ML25302A452
| ML25302A452 | |
| Person / Time | |
|---|---|
| Site: | Kemmerer File:TerraPower icon.png |
| Issue date: | 11/21/2025 |
| From: | Office of Nuclear Reactor Regulation |
| To: | TerraPower, US SFR Owner |
| References | |
| EPID L-2024-CPS-0000 | |
| Download: ML25302A452 (1) | |
Text
OFFICIAL USE ONLY PROPRIETARY INFORMATION OFFICIAL USE ONLY - EXPORT CONTROLLED INFORMATION US SFR OWNER, LLC -
SUMMARY
REPORT FOR THE GENERAL REGULATORY AUDIT OF THE KEMMERER POWER STATION UNIT 1 CONSTRUCTION PERMIT APPLICATION LIST OF DOCUMENTS This enclosure consists of documents provided in the electronic reading room (ERR) by US SFR Owner, LLC (USO) for the U.S. Nuclear Regulatory Commission (NRC) staff to audit. To support addressing the staffs audit questions (see Enclosure 1, 2, and 3), USO made the following documents available in the ERR:
ADI-QUA-110, Revision (Rev.) 0, ASME Section III US SFR Owner, LLC (USO)
Aizawa, K., 1993. Experiences on PSA Application for LMFBRs in Japan.
ANL-ART-107, August 2017, Understanding and Predicting Effect of Sodium Exposure on Microstructure of Grade 19 Steel ANL-NSE-2, Rev. 0, Experimental Breeder Reactor II (EBR-II) Level 1 Probabilistic Risk Assessment
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Bechtel, 26396-000-V14-JN02-00002, Rev. 0, Naughton-Natrium Power Station Meteorological Report January 2019 through December 2021 Meteorological Data DBR-0075220, Rev. 0, Natrium Radiological Consequence Analysis - MACCS Sensitivity and Uncertainty DBR-0075782, Rev. 1, Natrium Radiological Consequences LBE Report DBR-0078017, Rev. 2, Radiological Consequences DBA Analysis for Natrium PSAR CPA Design Notes DOEGEHF08325, Rev. 3, PRISM All Modes Risk Integration Report GEFR 00873, Rev. 1, Probabilistic Risk Assessment of the Advanced Liquid Metal Reactor Gauthé, et al., 2012, Use of Simplified PSA Studies In Support of The ASTRID Design Process.
GE-Hitachi, Rev. 0, PRISM PRA Model Results Report, Chapter 3, Initiating Events GSNP01-PR-01, Rev. 1, Geologic Field Reconnaissance Report - Geologic Mapping and Preliminary Safety Analysis Reporting (PSAR), Natrium Project Krystek, B. Natrium PRA Software Demonstration August 27, 2024 NAT-13718, Rev. 0, Natrium Probabilistic Risk Assessment (PRA) Configuration Control Procedure NAT-13757, Rev. A, Natrium Coating Qualification Plan for Core Components NAT-16841, Rev. A, GMRS Sensitivity to MAM/MASW Shear Wave Velocity Profiles NAT-16849, Rev. 0, Site Response Analysis Sensitivity to MASW/MAM Data for Kemmerer Unit 1 NAT-1974, Rev. 7, Natrium Design Process & Control NAT-1975, Rev. 2, Natrium Design Change Control NAT-1976, Rev. 3, Natrium Design Inputs NAT-1977, Rev. 2, Natrium Open Items NAT-2565, Rev. 0, Natrium Materials Management Plan NAT-2599, Rev. 2, Natrium Fuel, Control, Shield, and Reflector Pin Design Criteria NAT-2696, Rev. 1, Sodium Cover Gas Design Basis Document NAT-2707, Rev. 1, SCG Non-Safety Sizing and Intermediate Overpressure Event Characterization Sizing Calculation NAT-2717, Rev. A, Natrium Materials Handbook
OFFICIAL USE ONLY PROPRIETARY INFORMATION 2
OFFICIAL USE ONLY - PROPRIETARY INFORMATION NAT-2843, Rev. F, Primary Sodium Pump Design Specification NAT-2937, Rev. 1, Natrium Intermediate Air Cooling System Design Basis Document NAT-2938, Rev. 2, Intermediate heat Transport System Design Basis Document NAT-2955, Rev. 1, Natrium Reactor Enclosure System (RES) Design Basis Document NAT-2974, Rev. 1, Natrium Reactor Air Cooling System Design Basis Document NAT-2975, Rev. 2, In-Vessel Fuel Handling System Design Basis Document NAT-3007, Rev. 0, IVS Criticality Safety Calculations NAT-3078, Rev. 1, Nominal and Peak Inventory in Cover Gas and Vapor Processing Equipment NAT-3099, Rev. 1, Upper Subcriticality Limit (USL) for the Criticality Analysis of the In-Vessel Storage (IVS)
NAT-3145, Rev. 2, Primary Heat Transport (PHT) System Design Basis Document NAT-3153, Rev. 4, Reactor Core System Design Basis Document NAT-3225, Rev. 0, ASME Design Specification for Reactor Fixed Internals NAT-3233 Rev. B, ASME Design Specification for Reactor Head NAT-3245, Rev. 0, Shutdown Margin Biases and Uncertainties Quantification NAT-3259, Rev. 1, Depletion Sensitivity Study of the Natrium Reactor Core NAT-3275, Rev. 0, Core Assembly Pressure Drop and Heat Transfer Correlations NAT-3295, Rev. 2, Sodium Processing System Design Basis Document NAT-3334, Rev. 2, Ex-Vessel Fuel Handling System Design Basis Document NAT-3476, Rev. 0, Equipment Qualification Program NAT-3495, Rev. 2, Material Property Data Acquisition and Verification NAT-3534, Rev. 1, Thermal Uncertainty and Bias Report (TUBR)
NAT-3637, Rev. 3, Boring Location Plan (As-Built)
NAT-4549, Rev. 1, Control Rod Drive System Design Basis Document NAT-4547, Rev. B, Natrium Maintenance Program NAT-4607, Rev. 0, ASME Design Specification for Reactor Vessel NAT-4761, Rev. 0, Steady State Design Evaluations of the Natrium Reactor Core NAT-4762, Rev. A, RIM Degradation Mechanism Assessment for Natrium Demonstration Project NAT-4767, Rev. 2, Licensing Basis Event (LBE) Selection Report NAT-4770, Rev. 1, Natrium Demonstration Plant DID Evaluation Report NAT-4771, Rev. 1, Natrium Neutronics Uncertainties and Hot Channel Factors NAT-4781, Rev. 0, Seismic Interaction Strategy NAT-4792, Rev. 0, Initial Seismic Classification Assignment NAT-4792, Rev. 1, Initial Seismic Classification Assignment NAT-4792, Rev. 3, Implementation of Seismic Classifications and Design Criteria (Excerpts)
NAT-4817, Rev. 0, Loss of Coolant Inventory Control Evaluation for Natrium PSAR CPA NAT-4826, Rev. 1, Displacements per Atom and Fluence in Ex-Core Structures NAT-4826, Rev. 2, Displacements per Atom and Fluence in Ex-Core Structures NAT-4843, Rev. 1, Bearing Capacity and Settlement Calculation for NI NAT-4850, Rev. 0, Risk-Informed Seismic Classification and Performance Criteria Guide NAT-4850, Rev. 1, Risk-Informed Seismic Classification and Performance Criteria Guide NAT-4925, Rev. 1, System Level SSC Classification Worksheet Template NAT-4926, Rev. 0, System Level SSC Classification Worksheet Work Guide NAT-4932, Rev. 1, Generic Special Treatment Work Guide
OFFICIAL USE ONLY PROPRIETARY INFORMATION 3
OFFICIAL USE ONLY - PROPRIETARY INFORMATION NAT-4934, Rev. 0, Nala Simulation Process and Modeling Inputs for the Natrium Reactor Core NAT-4953, Rev. 0, FAB Ground Floor Plan Elevation 500-0 NAT-4949, Rev. 0, Comprehensive Vibration Assessment Program Plan NAT-4961, Rev. 0, FAB Section Looking West NAT-4964, Rev. 0, NCB Substructure Plan Elevation 470-0 NAT-4965, Rev. 0, NCB Ground Floor Plan Elevation 500-0 NAT-4967, Rev. 0, NCB Section Looking West NAT-4968, Rev. 0, NCB Section Looking South NAT-4994, Rev. 0, Safety Bias, Uncertainty Quantification, and Margin Assessment Methodology NAT-4999, Rev. 0, Non-DBA In-Vessel Licensing Basis Events without Radiological Release Methodologies Report NAT-5012, Rev. 0, SAS Full Power Loss of IHT Heat Removal Control Analysis for Natrium PSAR CPA NAT-5023, Rev. B, Intermediate Heat Transport (IHT) Technology Maturation Plan (TMP)
NAT-5026, Rev. 2, Radiological Release Consequence Methodology Topical Report NAT-5037, Rev. 0, Slope Stability Calculation NAT-5038, Rev. 2, Excavation Support Analysis for Nuclear Island NAT-5040, Rev. 2, Static and Dynamic Geotechnical Engineering Properties NAT-5079, Rev. 0, Vapor Trap Cell Preformed Liner Equipment Specification NAT-5081, Rev. 1, Natrium Inlet Flow Distribution Uncertainty Report NAT-5263, Rev. 1, Natrium Testing Program Plan NAT-5267, Rev. 0, Enveloping Offsite and Control Room X/Q Values for Natrium NAT-5318, Rev. 1, Instrumentation & Control Equipment Qualification Program NAT-5324, Rev. 0, Mechanical Equipment Qualification Program NAT-5500, Rev. B, PHT System Failure Modes Effects Analysis (FMEA)
NAT-5502, Rev. 0, Reactor Air Cooling Safety Analysis Performance Envelope NAT-5535, Rev. 0, Natrium IDPP Charter NAT-5368, Rev. 0, Electrical Equipment Qualification Program NAT-5381, Rev. 0, Inservice Testing (IST) Program, OM Code NAT-5578, Rev. 0, RAB General Arrangement Plan View at Elevation 438-0 to 470-0 NAT-5579, Rev. 0, RAB General Arraignment Plan View at Elevation 500-0 NAT-5581, Rev. 0, RAB General Arrangement Plan View at Elevation 537-0 NAT-5582, Rev. 0, RAB General Arrangement Section View A Looking North NAT-5583, Rev. 0, RAB General Arrangement Section View B Looking East NAT-5584, Rev. 0, RAB General Arrangement Section View C Looking East NAT-5596, Rev. 1, Reliability and Integrity Management Program Plan NAT-5599, Rev. 0, Natrium LBE Selection Guide NAT-5601, Rev. 0, Natrium SSC Classification Guide NAT-5603, Rev. 0, Natrium Defense-in-Depth (DID) Adequacy Guide NAT-5613, Rev. 0, In-vessel Releases from At-Power Events NAT-5614, Rev. 0, In-vessel Releases from Fuel Handling Events NAT-5615, Rev. 0, Releases from In-vessel Design Basis Accidents NAT-5620, Rev. 1, Ex-vessel Releases from Auxiliary System Events NAT-5621, Rev. 0, Ex-vessel Releases from Fuel Handling Events EVHM, BLTC, EVST NAT-5624, Rev. 0, Ex-vessel Releases from Drop Event in the Spent Fuel Pool NAT-5647, Rev. B, RES Core Barrel Structures ASME Design Specification
OFFICIAL USE ONLY PROPRIETARY INFORMATION 4
OFFICIAL USE ONLY - PROPRIETARY INFORMATION NAT-5650, Rev. A, Natrium Reactor Head Assembly Fabrication Specification NAT-5726, Rev. 0, FHB Plan View at 450-0 and 488-0 NAT-5727, Rev. 0, FHB Plan View at 500-0 NAT-5728, Rev. 0, FHB Plan View at 524-9 NAT-5729, Rev. 0, FHB General Arrangement Section View A Looking West NAT-5730, Rev. 0, FHB General Arrangement Section View B Looking North NAT-5731, Rev. 0, FHB General Arrangement Section View C Looking North NAT-5805, Rev. B, ASME Design Transient Event List NAT-5812, Rev. 1, Statement of Work - Materials Degradation Matrix (MDM), Issue Management Tables (IMT), and Degradation Mechanism Assessment (DMA)
NAT-5879, Rev. 1, Normal Operational Plant Dose Calculation NAT-5880, Rev. 0, RAB General Arrangement Plan View at Elevation 517-6 NAT-5881, Rev. 1, Radiological Consequences LBE Analysis for Natrium PSAR CPA NAT-5882, Rev. 0, SAS Full Power Seismic Reactivity Insertion Analysis for Natrium PSAR CPA NAT-5883, Rev. 0, SAS Plant Model Description for the Natrium Reactor NAT-5886, Rev. 0, SAS Full Power Loss of Primary Flow AOO NAT-5887, Rev. 0, SAS Analysis of Rod Withdrawal LBEs for Natrium PSAR CPA NAT-5889, Rev. 0, SAS Full Power Loss of Heat Removal Control from NSS Analysis for Natrium PSAR CPA NAT-5893, Rev. 0, SAS Reactor Protection System and Radial Expansion Reactivity Model Documentation for Natrium PSAR/CPA NAT-5936, Rev. 1, Liquid Radwaste Processing (RWL) System Tank Sizing Calculation NAT-5949, Rev. 1, Seismic Analysis Criteria for Safety-Related Structures of Natrium Reactor and Integrated Storage Facility NAT-5959, Rev. 2, Radiological Consequences DBA Analysis for Natrium PSAR CPA NAT-5997, Rev. 0, Seismic Design Criteria - Nuclear Island NAT-6006, Rev. 0, Reactor Stability Analysis for Natrium Preliminary Safety Analysis Report and Construction Permit Application NAT-6013, Rev. 2, Structural Design Criteria - Nuclear Island NAT-6031, Rev. 0, SAS Full Power Decrease and Increase in Heat Removal Analysis for Natrium PSAR CPA NAT-6047, Rev. 0, RXB General Arrangement Operating Deck Elevation 457-0 NAT-6048, Rev. 0, RXB General Arrangement Ground Floor Elevation 500-0 NAT-6049, Rev. 0, RXB General Arrangement Section A Looking East NAT-6050, Rev. 0, RXB General Arrangement Section B Looking North NAT-6054, Rev. A, Core Barrel Structure (CBS), Reactor Fixed Internals (RFI), & Drywells Fabrication Specification NAT-6058, Rev. 0, Radiological Consequences MACCS EPZ Evaluation for Natrium PSAR/CPA NAT-6065, Rev. 0, Interim 500,000 Hour Material Properties for 304H and 316H Stainless Steel for ASME Section III, Division 5 Design NAT-6097, Rev. A, Normal Operation System Source Term - RWG NAT-6098, Rev. A, Normal Operation System Source Term - RWL NAT-6100, Rev. A, Normal Operation System Source Term - IHTS NAT-6101, Rev. A, Normal Operation System Source Term - PHTS NAT-6102, Rev. 0, Normal Operation System Source Term - RAC NAT-6161, Rev. A, PRA Source Term and Radiological Consequences Analyses
OFFICIAL USE ONLY PROPRIETARY INFORMATION 5
OFFICIAL USE ONLY - PROPRIETARY INFORMATION NAT-6168, Rev. 0, Reactor Air Cooling System Technology Maturation Plan NAT-6178, Rev. 1, SAS Core Model, Model Integration, and Initialization for In-Vessel LBE Analyses NAT-6200, Rev. 1, SFT DBA Analysis of Non-SR SSCs Treatment NAT-6215, Rev. B, Core-Vessel Interface Shell and Ribs NAT-6217, Rev. 0, SAS Nuclear Island Control System Model Documentation for Natrium PSAR/CPA NAT-6237, Rev. B, Intermediate Heat Exchanger ASME Design Specification NAT-6291, Rev. 0, CPA Chapter 13 - R&D Scope Screening Guidance NAT-6298, Rev. 4, Plant Design Specification - Plant - Level Requirements NAT-6301, Rev. 5, Plant Design Specification - Regulations, Orders, Codes & Standards NAT-6302, Rev. 0, Plant Design Specification - Design Basis Hazards NAT-6396, Rev. 0, Integrated Radionuclide Library NAT-6398, Rev. A, Natrium Normal Yearly Effluent Calculation NAT-6510, Rev. 0, Kemmerer Unit 1, WY ARCON /Q Calculation for Control Room Air Intake and Exclusion Area Boundary NAT-6580, Rev. A, Identify and Screen Radionuclide Sources NAT-6612, Rev. A, Non-Metallic Materials Limits Specification NAT-6636, Rev. 0, Transient Fuel Performance Analysis for Natrium Core NAT-6871, Rev. 0, Alloy 718 Basic Mechanical and Thermal Properties NAT-6899, Rev. 0, In-Vessel DBAs and Non-DBA LBEs without Radiological Release Application Methods NAT-6954, Rev. C, Core Seismic Analysis Report NAT-6955, Rev. 0, Kemmerer Unit 1 /Q and D/Q Estimates for Routine Releases NAT-6959, Rev. 0, Other Quantified Events with Release for PRA Quantification NAT-6966, Rev. 0, Fuel Pin Cladding Temperature Criteria for Failure Analysis NAT-6979, Rev. 0, Loss of active cooling for EVST with transient CFD NAT-6993, Rev. 1, Natrium Demonstration Project Chapter 13 Screening Results NAT-7001, Rev. B, System Specific SARRDL Definition NAT-7015, Rev. 0, Lateral Earth Pressure Calculation NAT-7046, Rev. 2, Natrium Demonstration Plant Level Safety Classification Report NAT-7049, Rev. 0, Natrium General Welding Specification ASME Section III NAT-7078, Rev. 2, Subsurface Investigation Data Report NAT-7093, Rev. 0, Verification of Nascent DR1 Peak Fluid Temperature Values NAT-7109, Rev. A, Natrium PRA Plant Operating States (POS) Analysis NAT-7127, Rev. A, Natrium PRA Initiating Events (IE) Analysis NAT-7137, Rev. A, Natrium PRA System Analysis - Confinement NAT-7138, Rev. A, Natrium PRA System Analysis - Control (RPS/NIC)
NAT-7139, Rev. A, Natrium PRA System Analysis - Electrical NAT-7140, Rev. A, Natrium PRA System Analysis - Ex-Vessel Fuel Handling Machine (EVHM)
NAT-7141, Rev. A, Natrium PRA System Analysis - Ex-Vessel Storage Tank (EVST)
Cooling NAT-7142, Rev. A, Natrium PRA System Analysis - Gaseous Radwaste Processing (RWG)
NAT-7143, Rev. A, Natrium PRA System Analysis - Inherent Reactivity Feedback Feature (IRF)
NAT-7144, Rev. A, Natrium PRA System Analysis - Intermediate Air Cooling (IAC)
OFFICIAL USE ONLY PROPRIETARY INFORMATION 6
OFFICIAL USE ONLY - PROPRIETARY INFORMATION NAT-7145, Rev. A, Natrium PRA System Analysis - Intermediate Heat Transport System (IHT)
NAT-7146, Rev. A, Natrium PRA System Analysis -Miscellaneous NAT-7147, Rev. A, Natrium PRA System Analysis - Molten Salt and Steam Generation NAT-7148, Rev. A, Natrium PRA System Analysis - Nuclear Island Air and Inert Gas Distribution System NAT-7149, Rev. A, Natrium PRA System Analysis - Primary Heat Transport (PHT)
NAT-7150, Rev. A, Natrium PRA System Analysis - Reactivity Control (CRD)
NAT-7151, Rev. A, Natrium PRA System Analysis - RAC System NAT-7152, Rev. A, Natrium PRA System Analysis - Sodium Cover Gas (SCG)
NAT-7153, Rev. A, Natrium PRA System Analysis - Sodium Processing Systems (SPS)
NAT-7154, Rev. A, Natrium PRA Event Sequence Analysis (ES)
NAT-7238, Rev. 1, Liquefaction Potential NAT-7244, Rev. A, In-Vessel Transfer Machine Technology Maturation Plan NAT-7267, Rev. 0, Groundwater Flow Model NAT-7275, Rev. 0, Environmental Qualification Methods NAT-7327, Rev. 1, Seismic Performance Criteria Report NAT-7364, Rev. B, Natrium Event Sequence Quantification NAT-7371, Rev. B, TP RELAP5-3D Analysis of Loss of Offsite Power (LOOP) ASME Events B.5 & D.1 NAT-7415, Rev. 0, Kemmerer Unit 1, WY External Hazards Calculation (Flammability/Explosions)
NAT-7417, Rev. 0, Kemmerer Unit 1, WY Internal and External Hazards (Toxicity)
Calculation NAT-7444, Rev. A, Natrium PRA Methodology NAT-7445, Rev. 0, Natrium Plant Mild Environment Definitions NAT-7468, Rev. 0, Alloy 718 Hardness Temperature Derating NAT-7494, Rev. 1, Design Reliability Assurance Program (D-RAP)
NAT-7547, Rev. B, Natrium Demonstration - Scoping PRA Analysis for Spent Fuels from EVST to Spent Fuel Pool (SFP) and in the SFP NAT-7580, Rev. A, Natrium PRA Success Criteria Analysis (SC)
NAT-7584, Rev. 0, SAS Low Power Loss of IHT Loop(s) Analysis for Natrium PSAR CPA NAT-7719, Rev. 0, Detailed Depletion Evolutions of the natrium Reactor Core NAT-7722, Rev. 0, Mongoose++ Software Test Plan (STP) and Software Test Report (STR)
NAT-7731, Rev. 0, SAS Low Power Loss of Flow and Loss of IAC Analysis for Natrium PSAR CPA NAT-7781, Rev. 0, Detonation Gun Coating Literature Review and Development Study NAT-7810, Rev. A, Definition of Systems, Structures, and Components (SSCs) Scope for Natrium Reliability and Integrity Management (RIM) Program NAT-7827, Rev. B, PRA Analysis - Risk Integration (Model)
NAT-7878, Rev. A, Natrium PRA Data Analysis (DA)
NAT-7879, Rev. A, Natrium PRA Human Reliability (HR) Analysis NAT-7881, Rev. 0, Thermal Cycling of Coatings in Liquid Sodium Test Requirement NAT-7948, Rev. 0, SAS BDBE Analyses for Natrium PSAR CPA NAT-8037, Rev. A, LBE Selection and SSC Classification NAT-8076, Rev. A, Natrium PRA - Risk Integration Sensitivities NAT-8095, Rev. 0, Initial EPZ Sizing Calculation
OFFICIAL USE ONLY PROPRIETARY INFORMATION 7
OFFICIAL USE ONLY - PROPRIETARY INFORMATION NAT-8172, Rev. 0, LBE Analysis of Release from RWG NAT-8174, Rev. 1, LBE Analysis of Release from SPS-I Cold Trap NAT-8194, Rev. A, Corrosion Allowance Report for Sodium Wetted IHT/IHX/SHX NAT-8194, Rev. B, Screening Criteria and Technical Basis for General Corrosion Flow-accelerated Corrosion, Mass Transfer, and Carburization/Decarburization of NDP Structural Materials in Liquid Sodium NAT-8218, Rev. B, Natrium PRA Self-Assessment Against ASME/ANS RA-S-1.4-2021 NAT-8265, Rev. B, Leak Rate Calculation Methodology Development for Leak Monitoring NAT-8286, Rev. 0, Natrium Demonstration Project SSHAC Level 3 Probabilistic Seismic Hazard Analysis NAT-8294, Rev. B, Natrium Demonstration - PRA Screening of External Hazards NAT-8339, Rev. 0, SAS Safety Analysis SQA and Model Disposition Study for CPA/PSAR NAT-8483, Rev. 1, Natrium PRA Summary Report NAT-8495, Rev. 0, Application of DSAW in Support of Transient Fuel Performance Analysis for Natrium Core NAT-8503, Rev. 0, Screening Criteria and Technical Basis for Neutron Embrittlement of NDP Structural Materials NAT-8518, Rev. A, Natrium PRA Rev. C Design Delta Review NAT-8622, Rev. B, PRA Analysis - Natrium PRA Model Rev C Sensitivities NAT-8642, Rev. 1, Seismic Classification and fragility Report NAT-8645, Rev. A, TerraPower Manual Action Strategy Document Natrium Demonstration Project, Table of Contents NAT-8646, Rev. A, Table of Contents NAT-8767, Rev. 0, Natrium Mechanistic Source Term Summary Table NAT-8807, Rev. A, Quantitative Health Objective Update for the IDPP NAT-8839, Rev. 0, Equipment Qualification Package Procedure NAT-8924, Rev. B, Natrium PRA Screening of External Hazards NAT-9030, Rev. 0, IDPP Training Qualification NAT-9034, Rev. 0, IDPP Report Natrium License Basis Events, SSC Classification and Defense in Depth NAT-9390, Rev. 0, Design Basis Accident Methodology for In-Vessel Events without Radiological Release NAT-9393, Rev. 0, Stability Methodology Topical Report NAT-9605, Rev. 0, Mechanical Testing of Coatings NAT-9637, Rev. 0, Fuel Handling Instrumentation and Control Technical Report NAT-9909, Rev. 0, Reliability and Integrity Management Program Work Guide NAT-9911, Rev. A, Bi-Metallic Assembly Technology Maturation Plan NAT-10000, Rev. 0, Natrium Welding Filler Material Specification for QL-1 SSC NAT-10173, Rev. 0, Guard Vessel - Collector Cylinder Design Specification NAT-10335, Rev. 0, Assessment of Cover Gas Entrainment Risk into Primary Sodium Loop NAT-10632, Rev. 0, Gamma and Neutron Heating in the IVS NAT-10636, Rev. A, Reliability and Integrity Management Program - Reliability Target Allocation NAT-10640, Rev. 0, Inaugural IDPP Convocation Summary Report NAT-10776, Rev. 0, CR-2024-0134 and CR-2024-0169 disposition study for CPA/PSAR SAS models NAT-10867, Rev. C, ASME Design Specification for Fixed In Vessel Shielding
OFFICIAL USE ONLY PROPRIETARY INFORMATION 8
OFFICIAL USE ONLY - PROPRIETARY INFORMATION NAT-10919, Rev. 0, Interim Process for Changes to IDPP-endorsed DID Baseline NAT-10985, Rev. A, Natrium PRA PIC Excess Sodium-Water Reaction Sensitivity Evaluation NAT-11114, Rev. A, RES Material Selection Basis NAT-11332, Rev. A, RELAP5-3D Analysis of ASME Transient B.6: Reactor Power Runback NAT-11395, Rev. A, NAPS Criticality Analysis:
NAT-11489, Rev. 0, Estimated Yearly Offsite Dose, Finite Plume Correction NAT-11646, May 2024, Natrium Advanced Reactor Demonstration Project: HFIR Materials Irradiation Project Plan NAT-11764, Rev. 0, RIM Screening Criteria and Technical Basis for Liquid Metal Embrittlement NAT-1250, Rev. C, Specification - Sodium-Salt Heat Exchanger NAT-12647, Rev. 0, AltaSim Wind Analysis CFD)
NAT-12808, Rev. 0, Ignacio/Sumas Loop, 24 in. Natural Gas Pipeline Sensitivity Calculation NAT-13254, Rev. A, Identification and Evaluation of Reliability and Integrity Management Strategies NAT-13478, Rev. DRAFT, Natrium Demonstration Plant Long-Lived Passive Structural Materials of Construction Selection and Development NAT-13718, Rev. 0, Natrium PRA Configuration Control Procedure, NAT-13838, Rev. 0, RIM Screening Criteria and Technical Basis for Neutron Irradiation Induced Void Swelling NAT-13900, Rev. 0, Salt-Sodium Interaction Loop Test Report 04 NAT-13921, Rev. A, RIM Screening Criteria and Technical Basis for Neutron Irradiation and Sodium Effects on Creep Strength and Creep Embrittlement NAT-13941, Rev. 0, Natrium Piping Leakage Postulation Methodology NAT-13965, Rev. A, Core Mechanical Tribology Test Requirements Document NAT-14006, Rev. A, RIM Screening Criteria and Technical Basis for Wear and Fretting NAT-14011, Rev. A, Reliability and Integrity Management Screening Criteria and Technical Basis for Stress Corrosion Cracking of Structural Materials in Sodium NAT-14019, Rev. 0, Kemmerer Unit 1 Preliminary Safety Analysis Report-Meteorology (PSAR Section 2.4)
NAT-14311, Rev. 0, Natrium Methodology for Postulation Ruptures in Moderate Energy Piping Systems NAT-14890, Rev. A, SHX Test Roadmap NAT-14962, Rev. 0, SNaIL Phase 4 Trail 2 Test System Failure Analysis Report NAT-15867, Rev. 0, IHT 60% SHX Inspection and Detection Strategy NAT-15939, Rev. A, Assessment of Irradiation Effects on ASME Section III, Division 5 Material Properties and Design Recommendations NAT-16122, Rev. 0, Natrium Reliability and Integrity Management (RIM) Program Non-Destructive Examination (HDE) Capability Assessment Report NAT-16150, Rev. 0, Sodium Salt Heat Exchanger Leak Mitigation Options Assessment NAT-16182, Rev. 0, Core Component Coatings Historical Summary NAT-16551, Rev. 3, RIM Screening Criteria and Technical Basis for Stress Relation Cracking Natrium, Natrium Materials of Construction Selection and Qualification Summary - Reactor Structural Materials.
OFFICIAL USE ONLY PROPRIETARY INFORMATION 9
OFFICIAL USE ONLY - PROPRIETARY INFORMATION NEA/CSNI/R(2012)2, Rev. 1, Level-1 PSA to support the design of the KALIMER-600 Sodium Cooled Fast Reactor NUREG-0800, Rev. 3, Protection Against Postulated Piping Failures In fluid Systems Outside Containment NUREG/CR-3862, Rev. 0, Development of Transient Initiating Event Frequencies for Use in Probabilistic Risk Assessments NUREG/CR-5750, Rev. 1, Rates of Initiating Events at U.S. Nuclear Power Plants: 1987 -
1995 NUREG/CR-6928, Rev. 2, Industry-Average Performance for Components and Initiating Events at U.S. Commercial Nuclear Power Plants: 2020 Update NUREG/CR-7046, Rev. 0, Design Basis Flood Estimation for Site Characterization at Nuclear Power Plants in the United States of America Phoenix Architect Appendix 1: CAFTA 11.0, March 2022 Phoenix Architect Appendix 2: PRAQuant 11.0, March 2022 Phoenix Architect Appendix 3: UNCERT 11.0, March 2022 PSAR MST and RC Crosswalk, August 13, 2024 Simpson Gumpertz & Hertz, 241412-CA-01, Rev. 1, Calculation of GMRS and SSE Spectra TP-ENG-CALC-0003, Rev. A, K-eff Bias and Uncertainty Analysis for MCRE and Natrium Using Validation Benchmarks TP-ENG-PROC-0022, Rev. 4B, Engineering Review Process and Independent Design Verification TP-ENG-PROC-0042, Rev. 3, Classification of Structures, Systems, and Components (SSCs)
TP-LIC-RPT-0011, Rev. 1, Core Nuclear and Thermal Hydraulic Design Technical Report TP-LIC-RPT-0003, Rev. 1, Radiological Source Term Methodology Report TP-LIC-RPT-0005, Rev. 0, Radiological Release Consequences Methodology Topical Report TP-QA-PD-0001, Rev. 14-A, TerraPower Quality Assurance Program Description TP-PI-PROC-0001, Rev. 3, Corrective Action Program TP-PRC-PROC-003, Rev. 24, Procurement Requisitions TP-QA-PLAN-0004, Rev. 4, USO Quality Execution Plan (QEP)
TP-RMDC-PROC-0002, Rev. 14, Records Management and Document Control TWR-31-RPT-0043, Rev. 0, Preliminary Report on the Characterization of ACO-3 Duct Load Pad Coatings TWR-ENG-RPT-0012, Rev. 0, Neutron Dose Limit for Solution Annealed 316SS Structural Components in the TWR TWRP-ENG-RPT-0007, Rev. 1, Materials Degradation in Liquid Sodium TWRP-ENG-STS-0001, Rev. 0, Oxygen Solubility in Liquid Sodium