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 Issue dateTitleTopic
CNL-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 Out1 June 2023Transmittal 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-A30 January 2023Browns 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-AFire Protection Program
CNL-21-007, Organization Topical Report, TVA-NPOD89-A, Revision 2429 January 2021Organization Topical Report, TVA-NPOD89-A, Revision 24Fire Protection Program
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)30 September 2019Application to Revise Watts Bar Nuclear Plant (WBN) Unit 2 - Technical Specifications for Steam Generator Tube Repair Sleeve (WBN-TS-391-19-13)Anticipated operational occurrence
Safe Shutdown Earthquake
Post Accident Monitoring
Nondestructive Examination
Power change
ML19158A3953 July 2019Verification 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
ML19010A27418 March 2019Final 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 AuthorityCommercial Grade Dedication
RA-19-0115, Transmittal of the Duke Energy Corporation Topic Report (Duke QAPD-001-A), Amendment 4418 February 2019Transmittal of the Duke Energy Corporation Topic Report (Duke QAPD-001-A), Amendment 44Safe Shutdown
Fitness for Duty
Offsite Dose Calculation Manual
Commercial Grade Dedication
Coatings
Nondestructive Examination
Emergency Lighting
Condition Adverse to Quality
Aging Management
Process Control Program
Stress corrosion cracking
License Renewal
Commercial Grade
Maintenance Rule Program
Fatigue Rule
Fire Protection Program
CNL-19-001, Sequoyah Nuclear Plant and Watts Bar Nuclear Plant - Organization Topical Report, TVA-NPOD89-A15 January 2019Sequoyah Nuclear Plant and Watts Bar Nuclear Plant - Organization Topical Report, TVA-NPOD89-AFire Protection Program
CNL-18-069, Tennessee Valley Authority - Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revisions 35 and 368 May 2018Tennessee Valley Authority - Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revisions 35 and 36Fitness for Duty
Offsite Dose Calculation Manual
Safe Shutdown Earthquake
Coatings
Nondestructive Examination
Cyber Security
B.5.b
Process Control Program
Fire Protection Program
Grace period
CNL-17-012, Organization Topical Report, TVA-NPOD89-A17 January 2017Organization Topical Report, TVA-NPOD89-AFire Protection Program
ML17018A15017 January 2017Units 1 and 2, Watts Bar, Units 1 and 2 - Organization Topical Report, TVA-NPOD89-AFire Protection Program
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-A17 January 2017Browns Ferry, Units 1, 2, and 3, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2 - Organization Topical Report, TVA-NPOD89-AFire Protection Program
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 Information4 April 2016Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 9, Responses to Requests for Additional InformationShutdown Margin
Anticipated operational occurrence
Feedwater Controller Failure
MELLLA
Fuel cladding
Power change
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 Enclose28 December 2015Brown 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 EnclosedMinimum Critical Power Ratio
CNL-15-060, Technical Specifications Change No. WBN2-TS-15-16 - Revise Technical Specifications for Use of Steam Generator Alternate Repair Criterion F15 December 2015Technical Specifications Change No. WBN2-TS-15-16 - Revise Technical Specifications for Use of Steam Generator Alternate Repair Criterion FAnticipated operational occurrence
Post Accident Monitoring
Nondestructive Examination
Finite Element Analysis
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 715 December 2015Proposed 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 Information15 December 2015Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 1, Spent Fuel Pool Criticality Safety Analysis InformationAging Management
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 EPU31 March 2015Browns Ferry, Units 1, 2 and 3, ANP-3327NP, Revision 1, Evaluation of Areva Fuel Thermal-Hydraulic Performance for Browns Ferry at EPU
ML15282A22131 March 2015ANP-3327NP, Revision 1, Evaluation of Areva Fuel Thermal-Hydraulic Performance for Browns Ferry at EPU
CNL-14-226, Organization Topical Report, TVA-NPOD89-A13 February 2015Organization Topical Report, TVA-NPOD89-AFire Protection Program
ML13358A06818 December 2013NEDO-33445, Rev.0, Browns Ferry Unit 1, Pressure and Temperature Limits Report (PTLR) Up to 25 and 38 Effective Full-Power Years.Hydrostatic
Finite Element Analysis
Pressure and Temperature Limits Report
ML13253A0755 September 2013Tennessee Valley Authority - Organization Topical Report, TVA-NPOD89-AProbabilistic Risk Assessment
Fire Protection Program
ML12342A13412 November 2012Fukushima Near-Term Task Force Recommendation 2.3: Seismic Response ReportSafe Shutdown
Unanalyzed Condition
Boric Acid
Safe Shutdown Earthquake
Hydrostatic
Probabilistic Risk Assessment
Operating Basis Earthquake
Finite Element Analysis
Design basis earthquake
Large early release frequency
Earthquake
Maintenance Rule Program
Scaffolding
ML12342A13312 November 2012Fukushima Near-Term Task Force Recommendation 2.3: Seismic Response ReportSafe Shutdown
Unanalyzed Condition
Boric Acid
Fire Barrier
Safe Shutdown Earthquake
Hydrostatic
Probabilistic Risk Assessment
Operating Basis Earthquake
Finite Element Analysis
Design basis earthquake
Large early release frequency
Earthquake
Maintenance Rule Program
Scaffolding
ML11249A04631 August 2011Organization Topical Report, TVA-NPOD89-AProbabilistic Risk Assessment
Fire Protection Program
ML09260018514 September 2009Transmittal of Organization Topical Report, TVA-NPOD89-AFitness for Duty
Nondestructive Examination
Fire Protection Program
ML08247002929 August 2008TVA 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 UpdateFitness for Duty
Nondestructive Examination
Fire Protection Program
ML08218009431 July 2008WCAP-16932-NP, Rev. 1, Control Rod Insertion Following a Cold Leg LOCA for Watts Bar Unit 1.Safe Shutdown Earthquake
Tritium Producing Burnable Absorber Rods
Earthquake
ML08155027929 February 2008WCAP-16845-NP, Revision 0, Browns Ferry Nuclear Plant Unit 2, Evaluation of Dissimilar Metal Weld Indication at Weld RCRD-2-52.Non-Destructive Examination
Liquid penetrant
Through Wall Leak
Dissimilar Metal Weld
ML08099053429 February 2008ANP-2655(NP), Rev. 1, Sequoyah Nuclear Plant Unit 2 - Realistic Large Break Loss of Coolant Accident Analysis.Loop seal
Coatings
Fuel cladding
ML07320024430 November 2007WCAP-16760-NP, Rev. 0, Analysis of Capsule Z from the Tennessee Valley Authority, Watts Bar Unit 1 Reactor Vessel Radiation Surveillance Program.
ML07249014631 August 2007TVA 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 UpdatesFitness for Duty
Offsite Dose Calculation Manual
Safe Shutdown Earthquake
Coatings
Nondestructive Examination
B.5.b
Process Control Program
Fire Protection Program
Power Uprate
ML06072028128 February 2006NEDO-33173, Applicability of GE Methods to Expanded Operating Domains.Shutdown Margin
Safety Limit Minimum Critical Power Ratio
Anticipated operational occurrence
Probabilistic Risk Assessment
Feedwater Controller Failure
MELLLA
Rod Drop Event
Fuel cladding
Power change
Flow Induced Vibration
Coast down
ML05245014730 August 2005Tennessee Valley Authority Transmittal of Revised Topical Report Incorporating Organizational Change That Have Been Announced Through 07/31/2005Fitness for Duty
Fire Protection Program
ML05182039130 June 2005to 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.
ML05074002728 February 2005LTR-CDME-04-148, Rev 1, Application of W* Alternate Repair Criteria to Sequoyah Unit 2. (Non-Proprietary Version)Finite Element Analysis
ML04300035831 October 2004WCAP-16333-NP, Fracture Toughness Testing of Compact Tension Specimens Form Watt Bar Unit 1 Surveillance Capsule.
ML04239021420 August 2004Westinghouse Owners Group Request to Withdraw WCAP-16168-NP, Risk-Informed Extension of Reactor Vessel In-Service Inspection Interval, (PA-MSC-0120)
ML04300035630 April 2004to WCAP-16245-NP, Analysis of Capsule X from Tennessee Valley Authority, Watt Bar Unit 1 Reactor Vessel Radiation Surveillance Program.
ML04344023131 January 2004Nonproprietary Revision 0 to NEDO-33112, Pressure-Temperature Curves for TVA Browns Ferry Unit 1.Shutdown Margin
Anticipated operational occurrence
Hydrostatic
Finite Element Analysis
ML03323022512 November 2003Submittal of WCAP-16084-NP, Development of Risk-Informed Safety Analysis Approach and Pilot Application.Anticipated operational occurrence
Probabilistic Risk Assessment
Fuel cladding
Coast down
ML03311009123 October 2003Submittal 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 SpecificationCondition Adverse to Quality
GOTHIC
ML0325214783 September 2003Updated Pressure Temperature Limits Report and Topical Reports for SQN Technical Specification Change No. 00-14Hydrostatic
ML03275034931 August 2003to GE-NE-0000-0013-3193-01a-R1, Pressure-Temperature Curves for TVA Browns Ferry, Unit 2.Shutdown Margin
Anticipated operational occurrence
Hydrostatic
Finite Element Analysis
ML03275039331 August 2003to GE-NE-0000-0013-3193-02a-R1, Pressure-Temperature Curves for TVA Browns Ferry, Unit 3.Shutdown Margin
Anticipated operational occurrence
Hydrostatic
Finite Element Analysis
ML03240017225 August 2003TVA Nuclear Organization Topical Report - Bellefonte, Browns Ferry, Sequoyah, and Watts Bar Nuclear PlantsFitness for Duty
Fire Protection Program
ML03192064719 June 2003to Ice Condenser Utility Group Topical Report No. ICUG-001: Application of the Active Ice Mass Management Concept to the Ice Condenser Ice Mass Technical SpecificationCondition Adverse to Quality
ML03149046619 May 2003Accepted Version of Topical Report No. 24370-TR-C-001-A, Alternative Rebar Splice -Bar-Lock Mechanical Splices.Commercial Grade Dedication
Earthquake
ML03163082419 May 2003Accepted Version of Topical Report No. 24370-TR-C-003-A, Steam Generator Compartment Roof Modification.Unanalyzed Condition
Safe Shutdown Earthquake
Operating Basis Earthquake
Finite Element Analysis
Design basis earthquake
Earthquake
ML03182067030 April 2003to WCAP-15984-NP, Reactor Vessel Closure Head/Vessel Flange Requirements Evaluation for Sequoyah Units 1 & 2.Hydrostatic
Finite Element Analysis