ML25231A144
| ML25231A144 | |
| Person / Time | |
|---|---|
| Site: | Clinch River |
| Issue date: | 08/20/2025 |
| From: | Schiele R Tennessee Valley Authority |
| To: | Quynh Nguyen Advisory Committee on Reactor Safeguards |
| References | |
| Download: ML25231A144 (1) | |
Text
TVA Clinch River Nuclear Project Construction Permit Application -
Application Overview Ray Schiele Senior Licensing Manager
Topics
Introductions
TVA Mission and the Role of New Reactors Pathway from Early Site Permit to Construction Permit Application Structure/Content of the Construction Permit Application Questions 2
TVA Mission and the Role of New Reactors B U I L T F O R T H E P E O P L E O F T H E V A L L E Y 3
I N N O V A T I N G F O R T H E P E O P L E O F T H E V A L L E Y Since its inception, TVA has innovated to meet the needs of the Valley.
1 9 3 3 T V A A C T S I G N E D 1 9 4 0 s H Y D R O 1 9 5 0 s F O S S I L 1 9 6 0 s N U C L E A R 1 9 7 0 s P U M P E D S T O R A G E &
G A S 2020+
T V A S E N E R G Y F U T U R E E N E R G Y Electricity at the lowest feasible rate and highest feasible reliability E N V I R O N M E N T Stewardship of the natural resources for best use by the public E C O N O M I C D E V E L O P M E N T To attract and retain good jobs and capital investment in the Valley Today and in the future, the Valley needs affordable, reliable, resilient, and secure energy to lead the nation in energy innovation and economic development.
TVAs Clinch River Nuclear Site Department of Energy Oak Ridge Reservation The CRN Site is located on 935-acres of TVA land in Oak Ridge, Roane County, Tennessee adjacent to US Department of Energy Oak Ridge Reservation.
CRN Site 4
5 2019 2020 2021 2022 2023 2024 2025 ESP Issued SMR Technology Evaluation CPA Scoping CPA Development CPA Submittal Annotated Outlines:
- NUREG 0800 Environmental Report
- Select GVH BWRX-300 Technology
- Development of Regulatory Framework Documents
- Develop an Environmental Report for CRN-1
- Develop 10 CFR 50 Construction Permit Application
- Part 1 ER 4/2025
- Part 2 PSAR 5/2025 CPA Acceptance Review
- ER 6/12/2025
- ER 7/14/2025
- PSAR 7/14/2025
- Topical Report for NQA-1 CRN 1 Program
- Exemption Request 2.101(a)(5)
- Exemption Request Excavation
- LCOE
- Supply Chain Constraints
- Advanced Manufacturing
- Seismic Considerations
- Modular Construction
Construction Permit Application Content (CPA) 6 Content of TVA CRN-1 CPA - General and Administrative Information 10 CFR 50.33 Contents of applications; general information - Preliminary Safety Analysis Report [Non-Public]
10 CFR 50.34(a) Contents of applications; technical information.
NUREG 0800 Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: (LWR Edition)
Reg Guide 1.70 Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants (LWR Edition) - Preliminary Safety Analysis Report [Public] - Exemptions and Variances 10 CFR 50.12 Specific exemptions 10 CFR 52.39 Finality of early site permit determinations - Environmental Report 10 CFR 51.50 Environmental report-construction permit, early site permit, or combined license stage NUREG 1555 Standard Review Plans for Environmental Reviews for Nuclear Power Plants Reg Guide 4.2 Preparation Of Environmental Reports For Nuclear Power Stations Application Content
>4000 pages
7
- Field surveys of the entirety of the CRN Site were conducted for nine resources from 2021-2024.
CRN-1 Disturbance Area Barge Unloading Facility 7
PSAR Chapter 1 Introduction and General Plant Description
8 PSAR Chapter 2 - Site Characteristics and Site Parameters Dispositions ESP-006 Permit Conditions and COL Action Items Updated CRN Site Characteristics and Parameters Aspects of CRN ESPA Site Safety Analysis Report Incorporated by Reference PSAR Table 1.8-1 provides a cross reference of Site Safety Analysis Report information that is incorporated by reference into this PSAR:
2.0 Plant Parameter Envelope Evaluation 2.1 Geography and Demography 2.2 Nearby Industrial, Transportation and Military Facilities 2.3 Meteorology 2.4 Hydrologic Engineering 2.5 Geology, Seismology, and Geotechnical Engineering 13.3 Emergency Preparedness 13.6 Physical Security
9 CRN-1 Site Plan Confirmatory Core Bores
Chapter 3-Design of Structures, Systems, and Components 10 BWRX-300 Design Feature Safety Strategy LTR in Review (Section 3.2)
DPSC LTR Rev 3 in Review (Section 3.8)
11 BWRX-300 Design Feature
Natural Circulation BWR Increased RPV height
Tall chimney Reactor Isolation Valves Flow Stability LTR In Review Reactor Isolation Valves Chapter 4 - Reactor & Chapter 5 - Reactor Coolant System and Connected Systems
12 Chapter 6 - Engineered Safety Features
Chapter 7 -
Instrumentation and Controls 13
14 Chapter 8 - Electric Power Chapter 8 Contents Includes:
Offsite and Onsite Power Systems Uninterruptable Power Supply BWRX-300 Design Feature The BWRX-300 does not require AC power to reach a safe, stable shutdown following an Anticipated Operational Occurrence or a Design Basis Accident Stored energy via batteries is provided:
1.
Ensure that all functions that maintain the plant in a safe condition are available 2.
Monitoring equipment can be powered for at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following a Design Basis Accident.
15 Chapter 9-Auxiliary Systems BWRX-300 Design Feature
Multiple credited Ultimate Heat Sinks
BWRX-300 water is strategically located during operations in SC1 pools to last for 7 days until FLEX/EME replenishment
16 Chapter Contents Includes:
Turbine Generator Main Steam System Additional Steam and Power Conversion Systems Chapter 10 -
Steam and Power Conversion System
Chapter 11 - Radioactive Waste Management 17 Chapter Contents Includes:
Source Terms Liquid Waste Management System Gaseous Waste Management System Solid Waste Management System Process Radiation Monitoring Chapter 12 -Radiation Protection Chapter Contents Includes:
Occupational Radiation Exposure ALARA Radiation Sources Radiation Protection Design Features Dose Assessment Health Physics Program Chapter 14 - Initial Test Program Chapter Contents Includes:
Scope of Initial Test Program Design Features that are Specific, Unique or First of a Kind Conformance of Test Programs with Regulatory Guides Test Program Schedule Augmenting Staff During Test Program Chapter Contents Includes:
Organizational Structure Training Emergency Preparedness Operational Programs Plant Procedures Physical Security Fitness for Duty Chapter 13 -
Conduct of Operations
Chapter 15 -
Safety Analyses 18 Chapter Contents Includes:
Considerations of the BWRX-300 Safety Analysis Identification, Categorization and Grouping of Postulated Initiating Events and Accident Scenarios Safety Objectives and Acceptance Criteria Human actions Deterministic Safety Analyses Probabilistic Safety Assessment Results of Deterministic Safety Analyses and Probabilistic Safety Assessment BWRX-300 Design Feature Re-characterization of Safety Related/Non-Safety Related to the Safety Class 1, 2, 3, N structure Chapter 16 -
Technical Specifications Chapter Contents Includes:
Preliminary Safety Analysis Report Requirements Regulatory Guidance for Preliminary Technical Specification Contents Conformance with Industry Standards and Practices Methodology for Selection of Preliminary Technical Specification Contents Results of Selection Methodology Application
19 Variances
CRN ESP VAR 2.0-1 Site Grade Level
CRN ESP VAR 2.0-2 Ground Water Level
CRN ESP VAR 2.0-3 Single Unit Thermal Megawatts
CRN ESP VAR 2.1-1 2020 Census Data
CRN ESP VAR 2.2-1 Nearby Industrial, Transportation and Military Facilities
CRN ESP VAR 2.4.12-1 Groundwater Level Models
CRN ESP VAR 2.4.12-1 C-1Groundwater Vistas Version 8.19 Build 4 - Exemptions and Variances Exemptions
Reactor Vessel Material Surveillance Program Chapter 17 - Quality Assurance Chapter Contents Includes:
Quality Assurance During Design and Construction Phases Design Reliability Assurance Program Quality Assurance Program Description-New Reactor Applicants Topical Report - NNP-TR-001-NP Quality Assurance Program Description for TVA New Nuclear incorporated by reference.
Final Safety Evaluation contains Limitations and Conditions (PSAIs) and are disposition in Chapter 17.5
Questions/Comments/Actions 20
21