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CNL-23-001, Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01)13 December 2023Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01)
WBL-22-026, Periodic Submission for Changes Made to the Technical Specification Bases and Technical Requirements Manual11 May 2022Periodic Submission for Changes Made to the Technical Specification Bases and Technical Requirements Manual
ML20232C62211 February 2021Issuance of Amendment Nos. 142 and 49 Regarding Revision to Technical Specifications to Implement WCAP-17661-P-A, Revision 1, Improved RAOC and CAOC Fq Surveillance Technical Specifications (EPID L-2020-LLA-0037
CNL-21-010, Correction of Application to Implement the Full Spectrum LOCA (Fsloca) Methodology for Loss-of-Coolant Accident (LOCA) Analysis and New LOCA-specific Tritium Producing Burnable Absorber Rod Stress Analysis Methodology (WBN-TS-19-04) (EPID26 January 2021Correction of Application to Implement the Full Spectrum LOCA (Fsloca) Methodology for Loss-of-Coolant Accident (LOCA) Analysis and New LOCA-specific Tritium Producing Burnable Absorber Rod Stress Analysis Methodology (WBN-TS-19-04) (EPID L
ML20323A31129 October 2020Amendment 3 to Updated Final Safety Analysis Report, Chapter 4, Reactor
CNL-19-115, Non-Voluntary License Amendment Request to Modify Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications 3.2.1, Fq(Z), to Implement Methodology from WCAP-17661, Revision 1, Improved RAOC and CAOC Fq Surveillance Technical Specific2 March 2020Non-Voluntary License Amendment Request to Modify Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications 3.2.1, Fq(Z), to Implement Methodology from WCAP-17661, Revision 1, Improved RAOC and CAOC Fq Surveillance Technical Specificat
CNL-19-051, Application to Implement the Full Spectrum LOCA (Fsloca) Methodology for Loss-of-Coolant Accident (LOCA) Analysis and New LOCA-specific Tritium Producing Burnable Absorber Rod Stress Analysis Methodology17 January 2020Application to Implement the Full Spectrum LOCA (Fsloca) Methodology for Loss-of-Coolant Accident (LOCA) Analysis and New LOCA-specific Tritium Producing Burnable Absorber Rod Stress Analysis Methodology
L-19-023, Periodic Submission for Changes Made to the WBN Technical Specification Bases and Technical Requirements Manual19 March 2019Periodic Submission for Changes Made to the WBN Technical Specification Bases and Technical Requirements Manual
CNL-18-067, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (WBN-TS-18-14)12 October 2018Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (WBN-TS-18-14)
CNL-18-116, Response to Request for Additional Information Regarding the Application to Revise Watts Bar Nuclear Plant Unit 2 - License Condition 2.C(4) PAD4TCD (391-WBN-TS-18-03)11 October 2018Response to Request for Additional Information Regarding the Application to Revise Watts Bar Nuclear Plant Unit 2 - License Condition 2.C(4) PAD4TCD (391-WBN-TS-18-03)
ML17334A1692 November 2017Amendment 1 to Updated Safety Analysis Report, Chapter 4, Reactor
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 2017Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Revision 1, Clarification of Rod Position Requirements (WBN-TS-16-025)
NL-17-008, Sequoyah and Watts Bar - License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 3.2.4, Qptr, and TS 3.3.1, Reactor Trip System (RTS) Instrumentation, Condition D (SQN-TS-17-02 and WBN-TS-17-014)7 August 2017Sequoyah and Watts Bar - License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 3.2.4, Qptr, and TS 3.3.1, Reactor Trip System (RTS) Instrumentation, Condition D (SQN-TS-17-02 and WBN-TS-17-014)
CNL-17-008, License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 3.2.4, QPTR, and TS 3.3.1, Reactor Trip System (RTS) Instrumentation, Condition D (SQN-TS-17-02 and WBN-TS-17-014)7 August 2017License Amendment Request to Modify Technical Specification (TS) Surveillance Requirement 3.2.4, QPTR, and TS 3.3.1, Reactor Trip System (RTS) Instrumentation, Condition D (SQN-TS-17-02 and WBN-TS-17-014)
CNL-16-148, Application to Revise Technical Specifications to Adopt TSTF-547, Revision 1, Clarification of Rod Position Requirements (WBN-TS-16-025)23 November 2016Application to Revise Technical Specifications to Adopt TSTF-547, Revision 1, Clarification of Rod Position Requirements (WBN-TS-16-025)
ML15279A27011 September 2015Amendment 114 to Final Safety Analysis Report, Section 4.0 - Reactor, Pages 4-i - 4.4-52
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 4.0 - Reactor, Pages 4-i - 4.4-5211 September 2015Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 4.0 - Reactor, Pages 4-i - 4.4-52
ML14160B10430 May 2014Final Safety Analysis Report, Amendment 112, Section 4.0, Reactor
ML13255A27814 August 2013Final Safety Analysis Report (Fsar), Amendment 110, Section 4, Rector
ML13205A13630 June 2013NUREG-0847 Supp 26 Safety Evaluation Report Related to the Operation of Watts Bar Nuclear Plant, Unit 2
ML12244A06923 August 2012Final Safety Analysis Report (Fsar), Amendment 109 - Section 4, Reactor - Page 4-I Through 4.4-52
ML12083A1705 March 2012Final Safety Analysis Report, Amendment 108. Chapter 4 - 4.0 Through 4.4-52
ML12178A18517 November 2011Final Safety Analysis Report, Amendment 107 - Section 4 - Reactor
ML11321A30814 November 2011Changes Made to the Technical Specification Bases
ML11277A14830 September 2011NUREG-0847 Supp 24 Safety Evaluation Report Related to the Operation of Watts Bar Nuclear Plant, Unit 2.
ML12170A59815 September 2011Final Safety Analysis Report, Amendment 106, Section 4.0, Reactor Through Section 4.4, Figure 4.4-6
ML12171A07912 August 2011Unit 2 - Final Safety Analysis Report (Fsar), Amendment 105, 4.0 Reactor
ML11206A49930 June 2011NUREG-0847 Supp 23, Safety Evaluation Report, Related to the Operation of Watts Bar Nuclear Plant, Unit 2.
ML11174A28221 June 2011Response to NRC Staff Comments on Developmental Revisions of the Unit 2 Technical Specifications and Technical Specification Bases; Submittal of Developmental Revision F
ML11178A1723 June 2011Final Safety Analysis Report (Fsar), Amendment 104, Table of Contents, Section 4.0 Reactor, Through Figure 4.4-6, Location of Incore Instrumentation System Fixed Incore Detector Core Exit Thermocouples and Iitas (Unit 2)
ML12073A20929 April 2011Initial Exam 2011-302 Draft SRO Written Exam 1 of 3
ML11087155015 March 2011Unit 2 - Final Safety Analysis Report (Fsar), Amendment 103. Table of Contents - Section 4.0 Through 4.4-52 Thermal and Hydraulic Design
ML11035015525 February 2011Issuance of Amendment Regarding the Control Rod Assemblies (Tac ME3991)
ML11221A25417 December 2010Amendment 102 to Final Safety Analysis Report (Fsar), Section 4, Reactor
ML10316049629 October 2010Amendment 101 to Final Safety Analysis Report (Fsar), Section 4, Reactor, Pages 4.4-1 Through 4.4-52
ML10161035627 May 2010Amendment 99 to Final Safety Analysis Report (Fsar), Section 4 - Reactor, Pages 4.1-1 Through 4.4-52
ML1013706967 May 2010Amendment 98 to Final Safety Analysis Report, Section 4, Reactor
ML1013703977 May 2010Amendment 98 to Final Safety Analysis Report, Section 4 - Reactor, Pages 4.1-1 Thur 4.4-52
ML1012000353 May 2010Correction Letter for Watts Bar Nuclear Plant, Unit 2 - Safety Evaluation Regarding Bulletin 1996-01, Control Rod Insertion Problems (Tac MD6707)
ML10117014820 April 2010Changes Made to the Technical Specification Bases
ML1001200261 April 2010Safety Evaluation Regarding Bulletin 1996-01, Control Rod Insertion Problems
ML1005504942 February 2010Developmental Revision B - Technical Specifications Bases B 3.1 - Reactivity Control Systems
ML1005506002 February 2010Developmental Revision B - Technical Specifications Bases B 3.9 - Refueling Operations
ML1005504972 February 2010Developmental Revision B - Technical Specifications Bases B 3.2 - Power Distribution Limits
ML10019167311 January 2010Final Safety Analysis Report, Amendment 97, Section 4 - Reactor Through Figure 4.4-5, Page 4.4-53
ML09357049514 December 2009Final Safety Analysis Report, Amendment 96, Table of Contents - Section 4 - Table of Contents - Reactor, Page 4.1 Though 4.4-53
ML09337034524 November 2009Final Safety Analysis Report, Amendment 95, Chapter 4, Sections 4.0 Through 4.4-53
ML09247032427 August 2009Final Safety Analysis Report, Amendment 94, Section 4, Reactor Through Figure 4.4-23
ML0919401919 July 2009Watts, Unit 1 - Technical Specifications Change - Core Power Distribution Monitoring System.
ML09140065130 April 2009Final Safety Analysis Report (Fsar), Amendment 93, Section 4.0, Reactor Through Page 4.4-70
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