ML12342A133
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| ML12342A133 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 11/12/2012 |
| From: | Tennessee Valley Authority |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML12342A133 (445) | |
Similar Documents at Sequoyah | |
|---|---|
Category:Topical Report
MONTHYEARCNL-23-003, Browns Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2; and Watts Bar Nuclear Plant, Units 1 & 2 - Organizational Topic Report TVA-NPOD89-A2023-01-30030 January 2023
[Table view]Browns Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2; and Watts Bar Nuclear Plant, Units 1 & 2 - Organizational Topic Report TVA-NPOD89-A CNL-21-007, Organization Topical Report, TVA-NPOD89-A, Revision 242021-01-29029 January 2021 Organization Topical Report, TVA-NPOD89-A, Revision 24 ML19158A3952019-07-0303 July 2019 Verification Letter of the Approval Version of Tennessee Valley Authority Topical Report TVA Overall Basin Probable Maximum Precipitation and Local Intense Precipitation Analysis Calculation CDQ0000002016000041, Rev. 1 ML19010A2742019-03-18018 March 2019 Final Safety Evaluation by the Office of Nuclear Reactor Regulation Topical Report- TVA Overall Basin Probable Maximum Precipitation and Local Intense Precipitation, Calculation, CDQ0000002016000041 Tennessee Valley Authority CNL-19-001, Sequoyah Nuclear Plant and Watts Bar Nuclear Plant - Organization Topical Report, TVA-NPOD89-A2019-01-15015 January 2019 Sequoyah Nuclear Plant and Watts Bar Nuclear Plant - Organization Topical Report, TVA-NPOD89-A CNL-18-069, Tennessee Valley Authority - Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revisions 35 and 362018-05-0808 May 2018 Tennessee Valley Authority - Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revisions 35 and 36 CNL-17-012, Organization Topical Report, TVA-NPOD89-A2017-01-17017 January 2017 Organization Topical Report, TVA-NPOD89-A NL-17-012, Browns Ferry, Units 1, 2, and 3, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2 - Organization Topical Report, TVA-NPOD89-A2017-01-17017 January 2017 Browns Ferry, Units 1, 2, and 3, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2 - Organization Topical Report, TVA-NPOD89-A ML17018A1502017-01-17017 January 2017 Units 1 and 2, Watts Bar, Units 1 and 2 - Organization Topical Report, TVA-NPOD89-A CNL-14-226, Organization Topical Report, TVA-NPOD89-A2015-02-13013 February 2015 Organization Topical Report, TVA-NPOD89-A ML13253A0752013-09-0505 September 2013 Tennessee Valley Authority - Organization Topical Report, TVA-NPOD89-A ML12342A1332012-11-12012 November 2012 Fukushima Near-Term Task Force Recommendation 2.3: Seismic Response Report ML12342A1342012-11-12012 November 2012 Fukushima Near-Term Task Force Recommendation 2.3: Seismic Response Report ML11249A0462011-08-31031 August 2011 Organization Topical Report, TVA-NPOD89-A ML0926001852009-09-14014 September 2009 Transmittal of Organization Topical Report, TVA-NPOD89-A ML0824700292008-08-29029 August 2008 TVA Nuclear Quality Assurance (Nqa) Plan (TVA-NQA-PLN89-A) and Organization Topical Report (TVA-NPOD89-A) - Browns Ferry, Sequoyah, and Watts Bar Nuclear Plants - Annual Update ML0809905342008-02-29029 February 2008 ANP-2655(NP), Rev. 1, Sequoyah Nuclear Plant Unit 2 - Realistic Large Break Loss of Coolant Accident Analysis. ML0724901462007-08-31031 August 2007 TVA Nuclear Quality Assurance (Nqa) Plan, TVA-NQA-PLN89-A) and Organization Topical Report (TVA-NPOD89-A) - Browns Ferry, Sequoyah, and Watts Bar Nuclear Plants - Annual Updates ML0524501472005-08-30030 August 2005 Tennessee Valley Authority Transmittal of Revised Topical Report Incorporating Organizational Change That Have Been Announced Through 07/31/2005 ML0507400272005-02-28028 February 2005 LTR-CDME-04-148, Rev 1, Application of W* Alternate Repair Criteria to Sequoyah Unit 2. (Non-Proprietary Version) ML0423902142004-08-20020 August 2004 Westinghouse Owners Group Request to Withdraw WCAP-16168-NP, Risk-Informed Extension of Reactor Vessel In-Service Inspection Interval, (PA-MSC-0120) ML0332302252003-11-12012 November 2003 Submittal of WCAP-16084-NP, Development of Risk-Informed Safety Analysis Approach and Pilot Application. ML0331100912003-10-23023 October 2003 Submittal of Revision 3 to Ice Condenser Utility Group Topical Report No. ICUG-001: Application of the Active Ice Mass Management Concept to the Ice Condenser Ice Mass Technical Specification ML0325214782003-09-0303 September 2003 Updated Pressure Temperature Limits Report and Topical Reports for SQN Technical Specification Change No. 00-14 ML0324001722003-08-25025 August 2003 TVA Nuclear Organization Topical Report - Bellefonte, Browns Ferry, Sequoyah, and Watts Bar Nuclear Plants ML0319206472003-06-19019 June 2003 to Ice Condenser Utility Group Topical Report No. ICUG-001: Application of the Active Ice Mass Management Concept to the Ice Condenser Ice Mass Technical Specification ML0316308242003-05-19019 May 2003 Accepted Version of Topical Report No. 24370-TR-C-003-A, Steam Generator Compartment Roof Modification. ML0314904662003-05-19019 May 2003 Accepted Version of Topical Report No. 24370-TR-C-001-A, Alternative Rebar Splice -Bar-Lock Mechanical Splices. ML0318206702003-04-30030 April 2003 to WCAP-15984-NP, Reactor Vessel Closure Head/Vessel Flange Requirements Evaluation for Sequoyah Units 1 & 2. ML0305102342003-02-14014 February 2003 Steam Generator Replacement Project - Topical Report No. 24370-TR-C-003, Steam Generator Compartment Roof Modification, Revision 1. ML0301602402003-01-15015 January 2003 Steam Generator Replacement Project - Topical Report No. 24370-TR-C-002, Rigging and Heavy Load Handling Topical Report, Response to NRC Request for Additional Information ML0236403192002-12-31031 December 2002 Topical Report WCAP-15984-NP, Reactor Vessel Closure Head/Vessel Flange Requirements Evaluation for Sequoyah Units 1 & 2. ML0316109082002-12-24024 December 2002 Rev 3 to 24370-TR-C-002-A, Sequoyah Unit 1 Steam Generator Replacement Rigging and Heavy Load Handling Topical Report, Attachment 1 Through Figure 3 ML0316108992002-12-24024 December 2002 Rev 3 to 24370-TR-C-002-A, Sequoyah Unit 1 Steam Generator Replacement Rigging and Heavy Load Handling Topical Report, Table of Contents Through Figure 1 ML0236403132002-12-19019 December 2002 Topical Report (WCAP-15984) for Technical Specification Change No. 00-14, Pressure Temperature Limits Report (PTLR) and Request for Exemption from the Requirements of 10 CFR 50, Appendix G, Enclosures 1 & 2 ML0224200402002-08-26026 August 2002 TVA Nuclear (Tvan) Organization Topical Report - Bellefonte, Browns Ferry, Sequoyah, & Watts Bar Nuclear Plants ML0210605812002-04-15015 April 2002 Steam Generator Replacement Project - Topical Report No. 24370-TR-C-002, Rigging & Heavy Load Handling. ML0209107922002-03-28028 March 2002 Steam Generator Replacement Project - Topical Report No. 24370-TR-C-003, Steam Generator Compartment Roof Modification. ML0207806122002-03-18018 March 2002 Submittal of Nonproprietary Sequoyah Nuclear Plant Steam Generator Replacement Project Topical Report No. 24370-TR-C-001, Alternate Rebar Splice - Bar Lock Splices. 2023-01-30 |
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