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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:License-Application for Facility Operating License (Amend/Renewal) DKT 50
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) 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-23-045, 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) 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-23-002, 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-23-015, Expedited 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-22-08)2023-02-27027 February 2023 Expedited 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-22-08) CNL-22-030, Application to Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection System for Sequoyah Nuclear Plant (SQN-TSC-22-01) and TS 3.4.12 Cold Overpressure Mitigation System for Watts Bar Nuclear Plant (WBN-TS-22-03)2022-07-27027 July 2022 Application to Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection System for Sequoyah Nuclear Plant (SQN-TSC-22-01) and TS 3.4.12 Cold Overpressure Mitigation System for Watts Bar Nuclear Plant (WBN-TS-22-03) CNL-22-071, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections (SQN-TS-21-03 and WBN-TS-21-08)2022-07-13013 July 2022 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections (SQN-TS-21-03 and WBN-TS-21-08) CNL-22-039, Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements (BFN TS-537) (SQN-21-05) (WBN-TS-21-04)2022-07-13013 July 2022 Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements (BFN TS-537) (SQN-21-05) (WBN-TS-21-04) 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-22-001, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections (SQN-TS-21-03 and WBN-TS-21-08)2022-04-0404 April 2022 Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections (SQN-TS-21-03 and WBN-TS-21-08) CNL-22-003, Application to Modify the Allowable Value for Watts Bar Nuclear Plant, Unit 1 Technical Specification Table 3.3.2-1, Function 6.e(1) (WBN-TS-21-010)2022-02-17017 February 2022 Application to Modify the Allowable Value for Watts Bar Nuclear Plant, Unit 1 Technical Specification Table 3.3.2-1, Function 6.e(1) (WBN-TS-21-010) CNL-21-018, Application to Adopt TSTF-205-A, Revision of Channel Calibration, Channel Functional Test, and Related Definitions, and TSTF-563-A, Revise Instrument Testing Definitions to Incorporate the Surveillance .2021-12-0909 December 2021 Application to Adopt TSTF-205-A, Revision of Channel Calibration, Channel Functional Test, and Related Definitions, and TSTF-563-A, Revise Instrument Testing Definitions to Incorporate the Surveillance . CNL-21-062, Application to Modify Watts Bar Nuclear Plant Units 1 and 2 Technical Specification 3.7.8 to Support Shutdown Board Cleaning (WBN-TS-19-019)2021-09-29029 September 2021 Application to Modify Watts Bar Nuclear Plant Units 1 and 2 Technical Specification 3.7.8 to Support Shutdown Board Cleaning (WBN-TS-19-019) ML21202A2242021-07-0202 July 2021 Tennessee Valley Authority (TVA)- Watts Bar Nuclear Plant (WBN)- NPDES Permit No. TN0020168-Application Request for Permit Renewal CNL-21-038, Application to Revise the Measurement Units for the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for the Containment Vent Isolation Instrumentation and Control Room Emergency Ventilation System Radiation Monitors (W2021-06-0101 June 2021 Application to Revise the Measurement Units for the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for the Containment Vent Isolation Instrumentation and Control Room Emergency Ventilation System Radiation Monitors (WBN CNL-21-045, Bellefonte Nuclear Plant, Units 1 and 2; Browns Ferry Nuclear Plant, Units 1, 2, and 3; Clinch River Nuclear Site; Sequoyah Nuclear Plant, Units 1 and 2; Watts Bar Nuclear Plant, Unit 1 and 2 - Nuclear Quality Assurance Plan, TVA-NQA-PLN82021-04-29029 April 2021 Bellefonte Nuclear Plant, Units 1 and 2; Browns Ferry Nuclear Plant, Units 1, 2, and 3; Clinch River Nuclear Site; Sequoyah Nuclear Plant, Units 1 and 2; Watts Bar Nuclear Plant, Unit 1 and 2 - Nuclear Quality Assurance Plan, TVA-NQA-PLN89- CNL-21-013, Application to Modify Technical Specifications Steam Generator Inspection/Repair Program Provisions and Unit 2 Facility Operating License Condition 2.C.(4) (WBN-TS-20-06)2021-03-11011 March 2021 Application to Modify Technical Specifications Steam Generator Inspection/Repair Program Provisions and Unit 2 Facility Operating License Condition 2.C.(4) (WBN-TS-20-06) CNL-21-015, Expedited Application to Modify Watts Bar Nuclear Plant, Unit 1 Technical Specification 3.7.12, Auxiliary Building Gas Treatment System, for One-Time Exception to Permit Opening of the Auxiliary Building Secondary Containment Enclosure as2021-03-0303 March 2021 Expedited Application to Modify Watts Bar Nuclear Plant, Unit 1 Technical Specification 3.7.12, Auxiliary Building Gas Treatment System, for One-Time Exception to Permit Opening of the Auxiliary Building Secondary Containment Enclosure as N CNL-21-016, License Amendment Request to Revise Technical Specifications to Change the Steam Generator Secondary Side Water Level to Accommodate the Replacement Steam Generators (WBN-TS-20-05)2021-03-0202 March 2021 License Amendment Request to Revise Technical Specifications to Change the Steam Generator Secondary Side Water Level to Accommodate the Replacement Steam Generators (WBN-TS-20-05) CNL-21-010, Correction of Application to Implement the Full Spectrum LOCA (Fsloca) Methodology for Loss-of-Coolant Accident (LOCA) Analysis and New LOCA-specific Tritium Producing Burnable Absorber Rod Stress Analysis Methodology (WBN-TS-19-04) (EPID2021-01-26026 January 2021 Correction of Application to Implement the Full Spectrum LOCA (Fsloca) Methodology for Loss-of-Coolant Accident (LOCA) Analysis and New LOCA-specific Tritium Producing Burnable Absorber Rod Stress Analysis Methodology (WBN-TS-19-04) (EPID L CNL-20-104, Expedited Application for Approval to Use an Alternate Method of Determining Probability of Detection for (WBN TS-391-20-024)2020-12-23023 December 2020 Expedited Application for Approval to Use an Alternate Method of Determining Probability of Detection for (WBN TS-391-20-024) CNL-20-093, Supplement to Application to Modify the Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specifications 5.7.2.19 'Containment Leakage Rate Testing Program' (WBN-TS-19-01)2020-12-15015 December 2020 Supplement to Application to Modify the Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specifications 5.7.2.19 'Containment Leakage Rate Testing Program' (WBN-TS-19-01) CNL-20-087, Non-Voluntary Application to Modify Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specifications Surveillance Requirement 3.6.15.4, Shield Building, (WBN-TS-20-017)2020-12-15015 December 2020 Non-Voluntary Application to Modify Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specifications Surveillance Requirement 3.6.15.4, Shield Building, (WBN-TS-20-017) CNL-20-078, Supplement to Application to Revise Watts Bar Nuclear Plant (Wbn), Unit 1 Technical Specifications for Steam Generator Tube Inspection Frequency and to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sa2020-10-13013 October 2020 Supplement to Application to Revise Watts Bar Nuclear Plant (Wbn), Unit 1 Technical Specifications for Steam Generator Tube Inspection Frequency and to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Samp CNL-20-006, Application to Modify the Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specifications 5.7.2.19 Containment Leakage Rate Testing Program (WBN-TS-19-01)2020-10-0202 October 2020 Application to Modify the Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specifications 5.7.2.19 Containment Leakage Rate Testing Program (WBN-TS-19-01) CNL-20-058, Tennessee Valley Authority, Application to Modify the Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specifications for Function 6.e of Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation (WBN-TS-19-27)2020-08-27027 August 2020 Tennessee Valley Authority, Application to Modify the Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specifications for Function 6.e of Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation (WBN-TS-19-27) CNL-20-041, License Amendment Request to Remove Licensee Control (BFN TS-527, SQN-TS-20-08, and WBN-TS-20-016)2020-08-14014 August 2020 License Amendment Request to Remove Licensee Control (BFN TS-527, SQN-TS-20-08, and WBN-TS-20-016) CNL-20-047, Brown Ferry Nuclear Plant, Sequoyah Nuclear Plant & Watts Bar Nuclear Plant - Tennessee Valley Authority License Amendment Request to Revise Radiological Emergency Plan Regarding On-shift Emergency Medical Technician and Onsite Ambulance2020-07-31031 July 2020 Brown Ferry Nuclear Plant, Sequoyah Nuclear Plant & Watts Bar Nuclear Plant - Tennessee Valley Authority License Amendment Request to Revise Radiological Emergency Plan Regarding On-shift Emergency Medical Technician and Onsite Ambulance Re CNL-20-063, Supplement to License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06)2020-07-27027 July 2020 Supplement to License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06) CNL-20-053, Application to Revise Watts Bar Nuclear Plant, Unit 1, Technical Specifications for Steam Generator Tube Inspection Frequency & to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies & Tube Sample Selection, (WBN-392020-07-17017 July 2020 Application to Revise Watts Bar Nuclear Plant, Unit 1, Technical Specifications for Steam Generator Tube Inspection Frequency & to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies & Tube Sample Selection, (WBN-390- CNL-20-040, License Amendment Request to Adopt TSTF-490, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec (WBN-TS-20-07)2020-07-17017 July 2020 License Amendment Request to Adopt TSTF-490, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec (WBN-TS-20-07) 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-20-012, 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-18-16)2020-05-19019 May 2020 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-18-16) CNL-20-005, License Amendment Request to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position, (WBN-TS-20-02)2020-04-0303 April 2020 License Amendment Request to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position, (WBN-TS-20-02) CNL-19-115, Non-Voluntary License Amendment Request to Modify Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications 3.2.1, Fq(Z), to Implement Methodology from WCAP-17661, Revision 1, Improved RAOC and CAOC Fq Surveillance Technical Specific2020-03-0202 March 2020 Non-Voluntary License Amendment Request to Modify Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications 3.2.1, Fq(Z), to Implement Methodology from WCAP-17661, Revision 1, Improved RAOC and CAOC Fq Surveillance Technical Specificat CNL-19-084, Second Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program...2020-01-17017 January 2020 Second Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program... 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-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-19-110, Application to Revise Technical Specifications 3.8.1, AC Sources - Operating (WBN-TS-18-10)2019-12-17017 December 2019 Application to Revise Technical Specifications 3.8.1, AC Sources - Operating (WBN-TS-18-10) CNL-19-077, Application to Modify Watts Bar Nuclear Plant (WBN) Unit 1 and Unit 2 Technical Specifications 3.6.15, Shield Building, (WBN-TS-19-10)2019-12-0606 December 2019 Application to Modify Watts Bar Nuclear Plant (WBN) Unit 1 and Unit 2 Technical Specifications 3.6.15, Shield Building, (WBN-TS-19-10) CNL-19-067, Application to Revise Watts Bar Nuclear Plant (WBN) Unit 2 - Technical Specifications for Steam Generator Tube Repair Sleeve (WBN-TS-391-19-13)2019-09-30030 September 2019 Application to Revise Watts Bar Nuclear Plant (WBN) Unit 2 - Technical Specifications for Steam Generator Tube Repair Sleeve (WBN-TS-391-19-13) CNL-19-060, Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (WBN-TS-18-14)2019-08-29029 August 2019 Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (WBN-TS-18-14) CNL-19-038, License Amendment Request to Make Miscellaneous Administrative Changes (WBN-TS-19-02)2019-06-0707 June 2019 License Amendment Request to Make Miscellaneous Administrative Changes (WBN-TS-19-02) CNL-19-014, Application to Modify Watts Bar Nuclear Plant Unit 2 Technical Specifications 3.7.8 to Extend the Completion Time for an Inoperable Essential Raw Cooling Water Train on a One-Time Basis (WBN-TS-18-07)2019-02-0707 February 2019 Application to Modify Watts Bar Nuclear Plant Unit 2 Technical Specifications 3.7.8 to Extend the Completion Time for an Inoperable Essential Raw Cooling Water Train on a One-Time Basis (WBN-TS-18-07) CNL-18-118, Application to Revise Technical Specifications Regarding DC Electrical Systems TStf-500, Revision 2, DC Electrical Rewrite - Update to TSTF-360 (WBN-TS-18-09)2018-11-29029 November 2018 Application to Revise Technical Specifications Regarding DC Electrical Systems TStf-500, Revision 2, DC Electrical Rewrite - Update to TSTF-360 (WBN-TS-18-09) CNL-18-068, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (WBN-TS-17-24)2018-11-29029 November 2018 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors (WBN-TS-17-24) CNL-18-119, Application to Revise Watt Bar Nuclear Plant, Units 1 & 2, Technical Specifications 3.8.1, 3.8.7, 3.8.8, and 3.8.9, Regarding Electrical Power Systems (WBN-TS-1808)2018-11-26026 November 2018 Application to Revise Watt Bar Nuclear Plant, Units 1 & 2, Technical Specifications 3.8.1, 3.8.7, 3.8.8, and 3.8.9, Regarding Electrical Power Systems (WBN-TS-1808) 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 2023-09-20
[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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Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 William R. Lagergren, Jr.
Site Vice President, Watts Bar Nuclear Plant APR 0 7 2004 TVA-WBN-TS-03-16 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Gentlemen:
In the Matter of ) Docket No. 50-390 Tennessee Valley Authority )
WATTS BAR NUCLEAR PLANT (WBN) - UNIT 1 - TECHNICAL SPECIFICATION (TS) CHANGE TS-03-16, "REVISION OF ULTIMATE HEAT SINK (UHS) TEMPERATURE" Pursuant to 10 CFR 50.90, TVA is submitting a request for an amendment to WBN's License NPF-90 to change the Technical Specifications for Unit 1.
The proposed TS change (TS 03-16) will revise the limiting condition for operation for TS Section 3.7.9, "Ultimate Heat Sink." The maximum essential raw cooling water (ERCW) temperature limit associated with Surveillance Requirement (SR) 3.7.9.1 will be annotated with a note allowing an occasional increase from 85 degrees Fahrenheit (0F) to 880 F.
This proposed change is based on recent evaluations of the ERCW system and the UHS functions and maximum temperatures that will satisfy the associated safety functions. In addition, an administrative change is proposed to clarify the maximum allowable internal containment pressure.
Corresponding TS Bases changes are also included for the temperature increase for UHS and the containment pressure clarification including a minor change in the maximum calculated containment pressure resulting from the increased UHS temperature.
1--~56 Pa0ted.]n ,Ededpa
U.S. Nuclear Regulatory Commission Page 2 APR 0 7 2004 TVA discussed its plans for this proposal in a meeting with NRC staff in August 2003. -The meeting provided TVA the opportunity to describe the basis and key considerations for the UHS Temperature Increase evaluation. The discussion was beneficial for TVA's understanding of potential Staff questions and concerns; these items have been addressed herein.
This request is similar to the approved license amendment request by Nebraska Public Power District, Cooper Nuclear Station, Amendment No. 193, issued July 22, 2002; Consumers Energy Company, Palisades Plant, Amendment No. 202, issued June 4, 2001; and Commonwealth Edison Company, Braidwood Station, Amendment Nos. 107 and 107 for Units 1 and 2, respectively, issued June 13, 2000. These requests proposed and received NRC approval for an increase in a single maximum UHS temperature limit.
TVA has determined that there are no significant hazards considerations associated with the proposed change and that the TS change qualifies for 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 enclosures to the Tennessee State Department of Public Health. to this letter provides the description and evaluation of the proposed change. This includes TVA's determination that the proposed change does not involve a significant hazards consideration, and is exempt from environmental review. An Attachment to Enclosure 1 provides TVA's detailed Engineering Report for the subject proposal.
Enclosures 2 and 3 contain copies of the applicable Unit 1 TS and TS Bases pages, respectively, marked-up to show the proposed changes. Enclosure 4 lists the commitments made for this submittal.
The proposed change addresses temperature limits for the UHS function that have been challenged in late summer. Therefore, TVA requests approval of this amendment by August 1, 2004, and requests that implementation occur within 45 days of approval.
U.S. Nuclear Regulatory Commission Page 3 APR 0 7 2004 If you have any questions about this change, please telephone P. L. Pace at (423) 365-1824.
I declare under penalty of perjury that the foregoing is true and correct. Executed on this 7th day of April, 2004.
Sincere y, W. R. agerg n
Enclosures:
- 1. TVA Description and Evaluation of the Proposed Change Attachment - Engineering Report, "Ultimate Heat Sink -
88°F Maximum Operating Temperature Evaluation, Watts Bar Nuclear Plant, April 2, 2004, Revision 2"
- 2. Proposed Technical Specifications Changes (mark-up)
- 3. Proposed Technical Specifications Bases Changes (mark-up)
- 4. List of Commitments Enclosures cc: See Page 4
U.S. Nuclear Regulatory Commission Page4 -
APR 0 7 200O cc (Enclosures):
NRC Resident Inspector Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381 Ms. Margaret H. Chernoff, Project Manager U.S. Nuclear Regulatory Commission MS 08G9 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 WATTS BAR NUCLEAR PLANT (WBN)
UNITS 1 DOCKET NO. 390 PROPOSED LICENSE AMENDMENT REQUEST WBN-TS-03 REVISION OF ULTIMATE HEAT SINK (UHS) TEMPERATURE DESCRIPTION AND EVALUATION OF PROPOSED CHANGE
1.0 DESCRIPTION
The purpose of this letter is to request an amendment to the Operating License NPF-90 and Technical Specifications (TS) for Watts Bar Nuclear Plant Unit 1. The proposed TS change will revise the limiting condition for operation (LCO) for TS Section 3.7.9, "Ultimate Heat Sink." The change will increase the maximum allowed essential raw cooling water (ERCW) temperature from 85 degrees Fahrenheit (0F) to 880 F for Surveillance Requirement (SR) 3.7.9.1 for short durations due to seasonal variations. The proposed change is based on recent evaluations of the ERCW system and the UHS functions and maximum temperatures and minimum river elevations that will satisfy the associated safety functions. The proposed change satisfies TVA's intent to propose a permanent TS change that will reduce the challenges to the UHS limit. In addition, an administrative change is proposed to clarify the maximum allowable internal containment pressure. Corresponding TS Bases changes are included for the temperature increase for UHS and the containment pressure clarification including a minor change in the maximum calculated containment pressure resulting from the increased UHS temperature.
2.0 PROPOSED CHANGE
The proposed change will revise WBN TS Section 3.7.9, "Ultimate Heat Sink," specifically, Surveillance Requirement (SR) 3.7.9.1. A footnote has been added to the SR which would allow an increase in the ERCW temperature limit from 850 F to 880 F for short durations due to seasonal variations. An administrative change is proposed to clarify the maximum allowable internal containment pressure consistent with the current TS Bases. Corresponding TS Bases changes are also proposed. The TS and TS Bases changes affect the following sections and are illustrated by marked-up pages provided in Enclosures 2 and 3:
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Technical Specification
- 1) SR 3.7.9.1 (Page 3.7-21) is revised to add the following footnote:
"(*) UHS average water temperature > 850 F and < 88 0 F is acceptable for short durations due to seasonal variations.N
- 2) TS 5.7.2.19 (Page 5.0-28), second paragraph is revised from:
"The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa, is 15.0 psig.0 to:
"The maximum allowable containment internal pressure, Pa, is 15.0 psig, which bounds the peak calculated containment internal pressure resulting from the design basis LOCA.L Technical Specification Bases Corresponding TS Bases changes are included for the temperature increase to 880 F for UHS. The TS Bases are also revised to reflect the revised peak containment pressure resulting from the containment pressure reanalysis using the increased ERCW temperature of 88 0 F, and to clarify the maximum allowable internal containment pressure.
Refer to the markups provided in Enclosure 3.
In particular, as discussed in Section 4 of this report, the proposed revisions to the TS Bases include a discussion of contingency measures considered prudent if UHS temperature should exceed 850 F. The following change is proposed:
- 5) Section B 3.7.9, SR 3.7.9.1 (Page B 3.7-50):
Insert:
"A note indicates UHS average water temperature > 85 0 F and
<880 F is acceptable for short durations and is based on the engineering evaluation provided in Reference 4. If surveillance performance indicates the average water temperature of UHS will exceed 85 0 F, site procedures/documents require the following contingency actions:
Perform an engineering evaluation and appropriate risk-management actions (1) To confirm UHS operability for existing ERCW equipment problems that would remain concurrent with UNS temperature above 85 0 F, and (2) Prior to initiating an elective work activity that would render an ERCW component required by LCO 3.7.8 inoperable.
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These contingency measures are not required for UHS operability and are not credited in the safety analyses/evaluations of Reference 4. However, they are intended to minimize the impact of operation above 850F, since such operation may exceed the original design parameters for ERCW supplied components.
Because margin above design has been utilized to validate such operation, the contingency measures are considered prudent to maintain defense-in-depth."
3.0 BACKGROUND
AND
SUMMARY
On August 2, 2002, the UHS temperature at WBN approached the Technical Specification limit of 85'F. If this limit had been exceeded it could have resulted in an unnecessary unit shutdown to comply with Technical Specification LCO 3.7.9. Multipurpose river operation coupled with hotter than normal summers and below normal river flows has prompted resolution of this critical operating condition. Past efforts by TVA to address this condition have included temporary manipulation of the Tennessee River system, including upstream reservoirs, in order to maintain acceptable temperature in the Chickamauga Reservoir pool. These special operations can involve significant operating expenses and coordination difficulties with unpredictable results and limited success.
Therefore, TVA proposes that the maximum ERCW temperature limit in SR 3.7.9.1 will be increased from 850 F to 880F. The proposed change is based on recent evaluations of the ERCW system, UHS functions, and maximum temperatures utilizing existing margins in the ERCW design basis in proving acceptable plant operation and safety performance for a short duration and infrequent event. The proposed change satisfies TVA's intent to incorporate a permanent TS change that will reduce challenges to the UHS limit.
4.0 TECHNICAL ANALYSIS
The methodology and results of TVA's evaluation of the proposed UHS temperature increase of up to 30 F above the existing design basis value of 850 F to 880 F are discussed in detail in the attached report, "Ultimate Heat Sink - 880 F Maximum Temperature Evaluation, Engineering Report, Watts Bar Nuclear Plant, April 2, 2004, Revision 2," (Reference 1). A description of the ERCW and UHS Systems is provided in the WBN Updated Final Safety Analysis Report (UFSAR)
Sections 9.2.1 and 9.2.5, respectively.
The effects of the proposed temperature increase have been examined in detail on equipment, components, systems, and safety analyses and have been found to be acceptable. An extensive review was performed of existing calculations, procedures, design criteria, system descriptions and the UFSAR. The evaluation included several new El-3
heat transfer calculations, a new UHS drawdown calculation resulting from postulated breach of the Chickamauga Dam, a revised Residual Heat Removal (RHR) design basis cooldown analysis, and a revised design basis containment pressure response calculation for a postulated loss of coolant accident (LOCA) occurring with UHS/ERCW intake water temperature of 880F. As discussed in the attached Engineering Report (ER), the methods of evaluation varied and included sensitivity evaluations, bounding analyses, and design basis re-analysis (e.g., for the containment pressure analysis) to demonstrate that the cooling water requirements for the most demanding accident, shutdown, and cooldown have been met.
Margin exists in many areas within the ERCW design basis analyses.
ERCW flow rates, cooled medium (water and air) flow rates, heat exchanger fouling, heat exchanger tube plugging, equipment and room heat loads, heat load losses to ambient, assumed lake levels, and margin inherent in structural Codes (piping and supports) all offer various amounts of margin in the analyses. In most cases, only ERCW flow rate margin was utilized, and in some cases, heat load margins were used to evaluate acceptable ERCW system performance at 880 F.
Some specific systems, structures and/or components required a more in-depth evaluation to determine acceptability of minimum required performance. More limiting input assumptions were utilized in some evaluations such that additional margins were created, for example, use of a higher ERCW flow rate for a component supported by preoperational test data. The attached ER discusses when such techniques or different methods were used for the evaluations. With the exception of these ERCW component evaluations and the RHR cooldown analysis discussed below, no other changes in assumptions or methodologies were credited for the evaluation of the revised UHS temperature change.
The impact of the proposed change on shutdown and removal of residual heat, including time requirements for achieving a safe shutdown conditions were evaluated in Section 3.16 (RHR Impact).
The analysis concluded that acceptable system performance during normal plant cooldowns at 880 F would be obtained. For the case of single train cooldown, in which TS compliance with the 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> to cold shutdown is dependent on single train availability of RHR, the cooldown time period could be achieved by limiting isolation of spent fuel pool cooling for up to 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> and assurance that the remaining reactor coolant pump be secured no later than 25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> after shutdown. Securing the last pump at 25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> is consistent with and bounded by operational practices that would occur during a loss of offsite power event, where all power is provided by the emergency diesel generators (EDGs), since the reactor coolant pumps (RCPs) are not loaded on the emergency shut down electric boards.
As discussed in the attached ER, Section 3.18, TVA River Systems Operation and Engineering performed a re-analysis of the postulated effects of a non-flood failure of Chickamauga Dam (downstream of WBN). The TVA River model discussion is attached to the ER as well as performance graphs for several failure scenarios, and operating E1-4
guides for Chickamauga and Watts Bar reservoirs. Although the analysis of UHS and ERCW performance at 880 F did not quantitatively credit this analysis, the results indicate a higher minimum river water pool elevation (approximately seven feet greater than assumed for the original ERCW flow balance), thus providing additional flow margins to ERCW components.
TVA notes that a revised river plan is under consideration. The new plan, if adopted, would not impact the conclusions of the ER for the increased UHS temperature for WBN.. The expected frequency of extreme river temperature events (exceedances of 850 F) would continue to be consistent with assumptions of the ER, that is, infrequent and of short duration. The river plan would impact the attached reservoir operating guides, however, these curves are not utilized as input for any evaluations performed in support of increased UHS temperature at WBN. They have been included to provide the reviewer a better understanding of TVA's ability to exercise control of UHS levels. Key reservoir levels used as design input parameters to plant specific analyses include minimum lake level from a loss of downstream dam, which is primarily influenced by upstream dam releases during such an event, and maximum flood levels, which do not challenge the plant from a UHS temperature basis. These key design parameters are not shown on the normal operating guide graphs and are not impacted by the revised river plan.
The UHS temperature increase to 880 F resulted in a minor increase in the maximum calculated containment pressure due to a design basis LOCA. This change from 10.64 psig to 10.90 psig remains below the ASME Code design internal pressure of 13.5 psig. The containment accident reanalysis is discussed in the attached ER, Section 3.4.
The containment functional design is discussed in UFSAR Section 6.2.1.
TVA's evaluation concluded that there is not a significant increase in the risk or consequences of normal operation, shutdown, or accident mitigation or danger to the public, equipment, or site personnel because adequate margins exist in the critical systems, structures and/or components. The evaluation concluded that a Technical Specification change to allow continued plant operation up to 880 F is acceptable.
Design Bases Control As discussed in the ER (Section 3.32), the WBN Design Basis will be revised to reflect a UHS limit of 880 F for two analyses, (1)
Containment Pressurization and Temperature Response Analysis, and (2) Residual Heat Removal Cool-down Analysis. However, due to the short duration and infrequent nature of the UHS heat-up event, the design basis for the ERCW and UHS Systems will continue to reflect a UHS limit of 850 F while utilizing existing margins in the ERCW design in proving acceptable plant operation. This approach will El-5
eliminate the need for extensive and cost-prohibitive revisions to all design basis documents (e.g., calculations, design drawings, etc.) to fully capture a new design basis temperature of 880 F in all plant documents. Further, this approach will allow retention of margin that exists in many areas within the ERCW design basis. It is desired to avoid the consumption of this existing plant operational margin within the design basis for an infrequent event since, should it occur, the event would only last for a few days.
Reserving such margin limits operational flexibility through much of the year in evaluating other conditions that may arise in which taking credit for lower ERCW temperatures and existing flow margins would prove beneficial.
The importance of maintaining the design basis configuration is recognized. Furthermore, the importance of maintaining the approach and methodology that allowed the conclusion that safe operation is achievable even at 880 F UHS temperatures is acknowledged. For this reason, the UFSAR, System Descriptions, Design Criteria, and other key design documents will be revised to ensure that 880 F is considered in future procurements, specifications, analyses, and evaluations. NRC approval of the proposed UHS Tech Spec change will establish a licensing basis value for continued operation up to 880 F ERCW temperature. The design basis value will continue to be 850 F.
However, the conclusions of the Engineering Report will not be invalidated since future analyses will include a 30 F margin over the current design basis value of 85'F.
Recommendations/Contingency Actions The attached Engineering Report identifies several requirements and recommendations which should be satisfied in order take advantage of the higher temperature allowance for the UHS. These issues will be implemented through the design change and TS change implementation processes and are discussed below.
- 1) (ER - Page 24) The Shutdown Board Room (SDBR) chiller was found to have a potential performance deficiency above 850 F based on discussions with the component vendor. The chiller compressor's thermodynamic design point indicated 850 F was the maximum recommended operational value for cooling water (ERCW).
For this reason, WBN initiated a vendor recommended change to re-gear the compressor to assure acceptable thermodynamic operation of the chiller unit at the higher UHS temperature of 880 F. Prior to implementation of the proposed TS, TVA will implement this modification to re-gear the compressors for SDBR chillers A-A and B-B by August 1, 2004.
- 2) (ER - Page 24) The Emergency Diesel Generator's jacket water heat exchangers were also shown to be marginal in their performance capabilities at 880 F UHS temperature if design fouling conditions were assumed. The evaluation concluded that E1-6
expected actual fouling rates of the EDG heat exchanger would provide acceptable EDG cooling provided tube cleaning was performed annually during the spring time-frame, assuring relatively clean EDG coolers during the late summer time period of maximum UHS temperatures. The "once a year during spring" allows exceeding the 365 days between cleanings, since lower ERCW temperatures during the spring can compensate for higher fouling. Therefore, TVA will revise the UFSAR to require EDG jacket water heat exchangers to be cleaned once a year during spring, within a time frame no earlier than March 1st but no later than June 30th. A one time exception to this cleaning interval for the 2A-A EDG is acceptable to support cleaning of its heat exchangers which were recently completed in February 2004.
- 3) (ER - Page 18) As discussed above, procedure changes will be necessary to address RHR shutdown cooling assumptions. TVA will revise the UFSAR to address single-train RHR cooldown restrictions for ERCW temperature of 880 F which consist of a five hour limitation on spent fuel pool (SFP) cooling isolation and a requirement to secure the remaining reactor coolant pump within 25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> after shutdown.
- 4) (ER - Page 32) In Section 5.0 of the ER, several Recommendations are provided for the UHS Temperature Evaluation project. The following summarizes several of the more important recommendations:
Recommendation 5.4 - Revise UFSAR, System Descriptions, Design Criteria, and other key design documents to ensure that 880 F is considered in future procurements, specifications, analyses, and evaluations.
This recommendation addresses the future design change control requirements for the UHS temperature change (Reference ER Section 3.32) and is necessary because the ERCW design basis temperature will remain at 850 F.
Recommendation 5.6 - Revise UFSAR and System Description to require Diesel Generator Heat Exchangers be cleaned once a year during spring, within a time frame no earlier than March 1st but no later than June 30th.
This recommendation is discussed in greater detail in Item 2 above.
Recommendation 5.7 - Revise appropriate procedures to require Engineering to initiate reviews of open items associated with ERCW temperature, such as GL 91-18 issues, temporary alterations (TACFs), etc., prior to reaching the ERCW design temperature of 850 F. (Refer to discussion below)
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Recommendation 5.8 - Revise the Technical Specifications Bases (and appropriate procedures) to address contingency actions in 5.7 above for plant operation at UHS temperature exceeding 850 F. These actions require performance of an engineering evaluation and appropriate risk-management actions:
(1) To confirm UHS operability for existing ERCW equipment problems that would remain concurrent with UHS temperature above 850 F, and, (2) Prior to initiating an elective work activity that would render an ERCW component required by LCO 3.7.8 inoperable.
Recommendations 5.7 and 5.8 address contingency measures to be taken for plant operation at UHS temperature exceeding 850 F.
These actions are intended to provide a confirmation that any existing ERCW degradation issues would not impact the assumptions or validity of the UHS Temperature Evaluation project. Such items may include operability issues, temporary alterations, or degraded plant conditions (i.e., Generic Letter 91-18 issues) sensitive to ERCW/UHS cooling requirements. WBN procedures will require performance of appropriate engineering evaluations and/or the use of risk-management actions to address these issues with UHS temperature in excess of 850F.
A discussion of these measures has been incorporated into the proposed TS Bases 3.7.9, (Section 2.0, of this Enclosure).
These contingency actions are not required for UHS operability and are not credited in the safety analyses or evaluations of this ER, since the evaluation demonstrated acceptable plant operation at the higher 880 F temperature based on available margins within the ERCW design basis. However, they will minimize the impact of operation above 850F, since such operation may exceed the original design parameters for ERCW supplied components. Because margin above design has been utilized to validate such operation, the contingency measures are considered prudent to maintain defense-in-depth.
5.0 REGULATORY SAFETY ANALYSIS The proposed technical specification (TS) change will revise the limiting condition for operation for the Ultimate Heat Sink. The essential raw cooling water (ERCW) temperature limit will be increased from 85 degrees Fahrenheit (0F) to 880F. These proposed changes are based on recent evaluations of the ERCW system and the Ultimate Heat Sink (UHS) functions and maximum temperatures and minimum river elevations that will satisfy the associated safety functions. The proposed changes will minimize the likelihood of a required unit shutdown as a result of high river temperatures in the summer. In addition, a change is proposed to clarify the maximum allowable internal containment pressure. Corresponding TS Bases El-8
changes are also included for the temperature increase for UHS and the containment pressure clarification including a minor change in the maximum calculated containment pressure resulting from the increased UHS temperature.
5.1 No Significant Hazards Consideration 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 change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
The proposed change to increase the UHS maximum temperature will not adversely alter the function, design, or operating practices for plant systems or components. The UHS is utilized to remove heat loads from plant systems during normal and accident conditions. This function is not expected or postulated to result in the generation of any accident and continues to adequately satisfy the associated safety functions with the proposed changes. Therefore, the probability of an accident presently evaluated in the safety analyses will not be increased. With the exception of re-gearing the shutdown board room chiller compressors, no other plant equipment must be altered as a result of this change.
Re-gearing of the shutdown board room chillers will ensure their continued performance in accordance with design concurrent with the increased UHS temperature. The heat loads that the UHS is designed to accommodate have been evaluated for functionality with the higher temperature limits. The result of these evaluations is that there is existing margin associated with the systems that utilize the UHS for normal and accident conditions. These margins are sufficient to accommodate the postulated normal and accident heat loads with the proposed changes to the UHS. Since the safety functions of the UHS are maintained, the systems that ensure acceptable offsite dose consequences will continue to operate as designed. The change in the maximum calculated containment pressure associated with the design basis loss of coolant accident remains below the ASME Code design internal pressure. The change to clarify the maximum allowable internal containment pressure is administrative consistent with present wording in the TS Bases. Therefore, the consequence of any accident will be the same as those previously analyzed.
Therefore, since the UHS safety function will continue to meet accident mitigation requirements and limit dose E1-9
consequences to acceptable levels, TVA has concluded that the proposed TS change does not involve a significant increase 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.
The UHS function provides accident mitigation capabilities and serves as a heat sink for normal and upset plant conditions; the UHS is not an initiator of any accident. By allowing the proposed change in the UHS temperature requirements, only the parameters for UHS operation are changed while the safety functions of the UHS and systems that transfer the heat sink capability continue to be maintained. The proposed change does not impact the response of the systems and components assumed in the safety analysis.
Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does the proposed change involve a significant reduction in a margin of safety?
Response: No.
The proposed change has been evaluated for systems that are needed to support accident mitigation functions as well as normal operational evolutions. Operational margins were found to exist in the systems that utilize the UHS capabilities such that these proposed changes will not result in the loss of any safety function necessary for normal or accident conditions. The ERCW system has excess flow margins that will accommodate the increased flows necessary for the proposed temperature increase. While operating margins have been reduced by the proposed changes, safety margins have been maintained as assumed in the accident analyses for postulated events. The proposed change results in an increase in the maximum calculated containment peak pressure.
However, the change in the maximum calculated containment peak pressure associated with the design basis LOCA is a small percentage of the margin between the current maximum calculated containment peak pressure and the ASME Code design internal pressure. The change to clarify the maximum allowable internal containment pressure is administrative.
This aspect of the proposed change does not involve a significant reduction in a margin of safety. Additionally, the proposed changes do not require any further modification (the shutdown board room chiller will be re-geared) of component setpoints or operating provisions that are EI-10
necessary to maintain margins of safety established by the WBN design. 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(s) present 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.
5.2 Applicable Regulatory Requirements/Criteria The Commission's regulatory requirements related to the content of the TS are contained in Title 10, Code of Federal Regulations (10 CFR), Section 50.36. The Ultimate Heat Sink (UHS) temperature satisfies Criterion 3 of 10 CFR 50.36(c)(2)(ii) and is therefore included in TS 3.7.9. The proposed change does not relocate the UHS temperature from TS 3.7.9 and therefore the requirements of Criterion 3 of 10 CFR 50.36(c)(2)(ii) continue to be met.
General Design Criterion 44, "Cooling Water," of Appendix A, "General Design Criteria," to 10 CFR Part 50, provides design considerations for the UHS. Regulatory Guide 1.27 provides an acceptable approach for satisfying this criterion. The discussion below regarding Regulatory Guide 1.27 compliance demonstrates the ability to meet the recommendations of the regulatory guide and therefore satisfies the requirements of General Design Criterion 44.
As discussed in WBN UFSAR Section 9.2.5, UHS, Regulatory Guide 1.27 provides an acceptable approach for the design of the UHS.
This guidance provides four criteria for an acceptable UHS function. These criteria include recommendations for sufficient cooling capability, integrity during postulated events, function availability and redundancy, and control by the TSs. TVA has evaluated the proposed changes and their impact on the UHS design based on the criteria in Regulatory Guide 1.27 and has determined that these recommendations continue to be met. The cooling ability of the UHS, with the proposed increase in temperature, has been evaluated and verified to satisfy the recommendations for heat removal considerations. The integrity and availability recommendations have not been affected by the proposed changes as the features are not being altered physically. The TS provisions are proposed to be changed but continue to meet the recommendation to provide actions in the event the function of the UHS cannot be satisfied. Therefore, operation of the WBN unit with the proposed TS change will not result in a deviation from the recommendations of Regulatory Guide 1.27.
Appendix A to 10 CFR 50, General Design Criteria (GDC) 16, "Containment design," GDC 38, "Containment heat removal,' and El-li
GDC 50, "Containment design basis," continue to be met with the proposed change.
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.
6.0 ENVIRONMENTAL CONSIDERATION
A review has determined that the proposed amendment 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 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)(9). Therefore, pursuant to 10 CFR 50.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
7.0 REFERENCES
Refer to Reference 1 (Attached Engineering Report), Section 6, for the complete listing of References. In addition, the following references are included.
- 1. Engineering Report, "Ultimate Heat Sink - 880 F Maximum Temperature Evaluation, Watts Bar Nuclear Plant, April 2, 2004, Revision 2.a
- 2. Nebraska Public Power District, Cooper Nuclear Station, Amendment No. 193, issued July 22, 2002.
- 3. Consumers Energy Company, Palisades Plant, Amendment No. 202, issued June 4, 2001.
- 4. Commonwealth Edison Company, Braidwood Station, Amendment Nos.
107 and 107 for Units 1 and 2, respectively, issued June 13, 2000.
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