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
v 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 23-34-9315 NNSA NPO l February 01, 2024 Reactor Material Supply & Disposition Programs Consolidated Nuclear Security, LLC 1
Changes in the ES-3100 NRC SAR 2
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
Changes to the ES-3100 NRC SAR 3
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)
Changes to the ES-3100 NRC SAR 4
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
Changes to the ES-3100 NRC SAR 5
Additional contents added
Tristructural-isotropic (TRISO) micro fuel particles
Added uranium compounds [UC, U2C3, 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
Changes to the ES-3100 NRC SAR 6
Additional contents added
Tristructural-isotropic (TRISO) micro fuel particles (cont.)
Authorized Content for TRISO:
Changes to the ES-3100 NRC SAR 7
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
Changes to the ES-3100 NRC SAR 8
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.
Changes to the ES-3100 NRC SAR 9
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
Changes to the ES-3100 NRC SAR 10 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
Changes to the ES-3100 NRC SAR 11 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
Changes to the ES-3100 NRC SAR 12 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
Changes to the ES-3100 NRC SAR 13 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
Changes to the ES-3100 NRC SAR 14 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
Changes to the ES-3100 NRC SAR 15 Chapter 5. Shielding Evaluation ES-3100 packaging detailed model
Changes to the ES-3100 NRC SAR 16 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)
Changes to the ES-3100 NRC SAR 17 Chapter 5. Shielding Evaluation Sample photon dose rate contours for the cylinder at the top of CV configuration (x-z plane)
Changes to the ES-3100 NRC SAR 18 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
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, U2C3, and UC2 19
Changes to the ES-3100 NRC SAR 20 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 case name UCx (g) 235U (g)
Sat.
H2O (g)
CV H2O (g) h/x keff
keff+2 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
Changes to the ES-3100 NRC SAR 21 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 case name UCx (g) 235U (g)
Sat.
H2O (g)
CV H2O (g) h/x keff keff+2 5ncsrpuct11_1_10_15 10,000 9,514 4,259 4,663 26.24 0.81163 0.00116 0.81395 5ncsrpuct11_1_9_15 9,000 8,563 3,833 5,163 29.38 0.80769 0.00145 0.81060 5ncsrpuct11_1_8_15 8,000 7,612 3,407 5,662 33.30 0.79915 0.00170 0.80254 5ncsrpuct11_1_7_15 7,000 6,660 2,981 6,161 38.34 0.78922 0.00142 0.79207 5ncsrpuct11_1_6_15 6,000 5,709 2,555 6,660 45.07 0.77601 0.00157 0.77915 5ncsrpuct11_1_5_15 5,000 4,757 2,129 7,159 54.49 0.75825 0.00153 0.76130 5ncsrpuct11_1_4_15 4,000 3,806 1,704 7,658 68.61 0.73808 0.00130 0.74068 5ncsrpuct11_1_3_15 3,000 2,854 1,278 8,157 92.15 0.70280 0.00142 0.70564 case name UCx (g) 235U (g)
Sat.
H2O (g)
CV H2O (g) h/x moifr keff keff+2 5ncsrpuct11_1_2_15 2,000 1,903 852 8,656 139.22 1.0E+00 0.65451 0.00136 0.65724 5ncsrpuct11_1_2_8 2,000 1,903 852 2,597 56.11 3.0E-01 0.62741 0.00153 0.63046 5ncsrpuct11_1_2_6 2,000 1,903 852 866 32.37 1.0E-01 0.61746 0.00123 0.61991 5ncsrpuct11_1_2_5 2,000 1,903 852 87 21.68 1.0E-02 0.61244 0.00119 0.61482 5ncsrpuct11_1_2_4 2,000 1,903 852 9
20.61 1.0E-03 0.61168 0.00122 0.61413 5ncsrpuct11_1_2_3 2,000 1,903 852 1
20.51 1.0E-04 0.61271 0.00127 0.61524 5ncsrpuct11_1_2_2 2,000 1,903 852 0
20.50 1.0E-05 0.61238 0.00127 0.61493 5ncsrpuct11_1_2_1 2,000 1,903 852 0
20.50 1.0E-20 0.61350 0.00158 0.61667 5ncsrpuct11_1_1_15 1,000 952 426 9,155 280.42 1.0E+00 0.57240 0.00136 0.57511
Changes to the ES-3100 NRC SAR 22 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 case name UCx (g) 235U (g)
Sat.
H2O (g)
CV H2O (g) h/x moifr keff keff+2 UC content, 500 g poly, flooded containment vessel, infinite array of packages 5nciapuct11_1_9_3 9,000 8,563 3,833 5,163 29.38 1.0E-04 0.90795 0.00136 0.9106 5nciapuct11_1_8_3 8,000 7,612 3,407 5,662 33.30 1.0E-04 0.89136 0.00139 0.8941 5nciapuct11_1_7_3 7,000 6,660 2,981 6,161 38.34 1.0E-04 0.87019 0.00131 0.8728 5nciapuct11_1_6_3 6,000 5,709 2,555 6,660 45.07 1.0E-04 0.84331 0.00140 0.8461 5nciapuct11_1_5_3 5,000 4,757 2,129 7,159 54.49 1.0E-04 0.81542 0.00127 0.8179 5nciapuct11_1_4_3 4,000 3,806 1,704 7,658 68.61 1.0E-04 0.78005 0.00139 0.7828 5nciapuct11_1_3_3 3,000 2,854 1,278 8,157 92.15 1.0E-04 0.73291 0.00130 0.7355 5nciapuct11_1_2_3 2,000 1,903 852 8,656 139.22 1.0E-04 0.67136 0.00129 0.6739 5nciapuct11_1_1_3 1,000 952 426 9,155 280.42 1.0E-04 0.57485 0.00114 0.5771 UC content, 500 g poly, dispersed in flooded containment vessel, infinite array of packages 5nciadpuct11_1_9_15_3 9,000 8,563 8,995 29.38 1.0E-04 1.02430 0.00136 1.0270 5nciadpuct11_1_8_15_3 8,000 7,612 9,069 33.30 1.0E-04 1.01560 0.00151 1.0186 5nciadpuct11_1_7_15_3 7,000 6,660 9,142 38.34 1.0E-04 1.00614 0.00147 1.0090 5nciadpuct11_1_6_15_3 6,000 5,709 9,215 45.07 1.0E-04 0.99808 0.00135 1.0007 5nciadpuct11_1_5_15_3 5,000 4,757 9,288 54.49 1.0E-04 0.98482 0.00115 0.9871 5nciadpuct11_1_4_15_3 4,000 3,806 9,362 68.61 1.0E-04 0.96658 0.00121 0.9689 5nciadpuct11_1_3_15_3 3,000 2,854 9,435 92.15 1.0E-04 0.94085 0.00131 0.9434 5nciadpuct11_1_2_15_3 2,000 1,903 9,508 139.22 1.0E-04 0.89104 0.00175 0.8945 5nciadpuct11_1_1_15_3 1,000 952 9,581 280.42 1.0E-04 0.78231 0.00129 0.7848
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.
23 Comparative Calculations Kaolite vs Packcrete for Single Package Maximum Amount of Water in Kaolite and Packcrete Original Kaolite Packcrete
(*p)
Description Case Name keff + 2 keff + 2 Slugs, no spacers, 18,277 g 235U nscr5st11_1_1_15 0.88510 0.88727 Broken metal, no spacers, 100% enrichment, 35,142 g 235U ncsrbmt11_36_1_5 0.80799 0.81753 Cylinders (3.24 < d 4.25 in.), no spacers, 17 kg 235U ncsrcyct11_17_1_15 0.89674 0.89755 HEU product oxide, no spacers, 24 kg UO2 ncsrpdoxt11_1_3_24 0.80888 0.80936 Square bars (l,w 2.29), no spacers, 36 kg 235U ncsrsqt11_36_1_15 0.86569 0.86544 Three 5" tall TRIGA fuel per can, 921 g 235U ncsrtriga_1_15_15 0.49314 0.49477
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 24 Comparative calculations Kaolite vs Packcrete for Array Description Case Name Kaolite Packcrete (Min H2O from) keff + 2 Packcrete
(*p)
Kaolite
(*pp) keff + 2 keff + 2 Slugs, no spacers, 17,374 g 235U ncia5st11_1_1_7_3 0.91136 0.89351 0.91034 Broken metal, spacers, 100% enrichment, 2,774 g 235U nciabmt11_3_2_8_3 0.90273 0.84435 0.90395 Broken metal, no spacers, 60% enrichment, 5,577 g U nciabmt11_6_1_3_3 0.91388 0.84843 0.91525 Cylinders (3.24 < d 4.25 in.), no spacers, 15 kg 235U nciacyct11_15_1_3 0.90084 0.88652 0.89964 HEU product oxide, no spacers, 9.682 kg UO2 nciapdoxt11_1_1_11_3 0.91708 0.86921 0.91666 Square bars (l,w 2.29), no spacers, 30 kg 235U nciasqt11_30_1_3 0.92164 0.90075 0.92265 Three 5" tall TRIGA fuel per can, 921 g 235U nciatriga_1_15_3 0.52611 0.50711 0.52574
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.
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 Comparative calculations Kaolite vs Packcrete for Array with No Water Packcrete Kaolite w/no H2O Packcret w/no H2 Description Case Name keff + 2 keff + 2 keff + 2 Slugs, no spacers, 17,374 g 235U ncia5st11_1_1_7_3 0.89351 0.92770 0.92562 Broken metal, spacers, 100% enrichment, 2,774 g 235U nciabmt11_3_2_8_3 0.84435 0.96678 0.96794 Broken metal, no spacers, 60% enrichment, 5,577 g U nciabmt11_6_1_3_3 0.84843 0.98300 0.98429 Cylinders (3.24 < d 4.25 in.), no spacers, 15 kg 235U nciacyct11_15_1_3 0.88652 0.91184 0.91049 HEU product oxide, no spacers, 9.682 kg UO2 nciapdoxt11_1_1_11_3 0.86921 0.96642 0.96605 Square bars (l,w 2.29), no spacers, 30 kg 235U nciasqt11_30_1_3 0.90075 0.94455 0.94494 Three 5" tall TRIGA fuel per can, 921 g 235U nciatriga_1_15_3 0.50711 0.54348 0.54350
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