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 Issue dateTitle
IR 05000443/20230028 August 2023Integrated Inspection Report 05000443/2023002
L-2023-034, Relief Request 4RA-22-001, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2)24 February 2023Relief Request 4RA-22-001, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2)
SBK-L-22094, Relief Request 4RA-22-001, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2)26 October 2022Relief Request 4RA-22-001, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2)
ML22262A3144 October 2022Relief Requests 3IR-18 and 3IR-19, Relief from the Requirements of the ASME Code
ML22131A1065 May 20221 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems
ML22131A1175 May 20221 to Updated Final Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment and Systems
ML22131A1295 May 20221 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features
SBK-L-21126, Fourth 10 Year Interval - Inservice Inspection (ISI) Program Plan4 January 2022Fourth 10 Year Interval - Inservice Inspection (ISI) Program Plan
ML20323A15222 October 2020Rev. 20 to Updated Final Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment and Systems
ML20323A12122 October 2020Rev. 20 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features
ML20323A11922 October 2020Rev. 20 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems
IR 05000443/201100324 July 2019NRC023 - Letter from Arthur L. Burritt, NRC, to Paul Freeman, NextEra, Seabrook Station, Unit No. 1 - NRC Integrated Inspection Report 05000443/2011003 (Aug. 12, 2011)
IR 05000443/201400324 July 2019NRC029 - Letter from Glenn T. Dentel, NRC, to Dean Curtland, NextEra, Seabrook Station, Unit No. 1 - NRC Integrated Inspection Report 05000443/2014003, (Aug. 5, 2014)
ML19205A35024 July 2019NRC007 - Seabrook Station Updated Final Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment and Systems (Oct. 2017)
IR 05000443/201800430 January 2019Integrated Inspection Report 05000443/2018004
ML17310A41227 October 2017Seabrook Station Revision 18 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features
ML17310A41127 October 2017Seabrook Station Revision 18 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant Systems and Connected Systems
ML17310A40627 October 2017Seabrook Station Revision 18 to Updated Final Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment and Systems
ML17027A0787 April 2017Issuance of Amendments Regarding Technical Specifications for Inservice Testing Programs (CAC Nos. MF8202 Through MF8209)
ML16214A27628 July 2016NextEra Energy Resources, LLC, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, and to Request an Alternative to t
ML16147A19029 April 2016Revision 17 to Updated Final Safety Analysis Report, Chapter 5 - Reactor Coolant System and Connected Systems
ML16147A19129 April 2016Revision 17 to Updated Final Safety Analysis Report, Chapter 6 - Engineered Safety Features
ML14317A60221 October 2014Seabrook Station Updated Final Safety Analysis Report, Revision 16, Chapter 6, Engineered Safety Features
ML14317A50921 October 2014Seabrook Station Updated Final Safety Analysis Report, Revision 16, Chapter 3, Design of Structures, Components, Equipment and Systems
ML14317A60521 October 2014Seabrook Station Updated Final Safety Analysis Report, Revision 16, Chapter 5, Reactor Coolant System and Connected Systems
ML14212A4585 August 2014IR 05000443-14-003, April 1, 2014 - June 30, 2014, Seabrook Station, Unit 1, NRC Integrated Report
ML13134A08126 April 2013Updated Final Safety Analysis Report, Revision 15, Chapter 5 - Reactor Coolant System and Connected Systems
ML13134A08226 April 2013Updated Final Safety Analysis Report, Revision 15, Chapter 6 - Engineered Safety Features
ML13134A07126 April 2013Updated Final Safety Analysis Report, Revision 15, Chapter 3 - Design of Structures, Components, Equipment and Systems Through Table 3.9(N)-11
ML13028A1464 April 2013Issuance of Amendment Regarding the Extension of the Inspection Interval for the Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process
SBK-L-12176, Response to Request for Additional Information Regarding Relief Request for Service Water Piping7 September 2012Response to Request for Additional Information Regarding Relief Request for Service Water Piping
ML12226A4624 September 2012Request for Additional Information Regarding Relief Request for Service Water Piping
SBK-L-12137, Relief Request - Proposed Alternative in Accordance with 10 CFR 50.55a (a)(3)(ii)1 August 2012Relief Request - Proposed Alternative in Accordance with 10 CFR 50.55a (a)(3)(ii)
ML12145A0484 June 2012Second 10-Year Interval Inservice Inspection Program Plan Request for Relief No. 21R-19
ML12144A4354 June 2012Second 10-Year Interval Inservice Inspection Program Plan Request for Relief No. 2lR-18
ML11336A28817 November 2011Updated Final Safety Analysis Report, Revision 14, Chapter 3, Design of Structures, Components, Equipment and Systems, - Page Continue
ML11224154312 August 2011IR 05000443/2011003; on 04/01/2011-06/30/2011; Seabrook Station, Unit No. 1; Routine Integrated Report; Fire Protection; Operability Evaluations
ML10159009125 May 2010Seabrook Station - License Renewal Application, Volume Iii
ML09090007615 April 2009Relief Request for Use of Subsequent Edition of Code for the Second Inservice Inspection Interval
ML0913304763 November 2008Seabrook - Updated Final Safety Analysis Report, Revision 12, Chapter 5, Reactor Coolant System and Connected Systems
ML0913304613 November 2008Seabrook - Updated Final Safety Analysis Report, Revision 12, Chapter 6, Engineered Safety Features
ML0913304113 November 2008Seabrook - Updated Final Safety Analysis Report, Revision 12, Chapter 3, Design of Structures, Components, Equipment and Systems
SBK-L-08173, Request for Use of a Subsequent Edition and Addenda of the ASME Code30 September 2008Request for Use of a Subsequent Edition and Addenda of the ASME Code
IR 05000443/20080031 August 2008IR 05000443-08-003; 04/01/2008 - 06/30/2008; Seabrook Station, Unit No. 1; Outage Activities and Access to Radiological Significant Areas
ML0810000081 May 2008Evaluation of Relief Request Alternative to Install Weld Overlays on Pressurizer Dissimilar Metal Welds
SBK-L-08022, Supplement to Request for Use of Structural Weld Overlays as an Alternative Repair Technique13 February 2008Supplement to Request for Use of Structural Weld Overlays as an Alternative Repair Technique
ML0804401697 February 2008G20080093/LTR/08-0076/EDATS: SECY-2008-0086 - Ltr. Sandra Gavutis Request for an Immediate NRC Audit to Verify That All Transnuclear NUHOMS-32PT Casks Have Verified Certificates of Performance
SBK-L-07120, Request for Use of Structural Weld Overlays as an Alternative Repair Technique3 July 2007Request for Use of Structural Weld Overlays as an Alternative Repair Technique
IR 05000443/200600517 January 2007IR 05000443-06-005, 10/1/2006-12/31/2006; Seabrook Station, Unit 1; Refueling and Outage Activities
IR 05000443/200500522 July 2005IR 05000443-05-005; on 4/1/2005-6/30/2005 for Seabrook Station, Unit 1; Post-Maintenance Testing
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