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MONTHYEARCNL-16-148, Application to Revise Technical Specifications to Adopt TSTF-547, Revision 1, Clarification of Rod Position Requirements (WBN-TS-16-025)2016-11-23023 November 2016 Application to Revise Technical Specifications to Adopt TSTF-547, Revision 1, Clarification of Rod Position Requirements (WBN-TS-16-025) Project stage: Request ML17030A0052017-01-27027 January 2017 NRR E-mail Capture - Watts Bar Nuclear Plant Units 1 and 2 - Acceptance for Review - Request to Adopt TSTF-547, Revision 1, Clarification of Rod Position Requirements Project stage: Acceptance Review 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)2017-09-29029 September 2017 Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Revision 1, Clarification of Rod Position Requirements (WBN-TS-16-025) Project stage: Supplement ML17321A0332017-11-16016 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) Project stage: Supplement 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)2017-12-27027 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) Project stage: Supplement ML18039A8922018-02-14014 February 2018 Individual Notice of Consideration of Issuance of Amendments to Facility Operating Licenses, Proposed No Sig. Hazards Consideration Determination, and Opportunity for Hearing (CAC Nos. MF8912-13; EPID L-2016-0034) Project stage: Other L-2016-003, Individual Notice of Consideration of Issuance of Amendments to Facility Operating Licenses, Proposed No Sig. Hazards Consideration Determination, and Opportunity for Hearing (CAC Nos. MF8912-13; EPID L-2016-0034)2018-02-14014 February 2018 Individual Notice of Consideration of Issuance of Amendments to Facility Operating Licenses, Proposed No Sig. Hazards Consideration Determination, and Opportunity for Hearing (CAC Nos. MF8912-13; EPID L-2016-0034) Project stage: Approval CNL-18-073, Supplemental Information to Correct an Error Related to the Application to Revise Technical Specifications to Adopt TSTF-547, Revision 1, Clarification of Rod Position Requirements (WBN-TS-16-025)2018-05-11011 May 2018 Supplemental Information to Correct an Error Related to the Application to Revise Technical Specifications to Adopt TSTF-547, Revision 1, Clarification of Rod Position Requirements (WBN-TS-16-025) Project stage: Supplement ML18079A0292018-06-26026 June 2018 Issuance of Amendments Regarding Adoption of TSTF-547, Clarification of Rod Position Requirements (CAC Nos. MF8912and MF8913; EPID L-2016-LLA-0034) Project stage: Approval 2017-12-27
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Category:Letter
MONTHYEARIR 05000390/20250102024-11-0404 November 2024 Notification of an NRC (FPTI) (NRC Inspection Report 05000390/2025010 0500039/ 2025010) (RFI) CNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000390/20243012024-10-17017 October 2024 Operator Licensing Examination Approval 05000390/2024301 and 05000391/2024301 ML24282B0412024-10-15015 October 2024 Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 ML24260A1682024-10-0404 October 2024 Regulatory Audit Summary Related to Request to Add and Revise Notes Related to Technical Specification Table 3.3.2-1, Function 5 ML24261C0062024-10-0404 October 2024 Correction to Amendment No. 134 to Facility Operating License No. NPF-90 and Amendment No. 38 to Facility Operating License No. NPF-96 ML24284A1072024-09-26026 September 2024 Affidavit for Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2 CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description CNL-24-047, Decommitment of Flood Mode Mitigation Improvement Systems2024-09-24024 September 2024 Decommitment of Flood Mode Mitigation Improvement Systems ML24262A0602024-09-23023 September 2024 Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 05000390/LER-2024-002, Automatic Reactor Trip Due to Main Generator Protection Relay Actuation2024-09-0505 September 2024 Automatic Reactor Trip Due to Main Generator Protection Relay Actuation IR 05000390/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390-2024005 and 05000391-2024005 ML24218A1442024-08-27027 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 IR 05000390/20244022024-08-20020 August 2024 – Security Baseline Inspection Report 05000390-2024402 and 05000391/2024402 - Public CNL-24-061, Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08),2024-08-19019 August 2024 Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08), ML24219A0262024-08-12012 August 2024 Request for Withholding Information from Public Disclosure IR 05000390/20240022024-08-0707 August 2024 Integrated Inspection Report 05000390/2024002 and 05000391/2024002 Rev ML24204A2652024-07-25025 July 2024 Regulatory Audit Summary Related to Request to Revise Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) 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 ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter IR 05000390/20244402024-07-12012 July 2024 95001 Supplemental Inspection Supplemental Report 05000390-2024440 and 05000391-2024440 and Follow-Up Assessment Letter 05000391/LER-2024-003, Inoperability of Both Trains of Unit 2 Low Head Safety Injection2024-07-11011 July 2024 Inoperability of Both Trains of Unit 2 Low Head Safety Injection ML24131A0012024-07-0202 July 2024 Issuance of Amendment Nos. 167 and 73 Regarding Adoption of Technical Specification Task Force Traveler TSTF-427-A, Revision 2 CNL-24-052, Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-06-27027 June 2024 Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-24-018, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS2024-06-25025 June 2024 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS ML24089A1152024-06-21021 June 2024 Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2) ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc 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) IR 05000390/20240012024-05-14014 May 2024 Integrated Inspection Report 05000390/2024001 and 05000391/2024001 CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 05000391/LER-2024-002, Re Automatic Reactor Trip Due to Steam Generator 3 Level LO-LO2024-05-0606 May 2024 Re Automatic Reactor Trip Due to Steam Generator 3 Level LO-LO IR 05000391/20240072024-04-30030 April 2024 Assessment Follow-up Letter for Watts Bar Nuclear Plant, Unit 2 – Report 05000391/2024007 ML24120A1182024-04-29029 April 2024 – Notification of NRC Supplemental Inspection (95001) and Request for Information CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42 ML24087A1912024-04-18018 April 2024 Exemption from Select Requirements of 10 CFR Part 73, Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting CNL-24-024, Hydrologic Engineering Center River Analysis System Project Milestone Status Update2024-04-17017 April 2024 Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-24-010, License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19)2024-04-17017 April 2024 License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19) CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 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 CNL-24-004, Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13)2024-04-0404 April 2024 Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13) IR 05000390/20244012024-04-0202 April 2024 – Security Baseline Inspection Report 05000390/2024401 and 05000391/2024401 - (Public) CNL-24-020, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements2024-04-0101 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements 05000391/LER-2024-001, Automatic Reactor Trip Due to Main Generator Protection Relay Actuation2024-03-27027 March 2024 Automatic Reactor Trip Due to Main Generator Protection Relay Actuation CNL-24-007, Annual Insurance Status Report2024-03-27027 March 2024 Annual Insurance Status Report CNL-24-008, Guarantee of Payment of Deferred Premiums - 2023 Annual Report2024-03-27027 March 2024 Guarantee of Payment of Deferred Premiums - 2023 Annual Report CNL-24-025, Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule2024-03-25025 March 2024 Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule ML24081A0262024-03-21021 March 2024 Emergency Plan Implementing Procedure Revisions ML24079A0312024-03-19019 March 2024 Wb 2024-301, Corporate Notification Letter (210-day Ltr) 2024-09-05
[Table view] Category:Technical Specification
MONTHYEARCNL-24-004, Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13)2024-04-0404 April 2024 Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13) 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)2023-12-18018 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) WBL-23-052, Periodic Submission for Changes Made to the Technical Specification Bases and Technical Requirements Manual2023-11-0808 November 2023 Periodic Submission for Changes Made to the Technical Specification Bases and Technical Requirements Manual 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-23-2023-09-20020 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 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)2023-08-0202 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) 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)2023-06-28028 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) ML23122A2322023-06-0707 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) 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 Sche2023-03-20020 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)2022-06-13013 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) WBL-22-026, Periodic Submission for Changes Made to the Technical Specification Bases and Technical Requirements Manual2022-05-11011 May 2022 Periodic Submission for Changes Made to the Technical Specification Bases and Technical Requirements Manual ML20273A0432020-09-29029 September 2020 Plants Unit 1 and 2 - Periodic Submission for Changes Made to the Technical Specification Bases and Technical Requirements Manual 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)2020-07-27027 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) 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)2020-06-22022 June 2020 Application to Modify Watts Bar Nuclear Plant Unit 1 Technical Specifications 3.3.3, Post Accident Monitoring Instrumentation, (WBN-TS-19-23) 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)2020-01-17017 January 2020 Units 1 and 2, License Amendment Request to Revise Technical Specification 3.3.5, LOP DG Start Instrumentation, (WBN-TS-20-01) 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 Methodology2020-01-17017 January 2020 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 CNL-19-097, Non-Voluntary License Amendment Request to Correct Unbalanced Voltage Relay Instrumentation Values (TS-19-22)2019-10-23023 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)2019-10-10010 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) L-19-023, Periodic Submission for Changes Made to the WBN Technical Specification Bases and Technical Requirements Manual2019-03-19019 March 2019 Periodic Submission for Changes Made to the WBN Technical Specification Bases and Technical Requirements Manual CNL-18-130, Revised Application to Modify the Technical Specifications for Unbalanced Voltage Relays2018-11-19019 November 2018 Revised Application to Modify the Technical Specifications for Unbalanced Voltage Relays CNL-18-006, Technical Specification Change - Reactor Coolant Temperature Indicator Inoperable - Exigent Amendment (391-WBN-TS-2018-01)2018-01-10010 January 2018 Technical Specification Change - Reactor Coolant Temperature Indicator Inoperable - Exigent Amendment (391-WBN-TS-2018-01) 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)2017-12-27027 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) ML17321A0332017-11-16016 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) ML17306A8022017-11-0202 November 2017 Periodic Submission for Changes Made to the WBN Technical Specification Bases and Technical Requirements Manual 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)2017-10-11011 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)2017-10-11011 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-17-123, Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Revision 1, Clarification of Rod Position Requirements (WBN-TS-16-025)2017-09-29029 September 2017 Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Revision 1, Clarification of Rod Position Requirements (WBN-TS-16-025) 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 22017-05-0505 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 CNL-17-022, Application to Modify Technical Specification 5.7.2.19 Regarding One-Time Extension of 10 CFR 50, Appendix J Type C Local Leakage Rate Tests (391-WBN-TS-17-05)2017-02-16016 February 2017 Application to Modify Technical Specification 5.7.2.19 Regarding One-Time Extension of 10 CFR 50, Appendix J Type C Local Leakage Rate Tests (391-WBN-TS-17-05) ML16113A0772016-04-22022 April 2016 Periodic Submission for Changes Made to the WBN Technical Specification Bases and Technical Requirements Manual 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 ML15267A1832015-09-23023 September 2015 Watts Bar, Unit 2 - Submittal of Final Revision 0 of the Technical Specifications & Technical Specification Bases, and Final Revision 0 of the Technical Requirements Manual & Technical Requirements Manual Bases NL-15-181, Watts Bar Unit 1, Revision to Essential Raw Cooling Water and Component Cooling System License Amendment Request Including Proposed Changes to Auxiliary Feedwater Pump Suction Transfer Instrumentation and Reactor Coolant System Loops - Mod2015-09-0303 September 2015 Watts Bar Unit 1, Revision to Essential Raw Cooling Water and Component Cooling System License Amendment Request Including Proposed Changes to Auxiliary Feedwater Pump Suction Transfer Instrumentation and Reactor Coolant System Loops - Mode CNL-15-181, Revision to Essential Raw Cooling Water and Component Cooling System License Amendment Request Including Proposed Changes to Auxiliary Feedwater Pump Suction Transfer Instrumentation and Reactor Coolant System Loops - Mode 42015-09-0303 September 2015 Revision to Essential Raw Cooling Water and Component Cooling System License Amendment Request Including Proposed Changes to Auxiliary Feedwater Pump Suction Transfer Instrumentation and Reactor Coolant System Loops - Mode 4 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)2015-07-15015 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) 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)2015-06-17017 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) CNL-14-218, Application to Modify Technical Specification 3.8.1 Regarding Diesel Generator Steady State Frequency (WBN-TS-13-08)2015-04-0606 April 2015 Application to Modify Technical Specification 3.8.1 Regarding Diesel Generator Steady State Frequency (WBN-TS-13-08) CNL-15-001, Application to Revise Technical Specification 4.2.1, Fuel Assemblies, (WBN-TS-15-03)2015-03-31031 March 2015 Application to Revise Technical Specification 4.2.1, Fuel Assemblies, (WBN-TS-15-03) CNL-14-217, Responses to Requests for Additional Information - Developmental Revision I Technical Specification Sections 3.8 and 5.72015-03-0505 March 2015 Responses to Requests for Additional Information - Developmental Revision I Technical Specification Sections 3.8 and 5.7 CNL-14-180, Technical Specification Sections 3.0 and 3.10.12015-01-22022 January 2015 Technical Specification Sections 3.0 and 3.10.1 ML14307A9812014-11-0303 November 2014 Periodic Submission for Changes Made to Technical Specification Bases and Technical Requirement Manual ML14170A0442014-06-16016 June 2014 Attachment 5 - WBN Unit 2 TS and Tsb Through Developmental Revision I, and Trm and Trmb Through Developmental Revision D ML14170A0452014-06-16016 June 2014 Attachment 1 - TS Developmental Revision I Changes (Mark-Up) for WBN Unit 2 ML14170A0462014-06-16016 June 2014 Attachment 2 - TS Bases Developmental Revision I Changes (Mark-Up) for WBN Unit 2 ML13357A0542013-12-12012 December 2013 Technical Specifications Bases ML13357A0512013-12-12012 December 2013 Synopsis of Revisions Included in Watts Bar Unit 2 Developmental Revision H of Technical Specifications and Technical Specification Bases. Part 2 of 2 ML13353A4782013-12-12012 December 2013 Fuel Handling Accident Dose Analysis Final Safety Analysis Report and Technical Specification Revision ML12333A2422012-11-20020 November 2012 Application to Modify Technical Specification 4.3.1, Criticality, (WBN-TS-12-03) ML12333A2402012-11-19019 November 2012 Unit I, Application to Modify Technical Specification 3.7.10, Control Room Emergency Ventilation System (WBN-TS-12-01) ML12240A2242012-08-23023 August 2012 Update to Technical Requirements Manual (TRM) Bases Section 3.7.2, Developmental Revision B ML12065A0362012-02-28028 February 2012 Submittal of Developmental Revision G of the Unit 2 Technical Specification (TS) and Technical Specification Bases 2024-04-04
[Table view] Category:Amendment
MONTHYEARCNL-24-004, Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13)2024-04-0404 April 2024 Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13) 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)2023-12-18018 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) 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-23-2023-09-20020 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 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)2023-08-0202 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) 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)2023-06-28028 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) ML23122A2322023-06-0707 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) 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 Sche2023-03-20020 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)2022-06-13013 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) 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)2020-07-27027 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) 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)2020-06-22022 June 2020 Application to Modify Watts Bar Nuclear Plant Unit 1 Technical Specifications 3.3.3, Post Accident Monitoring Instrumentation, (WBN-TS-19-23) 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)2020-01-17017 January 2020 Units 1 and 2, License Amendment Request to Revise Technical Specification 3.3.5, LOP DG Start Instrumentation, (WBN-TS-20-01) CNL-19-097, Non-Voluntary License Amendment Request to Correct Unbalanced Voltage Relay Instrumentation Values (TS-19-22)2019-10-23023 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)2019-10-10010 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)2017-12-27027 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) ML17321A0332017-11-16016 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) 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)2017-10-11011 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) 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)2017-10-11011 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-17-123, Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Revision 1, Clarification of Rod Position Requirements (WBN-TS-16-025)2017-09-29029 September 2017 Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Revision 1, Clarification of Rod Position Requirements (WBN-TS-16-025) 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 22017-05-0505 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 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)2015-07-15015 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) 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)2015-06-17017 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) CNL-14-218, Application to Modify Technical Specification 3.8.1 Regarding Diesel Generator Steady State Frequency (WBN-TS-13-08)2015-04-0606 April 2015 Application to Modify Technical Specification 3.8.1 Regarding Diesel Generator Steady State Frequency (WBN-TS-13-08) CNL-15-001, Application to Revise Technical Specification 4.2.1, Fuel Assemblies, (WBN-TS-15-03)2015-03-31031 March 2015 Application to Revise Technical Specification 4.2.1, Fuel Assemblies, (WBN-TS-15-03) ML14170A0462014-06-16016 June 2014 Attachment 2 - TS Bases Developmental Revision I Changes (Mark-Up) for WBN Unit 2 ML14170A0452014-06-16016 June 2014 Attachment 1 - TS Developmental Revision I Changes (Mark-Up) for WBN Unit 2 ML14170A0442014-06-16016 June 2014 Attachment 5 - WBN Unit 2 TS and Tsb Through Developmental Revision I, and Trm and Trmb Through Developmental Revision D ML11228A0472011-08-10010 August 2011 Technical Specifications (Developmental Revision F), Enclosure 1 ML1022900752010-08-16016 August 2010 Unit 2 - Change to Developmental TS Section 4.2.2, Control Rod Assemblies ML1005504472010-02-0202 February 2010 Developmental Revision B - Technical Specifications 3.0 - Limiting Condition for Operation (LCO) Applicability ML1005503672010-02-0202 February 2010 Developmental Revision B - Technical Specifications Table of Contents ML1005504012010-02-0202 February 2010 Developmental Revision B - Technical Specifications 1.0 - Use and Application ML1005504412010-02-0202 February 2010 Developmental Revision B - Technical Specifications 2.0 - Safety Limits ML1005504742010-02-0202 February 2010 Developmental Revision B - Technical Specifications 5.0 - Administrative Controls ML1005504492010-02-0202 February 2010 Developmental Revision B - Technical Specifications 3.1 - Reactivity Control Systems ML1005504712010-02-0202 February 2010 Developmental Revision B - Technical Specifications 4.0 - Design Features ML1005504642010-02-0202 February 2010 Developmental Revision B - Technical Specifications 3.9 - Refueling Operations ML1005504502010-02-0202 February 2010 Developmental Revision B - Technical Specifications 3.2 - Power Distribution Limits ML1005504512010-02-0202 February 2010 Developmental Revision B - Technical Specifications 3.3 - Instrumentation ML1005504532010-02-0202 February 2010 Developmental Revision B - Technical Specifications 3.4 - Reactor Coolant System ML1005504562010-02-0202 February 2010 Developmental Revision B - Technical Specifications 3.5 - Emergency Core Cooling Systems ML1005504582010-02-0202 February 2010 Developmental Revision B - Technical Specifications 3.6 - Containment Systems ML1005504622010-02-0202 February 2010 Developmental Revision B - Technical Specifications 3.8 - Electrical Power Systems ML1005504612010-02-0202 February 2010 Developmental Revision B - Technical Specifications 3.7 - Plant Systems ML0929503402009-10-20020 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 ML0913205622009-04-30030 April 2009 Application for Technical Specification Change to Correct Minor Error in Amendment 70 ML0900900442008-12-31031 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 ML0831708612008-11-12012 November 2008 License Amendment Request TS-08-11 to Revise Reactor Coolant System Leakage Detection Systems - Exigent Change Request ML0712106042007-04-25025 April 2007 (WBN) Unit 1 - Technical Specification Change 07-01, Revision of Number of Tritium Producing Burnable Absorber Rods (TPBARS) in the Reactor Core ML0616502672006-06-12012 June 2006 Technical Specifications (TS) Change WBN-TS-05-10 - Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity - Request for Additional Information ML0526500612005-09-20020 September 2005 T.S. for License Amendment, Regarding Alternative Means for Monitoring Control or Shutdown Rod Position 2024-04-04
[Table view] |
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Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-17-143 November 16, 2017 10 CFR 50.90 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 1 Facility Operating License No. NPF
-90 NRC Docket No. 50
-390 Watts Bar Nuclear Plant, Unit 2 Facility Operating License No. NPF
-96 NRC Docket No. 50-391
Subject:
Additional Supplement to Application to Revise Technical Specifications to Adopt TSTF
-547, Revision 1, "Clarification of Rod Position Requirements" (WBN-TS-16-025)
References:
- 1. TVA letter to NRC, CNL 148, "Application to Revise Technical Specifications to Adopt TSTF
-547, Revision 1, 'Clarification of Rod Position Requirements' (WBN
-TS-16-025)," dated November 23, 2016 (ML16335A179)
- 2. Technical Specification Task Force (TSTF) letter to NRC, "TSTF Comments on Draft Model Safety Evaluation of Traveler TSTF
-547, Revision 0, 'Clarification of Rod Position Requirements,' and Transmittal of TSTF-547, Revision 1, dated December 31, 2015 (ML15365A610)
- 3. NRC letter to TSTF, "Final Safety Evaluation of Technical Specifications Task Force Traveler TSTF
-547, Revision 1, 'Clarification of Rod Positon Requirements' (TAC N o. MF3570)," dated March 4, 2016 (ML16012A130 and ML15328A350)
- 4. TVA letter to NRC, CNL 123, "Supplement to Application to Revise Technical Specifications to Adopt TSTF
-547, Revision 1, "Clarification of Rod Position Requirements" (WBN
-TS-16-025)," dated September 29, 2017 (ML17272A955)
U. S. Nuclear Regulatory Commission CNL-17-143 Page 2 November 16, 2017 In Reference 1, the Tennessee Valley Authority (TVA) submitted a request for an amendment to the Technical Specifications (TS) for the Watts Bar Nuclear Plant (WBN), Units 1 and 2. The proposed amendment revises the requirements on control and shutdown rods, and rod and bank position indication in accordance wi th Technical Specification Task Force (TSTF)-547, Revision 1, "Clarification of Rod Position Requirements" (References 2 and 3). In Reference 4, TVA submitted a supplement to the license amendment request (LAR) to revise WBN Units 1 and 2 TS 3.1.6 and 3.1.7 to add the plant specific number of steps for control rod movement for consistency with WBN Units 1 and 2 SR 3.1.5.2. For completeness, this supplement contained all of the proposed changes to the WBN Units 1 and 2 TS and Bases and superseded those provided in Reference 1. On November 1, 2017, NRC informed TVA that some of the proposed TS changes in References 1 and 4 were not identified as changes in TSTF-547, Revision 1. For example , Required Action A.1.1 for TS 3.1.5 , " Rod Group Alignment Limits ," was changed from " Verify SOM 1.6% b.k/k" to "Verify SOM to be within the limits specified in the COLR." While this change is consistent with the Westinghouse Standard Technical Specifications (NUREG-141 , Revision 4), it was not identified as a change in the TSTF. TVA has entered this error into our corrective action program. TVA has compared the TS changes in Reference 4 to those in TSTF-547 , Revision 1 and is supplementing Attachment 1 to Reference 1 to address those TS changes that deviate from the TS changes in TSTF-547, Revision 1. The revised Attachment 1 to this submittal also includes the information in Reference 4 and supersedes the Attachment 1 in Reference 1. No further changes to the TS , as provided in Reference 4, are required. This response does not change the no significant hazards considerations determination contained in Reference 1. Attachment 2 contains the new regulatory commitment associated with this subm i ttal. Please address any questions regard i ng this request to Edward D. Schrull at (423) 751-3850. I declare under penalty of perjury that the foregoing is true and correct Executed on this 16th day of November 2017 . . Shea e President , Nuclear Regulatory Affairs and Support Services Attachments
- 1. Description and Assessment 2. New Regulatory Commitment cc: See Page 3 U. S. Nuclear Regulatory Commission CNL-17-143 Page 3 November 16, 2017 cc (Attachments
): NRC Regional Administrator - Region II NRC Senior Resident Inspector - Watts Bar Nuclear Plant NRC Project Manager - Watts Bar Nuclear Plant Director, Division of Radiological Health - Tennessee State Department of Environment and Conservation attachments)
ATTACHMENT 1 - DESCRIPTION AND ASSESSMENT CNL-17-143 A1-1 of 9
1.0 DESCRIPTION
The proposed amendment revises the requirements on control and shutdown rods, and rod and bank position indication in the Watts Bar Nuclear (WBN) Plant, Unit 1 and Unit 2 Technical Specification (TS) 3.1.5, "Rod Group Alignment Limits," TS 3.1.6, "Shutdown Bank Insertion Limits," TS 3.1.7, "Control Bank Insertion Limits," and TS 3.1.8, "Rod Position Indication
." The proposed amendment provide s time to repair rod movement failures that do not affect rod Operability, to provide time for analog position indication instruments to read accurately after rod movement, to correct conflicts between the TS, to eliminate an unnecessary action, and to increase consistency and to improve the presentation. 2.0 ASSESSMENT
2.1 Applicability
of Safety Evaluation The Tennessee Valley Authority (TVA) has reviewed the safety evaluation for Technical Specifications Task Force 547 (TSTF-547), Revision 1 provided to the TSTF in a letter dated March 4, 2016. This review included a review of the Nuclear Regulatory Commission (NRC) staff's evaluation, as well as the information provided in TSTF-547, Revision 1. As described in the subsequent paragraphs, TVA has concluded that the justifications presented in the TSTF-547, Revision 1 proposal and the safety evaluation prepared by the NRC staff are applicable to WBN Unit 1 and Unit 2, and justify this amendment for the incorporation of the changes to the WBN Unit 1 and Unit 2 TS. 2.2 Variations TVA is proposing the following minor variations from the TS changes described in TSTF-547, Revision
- 1. These variations do not affect the applicability of TSTF
-547, Revision 1 or the NRC staff's safety evaluation to the proposed license amendment.
- 1. The WBN Unit 1 and Unit 2 TS utilize different numbering than the Standard Technical Specifications on which TSTF
-547, Revision 1 was based. The following table summarizes the differences between the WBN Unit 1 and Unit 2 TS numbering and the TSTF
-547, Revision 1 numbering.
TSTF-547, Rev.
1 WBN Unit 1 WBN Unit 2 TS 3.1.4, "Rod Group Alignment Limits" TS 3.1.5, "Rod Group Alignment Limits" TS 3.1.5, "Rod Group Alignment Limits" TS 3.1.5, "Shutdown Bank Insertion Limits" TS 3.1.6, "Shutdown Bank Insertion Limits" TS 3.1.6, "Shutdown Bank Insertion Limits" TS 3.1.6, "Control Bank Insertion Limits" TS 3.1.7, "Control Bank Insertion Limits" TS 3.1.7, "Control Bank Insertion Limits" TS 3.1.7, "Rod Position Indication" TS 3.1.8, "Rod Position Indication" TS 3.1.8, "Rod Position Indication" ATTACHMENT 1 - DESCRIPTION AND ASSESSMENT CNL-17-143 A1-2 of 9 The use of different numbering does not affect the applicability of TSTF-547, Revision 1 to the WBN Unit 1 and Unit 2 TS. 2. TSTF-547, Revision 1, TS 3.1.7, "Rod Position Indication," Required Actions A.1 and C.1 discuss indirect verification of rod position by using movable incore detectors when the rod position indication system is inoperable. As described in Section 7.7.1.9 of the WBN Dual Unit Updated Final Safety Analysis Report, WBN Unit 1 and Unit 2 have a power distribution monitoring system (PDMS) that can be utilized to obtain a three
-dimensional power distribution measurement to indirectly provide rod position verification.
WBN Unit 1 has the ability to indirectly verify rod position utilizing either a movable incore system or the PDMS (References 1 and 2). WBN Unit 2 uses the fixed incore system as input to PDMS to indirectly verify rod position (Reference 3). Accordingly, the proposed WBN Unit 1 and Unit 2 TS 3.1.8, "Rod Positon Indication" and associated TS Bases refer to utilizing the PDMS or moveable incore detectors for WBN Unit 1 and the PDMS for WBN Unit 2 in order to provide indirect verification of rod position for an inoperable rod indicator.
TVA has determined that the variation from TSTF
-547 to continue allowing the use of the PDMS to indirectly verify rod position does not affect the applicability of TSTF-547, Revision 1 to the WBN Unit 1 and Unit 2 TS. 3. TSTF-547, Revision 1, Surveillance Requirement (SR) 3.1.4.3 contains a value for Tavg of 500 o F, whereas the current WBN value (in SR 3.1.5.3) is 551 o F. The temperature of 551 oF represents a WBN Unit 1 plant-specific historical artifact of the licensing evolution process as the WBN Unit 1 TS transitioned from NUREG
-0452, Revision 4 to NUREG
-1431, Revision 0 (t he Westinghouse Standard Technical Specifications), which kept the value at 551 oF. The SR to demonstrate rod drop time was initially based on performing the test with all reactor coolant pumps operating oF to simulate a reactor trip under actual conditions. WBN Unit 2 also specifies the 551 oF temperature.
TVA has determined that the variation of the temperature specified in SR 3.1.4.3 (TVA proposed SR 3.1.5.3) is consistent with the current licensing basis of the plants and does not affect the applicability of TSTF
-547, Revision 1 to the WBN Unit 1 and Unit 2 TS. 4. Incorporation of specific WBN minor format variations:
Indentation of "
OR" between TS 3.1.5, Required Action B.1.1 and B.1.2.
Addition of the word "overlap" in TS 3.1.7, Required Action A.3, which was inadvertently left out of the TSTF
-547 template. Note that the word "overlap" is correctly contained in and consistent with Limiting Condition for Operation (LCO) 3.1.7, TS 3.1.7 Conditions A.
and C., TS 3.1.7 Required Action C.2, and SR 3.1.7.3. These differences are administrative and do not affect the applicability of TSTF
-547, Revision 1 to the WBN Unit 1 and Unit 2 TS.
ATTACHMENT 1 - DESCRIPTION AND ASSESSMENT CNL-17-143 A1-3 of 9 5. The proposed changes to the TS pages for Condition A of WBN Unit 1 and Unit 2 TS 3.1.6 and TS 3.1.7 replace the bracketed with "inserted 10 steps." As noted in TSTF-547, Revision 1, and the NRC Safety Evaluation (Reference 4), the number 16 is bracketed and it is to be replaced with the "plant
-specific minimum number of steps that the rods must be moved to perform SR 3.1.5.2." As noted in Item 1, TS 3.1.4 in TSTF
-547, Revision 1 corresponds to WBN Units 1 and 2 TS 3.1.5. Correspondingly, WBN Units 1 and 2 SR 3.1.5.2 states "Verify rod freedom of movement (trippability) by moving each rod not fully Therefore, the proposed changes to WBN Unit 1 and Unit 2 TS 3.1.6 and 3.1.7 are consistent with WBN Units 1 and 2 SR 3.1.5.2. As noted in the Bases for WBN Units 1 and 2 SR 3.1.5.2, "Moving each control rod by 10 steps will not cause radial or axial power tilts, or oscillations, to occur." The number of steps in WBN Units 1 and 2 SR 3.1.5.2 is also consistent with SR 3.1.4.2 in the Westinghouse Standard TS (STS) in NUREG-1431, Revision 4, "Standard Technical Specifications Westinghouse Plants."
- 6. The following TS changes are consistent with the Westinghouse STS, but are not identified as changes in TSTF
-547, Revision 1. WBN 1 and 2 TS Description of Change Justification
3.1.5 Limiting
Condition for Operation (LCO) Changed "All shutdown and control rods shall be OPERABLE., with all individual indicated rod positions within 12 steps of their group step counter demand position" to
"All shutdown and control rods shall be OPERABLE AND Individual indicated rod positions shall be within 12 steps of their group step counter demand position" This change is consistent with the Westinghouse STS and is editorial in nature to clarify the applicability of the LCO.
3.1.5, Condition A Changed "one or more rod(s) untrippable" to "one or more rod(s) inoperable" This change is consistent with the Westinghouse STS and TSTF-9-A, Revision 1
. 3.1.5, Required Action B.4 Added SR 3.2.1.2 This change is consistent with the Westinghouse STS and the current WBN TS Bases B3.1.5, Actions B.2.2, B.2.3, B.2.4, B.2.5, and B.2.6.
ATTACHMENT 1 - DESCRIPTION AND ASSESSMENT CNL-17-143 A1-4 of 9 WBN 1 and 2 TS Description of Change Justification 3.1.5, Required Actions A.1.1, B.1.1, B.3, and D.1.1 3.1.6, Required Action B.1.1 3.1.7, Required Actions B1.1 and C.1.1 " was changed to "Verify SDM to be within the limits specified in the Core Operating Limits Report (COLR)." This change is consistent with the Westinghouse STS and TSTF-9-A, Revision 1, "Relocate value for shutdown margin to COLR" (Reference 5
), which was approved by NRC in Reference 6.
The COLR process reduces the burden on the licensees and the NRC from processing changes to cycle-specific parameter limits in TSs for each fuel cycle, provided the limits are developed using an NRC approved methodology. TVA will revise the COLR for WBN Units 1 and 2 to relocate the shutdown margin (SDM) limits in the following Technical Specifications to the COLR:
3.1.5, "Rod Group Alignment Limits" 3.1.6, "Shutdown Bank Insertion Limits" 3.1.7, "Control Bank Insertion Limits" SR 3.1.5.3 Revised the frequency from "Prior to reactor criticality after initial fuel loading and each removal of the reactor head" to "Prior to criticality after each removal of the reactor head" This change is consistent with the Westinghouse STS. Initial fuel loading has been completed for WBN Units 1 and 2.
ATTACHMENT 1 - DESCRIPTION AND ASSESSMENT CNL-17-143 A1-5 of 9 WBN 1 and 2 TS Description of Change Justification 3.1.6 The Applicability Statement was revised from:
"MODE 1, MODE 2 with any control bank not fully inserted."
to "MODES 1 and 2" This change is consistent with the Westinghouse STS and TSTF-239-A, Revision 0, "Correct shutdown bank insertion limits applicability" (Reference 7)
. As noted in TSTF
-239, "NUREG
-1431, LCO 3.1.6, Shutdown Bank Insertion Limits, is applicable in Mode 1 and Mode 2 with any control bank not fully inserted. Since the reactor must be critical to be in Mode 2 and the control banks must be withdrawn to be critical, the qualification on the Mode 2 Applicability is meaningless and confusing.
Therefore, the Applicability is changed to simply
'Mode 1 and Mode 2.' This does not result in any actual change to the requirements but simplifies the specifications. Appropriate Bases changes were also made."
SR 3.1.6.1 (Unit 1 only)
The surveillance was revised to add "insertion" between "the" and "limits" This is change is consisten t with the WBN Unit 2 TS and the Westinghouse STS
. 3.1.7, Required Action D.1 Revised "Be in MODE 3" to "Be in MODE 2 with keff < 1.0." This change is consisten t with the current Applicability Statement for TS 3.1.7 and the Westinghouse STS. Therefore, TVA is not proposing any significant variations or deviations from the TS changes described in TSTF
-547, Revision 1 or the applicable parts of the NRC staff's Safety Evaluation.
The Traveler and safety evaluation discuss the applicable regulatory requirements and guidance, including the 10 CFR 50, Appendix A, General Design Criteria (GDC). WBN Unit 1 and Unit 2 were designed to meet the intent of the "Proposed General Design Criteria for Nuclear Power Plant Construction," published for comment in the Federal Register on July 11, 1967 (32 FR 10213). The WBN Unit 1 and Unit 2 construction permit was issued in January 1973. UFSAR Section 3.1, "Conformance with NRC General Design Criteria,"
addresses the NRC General Design Criteria published as Appendix A to 10 CFR 50 in July 1971, including Criterion 4 as amended October 27, 1987. This difference does not alter the conclusion that the proposed change is applicable to WBN Unit 1 and Unit
- 2.
ATTACHMENT 1 - DESCRIPTION AND ASSESSMENT CNL-17-143 A1-6 of 9
3.0 REGULATORY ANALYSIS
3.1 No Significant Hazards Consideration Analysis TVA requests adoption of TSTF-547, Revision 1, "Clarification of Rod Position Requirements," which is an approved change to the Standard Technical Specifications, into the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications (TS). The proposed change revises the requirements on control and shutdown rods, and rod and bank position indication to provide time to repair rod movement failures that do not affect rod Operability, to provide time for analog position indication instruments to read accurately after rod movement, to correct conflicts between the TS, to eliminate an unnecessary action, and to increase consistency and to improve the presentation.
TVA has evaluated whether or not a significant hazards consideration is involved with the proposed amendment(s) by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below:
- 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No Control and shutdown rods are assumed to insert into the core to shut down the reactor in evaluated accidents. Rod insertion limits ensure that adequate negative reactivity is available to provide the assumed shutdown margin (SDM). Rod alignment and overlap limits maintain an appropriate power distribution and reactivity insertion profile.
Control and shutdown rods are initiators to several accidents previously evaluated, such as rod ejection. The proposed change does change the limiting conditions for operation for the rods and makes technical changes to the Surveillance Requirements (SRs) governing the rods. However, the proposed change has no significant effect on the probability of any accident previously evaluated.
Revising the TS Actions to provide a limited time to repair rod movement control has no effect on the SDM assumed in the accident analysis as the proposed Action require verification that SDM is maintained.
The effects on power distribution will not cause a significant increase in the consequences of any accident previously evaluated as all TS requirements on power distribution continue to be applicable.
Revising the TS Actions to provide an alternative to frequent use of the moveable incore detector system to verify the position of rods with inoperable rod position indicator does not change the requirement for the rods to be aligned and within the insertion limits. Therefore, the assumptions used in any accidents previously evaluated are unchanged and there is no significant increase in the consequences.
ATTACHMENT 1 - DESCRIPTION AND ASSESSMENT CNL-17-143 A1-7 of 9 The consequences of an accident that might occur during the 1-hour period provided for the analog rod position indication to stabilize after rod movement are no different than the consequences of the accident under the existing actions with the rod declared inoperable.
The proposed change to resolve the conflicts in the TS ensure that the intended Actions are followed when equipment is inoperable. Actions taken with inoperable equipment are not assumptions in the accidents previously evaluated and have no significant effect on the consequences.
The proposed change to eliminate an unnecessary action has no effect on the consequences of accidents previously evaluated as the analysis of those accidents did not consider the use of the action.
The proposed change to increase consistency within the TS has no effect on the consequences of accidents previously evaluated as the proposed change clarifies the application of the existing requirements and does not change the intent. Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed amendment create the possibility of a new or different kind of accident from any previously evaluated?
Response: No The proposed change does not involve a physical alteration of the plant (i.e., no new or different type of equipment will be installed).
The change does not alter assumptions made in the safety analyses. The proposed change does alter the limiting conditions for operation for the rods and makes technical changes to the SRs governing the rods.
However, the proposed change to actions maintains or improves safety when equipment is inoperable and does not introduce new failure modes. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.
- 3. Does the proposed amendment involve a significant reduction in a margin of safety? Response: No The proposed change to allow time for rod position indication to stabilize after rod movement and to allow an alternative method of verifying rod position has no effect on the safety margin as actual rod position is not affected. The proposed change to provide time to repair rods that are Operable but immovable does not result in a significant reduction in the margin of safety because all rods must be verified to be Operable, and all other banks must be within the insertion limits. The remaining proposed changes to make the requirements internally consistent and to eliminate unnecessary actions do not affect the margin of safety as the changes do not affect th e ability of the rods to perform their specified safety function.
ATTACHMENT 1 - DESCRIPTION AND ASSESSMENT CNL-17-143 A1-8 of 9 Therefore, the proposed change does not involve a significant reduction in a margin of safety. Based on the above, TVA concludes that the proposed change presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.
3.2 Conclusions
In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
4.0 ENVIRONMENTAL
EVALUATION The proposed change would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or would change an inspection or surveillance requirement.
However, the proposed change does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed change meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed change.
5.0 REFERENCES
- 1. NRC letter to TVA, "Watts Bar Nuclear Plant Unit 1 - Issuance of Amendment Regarding the Application to Implement BEACON Core Power Distribution and Monitoring System (TAC No. ME1698)," dated October 27, 2009 (ML092710381)
- 2. NRC letter to TVA, "Watts Bar Nuclear Plant Unit 1 - Issuance of Amendment Regarding Alternate Means for Monitoring Control or Shutdown Rod Positions (TAC No. MC1419) (WBN
-TS-03-12)," dated September 20, 2005 (ML052300162)
- 3. Watts Bar Nuclear Plant Unit 2, Technical Specification 3.1.8, "Rod Positon Indication," Facility Operating License No.
NPF-96, dated October 22, 2015 (ML15251A587)
- 4. NRC letter to TSTF, "Final Safety Evaluation of Technical Specifications Task Force Traveler TSTF
-547, Revision 1, 'Clarification of Rod Positon Requirements' (TAC No. MF3570)," dated March 4, 2016 (ML16012A130 and ML15328A350)
- 5. TSTF-9-A, Revision 1, "Relocate value for shutdown margin to COLR," dated January 8, 1996 (ML040400130)
- 6. NRC letter to Nuclear Energy Institute dated September 27, 1996 (Legacy Accession Number 9610030183)
ATTACHMENT 1 - DESCRIPTION AND ASSESSMENT CNL-17-143 A1-9 of 9 7. TSTF-239-A, Rev. 0, "Correct shutdown bank insertion limits applicability," dated February 5, 1998 (ML040611057)
ATTACHMENT 2 New Regulatory Commitment CNL-17-143 A2-1 of 1 Commitment Due Date/Event TVA will revise the Core Operating Limits Report (COLR) for WBN Units 1 and 2 to relocate the shutdown margin (SDM) limits in the following Technical Specifications to the COLR:
3.1.5, "Rod Group Alignment Limits" 3.1.6, "Shutdown Bank Insertion Limits" 3.1.7, "Control Bank Insertion Limits" Within 60 days following NRC approval of License Amendment Request WBN-TS-16-025 (TVA letters CNL-16-148 and CNL-17-123)