Design Basis Floods for Nuclear Power Plants
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Information Notice 2009-06, Construction-Related Experience with Flood Protection Features
CNL-20-082, Partial Response to Request for Additional Information Regarding Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis (TS-19-02)
CNL-22-053, Response to Request for Additional Information Regarding Application to Revise Sequoyah Nuclear Plant Units 1 and 2 Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis - Second Partial Response to Additional Requ
COMSECY-14-0037, Enclosure 3 - Non-Concurrence Process Record for NCP-2014-010
CNL-24-006, Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis (BFN-TS-550)
DCL-16-016, Units and 2 - Updated Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 Flooding. Part 2 of 2
CNL-15-131, Individual Plant Examination of External Events (IPEEE) Report, Revision 3
NRC 2015-0017, Response to NRC 10 CFR 50.54(f) Request for Information Regarding Near-Term Task Force Recommendation 2.1, Flooding - Submittal of Flooding Hazards Revaluation Report
DCL-15-034, Final Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 Flooding. Part 2 of 2
L-15-074, FENOC, Perry Nuclear Power Plant - Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights from the Fukushima Dai-ichi Ac
PLA-7287, Flood Hazards Reevaluation Report PLA-7287
CNL-14-228, Request for Additional Information Related to License Amendment Request to Updated Final Safety Analysis Report Changes Associated with Hydrologic Analysis
HNP-14-029, Response to Request for Additional Information Regarding Fukushima Lessons Learned - Flooding Hazard Reanalysis Report
L-14-104, Firstenergy Nuclear Operating Co. Response to NRC Request for Information Pursuant to 10 CFR 50.54 (F) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
CNL-14-026, Transmittal of Supplemental Clarification Information for the Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis, TAC No. ME8200 (WBN-UFSAR-12-01)
NL-13-156, 51-9195289-000, Flood Hazard Reevaluation Report Required by 10 CFR 50.54 (F) Near-Term Task Force Recommendation 2.1. Page 3-106 Through Page A-5, Enclosure to NL-13-156
RS-13-110, Flood Hazard Reevaluation Report in Response to the 50.54(f) Information Request Regarding Near-Term Task Force Recommendation 2.1: Flooding
GNRO-2013/00020, Required Response 2 for Near-Term Task Force Recommendation 2.1: Flooding - Hazard Reevaluation Report
SVPLTR 13-0005, Response to NRC Acknowledgement of Response to NRC Request for a Written, Response to NRC Observations and Concerns Regarding Dresden Station, Response Plan for External Flooding Events
L-2012-428, FPL060-PR-001, Rev. 0, Flooding Walkdown Report, in Response to NRC 10 CFR 50.54(f) Request for Information Regarding Near-Term Task Force Recommendation 2.3, Flooding
PLA-6938, Response to Request for Information Pursuant to 10 CFR 50.54 (F) Regarding Results of the SSES Flooding Walkdown (References 1 and 2) PLA-6938
LIC-12-0056, License Amendment Request (LAR) 12-03, Proposed Change to Revise Operating Requirements for Technical Specification 2.16, River Level, & Establish Emergency Action Level Classification Criteria for External Flooding Events Under the Radi
CNL-17-010, Submittal of Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (SQN-TS-17-06)
DCL-17-038, Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 2, Site Characteristics
LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 1, Introduction and General Description of Plant
NL-17-0534, Joseph M. Farley Nuclear Plant, Updated Final Safety Analysis Report, Revision 27, Chapter 3, Part 1
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Appendix 3A, Pse&G Positions on Us NRC Regulatory Guides
NL-16-2280, Vogtle Electric Generating Plant, Units 1 & 2, Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant
NRC-16-0034, Fermi, Unit 2, Revision 20 to Updated Final Safety Analysis Report. Appendix a
RS-15-069, Enclosure 2: Areva, Inc., Rev. 1 to 51-9205719-001, R.E. Ginna Nuclear Power Plant Flood Hazard Reevaluation Report, Part 1 of 2
RS-14-128, LaSalle, Units 1 & 2, Updated Final Safety Analysis Report, Revision 20, Chapter 2.0, Site Characteristics
LR-N14-0041, SL-012271, Revision 0, Hope Creek Generating Station Flood Hazard Reevaluation, Page 1-8 Through Page 2-6
LR-N14-0042, SL-012270, Revision 0, Salem Generating Station Flood Hazard Reevaluation, Page 2-18 Through Page 2-34
LR-N14-0042, SL-012270, Revision 0, Salem Generating Station Flood Hazard Reevaluation, Page 2-35 Through Page 2-55
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 2.4 - Hydrologic Engineering, Pages 2.4-1- 2-4-143
RS-14-006, Clinton, Unit 1, Updated Safety Analysis Report, Revision 16, Chapter 1 - Introduction and General Description of Plant
NL-13-156, 51-9195289-000, Flood Hazard Reevaluation Report Required by 10 CFR 50.54 (F) Near-Term Task Force Recommendation 2.1. Cover Through Page 3-57, Enclosure to NL-13-156
RS-13-009, Clinton, Unit 1, Updated Safety Analysis Report, Revision 15, Chapter 3 - Design of Structures, Components, Equipment and Systems
L-MT-10-080, Correction to Appendix C of the Monticello Individual Plant Examination of External Events
LIC-10-0098, NRC Inspection Report 05000285-10-008, Reply to a Notice of Violation; EA-10-084
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Appendix a Through Appendix N
RS-08-045, LaSalle, Units 1 and 2, Updated Final Safety Analysis Report (Ufsar), Revision 17, Chapter 2.0 - Site Characteristics
RC-18-0080, Virgil C. Summer Nuclear Station, Unit 1, Updated Final Safety Analysis Report, Chapter 3.0, Design of Structures, Components, Equipment and Systems
NL-18-067, Watts Bar Nuclear Plant, Units 1 & 2 - Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (WBN-TS-18-14)
CNL-18-068, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (WBN-TS-17-24)
NRC Generic Letter 79-05, Information Relating to Categorization of Recent Regulatory Guides by the Regulatory Requirements Review Committee
ST-HL-AE-3682, Provides Addl Info on External Events Analysis in Probabilistic Safety Assessment Issued by NRC & Sandia
L-2019-147, Exigent Technical Specification Amendment Request One-Time Allowed Outage Time Extension for Inoperable EDG
TXX-3159, Forwards Freese & Nichols,Inc in Response to NRC 800415 Request for Addl Info Re Floodplain Mgt.Response Will Be Incorporated Into Util Environ Rept
NUREG/CR-7131, Review of Probable Maximum Precipitation Procedures and Databases Used to Develop Hydrometeorological Reports
CNL-17-070, Clinch River Nuclear Site - Submittal of Supplemental Information Associated with Hydrologic Engineering in Support of the Clinch River Nuclear Site Early Site Permit Application
CNL-18-059, Submittal of Revised Site Safety Analysis Report Subsection 2.4.2.2, Flood Design Considerations, and Subsection 2.4.3.5, Probable Maximum Flood Flow, and Figure 2.4.3-3 in Support of Early Site Permit Application for Clinch River Nuclear
IA-85-454, Draft IE Info Notice Entitled, Deficiencies in Equipment Qualification Testing & Certification Process & Recent Environ Qualification Test Facility Insp Results
NSD-NRC-97-5501, Forwards W Responses to FSER Open Items on AP600.Summary of Responses Provided in Table 1,including FSER Open Item Number,Associated Oits Number & Status to Be Designated in W Status Column
IA-86-679, Sser Re Effect of Breakwater Damage on Saltwater Intake Structure
ST-HL-AE-1796, Forwards Annotated Changes to FSAR & Revised Responses to NRC Questions Providing Results of Internal Flooding Analysis/Evaluation.Consequences of Flooding Inside Reactor Makeup Water Sys Acceptable.Related Correspondence
ST-HL-AE-1674, Forwards Comments & marked-up SER (NUREG-0781) Re Operation of South Texas Projects 1 & 2
TSTF-22-06, Technical Specifications Task Force - Request for a Workshop to Discuss the Interaction of Natural Phenomena Protection Design Features and Operability
ST-HL-AE-1447, Forwards Response to Draft SER or FSAR Item F 3.8-2 Re Identification of Codes,Stds & Specs Applicable to Design. Changes Will Be Incorporated in Future FSAR Amend
ST-HL-AE-1418, Forwards Response to Draft SER or FSAR Items Re Sections 2.4,3.4 & 3.5,including marked-up FSAR Pages to Be Incorporated in Future FSAR Amend.List of Draft SER & FSAR Open & Confirmatory Items & Open NRC Questions Provided
ST-HL-AE-1240, Forwards Main Cooling Reservoir Embankment Summary Rept Re Erosion Effects Due to Dike Failure Identified in 10CFR50.55(e) Repts.Analyses Demonstrate Adequate Margin of Safety.Design Basis Contingent Upon Listed Items
ST-HL-AE-1223, Forwards Complete Attachment 2 of Util Responding to Environ & Hydrologic Engineering Branch Request for Addl Info
ST-HL-AE-1093, Final Deficiency Rept Re Insufficient Procedures for Evaluation of Design Basis Flood.Initially Reported on 830830.Circulating Water Piping Will Be Modified by Exposing Concrete Chute at Embankment Crest
ST-HL-AE-1011, First Interim Deficiency Rept Re Design Basis Flood Calculations Not Considering Erosion Effects of Postulated Embankment Breach.Initially Reported on 830830.Next Rept Expected by 840120
RBG-17-552, Forwards Results of Util Studies Re Effect on Plant Structures & Slopes of Ponding in Unit 2 Excavation Identified as Open Item in Draft Ser.Ponding Will Have No Affect on Structural Integrity of Adjacent Plant Structures
NUREG/CR-7133, Synthesis of Extreme Storm Rainfall and Probable Maximum Precipitation in the Southeastern U.S. Pilot Region
05000272/LER-1984-009, :on 840229,technical Discrepancy Confirmed by Bechtel in Design Elevation Calculations for Svc Water Intake Structure.Caused by Design Error.Design Change Will Be Made to Raise Level of Air Intake Louvers
LIC-93-0301, Phase I Rept on IPEEE for FCS Re Tornado,Flooding, Transportation & Nearby Facilities Accidents & Others
A02231, Forwards Agenda to Safety Assessment Repts for SEP Topics II-3.A,hydrologic Description & II-3.C,safety-related Water Supply (UHS)
ST-HL-AE-1219, Forwards Responses to NRC 850211 Questions.Procedures & Sys Review Branch Questions Will Be Answered by Amend to FSAR Section 14.2 by 850601.W/22 Oversize Drawings.Aperture Cards Available in PDR
B10268, Forwards Safety Assessment Rept for SEP Topic II-3.A, Hydrologic Description,Per 810729 Commitment
B10270, Forwards SAR for SEP Topic II-3.B.1, Capability of Operating Plant to Cope W/Design Basis Flooding Conditions. Pending Resolution of Topic,Requirements Procedures Re Selected safety-related Sys May Emerge
B10269, Forwards SAR for SEP Topic II-3.B, Flooding Potential & Protection Requirements, Per 810729 Commitment
CNL-19-002, Response to Request for Additional Information Regarding Application to Modify Sequoyah Nuclear Plant Units 1 and 2, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures,
L-94-220, Forwards Response to Addl Info Re Proposed License Amends on Flood Protection
CNL-15-042, Flood Hazard Reevaluation Report for Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review
RBG-47447, Report 51-9207360-000, Entergy Fleet Fukushima Program Flood Hazard Reevaluation Report for River Bend Station
GNRO-2012/00140, Unit No.1 - Flooding Walkdown Report - Entergys Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from
NUREG/CR-7132, Application of Radar-Rainfall Estimates to Probable Maximum Precipitation in the Carolinas