Our Courses
Professional Instruction • Subject-Matter Expertise
Training Programs
10 CFR 50 – Two-Step Licensing
10 CFR 52 – One-Step Combined License
Light Water Cooled SMR Design-Build per ASME Sec.III Div. 1
High Temperature Gas Cooled SMR Design-Build Per ASME SEC. III Div.5
Probabilistic Risk Assessment (PRA) Methodology in SMR Operability
Elevated Temperature Reactor OPEX
Climate Change Impact on Nuclear Power
⚙️ Advance Your Knowledge in SMR Technologies and Code Compliance
SMR Deployment Strategy
Licensing pathway development & regulatory review process for SMRs
Regulatory & Policy Advisory
Structured alignment with nuclear regulatory expectations
Advanced Reactor R&D
Technology roadmap development and integration of next-generation nuclear innovation platforms.
Course Details for Advanced Reactor Licensing & Engineering Training Programs
10 CFR 50 – Two-Step Licensing Process
- Construction Permit requirements
- Final Safety Analysis Report (FSAR) development
- Technical Specifications framework
- NRC Requests for Additional Information (RAI) management
- Transition strategies to operating license
10 CFR 52 – One-Step Licensing Process
- Combined License Application (COLA) structure
- Design Certification Rule integration
- Inspections, Tests, Analyses & Acceptance Criteria (ITAAC)
- Closure verification strategies
- Design control document alignment
Course Details for Core Training Modules
Light Water Cooled SMR Design per ASME Sec. III Div.1
- Subsection NCA (1000-9000)
- NB-3000
- NC/ND/NE/NG-3000
- NF-3000
- QA Requirements (Appendix B 10 CFR 50 / NQA-1 / NCA-4000
SMR & ASME SEC. III Division 5
- Creep-fatigue evaluation methods
- In-elastic analysis techniques
- Class A component design
- Code case application strategy
- SRP-0800 expectations for Div.5 components
Probabilistic Risk Assessment (PRA) Level 1,2,3
- Level 1, 2 & 3 PRA fundamentals
- Risk-informed methods
- Significance determination process
- Integration of PRA into reactor licensing
Elevated Temperature Systems OPEX
- Training for elevated temperature systems OPEX (MAGNOX /AGR)
- High-temperature materials behaviour
- ASME Section III Division 5 applications
- Creep-fatigue analysis methods
Who Should Attend?
Reactor Design Engineers
Structural Analysts
Licensing Managers
Authorized Nuclear Inspectors
Utility Engineers
QA/QC Personnel
PRA Specialists
Manufacturing Engineers
Join the Nuclear Renaissance
🌐 www.smrtrainingcourses.com
✉️ jay@alphanumericsolutions.biz
✉️ jay@smrtrainingcourses.com
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