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Issue date | Title | Topic | |
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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) | 18 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) | Safe Shutdown Anticipated operational occurrence |
CNL-23-059, Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23- | 20 September 2023 | Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 | Coatings Surveillance Frequency Control Program Fuel cladding |
CNL-23-028, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06) | 2 August 2023 | Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06) | Coatings Surveillance Frequency Control Program Fuel cladding |
CNL-23-020, Application to Revise Technical Specifications to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (WBN-TS-22-06) | 28 June 2023 | Application to Revise Technical Specifications to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (WBN-TS-22-06) | Safe Shutdown Hydrostatic Surveillance Frequency Control Program Offsite Circuit |
ML23122A232 | 7 June 2023 | Issuance of Amendment Nos. 162 and 69 Regarding Change to Date in Footnotes for Technical Specification 3.7.11, Control Room Emergency Air Temperature Control System (Creatcs) | Cyber Security Surveillance Frequency Control Program Fire Protection Program |
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-22-008, and Watts Bar Nuclear Plant - Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules (BFN-TS-541, SQN-TS-21-09, and WBN-TS-22-002) | 13 June 2022 | and Watts Bar Nuclear Plant - Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules (BFN-TS-541, SQN-TS-21-09, and WBN-TS-22-002) | Time of Discovery Incorporated by reference Missed surveillance |
CNL-20-008, Application to Modify Watts Bar Nuclear Plant (WBN) Unit 2 Technical Specification 5.9.6, Reactor Coolant System Pressure and Temperature Limits Report, (WBN-TS-19-28) | 27 July 2020 | Application to Modify Watts Bar Nuclear Plant (WBN) Unit 2 Technical Specification 5.9.6, Reactor Coolant System Pressure and Temperature Limits Report, (WBN-TS-19-28) | Unanalyzed Condition Anticipated operational occurrence Hydrostatic Pressure and Temperature Limits Report Surveillance Frequency Control Program |
CNL-20-016, Application to Modify Watts Bar Nuclear Plant Unit 1 Technical Specifications 3.3.3, Post Accident Monitoring Instrumentation, (WBN-TS-19-23) | 22 June 2020 | Application to Modify Watts Bar Nuclear Plant Unit 1 Technical Specifications 3.3.3, Post Accident Monitoring Instrumentation, (WBN-TS-19-23) | Reactor Vessel Water Level Anticipated operational occurrence Post Accident Monitoring |
CNL-20-004, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.3.5, LOP DG Start Instrumentation, (WBN-TS-20-01) | 17 January 2020 | Units 1 and 2, License Amendment Request to Revise Technical Specification 3.3.5, LOP DG Start Instrumentation, (WBN-TS-20-01) | Open Phase Condition |
CNL-19-097, Non-Voluntary License Amendment Request to Correct Unbalanced Voltage Relay Instrumentation Values (TS-19-22) | 23 October 2019 | Non-Voluntary License Amendment Request to Correct Unbalanced Voltage Relay Instrumentation Values (TS-19-22) | |
CNL-19-105, Supplemental Response to Second-Round NRC Request for Additional Information Regarding Application to Revise Technical Specifications Regarding DC Electrical Systems TSTF-500, Revision 2 (WBN-TS-18-09) | 10 October 2019 | Supplemental Response to Second-Round NRC Request for Additional Information Regarding Application to Revise Technical Specifications Regarding DC Electrical Systems TSTF-500, Revision 2 (WBN-TS-18-09) | |
CNL-17-149, Revised Additional Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Revision 1, Clarification of Rod Position Requirements (WBN-TS-16-025) | 27 December 2017 | Revised Additional Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Revision 1, Clarification of Rod Position Requirements (WBN-TS-16-025) | Shutdown Margin |
ML17321A033 | 16 November 2017 | Additional Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Revision 1, Clarification of Rod Position Requirements (WBN-TS-16-025) | Shutdown Margin |
NL-17-128, Application to Modify the Watts Bar Nuclear Plant Unit 2 Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Fluid Oil Pressure (391-WBN-TS-17-23) | 11 October 2017 | Application to Modify the Watts Bar Nuclear Plant Unit 2 Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Fluid Oil Pressure (391-WBN-TS-17-23) | |
CNL-17-128, Application to Modify the Watts Bar Nuclear Plant Unit 2 Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Fluid Oil Pressure (391-WBN-TS-17-23) | 11 October 2017 | Application to Modify the Watts Bar Nuclear Plant Unit 2 Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Fluid Oil Pressure (391-WBN-TS-17-23) | Anticipated operational occurrence Fuel cladding |
CNL-17-123, Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Revision 1, Clarification of Rod Position Requirements (WBN-TS-16-025) | 29 September 2017 | Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Revision 1, Clarification of Rod Position Requirements (WBN-TS-16-025) | Boric Acid Shutdown Margin Anticipated operational occurrence Fuel cladding |
CNL-17-044, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.7.12, Auxiliary Building Gas Treatment System (Abgts), for Watts Bar Nuclear Plant, Units 1 and 2 | 5 May 2017 | Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.7.12, Auxiliary Building Gas Treatment System (Abgts), for Watts Bar Nuclear Plant, Units 1 and 2 | Safe Shutdown Unanalyzed Condition |
CNL-15-133, Response to Request for Additional Information Related to Technical Specification 3.8.1 Regarding Diesel Generator Steady State Frequency (WBN-TS-13-08) | 15 July 2015 | Response to Request for Additional Information Related to Technical Specification 3.8.1 Regarding Diesel Generator Steady State Frequency (WBN-TS-13-08) | Boric Acid Stroke time |
CNL-15-088, Application to Revise Technical Specifications for Component Cooling Water Snd Essential Raw Cooling Water to Support Dual Unit Operation (TS-WBN-15-13) | 17 June 2015 | Application to Revise Technical Specifications for Component Cooling Water Snd Essential Raw Cooling Water to Support Dual Unit Operation (TS-WBN-15-13) | Safe Shutdown Ultimate heat sink Offsite Circuit |
CNL-14-218, Application to Modify Technical Specification 3.8.1 Regarding Diesel Generator Steady State Frequency (WBN-TS-13-08) | 6 April 2015 | Application to Modify Technical Specification 3.8.1 Regarding Diesel Generator Steady State Frequency (WBN-TS-13-08) | Safe Shutdown Boric Acid Stroke time Anticipated operational occurrence Offsite Circuit |
CNL-15-001, Application to Revise Technical Specification 4.2.1, Fuel Assemblies, (WBN-TS-15-03) | 31 March 2015 | Application to Revise Technical Specification 4.2.1, Fuel Assemblies, (WBN-TS-15-03) | Boric Acid Shutdown Margin Offsite Dose Calculation Manual Anticipated operational occurrence Tritium |
ML14170A046 | 16 June 2014 | Attachment 2 - TS Bases Developmental Revision I Changes (Mark-Up) for WBN Unit 2 | |
ML14170A045 | 16 June 2014 | Attachment 1 - TS Developmental Revision I Changes (Mark-Up) for WBN Unit 2 | Shutdown Margin Reactor Vessel Water Level High Radiation Area Offsite Dose Calculation Manual Post Accident Monitoring Hydrostatic Nondestructive Examination Pressure and Temperature Limits Report Annual Radiological Environmental Operating Report Process Control Program Pressure Boundary Leakage Offsite Circuit Fire Protection Program Power change Unidentified leakage |
ML14170A044 | 16 June 2014 | Attachment 5 - WBN Unit 2 TS and Tsb Through Developmental Revision I, and Trm and Trmb Through Developmental Revision D | |
ML11228A047 | 10 August 2011 | Technical Specifications (Developmental Revision F), Enclosure 1 | Time of Discovery Shutdown Margin Reactor Vessel Water Level High Radiation Area Ultimate heat sink Grab sample Offsite Dose Calculation Manual Post Accident Monitoring Hydrostatic Nondestructive Examination Pressure and Temperature Limits Report Annual Radiological Environmental Operating Report Process Control Program Pressure Boundary Leakage Offsite Circuit Fire Protection Program Power change Unidentified leakage |
ML102290075 | 16 August 2010 | Unit 2 - Change to Developmental TS Section 4.2.2, Control Rod Assemblies | Pressure and Temperature Limits Report |
ML100550441 | 2 February 2010 | Developmental Revision B - Technical Specifications 2.0 - Safety Limits | |
ML100550367 | 2 February 2010 | Developmental Revision B - Technical Specifications Table of Contents | Shutdown Margin High Radiation Area Ultimate heat sink Offsite Dose Calculation Manual Post Accident Monitoring Pressure and Temperature Limits Report Process Control Program |
ML100550474 | 2 February 2010 | Developmental Revision B - Technical Specifications 5.0 - Administrative Controls | High Radiation Area Offsite Dose Calculation Manual Post Accident Monitoring Hydrostatic Nondestructive Examination Pressure and Temperature Limits Report Annual Radiological Environmental Operating Report Process Control Program Fire Protection Program |
ML100550471 | 2 February 2010 | Developmental Revision B - Technical Specifications 4.0 - Design Features | |
ML100550401 | 2 February 2010 | Developmental Revision B - Technical Specifications 1.0 - Use and Application | Time of Discovery Shutdown Margin Hydrostatic Pressure Boundary Leakage |
ML100550447 | 2 February 2010 | Developmental Revision B - Technical Specifications 3.0 - Limiting Condition for Operation (LCO) Applicability | Time of Discovery |
ML100550464 | 2 February 2010 | Developmental Revision B - Technical Specifications 3.9 - Refueling Operations | |
ML100550449 | 2 February 2010 | Developmental Revision B - Technical Specifications 3.1 - Reactivity Control Systems | Shutdown Margin |
ML100550462 | 2 February 2010 | Developmental Revision B - Technical Specifications 3.8 - Electrical Power Systems | Offsite Circuit |
ML100550461 | 2 February 2010 | Developmental Revision B - Technical Specifications 3.7 - Plant Systems | Ultimate heat sink |
ML100550450 | 2 February 2010 | Developmental Revision B - Technical Specifications 3.2 - Power Distribution Limits | |
ML100550451 | 2 February 2010 | Developmental Revision B - Technical Specifications 3.3 - Instrumentation | Reactor Vessel Water Level Post Accident Monitoring |
ML100550453 | 2 February 2010 | Developmental Revision B - Technical Specifications 3.4 - Reactor Coolant System | Grab sample Hydrostatic Pressure Boundary Leakage Power change |
ML100550456 | 2 February 2010 | Developmental Revision B - Technical Specifications 3.5 - Emergency Core Cooling Systems | |
ML100550458 | 2 February 2010 | Developmental Revision B - Technical Specifications 3.6 - Containment Systems | High Radiation Area |
ML092950340 | 20 October 2009 | License Amendment Request for Adoption of TSTF-511, Revision 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26 - Browns Ferry TS Change 469; Sequoyah Change 09-04; and Watts Change 09-19 | Safe Shutdown |
ML091320562 | 30 April 2009 | Application for Technical Specification Change to Correct Minor Error in Amendment 70 | |
ML090090044 | 31 December 2008 | Revised Technical Specifications Change WBN-TS-08-04 - Revision to the Maximum Number of TPBARS That Can Be Irradiated in the Reactor Core Per Cycle | |
ML083170861 | 12 November 2008 | License Amendment Request TS-08-11 to Revise Reactor Coolant System Leakage Detection Systems - Exigent Change Request | Grab sample Fuel cladding Pressure Boundary Leakage |
ML071210604 | 25 April 2007 | (WBN) Unit 1 - Technical Specification Change 07-01, Revision of Number of Tritium Producing Burnable Absorber Rods (TPBARS) in the Reactor Core | |
ML061650267 | 12 June 2006 | Technical Specifications (TS) Change WBN-TS-05-10 - Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity - Request for Additional Information | |
ML052650061 | 20 September 2005 | T.S. for License Amendment, Regarding Alternative Means for Monitoring Control or Shutdown Rod Position | |
ML050980208 | 21 March 2005 | Tech Spec Pages for Amendment No. 57, Elimination of Monthly Report Requirement on Operating & Occupational Reports (TS-04-15) | Offsite Dose Calculation Manual Annual Radiological Environmental Operating Report Process Control Program |