NuScale Small Modular Reactor Design Certification — NRC Licensing Review Timeline

Containment Systems Audit

PRA Audit

Regulatory Audits 2017

Regulatory Audits 2018

Regulatory Audits 2019

Regulatory Audits 2020

Safety Classification of Passive Nuclear Power Plant Electrical Systems,

NuScale Advanced Sensors,

I&C Technical Specifications.

NuScale DCA Review Focus Areas

Shutdown Capability of the Nu Scale Power Module,

NuScale Source Term Revision,

Shutdown Capability of the NuScale Power Module,

NuScale Power Comprehensive Vibration Assessment Program - Audit Report Summary

NuScale Power Containment Leak Rate Test Program,

Risk-Informed Review of NuScale Initial Test Program

NuScale Accident Source Terms Methodology Options

Line Breaks in NuScale Plant Results, Status, and Plans for Closure,

ACRS Presentation: NuScale Instrumentation and Controls Design Overview,

CNV Peak Containment Pressure Closure Meeting - Part 2 Incoming RAI Discussion,

NuScale PRA Overview,

LTC RAI Closure Plan,

Scaling RAI Closure Meeting,

ACRS Presentation Chapter 2 - Site Characteristics and Site Parameters,

ACRS Presentation Chapter 17 - Quality Assurance and Reliability Assurance,

Basis for an RFT Stand COL Item,

Program Manual PM-1218-63882

Addressing Component Fatigue for NuScale DCA,

EGGS Valve DCA Demonstration Testing,

ACRS Subcommittee Presentation: NuScale FSAR - Emergency Core Cooling System - V

Chapters 2 and 17 ACRS Full Committee,

Policy Options for Single Failure Criterion,

Reactor Vessel Flange Tool (RFT) Design Plan and Schedule,

PM-0219-64501, Revision 0

ACRS Presentation Chapter 11 - Radioactive Waste Management,

ACRS Presentation Chapter 12 - Radiation Protection,

DHRS and ECCS Logic Changes,

ACRS Presentation: NuScale Chapter 9, Auxiliary Systems,

ACRS Presentation: Chapter 4, Reactor Overview,

ACRS Presentation: Chapter 5, Reactor Coolant System and Connecting Systems Over

ACRS Presentation: NuScale Chapters 4 and 5 Full Committee,

FSAR Section 3.9.2: Dynamic Testing and Analysis of Systems, Components, and Equ

ACRS Subcommittee Presentation: NuScale FSAR Chapter 14, Initial Test Program an

ACRS Subcommittee Presentation: NuScale FSAR Chapter 21, Multi-Module Design Con

ACRS Subcommittee Presentation: NuScale FSAR Chapter 19, Probabilistic Risk Asse

Mitigation of Beyond-Design-Basis-Events, NuScale FSAR Chapter 20,

ACRS Subcommittee Presentation, NuScale FSAR Chapter 6, Engineered Safety Featur

ACRS Subcommittee Presentation, NuScale FSAR Chapter 15, Transient and Accident

TF-3 Modal Demonstration Testing and SIET Tour,

ACRS Subcommittee Presentation, NuScale FSAR Chapter 20, Mitigation of Beyond-De

ACRS NuScale Full Committee Presentation: NuScale FSAR Chapter 3, Design of Stru

ACRS Full Committee Presentation: NuScale Topical Report-Evaluation Methodology

ACRS Full Committee Presentation: NuScale FSAR Chapter 15 - Transient and Accide

ACRS Full Committee Presentation: NuScale Topical Report-Evaluation Methodology

ACRS Subcommittee Presentation NuScale Topical Report -Accident Source Term Meth

ACRS Subcommittee Presentation: NuScale Source Term Methodology Application,

ACRS Subcommittee Presentation: NuScale FSAR Chapter 3 - Protection Against Turb

ACRS Subcommittee Presentation: NuScale FSAR - Steam Generator Design,

ACRS Subcommittee Presentation: NuScale FSAR Chapter 8 - Electric Power,

ACRS Subcommittee Presentation: NuScale Topical Report - Rod Ejection Accident M

ACRS Subcommittee Presentation: NuScale Topical Report - Rod Ejection Accident M

ACRS Subcommittee Presentation: NuScale Topical Report- Non-Loss-of-Coolant Acci

ACRS Subcommittee Presentation: NuScale Topical Report - Non-Loss-of-Coolant Acc

ACRS Subcommittee Presentation: NuScale Topical Report - Loss-of-Coolant Acciden

ACRS Subcommittee Presentation: NuScale Topical Report - Loss-of-Coolant Acciden

ACRS Subcommittee Presentation: NuScale FSAR Topic-Resolution of Chapter 15 Phas

ACRS Subcommittee Presentation: NuScale FSAR Chapter 19 - Probabilistic Risk Ass

ACRS Subcommittee Presentation: NuScale FSAR Topic-Resolution of Chapter 15 Phas

ACRS Full Committee Presentation: NuScale - Steam Generator Design,

ACRS Full Committee Presentation: NuScale - Steam Generator Design (Closed Sessi

ACRS Subcommittee Presentation: NuScale Topic - Hydrogen Monitoring,

ACRS Full Committee Presentation: NuScale Topical Report-Rod Ejection Accident M

ACRS Full Committee Presentation: NuScale Topical Report-Non-Loss-of-Coolant Acc

ACRS Full Committee Presentation: NuScale Topical Report, Loss-of-Coolant Accide

Public Meeting Presentation: Topic - Emergency Core Cooling System (ECCS) Boron

ACRS Full Committee Presentation NuScale Topic-Probabilistic Risk Assessment wit

ACRS Full Committee Presentation: Nuscale Topic - Hydrogen/Oxygen Monitoring

NRC Public Meeting: Revisions to NuScale's EPZ Sizing Methodology Topical Report

Public Meeting Presentation: Topic - Emergency Core Cooling System (ECCS) Boron

Public Meeting Presentation: Topic - Emergency Core Cooling System (ECCS) Boron

Program Manual PM-0620-70243

NRC Public Meeting Presentation: Boron Redistribution and Associated Design and

ACRS Full Committee Presentation: NuScale Topic - Boron Redistribution and Assoc

ACRS Full Committee Presentation: NuScale Topic - Boron Redistribution and Gener

Topical Report TR-0915-17772

Loss-Of-Coolant Accident Evaluation Model,

- TR-1015-18653, Design of Highly Integrated Protection System Platform, Revis

NuScale Power Critical Heat Flux Correlation NSP2,

Loss Of Coolant Accident Evaluation Model.

Evaluation Methodology For Stability Analysis Of the NuScale Power Module.

Summary Of The May 23, 2017, Category 1, Public Teleconference To Discuss The D

NuScale Instrument Setpoint Methodology Technical Report

Presentation to the ACRS Subcommittee, NuScale TR-0116-20825 Rev. 1, Applicabil

Accident Source Term Methodology

Request for Public Meeting to Address Proposed Limitation and Condition 4.5 in t

NuScale Generic Technical Guidelines,

"Containment Vessel Ultimate Pressure Integrity, TR-0917-56119 (NRC Docket No. 5

NuScale Comprehensive Vibration Assessment Program,

Safety Evaluation of NuScale TR-0118-58005, Improvements in SSFI Analysis, Rev 2

ACRS Response Letter (Oedo-18-00321) - Safety Evaluation Nuscale TR-0616-48793,

NuScale Power Module Seismic Analysis,

Nuclear Steam Supply System Advanced Sensors Technical Report,

Pipe Rupture Hazards Analysis.

Subchannel Analysis Methodology.

Technical Specifications Regulatory Conformance and Development,

Fuel Storage Rack Analysis,

Effluent Release (GALE Replacement) Methodology and Results,

NuScale Comprehensive Vibration Assessment Program Measurement and Inspection Pl

NuScale Design of Physical Security Systems,

Combustible Gas Control,

Containment Systems,

NuScale Containment Leakage Integrity Assurance,

Mitigation Strategies for Extended Loss of AC Power Event,

Loss of Large Areas Due to Explosions and Fires Assessment,

NuScale Topical Report: Quality Assurance Program Description for the NuScale Po

Fluence Calculation Methodology and Results,

NuScale Applicability of AREVA Method for the Evaluation of Fuel Assembly Struct

NuScale Power Module Short-Term Transient Analysis,

NuFuel-HTP2 Fuel and Control Rod Assembly Designs,

Long-Term Cooling Methodology,

Topical Report TR-0711-6

Letter to NuScale Requesting -A for TR-0716-50350

Safety Evaluation for , Control Room Staffing Topical report TR-0420-69456 Publi

Building Design and Analysis Methodology for Safety-Related Structures

FSAR Chapter 4: Reactor

FSAR Chapter 3: Design of Structures, Components

FSAR Chapter 5: Reactor Coolant System

FSAR Chapter 9: Auxiliary Systems

FSAR Chapter 7: Instrumentation and Controls

FSAR Chapter 15: Transient and Accident Analysis

FSAR Chapter 20: Generic Issues

FSAR Chapter 18: Human Factors Engineering

FSAR Chapter 8: Electric Power

FSAR Chapter 19: PRA and Severe Accidents

FSAR Chapter 10: Steam and Power Conversion

FSAR Chapter 14: Initial Test Program

FSAR Chapter 17: Quality Assurance

FSAR Chapter 16: Technical Specifications

FSAR Chapter 6: Engineered Safety Features

FSAR Chapter 21: Multi-Module Design

FSAR Chapter 12: Radiation Protection

FSAR Chapter 1: Introduction and General Description

FSAR Chapter 2: Site Characteristics

FSAR Chapter 11: Radioactive Waste Management

FSAR Chapter 13: Conduct of Operations

ACRS Review 2017-09

ACRS Review 2018-06

ACRS Review 2018-08

ACRS Review 2018-10

ACRS Review 2018-12

ACRS Review 2019-01

ACRS Review 2019-02

ACRS Review 2019-03

ACRS Review 2019-04

ACRS Review 2019-05

ACRS Review 2019-06

ACRS Review 2019-07

ACRS Review 2019-09

ACRS Review 2019-10

ACRS Review 2019-11

ACRS Review 2019-12

ACRS Review 2020-01

ACRS Review 2020-02

ACRS Review 2020-03

ACRS Review 2020-04

ACRS Review 2020-05

ACRS Review 2020-07

Applicant Correspondence

NRC Correspondence

ACRS Meetings

Public Meetings

Other Meetings

All Inspections