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Category:Letter
MONTHYEARML23319A2452024-01-29029 January 2024 Issuance of Amendment Nos. 366 and 360; 164 and 71 Regarding the Adoption of TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues ML24008A2462024-01-18018 January 2024 Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions CNL-24-016, Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-01-10010 January 2024 Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-23-052, Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability2024-01-0909 January 2024 Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability CNL-23-062, Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018)2024-01-0808 January 2024 Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018) ML23346A1382024-01-0303 January 2024 Regulatory Audit Summary Related to Request to Increase the Number of Tritium Producing Burnable Absorber Rods CNL-23-069, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000390/20234412023-12-21021 December 2023 Plantfinal Significance Determination for a Security-Related Greater than Green Finding, Nov, and Assessment Follow-up, 05000390-2023441 and 05000391-2023441-Public 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) IR 05000390/20234042023-12-14014 December 2023 Security Baseline Inspection Report 05000390/2023404 and 05000391/2023404 CNL-23-001, Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01)2023-12-13013 December 2023 Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01) ML23293A0572023-12-0606 December 2023 Issuance of Amendment Nos. 163 and 70 Regarding Adoption of TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control IR 05000390/20230102023-11-30030 November 2023 RE-Issue Watts Bar Nuclear Plant - Biennial Problem Identification and Resolution Inspection Report 050000390/2023010 and 05000391/2023010 and Apparent Violation CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000390/20230032023-11-13013 November 2023 Integrated Inspection Report 05000390/2023003 and 05000391/2023003 and Apparent Violation ML23312A1432023-11-0808 November 2023 Submittal of Dual Unit Updated Final Safety Analysis Report (UFSAR) Amendment 5 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-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision ML23251A2002023-09-11011 September 2023 Request for Withholding Information from Public Disclosure for Watts Bar Nuclear Plant, Units 1 and 2 CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 642023-09-0505 September 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 64 IR 05000390/20230052023-08-30030 August 2023 Updated Inspection Plan for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390/2023005 and 05000391/2023005 ML23233A0042023-08-28028 August 2023 Proposed Alternative to the Requirements of the ASME Boiler and Pressure Vessel Code for Upper Head Injection Dissimilar Metal Butt Welds IR 05000390/20230022023-08-16016 August 2023 Reissue - Watts Bar Nuclear Plant - Integrated Inspection Report 05000390/2023002 and 05000391/2023002 ML23220A1582023-08-0909 August 2023 Integrated Inspection Report 05000390/2023002 and 05000391/2023002 CNL-23-045, License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts (WBN-TS-23-010)2023-08-0707 August 2023 License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts (WBN-TS-23-010) 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) ML23192A4472023-07-31031 July 2023 Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information CNL-23-055, Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills2023-07-25025 July 2023 Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills IR 05000390/20230112023-07-24024 July 2023 Quadrennial Focused Engineering Inspection (FEI) Commercial Grade Dedication Report 05000390 2023011 and 05000391 2023011 CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions 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) CNL-23-049, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan .2023-06-26026 June 2023 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan . 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-23-044, Transmittal of Revision 3 to WCAP-18774-P and WCAP-18774-NP, Addendum to the Rotterdam Dockyard Company Final Stress Report for 173 P.W.R. Vessels TVA III & IV (Report No. 30749-B-030, Rev. 3) - Evaluation of One Closure Stud Out2023-06-0101 June 2023 Transmittal of Revision 3 to WCAP-18774-P and WCAP-18774-NP, Addendum to the Rotterdam Dockyard Company Final Stress Report for 173 P.W.R. Vessels TVA III & IV (Report No. 30749-B-030, Rev. 3) - Evaluation of One Closure Stud Out IR 05000390/20234032023-05-30030 May 2023 Cyber Security Inspection Report 05000390/2023403 and 05000391/2023403 ML23131A1812023-05-23023 May 2023 Correction to Amendment No. 161 to Facility Operating License No. NPF-90 CNL-23-042, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-05-16016 May 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000390/20220032023-05-0909 May 2023 Reissue Watts Bar Nuclear Plant - Integrated Inspection Report 05000390/2022003 and 05000391/2022003 ML23125A2202023-05-0505 May 2023 Issuance of Amendment No. 161 Regarding a Change to Footnotes for Technical Specification Table 1.1-1 Modes (Emergency Circumstances) IR 05000390/20230012023-05-0404 May 2023 Integrated Inspection Report 05000390/2023001 and 05000391/2023001 CNL-23-043, Emergency License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes (WBN-TS-23-09)2023-05-0404 May 2023 Emergency License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes (WBN-TS-23-09) CNL-23-032, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 412023-04-27027 April 2023 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 41 CNL-23-030, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2023-04-27027 April 2023 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-23-033, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-04-24024 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision CNL-23-029, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-04-11011 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML23072A0652023-04-0505 April 2023 Units 1 and 2 Issuance of Amendment Nos. 364 and 358; 160 and 68 Regarding a Revision to Technical Specification 3.4.12 ML23073A2762023-04-0303 April 2023 Individual Notice of Consideration of Issuance of Amendments to Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing (EPID L-2023-LLA-0029) (Letter) CNL-23-023, Annual Insurance Status Report2023-03-30030 March 2023 Annual Insurance Status Report CNL-23-024, TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report2023-03-29029 March 2023 TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report 2024-01-09
[Table view] Category:Technical Specification
MONTHYEARCNL-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 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 ML13357A0542013-12-12012 December 2013 Technical Specifications Bases 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 ML12065A0352012-02-28028 February 2012 Watts Bar, Unit 2 - Technical Specifications Table of Contents Through Page B 3.9-32 ML12065A0362012-02-28028 February 2012 Submittal of Developmental Revision G of the Unit 2 Technical Specification (TS) and Technical Specification Bases 2023-09-20
[Table view] Category:Bases Change
MONTHYEARWBL-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-23-002, 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 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-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 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) ML17306A8022017-11-0202 November 2017 Periodic Submission for Changes Made to the WBN Technical Specification Bases and Technical Requirements Manual 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 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 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-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 ML13357A0542013-12-12012 December 2013 Technical Specifications Bases ML13353A4782013-12-12012 December 2013 Fuel Handling Accident Dose Analysis Final Safety Analysis Report and Technical Specification Revision 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 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 ML12065A0352012-02-28028 February 2012 Watts Bar, Unit 2 - Technical Specifications Table of Contents Through Page B 3.9-32 ML12065A0362012-02-28028 February 2012 Submittal of Developmental Revision G of the Unit 2 Technical Specification (TS) and Technical Specification Bases ML11321A3082011-11-14014 November 2011 Changes Made to the Technical Specification Bases ML11228A0482011-08-10010 August 2011 Technical Specifications Bases (Developmental Revision F), Enclosure 2 ML11227A2562011-08-10010 August 2011 Application to Modify Watts Bar Nuclear Plant, Unit 1, Technical Specifications in Support of Watts Bar Nuclear Plant, Unit 2, Testing and Operation (TS-WBN-11-02) ML1104905702011-02-16016 February 2011 Supplemental Information for Review of Developmental Revision a of the Unit 2 Technical Specifications (TS) and Technical Specifications Bases (TS Bases) ML1015400652010-05-28028 May 2010 Technical Specifications Change WBN-TS-10-05 - Control Rod Assemblies ML1011701482010-04-20020 April 2010 Changes Made to the Technical Specification Bases ML1005506002010-02-0202 February 2010 Developmental Revision B - Technical Specifications Bases B 3.9 - Refueling Operations ML1005504822010-02-0202 February 2010 Developmental Revision B - Technical Specifications Bases B 2.0 - Safety Limits ML1005505972010-02-0202 February 2010 Developmental Revision B - Technical Specifications Bases B 3.8 - Electrical Power Systems ML1005505942010-02-0202 February 2010 Developmental Revision B - Technical Specifications Bases B 3.7 - Plant Systems ML1005505902010-02-0202 February 2010 Developmental Revision B - Technical Specifications Bases B 3.6 - Containment Systems ML1005505052010-02-0202 February 2010 Developmental Revision B - Technical Specifications Bases B 3.4 - Reactor Coolant System ML1005504972010-02-0202 February 2010 Developmental Revision B - Technical Specifications Bases B 3.2 - Power Distribution Limits ML1005504882010-02-0202 February 2010 Developmental Revision B - Technical Specifications Bases B 3.0 - Limiting Condition for Operation (LCO) Applicability ML1005504782010-02-0202 February 2010 Developmental Revision B - Technical Specifications Bases, Table of Contents ML1005505012010-02-0202 February 2010 Developmental Revision B - Technical Specifications Bases B 3.3 - Instrumentation ML1005505372010-02-0202 February 2010 Developmental Revision B - Technical Specifications Bases B 3.5 - Emergency Core Cooling Systems ML1005504942010-02-0202 February 2010 Developmental Revision B - Technical Specifications Bases B 3.1 - Reactivity Control Systems ML0919401912009-07-0909 July 2009 Watts, Unit 1 - Technical Specifications Change - Core Power Distribution Monitoring System. ML0916100682009-06-0505 June 2009 Change to TS 3.6.3, Containment Isolation Valves, Regarding Position Verification Requirements (TSTF-269-A, TSTF-45-A, and TSTF-440-A) ML0826610312008-09-22022 September 2008 Changes Made to the WBN Technical Specification Bases and Technical Requirements Manual ML0826703612008-09-18018 September 2008 Unit 1 - License Amendment (TS-08-09) to Revise the Technical Specifications (Ts), Bases and Updated Final Safety Analysis Report (UFSAR) for the Unit 2 Vital Inverters ML0826705432008-09-18018 September 2008 Technical Specification (TS) Change No. 08-07, Auxiliary Feedwater Auto-Start Upon Trip of the Turbine Driven Main Feedwater Pumps ML0821800932008-08-0101 August 2008 Watt'S Bar, Unit 1, Technical Specifications Change - Revision of Boron Requirements for Cold Leg Accumulators and Refueling Water Storage Tank. 2023-03-20
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{{#Wiki_filter:Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 SEP 2 3 2004 WBN-TS-04-013 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Gentlemen:
In the Matter of ) Docket No.50-390 Tennessee Valley Authority WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 - TECHNICAL SPECIFICATION (TS) CHANGE NO. 04-013 - AUXILIARY FEEDWATER (AFW) START UPON TRIP OF TURBINE DRIVEN MAIN FEEDWATER (TDMFW) PUMPS Pursuant to 10 CFR 50.90, TVA is submitting a request for a TS change (WBN-TS-04-013) to license NPF-90 for WBN Unit 1. The proposed TS change revises Limiting Condition for Operation (LCO) 3.3.2 (6)(e) to allow the AFW Start upon Trip of TDMFW Pump function to be required only when the one or more of TDMFW Pumps are operating. This function is an anticipatory circuit which provides early actuation of the AFW system but it is not a safety-related function. Current TS requires this function to be operable prior to adequate steam being available to run the TDMFW pumps. By making the proposed change, this trip function can be made operable later in the unit startup timeline resulting in additional time to spread a number of activities, which prepare the MFW pumps for operation, over a longer duration minimizing the potential for human performance errors.
P-ed roncydpaw
U.S. Nuclear Regulatory Commission Page 2 SEP 2 3 2004 to this letter provides the description and evaluation of the proposed change. TVA has determined that the proposed change does not involve a significant hazards consideration, and the TS change qualifies for a categorical exclusion from environmental review pursuant to the provisions of 10 CFR 51.22(c)(9). Additionally, in accordance with 10 CFR 50.91(b)(1), TVA is sending a copy of this letter and attachments to the Tennessee State Department of Public Health. contains copies of the appropriate TS pages marked-up to show the proposed change. Enclosure 3 contains the updated TS pages with the proposed change incorporated. provides, for information only, the marked-up TS Bases page B 3.3-93 associated with this proposed change.
TVA requests approval of this amendment as soon as practical in support of the Spring 2005 Cycle 6 Refueling Outage. Further, TVA requests that implementation of the revised TS be prior to entering Mode 2 following the refueling outage. TVA is prepared to meet with the Staff if necessary, to facilitate the NRC's review.
No commitments are made by this letter. If you have any questions about this change, please contact me at (423) 365-1824.
I declare under penalty of perjury that the foregoing is true and correct. Executed on 23th day of September 2004.
Sincerely, P. L. Pace Manager, Site Licensing and Industry Affairs
Enclosures:
- 1. TVA's Evaluation of the Proposed Change
- 2. Proposed Technical Specification Change (Marked-up)
- 3. Proposed Technical Specification Change (Retyped)
- 4. Proposed Technical Specification Bases Change (Marked-up) cc: See page 3
U.S. Nuclear Regulatory Commission Page 3 SEP 2 3 2004 cc (Enclosures):
NRC Resident Inspector Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381 Mr. R. J. Pascarelli, Project Manager U.S. Nuclear Regulatory Commission MS 07A15 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738 U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 Mr. Lawrence E. Nanney, Director Division of Radiological Health Third Floor L&C Annex 401 church Street Nashville, Tennessee 37243-1532
ENCLOSURE 1 TENNESSEE VALLEY AUTHORITY (TVA)
WATTS BAR NUCLEAR PLANT (WBN)
UNIT 1 TVA EVALUATION OF PROPOSED CHANGE
1.0 DESCRIPTION
This proposed Technical Specification (TS) change will revise Limiting Condition for Operation (LCO) 3.3.2 (6)(e) to allow Auxiliary Feedwater (AFW) start upon trip of Turbine Driven Main Feedwater (TDMFW) Pump function to be required only when one or more of TDMFW pumps are operating. This proposed change will also require a clarification to the TS Bases section 3.3.2 to describe this arrangement.
The AFW start function is an anticipatory circuit which provides early actuation of the AFW system but it is not a safety-related function. Current TS requires this function to be operable upon entry into Mode 1 or 2 which is prior to adequate steam being available to run the TDMFW pumps. This proposed change will allow the trip function to be made operable at a later time which will eliminate additional work for plant maintenance upon plant startup and decrease the duration of plant outages.
2.0 PROPOSED CHANGE
This proposed TS change will modify the mode applicability for function 6(e) of TS Table 3.3.2-1. Specifically, a footnote will be added to the applicable modes for this function, to clarify that this function is only required in Modes 1 and 2 when one or more TDMFW Pumps are operating. Enclosure 2 provides the TS page mark-up of these changes.
3.0 BACKGROUND
The safety-related AFW system supplies feedwater to the steam generators in the event of a loss of MFW to remove reactor decay heat and avoid reactor coolant system over pressurization. Upon startup at WBN, a motor driven Standby Main Feedpump is primarily used for plant startup when sufficient steam is not yet available to supply the TDMFW pumps. The standby pump is also available to supplement the two TDMFW pumps designed for normal operation.
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Each TDMFW pump is equipped with one pressure switch on the control oil line for the speed control system. A low pressure signal from this pressure switch indicates a trip of that pump and a trip of both TDMFW pumps starts the motor driven and turbine driven AFW pumps. LCO function 3.3.2,(6)(e) requires the automatic start of the AFW system on trip of both TDMFW pumps to be operable during modes 1 and 2.
Typically, during plant refueling outages, one of the main feedwater pump turbines is disassembled to perform periodic preventative maintenance. This work requires the removal of sensitive instrumentation to prevent damage to these instruments while the pump is undergoing full disassembly. Near the end of outage when the pump is being reassembled, a number of activities need to be completed within a short duration including the replacement of the sensitive instrumentation. In conjunction with oil pump flushing, these instruments require calibration prior to testing of the entire MFW pump turbine.
During plant startup and up to approximately 18 percent load, the motor driven Standby Main Feedwater Pump (SBMFP) is normally used instead of the TDMFW pumps as sufficient steam is not yet available. Once steam is established, the main feedwater pumps are placed into operation. It is also important to note that in the unlikely event that the SBMFP trips, in addition to autostart of AFW upon Steam Generator Lo-Lo Level, AFW can be manually started to supply the required necessary feedwater and continue with plant startup until sufficient steam is generated for the TDMFW pump's supply.
As stated above currently the AFW Start upon Trip of Main Feedwater Pump function for the both pumps must be operable during this time to satisfy LCO 3.3.2 (6)(e) even though the MFW pumps are not running. This proposed TS change will revise this LCO to allow this function to be required only when one or more of the TDMFW pumps are operating. Thus, this will provide the time from initial entry into Mode 2 until approximately 18 percent power when the TDMFW pumps are placed into operation to accomplish the previously described work activities.
In summary, by making the proposed change, this trip function can be made operable later in the unit startup timeline resulting in additional time to spread a number of activities, which prepare the TDMFW pumps for operation over a longer duration, minimizing the potential for human performance errors.
4.0 TECHNICAL ANALYSIS
LCO 3.3.2,(6)(e) is an anticipatory function which provides early actuation of the AFW system but it is not a safety-related function. Steam generator low-low level or a safety injection (SI) signal are the safety related signals credited for actuating E1-2
the AFW system during an accident. The TDMFW pump oil pressure switches, which indicate a trip of their respective pump, are non-quality related and there is no redundancy for this function (i.e., only one switch per pump). This proposed TS change will only change this function during mode 2 and the part of mode 1 where both TDMFW pumps are not operating (less than 18 percent load). During startup, the plant is being monitored very closely and the need for AFW is less than at full power. If the SBMFP should trip during this time, the AFW system would be started automatically by a low-low steam generator level signal or by operator manual initiation.
The loss of one TDMFW pump during normal operation (100 percent power) will cause automatic start of the SBMFP, isolation of the condensate flow through the tripped main feed pump turbine's condenser, and main turbine runback to below 85 percent unit load. This results in feedwater flow being restored to the steam generators within 20 seconds of the loss of one TDMFW Pump which prevents a reactor trip due to low steam generator level. During this scenario, the auto start circuit for the AFW system is half made up and should the other TDMFW Pump trip, AFW start will actuate.
The design basis events, which impose AFW safety function requirements, are loss of normal MFW, main feedline or main steamline break, loss of offsite power, loss of coolant accident, and small break loss of coolant accident. These accident evaluations assume actuation of AFW occurring due to low-low steam generator level or a safety injection signal. Start of AFW due to trip of the TDMFW pumps has not been credited in either the transient or accident analyses.
In summary, start of AFW due to trip of both TDMFW pumps is required by TS LCO 3.3.2 (6)(e) but it is not a safety related feature and is not credited in either transient or accident analyses. This proposed TS change will only require AFW automatic start on trip of both TDMFW pumps during modes 1 and 2 when the TDMFW pumps are operating. In the unlikely event that SBMFP trips during plant startup, the AFW system will still have automatic start due to a low-low steam generator level signal or the operator can manually initiate AFW and continue startup until such time as steam would be available to start one of the TDMFW pumps.
5.0 REGULATORY SAFETY ANALYSIS 5.1 No Significant Hazards Consideration The proposed Technical Specification (TS) change will modify the mode applicability for function (6)(e) of TS Table 3.3.2-1.
Specifically, a footnote will be added to the applicable modes for this function, to clarify that the Auxiliary Feedwater (AFW) start function upon trip of the Turbine Driven Main Feedwater (TDMFW) pumps is only required in Modes 1 and 2 when E1-3
one or more TDMFW Pumps are operating. TVA has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below:
- 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
The design basis events which impose AFW safety function requirements are loss of normal main feedwater, main feedline or main steamline break, loss of offsite power, loss of coolant accident, and small break loss of coolant accident. These accident evaluations assume actuation of AFW occurring due to low-low steam generator level or a safety injection signal. These signals are required safety related features unlike start-up of the AFW pumps due to the trip of both TDMFW pumps which is an anticipatory function and not required for either transient or accident analyses.
Requiring this function only when the TDMFW pumps are running will not impact any previously evaluated design basis events. Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No.
This TS change involves the automatic start of the AFW pumps when the TDMFW Pumps trip. This change involves a function that is not a safety related feature and, therefore, is not credited in either transient or accident analyses. Since this change only affects the point at which this trip function needs to be operable and does not affect the function that actuates AFW due to low-low steam generator level or a safety injection signal, it will not be an initiator to a new or different kind of accident from any accident previously evaluated.
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- 3. Does the proposed change involve a significant reduction in margin of safety?
Response: No.
This TS change involves the automatic start of the AFW pumps when the TDMFW pumps trip which is not a safety related plant function. This change does not change any values or limits involved in a safety related function. Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Based on the above, TVA concludes that the proposed amendment does not involve a 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.
5.2 Applicable Regulatory Requirements/Criteria Regulatory requirements and criteria applicable to the design bases for the AFW system are provided in the WBN UFSAR Section 10.4.9, "Auxiliary Feedwater System," and WBN System Description N3-3B-4002, "Auxiliary Feedwater System." Included in these are General Design Criteria (GDC) of 10 CFR 50 Appendix A, GDC 34, "Residual Heat Removal" and NRC Standard Review Plan (SRP)-10.4.9, "Auxiliary Feedwater System (PWR)."
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.
6.0 ENVIRONMENTAL CONSIDERATION
The proposed amendment will modify the mode applicability for function 6(e) of TS Table 3.3.2-1 to clarify that the Auxiliary Feedwater start function upon trip of the TDMFW pumps is only required in Modes 1 and 2 when one or more TDMFW Pumps are operating. Therefore, the proposed amendment does not involve:
(i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(q). Therefore, pursuant to 10 CFR 51.22(b),
no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
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7.0 REFERENCES
WBN UFSAR Section 10.4.9, "Auxiliary Feedwater System" WBN System Description N3-3B-4002, "Auxiliary Feedwater System" NRC General Design Criteria (GDC) of 10 CFR 50 Appendix A, GDC 34 "Residual Heat Removal" NRC Standard Review Plan (SRP)-10.4.9, "Auxiliary Feedwater System (PWR)"
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ENCLOSURE 2 WBN-TS-04-013 TS PAGE 3.3.-38 PROPOSED TECHNICAL SPECIFICATION PAGE MARK-UP
ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 5 of 7)
.:Replaze. with .. :.. Engineered Safety feature Actuation System Instruwentation Trip
.. ....... of..... ...... llTurbine Driven Mai APPLICABLE KODES OR
.Feedwaterpumps OTHER NOIUAL SPECIFIED REOUIRED SURVEI LLANCE ALLOUABLE TRIP CONDItIONS CHANNELS CONDITIONS REOUIREKEMTS VALUE SETPOINT FUINCTI 0U
- 6. Auxiliary Feedwater Ccontirued)
- c. Safety Injection Refer to Function 1 CSafety Injection) for all initiation fuwctiora and requirements
- d. Loss of OffsIte 1.2.3 4 per F Refer to Function 4 of Table 3.3.5-1 for Power bus SRs and Allowable Values J SR 3.3.2.8 > 48 psig So psig
- e. rip of ell 4ain j 1 per IFeedwater Pumps pu3p SR 3.3.2.9 SR 3.3.2.10
- f. Auxiliary 1Z.3 F SR 3.3.2.6 A) i 0.5 A) 1.2 I Feedwater Puzips SR 3.3.2.9 psig psig Train A and B SR 3.3.2.10 Suction Transfer B) > 1.33 8) 2.0 psig psig on Suction Pressure -Low
.Replace
.. .. ........ ...... with:.... : /
I
- j-{.....-i.t.... ...:..
..... .:.:.:..... 2 : :.a
- 7. Automatic Switchover to Contairssent Sump R. Automatic 1,2,3,4 2 trains C SR 3.3.2.2 NA NA Actuation Logic SR 3.3.2.3 and Actuation SR 3.3.2.5 Relays (continued)
V .. . .. ......... .. .. ......
.. .. o..........-ir--eq t0r';-pl ............s..
bpetit'ih ..........
............ .......... I...........
Watts Bar-Unit 1 3 .3-38 Amendmen t No. I
ENCLOSURE 3 W'BN-TS-04-013 TS PAGE 3.3-38 PROPOSED TECHNICAL SPECIFICATION TYPED PAGES
ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 5 of 7)
Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES NOMINAL OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT
- 6. Auxiliary Feedwater (continued)
- c. Safety Refer to Function I (Safety Injection) for all initiation Injection functions and requirements.
- d. Loss of Offsite 1, 2, 3 4 per bus F Refer to Function 4 of Table 3.3.5-1 for Power SRs and Allowable Values e.. Trip of all 1(a).2(2) 1 per J SR 3.3.2.8 2 48 psig 50 psig Turbine Driven pump SR 3.3.2.9 Main Feedwater SR 3.3.2.10 Pumps
- f. Auxiliary 1, 2,3 3 F SR3.3.2.6 A) 20.5 A) 1.2 Feedwater SR 3.3.2.9 psig psig Pumps SR 3.3.2.10 Train A and B B) 2 1.33 B) 2.0 Suction Transfer psig psig on Suction Pressure - Low
- 7. Automatic Switchover to Containment Sump
- a. Automatic 1, 2,3, 4 2 trains C SR 3.3.2.2 NA NA Actuation Logic SR 3.3.2.3 and Actuation SR 3.3.2.5 Relays (continued)
(a) Not required unless one or more turbine driven main feedwater pumps are operating.
Watts Bar-Unit 1 3 .3-38 Amendment 1
ENCLOSURE 4 WBN-TS-04-013 TECHNICAL SPECIFICATION BASES PAGE B 3.3-93 INFORMATION ONLY
ESFAS Instrumentation B 3.3.2 BASES APPLICABLE e. Auxiliary Feedwater-Trip Of All Main Feedwater SAFETY ANALYSES, Pumps LCO, and APPLICABILITY A Trip of both turbine driven MFW pumps is an (continued) indication of a loss of MFW and the subsequent need for some method of decay heat and sensible heat removal to bring the reactor back to no load temperature and pressure. A turbine driven MFW pump is equipped with one pressure switch on the control oil line for the speed control system. A low pressure signal from this pressure switch indicates a trip of that pump. A trip of both turbine driven MFW pumps starts the motor driven and turbine driven AFW pumps to ensure that enough water is available to act as the heat sink for the reactor.
'T sencti on m OPERA M ODES I ie s ens rsfat at, les ne SG isw5ided with w 'o serve, 'te heat se'to remv>'
>n ncr; In MODES 3, 4, and 5, the RCPs and MFW pumps may be normally shut down, and thus neither pump trip is indicative of a condition requiring automatic AFW initiation.
- f. Auxiliary Feedwater-Pump Suction Transfer on Suction Pressure-Low I A low pressure signal in the AFW pump suction line protects the AFW pumps against a loss of the normal supply of water for the pumps, the CST.
Three pressure switches are located on each motor driven AFW pump suction line from the CST. A low I pressure signal sensed by two switches of a set will cause the emergency supply of water for the respective pumps to be aligned, ERCW (safety I
-. - ... ............ a w it :: .......... ie turbine.drivenmn ........... .. e...m are p a i in (es ..... with the Sintent of'op'eratinig).S'--n'.the 'case ofoetrie rvnmi
.feedwater
.. p p operatio t.....r.. ..........
.ct o t.;.n pump must also be opera1';: This antipaoy ' funci 'n is notr
,the.-safet-y .gra.decircuit..c.redi.tedin eit trr analyses'. but.. doe.s.. ensure that,atlest one Su is .ove i h ;
water..to. serve.as ..the. heatnsink Co remove reaor e et and sensibleheatintheevent of anaccident. I continued Watts Bar-Unit I B 3.3-93 Revision 2 Amendment No. 1}}