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CNL-23-036, Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08)18 December 2023Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08)
IR 05000327/202301116 October 2023Triennial Fire Protection Inspection Report 05000327/2023011 and 05000328/2023011
ML23163A03913 June 2023Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000327/2023011, 05000328/2023011) and Request for Information (RFI)
ML22334A0736 February 2023Issuance of Amendment Nos. 363 and 357 Regarding Modification of the Approved Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
ML22210A11824 August 2022Issuance of Amendment Nos. 358 and 352 Regarding Technical Specifications Task Force Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B
CNL-22-034, Second Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b (SQN-TS-20-03)13 May 2022Second Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b (SQN-TS-20-03)
IR 05000327/202200111 May 2022Integrated Inspection Report 05000327/2022001, 05000328/2022001 and 07200034/2010002
CNL-22-023, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf28 April 2022Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf
IR 05000327/202201025 April 2022Design Basis Assurance Inspection (Teams) Inspection Report 05000327/2022010 and 05000328/2022010
CNL-21-085, License Amendment Request to Modify Approved 10 CFR 50.69 Categorization Process (SQN-TS-21-07)24 February 2022License Amendment Request to Modify Approved 10 CFR 50.69 Categorization Process (SQN-TS-21-07)
ML21308A4938 November 2021Pre-submittal Meeting Presentation - License Amendment Request to Revise Sequoyah Operating License to Use Fire and Seismic PRA Models for 10 CFR 50.69 Risk-Informed Categorizations (EPID L-2021-LRM-0109) (Slides)
05000327/LER-2021-001, & LER 2021-001-00 for Sequoyah Nuclear Plant, Units 1 & 2, Ice Bed Inoperable Due to Exceeding Surveillance Requirement Frequency22 September 2021& LER 2021-001-00 for Sequoyah Nuclear Plant, Units 1 & 2, Ice Bed Inoperable Due to Exceeding Surveillance Requirement Frequency
CNL-21-026, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b (SQN-TS-20-03)5 August 2021License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b (SQN-TS-20-03)
ML21084A1904 May 2021Issuance of Amendment Nos. 355 and 348 Regarding Revision to Technical Specification Table 3.3.3-1, Post Accident Monitoring Instrumentation
IR 05000327/202001220 October 2020Plants - Triennial Fire Protection Inspection Report 05000327/2020012 and 05000328/2020012
IR 05000327/202030124 April 2020NRC Operator License Examination Report 05000327/2020301 and 05000328/2020301
ML20106F09914 April 2020301 Final SRO Written Exam
ML20106F07314 April 2020301 Final RO Written Exam
ML20098D8617 April 2020Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000327/2020012 and 05000328/2020012) and Request for Information)
CNL-19-066, Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis, (TS-19-02)14 January 2020Application to Revise Updated Final Safety Analysis Report Regarding Changes to Hydrologic Analysis, (TS-19-02)
CNL-19-061, Seismic Probabilistic Risk Assessment for Sequoyah Nuclear Plant, Units 1 and 2 - Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task18 October 2019Seismic Probabilistic Risk Assessment for Sequoyah Nuclear Plant, Units 1 and 2 - Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Fo
ML19179A13518 September 2019Issuance of Amendment Nos. 346 and 340, Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors
ML18277A11027 August 2019Units, 1 & 2 Issuance of Amendment Nos. 309, 332, 292, 345, 339, 128, and 31 Regarding Unbalanced Voltage Protection
ML19156A2615 June 201910 CFR 50.59 and 10 CFR 72.48 Changes, Tests, and Experiments Summary Report and Commitment Summary Report
ML19151A58431 May 2019Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Specification Bases
ML19058A0297 May 2019Issuance of Amendments Request to Modify Essential Raw Cooling Water Control Center Breakers and to Revise the Updated Final Safety Analysis Report (SQN-TS-17-04)
IR 05000327/201901025 April 2019NRC Design Bases Assurance Inspection (Team) Report 05000327/2019010 and 05000328/2019010
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,.21 March 2019Response 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,.
ML19015A41915 January 2019NRR E-mail Capture - RAI - Sequoyah Nuclear Plant, Units 1 and 2, LAR to Adopt 10 CFR50.69 Risk-informed SSC
CNL-18-130, Revised Application to Modify the Technical Specifications for Unbalanced Voltage Relays19 November 2018Revised Application to Modify the Technical Specifications for Unbalanced Voltage Relays
ML18233A19421 August 2018NRR E-mail Capture - Additional Information Needs Identified - Sequoyah 1 and 2, Request to Modify Essential Raw Cooling Water Motor Control Center Breakers and to Revise Updated Final Analysis Report (SQN-TS-17-04)
ML20311A41220 April 20182017 Q1-Q4 ROP Inspection Findings
ML20311A37920 April 20182017 Q1-Q4 ROP Inspection Findings
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)16 March 2018Submittal 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)
CNL-17-150, Request to Modify Essential Raw Cooling Water Motor Control Center Breakers and to Revise the Updated Final Safety Analysis Report (SQN-TS-17-04)9 March 2018Request to Modify Essential Raw Cooling Water Motor Control Center Breakers and to Revise the Updated Final Safety Analysis Report (SQN-TS-17-04)
NL-17-034, Application to Modify the Technical Specifications for Browns Ferry (TS-512), Sequoyah (TS-17-03), and Watts Bar (TS-17-20) to Resolve the Open Phase Issue Identified in NRC Bulletin 2012-01, Design Vulnerability in Electrical Power System17 November 2017Application to Modify the Technical Specifications for Browns Ferry (TS-512), Sequoyah (TS-17-03), and Watts Bar (TS-17-20) to Resolve the Open Phase Issue Identified in NRC Bulletin 2012-01, Design Vulnerability in Electrical Power System.
CNL-17-034, Application to Modify the Technical Specifications for Browns Ferry (TS-512), Sequoyah (TS-17-03), and Watts Bar (TS-17-20) to Resolve the Open Phase Issue Identified in NRC Bulletin 2012-01, Design Vulnerability in Electrical Power Syste17 November 2017Application to Modify the Technical Specifications for Browns Ferry (TS-512), Sequoyah (TS-17-03), and Watts Bar (TS-17-20) to Resolve the Open Phase Issue Identified in NRC Bulletin 2012-01, Design Vulnerability in Electrical Power System.
ML17156A21418 September 2017Transmittal Letter Requesting Licensee Comments on OPC 2.206 Proposed DD
CNL-17-098, Revised Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels27 July 2017Revised Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels
05000327/LER-2017-00214 July 2017Automatic Actuation of Emergency Diesel Generators Due to Loss of Power to 6.9kV Shutdown Board
LER 17-002-00 for Sequoyah, Unit 1, Regarding Automatic Actuation of Emergency Diesel Generators Due to Loss of Power to 6.9kV Shutdown Board
ML17193A96112 July 2017(Retake) 2016-302 Exam Draft Items - Delay Release 2 Yrs
CNL-17-085, Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels7 July 2017Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels
ML17150A07923 May 2017NRR E-mail Capture - Request for Additional Information Related to TVA Fleet LAR for EAL Change to Adopt NEI-99-01 Rev.6 (CAC Nos. MF9054 - MF9060)
IR 05000327/201700718 May 2017Triennials Fire Protection Program Inspection (NRC Inspection Report 05000327/2017007 and 05000328/2017007)
IR 05000327/20170013 May 2017Sequoyah - NRC Integrated Inspection Report 05000328/2017001
IR 05000328/20170013 May 2017NRC Integrated Inspection Report 05000328/2017001
05000327/LER-2017-00126 April 2017Breached Door Renders Both Trains of the Auxiliary Building Gas Treatment System Inoperable
LER 17-001-00 for Sequoyah, Unit 1, Regarding Breached Door Renders Both Trains of the Auxiliary Building Gas Treatment System Inoperable
IR 05000327/201600414 February 2017Reissue Sequoyah Nuclear Plant - NRC Integrated Inspection Report 05000327/2016004 and 05000328/2016004
ML17004A0614 January 2017Notification of NRC Triennial Fire Protection Inspection (Team)(Report 05000327/2017007 and 05000328/2017007)
IR 05000327/201600328 October 2016NRC Integrated Inspection Report Inspection Report 05000327/2016003 and 05000328/2016003