Category:Letter
MONTHYEARML24032A4762024-02-0101 February 2024 Final Report of a Part 21 Evaluation Associated with Starter Contactors for the BFN Unit 1 High Pressure Coolant Injection Suppression Pool Inboard Suction Valve ML24032A0202024-01-31031 January 2024 NPDES Biocide/Corrosion Treatment Plan Annual Report, Cy 2023 ML23319A2452024-01-29029 January 2024 Issuance of Amendment Nos. 366 and 360; 164 and 71 Regarding the Adoption of TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues ML24023A2802024-01-23023 January 2024 Final Report of a Deviation or Failure to Comply Associated with a Relay in the Reactor Core Isolation Cooling Condensate Pump ML24008A2462024-01-18018 January 2024 Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions ML24018A0142024-01-17017 January 2024 Engine Systems, Inc., Report No. 10CFR21-0137, Rev. 1, 56913-EN 56913 ML24016A3042024-01-16016 January 2024 Final Report of a Part 21 Evaluation Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump CNL-23-071, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472024-01-11011 January 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 IR 05000327/20234422024-01-11011 January 2024 95001 Supplemental Inspection Report 05000327/2023442 and 05000328/2023442 and Follow-Up Assessment Letter ML24011A3162024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), August 2023 ML24011A3172024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), September 2023 ML24011A3182024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), October 2023 ML24011A3192024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), November 2023 ML24011A3202024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), December 2023 ML24010A2132024-01-10010 January 2024 CFR 21.21 Final Report Regarding Siemens Medium Voltage Circuit Breakers CNL-24-016, Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-01-10010 January 2024 Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-23-052, Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability2024-01-0909 January 2024 Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability CNL-23-062, Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018)2024-01-0808 January 2024 Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018) ML24018A0952024-01-0404 January 2024 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance Report No. 10CFR21-0137, Rev. 0 ML24004A0332024-01-0303 January 2024 Interim Report of a Deviation or Failure to Comply Crompton Instruments Type 077 Ammeter ML24004A0402024-01-0303 January 2024 Response to NRCs November 8, 2023, Request for Additional Information - Related to Independent Spent Fuel Storage Installation ML23346A1382024-01-0303 January 2024 Regulatory Audit Summary Related to Request to Increase the Number of Tritium Producing Burnable Absorber Rods ML24022A1732024-01-0303 January 2024 Receipt and Availability of the Subsequent License Renewal Application ML23319A1992024-01-0303 January 2024 Issuance of Amendment Nos. 333, 356, and 316 Regarding the Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves ML23355A2062023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation CNL-23-068, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation CNL-23-069, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000390/20234412023-12-21021 December 2023 Plantfinal Significance Determination for a Security-Related Greater than Green Finding, Nov, and Assessment Follow-up, 05000390-2023441 and 05000391-2023441-Public 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)2023-12-18018 December 2023 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) IR 05000390/20234042023-12-14014 December 2023 Security Baseline Inspection Report 05000390/2023404 and 05000391/2023404 ML23348A3942023-12-14014 December 2023 Interim Part 21 Report of a Potential Deviation or Failure to Comply Associated with Starter Contactors for the High Pressure Coolant Injection Suppression Pool Inboard Suction Valve CNL-23-001, Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01)2023-12-13013 December 2023 Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01) ML23346A1222023-12-12012 December 2023 Annual Non-Radiological Environmental Operating Report - 2023 IR 05000259/20230102023-12-11011 December 2023 Commercial Grade Dedication Inspection Report 05000259/2023010 and 05000260/2023010 and 05000296/2023010 ML23293A0572023-12-0606 December 2023 Issuance of Amendment Nos. 163 and 70 Regarding Adoption of TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML23335A0722023-12-0101 December 2023 Interim Report of a Deviation or Failure to Comply Associated with a Relay in the Unit 2 Reactor Core Isolation Cooling Condensate Pump ML23334A2492023-11-30030 November 2023 Site Emergency Plan Implementing Procedure Revision IR 05000390/20230102023-11-30030 November 2023 RE-Issue Watts Bar Nuclear Plant - Biennial Problem Identification and Resolution Inspection Report 050000390/2023010 and 05000391/2023010 and Apparent Violation CNL-23-070, Submittal of Fifth 10-Year Interval Inservice Testing Program Plan2023-11-29029 November 2023 Submittal of Fifth 10-Year Interval Inservice Testing Program Plan IR 05000327/20234202023-11-28028 November 2023 Security Baseline Inspection Report 05000327/2023420 and 05000328/2023420 CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML23331A2532023-11-27027 November 2023 Summary Report for 10 CFR 50.9 Evaluations, Technical Specifications Bases Changes, Technical Requirement Manual Changes, and NRC Commitment Revisions ML23325A1102023-11-21021 November 2023 Anchor Darling Double Disc Gate Valve Commitment Revision ML23320A2542023-11-16016 November 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump IR 05000259/20230032023-11-13013 November 2023 Integrated Inspection Report 05000259/2023003, 05000260/2023003 and 05000296/2023003 IR 05000390/20230032023-11-13013 November 2023 Integrated Inspection Report 05000390/2023003 and 05000391/2023003 and Apparent Violation 2024-02-01
[Table view] Category:Topical Report
MONTHYEARCNL-23-044, Transmittal of Revision 3 to WCAP-18774-P and WCAP-18774-NP, Addendum to the Rotterdam Dockyard Company Final Stress Report for 173 P.W.R. Vessels TVA III & IV (Report No. 30749-B-030, Rev. 3) - Evaluation of One Closure Stud Out2023-06-0101 June 2023 Transmittal of Revision 3 to WCAP-18774-P and WCAP-18774-NP, Addendum to the Rotterdam Dockyard Company Final Stress Report for 173 P.W.R. Vessels TVA III & IV (Report No. 30749-B-030, Rev. 3) - Evaluation of One Closure Stud Out CNL-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 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 CNL-19-067, Application to Revise Watts Bar Nuclear Plant (WBN) Unit 2 - Technical Specifications for Steam Generator Tube Repair Sleeve (WBN-TS-391-19-13)2019-09-30030 September 2019 Application to Revise Watts Bar Nuclear Plant (WBN) Unit 2 - Technical Specifications for Steam Generator Tube Repair Sleeve (WBN-TS-391-19-13) 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 RA-19-0115, Transmittal of the Duke Energy Corporation Topic Report (Duke QAPD-001-A), Amendment 442019-02-18018 February 2019 Transmittal of the Duke Energy Corporation Topic Report (Duke QAPD-001-A), Amendment 44 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 ML17018A1502017-01-17017 January 2017 Units 1 and 2, Watts Bar, Units 1 and 2 - 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 CNL-16-056, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 9, Responses to Requests for Additional Information2016-04-0404 April 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 9, Responses to Requests for Additional Information CNL-15-247, Brown Ferry Unit 1, Submittal of Response to NRC Request for Additional Information Re Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limits (TS-506). Enclosure 2 ANP-3458NP Enclose2015-12-28028 December 2015 Brown Ferry Unit 1, Submittal of Response to NRC Request for Additional Information Re Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limits (TS-506). Enclosure 2 ANP-3458NP Enclosed CNL-15-060, Technical Specifications Change No. WBN2-TS-15-16 - Revise Technical Specifications for Use of Steam Generator Alternate Repair Criterion F2015-12-15015 December 2015 Technical Specifications Change No. WBN2-TS-15-16 - Revise Technical Specifications for Use of Steam Generator Alternate Repair Criterion F CNL-15-250, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 2, MICROBURN-B2 Information, Including Enclosures 2, 4, 6, and 72015-12-15015 December 2015 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 2, MICROBURN-B2 Information, Including Enclosures 2, 4, 6, and 7 CNL-15-249, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 1, Spent Fuel Pool Criticality Safety Analysis Information2015-12-15015 December 2015 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 1, Spent Fuel Pool Criticality Safety Analysis Information NL-15-169, Browns Ferry, Units 1, 2 and 3, ANP-3327NP, Revision 1, Evaluation of Areva Fuel Thermal-Hydraulic Performance for Browns Ferry at EPU2015-03-31031 March 2015 Browns Ferry, Units 1, 2 and 3, ANP-3327NP, Revision 1, Evaluation of Areva Fuel Thermal-Hydraulic Performance for Browns Ferry at EPU ML15282A2212015-03-31031 March 2015 ANP-3327NP, Revision 1, Evaluation of Areva Fuel Thermal-Hydraulic Performance for Browns Ferry at EPU CNL-14-226, Organization Topical Report, TVA-NPOD89-A2015-02-13013 February 2015 Organization Topical Report, TVA-NPOD89-A ML13358A0682013-12-18018 December 2013 NEDO-33445, Rev.0, Browns Ferry Unit 1, Pressure and Temperature Limits Report (PTLR) Up to 25 and 38 Effective Full-Power Years. ML13253A0752013-09-0505 September 2013 Tennessee Valley Authority - Organization Topical Report, TVA-NPOD89-A ML12342A1342012-11-12012 November 2012 Fukushima Near-Term Task Force Recommendation 2.3: Seismic Response Report ML12342A1332012-11-12012 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 ML0821800942008-07-31031 July 2008 WCAP-16932-NP, Rev. 1, Control Rod Insertion Following a Cold Leg LOCA for Watts Bar Unit 1. ML0815502792008-02-29029 February 2008 WCAP-16845-NP, Revision 0, Browns Ferry Nuclear Plant Unit 2, Evaluation of Dissimilar Metal Weld Indication at Weld RCRD-2-52. ML0809905342008-02-29029 February 2008 ANP-2655(NP), Rev. 1, Sequoyah Nuclear Plant Unit 2 - Realistic Large Break Loss of Coolant Accident Analysis. ML0732002442007-11-30030 November 2007 WCAP-16760-NP, Rev. 0, Analysis of Capsule Z from the Tennessee Valley Authority, Watts Bar Unit 1 Reactor Vessel Radiation Surveillance Program. 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 ML0607202812006-02-28028 February 2006 NEDO-33173, Applicability of GE Methods to Expanded Operating Domains. ML0524501472005-08-30030 August 2005 Tennessee Valley Authority Transmittal of Revised Topical Report Incorporating Organizational Change That Have Been Announced Through 07/31/2005 ML0518203912005-06-30030 June 2005 to SG-SGDA-05-24, Condition Monitoring & Operational Assessment: GL-95-05 Alternate Repair Criterion End of Cycle 6 90 Day Report, Watts Bar Unit 1. ML0507400272005-02-28028 February 2005 LTR-CDME-04-148, Rev 1, Application of W* Alternate Repair Criteria to Sequoyah Unit 2. (Non-Proprietary Version) ML0430003582004-10-31031 October 2004 WCAP-16333-NP, Fracture Toughness Testing of Compact Tension Specimens Form Watt Bar Unit 1 Surveillance Capsule. 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) ML0430003562004-04-30030 April 2004 to WCAP-16245-NP, Analysis of Capsule X from Tennessee Valley Authority, Watt Bar Unit 1 Reactor Vessel Radiation Surveillance Program. ML0434402312004-01-31031 January 2004 Nonproprietary Revision 0 to NEDO-33112, Pressure-Temperature Curves for TVA Browns Ferry Unit 1. 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 ML0327503492003-08-31031 August 2003 to GE-NE-0000-0013-3193-01a-R1, Pressure-Temperature Curves for TVA Browns Ferry, Unit 2. ML0327503932003-08-31031 August 2003 to GE-NE-0000-0013-3193-02a-R1, Pressure-Temperature Curves for TVA Browns Ferry, Unit 3. 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 ML0314904662003-05-19019 May 2003 Accepted Version of Topical Report No. 24370-TR-C-001-A, Alternative Rebar Splice -Bar-Lock Mechanical Splices. ML0316308242003-05-19019 May 2003 Accepted Version of Topical Report No. 24370-TR-C-003-A, Steam Generator Compartment Roof Modification. ML0318206702003-04-30030 April 2003 to WCAP-15984-NP, Reactor Vessel Closure Head/Vessel Flange Requirements Evaluation for Sequoyah Units 1 & 2. 2023-06-01
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