Site Map: Nuclear Reactors
This page shows how the U.S. Nuclear Regulatory Commission (NRC) has organized the reactor-related information available through our public Web site. These links will take you directly to the indicated pages on our site.
- Regulated Reactors
- Regulated Activities
- Operating
Reactors
- What We Regulate
- How We Regulate
- Regulations, Guidance, and Communications
- Licensing
- Technical Specifications
- Power
Uprates
- Background on Power Uprates
- Types of Power Uprates
- Regulatory Process for Submitting/Reviewing Power Uprate Requests
- Regulations and
Guidance
- Generic Guidance for Power Uprates
- Recent Safety Evaluations for Power Uprates
- Past Requests for
Additional Information Concerning Power Uprates
- Measurement Uncertainty Recapture Uprates for Boiling Water Reactors
- Measurement Uncertainty Recapture Uprates for Pressurized Water Reactors
- Surry 1 & 2
- Prairie Island 1 & 2
- North Anna 1 & 2
- Calvert Cliffs 1 & 2
- Davis-Besse
- Vogtle 1 & 2
- Crystal River 3
- Seabrook
- Palisades
- Kewaunee
- Indian Point 2
- D.C. Cook 2
- D.C. Cook 1
- Point Beach 1 & 2
- Indian Point 3
- H. B. Robinson
- Sequoyah 1 & 2
- South Texas 1 & 2
- Waterford 3
- Comanche Peak 1 & 2
- Beaver Valley 1 & 2
- San Onofre 2 & 3
- Salem 1 & 2
- Watts Bar
- Stretch Uprates for Pressurized Water Reactors
- Extended Uprates for Boiling Water Reactors
- Extended Uprates for Pressurized Water Reactors
- Status of Power Uprate Applications
- Public Involvement
- Public Meetings
- Contact Us
- License
Renewal
- Overview
- License Renewal Process
- Regulations
- Guidance
- Guidance, Updates, Schedule and Background
- Public Involvement
- Commission Papers Presenting Staff Recommendations
- Status of Current
Applications and Industry Initiatives
- Plant Applications
for License Renewal
- Completed
Applications
- Calvert Cliffs, Units 1 and 2
- Oconee Nuclear Station, Units 1, 2 and 3
- Arkansas Nuclear One, Unit 1
- Edwin I. Hatch Nuclear Plant, Units 1 and 2
- Turkey Point Nuclear Plant, Units 3 and 4
- North Anna, Units 1 and 2, and Surry, Units 1 and 2
- Peach Bottom, Units 2 and 3
- St. Lucie, Units 1 and 2
- Fort Calhoun Station, Unit 1
- McGuire, Units 1 and 2, and Catawba, Units 1 and 2
- H.B. Robinson Nuclear Plant, Unit 2
- R.E. Ginna Nuclear Power Plant, Unit 1
- V.C. Summer Nuclear Station, Unit 1
- Dresden, Units 2 and 3, and Quad Cities, Units 1 and 2
- Farley, Units 1 and 2
- Arkansas Nuclear One, Unit 2
- D.C. Cook, Units 1 and 2
- Millstone, Units 2 and 3
- Point Beach, Units 1 and 2
- Browns Ferry, Units 1, 2, and 3
- Brunswick, Units 1 and 2
- Nine Mile Point, Units 1 and 2
- Monticello
- Palisades
- James A. FitzPatrick
- Wolf Creek, Unit 1
- Harris, Unit 1
- Oyster Creek
- Vogtle, Units 1 and 2
- Three Mile Island, Unit 1
- Beaver Valley, Units 1 and 2
- Susquehanna, Units 1 and 2
- Cooper Nuclear Station
- Duane Arnold Energy Center
- Kewaunee Power Station
- Vermont Yankee Nuclear Power Station
- Applications
Currently Under Review
- Pilgrim 1, Unit 1
- Indian Point, Units 2 and 3
- Prairie Island, Units 1 and 2
- Palo Verde, Units 1, 2, and 3
- Crystal River, Unit 3
- Hope Creek
- Salem, Units 1 and 2
- Diablo Canyon, Units 1 and 2
- Columbia Generating Station
- Seabrook Station, Unit 1
- Davis-Besse Nuclear Power Station, Unit 1
- South Texas Project, Units 1 and 2
- Future Submittals of Applications
- Completed
Applications
- Owners' Groups
- Industry Activities
- Subscribe to License Renewal Correspondence for a Specific Plant
- Plant Applications
for License Renewal
- Introduction to License Renewal Tutorial
- License Transfers and Mergers
- License Fees
- Oversight
- Power
Reactors
- About Reactor Oversight
- Recent Results
- Background
- Research and Test Reactors
- High-Value Datasets
- Power
Reactors
- Operational
Experience
- Reactor Safety Focus Areas
- Davis-Besse Reactor
Vessel Head Degradation
- 0350 Oversight Panel
- Overview
- Images
- Reactor Pressure Vessel Top Head Images
- Overview of the Davis Besse Reactor Head Inspection Area
- Looking Down at the Davis Besse Reactor Head Inspection Area
- Looking Down (second angle) at the Davis Besse Reactor Head Inspection Area
- Looking Up at the Davis Besse Reactor Head Inspection Area
- Underneath the Davis Besse Reactor Head
- Davis Besse Control Rod Drive Open Access Hatch View
- Davis Besse Reactor Vessel Head Insulation Top View with Nozzle #3 Removed
- Davis Besse Reactor Vessel Head Insulation Top View with Nozzle #3 Removed (overhead view)
- Cavity Looking Toward Nozzle Eleven
- Closeup View of Cavity Looking Toward Nozzle Eleven
- Containment Access Location
- Underneath View of Cutout
- Underneath View of Cutout - Closeup View
- 17 Inch Cutout - View 1
- 17 Inch Cutout - View 2
- Downward View of Reactor Vessel Head Cutout Hole - View 1
- Downward View of Reactor Vessel Head Cutout Hole - View 2
- Downward View of Reactor Vessel Head Cutout Hole - View 3
- Looking Back Toward Nozzle Three
- Looking Toward Nozzle Eleven
- Nozzle Eleven Perspective
- Undercut Area Toward Nozzle Eleven
- Transporting New Head to Davis-Besse
- Reactor Pressure Vessel Bottom Head Images
- Reactor Pressure Vessel Top Head Images
- Fire Protection Program
- Fitness-for-Duty
Programs
- New Requirements for Part 26
- Regulatory Guide For Implementing Fatigue Management Programs
- Industry Guidance for Reactor Construction FFD Programs (NEI 06-06, Rev. 5)
- Frequently Asked Questions
- FFD Program Performance Reports
- History of the Fitness-for-Duty Program
- Related Documents and Other Resources
- Contact Us About Fitness-for-Duty
- Access Authorization Programs
- Human Factors
- Operating Reactor Maintenance Effectiveness
- Multiple/Repetitive Degraded Cornerstone Column
- PWR Sump Performance
- Overview
- NRC Activities
- Reports and Correspondence
- Reactor Pressure Boundary Integrity Issues for Pressurized Water Reactors
- Reactor Vessel Integrity
- Steam Generator Action Plan
- Groundwater Contamination (Tritium)
- Buried Piping Activities
- Expectation of Increase in Reports of Degraded Buried Piping
- Davis-Besse Reactor
Vessel Head Degradation
- Results and Databases
- Reactor Safety Focus Areas
- Operator
Licensing
- Regulations, Guidance, and Communications
- Licensing Process
- Oversight Program
- Public Involvement
- Related Documents and Other Resources
- Generic
Fundamentals Examinations
- General Information
- Boiling
Water Reactor (BWR) Question Bank
- Components
- Reactor Theory
- Thermodynamics
- Past Exams - questions organized by exam date (beginning with the January 2001 exam)
- Pressurized
Water Reactor (PWR) Question Bank
- Components
- Reactor Theory
- Thermodynamics
- Past Exams - questions organized by exam date (beginning with the January 2001 exam)
- Operator Licensing Program Feedback
- Contact Us About Operator Licensing
- New
Reactors
- What We Regulate
- Combined License Applications
- Location of Projected New Nuclear Power Reactors
- Bell
Bend Nuclear Power Plant
- Application
Documents
- Applicant Documents
- NRC Documents
- Application Review Schedule
- Requests for Additional Information
- Public Meetings
- Application
Documents
- Bellefonte Nuclear Station, Units 3 and 4
- Callaway
Plant, Unit 2
- Application
Documents
- Applicant Documents
- NRC Document
- Application Review Schedule
- Requests for Additional Information
- Public Meetings
- Application
Documents
- Calvert Cliffs, Unit 3
- Comanche
Peak, Units 3 and 4
- Application
Documents
- Applicant Documents
- NRC Documents
- Application Review Schedule
- Requests for Additional Information
- Public Meetings
- Application
Documents
- Fermi,
Unit 3
- Application
Documents
- Applicant Documents
- NRC Documents
- Application Review Schedule
- Requests for Additional Information
- Public Meetings
- Application
Documents
- Grand
Gulf, Unit 3
- Application
Documents
- Applicant Documents
- NRC Documents
- Application Review Schedule
- Requests for Additional Information
- Public Meetings
- Application
Documents
- Levy County, Units 1 and 2
- Nine
Mile Point, Unit 3
- Application
Documents
- Applicant Documents
- NRC Documents
- Application Review Schedule
- Requests for Additional Information
- Public Meetings
- Application
Documents
- North
Anna, Unit 3
- Application
Documents
- Applicant Documents
- NRC Documents
- Application Review Schedule
- Requests for Additional Information
- Public Meetings
- Application
Documents
- River
Bend Station, Unit 3
- Application
Documents
- Applicant Documents
- NRC Documents
- Application Review Schedule
- Requests for Additional Information
- Public Meetings
- Application
Documents
- Shearon Harris, Units 2 and 3
- South Texas Project, Units 3 and 4
- Turkey Point, Units 6 and 7
- Victoria
County Station, Units 1 and 2
- Application
Documents
- Applicant Documents
- NRC Documents
- Application Review Schedule
- Requests for Additional Information
- Public Meetings
- Application
Documents
- Virgil C. Summer, Units 2 and 3
- Vogtle, Units 3 and 4
- William States Lee III, Units 1 and 2
- Design Certification Applications
- Issued Design Certifications
- Design Certification Applications Currently Under Review
- AP1000 Amendment
- ABWR
Design Certification Rule (DCR) Amendment
- Project Overview
- Application
Documents
- Applicant Documents
- NRC Documents
- Application Review Schedule
- Economic Simplified Boiling-Water Reactor (ESBWR)
- U.S. EPR
- U.S. Advanced Pressurized-Water Reactor (US-APWR)
- ABWR Design Certification Renewal (Toshiba)
- ABWR Design Certification Renewal (GE-Hitachi)
- Early Site Permit Applications
- Issued Early Site Permits
- Early Site Permit Applications Currently Under Review
- Combined License Applications
- How We Regulate
- Regulations, Guidance, and Communications
- Regulatory
Oversight
- Construction
Reactor Oversight Process
- Detailed cROP Description
- Construction Assessment Reports/Inspection Plans
- List of QA Inspection and Audit Reports and Construction Inspection Reports
- Construction Action Matrix Summary and Current Regulatory Oversight
- Construction Action Matrix Deviations
- Construction Substantive Cross Cutting Issues Summary
- cROP Historical Performance from Previous Quarters
- Frequently Asked Questions About the Construction Inspection Program
- Frequently Asked Questions About the Construction Assessment Program
- Construction Inspection Program
- Quality
Assurance (QA)
- Regulations, Standard Review Plan, SECY Paper, and NUREG-1055
- Safety Evaluation Reports Concerning Revised Basis for QA Programs
- QA Inspections for New Reactor Licensing
- Vendor QA
Inspections
- NRO SECY Paper on Enhancements to the Vendor Inspection Program for New Reactors
- NRO SECY Paper on Legal Constraints of Relying on Vendor Inspection Results of Foreign Regulators and the Need for Additional Resources to Achieve the Appropriate Number of NRC Vendor
- Inspection Procedures
- Generic Letters
- Information Notices
- Regulatory Information Summaries
- Commercial-Grade Dedication
- NUREG-0302, Revision 1 (10 CFR Part 21)
- Inspection Reports
- Nuclear Procurement
Issues Committee (NUPIC) and Industry Interactions
- NRC Presentations at Industry Conferences
- Workshops on Vendor Oversight for New Reactor Construction
- Vendor
QA Inspections
- QA Inspection and Audit Reports
- Radiation Protection
- Aircraft
Impact Assessment (AIA) Inspections
- Inspection Reports
- Construction
Reactor Oversight Process
- What We Regulate
- Advanced
Reactors
- Policy Issues Associated with Licensing Non-LWR Designs
- Next Generation Nuclear Plant (NGNP)
- NuScale
- B&W mPower
- Clinch River Site (Tennessee Valley Authority)
- Super-Safe, Small and Simple (4S) Design
- Power Reactor Innovative Small Module (PRISM) Design
- Pebble Bed Modular Reactor (PMBR)
- Hyperion Power Module (HPM)
- Operator Licensing for New Reactors
- Operating
Reactors
- Related Information
Page Last Reviewed/Updated Monday, December 17, 2012
