| 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 Acc | 31 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 | Safe Shutdown
Boric Acid
Mission time
Safe Shutdown Earthquake
Probabilistic Risk Assessment
Fukushima Dai-Ichi
Seismically rugged
Design basis earthquake
Earthquake
Seismic Walkdown Report |
| CNL-14-089, (Bfn), Units 1, 2, and 3 - Application to Modify Technical Specification 2.1.1, Reactor Core Safety Limits (BFN-TS-492) | 11 December 2014 | (Bfn), Units 1, 2, and 3 - Application to Modify Technical Specification 2.1.1, Reactor Core Safety Limits (BFN-TS-492) | Reactor Vessel Water Level
Stroke time
Anticipated operational occurrence
Minimum Critical Power Ratio
Fuel cladding
Power change |
| CNL-14-208, Response to NRC Request for Additional Information Regarding the License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants for the Browns Ferry Nuclear Pl | 17 December 2014 | Response to NRC Request for Additional Information Regarding the License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants for the Browns Ferry Nuclear Plan | Hot Short
Safe Shutdown
High Radiation Area
Mission time
Fire Barrier
Internal Flooding
Hydrostatic
Probabilistic Risk Assessment
Coatings
Multiple Spurious Operation
Incorporated by reference
FLEX
Thermoset
Large early release frequency
Severe Accident Management Guideline
Fire Protection Program
Fire Watch
Very Early Warning Fire Detection |
| CNL-15-039, Severe Accident Management Alternatives for Reactor Coolant Pump Seals | 10 April 2015 | Severe Accident Management Alternatives for Reactor Coolant Pump Seals | Internal Flooding
Probabilistic Risk Assessment
FLEX
Large early release frequency
Earthquake |
| CNL-15-056, Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limits (TS-506) | 25 September 2015 | Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limits (TS-506) | Reactor Vessel Water Level
Safety Limit Minimum Critical Power Ratio
Anticipated operational occurrence
MELLLA |
| CNL-15-085, Response to NRC Request for Additional Information Regarding Proposed Technical Specification Change to Modify Technical Proposed Technical Specification Change to Modify Technical | 3 June 2015 | Response to NRC Request for Additional Information Regarding Proposed Technical Specification Change to Modify Technical Proposed Technical Specification Change to Modify Technical | Stroke time
Fuel cladding |
| CNL-15-097, Flood Hazard Reevaluation Report for Watts Bar Plant, Response to NRC Request for Information Per 10CFR50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident | 16 June 2015 | Flood Hazard Reevaluation Report for Watts Bar Plant, Response to NRC Request for Information Per 10CFR50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident | Ultimate heat sink
Safe Shutdown Earthquake
Hydrostatic
Operating Basis Earthquake
Fukushima Dai-Ichi
Earthquake |
| CNL-15-143, the Tennessee Valley Authority (TVA) Nuclear Power Group Commercial Grade Dedication Recovery Project - Closure Report | 31 July 2015 | the Tennessee Valley Authority (TVA) Nuclear Power Group Commercial Grade Dedication Recovery Project - Closure Report | Commercial Grade Dedication |
| CNL-15-204, Response to NRC Question Regarding the Revised Containment Analysis, Including Enclosure 3, WCAP-17834-NP, Revision 2, Wcobra/Trac Long Term LOCA M&E and Containment Integrity Analysis and Enclosure 4, Affidavit | 21 September 2015 | Response to NRC Question Regarding the Revised Containment Analysis, Including Enclosure 3, WCAP-17834-NP, Revision 2, Wcobra/Trac Long Term LOCA M&E and Containment Integrity Analysis and Enclosure 4, Affidavit | GOTHIC |
| CNL-16-169, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 35, Consolidated Power Uprate Safety Analysis Report Revision | 28 October 2016 | Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 35, Consolidated Power Uprate Safety Analysis Report Revision | |
| CNL-17-050, Submission of Technical Reports to Support a Public Meeting Regarding the Transition to the Reactor Oversight Process for the Mitigating Systems Performance Index | 30 May 2017 | Submission of Technical Reports to Support a Public Meeting Regarding the Transition to the Reactor Oversight Process for the Mitigating Systems Performance Index | |
| CNL-17-134, Transmittal of WCAP-18191-NP, Watts Bar Unit 2 Heatup and Cooldown Limit Curves for Normal Operation and Supplemental Reactor Vessel Integrity Evaluations | 13 October 2017 | Transmittal of WCAP-18191-NP, Watts Bar Unit 2 Heatup and Cooldown Limit Curves for Normal Operation and Supplemental Reactor Vessel Integrity Evaluations | Hydrostatic
Aging Management |
| CNL-18-112, Extended Power Uprate - Flow Induced Vibration Summary Report | 13 September 2018 | Extended Power Uprate - Flow Induced Vibration Summary Report | Flow Induced Vibration |
| CNL-18-134, Extended Power Uprate - Replacement Steam Dryer Revised Analysis and Limit Curves Report | 29 November 2018 | Extended Power Uprate - Replacement Steam Dryer Revised Analysis and Limit Curves Report | |
| CNL-19-004, Tennessee Valley Authority, Browns Ferry Nuclear Plant, Unit 2, Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions | 7 June 2019 | Tennessee Valley Authority, Browns Ferry Nuclear Plant, Unit 2, Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions | FLEX
Design basis earthquake
Spent Fuel Pool Instrumentation
Severe Accident Management Guideline
Hardened vent |
| CNL-19-032, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 8, Additional Operator Training Information | 13 March 2019 | Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 8, Additional Operator Training Information | |
| CNL-19-041, Extended Power Uprate - Unit 1 Flow Induced Vibration Summary Report | 16 April 2019 | Extended Power Uprate - Unit 1 Flow Induced Vibration Summary Report | Flow Induced Vibration
Power Uprate |
| CNL-19-074, Extended Power Uprate - Flow Induced Vibration Summary Report | 4 September 2019 | Extended Power Uprate - Flow Induced Vibration Summary Report | Flow Induced Vibration |
| CNL-19-082, License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06) | 10 October 2019 | License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06) | Safe Shutdown
Boric Acid
Shutdown Margin
Ultimate heat sink
Anticipated operational occurrence
Safe Shutdown Earthquake
Internal Flooding
Hydrostatic
Coatings
Operating Basis Earthquake
Cyber Security
Emergency Lighting
FLEX
Pressure and Temperature Limits Report
Annual Radioactive Effluent Release Report
Process Control Program
Time Critical Operator Action
Earthquake
Maintenance Rule Program
Fuel cladding
Fire Protection Program
Flow Induced Vibration |
| CNL-20-074, Submittal of Additional Supplement to License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06) | 28 August 2020 | Submittal of Additional Supplement to License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06) | |
| CNL-20-102, 10 CFR 71.95 Report for 3-60B Casks User | 16 December 2020 | 10 CFR 71.95 Report for 3-60B Casks User | |
| CNL-21-011, Expedited Application for Approval to Use a Growth Rate Temperature Adjustment When Implementing the Generic Letter 95-05 Analysis for the (WBN TS-391-21-002) | 25 February 2021 | Expedited Application for Approval to Use a Growth Rate Temperature Adjustment When Implementing the Generic Letter 95-05 Analysis for the (WBN TS-391-21-002) | Anticipated operational occurrence |
| CNL-21-018, Application to Adopt TSTF-205-A, Revision of Channel Calibration, Channel Functional Test, and Related Definitions, and TSTF-563-A, Revise Instrument Testing Definitions to Incorporate the Surveillance . | 9 December 2021 | Application to Adopt TSTF-205-A, Revision of Channel Calibration, Channel Functional Test, and Related Definitions, and TSTF-563-A, Revise Instrument Testing Definitions to Incorporate the Surveillance . | Safe Shutdown
Shutdown Margin
Surveillance Frequency Control Program
Pressure Boundary Leakage |
| CNL-21-040, Supplement to Expedited Application for Approval to Use a Growth Rate Temperature Adjustment When Implementing the Generic Letter 95-05 Analysis for the (WBN TS-391-21-002) | 23 March 2021 | Supplement to Expedited Application for Approval to Use a Growth Rate Temperature Adjustment When Implementing the Generic Letter 95-05 Analysis for the (WBN TS-391-21-002) | Nondestructive Examination
Foreign Material Exclusion
Coast down |
| CNL-21-055, Revision to Refueling Outage 3 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report | 20 July 2021 | Revision to Refueling Outage 3 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report | Safe Shutdown Earthquake
Nondestructive Examination
Downpower |
| CNL-21-072, TVA Nuclear Calculation Coversheet/ Ecm Metadata Update | 13 August 2021 | TVA Nuclear Calculation Coversheet/ Ecm Metadata Update | |
| CNL-22-057, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel Use | 27 May 2022 | to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel Use | |
| CNL-22-066, Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information | 18 July 2022 | Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information | Stroke time
Anticipated operational occurrence
Abnormal operational transient |
| CNL-22-100, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535) | 9 December 2022 | to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535) | Safety Limit Minimum Critical Power Ratio
Anticipated operational occurrence
Abnormal operational transient
Feedwater Controller Failure
MELLLA |
| CNL-23-002, Application to Revise Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications to Change the Number of Tritium Producing Burnable Absorber Rods (WBN-TS-21-02) and Proposed Revision to Reactor Vessel Surveillance Capsule Removal Sche | 20 March 2023 | Application to Revise Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications to Change the Number of Tritium Producing Burnable Absorber Rods (WBN-TS-21-02) and Proposed Revision to Reactor Vessel Surveillance Capsule Removal Schedu | |
| CNL-24-016, Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) | 10 January 2024 | Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) | |
| L-19-026, Revised Pressure and Temperature Limits Report (PTLR) | 4 April 2019 | Revised Pressure and Temperature Limits Report (PTLR) | Hydrostatic
Pressure and Temperature Limits Report |
| L-19-034, Wafts Bar Nuclear Plant, Unit 1 - Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report | 18 June 2019 | Wafts Bar Nuclear Plant, Unit 1 - Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report | Post Accident Monitoring |
| ML020310185 | 6 February 2002 | Relief Request, Evaluation of ISI Program | VT-2
Incorporated by reference
Liquid penetrant
Dissimilar Metal Weld |
| ML020530458 | 19 February 2002 | Submittal of New (Revision 3) non-proprietary Version of Holtec, International Report HI-2012620. Revisions Identify Appendices a & C to Be Withheld in Accordance with Paragraph (B) (4) of 10 CFR 2.790 | Fuel cladding |
| ML020580082 | 19 February 2002 | Response to Request for Additional Information Re Tritium Production - Holtec Analysis. Submits New non-proprietary Version (Revision 3) of Holtec International Report HI-2012620 | Fuel cladding |
| ML020850483 | 25 March 2002 | Generator (SG) 120-Day Report for Unit 1 Cycle 11 (U1C11) Refueling Outage SG Inspections | |
| ML021070404 | 3 April 2002 | Emergency Core Cooling System (ECCS) Evaluation Model Changes, Annual Notification & Reporting for 2001 | |
| ML021070745 | 11 April 2002 | Discharge Monitoring Report for Sequoyah Nuclear Plant from Tennessee Valley Authority | |
| ML021720525 | 11 June 2002 | Technical Specification Change No. 00-06, Supplemental Response Regarding Radiological Impact | Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Tritium |
| ML022660232 | 17 September 2002 | Enclosure 1, TVA Sequoyah Plant Unit 2, Cycle 11 Steam Generator Tube Inspection as of 04/28/2002 | |
| ML022660234 | 17 September 2002 | Enclosure 2, TVA Sequoyah Plant Unit No. 2 Cycle 11 Steam Generator Tube Inspection Update as of 4/29/2002 | |
| ML023040338 | 19 September 2002 | Part 2 of 4 - Course Outline for R-304-B and BWR Systems Lesson Plans | Reactor Vessel Water Level
Loop seal
Hydrostatic
Earthquake
Fuel cladding
Power change
Coast down |
| ML023040361 | 19 September 2002 | Part 4 of 4 - Course Outline for R-304-B and BWR Systems Lesson Plans | |
| ML030100442 | 10 January 2003 | Steam Generator Compartment Roof Modification Topical Report Technical Assessment | |
| ML030160157 | 14 January 2003 | Technical Specification Change 02-08, Partial Scope Implementation of the Alternate Source Term and Revision of Requirements for Closure of the Containment Building Equipment Door During Movement of Irradiated Fuel. | Recently irradiated fuel |
| ML030420498 | 3 February 2003 | Response to NRC Request for Additional Information Regarding Licensee Identified Material Wastage | Boric Acid |
| ML030590318 | 25 February 2003 | Attachments to 02/12/2003 Meeting Summary - Design Summary of the Steam Generator Enclosure Roof Support Frames | Unanalyzed Condition
Safe Shutdown Earthquake
Operating Basis Earthquake
Finite Element Analysis
Design basis earthquake
Earthquake |
| ML031330767 | 5 May 2003 | Cycle 11 (U2C11) 12-Month Steam Generator (SG) Inspection Report and Metallurgical Examination Report on Tube Removed from Steam Generator | |
| ML032521478 | 3 September 2003 | Updated Pressure Temperature Limits Report and Topical Reports for SQN Technical Specification Change No. 00-14 | Hydrostatic |