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L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications27 March 2023and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or ApplicationsFuel cladding
L-2019-151, 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report6 August 201910 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report
ML19002A16012 March 2019Nrc'S Record of Decision for the License Renewal Application for Seabrook Station, Unit 1 - 1-4-19Incorporated by reference
License Renewal
Environmental Justice
ML19101A45514 November 2018Samuel Miranda Public Comments for November 15, 2018 Seabrook LRA MeetingProbabilistic Risk Assessment
Aging Management
SBK-L-17172, Seventh Annual Update to the License Renewal Application18 October 2017Seventh Annual Update to the License Renewal ApplicationNon-Destructive Examination
Aging Management
Moisture barrier
ML17191A41210 July 2017NextEra Service Position Paper: Seabrook Service Water TS 3.7.4
SBK-L-17099, Flooding Focused Evaluation for Impact of New Flooding Hazard Information28 June 2017Flooding Focused Evaluation for Impact of New Flooding Hazard InformationInternal Flooding
Hydrostatic
FLEX
Fukushima Dai-Ichi
Flooding Focused Evaluation
SBK-L-16108, Status of Required Actions for EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design Basis External Events26 July 2016Status of Required Actions for EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design Basis External EventsSafe Shutdown
Boric Acid
High winds
Shutdown Margin
Ultimate heat sink
Safe Shutdown Earthquake
Internal Flooding
FLEX
Tornado Generated Missile
Fukushima Dai-Ichi
Seismically rugged
Spent Fuel Pool Instrumentation
Earthquake
ML16147A19629 April 201610 CFR 50.59 Report, Revision 17 to Updated Final Safety Analysis Report, Revision 14 to Appendix R, Revision 15 to Appendix a, and Revision 146 to the Technical Requirements ManualSafe Shutdown
Spent Fuel Pool Instrumentation
ML16117A31226 April 2016SBK-L-16056 - NextEra Energy Seabrook, LLC - Revised Response to NRC 12/23/2015 Questions on Ceb Root CauseHydrostatic
Finite Element Analysis
SBK-L-15195, Best Estimate Large Break Loss of Coolant Accident 10 CFR 50.46 30-Day Report7 November 2015Best Estimate Large Break Loss of Coolant Accident 10 CFR 50.46 30-Day Report
ML15274A21425 September 2015FPL-081-PR-002, Revision 0, Flooding Hazards Reevaluation Report, Figure 4-1 Through Figure 4-33
ML15274A21225 September 2015FPL-081-PR-002, Revision 0, Flooding Hazards Reevaluation Report, Pp. 1 Through Figure 2-1High winds
Ultimate heat sink
Tornado Missile
Hydrostatic
FLEX
Tornado Generated Missile
Fukushima Dai-Ichi
Earthquake
SBK-L-15181, FPL-081-PR-002, Revision 0, Flooding Hazards Reevaluation Report, Figure 4-34 Through Figure the End25 September 2015FPL-081-PR-002, Revision 0, Flooding Hazards Reevaluation Report, Figure 4-34 Through Figure the EndHydrostatic
Earthquake
ML15208A04912 August 2015Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Revaluations for Recommendation 2.1 of the Near-Term Task Force Review of InsightsSafe Shutdown Earthquake
Fukushima Dai-Ichi
Earthquake
SBK-L-14229, Expedited Seismic Evaluation Process Report (CEUS Sites) Related to the Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from The...19 December 2014Expedited Seismic Evaluation Process Report (CEUS Sites) Related to the Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from The...Safe Shutdown
Boric Acid
Ultimate heat sink
Probabilistic Risk Assessment
FLEX
Fukushima Dai-Ichi
Earthquake
Power-Operated Valves
SBK-L-14090, ANP-3243NP, Rev. 1, Seabrook Station, Unit 1, Fixed Incore Detector System Analysis Supplement to YAEC-1855PA, Licensing Report.31 May 2014ANP-3243NP, Rev. 1, Seabrook Station, Unit 1, Fixed Incore Detector System Analysis Supplement to YAEC-1855PA, Licensing Report.
ML13295A25217 December 2013Review of the 2012 Steam Generator Tube Inspections
ML13267A3884 December 2013Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool InstrumentationHigh Radiation Area
Mission time
FLEX
Spent Fuel Pool Instrumentation
Battery sizing
Fire Protection Program
ML13189A1972 July 2013Third Annual Update to License Renewal ApplicationNon-Destructive Examination
Hydrostatic
Coatings
Aging Management
Moisture barrier
License Renewal
SBK-L-12101, NextEra Energy Seabrook License Renewal Application, Structures Monitoring Program Supplement-Alkali-Silica Reaction (ASR) Monitoring16 May 2012NextEra Energy Seabrook License Renewal Application, Structures Monitoring Program Supplement-Alkali-Silica Reaction (ASR) MonitoringNon-Destructive Examination
Fire Barrier
Aging Management
Moisture barrier
Maintenance Rule Program
Fire Protection Program
ML12179A28215 March 2012ASR at Seabrook Station, Shear and Lap Splice Testing
SBK-L-11173, First Annual Update to License Renewal Application and Changes to LRA Appendix a25 August 2011First Annual Update to License Renewal Application and Changes to LRA Appendix aBoric Acid
Aging Management
SBK-L-10118, 10 CFR 72.48 Report of Changes, Tests and Experiments10 August 201010 CFR 72.48 Report of Changes, Tests and Experiments
ML1012704395 May 2010Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants
ML10362031821 January 2010Attachment 2, Document SEA-FLU-001-R-004, Rev 0, Non-Proprietary Version of Seabrook Station Reactor Pressure Vessel Fluence Evaluation at 55 EFPY
ML09265037012 August 2009Westinghouse Electric Company LLC, LTR-SGMP-09-100 NP-Attachment, Response to NRC Request for Additional Information on H*; Model F and Model D5 Steam Generators, Attachment 7Finite Element Analysis
ML09268025130 April 2009Attachment 3, Corrected Pages for WCAP-17071-NP, Revision 0 (Non-Proprietary)
SBK-L-08179, Nine-Month Response to NRC Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems.14 October 2008Nine-Month Response to NRC Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems.
SBK-L-06227, Enclosure 3 to Fple Letter SBK-L-06227 - Ealdbd, Rev a, Seabrook Emergency Action Level Design Basis Document17 October 2007Enclosure 3 to Fple Letter SBK-L-06227 - Ealdbd, Rev a, Seabrook Emergency Action Level Design Basis DocumentSafe Shutdown
High winds
Reactor Vessel Water Level
Ultimate heat sink
Offsite Dose Calculation Manual
Anticipated operational occurrence
Tornado Missile
Internal Flooding
Probabilistic Risk Assessment
Operating Basis Earthquake
Design basis earthquake
Safeguards Contingency Plan
Earthquake
Fuel cladding
Pressure Boundary Leakage
SBK-L-07040, Semi-Annual Fitness-For-Duty Report for July-December 200626 February 2007Semi-Annual Fitness-For-Duty Report for July-December 2006Fitness for Duty
SBK-L-07002, NRC Bulletin 2004-01, OR11, Inspection of Alloy 82/182/600 Materials 60-Day Report4 January 2007NRC Bulletin 2004-01, OR11, Inspection of Alloy 82/182/600 Materials 60-Day ReportBoric Acid
VT-2
Pressure Boundary Leakage
Through-Wall Leak
ET 06-0035, Relaxation Request from First Revised NRC Order EA-03-009 Regarding Requirements for Nondestructive Examination of Nozzles Below J-Groove5 October 2006Relaxation Request from First Revised NRC Order EA-03-009 Regarding Requirements for Nondestructive Examination of Nozzles Below J-GrooveNondestructive Examination
Pressure Boundary Leakage
SBK-L-06176, Semi-Annual Fitness-For-Duty Report31 August 2006Semi-Annual Fitness-For-Duty ReportFitness for Duty
L-2006-180, Sation; St. Lucie, Units 1 and 2 and Turkey Point, Units 3 and 4 - Groundwater Questionnaire31 July 2006Sation; St. Lucie, Units 1 and 2 and Turkey Point, Units 3 and 4 - Groundwater QuestionnaireBoric Acid
Offsite Dose Calculation Manual
SBK-L-06071, Reactor Vessel Weld Wire Material Data Update12 April 2006Reactor Vessel Weld Wire Material Data Update
SBK-L-06068, Resubmittal of Semi-Annual Fitness-For-Duty Report24 March 2006Resubmittal of Semi-Annual Fitness-For-Duty ReportFitness for Duty
SBK-L-06017, Semi-Annual Fitness-for-Duty Report1 March 2006Semi-Annual Fitness-for-Duty ReportFitness for Duty
ML07271056216 December 2005Caoldon Non-Proprietary Information Package for Seabrook/Nrc Meeting on December 16, 2005
SBK-L-05166, Semi-Annual Fitness-for-Duty Report19 August 2005Semi-Annual Fitness-for-Duty ReportFitness for Duty
SBK-L-05122, Cycle 11 Core Operating Limits Report26 May 2005Cycle 11 Core Operating Limits ReportBoric Acid
Shutdown Margin
SBK-L-05030, Semi-Annual Fitness-For-Duty Report from 07/1/2004 Through 12/31/200423 February 2005Semi-Annual Fitness-For-Duty Report from 07/1/2004 Through 12/31/2004Fitness for Duty
ML07270084931 January 2005Caldon Experience in Nuclear Feedwater Flow MeasurementPower change
SBK-L-04019, Semi-Annual Fitness-For-Duty Report26 August 2004Semi-Annual Fitness-For-Duty ReportFitness for Duty
ML04156034826 May 2004Special Report: Explosive Gas Monitoring Instrumentation Inoperable Greater than 30 DaysGrab sample
ML0410501751 April 2004Background Information to Support License Amendment Request 04-03, Application for Stretch Power UpratePower change
ML0404906719 February 2004Semi-Annual Fitness-for-Duty Report for Period Ending December 31, 2003Fitness for Duty
ML04021052016 January 2004Part 21 Report Involving an Undersized Emergency Feedwater Pump Shaft
ML03364059123 December 2003Unusual Fish Impingement - December 2003High winds
ML03329045217 November 2003Cycle 10 Core Operating Limits ReportShutdown Margin