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Category:NUREG
MONTHYEARNUREG-1437, Dfc, Supplement 62, Generic Environmental Impact Statement for License Renewal of Nuclear Plants, Supplement 62, Regarding License Renewal of Diablo Canyon Nuclear Power Plant, Units 1 and 22024-10-31031 October 2024 NUREG-1437 Dfc, Supplement 62, Generic Environmental Impact Statement for License Renewal of Nuclear Plants, Supplement 62, Regarding License Renewal of Diablo Canyon Nuclear Power Plant, Units 1 and 2 NUREG-1437 Volume 1, Revision 2, Generic Environmental Impact Statement for License Renewal of Nuclear Plants Final Report2024-08-31031 August 2024 NUREG-1437, Volume 1, Revision 2, Generic Environmental Impact Statement for License Renewal of Nuclear Plants Final Report NUREG-1437 Volume 2, Revision 2, Generic Environmental Impact Statement for License Renewal of Nuclear Plants Final Report2024-08-31031 August 2024 NUREG-1437, Volume 2, Revision 2, Generic Environmental Impact Statement for License Renewal of Nuclear Plants Final Report NUREG-1437 Volume 3, Revision 2, Generic Environmental Impact Statement for License Renewal of Nuclear Plants Final Report2024-08-31031 August 2024 NUREG-1437, Volume 3, Revision 2, Generic Environmental Impact Statement for License Renewal of Nuclear Plants Final Report NUREG-2266, Environmental Evaluation of Accident Tolerant Fuels with Increased Enrichment and Higher Burnup Levels Final Report2024-07-31031 July 2024 NUREG-2266, Environmental Evaluation of Accident Tolerant Fuels with Increased Enrichment and Higher Burnup Levels Final Report NUREG-1556 Volume 2, Rev. 1, Suppl. 1, Consolidated Guidance About Materials Licenses - Program-Specific Guidance About Industrial Radiography Licenses Final Report2024-05-31031 May 2024 NUREG-1556, Vol. 2, Rev. 1, Suppl. 1, Consolidated Guidance About Materials Licenses - Program-Specific Guidance About Industrial Radiography Licenses Final Report ML23355A1432024-01-17017 January 2024 January 17, 2024 Public Meeting Handout - Fusion Systems Rulemaking ML23303A2212023-10-31031 October 2023 NUREG/BR-0096, Revision. 2, Instructions and Guidance for Completing Physical Inventory Summary Reports - NRC Form 327 Final Report ML23123A3322023-06-0606 June 2023 SGI Pamphlet NUREG-1555, Dfc, Supp 1, Rev 2, Standard Review Plans for Environmental Reviews for Nuclear Power Plants, Supplement 1: Operating License Renewal2023-02-28028 February 2023 NUREG-1555 Dfc, Supp 1, Rev 2, Standard Review Plans for Environmental Reviews for Nuclear Power Plants, Supplement 1: Operating License Renewal NUREG-2243, Environmental Impact Statement for the Disposal of Mine Waste at the United Nuclear Corporation Mill Site in Mckinley County, New Mexico2023-01-31031 January 2023 NUREG-2243, Environmental Impact Statement for the Disposal of Mine Waste at the United Nuclear Corporation Mill Site in Mckinley County, New Mexico NUREG-2183, Supplement 1, Environmental Impact Statement Related to the Operating License for the Shine Medical Isotope Production Facility Final Report2023-01-31031 January 2023 NUREG-2183, Supplement 1, Environmental Impact Statement Related to the Operating License for the Shine Medical Isotope Production Facility Final Report ML22299A2382022-10-31031 October 2022 NUREG-2237, Supplement 1, Environmental Impact Statements for Holtec Internationals License Application for a Consolidated Interim Storage Facility for Spent Nuclear Fuel in Lea County, New Mexico NUREG-2248, Environmental Impact Statement for the License Renewal of the Columbia Fuel Fabrication Facility in Richland County, South Carolina. Final Report2022-07-31031 July 2022 NUREG-2248, Environmental Impact Statement for the License Renewal of the Columbia Fuel Fabrication Facility in Richland County, South Carolina. Final Report ML22181B0942022-07-31031 July 2022 NUREG-2237, Environmental Impact Statement for the Holtec International'S License Application for a Consolidated Interim Storage Facility for Spent Nuclear Fuel in Lea County, New Mexico Final Report NUREG-2159, Revision 1, Final, Acceptable Standard Format and Content for the Fundamental Nuclear Material Control Plan Required for Special Nuclear Material of Moderate Strategic Significance2022-07-29029 July 2022 NUREG-2159, Revision 1, Final, Acceptable Standard Format and Content for the Fundamental Nuclear Material Control Plan Required for Special Nuclear Material of Moderate Strategic Significance ML22175A2022022-06-30030 June 2022 NUREG/BR-0058, Rev. 5, Appendix K Monetary Valuation of Nonfatal Cancer Risk for Use in Cost-Benefit Analysis Dfc ML22175A2032022-06-30030 June 2022 NUREG/BR-0058 Dfc, Rev. 5, Appendix L Replacement Energy Costs NUREG-2155, Rev 2, Implementation Guidance for 10 CFR Part 37, Physical Protection of Category 1 and Category 2 Quantities of Radioactive Material2022-03-31031 March 2022 NUREG-2155, Rev 2, Implementation Guidance for 10 CFR Part 37, Physical Protection of Category 1 and Category 2 Quantities of Radioactive Material ML22042A1162022-02-0909 February 2022 Document to Support ACRS Subcommittee Meeting Draft NUREG 1021, Rev 13, Operator Licensing Examination Standards for Power Reactors ML21209A9552021-07-31031 July 2021 NUREG-2239, Environmental Impact Statement for Interim Storage Partners Llc'S License Application for a Consolidated Interim Storage Facility for Spent Nuclear Fuel in Andrews County, Texas Final Report ML21096A2922021-04-30030 April 2021 NUREG/BR-0058, Rev. 5, Appendix F Data Sources - Dfc ML21096A2932021-04-30030 April 2021 NUREG/BR-0058, Rev. 5, Appendix G Regulatory Analysis Methods and Data for Nuclear Facilities Other than Power Reactors - Dfc ML21096A2942021-04-30030 April 2021 NUREG/BR-0058, Rev. 5, Appendix H Severe Accident Risk Analysis - Dfc ML21096A2952021-04-30030 April 2021 NUREG/BR-0058, Rev. 5, Appendix I National Environmental Policy Act Cost-Benefit Analysis - Dfc ML21005A1532020-12-31031 December 2020 NUREG/BR-0520, State Programs at the U.S. Nuclear Regulatory Commission NUREG-2242, Replacement Energy Cost Estimates for Nuclear Power Plants: 2020-2030 - Draft for Comment2020-12-31031 December 2020 NUREG-2242, Replacement Energy Cost Estimates for Nuclear Power Plants: 2020-2030 - Draft for Comment NUREG-1556 Volume 20, Rev. 1, Consolidated Guidance About Materials Licenses: Guidance About Administrative Licensing Procedures Final Report2020-11-30030 November 2020 NUREG-1556, Vol. 20, Rev. 1, Consolidated Guidance About Materials Licenses: Guidance About Administrative Licensing Procedures Final Report NUREG-2224, Dry Storage and Transportation of High Burnup Spent Fuel2020-11-30030 November 2020 NUREG-2224, Dry Storage and Transportation of High Burnup Spent Fuel NUREG-2216, Review Plan for Transportation Packages for Spent Fuel and Radioactive Material2020-08-31031 August 2020 NUREG-2216 Review Plan for Transportation Packages for Spent Fuel and Radioactive Material NUREG-1507, Rev. 1, Minimum Detectable Concentrations with Typical Survey Instruments for Various Contaminants and Field Conditions2020-08-31031 August 2020 NUREG-1507, Rev. 1, Minimum Detectable Concentrations with Typical Survey Instruments for Various Contaminants and Field Conditions ML20178A4332020-06-30030 June 2020 NUREG-BR-0204,Revision 3, Instructions for Completing the U.S. Nuclear Regulatory Commission'S Uniform Low-Level Radioactive Waste Manifest - Final Report ML20122A2202020-05-31031 May 2020 NUREG-2239 Dfc, Environmental Impact Statement for Interim Storage Partners Llc'S License Application for a Consolidated Interim Storage Facility for Spent Nuclear Fuel in Andrews County, Texas ML20321A0972020-04-30030 April 2020 Chapter 3 - Principal Design Criteria Evaluation NUREG-2215, Standard Review Plan for Spent Fuel Dry Storage Systems and Facilities. Title, Table of Contents, Introduction2020-04-30030 April 2020 NUREG-2215, Standard Review Plan for Spent Fuel Dry Storage Systems and Facilities. Title, Table of Contents, Introduction ML20321A0982020-04-30030 April 2020 Chapter 4 - Structural Evaluation ML20321A0992020-04-30030 April 2020 Chapter 5 - Thermal Evaluation ML20321A1002020-04-30030 April 2020 Chapter 6 - Shielding Evaluation ML20321A1012020-04-30030 April 2020 Chapter 7 - Criticality Evaluation ML20321A1022020-04-30030 April 2020 Chapter 8 - Materials Evaluation ML20321A1122020-04-30030 April 2020 Chapter 17 - Technical Specifications Evaluation ML20321A1112020-04-30030 April 2020 Chapter 16 - Accident Analysis Evaluation ML20321A1102020-04-30030 April 2020 Chapter 15 - Quality Assurance Evaluation ML20321A1092020-04-30030 April 2020 Chapter 14 - Decommissioning Evaluation (SL) ML20321A1082020-04-30030 April 2020 Chapter 13 - Waste Management Evaluation (SL) ML20321A1072020-04-30030 April 2020 Chapter 12 - Conduct of Operations Evaluation ML20321A1062020-04-30030 April 2020 Chapter 11 - Operation Procedures and Systems Evaluation ML20321A1052020-04-30030 April 2020 Chapter 10B - Radiation Protection Evaluation for Dry Storage Systems (CoC) ML20321A1042020-04-30030 April 2020 Chapter 10A - Radiation Protection Evaluation for Dry Storage Facilities (SL) ML20321A0962020-04-30030 April 2020 Chapter 2 - Site Characteristics Evaluation for Dry Storage Facilities (SL) 2024-08-31
[Table view]Some use of "" in your query was not closed by a matching "". Category:Standard Review Plan
MONTHYEARML22041A3752022-02-0909 February 2022 Document to Support ACRS Subcommitee Meeting - Redline Standard Review Plan 1.0 Introduction and Interfaces ML22041A4442022-02-0909 February 2022 Document to Support ACRS Subcommittee Meeting - Redline Standard Review Plan 13.3 Emergency Planning ML22041A4462022-02-0909 February 2022 Document to Support ACRS Subcommittee Meeting - Redline Standard Review Plan 13.6.1 Physical Security-Combined License and Operating Reactors ML22041A4562022-02-0909 February 2022 Document to Support ACRS Subcommittee Meeting - Redline Standard Review Plan 13.6.4 Access Authorization - Operational Program ML22041A5272022-02-0909 February 2022 Document to Support ACRS Subcommittee Meeting Redline Standard Review Plan 19.0 Probablistic Risk Assessment and Accident Evaluation for New Reactors ML22041A5322022-02-0909 February 2022 Document to Support ACRS Subcommittee Meeting Redline Standard Review Plan 19.1 Determining the Technical Adequacy of Probablistic Risk Assessment for Risk-Informed License Amendment Requests After Initial Fuel Load ML20321A0932020-04-30030 April 2020 Appendix 8B - Fuel Cladding Creep ML20321A0912020-04-30030 April 2020 Appendix 7A - Technical Recommendations for the Criticality Safety Review of PWR Transportation Packages and Storage Casks ML20321A0952020-04-30030 April 2020 Chapter 1 - General Information for Evaluation ML20321A0962020-04-30030 April 2020 Chapter 2 - Site Characteristics Evaluation for Dry Storage Facilities (SL) ML20321A0972020-04-30030 April 2020 Chapter 3 - Principal Design Criteria Evaluation ML20321A0982020-04-30030 April 2020 Chapter 4 - Structural Evaluation ML20321A0992020-04-30030 April 2020 Chapter 5 - Thermal Evaluation ML20321A1002020-04-30030 April 2020 Chapter 6 - Shielding Evaluation ML20321A1012020-04-30030 April 2020 Chapter 7 - Criticality Evaluation ML20321A1022020-04-30030 April 2020 Chapter 8 - Materials Evaluation ML20321A1042020-04-30030 April 2020 Chapter 10A - Radiation Protection Evaluation for Dry Storage Facilities (SL) ML20321A1052020-04-30030 April 2020 Chapter 10B - Radiation Protection Evaluation for Dry Storage Systems (CoC) ML20321A1062020-04-30030 April 2020 Chapter 11 - Operation Procedures and Systems Evaluation ML20321A1072020-04-30030 April 2020 Chapter 12 - Conduct of Operations Evaluation ML20321A1082020-04-30030 April 2020 Chapter 13 - Waste Management Evaluation (SL) ML20321A1092020-04-30030 April 2020 Chapter 14 - Decommissioning Evaluation (SL) ML20321A1102020-04-30030 April 2020 Chapter 15 - Quality Assurance Evaluation ML20321A1112020-04-30030 April 2020 Chapter 16 - Accident Analysis Evaluation ML20321A1122020-04-30030 April 2020 Chapter 17 - Technical Specifications Evaluation ML20321A0882020-04-30030 April 2020 Appendix a - Interim Staff Guidance (ISG) Incorporated Into NUREG-2215 ML20321A0892020-04-30030 April 2020 Appendix 4A - Computational Modeling Software Technical Review Guidance ML20321A0902020-04-30030 April 2020 Appendix 4B - Pool and Pool Confinement Facilities ML20321A0922020-04-30030 April 2020 Appendix 8A - Clarifications, Guidance, and Expectations to ASTM Standard Practice C1671-15 ML20321A0942020-04-30030 April 2020 Appendix 8C - Fuel Oxidation and Cladding Splitting ML20321A1032020-04-0101 April 2020 Chapter 9 - Confinement Evaluation 2022-02-09
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APPENDIX 4A COMPUTATIONAL MODELING SOFTWARE TECHNICAL REVIEW GUIDANCE 4A.1 Computational Modeling Software Application The staff does not endorse the use of any specific type or code vendor of computational modeling software (CMS). Any appropriate CMS application could be used for analyses of cask or package components; however, for any CMS to demonstrate that a particular cask design satisfies regulatory requirements, the applicant should demonstrate adequate validation of that CMS.
Descriptions of CMS validations can be contained within a given application or incorporated by reference.
Verify that the SAR or related documentation (such as proprietary calculation packages or benchmark reports) provides the following information:
x details of the methodology used to assemble the computational models and the theoretical basis of the program used x a description of benchmarking against other codes or validation of the CMS against applicable published data or other technically qualified and relevant data that are appropriately documented x standardized verification problems analyzed using the CMS, including comparison of theoretically predicted results with the results of the CMS x release version and applicable platforms Once the information described above has been docketed, it need not be submitted with each subsequent application but can be referred to in subsequent safety analysis reports (SARs) or related documents. If an applicant changes its analysis methodology or changes the type or vendor of the CMS used, the applicant should submit either a revision of previously submitted information or include a clear explanation of the methodology changes, and their effects on the analysis in question, in subsequent SAR submittals.
4A.2 Modeling Techniques and Practices The staff may need to verify the modeling techniques and practices the applicants used to demonstrate adequacy of the model.
Verify that the CMS and the options the applicant used are appropriate for adequately capturing the behavior of a cask, package, or any components.
The original application should include relevant input and results files or an equivalent detailed model description and output.
4A.3 Computer Model Development Verify that the computer model used for the analysis is adequately described, either in the SAR or in other documentation; is geometrically representative of the cask design being analyzed; has 4A-1
addressed how material and manufacturing uncertainties might affect the analysis; has appropriate boundary conditions; and has no significant analysis errors.
Verify that the model description includes an adequate basis for the selection of parameters and components, as appropriate, used in the analysis model (e.g., the reason a particular element type was applied in the analysis model).
Verify that the models sufficiently represent cask or package geometry and that adequate justification is provided for simplifications used. Models created with CMS are often simplified to reduce computer processing time. Models can often omit geometric details or use homogenized or smeared material properties to represent complex geometry or material combinations and still retain analytic accuracy. If smeared or homogenized properties are used, verify that the applicant has provided adequate justification for this approach, as the response of the problem can be dramatically altered.
Verify that the applicant has discussed how manufacturing or assembly tolerances and contact resistances will affect the analyses that have been conducted, if at all, in both the structural and thermal disciplines. Verify that the applicant has described how tolerances or contact resistances are accounted for, if applicable, in the cask or package analysis models that are submitted for review.
Verify that the applicant has provided a general discussion of how error, warning, or advisory messages generated by the software affect the analysis result (if applicable). When processing a computer model developed using CMS, the software will frequently provide error, warning, or advisory messages indicating a possible problem with the model that may or may not be sufficient to terminate processing. If the error or warning function has been disabled during processing, ensure the applicant provides an explanation of why this is appropriate.
Verify that, within the specific disciplines, the dimensions and physical units used in the models developed are clearly labeled and mutually consistent. The fundamental units of time, mass, and length should be clearly identified. All other physical units derived should be consistent with the basic units adopted. For example, if the unit of length is the millimeter, time in milliseconds, and mass in gram, then the mechanical force should have units of Newton, energy in millijoule, and stress in megapascal. Verify that the input parameters are expressed in the units as assigned. If an applicant chooses not to adopt this uniformity of units, the appropriate conversion should be applied before processing input into CMS. Similar assurances should be provided for the output for the analysis solution.
4A.4 Computer Model Validation Verify that model validation done with applicable experiments or testing is properly documented and appropriate references are provided. For example, an analytical models ability to capture relevant model output such as g-loads, and plastic deformations could be demonstrated by comparing the physical test data of a similar package that was instead drop tested.
The test data used to validate or benchmark the analytical model should be similar in regard to the expected package behavior of interest. For instance, a package with impact limiters should be used to benchmark a package that also has impact limiters. Plastic strain data used for validation, for instance, should come from areas of the package where such data are crucial or relaxant to the performance of the package such as the containment boundary. Other details to consider when benchmarking and validating physical data include whether the package is bolted or 4A-2
welded, and whether the response will be dominated primarily by a quasi-static, wave or impulse-type response. The data source should be readily available or included, as appropriate, in the application and should describe all the assumptions and simplifications made during physical testing so that staff can weigh its relevance to the design of interest.
4A.5 Justification of Bounding Conditions and Scenario for Model Analysis Ensure the applicant determines the most damaging orientation and worst-case conditions for a given design and document how the analytic model was configured for the scenario. Verify that the applicant provided sufficient justification for selecting the most damaging orientation and worst-case conditions.
4A.6 Description of Boundary Conditions and Assumptions Verify, as necessary, that the textual description included in the SAR or other documents address boundary conditions such as an unyielding surface in a drop scenario. The textual description should also include justifications and bases for such items. Confirm that the application reflects appropriate material (temperature dependent) properties.
4A.7 Description of Model Assembly Verify that the SAR lists the types of elements used in the model along with the corresponding materials or components in which they are used in the analysis model. The reviewer should quickly be able to discern what elements and materials are associated with specific components of the analysis model.
Verify that a sufficient explanation of the logic behind the creation of each specific computer model (such as the mesh) is provided so that effective confirmatory calculations can be performed.
The applicant should provide the input files for the models used in the analysis. If input files are not provided or do not adequately describe model assembly, the applicant should provide in the appropriate SAR chapters or related documents an adequate explanation of how computer models were assembled using the CMS.
4A.8 Loads, Time Steps, and Impact Analyses Verify that the applicant has clearly explained the loads, load combinations, and, if used by the analytical code, the load steps used in the computer model. Evaluate all loads, how they are placed on the computer models, load combinations, and, if used, the time steps applied in the analysis.
Verify that the time steps specified for the solution of the analysis are sufficiently small to accurately capture the behavior of the structures, systems, or components being modeled.
For impact analyses using software such as LS-DYNA, examine the output files for hour-glassing energy in each part of the system in addition to the package as a whole. Verify that the impact analyses output is realistic. Parts of a model should not pass each other without deformation or through one another unrealistically. Disassemble the model by component and examine them for breaches or other unseen damage. For instance, components can be perforated, but this damage may be hidden from view by other components in the model.
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4A.9 Sensitivity Studies The discussion of the general development of the computer model should cover sensitivity studies, with relevant references to examples included in the SAR or related documents.
Verify that the applicant has completed sensitivity studies for relevant CMS modeling parameters.
This includes element type and mesh density, load step size, interfacing gaps or contact friction, material models and model parameters selection, and property interpolation, if applicable. For example, a mesh sensitivity study should be conducted not only for mesh density but also for mesh density and refinement in areas of thermal or structural concern or where performance of the material is crucial, such as seal areas and lid bolts. A mesh sensitivity is also needed to make sure the analysis results are mesh independent.
Verify that the results of applicable sensitivity studies are clearly described in the SAR or related documentation and can be independently verified, if necessary.
Verify that the applicants documentation includes at least a brief discussion of the different models used in its mesh sensitivity studies.
4A.10 Results of the Analysis Verify that the SAR or related document(s) includes all relevant results (tabular and computer plots) for applicable load cases and load combinations evaluated for design code compliance, and that all governing results (stresses and deformations) are clearly identified in the tables and on plots.
Verify that the results are consistent throughout the SAR, and that the correct results are used in calculations of other cask or package performance parameters (e.g., verify calculated temperatures used in the internal pressure calculation).
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