ML19304B899
| ML19304B899 | |
| Person / Time | |
|---|---|
| Site: | 07001113 |
| Issue date: | 10/31/2019 |
| From: | Global Nuclear Fuel |
| To: | Office of Nuclear Material Safety and Safeguards |
| Shared Package | |
| ML19304B896 | List: |
| References | |
| M190173 | |
| Download: ML19304B899 (4) | |
Text
M190173 US NRC 10/31/19 Page 1 of 3 SNM-1097 License Application Change Table 10/31/19 Section Description of Change Reason for Change Chapter 1 -GENERAL INFORMATION Section 1.1 - Facility and Process Description Section 1.1.4 - Process Description Section 1.2.2 - Type, Quantity, and Form of Licensed Material Section 1.2.2 - Type, Quality, and Form of Licensed Material Section 1.3.3.1 - Transfer of Hydrofluoric Acid (HF) for Testing Section 1.3.3.2 - Transfer of Hydrofluoric Acid (HF) as Product Section 1.3.3.3 - Transfer of Nitrate-Bearing Liquids Second sentence changed enrichment limit value from 5.0 to 8.0 weight percent U-235.
First sentence changed enrichment limit value from 5.0 to 8.0 weight percent U-235.
Sub-bullets 1) and 2) change enrichment limit value from 5.0% to 8.0%
Sub-bullet 2) change enrichment value from <10% to <20%
Second paragraph changed enrichment limit value from 5.0% to 8.0% U-235.
First paragraph changed enrichment limit value from 5.0 to 8.0 weight percent U-235.
First paragraph, changed enrichment limit value from 5.0 weight percent U-235 to 8.0 weight percent U-235.
Enrichment limit change Enrichment limit change Enrichment limit change Enrichment limit change Enrichment limit change Enrichment limit change Enrichment limit change Chapter 5 -NUCLEAR CRITICALITY SAFETY Section 5.1.1 - Criticality Safety Design Philosophy Section 5.1.2.2 Role of the Criticality Safety Function NCS program commitments statement a) remove the words an inadvertent from sentence.
Second sentence changed commensurate with the risk involved to. commensurate with risk.
Text clarification; words unnecessary Text clarification; words unnecessary
M190173 US NRC 10/31/19 Page 2 of 3 Section 5.4.2.3 - Administrative Controls Section 5.4.3 - Specific Parameter Limits 5.4.5.2 - Analytic Methods First paragraph describing augmented administrative controls and administrative controls are split into two separate bullets.
First paragraph, last sentence removes percentage basis statement for Table 5.1 favorable geometry values and replaces with new basis statement Acceptable safety margins for units listed in this table are documented in accord with Section 5.4.5 analysis methods (keff + 3 USL).
Second paragraph, last sentence changed to acknowledge explicit subcritical limits in accord with Section 5.4.5.
Third paragraph, last sentence changed to acknowledge mass limits are based on enrichment (not U235 mass limits).
First bullet in section; second sentence changed to removed over the range of 1.1% to 5% as this enrichment range is no longer valid.
Table 5.1 Favorable Geometry Values
- reported values have been replaced with calculated results for homogeneous UO2 and water, homogeneous aqueous uranyl nitrate and water, and heterogeneous UO2 and water mixtures over the enrichment range from 5.0 to 8.0 weight percent U-235 as noted above.
Theoretical densities used are specified and based on SCALE6.1 standard composition library.
Table 5.2 Safe Batch Values for UO2 and Water - reported values have been replaced with calculated safe batch results for homogeneous UO2 powder and water and heterogeneous UO2 pellets and water mixtures over the enrichment range from 5.0 to 8.0 weight percent U-235.
Text reformatting Historical percentages of published literature critical diameter, slab thickness, and sphere volume are now derived explicitly.
Text clarification.
Text clarification; uranium enrichment is basis of mass limits.
Text clarification; words unnecessary Historical percentages of published literature critical diameter, slab thickness, and sphere volume are now derived explicitly from SCALE/KENO-VI calculated minimum critical masses.
Table 5.2 list safe batch limits as a function of enrichment from 5.0 to 8.0 weight percent U-235.
Text update.
M190173 US NRC 10/31/19 Page 3 of 3 5.4.4.6 - Spacing (or Unit Interaction) 5.4.5.3-Validation Techniques First paragraph, first sentence; removed reference to Solid Angle methods (SAC code) and Monte Carlo code GEKENO, added MCNP.
Removed previous third paragraph GEKENO summary description paragraph.
Second paragraph (new) added to more fully describe the SCALE/KENO-VI Monte Carlo code used solve eigenvalue solution to the neutron transport equation in 3-dimensional space.
Fourth paragraph (new) added to more fully describe the MCNP Monte Carlo neutron particle transport code used solve eigenvalues for fissile medium systems.
Remove second paragraph, first sentence as Solid Angle interaction analysis is no longer used.
First and sixth paragraphs; replace ANSI/ANS-8.1-1998 reference with current ANSI/ANS-8.1-2014.
Replace last bullet with clarified and corrected statement: Statistical methods may be used to ensure that the extrapolation is not large. The SCALE/TSUNAMI code may be used to compare the application system to the benchmark experiments for similarity and USL penalty determination.
Historical methods using Solid Angle methods or GEKENO 16-energy group Knight Modified Hansen Roach cross section data set are no longer used in production applications.
MCNP is added as it may also be used in support of production applications.
Provide summary description of SCALE/KENO-VI transport code now used in support of production applications.
Provide summary description of MCNP transport code now used in support of production applications.
Text clarification; words unnecessary Text update.
Text clarification; and acknowledgement of TSUNAMI code to quantify AOAm.
M190173 US NRC 10/31/19 Page 4 of 3 5.4.5.5-Criticality Safety Analysis Sixth bullet; removed out of place /
incomplete sentence containing interface considerations.
Text correction; interface considerations for the process being analyzed is previously addressed in the general process description section of the documented nuclear criticality safety evaluation.