array package calcs, modeling Packcrete with minimum amount of water based on the Packcrete samples is significantly less reactive than Kaolite modeled with minimum amount of water based on the Kaolite samples
Co mp a r a t iv e c a lc u la t io n s K a o lit e v s Pa c k c r e t e fo r A rray D e s c r ip t io n Cas e Name K a o lit e Pack crete
( Min H2O f r o m )
P ackcr e t e Kaolit e kef f + 2 (* p) (* pp) kef f + 2 kef f + 2 S l u gs, n o sp ac e r s, 1 7,374 g 235U n c i a 5 s t1 1 _1_ 1_7_ 3 0.91136 0.89351 0.91034 Broken metal, spacers, 100% enrichment, 2,774 g 235U n c i ab mt1 1 _3 _2_8 _3 0.90273 0.84435 0.90395 Br oke n me tal, no spac er s, 6 0 % e nrichment, 5,5 7 7 g U n c i ab mt1 1 _6 _1_3 _3 0.91388 0.84843 0.91525 C y l i n d e r s ( 3. 2 4 < d 4. 2 5 i n. ), n o s p a c e r s, 1 5 k g 235U n c i a c y c t11 _15 _1_3 0.90084 0.88652 0.89964 HEU pr oduc t ox ide, no spac er s, 9.6 8 2 kg UO2 n c i a p d o x t11 _1_1 _11_3 0.91708 0.86921 0.91666 S q u a r e b a r s ( l, w 2. 2 9 ), n o s p a c e r s, 3 0 k g 235U nciasqt11_30_1_3 0.92164 0.90075 0.92265 Three 5" tall TRIGA fuel per can, 921 g 235U n c i a tr i g a _ 1 _15_ 3 0.52611 0.50711 0.52574
24 Changes to the ES-3100 NRC SAR Chapter 6. Criticality Evaluation (cont.)
Added new thermal insulating and impact limiting material (Packcrete), shown as equivalent to Kaolite
It is important to note that there were more Kaolite samples than Packcrete samples, which may be why the minimum water in the Packcrete is higher than Kaolite, which could be an issue.
To address potential concern, additional cases were run using the minimum amount of water used in the Kaolite models in the Packcrete models for comparison purposes.
Results show when modeling the minimum amount of water in the Packcrete models the same as in in the Kaolite models, there is very little difference in the reactivity between the two types of concrete.
25 Changes to the ES-3100 NRC SAR Chapter 6. Criticality Evaluation (cont.)
Added new thermal insulating and impact limiting material (Packcrete), shown as equivalent to Kaolite
Calculations were performed modeling Kaolite and Packcrete with no water. Both were modeled at average density. This model will examine the effects that the dry constituents have on reactivity.
Co mp a r a t iv e c a lc u la t io n s K a o lit e v s Pa c k c r e t e fo r A r r a y wit h N o W ater P ackcr e t e Kaolit e P ackcr e t w / no H2O w / no H2 D e s c r ip t io n Cas e Name kef f + 2 kef f + 2 kef f + 2 S l u gs, n o sp ac e r s, 1 7,374 g 235U n c i a 5 s t1 1 _1_ 1_7_ 3 0.89351 0.92770 0.92562 Broken metal, spacers, 100% enrichment, 2,774 g 235U n c i ab mt1 1 _3 _2_8 _3 0.84435 0.96678 0.96794 Br oke n me tal, no spac er s, 6 0 % e nrichment, 5,5 7 7 g U n c i ab mt1 1 _6 _1_3 _3 0.84843 0.98300 0.98429 C y l i n d e r s ( 3. 2 4 < d 4. 2 5 i n. ), n o s p a c e r s, 1 5 k g 235U nciacyct11 _15 _1_3 0.88652 0.91184 0.91049 HEU pr oduc t ox ide, no spac er s, 9.6 8 2 kg UO2 n c i a p d o x t11 _1_1 _11_3 0.86921 0.96642 0.96605 S q u a r e b a r s ( l, w 2. 2 9 ), n o s p a c e r s, 3 0 k g 235U nciasqt11_30_1_3 0.90075 0.94455 0.94494 Three 5" tall TRIGA fuel per can, 921 g 235U n c i a tr i g a _ 1 _15_ 3 0.50711 0.54348 0.54350
When modeling no water in Kaolite and Packcrete, there is no difference in reactivity Reactivity effects of the Kaolite and Packcrete are based on the amount of water in the Kaolite and Packcrete, not the dry constituents Based on these calculation results, it can be concluded that Kaolite will bound the use of Packcrete in the ES-3100
26 Changes to the ES-3100 NRC SAR Chapter 6. Criticality Evaluation (cont.)
Clarified that bagging may be polyethylene, nylon, or Teflon
Hydrogen density of nylon and Teflon is less than polyethylene
Teflon has no hydrogen atoms
27 Changes to the ES-3100 NRC SAR Chapter 7. Package Operations
Added package description information
Added instructions on placement and type of labels, tags, stickers, tape, or document holders
Added requirement to control packaging components and minimize damage
All replacement parts must be traceable
28 Changes to the ES-3100 NRC SAR Chapter 8. Acceptance Tests and Maintenance Program
Added requirement to control packaging components and minimize damage All replacement parts must be traceable Added information regarding use of forklift tines or pincher assembly
Included Packcrete as a replacement for Kaolite
Added Table 8.3, Acceptance tests for packing materials
Added weld examination details to Sect. 8.1.2
Added pressure test details to Sect. 8.1.3.3
Revised leakage test requirement from annually to a 2-year basis
Included containment vessel O-ring storage requirements (i.e., not stored more than 4 years)
Included detailed requirements for visual inspection of containment vessel in Sect. 8.2.5.2
Included requirements for silicone rubber pads in Sect. 8.2.5.6
29 Changes to the ES-3100 NRC SAR Proposed Schedule for Certificate of Conformance
Y-12 realizes that this is a major revision to the SAR, and that time required for the regulatory review is difficult to estimate
Y-12 proposes that the NRC endeavor to complete the review cycle and issue a revised Certificate of Conformance (CoC) to Y-12 by October 31, 2024
30 Changes to the ES-3100 NRC SAR Questions?
31