Category:Letter
MONTHYEARIR 05000390/20250102024-11-0404 November 2024 Notification of an NRC (FPTI) (NRC Inspection Report 05000390/2025010 0500039/ 2025010) (RFI) CNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000390/20243012024-10-17017 October 2024 Operator Licensing Examination Approval 05000390/2024301 and 05000391/2024301 ML24282B0412024-10-15015 October 2024 Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 ML24260A1682024-10-0404 October 2024 Regulatory Audit Summary Related to Request to Add and Revise Notes Related to Technical Specification Table 3.3.2-1, Function 5 ML24261C0062024-10-0404 October 2024 Correction to Amendment No. 134 to Facility Operating License No. NPF-90 and Amendment No. 38 to Facility Operating License No. NPF-96 ML24284A1072024-09-26026 September 2024 Affidavit for Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2 CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description CNL-24-047, Decommitment of Flood Mode Mitigation Improvement Systems2024-09-24024 September 2024 Decommitment of Flood Mode Mitigation Improvement Systems ML24262A0602024-09-23023 September 2024 Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 05000390/LER-2024-002, Automatic Reactor Trip Due to Main Generator Protection Relay Actuation2024-09-0505 September 2024 Automatic Reactor Trip Due to Main Generator Protection Relay Actuation IR 05000390/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390-2024005 and 05000391-2024005 ML24218A1442024-08-27027 August 2024 Issuance of Amendment Nos. 169 and 75 Regarding Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate IR 05000390/20244022024-08-20020 August 2024 – Security Baseline Inspection Report 05000390-2024402 and 05000391/2024402 - Public CNL-24-061, Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08),2024-08-19019 August 2024 Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08), ML24219A0262024-08-12012 August 2024 Request for Withholding Information from Public Disclosure IR 05000390/20240022024-08-0707 August 2024 Integrated Inspection Report 05000390/2024002 and 05000391/2024002 Rev ML24204A2652024-07-25025 July 2024 Regulatory Audit Summary Related to Request to Revise Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24170A8002024-07-15015 July 2024 Issuance of Amendment Nos. 168 and 74 Regarding Revision to Technical Specification Table 1.1-1 for Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter IR 05000390/20244402024-07-12012 July 2024 95001 Supplemental Inspection Supplemental Report 05000390-2024440 and 05000391-2024440 and Follow-Up Assessment Letter 05000391/LER-2024-003, Inoperability of Both Trains of Unit 2 Low Head Safety Injection2024-07-11011 July 2024 Inoperability of Both Trains of Unit 2 Low Head Safety Injection ML24131A0012024-07-0202 July 2024 Issuance of Amendment Nos. 167 and 73 Regarding Adoption of Technical Specification Task Force Traveler TSTF-427-A, Revision 2 CNL-24-052, Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-06-27027 June 2024 Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-24-018, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS2024-06-25025 June 2024 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS ML24089A1152024-06-21021 June 2024 Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2) ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24100A7642024-05-16016 May 2024 Issuance of Amendment No. 166 Regarding Revision to Technical Specification 3.8.2, AC Sources-Shutdown, to Remove Reference to C-S Diesel Generator (CNL-23-062) IR 05000390/20240012024-05-14014 May 2024 Integrated Inspection Report 05000390/2024001 and 05000391/2024001 CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 05000391/LER-2024-002, Re Automatic Reactor Trip Due to Steam Generator 3 Level LO-LO2024-05-0606 May 2024 Re Automatic Reactor Trip Due to Steam Generator 3 Level LO-LO IR 05000391/20240072024-04-30030 April 2024 Assessment Follow-up Letter for Watts Bar Nuclear Plant, Unit 2 – Report 05000391/2024007 ML24120A1182024-04-29029 April 2024 – Notification of NRC Supplemental Inspection (95001) and Request for Information CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42 ML24087A1912024-04-18018 April 2024 Exemption from Select Requirements of 10 CFR Part 73, Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting CNL-24-024, Hydrologic Engineering Center River Analysis System Project Milestone Status Update2024-04-17017 April 2024 Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-24-010, License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19)2024-04-17017 April 2024 License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19) CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24072A0052024-04-15015 April 2024 Issuance of Amendment Nos. 165 and 72 Regarding Increase in the Maximum Number of Tritium Producing Burnable Absorber Rods and Supporting Changes, and Revision to the Updated Final Safety Analysis Report CNL-24-004, Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13)2024-04-0404 April 2024 Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13) IR 05000390/20244012024-04-0202 April 2024 – Security Baseline Inspection Report 05000390/2024401 and 05000391/2024401 - (Public) CNL-24-020, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements2024-04-0101 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements 05000391/LER-2024-001, Automatic Reactor Trip Due to Main Generator Protection Relay Actuation2024-03-27027 March 2024 Automatic Reactor Trip Due to Main Generator Protection Relay Actuation CNL-24-007, Annual Insurance Status Report2024-03-27027 March 2024 Annual Insurance Status Report CNL-24-008, Guarantee of Payment of Deferred Premiums - 2023 Annual Report2024-03-27027 March 2024 Guarantee of Payment of Deferred Premiums - 2023 Annual Report CNL-24-025, Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule2024-03-25025 March 2024 Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule ML24081A0262024-03-21021 March 2024 Emergency Plan Implementing Procedure Revisions ML24079A0312024-03-19019 March 2024 Wb 2024-301, Corporate Notification Letter (210-day Ltr) 2024-09-05
[Table view] Category:Updated Final Safety Analysis Report (UFSAR)
MONTHYEARWBL-23-053, Updated Final Safety Analysis Report (UFSAR) Amendment 5, Redacted Version2023-11-0808 November 2023 Updated Final Safety Analysis Report (UFSAR) Amendment 5, Redacted Version ML23312A1462023-11-0808 November 2023 Updated Final Safety Analysis Report (UFSAR) Amendment 5 - Table of Contents ML20323A3182020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Table of Contents WBL-20-047, Amendment 3 to Updated Final Safety Analysis Report, Chapter 8, Electric Power (Redacted)2020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 8, Electric Power (Redacted) ML20323A3082020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 14, Initial Test Program ML20323A3142020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment, and Systems, Table of Contents to Sec 3.7 ML20323A3192020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 17, Quality Assurance ML20323A3172020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Division of Responsibility (Dor), Abbreviations ML20323A3112020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 4, Reactor ML20323A3222020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 13, Conduct of Operations ML21123A2262020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment, and Systems, Sections 3.8 to 3.12 (Redacted) ML20323A3152020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 11, Radioactive Waste Management ML20323A3032020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary System ML20323A3052020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 10, Main Steam and Power Conversion Systems ML20323A3002020-10-29029 October 2020 Submittal of Amendment 3 to Updated Final Safety Analysis Report ML20323A3202020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System ML21123A2252020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 2, Site Characteristics, Table of Contents to Sec 2.4 (Redacted) ML20323A3012020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls ML20323A3092020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 12, Radiation Protection ML20323A3162020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 15, Accident Analyses ML20323A3102020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 2, Sec 2.5, Geology, Seismology, and Geotechnical Engineering Summary of Foundation Conditions ML20323A3062020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant ML20323A3122020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 16, Technical Specifications ML20142A3892020-05-21021 May 2020 Wbnp PSAR, Chapter 12, Conduct of Operations L-19-022, Amendment 2 to Updated Final Safety Analysis Report, Chapter 8, Electric Power - Redacted2019-03-18018 March 2019 Amendment 2 to Updated Final Safety Analysis Report, Chapter 8, Electric Power - Redacted ML19060A1472019-02-19019 February 2019 Amendment 1 to USAR Chapter 2 Auxiliary System NRC Additional Redactions 2 of 5 ML19060A1762019-02-18018 February 2019 Amendment 1 to USAR Chapter 2 Auxiliary System NRC Additional Redactions 3 of 5 ML19060A1822019-02-18018 February 2019 Amendment 1 to USAR Chapter 2 Auxiliary System NRC Additional Redactions 5 of 5 ML19039A1042019-02-0808 February 2019 Amendment 1 to USAR Chapter 2 Auxiliary System NRC Additional Redactions 1 of 5 ML19060A1492019-02-0808 February 2019 Amendment 1 to USAR Chapter 2 Auxiliary System NRC Additional Redactions 4 of 5 ML17334A1602017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 13, Conduct of Operations ML17334A1732017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 8, Electric Power (Redacted) ML17334A1622017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 14, Initial Test Program ML17334A1692017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 4, Reactor ML17334A1562017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 1, Introduction and General Description of Plant (Redacted) ML17334A1722017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 7, Instrumentation and Controls ML17334A1582017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 11, Radioactive Waste Management ML17334A1592017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 12, Radiation Protection (Redacted) ML17334A1652017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 17, Quality Assurance ML17334A1702017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 5, Reactor Coolant System ML17334A1632017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 15, Accident Analyses ML17334A1572017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 10, Main Steam and Power Conversion Systems ML17334A1642017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 16, Technical Specifications ML15279A3042015-09-11011 September 2015 Amendment 114 to Final Safety Analysis Report, Section 2.0 - Site Characteristics, Figure 2.5-554. Sheet 1 of 2 ML15279A3072015-09-11011 September 2015 Amendment 114 to Final Safety Analysis Report, Section 2.0 - Site Characteristics, Figure 2.5-556 ML15279A3182015-09-11011 September 2015 Amendment 114 to Final Safety Analysis Report, Section 2.0 - Site Characteristics, Figure 2.5-579 ML15279A3192015-09-11011 September 2015 Amendment 114 to Final Safety Analysis Report, Section 2.0 - Site Characteristics, Figure 2.5-583 ML15279A3082015-09-11011 September 2015 Amendment 114 to Final Safety Analysis Report, Section 2.0 - Site Characteristics, Figure 2.5-571. Sheet 1 of 4 ML15279A3052015-09-11011 September 2015 Amendment 114 to Final Safety Analysis Report, Section 2.0 - Site Characteristics, Figure 2.5-554. Sheet 2 of 2 ML15279A3252015-09-11011 September 2015 Amendment 114 to Final Safety Analysis Report, Section 2.0 - Site Characteristics, Figure 2.5-597 2023-11-08
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