ML11116A211
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| ML11116A211 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 04/21/2011 |
| From: | Krich R M, Ceraldi M D Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML11116A211 (58) | |
Similar Documents at Sequoyah | |
|---|---|
Category:Report
MONTHYEARML23284A4252023-10-11011 October 2023
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ML14002A1132014-02-19019 February 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14041A1922014-02-16016 February 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Sequoyah Nuclear Plant, Units 1 and 2, TAC Nos.: MF0864 and MF0865 ML14016A0392014-02-0606 February 2014 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 CNL-14-013, Highlights of Improvements to the Sequoyah Nuclear Plant IPEEE Seismic Analysis Results and Supplemental Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f)Regarding...2014-01-31031 January 2014 Highlights of Improvements to the Sequoyah Nuclear Plant IPEEE Seismic Analysis Results and Supplemental Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f)Regarding... 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[Table view]Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information CNL-21-072, TVA Nuclear Calculation Coversheet/ Ecm Metadata Update2021-08-13013 August 2021 TVA Nuclear Calculation Coversheet/ Ecm Metadata Update ML21140A0282021-05-14014 May 2021 Gravel Lot Restoration Project, Construction General Permit, Notice of Intent CNL-20-102, 10 CFR 71.95 Report for 3-60B Casks User2020-12-16016 December 2020 10 CFR 71.95 Report for 3-60B Casks User ML20350B7202020-12-15015 December 2020 Discharge Monitoring Report Quality Assurance Study 40 Final Report 2020 ML20308A4762020-11-0202 November 2020 10 CFR 50.59 and 10 CFR 72.48 Changes, Tests, and Experiments Summary Report and Commitment Summary Report ML20304A4032020-10-28028 October 2020 Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Requirements Manual ML18352A2292018-12-17017 December 2018 Pressure Temperature Limits Report, Revision 7 ML18340A0302018-11-30030 November 2018 Tennessee Valley Authority - Sequoyah, Study to Confirm Calibration of Numerical Model ML18136A4952018-05-15015 May 2018 Pressure Temperature Limits Report, Revision 6 ML18061A0362018-03-0202 March 2018 IAEA Report of the Operational Safety Review Team (Osart) Mission to the Sequoyah Nuclear Power Plant CNL-15-143, the Tennessee Valley Authority (TVA) Nuclear Power Group Commercial Grade Dedication Recovery Project - Closure Report2015-07-31031 July 2015 the Tennessee Valley Authority (TVA) Nuclear Power Group Commercial Grade Dedication Recovery Project - Closure Report ML14283A5132014-11-17017 November 2014 NRC Staff Review Documentation Provided by TVA for the Sequoyah Nuclear Plant, Units 1 and 2 Concerning Resolution of GL2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurizer-Wate CNL-14-038, Tennessee Valley Authority'S Seismic Hazard & Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Recommendation 2.1 of Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Acc2014-03-31031 March 2014 Tennessee Valley Authority'S Seismic Hazard & Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Recommendation 2.1 of Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accid ML14063A5422014-03-0404 March 2014 TVA Response to Request for Clarification to NRC Request for Additional Information Regarding the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application, LRA B.1.31, B.1.25.1 B, B.1.34-Sa, B.1.34-9a, LRA Annual ... ML14002A1132014-02-19019 February 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14041A1922014-02-16016 February 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Sequoyah Nuclear Plant, Units 1 and 2, TAC Nos.: MF0864 and MF0865 ML13282A2332013-09-26026 September 2013 Fukushima Near-Term Task Force Recommendation 2.3: Seismic Response Report ML13206A0042013-06-24024 June 2013 Methodology for Evaluating the Potential for Multiple Dam Failures Due to Seismic Events ML13142A1982013-05-16016 May 2013 Path Forward for Resolution of Generic Safety Issue (GSI)-191 ML13072A5802013-03-0505 March 2013 Storm Water Pollution Prevention Plan ML13032A2532013-01-10010 January 2013 WCAP-17539-NP, Revision 0, Sequoyah, Units 1 and 2 Time-Limited Aging Analysis on Reactor Vessel Integrity ML1218500102012-06-30030 June 2012 Enclosure 2, Tennessee Valley Authority Sequoyah Nuclear Plant Units 1 and 2 - ANP-3053(NP), Revision 4, Sequoyah Htp Fuel Transition - NRC RAIs and Responses, June 2012 (Non-Proprietary Version) ML12153A3782012-05-31031 May 2012 Enclosure 2, Sequoyah Nuclear Plant, Units 1 & 2 - ANP-3053 (Np), Revision 3, Sequoyah Htp Fuel Transition - NRC RAIs and Responses ML12137A2982012-05-15015 May 2012 ANP-2970Q2(NP), Rev 0, Sequoyah, Units 1 and 2 Htp Fuel Realistic Large Break LOCA Analysis ML12118A1662012-04-26026 April 2012 ANP-2970Q1(NP), Revision 000, Htp Fuel Realistic Large Break LOCA Analysis, April 2012 (Non-Proprietary Version), Enclosure 2 ML12114A0612012-04-0505 April 2012 Technical Report, SQN2-SGR-TRI, Revision 3, Sequoyah Unit 2 Steam Generator Replacement Rigging and Heavy Load Handling. ML12088A1712012-03-31031 March 2012 ANP-3053(NP), Revision 2, Sequoyah Htp Fuel Transition - NRC RAIs and Responses, March 2012 (Non-Proprietary Version), Enclosure 2 ML11266A1582011-09-16016 September 2011 C17 Voltage-Based ARC 90-Day Report ML11266A1592011-09-16016 September 2011 Areva Np, Inc., Sequoyah 2C17 W-Star 90-Day Report ML11210B5322011-07-31031 July 2011 ANP-2986(NP), Revision 3, Sequoyah Htp Fuel Transition. Attachment 2 ML11172A0702011-06-30030 June 2011 ANP-2986(NP), Revision 2, Sequoyah Htp Fuel Transition, Attachment 8 ML11172A0722011-05-31031 May 2011 ANP-2971(NP), Rev 1, Sequoyah Units 1 and 2 Htp Fuel S-RELAP5 Small Break LOCA Analysis, Attachment 9 ML11172A0642011-04-30030 April 2011 ANP-2970(NP), Rev 0, Sequoyah, Units 1 and 2 Htp Fuel Realistic Large Break LOCA Analysis, Attachment 10 ML11116A2112011-04-21021 April 2011 Technical Report No. SQN2-SGR-TR3, Revision 0 Sequoyah Unit 2 Steam Generator Replacement Alternate Rebar Splice - Bar-Lock Mechanical Splices Technical Report, Attachment 2 ML1005507732010-01-31031 January 2010 SG-SGMP-10-2, Condition Monitoring and Operational Assessment: GL-95-05 Alternate Repair Criterion End of Cycle 16 - 90 Day Report, Enclosure 1 ML1108310412009-05-31031 May 2009 Engineering Evaluation of Hesco Barriers Performance at Fargo, Nd 2009, Wenck File 2283-01, Enclosure 2 ML0904007952009-02-0404 February 2009 GSI-189 Action Plan, Feb. 09 Update, Publicly Available Version ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 ML0824806912008-07-31031 July 2008 SG-CDME-08-24, Revision 0, Condition Monitoring and Operational Assessment: GL-95-05 Alternate Repair Criterion End of Cycle 15 90 Day Report, Sequoyah Unit 2. ML0810803382008-02-29029 February 2008 ANP-2695(NP), Rev 0, Enclosure 3, Sequoyah Nuclear Plant Unit 1, Realistic Large Break Loss of Coolant Accident Analysis ML0734000922007-11-30030 November 2007 Rev. 2 to SG-CDME-07-7, Condition Monitoring and Operational Assessment: GL-95-05 Alternate Repair Criterion End of Cycle 14, 90 Day Report for Sequoyah Unit 2. ML0732400482007-09-30030 September 2007 Rev. 0 to SG-CDME-07-21-NP, Examination of a Steam Generator Tube Removed from Sequoyah Unit 2. ML0711602272007-04-24024 April 2007 Staff Technical Evaluation Report, 06-03 ML0523405032005-08-15015 August 2005 Unit 2 Cycle 13 (U2C13) 90-Day Steam Generator (S/G) Report for Voltage-Based Alternate Repair Criteria and W* Alternate Repair Criteria ML11307A4202005-04-30030 April 2005 Enclosure 2 - Wenck Associates, Inc., Engineering Evaluation of Hesco Barriers Performance at Fargo, Nd 2009, May 2009 ML1108310422005-04-30030 April 2005 Texas Transportation Institute, DOS K12 Crash Test and Evaluation of the Hesco C-3315 Flood Barrier, April 2005, Enclosure 3 ML0410506212004-04-12012 April 2004 Diffuser Line Manhole Breach ML0409104172004-03-18018 March 2004 TRC Studies, EPA Information, Bmp Plan, Biodetergent 73551 ML0402106382003-12-0202 December 2003 November 2003 - Discharge Monitoring Report 2023-07-31 |
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