Category:Safety Evaluation
MONTHYEARML24218A1442024-08-27027 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
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
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)
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
ML24040A2062024-03-26026 March 2024
Issuance of Amendment Nos. 367 and 361 Regarding Changes to the Hydrologic Analyses (EPID L-2020-LLA-0004) - Public
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
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
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
ML23205A2132023-09-0808 September 2023
Issuance of Amendment Nos. 332, 355, and 315 Regarding the Revision of Technical Specifications to Adopt TSTF-566-A and TSTF-580-A, Rev. 1
ML23233A0042023-08-28028 August 2023
– Proposed Alternative to the Requirements of the ASME Boiler and Pressure Vessel Code for Upper Head Injection Dissimilar Metal Butt Welds
ML23219A1542023-08-17017 August 2023
Request to Use Later Edition of ASME Code for Operation and Maintenance and Alternative Requests BFN-IST-01 Through 05 for the Fifth 10-Year Interval Inservice Testing Program
ML23171A8862023-07-24024 July 2023
Issuance of Amend. Nos. 331, 354, and 314; 365 and 359 Regarding Adoption of TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position
ML23116A2472023-05-23023 May 2023
Issuance of Amendment Nos. 330, 353, and 313 Regarding Adoption of TSTF-478, Revision 2 for Combustible Gas Control
ML23101A1102023-05-16016 May 2023
Issuance of Amendment Nos. 329, 352, and 312 Regarding Removal of Site Acreage Description from Technical Specifications
ML23125A2202023-05-0505 May 2023
Issuance of Amendment No. 161 Regarding a Change to Footnotes for Technical Specification Table 1.1-1 Modes (Emergency Circumstances)
ML23073A2902023-05-0202 May 2023
Issuance of Amendment Nos. 328, 351, and 311 Adoption of TSTF-505, Revision 2, for Risk-Informed Completion Times and TSTF-439, Revision 2, to Eliminate Second Completion Times
ML23072A0652023-04-0505 April 2023
Units 1 and 2 – Issuance of Amendment Nos. 364 and 358; 160 and 68 Regarding a Revision to Technical Specification 3.4.12
ML23054A2902023-03-13013 March 2023
Request for Relief from the Requirements of the ASME Boiler and Pressure Vessel Code Regarding Weld Examination Coverage
ML23048A3042023-03-0808 March 2023
Tennessee Valley Authority - Request for Relief from Requirements of ASME Boiler and Pressure Vessel Code Regarding Weld Examination Coverage (EPID L-2022-LLR-0045,-0046,-0047)
ML22334A0732023-02-0606 February 2023
Issuance of Amendment Nos. 363 and 357 Regarding Modification of the Approved Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
ML22348A0052023-01-25025 January 2023
Issuance of Amendment Nos. 326, 349, and 309; 363 and 35; 159 and 67 Regarding Adoption of TSTF-554, Revise Reactor Coolant Leakage Requirements
ML22349A6472023-01-20020 January 2023
Issuance of Amendment Nos. 325, 348, and 308; 362 and 356; and 158 and 66 Regarding Adoption of TSTF-529, Rev. 4, Clarify Use and Application Rules
ML22348A0662023-01-13013 January 2023
Issuance of Amendment Nos. 325, 348, & 308 Regarding Application of Advanced Framatome Methodologies, & Adoption of TSTF Traveler TSTF-564-A, Rev. 2, in Support of Atrium 11 Fuel Use (EPID L-2021-LLA-0132) - Nonproprietary
ML22271A9142022-12-0707 December 2022
Issuance of Amendment Nos. 324, 347, and 307; 360 and 354; 157 and 65 Regarding a Revision to the Emergency Action Level Scheme
ML22304A1862022-12-0101 December 2022
Revised Authorization of Alternative Request RV-02 for Pressure Isolation Valve Seat Leakage
ML22273A1032022-11-22022 November 2022
Issuance of Amendment Nos. 323, 346, and 306 Regarding Chilled Water Cross-Tie Modification
ML22220A2602022-11-21021 November 2022
Issuance of Amendment Nos. 322, 345, and 305 Regarding Adoption of TSTF Traveler TSTF-205-A, Rev. 3, and TSTF-563-A
ML22298A2852022-11-14014 November 2022
Request for Alternative to American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Paragraph IWB-2420(B) and Use of Code Case N-526
ML22293A4082022-11-14014 November 2022
Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule
ML22284A0072022-11-0707 November 2022
Authorization of Alternative Request RP-12 for Testing of Centrifugal Charging Pump 1B-B
ML22257A0512022-11-0404 November 2022
Issuance of Amendment Nos. 156 and 64 Regarding Adoption of TSTF-205-A, Revision 3, and TSTF-563-A
ML22276A1612022-10-24024 October 2022
Issuance of Amendment Nos. 359, 353, 155, & 63 Regarding Adoption of TSTF Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections
ML22272A5682022-10-12012 October 2022
Authorization of Alternatives to Certain Inservice Testing Requirements in the American Society of Mechanical Engineers Operating and Maintenance Code
ML22263A3752022-09-29029 September 2022
Authorization of Alternative Request RV-02 for Pressure Isolation Valve Seat Leakage
ML22259A2042022-09-29029 September 2022
Correction to Amendment Nos. 358 and 352 Regarding Technical Specifications Task Force Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B
ML22187A0192022-09-20020 September 2022
Issuance of Amendment No. 154 Regarding Revision to Technical Specification 3.3.2 to Revise Allowable Value for Trip of Turbine-Driven Main Feedwater Pumps
ML22187A1812022-09-20020 September 2022
Issuance of Amendment Nos. 153 and 62 Regarding Extension of Completion Time for Technical Specification 3.7.8 for Inoperable Essential Raw Cooling Water Train
ML22210A1182022-08-24024 August 2022
Issuance of Amendment Nos. 358 and 352 Regarding Technical Specifications Task Force Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B
ML22165A1052022-07-12012 July 2022
Issuance of Amendment Nos. 357 and 351 Regarding Revision to Technical Specification Table 3.3.1-1, Reactor Trip System Instrumentation
ML22138A3252022-06-24024 June 2022
Issuance of Amendment Nos. 321, 344, and 304 Regarding Spent Fuel Pool Criticality Safety Analysis
ML22014A2062022-05-0404 May 2022
Issuance of Amendment Nos. 152 and 61 Regarding Revision to Technical Specifications to Delete a Redundant Unit of Measure for Certain Radiation Monitors
ML22084A0012022-04-0505 April 2022
Clinch River Nuclear Site; Sequoyah Nuclear Plant, Units 1 and 2; Watts Bar Nuclear Plant, Units 1 and 2, Review of Quality Assurance Plan Changes
ML22070A0022022-03-28028 March 2022
Review of the Fall 2021 Mid Cycle Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Report
ML22020A2282022-03-16016 March 2022
Issuance of Amendment Nos. 320, 343, and 303 Regarding the Adoption of Approved Technical Specification Task Force Traveler TSTF-568, Revision 2
ML21306A2872022-01-25025 January 2022
Issuance of Amendment No. 60 Regarding Revision of Technical Specification Requirements Specific to the Model D3 Steam Generators That Will No Longer Apply Following Steam Generator Replacement
ML21334A2952022-01-18018 January 2022
Issuance of Amendment No. 151 Regarding Revision to TS 3.7.12 for One-Time Exception to Permit Continuous Opening of Auxiliary Building Secondary Containment Enclosure During Unit 2 Steam Generator Replacement
ML22010A1952022-01-12012 January 2022
Request to Use Later Edition of the American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants
ML21334A3892022-01-12012 January 2022
Issuance of Amendment No. 59 Regarding Revision to Steam Generator Tube Rupture Dose Analysis
ML21271A1372021-12-16016 December 2021
Issuance of Amendment Nos. 150 and 58 Regarding Modification of Technical Specification Surveillance Requirement 3.6.15.4, Shield Building
ML21260A2102021-11-22022 November 2021
Issuance of Amendment No. 57 to Revise Technical Specifications to Change the Steam Generator Secondary Side Water Level
2024-08-27
[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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