Semantic search

Jump to navigation Jump to search
 Issue dateTitle
ML22353A06619 December 2022Response to Request for Supplemental Information (D-RSI) Request for Exemption from Non-Destruction-Examination Compliance
IR 05000327/202100227 July 2021Integrated Inspection Report 05000327/2021002 and 05000328/2021002
ML21131A16328 May 2021Authorization and Safety Evaluation for Alternative Request No. 21-ISI-1
CNL-21-037, Request for Alternative, 21-ISI-1 Alternative Repair and Examination for Mid Canopy Seal Weld Replacement26 March 2021Request for Alternative, 21-ISI-1 Alternative Repair and Examination for Mid Canopy Seal Weld Replacement
ML21061A0892 March 2021TVA Presentation Slides for March 2, 2021, Public Meeting to Discuss Sequoyah Alternative Request
IR 05000327/202000223 July 2020Integrated Inspection Report 05000327/2020002 and 05000328/2020002
IR 05000327/201800431 January 2019NRC Integrated Inspection Report 05000327/2018004 and 05000328/2018004
IR 05000327/20180021 November 2018Reissued - Sequoyah Nuclear Plant - Nuclear Regulatory Commission Integrated Inspection Report 05000327/2018002, 05000328/2018002, and 05000327/2018011
ML18219A6547 August 2018Nuclear Regulatory Commission Integrated Inspection Report 05000327/2018002 and 05000328/2018002
ML18058B16327 February 2018Emailed U1 ISI 2018002 RFI - Bcc
IR 05000327/20170021 August 2017NRC Integrated Inspection Reports 05000327/2017002 and 05000328/2017002
CNL-17-057, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Inservice Inspection (ISI) Program, Third Ten Year Interval Request for Relief for 17-ISI-128 April 2017American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Inservice Inspection (ISI) Program, Third Ten Year Interval Request for Relief for 17-ISI-1
ML17079A45517 March 2017Notification of Inspection and Request for Information
ML16286A0626 October 2016Notification of Inspection and Request for Information
ML16172A18610 June 2016Sequoyah Nuclear Plant, Units 1 and 2 - Updated Final Safety Analysis Report Amendment 26 Redacted Version
ML15126A3375 June 2015Corrections to Amendment Nos. 312 (TS-05-08), 306 (TS-05-07), 193 (TS-94-17), and 37 for Unit 1, and Amendment Nos. 290 (TS-03-13) and 170 (TS-94-02) for Unit 2
ML14213A1661 August 2014IR 05000327-14-003 & 05000328-14-003; on 4/1/2014 - 6/30/2014; Sequoyah Nuclear Plant, Units 1 and 2; In-Service Inspection; Radiological Hazard Assessment and Exposure Controls
ML14112A24722 April 2014Notification of Inspection and Request for Information
ML13330A92222 November 2013Enclosure 2 - Volume 16 - Improved Technical Specifications Conversion, ITS Chapter 5.0 Administrative Controls, Revision 0
ML13329A85522 November 2013Enclosure 2 - Volume 5 - Improved Technical Specifications Conversion, ITS Section 3.0, LCO and SR Applicability, Revision 0
ML13276A01830 September 2013Response to NRC Request for Additional Information Regarding the Review of the License Renewal Application, Sets 10 (B.1.23-2a), 11 (4.1-8a), and 12 (30-day)
ML13274A50227 September 2013Initial Exam 2012-302 Draft SRO Written Exam
ML13238A24430 August 2013RAI Set 12
ML13204A39911 July 2013Response to NRC Request for Additional Information Re Reactor Vessel Internals Review of the License Renewal Application, Set 6
ML13141A32013 June 2013Letter Aging Management Programs Audit Report Regarding the Sequoyah Nuclear Plant, Units 1 and 2
ML13151A29731 May 2013Tennessee Valley Authority'S Answer Opposing the Petition for Leave to Intervene and Request for Hearing by the Blue Ridge Environmental Defense League, ET AL
IR 05000327/200900529 January 2010IR 05000327-09-005, 05000328-09-005, 05000327-09-501, 05000328-09-501; 10/01/2009 - 12/31/2009; Sequoyah Nuclear Plant, Units 1 and 2; Refueling and Other Outage Activities and Event Followup
IR 05000327/20080036 August 2008IR 05000327-08-003 and 05000328-08-003, on April 1, 2008 - June 30, 2008, Sequoyah Nuclear Plant, Units 1 and 2; Maintenance Effectiveness
ML08101034210 April 2008Notification of Inspection and Request for Information
ML07080036111 June 2007Request for Relief G-RR-1 Regarding Preemptive Weld Overlays on Pressurizer Nozzles
IR 05000327/200600522 February 2007IR 05000327-06-005, IR 05000328-06-005; IR 07200034-06-002; 10/01/2006 - 12/31/2006; Sequoyah Nuclear Plant, Units 1 & 2; Licensed Operator Requalification Program
ML07065044120 February 2007Response to NRC Order EA-03-009, Issuance of Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors.
ML07030088130 January 2007(Superceded-see ML070720224) IR 05000327-06-005, IR 05000328-06-005; IR 07200034-06-002; 10/01/06 - 12/31/06; Sequoyah Nuclear Plant, Units 1 & 2; Licensed Operator Requalification Program
ML0634201226 December 2006American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI- Reactor Pressure Vessel Head Penetration Tube Remote Inner-Diameter Temper Bead Repair
ML06353020830 November 2006Correction to Amendments Regarding Addition of Limiting Condition for Operation 3.0.7 on Inoperable Snubbers - Unit 1 Tech Specs - S118819
ML06353020130 November 2006Correction to Amendments Regarding Addition of Limiting Condition for Operation 3.0.7 on Inoperable Snubbers - Tech Specs Unit 2 - S118818
ML0629002704 October 2006Tech Spec Pages for Amendment 301 Regarding Addition of Limiting Condition for Operation 3.0.7 on Inoperable Snubbers
ML0629002654 October 2006Tech Spec Pages for Amendment 312 Regarding Addition of Limiting Condition for Operation 3.0.7 on Inoperable Snubbers
ML06174035016 June 2006American Society of Mechanical Engineers (ASME) Boiler & Pressure Vessel Code, Section XI - Preemptive Weld Overlays on Alloy 600 Pressurizer Nozzle-To-Pipe Welds
ML06121010521 April 2006Risk-Informed Inservice Inspection (RI-ISI) Program and Updated Inservice Inspection Program for Third 10-Year Interval
ML06110040830 March 2006Technical Specification Change 05-11, Revision to TS to Support Third 10-Year Interval Inservice Test Program, Rev 1
ML06003045119 December 2005Technical Specifications Change 05-11, Revision to Technical Specification to Support Third 10-Year Interval Inservice Test (ISI) Program.
ML0532503504 November 2005Revisions to the Technical Requirements Manual (TRM) (Revisions 28, 29, 30, 31, 32, 33, 34, and 35) and Technical Specification (TS) Bases (Unit 1 Revisions 25, 26, 27, and 28; Unit 2 Revisions 24, 25, 26, and 27)
IR 05000327/200500328 July 2005IR 05000327-05-003, 05000328-05-003, on 04/01/2005 - 06/30/2005; Sequoyah Nuclear Power Plant, Units 1 & 2; Flood Protection Measures, Refueling and Outage Activities, Event Followup
ML05119048211 April 2005Technical Specifications, Amendment 290, Modifying Requirements for Mode Change Limitations Using the Consolidated Line Item Improvement Process
ML05119048411 April 2005Technical Specifications, Amendment 301, Modifying Requirements for Mode Change Limitations Using Consolidated Line Item Improvement Process
ML0434905992 December 2004Technical Specifications Change 03-13, Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process Cliip.)
ML04212024829 July 2004Issuance of Corrected Page for Amendment Nos. 293 and 283 Regarding Extension of Reactor Coolant Pump Flywheel Inspection Intervals
ML0419702448 July 2004Tech Spec Page for Amendment No. 293 Regarding Extending the Inspection Interval for Reactor Coolant Pump Flywheels (TS 04-02)
ML0419702478 July 2004Tech Spec Page for Amendment No. 283 Regarding Extending the Inspection Interval for Reactor Coolant Pump Flywheels (TS 04-02)
Retrieved from "https://kanterella.com/Special:Ask/-5B-5BTopic::Liquid-20penetrant-5D-5D-20-5B-5BSite::Sequoyah-5D-5D/-3FIssue-20date/-3FTitle/mainlabel%3D/order%3Ddescending/sort%3Dissue-20date/offset%3D0/format%3Dtable/searchlabel%3DSequoyah"