Category:Part 21 Correspondence
MONTHYEARML15105A3462015-03-23023 March 2015 NSAL-15-2 - Impact of a Break in the Reactor Coolant Pump No. 1 Seal Leak-off Line Piping on Seal Leakage During a Loss of Seal Cooling Event ML1000700732009-11-19019 November 2009 USNRC 10CFR Part 21 Notification - Flowserve Figure 848 Disk/Disk Nut Separation ML0404205672004-02-0303 February 2004 Undersized Emergency Feedwater Pump Shaft Report Pursuant to 10 CFR Part 21.21 ML0402105202004-01-16016 January 2004 Part 21 Report Involving an Undersized Emergency Feedwater Pump Shaft 2015-03-23
[Table view] Category:Report
MONTHYEARL-2024-084, Relief Request 4A-01, Rev 1 - Revision to Relief Request for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld2024-05-30030 May 2024 Relief Request 4A-01, Rev 1 - Revision to Relief Request for Examination of Control Rod Drive Mechanism (Rod) Housing H-4 Canopy Seal Weld L-2024-061, NextEra Energy Seabrook, LLC, License Amendment Request - One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite Transmission Network and the Onsite Class 1E Distribut2024-05-10010 May 2024 NextEra Energy Seabrook, LLC, License Amendment Request - One Time Extension to Technical Specification 3.8.1.1.a, Allowed Outage Time with One Independent Circuit Between the Offsite Transmission Network and the Onsite Class 1E Distributio 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 Applications2023-03-27027 March 2023 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 Applications L-2022-168, And Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2022-10-26026 October 2022 And Point Beach Units 1 and 2 - 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report SBK-L-21106, Transmittal of WCAP-18607-NP, Analysis of Capsule X from the NextEra Energy Seabrook Unit 1 Reactor Vessel Radiation Surveillance Program2021-09-30030 September 2021 Transmittal of WCAP-18607-NP, Analysis of Capsule X from the NextEra Energy Seabrook Unit 1 Reactor Vessel Radiation Surveillance Program ML21062A1462021-04-21021 April 2021 Memo to File: Final Ea/Fonsi of 2012 and 2015 Decommissioning Funding Plans for Seabrook Station Unit 1 Independent Spent Fuel Storage Installation (2012 and 2015) L-2019-151, 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2019-08-0606 August 2019 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report L-2019-010, Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Welds2019-03-19019 March 2019 Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography for Ferritic and Austenitic Welds ML19002A1602019-03-12012 March 2019 Nrc'S Record of Decision for the License Renewal Application for Seabrook Station, Unit 1 - 1-4-19 ML19101A4552018-11-14014 November 2018 Samuel Miranda Public Comments for November 15, 2018 Seabrook LRA Meeting ML18012A5682018-01-12012 January 2018 Technical Evaluation Report: Storm Surge_Seabrook_January2018 SBK-L-17172, Seventh Annual Update to the License Renewal Application2017-10-18018 October 2017 Seventh Annual Update to the License Renewal Application SBK-L-17136, Seismic High Frequency Confirmation Report for the Reevaluated Seismic Hazard Information2017-08-28028 August 2017 Seismic High Frequency Confirmation Report for the Reevaluated Seismic Hazard Information ML17191A4122017-07-10010 July 2017 NextEra Service Position Paper: Seabrook Service Water TS 3.7.4 SBK-L-17099, Flooding Focused Evaluation for Impact of New Flooding Hazard Information2017-06-28028 June 2017 Flooding Focused Evaluation for Impact of New Flooding Hazard Information L-2017-014, Florida Power & Light Company - 10 CPR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications for 20162017-04-17017 April 2017 Florida Power & Light Company - 10 CPR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications for 2016 ML16279A0502016-07-31031 July 2016 Enclosure 3: MPR-4153, Revision 2, Seabrook Station-Approach for Determining Through-Thickness Expansion from Alkali-Silica Reaction, July 2016 (Seabrook Fp# 100918) (Non-proprietary) ML16279A0492016-07-31031 July 2016 Enclosure 2: Simpson Gumpertz & Heger, Inc., Evaluation and Design Confirmation of As-Deformed Ceb, 150252-CA-02, Revision 0, July 2016 (Seabrook FP#100985) ML16216A2422016-07-31031 July 2016 MPR-4273, Revision 0, Seabrook Station - Implications of Large-Scale Test Program Results on Reinforced Concrete Affected by Alkali-Silica Reaction, July 2016 ML16216A2412016-07-31031 July 2016 MPR-4288, Revision 0, Seabrook Station: Impact of Alkali-Silica Reaction on Structural Design Evaluations, July 2016 SBK-L-16071, Sg&H Report 160268-R-01 Development of ASR Load Factors for Seismic Category I Structures (Including Containment) at Seabrook Station. Seabrook, Nh Revision 02016-07-27027 July 2016 Sg&H Report 160268-R-01 Development of ASR Load Factors for Seismic Category I Structures (Including Containment) at Seabrook Station. Seabrook, Nh Revision 0 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 Events2016-07-26026 July 2016 Status of Required Actions for EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design Basis External Events ML16147A1962016-04-29029 April 2016 10 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 Manual ML16117A3122016-04-26026 April 2016 SBK-L-16056 - NextEra Energy Seabrook, LLC - Revised Response to NRC 12/23/2015 Questions on Ceb Root Cause ML16068A1352016-02-27027 February 2016 Attachment 3 - Clean Copy of Seabrook Emergency Action Levels - Initiating Conditions, Threshold Values and Basis ML16068A1392016-02-27027 February 2016 Attachment 5 - Technical Information for Proposed Initiating Conditions and Emergency Action Levels ML16068A1312016-02-27027 February 2016 Attachment 2 - Markup of Seabrook Station Emergency Action Levels -Initiating Conditions, Threshold Values and Basis ML16068A1372016-02-27027 February 2016 Attachment 4 - NEI 99-01, Rev. 6, Deviations and Differences, Seabrook Station Nuclear Power Plant - Unit 1 SBK-L-15195, Best Estimate Large Break Loss of Coolant Accident 10 CFR 50.46 30-Day Report2015-11-0707 November 2015 Best Estimate Large Break Loss of Coolant Accident 10 CFR 50.46 30-Day Report ML15274A2142015-09-25025 September 2015 FPL-081-PR-002, Revision 0, Flooding Hazards Reevaluation Report, Figure 4-1 Through Figure 4-33 SBK-L-15181, FPL-081-PR-002, Revision 0, Flooding Hazards Reevaluation Report, Figure 4-34 Through Figure the End2015-09-25025 September 2015 FPL-081-PR-002, Revision 0, Flooding Hazards Reevaluation Report, Figure 4-34 Through Figure the End ML15274A2122015-09-25025 September 2015 FPL-081-PR-002, Revision 0, Flooding Hazards Reevaluation Report, Pp. 1 Through Figure 2-1 ML15208A0492015-08-12012 August 2015 Staff 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 Insights 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...2014-12-19019 December 2014 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... ML14216A4062014-07-24024 July 2014 Attachment 5, WCAP-17444-NP, Reactor Vessel Closure Head/Vessel Flange Requirements Evaluation for Seabrook Unit 1, (Non-proprietary) ML14216A4052014-07-24024 July 2014 Attachment 3, WCAP-17441-NP, Seabrook Unit 1 Heatup and Cooldown Limit Curves for Normal Operation SBK-L-14090, ANP-3243NP, Rev. 1, Seabrook Station, Unit 1, Fixed Incore Detector System Analysis Supplement to YAEC-1855PA, Licensing Report.2014-05-31031 May 2014 ANP-3243NP, Rev. 1, Seabrook Station, Unit 1, Fixed Incore Detector System Analysis Supplement to YAEC-1855PA, Licensing Report. ML14030A5522014-02-25025 February 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14049A1972014-02-14014 February 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Seabrook Station, TAC No.: MF0836 ML13295A2522013-12-17017 December 2013 Review of the 2012 Steam Generator Tube Inspections ML13267A3882013-12-0404 December 2013 Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation ML13260A1612013-07-31031 July 2013 ANP-3243NP, Rev. 0, Seabrook Station Unit I Fixed Incore Detector System Analysis Supplement to YAEC-1855PA, Licensing Report ML13189A1972013-07-0202 July 2013 Third Annual Update to License Renewal Application ML13099A0192013-03-19019 March 2013 Attachment 5 to SBK-L-13061, Holtec Non-Proprietary Licensing Report HI-2114996, Rev. 3, Licensing Report for Seabrook Spent Fuel Pool and New Fuel Vault Analyses. ML12340A4872012-11-21021 November 2012 Enclosure to SBK-L-12242, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic ML12339A2742012-09-13013 September 2012 Concrete Summary 4-12 SBK-L-12101, NextEra Energy Seabrook License Renewal Application, Structures Monitoring Program Supplement-Alkali-Silica Reaction (ASR) Monitoring2012-05-16016 May 2012 NextEra Energy Seabrook License Renewal Application, Structures Monitoring Program Supplement-Alkali-Silica Reaction (ASR) Monitoring ML12179A2822012-03-15015 March 2012 ASR at Seabrook Station, Shear and Lap Splice Testing ML12038A0382012-01-30030 January 2012 Licensing Report for Seabrook Spent Fuel Pool and New Fuel Vault Analyses (Holtec International Document HI-2114996, Revision 2 SBK-L-12256, WCAP-17441-NP, Rev 0, Seabrook Unit 1 Heatup and Cooldown Limit Curves for Normal Operation2011-10-31031 October 2011 WCAP-17441-NP, Rev 0, Seabrook Unit 1 Heatup and Cooldown Limit Curves for Normal Operation 2024-05-30
[Table view] Category:Miscellaneous
MONTHYEARL-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 Applications2023-03-27027 March 2023 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 Applications L-2019-151, 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report2019-08-0606 August 2019 10 CFR 50.46 - Emergency Core Cooling System LBLOCA 30-Day Report ML19002A1602019-03-12012 March 2019 Nrc'S Record of Decision for the License Renewal Application for Seabrook Station, Unit 1 - 1-4-19 ML19101A4552018-11-14014 November 2018 Samuel Miranda Public Comments for November 15, 2018 Seabrook LRA Meeting SBK-L-17172, Seventh Annual Update to the License Renewal Application2017-10-18018 October 2017 Seventh Annual Update to the License Renewal Application ML17191A4122017-07-10010 July 2017 NextEra Service Position Paper: Seabrook Service Water TS 3.7.4 SBK-L-17099, Flooding Focused Evaluation for Impact of New Flooding Hazard Information2017-06-28028 June 2017 Flooding Focused Evaluation for Impact of New Flooding Hazard Information 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 Events2016-07-26026 July 2016 Status of Required Actions for EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design Basis External Events ML16147A1962016-04-29029 April 2016 10 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 Manual ML16117A3122016-04-26026 April 2016 SBK-L-16056 - NextEra Energy Seabrook, LLC - Revised Response to NRC 12/23/2015 Questions on Ceb Root Cause SBK-L-15195, Best Estimate Large Break Loss of Coolant Accident 10 CFR 50.46 30-Day Report2015-11-0707 November 2015 Best Estimate Large Break Loss of Coolant Accident 10 CFR 50.46 30-Day Report ML15274A2142015-09-25025 September 2015 FPL-081-PR-002, Revision 0, Flooding Hazards Reevaluation Report, Figure 4-1 Through Figure 4-33 ML15274A2122015-09-25025 September 2015 FPL-081-PR-002, Revision 0, Flooding Hazards Reevaluation Report, Pp. 1 Through Figure 2-1 SBK-L-15181, FPL-081-PR-002, Revision 0, Flooding Hazards Reevaluation Report, Figure 4-34 Through Figure the End2015-09-25025 September 2015 FPL-081-PR-002, Revision 0, Flooding Hazards Reevaluation Report, Figure 4-34 Through Figure the End ML15208A0492015-08-12012 August 2015 Staff 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 Insights 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...2014-12-19019 December 2014 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... SBK-L-14090, ANP-3243NP, Rev. 1, Seabrook Station, Unit 1, Fixed Incore Detector System Analysis Supplement to YAEC-1855PA, Licensing Report.2014-05-31031 May 2014 ANP-3243NP, Rev. 1, Seabrook Station, Unit 1, Fixed Incore Detector System Analysis Supplement to YAEC-1855PA, Licensing Report. ML13295A2522013-12-17017 December 2013 Review of the 2012 Steam Generator Tube Inspections ML13267A3882013-12-0404 December 2013 Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation ML13189A1972013-07-0202 July 2013 Third Annual Update to License Renewal Application SBK-L-12101, NextEra Energy Seabrook License Renewal Application, Structures Monitoring Program Supplement-Alkali-Silica Reaction (ASR) Monitoring2012-05-16016 May 2012 NextEra Energy Seabrook License Renewal Application, Structures Monitoring Program Supplement-Alkali-Silica Reaction (ASR) Monitoring ML12179A2822012-03-15015 March 2012 ASR at Seabrook Station, Shear and Lap Splice Testing SBK-L-11173, First Annual Update to License Renewal Application and Changes to LRA Appendix a2011-08-25025 August 2011 First Annual Update to License Renewal Application and Changes to LRA Appendix a SBK-L-10118, 10 CFR 72.48 Report of Changes, Tests and Experiments2010-08-10010 August 2010 10 CFR 72.48 Report of Changes, Tests and Experiments ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants ML1036203182010-01-21021 January 2010 Attachment 2, Document SEA-FLU-001-R-004, Rev 0, Non-Proprietary Version of Seabrook Station Reactor Pressure Vessel Fluence Evaluation at 55 EFPY ML0926503702009-08-12012 August 2009 Westinghouse 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 7 ML0926802512009-04-30030 April 2009 Attachment 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.2008-10-14014 October 2008 Nine-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 Document2007-10-17017 October 2007 Enclosure 3 to Fple Letter SBK-L-06227 - Ealdbd, Rev a, Seabrook Emergency Action Level Design Basis Document SBK-L-07040, Semi-Annual Fitness-For-Duty Report for July-December 20062007-02-26026 February 2007 Semi-Annual Fitness-For-Duty Report for July-December 2006 SBK-L-07002, NRC Bulletin 2004-01, OR11, Inspection of Alloy 82/182/600 Materials 60-Day Report2007-01-0404 January 2007 NRC Bulletin 2004-01, OR11, Inspection of Alloy 82/182/600 Materials 60-Day Report ET 06-0035, Relaxation Request from First Revised NRC Order EA-03-009 Regarding Requirements for Nondestructive Examination of Nozzles Below J-Groove2006-10-0505 October 2006 Relaxation Request from First Revised NRC Order EA-03-009 Regarding Requirements for Nondestructive Examination of Nozzles Below J-Groove SBK-L-06176, Semi-Annual Fitness-For-Duty Report2006-08-31031 August 2006 Semi-Annual Fitness-For-Duty Report L-2006-180, Sation; St. Lucie, Units 1 and 2 and Turkey Point, Units 3 and 4 - Groundwater Questionnaire2006-07-31031 July 2006 Sation; St. Lucie, Units 1 and 2 and Turkey Point, Units 3 and 4 - Groundwater Questionnaire SBK-L-06071, Reactor Vessel Weld Wire Material Data Update2006-04-12012 April 2006 Reactor Vessel Weld Wire Material Data Update SBK-L-06068, Resubmittal of Semi-Annual Fitness-For-Duty Report2006-03-24024 March 2006 Resubmittal of Semi-Annual Fitness-For-Duty Report SBK-L-06017, Semi-Annual Fitness-for-Duty Report2006-03-0101 March 2006 Semi-Annual Fitness-for-Duty Report ML0727105622005-12-16016 December 2005 Caoldon Non-Proprietary Information Package for Seabrook/Nrc Meeting on December 16, 2005 SBK-L-05166, Semi-Annual Fitness-for-Duty Report2005-08-19019 August 2005 Semi-Annual Fitness-for-Duty Report SBK-L-05122, Cycle 11 Core Operating Limits Report2005-05-26026 May 2005 Cycle 11 Core Operating Limits Report SBK-L-05030, Semi-Annual Fitness-For-Duty Report from 07/1/2004 Through 12/31/20042005-02-23023 February 2005 Semi-Annual Fitness-For-Duty Report from 07/1/2004 Through 12/31/2004 ML0727008492005-01-31031 January 2005 Caldon Experience in Nuclear Feedwater Flow Measurement SBK-L-04019, Semi-Annual Fitness-For-Duty Report2004-08-26026 August 2004 Semi-Annual Fitness-For-Duty Report ML0415603482004-05-26026 May 2004 Special Report: Explosive Gas Monitoring Instrumentation Inoperable Greater than 30 Days ML0410501752004-04-0101 April 2004 Background Information to Support License Amendment Request 04-03, Application for Stretch Power Uprate ML0404906712004-02-0909 February 2004 Semi-Annual Fitness-for-Duty Report for Period Ending December 31, 2003 ML0402105202004-01-16016 January 2004 Part 21 Report Involving an Undersized Emergency Feedwater Pump Shaft ML0336405912003-12-23023 December 2003 Unusual Fish Impingement - December 2003 ML0332904522003-11-17017 November 2003 Cycle 10 Core Operating Limits Report 2023-03-27
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