Semantic search

Jump to navigation Jump to search
 Issue dateTitle
ML22131A1275 May 20228 to Fire Protection of Safe Shutdown Capability (Appendix R)
ML20322A4176 November 2020Memorandum and Order (Denying Motion to Reopen, Motion for Leave, and Motion for Partial Reconsideration; Granting in Part and Denying in Part Motion for Leave to Reply) (LBP-20-12)
ML20323A17022 October 2020Rev. 17 to Fire Protection Safe Shutdown Capability
ML20254A23410 September 2020Nextera'S Answer Opposing C-10 Motion for Leave and Motion for Partial Reconsideration of LBP-20-9
ML18302A2105 December 2019Documentation of the Completion of Required Actions Taken in Response to the Lessons Learned from the Fukushima Dai-Ichi Accident
IR 05000443/201500224 July 2019NRC031 - Letter from Glenn T. Dentel, NRC, to Dean Curtland, NextEra, Seabrook Station, Unit No. 1 - NRC Integrated Inspection Report 05000443/2015002, (Aug. 5, 2015)
ML17310A47327 October 2017Seabrook Station Revision 15 to Appendix R, Fire Protection of Safe Shutdown Capability
ML15096A2552 November 2015Issuance of Amendment Regarding License Amendment Request 14-04, Revised Reactor Coolant System Pressure-Temperature Limits Applicable for 44 Effective Full Power Years
ML15217A2565 August 2015IR 05000443/2015002, April 1, 2015 Through June 30, 2015, Seabrook Station, Unit No. 1 - Integrated Inspection Report
ML15105A34623 March 2015NSAL-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
ML14318A02421 October 2014Seabrook Station Updated Final Safety Analysis Report, Revision 16, Fire Protection of Safe Shutdown Capability (10CFR50, Appendix R), Revision 13
ML14245A38629 August 2014NRDC V. NRC Et. Al., No. 13-1311 (Scheduled Oral Argument November. 21, 2014)
L-14-102, License Amendment Request 14-04, Revised Reactor Coolant System Pressure - Temperature Limits Applicable for 55 Effective Full Power Years24 July 2014License Amendment Request 14-04, Revised Reactor Coolant System Pressure - Temperature Limits Applicable for 55 Effective Full Power Years
ML14128A49816 June 2014Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident
SBK-L-14052, NextEra Energy Seabrook, LLC Seismic Hazard and Screening Report (CEUS Sites) Response to NRC Request for Information Per 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-27 March 2014NextEra Energy Seabrook, LLC Seismic Hazard and Screening Report (CEUS Sites) Response to NRC Request for Information Per 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ich
ML13364A31124 January 2014Nuclear Regulatory Commission Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident (TAC No. Mf
ML13281A47621 November 2013Audit Report Regarding Seismic Walkdowns to Support Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident - Seabrook Station
ML13143A15426 June 2013Plan for the Regulatory Audit Regarding Seismic Walkdowns at the Seabrook, to Support Implementation of Near-Term Task Force Recommendation 2.3, Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident
SBK-L-12243, Response to NRC 10 CFR 50.54 (F) Request for Information Re Near-Term Force Recommendation 2.3, Flooding27 November 2012Response to NRC 10 CFR 50.54 (F) Request for Information Re Near-Term Force Recommendation 2.3, Flooding
SBK-L-12242, Response to NRC 10 CFR 50.54(f) Request for Information Regarding Near-Term Task Force Recommendation 2.3, Seismic26 November 2012Response to NRC 10 CFR 50.54(f) Request for Information Regarding Near-Term Task Force Recommendation 2.3, Seismic
ML12340A48721 November 2012Enclosure 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
ML12265A41021 September 2012Friends of the Coast and New England Coalition'S Motion (with September 19, 2012) Corrections for Leave to File a New Contention Concerning Nextera Energy Seabrook'S Amendment of Its Aging Management Program for Safety-Related Concrete Stru
ML12241A06127 August 2012Friends of the Coast and New England Coalition'S Motion for Leave to File a New Contention Concerning NextEra Energy Seabrook'S Amendment of Its Aging Management Program for Safety-Related Concrete Structures
ML12053A34012 March 2012Request 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 of Insights from the Fukushima Dai-Ichi Accident
ML12056A05012 March 2012Enclosure 4 - Recommendation 2.3: Flooding
ML12056A04912 March 2012Enclosure 3 - Recommendation 2.3: Seismic
IR 05000443/201000212 May 2010IR 05000443-10-002; 01/01/2010-03/31/2010; Seabrook Station, Unit No.1; Routine Integrated Report
ML0913305423 November 2008Seabrook - Fire Protection of Safe Shutdown Capability (10CFR50, Appendix R, Revision 9
IR 05000443/200500410 May 2005IR 05000443-05-004, on 01/01/2005 - 03/31/2005, Seabrook Station, Unit 1. Personnel Performance Related to Non-Routine Plant Evolutions and Events, Operability Evaluations & Post-Maintenance Testing
ML05076044030 December 2004Final - Section a Operating Exam (Folder 3)
ML0509500909 December 2004Draft - Section a Operating Exam (Folder 2)
ML20216F51431 August 1999Rept on Status of Public Petitions Under 10CFR2.206
IR 05000443/19970077 January 1998Insp Rept 50-443/97-07 on 971005-1206.No Violations Noted. Major Areas Inspected:Operations,Engineering,Maint & Plant Support Re Implementation of Security Program
Information Notice 1997-48, Inadequate or Inappropriate Interim Fire Protection Compensatory Measures9 July 1997Inadequate or Inappropriate Interim Fire Protection Compensatory Measures
ML20133A54624 December 1996Insp Rept 50-443/96-10 on 961001-1129.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering,Plant Support & Assurance of Quality
05000443/LER-1992-002, Forwards License Amend Request 92-12 to License NPF-86, Changing TS to Correct Acceptance Value for Sum of RHR Sys Injection Line Flow Rates,Per LER 92-02-0022 October 1992Forwards License Amend Request 92-12 to License NPF-86, Changing TS to Correct Acceptance Value for Sum of RHR Sys Injection Line Flow Rates,Per LER 92-02-00
NRC Generic Letter 1992-026 March 1992NRC Generic Letter 1992-002: Resolution of Generic Issue 79, Unanalyzed Reactor Vessel (PWR) Thermal Stress During Natural Convection Cooldown.
ML0311405497 November 1991Withdrawn NRC Generic Letter 1991-018: Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability
Information Notice 1991-38, Thermal Stratification in Feedwater System Piping13 June 1991Thermal Stratification in Feedwater System Piping
Information Notice 1989-55, Degradation of Containment Isolation Capability by a High-Energy Line Break30 June 1989Degradation of Containment Isolation Capability by a High-Energy Line Break
IR 05000443/19880026 April 1988Safety Insp Rept 50-443/88-02 on 880202-0328.No Violations Noted.Major Areas Inspected:Operational Safety,Licensee Action on Previous Insp Findings,Nrc Bulletins,Info Notices & Generic Ltr,Lers & Svc Water Sys Corrosion
Information Notice 1987-67, Lessons Learned from Regional Inspections of Licensee Actions in Response to IE Bulletin 80-1131 December 1987Lessons Learned from Regional Inspections of Licensee Actions in Response to IE Bulletin 80-11
Information Notice 1987-67, Lessons Learned from Regional Inspections of Licensee Actions in Response to Ie Bulletin 80-1131 December 1987Lessons Learned from Regional Inspections of Licensee Actions in Response to Ie Bulletin 80-11
NRC Generic Letter 1987-129 July 1987NRC Generic Letter 1987-012: Loss of Residual Heat Removal (RHR) While the Reactor Coolant System (RCS) Is Partially Filled
Information Notice 1987-05, Miswiring in a Westinghouse Rod Control System2 February 1987Miswiring in a Westinghouse Rod Control System
Information Notice 1986-53, Improper Installation of Heat Shrinkable Tubing26 June 1986Improper Installation of Heat Shrinkable Tubing
ML20137N02124 January 1986Forwards Revised Excerpts from Fire Protection of Safe Shutdown Capability (10CFR50,App R) & Deviations from 10CRF50,App R to Suppl 851202 Submittal
NRC Generic Letter 1983-4319 December 1983NRC Generic Letter 1983-043: Reporting Requirements of 10 CFR Part 50, Sections 50.72 & 50.73 & Standard Technical Specifications
Retrieved from "https://kanterella.com/Special:Ask/-5B-5BTopic::Unanalyzed-20Condition-5D-5D-20-5B-5BSite::Seabrook-5D-5D/-3FIssue-20date/-3FTitle/mainlabel%3D/order%3Ddescending/sort%3Dissue-20date/offset%3D0/format%3Dtable/searchlabel%3DSeabrook"