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Category:Letter type:CNL
MONTHYEARCNL-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) 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 CNL-23-036, Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08)2023-12-18018 December 2023 Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08) CNL-23-001, 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) 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 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 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 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-23-055, 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 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 . 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 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 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-23-030, 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-23-032, 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-23-033, 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 CNL-23-023, Annual Insurance Status Report2023-03-30030 March 2023 Annual Insurance Status Report CNL-23-022, Decommissioning Funding Status Report2023-03-29029 March 2023 Decommissioning Funding 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 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-23-021, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-03-0808 March 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 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-23-003, Browns Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2; and Watts Bar Nuclear Plant, Units 1 & 2 - Organizational Topic Report TVA-NPOD89-A2023-01-30030 January 2023 Browns Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2; and Watts Bar Nuclear Plant, Units 1 & 2 - Organizational Topic Report TVA-NPOD89-A CNL-23-009, Response to Request for Additional Information Request to Revise Technical Specification 3.4.122023-01-0404 January 2023 Response to Request for Additional Information Request to Revise Technical Specification 3.4.12 CNL-23-008, Tennessee Valley Authority Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2022-12-22022 December 2022 Tennessee Valley Authority Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-22-109, Steam Generator Tube Inspection Report to Reflect TSTF-577 Reporting Requirements2022-12-22022 December 2022 Steam Generator Tube Inspection Report to Reflect TSTF-577 Reporting Requirements CNL-22-101, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative WBN-2-ISI-012022-11-28028 November 2022 American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative WBN-2-ISI-01 CNL-22-106, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-14, Revision 38, Nuclear Emergency Public Information Organization and Operat2022-11-28028 November 2022 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-14, Revision 38, Nuclear Emergency Public Information Organization and Operatio CNL-22-099, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2022-10-31031 October 2022 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-22-098, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC EPIP-7, Rev. 45 & CECC EPIP-8, Rev. 552022-10-17017 October 2022 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC EPIP-7, Rev. 45 & CECC EPIP-8, Rev. 55 CNL-22-085, Response to Request for Additional Information Regarding Sequoyah Nuclear Plant (Sqn), Units 1 and 2 and Watts Bar Nuclear Plant (Wbn), Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Al2022-09-0202 September 2022 Response to Request for Additional Information Regarding Sequoyah Nuclear Plant (Sqn), Units 1 and 2 and Watts Bar Nuclear Plant (Wbn), Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alte CNL-22-077, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2022-08-11011 August 2022 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 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-22-039, 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-22-071, 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-22-070, Status Regarding the Improved Flood Mitigation System Project2022-06-30030 June 2022 Status Regarding the Improved Flood Mitigation System Project 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-22-064, Response to Request for Additional Information Regarding Tennessee Valley Authority License Amendment Request to Revise Emergency Plan Implementing Procedure Regarding Seismic Event Emergency Action Level Change2022-06-0909 June 2022 Response to Request for Additional Information Regarding Tennessee Valley Authority License Amendment Request to Revise Emergency Plan Implementing Procedure Regarding Seismic Event Emergency Action Level Change CNL-22-068, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2022-06-0808 June 2022 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-22-047, Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2022-05-23023 May 2022 Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions CNL-22-043, Response to Request for Additional Information and Confirmation of Information Regarding Application to Modify Watts Bar Nuclear Plant Units 1 and 2 Technical Specification 3.7.8 to Support Shutdown Board.2022-05-0202 May 2022 Response to Request for Additional Information and Confirmation of Information Regarding Application to Modify Watts Bar Nuclear Plant Units 1 and 2 Technical Specification 3.7.8 to Support Shutdown Board. CNL-22-046, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan.2022-04-28028 April 2022 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan. 2024-01-09
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARCNL-23-009, Response to Request for Additional Information Request to Revise Technical Specification 3.4.122023-01-0404 January 2023 Response to Request for Additional Information Request to Revise Technical Specification 3.4.12 CNL-22-085, Response to Request for Additional Information Regarding Sequoyah Nuclear Plant (Sqn), Units 1 and 2 and Watts Bar Nuclear Plant (Wbn), Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Al2022-09-0202 September 2022 Response to Request for Additional Information Regarding Sequoyah Nuclear Plant (Sqn), Units 1 and 2 and Watts Bar Nuclear Plant (Wbn), Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alte CNL-22-064, Response to Request for Additional Information Regarding Tennessee Valley Authority License Amendment Request to Revise Emergency Plan Implementing Procedure Regarding Seismic Event Emergency Action Level Change2022-06-0909 June 2022 Response to Request for Additional Information Regarding Tennessee Valley Authority License Amendment Request to Revise Emergency Plan Implementing Procedure Regarding Seismic Event Emergency Action Level Change CNL-22-043, Response to Request for Additional Information and Confirmation of Information Regarding Application to Modify Watts Bar Nuclear Plant Units 1 and 2 Technical Specification 3.7.8 to Support Shutdown Board.2022-05-0202 May 2022 Response to Request for Additional Information and Confirmation of Information Regarding Application to Modify Watts Bar Nuclear Plant Units 1 and 2 Technical Specification 3.7.8 to Support Shutdown Board. CNL-22-060, Response to Request for Additional Information and Clarification Regarding Request for Exemption from Requirements of 10 CFR 26.205(d)(4), 26.205(d)(6) and 26.205(d)(7), Fitness for Duty Programs - Work Hours2022-04-25025 April 2022 Response to Request for Additional Information and Clarification Regarding Request for Exemption from Requirements of 10 CFR 26.205(d)(4), 26.205(d)(6) and 26.205(d)(7), Fitness for Duty Programs - Work Hours WBL-22-010, Response to Request for Confirmation of Information Regarding the Watts Bar Nuclear Plant, Unit 2, Cycle 4 Mid-Cycle Outage Generic Letter 95-05 Final Report2022-03-0202 March 2022 Response to Request for Confirmation of Information Regarding the Watts Bar Nuclear Plant, Unit 2, Cycle 4 Mid-Cycle Outage Generic Letter 95-05 Final Report CNL-21-098, Supplement to Response to Request for Additional Information Regarding Application to Modify Technical Specifications Steam Generator Inspection/Repair Program Provisions and Operating License Condition 2.C.(4)2022-01-0505 January 2022 Supplement to Response to Request for Additional Information Regarding Application to Modify Technical Specifications Steam Generator Inspection/Repair Program Provisions and Operating License Condition 2.C.(4) CNL-21-075, Response to Request for Additional Information Regarding Expedited Application to Modify Technical Specification 3.7.12, Auxiliary Building Gas Treatment System, for One-Time Exception to Permit Opening2021-09-0808 September 2021 Response to Request for Additional Information Regarding Expedited Application to Modify Technical Specification 3.7.12, Auxiliary Building Gas Treatment System, for One-Time Exception to Permit Opening CNL-21-070, Response to Request for Additional Information Regarding Application to Modify Watts Bar Nuclear Plant, Unit 2 Technical Specifications Steam Generator Inspection/Repair Program Provisions and Unit 2 Facility Operating License Condition 22021-08-11011 August 2021 Response to Request for Additional Information Regarding Application to Modify Watts Bar Nuclear Plant, Unit 2 Technical Specifications Steam Generator Inspection/Repair Program Provisions and Unit 2 Facility Operating License Condition 2.C CNL-21-043, Response to Request for Additional Information Regarding Expedited Application for Approval to Use a Growth Rate Temperature Adjustment When Implementing the Generic Letter 95-05 Analysis for the Watts Bar Nuclear Plant2021-05-14014 May 2021 Response to Request for Additional Information Regarding Expedited Application for Approval to Use a Growth Rate Temperature Adjustment When Implementing the Generic Letter 95-05 Analysis for the Watts Bar Nuclear Plant CNL-21-041, Response to RAI Re Application to Modify the Watts Bar Nuclear Plant Technical Specifications 5.7.2.19, Containment Leakage Rate Testing Program (WBN-TS-19-01)2021-04-29029 April 2021 Response to RAI Re Application to Modify the Watts Bar Nuclear Plant Technical Specifications 5.7.2.19, Containment Leakage Rate Testing Program (WBN-TS-19-01) CNL-21-021, Response to Request for Additional Information Regarding Application to Revise Watts Bar Nuclear Plant (Wbn), Unit 1 Technical Specifications for Steam Generator Tube Inspection Frequency and to Adopt TSTF-510, .2021-03-30030 March 2021 Response to Request for Additional Information Regarding Application to Revise Watts Bar Nuclear Plant (Wbn), Unit 1 Technical Specifications for Steam Generator Tube Inspection Frequency and to Adopt TSTF-510, . CNL-21-005, Response to Request for Additional Info Re License Amendment Request to Adopt TSTF-490, Deletion of E Bar Definition & Revision to RCS Specific Activity Tech Spec (WBN-TS-20-07)2021-01-22022 January 2021 Response to Request for Additional Info Re License Amendment Request to Adopt TSTF-490, Deletion of E Bar Definition & Revision to RCS Specific Activity Tech Spec (WBN-TS-20-07) CNL-21-014, Response to Request for Additional Information for Expedited Application for Approval to Use an Alternate Method of Determining Probability of Detection for the Watts Bar Nuclear Plant, Unit 2 Steam Generators (WBN TS-391-20-024)2021-01-19019 January 2021 Response to Request for Additional Information for Expedited Application for Approval to Use an Alternate Method of Determining Probability of Detection for the Watts Bar Nuclear Plant, Unit 2 Steam Generators (WBN TS-391-20-024) CNL-20-074, Submittal of Additional Supplement to License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06)2020-08-28028 August 2020 Submittal of Additional Supplement to License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06) CNL-20-030, Response to Request for Additional Information to License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06)2020-04-29029 April 2020 Response to Request for Additional Information to License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06) CNL-19-124, Response to Request for Additional Information to 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 (W2020-01-13013 January 2020 Response to Request for Additional Information to 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 CNL-19-108, Response to NRC Second Request for Additional Information Regarding Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2019-10-28028 October 2019 Response to NRC Second Request for Additional Information Regarding Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors CNL-19-105, Supplemental Response to Second-Round NRC Request for Additional Information Regarding Application to Revise Technical Specifications Regarding DC Electrical Systems TSTF-500, Revision 2 (WBN-TS-18-09)2019-10-10010 October 2019 Supplemental Response to Second-Round NRC Request for Additional Information Regarding Application to Revise Technical Specifications Regarding DC Electrical Systems TSTF-500, Revision 2 (WBN-TS-18-09) CNL-19-062, 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)2019-09-0404 September 2019 Response to Second-Round NRC Request for Additional Information Regarding Application to Revise Technical Specifications Regarding DC Electrical Systems TSTF-500, Revision 2 (WBN-TS-18-09) CNL-19-069, Final Response to NRC Request for Additional Information Regarding Watts Bar Nuclear Plant, Units 1 and 2, Application to Adopt 10 CFR 50.69,Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Pow2019-07-29029 July 2019 Final Response to NRC Request for Additional Information Regarding Watts Bar Nuclear Plant, Units 1 and 2, Application to Adopt 10 CFR 50.69,Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power CNL-19-068, Response to Request for Additional Information Regarding the Sequoyah Nuclear Plant (SQN) Units 1 and 2 and Watts Bar Nuclear Plant (WBN) Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for2019-07-22022 July 2019 Response to Request for Additional Information Regarding the Sequoyah Nuclear Plant (SQN) Units 1 and 2 and Watts Bar Nuclear Plant (WBN) Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for .. CNL-19-065, Partial Response to NRC Request for Additional Information Regarding Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2019-07-15015 July 2019 Partial Response to NRC Request for Additional Information Regarding Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors CNL-19-056, Response to NRC Request for Additional Information Regarding Application to Revise Technical Specifications Regarding DC Electrical Systems TSTF-500, Revision 2, DC Electrical Rewrite - Update to TSTF-3602019-06-0707 June 2019 Response to NRC Request for Additional Information Regarding Application to Revise Technical Specifications Regarding DC Electrical Systems TSTF-500, Revision 2, DC Electrical Rewrite - Update to TSTF-360 CNL-19-033, Revised Response to Request for Additional Information Regarding Application to Modify Technical Specifications 3.8.9 Regarding Alternating Current (AC) Vital Buses (WBN-TS-17-19)2019-03-21021 March 2019 Revised Response to Request for Additional Information Regarding Application to Modify Technical Specifications 3.8.9 Regarding Alternating Current (AC) Vital Buses (WBN-TS-17-19) CNL-18-121, Response to Request for Additional Information Regarding Application to Modify Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications 3.8.9 Regarding Alternating Current (AC) Vital Buses (WBN-TS-17-19)2018-11-0909 November 2018 Response to Request for Additional Information Regarding Application to Modify Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications 3.8.9 Regarding Alternating Current (AC) Vital Buses (WBN-TS-17-19) CNL-18-128, Response to Request for Additional Information Regarding Application to Revise Technical Specifications for Use of Voltage-Based Alternate Repair Criteria in Accordance with Generic Letter 95-05 (391-WBN2-TS-17-30)2018-11-0808 November 2018 Response to Request for Additional Information Regarding Application to Revise Technical Specifications for Use of Voltage-Based Alternate Repair Criteria in Accordance with Generic Letter 95-05 (391-WBN2-TS-17-30) CNL-18-116, Response to Request for Additional Information Regarding the Application to Revise Watts Bar Nuclear Plant Unit 2 - License Condition 2.C(4) PAD4TCD (391-WBN-TS-18-03)2018-10-11011 October 2018 Response to Request for Additional Information Regarding the Application to Revise Watts Bar Nuclear Plant Unit 2 - License Condition 2.C(4) PAD4TCD (391-WBN-TS-18-03) CNL-18-113, Response to Request for Additional Information Regarding Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, Fuel Assemblies, and Watts Bar Units 1 and 2 Technical Specifications Related to Fuel Storage (WBN-TS-17-028) .2018-10-0404 October 2018 Response to Request for Additional Information Regarding Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, Fuel Assemblies, and Watts Bar Units 1 and 2 Technical Specifications Related to Fuel Storage (WBN-TS-17-028) ... CNL-18-104, Submittal of Revised Response to Request for Additional Information Regarding Application to Modify Plant Technical Specifications to Extend Surveillance Requirements 3.3.1.5, 3.3.2.2 and 3.3.6.2 Specified Intervals2018-07-30030 July 2018 Submittal of Revised Response to Request for Additional Information Regarding Application to Modify Plant Technical Specifications to Extend Surveillance Requirements 3.3.1.5, 3.3.2.2 and 3.3.6.2 Specified Intervals CNL-18-102, Response to Request for Additional Information Regarding Application to Modify Watts Bar Nuclear Plant Unit 1 Technical Specifications to Extend Surveillance Requirement 3.3.1.5, 3.3.2.2, and 3.3.6.2 Specified ...2018-07-24024 July 2018 Response to Request for Additional Information Regarding Application to Modify Watts Bar Nuclear Plant Unit 1 Technical Specifications to Extend Surveillance Requirement 3.3.1.5, 3.3.2.2, and 3.3.6.2 Specified ... ML18155A4872018-06-0404 June 2018 Response to Request for Additional Information Regarding Cycle 1 Steam Generator Tube Inspection Report CNL-18-061, Response to NRC Request for Supplemental Information Related to Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools2018-05-31031 May 2018 Response to NRC Request for Supplemental Information Related to Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools CNL-18-058, Supplement to Application to Revise Watts Bar Nuclear Plant Unit 2 - License Condition 2.C(4) PAD4TCD (391-WBN-TS-18-03)2018-04-27027 April 2018 Supplement to Application to Revise Watts Bar Nuclear Plant Unit 2 - License Condition 2.C(4) PAD4TCD (391-WBN-TS-18-03) NL-18-044, Browns Ferry Units 1, 2, and 3; Sequoyah Units 1 and 2; Watts Bar Units 1 and 2 - Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Pre2018-04-19019 April 2018 Browns Ferry Units 1, 2, and 3; Sequoyah Units 1 and 2; Watts Bar Units 1 and 2 - Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Prec CNL-18-044, Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Precipitation.2018-04-19019 April 2018 Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Precipitation. 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Text
Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-15-220 October7, 2015 10 CFR 50.36 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 2 Construction Permit No. CPPR-92 NRC Docket No. 50-391
Subject:
Watts Bar Nuclear Plant Unit 2, Response to Request for Additional Information - Developmental Revision I Technical Specification Section 3.8 -
Diesel Generator Batteries
References:
- 1. Electronic Mail from J. Poole (NRC) to G. Arent (TVA), Batteries, dated October 5, 2015
- 2. TVA Letter to NRC, Watts Bar Nuclear Plant Unit 2 - Submittal of Developmental Revision I of the Unit 2 Technical Specification & Technical Specification Bases and Developmental Revision D of the Unit 2 Technical Requirements Manual and Technical Requirements Manual Bases, dated June 16, 2014 [ML14169A525]
The purpose of this letter is to respond to a request for additional information (RAI) provided in Reference 1. Tennessee Valley Authority (TVA) was requested to confirm that the Diesel Generator batteries are designed to operate at 50o Fahrenheit (F). This question was identified by the Nuclear Regulatory Commission during their review of Technical Specification (TS) 3.8 provided in Development Revision I of the Watts Bar Nuclear Plant Unit 2 TSs (Reference 2).
The enclosure provides TVAs response to the Reference 1 RAI regarding batteries.
There are no new regulatory commitments associated with this letter. Please direct any questions concerning this matter to Gordon Arent at (423) 365-2004.
U.S. Nuclear Regulatory Commission CNL-15-220 Page 2 October 7, 2015 I declare under penalty of perjury that the foregoing is true and correct. Executed on the 7th day of October 2015.
Respectfully, Digitally signed by J. W. Shea J. W. Shea DN: cn=J. W. Shea, o=Tennessee Valley Authority, ou=Nuclear Licensing, email=jwshea@tva.gov, c=US Date: 2015.10.07 19:14:15 -04'00' J. W. Shea Vice President, Nuclear Licensing
Enclosure:
Response to NRC Request For Additional Information - Diesel Generator Battery Temperature cc (Enclosure):
U.S. Nuclear Regulatory Commission, Region II NRC Senior Resident Inspector - Watts Bar Nuclear Plant, Unit 2 NRC Project Manager - Watts Bar Nuclear Plant, Unit 2
Enclosure Response to NRC Request For Additional Information - Diesel Generator Battery Temperature
Background
By letter dated June 16, 2014, Tennessee Valley Authority (TVA) submitted the Watts Bar Nuclear Plant (WBN) Unit 2 Developmental Revision I of the Technical Specifications (TS) and TS Bases, and Developmental Revision D of the WBN Unit 2 Technical Requirements Manual (TRM) and TRM Bases to the Nuclear Regulatory Commission (NRC) (Reference 1). By electronic mail (email) dated October 5, 2015, the NRC provided a request for additional information (RAI) regarding TS Section 3.8 of Developmental Revision I (Reference 2).
The following response to the Reference 2 RAI addresses the NRC staff concerns related to the design of the Diesel Generator (DG) batteries.
NRC RAI TS 3.8.6.3 establishes battery operability based on battery cell parameters and average electrolyte temperatures for vital and DG batteries. If the average electrolyte temperature of the representative cells is outside the lower limit (< 60oF for vital batteries and < 50oF for DG batteries), the battery is considered inoperable. The staff requested information about Station battery sizing and testing criteria for 60oF ambient temperature and DG battery at 50oF ambient temperature.
The applicant provided details on correction factors for station batteries for temperature range at and above 60oF and correction factors for DG batteries for temperature range at and above 60oF and NOT 50oF. The staff recommends that the applicant confirm that the DG batteries are designed for operating at 50oF.
TVA Response Based on TVAs review of 125VDC Diesel Generator Battery sizing analysis calculation WBNEEBMSTI110062; the design temperature used for sizing the DG batteries is 50oF. provides pages from the calculation confirming the use of 50oF The cell sizing factor for 50oF corresponds to 1.19 and is obtained from Table 1 of IEEE Standard 485, IEEE Recommended Practice for Sizing Lead-Acid Batteries for Stationary Applications (Attachment 2). Therefore, TVA confirms that the DG batteries are designed for operating at 50oF.
References
- 1. TVA Letter to NRC, Watts Bar Nuclear Plant Unit 2 - Submittal of Developmental Revision I of the Unit 2 Technical Specification & Technical Specification Bases and Developmental Revision D of the Unit 2 Technical Requirements Manual and Technical Requirements Manual Bases, dated June 16, 2014 [ML14169A525].
- 2. Email from J Poole (NRC) to G. Arent (TVA), Batteries, dated October 5, 2015.
CNL-15-220 E-1
ATTACHMENT 1 TVA Calculation WBNEEBMSTI110062, 125VDC Diesel Generator (DG) Control Power System Evaluation Extracted Pages
NPG CALCULATION COVERSHEET I CTS UPDATE Page 1 REY 0 EDMS/RIMS NO. CTSJYPE; EDMS TYPE:
90021480004/826 900202 406 calculation CALCULATIONS (NUCLEAR) cak: Trtle:
125VDC DIESEL GENERATOR (DG) CONTROL POWER SYSTEM EVALUATION BBANQH NVMBER CYB REV NEW REV CALCID NUC WBN EEB WBNEEBMSmt0062 028 CTS UPDATE ONLY 0 NO CTS CHANGES
- ~ ~__..-'.v 10(
(Verifier and Approval Signatures Not Required) (For calc revision, has been and no CTS changes required)
Y.!::i1I (check one) SVSTEMS UNIDS o181. 1 O. 2 0. 3 D I
082 NIA APPLICABLE DESIGN pOCUMEN!(§)
I I pCN.E[)C NIA CLASS!RCADON See Bev Log NIA E OUAUJY SAEED' RELATEP7 UNVEBIREP SPECIAL REQUIREMENTS 1 oeslGN OIJJPUT SAR/TS and/or !SfSI
.ei:1...t.TED? (If yes, QB = yes) a"'" JMPTION &NrvnA uumNG
~ -* - .. -*
Yes 181 Non I I
£ , K Yes 181 No L I Yes D No 181 Yes D
- No 181 Yes D No~ Yes D No 181 CALCULATION NUMBER BEOl.JESTOR PBEPABING QISC!PUNE VERIFICATION METHOD
- 1NEW METHOD OE AN6LYS!S Name: vupetel PHONE: 301*228-7658 EEB Design Review 0 Yes 181 No PREPARER v.r:NAMEAN~Sl~./7 DATE CHECKER (PRl~NAMEA~SIGN) . DATE VlnuPatel ~cc.>CY to/>/,?_ DSBhatla (\,(~~ 1o/2Ji,_
VERIFIER (PRINT NAME ~G~ h . - DATE APPROVAL (PRINT NAME AND SIGN) DATE FAJl.~oQ SoF1 { fl- d'- - 10/tofrv ~Cox ~~ ~
10
//1fi2 I
STATEMENT OE PRQBL.EMIABSTRACT STATEMENT of PROBLEM:
Verify the adequacy of the design and compliance with design criteria and SAR requirements. Review and document and Impact.
ABSTRACT:
- This calculation evaluate the adequacy of the 125 VDC DG Control Power System battery sizing, charger sizing, protective devlc1 sizing, short circuit and cpordlnation, Appendix R, fleg. Gulde 1.75 - Associated Circuits, cascade fuses and maximum voltag.e to the control circuit components. Equipment submerged due to MELB event Is identified
- and the impact of Its submergence on the 125 VDC DG Control Power System Is evaluated in Appendix I. See Section 8.0 and 9.0 for results and conclusions.
The following revisions are Revision Log Change Only: 17, 21 The revision log changes must be worked in conjunction with the full version that issued the entire calculation.
See revision log for total pages and FSAR and Tech Spec compliance U:GmIUTY EVALUATED AND ACCE~ FOR ISSUE A-tl. /~ /1 InltJaJs: Oate ; __ /d(r:1.e.//2 MICROACHE/EACHE . Yes r l No D ACHE NUMBER(S)
TVA40532 Page 1 of2 NEDP*2-1 (10.31*2011]
WBN EEB-MS-Till-0062 Prepared By ---=!A=JC.r.,;;;____ Date '-22 -B Checked By JP;?i,.pi
~---
Date ;/J-2/4'3
~1 Page 6 The purpose of this calculation is to evaluate the adequacy of the 125VDCDiesel Generator Control Power System for compliance with FSAR and design criteria requirements for the following:
-battery sizing
-battery charger sizing
-protective device sizing
-short-circuit protection and coordination
-Appendix R power supply and associated circuits
-Reg Guide 1.75 associated circuits
-cascade fuse analysis
-voltage to components The purpose of this calculation is also to evaluate the impact of the MELB on fut.I 125V DC Diesel Generator Control Power System and demonstrate that in the event of its loss the plant's safe shutdown can be successfully achieved.
2.0 Assumptions Refer to Section 5.0 for documentation and justification of assumptions.
3.0 References and Sources of Design Input Data 3.1 WBN FSAR Sections 8.3.
3.2 Design Criteria WB-DC-30-27, "AC and DC Control Power Systems", DIMS WB-DC-30-27-1 (B26890324040), WB-30-27-2 (826900510078).
3.3 WBN Preop Test 14D R4.
3.4 TVA drawings and vendor documents listed below:
15N210-4 RF 15W814-5 RJ 1-45W727 R03 l-45W728-l R02 1-45W760-82-l R02, -2 ROl, -3 R03, -4 R02, -5 ROO, -6 R02, -11 ROO, -12 ROl, -13 ROI, -14 R02, -15 ROO, -16 R02, -20 R02, -21 ROO 45Wl761-l RM 45Wl762-l RH 45Wl763-l RK 45Wl780-l RG, -2 RD, -3 RF, -4 RF, -5 RC, -6 RE THIS PAGE ADDED BY REVISION 14
WBN EEB-MS-Till-0062 Prepared By~ Date :£.§£2 Checked By: .......... . I) .
Date: :i- z..- '..:z Page 7 45W1781-1 RN, -2 RD, -3 RG, -4 RF, -5 RC, -6 RE 45W1782-1 RE, -2 RB, -3 RD, -4 RB, -5 RB, -6 RC 45W1787-1 RG 45W2761-1 RJ 45W2763-1 RL 45W2780-1 RK, -2 RE, -3 RH, -4 RG, -5 RC, -6 RF 45W2781-1 RL, -2 RE, -3 RF, -4 RH, -5 RB, -6 RE 47E235-29 R04, -30 R03 Vendor Documents
/?.II Contract 83090 DG Manual VOl 1 & 2, TVA IDs 979, 980 (DG lA-A, lB-B, 2A-A, 2B-B); DG Manual Vol 1 & 2, TVA IDs 1548, 1549 (DG C-S) 650-242, 244; 655-241 6036B11010 RD, SHEETS 1-10 6036C04501 RB C379C11501 R904 6036C11501 R901 6036C11501 R902 6036F11502 RB 3.5 DS-ES.1.1 RS,"Substitution standard for Low-Voltage Power and control Fuses (600 Volts or Less)".
IEEE Standard 485 (1978), IEEE Recommended Practice for Sizing Large Lead Storage Batteries for Generating Stations and Substations".
3.7 SQN Calculation SQN-CPS-007 RO, "Diesel Generator Battery Capacity", B43861210901.
- 3. 8 SQN Calculation SQN-CPS-012 Rl, "Diesel Generator I~ If Lube Oil Pump Voltage", B87910118002.
3.9 Walkdown data for DG distribution panels included as attachment to memo from R.W. Bradford to H.B.
Bounds, dated Nov. 28, 1988, "Watts Bar Nuclear Plant-Unit 1 and 2-Walkdown of Electrical Equipment
-Walkdown Procedure WP-37 11 , C24881128629.
3.10 National Electric Code, 1987, Chapter 9, Table 8, "Properties of Conductors" (de resistance at 25° C) .
This Sheet Added By Rev 11
WBN EEB-MS-Till-0062 Prepared By: _ _?__~__.;?_'k.____ Date: 6/2-Y/t:/5""'
7 Checked By: _ _ -#-~<..-=----- Date: ~/'24!f )'b-Page 10 5.0
- 5. The minimum ambient temperature of the rooms containing the diesel batteries is 50° F.
Justifioation: TVA drawings 47E235-29R2 and 47E235-30RO list the average DG room temperature at 75° F and a normal minimum of so° F. Ref. DCN M11594A.
5.2 The diesel batteries shall support three start attempts; one at the beginning of its 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> duty cycle, one at the 29 minute mark and the other at the end of the 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Justification: DCN S-34918-A limits the number of starting attempts to three during the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Station Blackout event. If the diesel fails to RJ°l reach 200 rpm within 5 seconds of initial start, a fail to start condition exists and the diesel is locked out, requiring a manual reset for a restart attempt. Experience with the diesel has proven that if it does not start at the initial start command, the time required for response and problem correction is significant such that it is reasonable to assume that the first restart attempt will occur in the first 30 minute period. Assuming the third and final starting attempt occurs in the final minute is conservative.
5.3 It is assumed for short-circuit analysis that the DG battery system voltage is determined by the base emf of the battery at 2.06 volts-per-cell such that the battery voltage used in analysis is 119.5V (58 cells x 2.06V).
Justification: Under short-circuit conditions, the charger voltage declines as the output is current-limited. The use of 2.06 volts per cell will provide conservative results.
This Sheet Added By Rev 19
WBN EEB-MS-Ti ll- 006 2 PREPARED BY -fJ.?t.,'){
PAGE 15 11 CHECKED BY ~--
Battery Sizing Calculation IEEE 485-1983 Work Sheet DIESEL BATTERIES SIMULTANEOUS MOTOR STARTS Period load Change Duration Time to End Capacity Required In Load of Period of Section At T Min Section Section (A) (Amps) (minutes) Size Pos Pl Section 1 - First Period Only / o~. 't I 1 A1=
10824
~ A1-0= ~ M1= T=M1 72 .33
-f00*£1 I Of.4 Section 2 - deleted for clarity
. F Section 3 ; 1* ~Ist Th s . o ree ect1ons nly IOi I 02.'24y l 1 A1 1
- . . 1oe .;~ .. A1-0 = ~ M1 = '2 -29 .
1 T;:M1 :M3 30 47.33 ~
2 A2=n.:l11s .e *&4A2-A1 = (91 .2) M2= 28 T=M2:M3 29 47.33 (1 .93) 3 A3= -&+:e
-8'1; . o4 A3-A2 = 65.0 M3= T=M3 72 .33 o.9o R/'1
.?;2. ;i I Total .. . ~
1*'26 ~
Section 4 - deleted for clarity Section 51.PS.FJ.rst Five Periods Only A1-:-
.Jii* i~ (,.1i
~
1 M1= T= M1 : ~A5 240 ; 6.:: ~
2 A2=f7.~l Mi.!H7-04 A2-A1 = (91 .2) M2= 28 T='= M2 :M5 239 1 e.,'J0 (5.70) 3 A3=8'J..:lla1 .a ea e4A3-A2 = 65.0 M3= 1 T=M3 :M5 21 1 19.00 3.42 4 A4=1Pil 1i.O1Su24A4-A3 = (66.8) M4= 209 T=M4 :M5 210 19.00 (3.52) 5 A5=78.~f +M A5-A4 = 63.4 *Ms= °T=M5 72 .33
. 78* 64 0.88 Total ... 4-:88-
/.81;,
Battery Cell Size (No. Of Pos Plates) = Temp Car Factor X Aging Factor X Design Margin
). 8 b
= 1.19 x 1 .2s x 1 .ox 1 .aa ~ 85
= ~*~ Positive Plates
- .,;7 P,27 THIS PAGE ADDED BY REVISION 19
ATTACHMENT 2 IEEE Std 485-1997(R2003)
IEEE Recommended Practice for Sizing Lead-Acid Batteries for Stationary Applications Extracted Pages
IEEE Std 485-1997(R2003)
(Revision of IEEE Std 485-1983)
IEEE Recommended Practice for Sizing Lead-Acid Batteries for Stationary Applications Sponsor IEEE Standards Coordinating Committee 29 on Stationary Batteries Reaffirmed 11 September 2003 Approved 20 March 1997 IEEE Standards Board Abstract: Methods for defining the de load and for sizing a lead-acid battery to supply that load for stationary battery applications in full float operations are described . Some factors relating to cell selection are provided for consideration. Installation , maintenance, qualification , testing proce-dures, and consideration of battery types other than lead-acid are beyond the scope of this recom-mended practice. Design of the de system and sizing of the battery charger(s) are also beyond the scope of this recommended practice.
Keywords: battery duty cycle , cell selection , de load, full float operation , lead-acid batteries, rated capacity, sizing , stationary applications, valve-regulated lead-acid (VRLA) cell , vented battery The Institute of Electrical and Electronics Engineers, Inc.
345 East 47th Street, New York , NY 10017-2394, USA Copyright © 1997 by the Institute of Electrical and Electronics Engineers, Inc.
All rights reserved . Published 1997. Printed in the United States of America .
ISBN 1-55937-913-8 No part of this publication may be reproduced in any form, in an electronic retrieval system or otherwise, without the prior written permission of the publisher.
Copyright The Institute of Electrical and Electronics Engineers , Inc . Document provided by IHS Licensee=Tennessee Valley Authority/5919845100, Provided by IHS under license with IEEE User,,,ACBANGAL, 03/09/2004 12:55 :52 MST Questions or comments about this message: please call the Document Policy Group at 303*397-2295.
IEEE Std 485-1997 IEEE RECOMMENDED PRACTICE FOR Note that the "margins" required by 6.3.1.5 and 6.3.3 of IEEE Std 323-1 983 are to be applied during "quali-fication" and are not related to "design margin."
Table 1-Cell size correction factors for temperature Electrolyte temperature Cell size Electrolyte temperature Cell size correction correction (o F) (0 C) factor (o F) (o C) factor 25 -3.9 1.520 78 25.6 0.994 30 - I.I 1.430 79 26.1 0.987 35 1.7 1.350 80 26.7 0.980 r:
40 4.4 1.300 81 27.2 0.976
"-"- _ 72 - J .22_0 82 27.8 0.972
'{ 'I" '[ y rt" y v ~
50 10.0 1.190 A 83 28.3 0.968
.... - ... "TZ....u ,. - l.. -
-- l.. l..
A A
- ~ ~~
0.964
~
) J" ~ J~ - -~ 84 28.9 60 15.6 1.110 85 29.4 0.960 65 18.3 1.080 86 30.0 0.956 66 18.9 1.072 87 30.6 0.952 67 19.4 1.064 88 31.1 0.948 68 20.0 1.056 89 31.6 0.944 69 20.6 1.048 90 32.2 0.940 70 21. 1 1.040 95 35.0 0.930 71 21.7 1.034 100 37.8 0.910 72 22.2 1.029 105 40.6 0.890 73 22.8 1.023 110 43.3 0.880 74 23.4 1.017 11 5 46.1 0.870 75 23.9 1.011 120 48.9 0.860 76 24.5 1.006 125 51.7 0.850 77 25 .0 1.000 NOTE-This table is based on vented lead-acid nominal 1.215 specific gravity. However, it may be used for vented cells with up to a 1.300 specific gravity. For cells of other designs, refer to the manufacturer.
6.2.3 Aging factor As a rule, the performance of a lead-acid battery is relatively stable throughout most of its life, but begins to decline with increasing rapidity in its latter stages, with the "knee" of its life versus performance curve occurring at approximately 80% of its rated performance.
IEEE Std 450-1995 recommends that a battery be replaced when its actual performance drops to 80% of its rated performance because there is little life to be gained by allowing operation beyond this point. Therefore, to ensure that the battery is capable of meeting its design loads throughout its service life, the battery's rated capacity should be at least 125% ( 1.25 aging fac tor) of the load expected at the end of its service life.
Exceptions to this rule exist. For example, some manufacturers recommend that vented batteries with Plante, modified Plante, and round plate designs be replaced when their measured capacity drops below 100% of R
Co pyright The Institute of Electrical and Electronics Engineers , Inc. Document provided by IHS licensee=Tennessee Valley Authority/5919845100, Provided by IHS under license with IEEE User=ACBANGAL, 03/09/2004 12:55 :52 MST Questions or comments about this message: please call the Document Policy Group at 303-397-2295.
Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-15-220 October7, 2015 10 CFR 50.36 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 2 Construction Permit No. CPPR-92 NRC Docket No. 50-391
Subject:
Watts Bar Nuclear Plant Unit 2, Response to Request for Additional Information - Developmental Revision I Technical Specification Section 3.8 -
Diesel Generator Batteries
References:
- 1. Electronic Mail from J. Poole (NRC) to G. Arent (TVA), Batteries, dated October 5, 2015
- 2. TVA Letter to NRC, Watts Bar Nuclear Plant Unit 2 - Submittal of Developmental Revision I of the Unit 2 Technical Specification & Technical Specification Bases and Developmental Revision D of the Unit 2 Technical Requirements Manual and Technical Requirements Manual Bases, dated June 16, 2014 [ML14169A525]
The purpose of this letter is to respond to a request for additional information (RAI) provided in Reference 1. Tennessee Valley Authority (TVA) was requested to confirm that the Diesel Generator batteries are designed to operate at 50o Fahrenheit (F). This question was identified by the Nuclear Regulatory Commission during their review of Technical Specification (TS) 3.8 provided in Development Revision I of the Watts Bar Nuclear Plant Unit 2 TSs (Reference 2).
The enclosure provides TVAs response to the Reference 1 RAI regarding batteries.
There are no new regulatory commitments associated with this letter. Please direct any questions concerning this matter to Gordon Arent at (423) 365-2004.
U.S. Nuclear Regulatory Commission CNL-15-220 Page 2 October 7, 2015 I declare under penalty of perjury that the foregoing is true and correct. Executed on the 7th day of October 2015.
Respectfully, Digitally signed by J. W. Shea J. W. Shea DN: cn=J. W. Shea, o=Tennessee Valley Authority, ou=Nuclear Licensing, email=jwshea@tva.gov, c=US Date: 2015.10.07 19:14:15 -04'00' J. W. Shea Vice President, Nuclear Licensing
Enclosure:
Response to NRC Request For Additional Information - Diesel Generator Battery Temperature cc (Enclosure):
U.S. Nuclear Regulatory Commission, Region II NRC Senior Resident Inspector - Watts Bar Nuclear Plant, Unit 2 NRC Project Manager - Watts Bar Nuclear Plant, Unit 2
Enclosure Response to NRC Request For Additional Information - Diesel Generator Battery Temperature
Background
By letter dated June 16, 2014, Tennessee Valley Authority (TVA) submitted the Watts Bar Nuclear Plant (WBN) Unit 2 Developmental Revision I of the Technical Specifications (TS) and TS Bases, and Developmental Revision D of the WBN Unit 2 Technical Requirements Manual (TRM) and TRM Bases to the Nuclear Regulatory Commission (NRC) (Reference 1). By electronic mail (email) dated October 5, 2015, the NRC provided a request for additional information (RAI) regarding TS Section 3.8 of Developmental Revision I (Reference 2).
The following response to the Reference 2 RAI addresses the NRC staff concerns related to the design of the Diesel Generator (DG) batteries.
NRC RAI TS 3.8.6.3 establishes battery operability based on battery cell parameters and average electrolyte temperatures for vital and DG batteries. If the average electrolyte temperature of the representative cells is outside the lower limit (< 60oF for vital batteries and < 50oF for DG batteries), the battery is considered inoperable. The staff requested information about Station battery sizing and testing criteria for 60oF ambient temperature and DG battery at 50oF ambient temperature.
The applicant provided details on correction factors for station batteries for temperature range at and above 60oF and correction factors for DG batteries for temperature range at and above 60oF and NOT 50oF. The staff recommends that the applicant confirm that the DG batteries are designed for operating at 50oF.
TVA Response Based on TVAs review of 125VDC Diesel Generator Battery sizing analysis calculation WBNEEBMSTI110062; the design temperature used for sizing the DG batteries is 50oF. provides pages from the calculation confirming the use of 50oF The cell sizing factor for 50oF corresponds to 1.19 and is obtained from Table 1 of IEEE Standard 485, IEEE Recommended Practice for Sizing Lead-Acid Batteries for Stationary Applications (Attachment 2). Therefore, TVA confirms that the DG batteries are designed for operating at 50oF.
References
- 1. TVA Letter to NRC, Watts Bar Nuclear Plant Unit 2 - Submittal of Developmental Revision I of the Unit 2 Technical Specification & Technical Specification Bases and Developmental Revision D of the Unit 2 Technical Requirements Manual and Technical Requirements Manual Bases, dated June 16, 2014 [ML14169A525].
- 2. Email from J Poole (NRC) to G. Arent (TVA), Batteries, dated October 5, 2015.
CNL-15-220 E-1
ATTACHMENT 1 TVA Calculation WBNEEBMSTI110062, 125VDC Diesel Generator (DG) Control Power System Evaluation Extracted Pages
NPG CALCULATION COVERSHEET I CTS UPDATE Page 1 REY 0 EDMS/RIMS NO. CTSJYPE; EDMS TYPE:
90021480004/826 900202 406 calculation CALCULATIONS (NUCLEAR) cak: Trtle:
125VDC DIESEL GENERATOR (DG) CONTROL POWER SYSTEM EVALUATION BBANQH NVMBER CYB REV NEW REV CALCID NUC WBN EEB WBNEEBMSmt0062 028 CTS UPDATE ONLY 0 NO CTS CHANGES
- ~ ~__..-'.v 10(
(Verifier and Approval Signatures Not Required) (For calc revision, has been and no CTS changes required)
Y.!::i1I (check one) SVSTEMS UNIDS o181. 1 O. 2 0. 3 D I
082 NIA APPLICABLE DESIGN pOCUMEN!(§)
I I pCN.E[)C NIA CLASS!RCADON See Bev Log NIA E OUAUJY SAEED' RELATEP7 UNVEBIREP SPECIAL REQUIREMENTS 1 oeslGN OIJJPUT SAR/TS and/or !SfSI
.ei:1...t.TED? (If yes, QB = yes) a"'" JMPTION &NrvnA uumNG
~ -* - .. -*
Yes 181 Non I I
£ , K Yes 181 No L I Yes D No 181 Yes D
- No 181 Yes D No~ Yes D No 181 CALCULATION NUMBER BEOl.JESTOR PBEPABING QISC!PUNE VERIFICATION METHOD
- 1NEW METHOD OE AN6LYS!S Name: vupetel PHONE: 301*228-7658 EEB Design Review 0 Yes 181 No PREPARER v.r:NAMEAN~Sl~./7 DATE CHECKER (PRl~NAMEA~SIGN) . DATE VlnuPatel ~cc.>CY to/>/,?_ DSBhatla (\,(~~ 1o/2Ji,_
VERIFIER (PRINT NAME ~G~ h . - DATE APPROVAL (PRINT NAME AND SIGN) DATE FAJl.~oQ SoF1 { fl- d'- - 10/tofrv ~Cox ~~ ~
10
//1fi2 I
STATEMENT OE PRQBL.EMIABSTRACT STATEMENT of PROBLEM:
Verify the adequacy of the design and compliance with design criteria and SAR requirements. Review and document and Impact.
ABSTRACT:
- This calculation evaluate the adequacy of the 125 VDC DG Control Power System battery sizing, charger sizing, protective devlc1 sizing, short circuit and cpordlnation, Appendix R, fleg. Gulde 1.75 - Associated Circuits, cascade fuses and maximum voltag.e to the control circuit components. Equipment submerged due to MELB event Is identified
- and the impact of Its submergence on the 125 VDC DG Control Power System Is evaluated in Appendix I. See Section 8.0 and 9.0 for results and conclusions.
The following revisions are Revision Log Change Only: 17, 21 The revision log changes must be worked in conjunction with the full version that issued the entire calculation.
See revision log for total pages and FSAR and Tech Spec compliance U:GmIUTY EVALUATED AND ACCE~ FOR ISSUE A-tl. /~ /1 InltJaJs: Oate ; __ /d(r:1.e.//2 MICROACHE/EACHE . Yes r l No D ACHE NUMBER(S)
TVA40532 Page 1 of2 NEDP*2-1 (10.31*2011]
WBN EEB-MS-Till-0062 Prepared By ---=!A=JC.r.,;;;____ Date '-22 -B Checked By JP;?i,.pi
~---
Date ;/J-2/4'3
~1 Page 6 The purpose of this calculation is to evaluate the adequacy of the 125VDCDiesel Generator Control Power System for compliance with FSAR and design criteria requirements for the following:
-battery sizing
-battery charger sizing
-protective device sizing
-short-circuit protection and coordination
-Appendix R power supply and associated circuits
-Reg Guide 1.75 associated circuits
-cascade fuse analysis
-voltage to components The purpose of this calculation is also to evaluate the impact of the MELB on fut.I 125V DC Diesel Generator Control Power System and demonstrate that in the event of its loss the plant's safe shutdown can be successfully achieved.
2.0 Assumptions Refer to Section 5.0 for documentation and justification of assumptions.
3.0 References and Sources of Design Input Data 3.1 WBN FSAR Sections 8.3.
3.2 Design Criteria WB-DC-30-27, "AC and DC Control Power Systems", DIMS WB-DC-30-27-1 (B26890324040), WB-30-27-2 (826900510078).
3.3 WBN Preop Test 14D R4.
3.4 TVA drawings and vendor documents listed below:
15N210-4 RF 15W814-5 RJ 1-45W727 R03 l-45W728-l R02 1-45W760-82-l R02, -2 ROl, -3 R03, -4 R02, -5 ROO, -6 R02, -11 ROO, -12 ROl, -13 ROI, -14 R02, -15 ROO, -16 R02, -20 R02, -21 ROO 45Wl761-l RM 45Wl762-l RH 45Wl763-l RK 45Wl780-l RG, -2 RD, -3 RF, -4 RF, -5 RC, -6 RE THIS PAGE ADDED BY REVISION 14
WBN EEB-MS-Till-0062 Prepared By~ Date :£.§£2 Checked By: .......... . I) .
Date: :i- z..- '..:z Page 7 45W1781-1 RN, -2 RD, -3 RG, -4 RF, -5 RC, -6 RE 45W1782-1 RE, -2 RB, -3 RD, -4 RB, -5 RB, -6 RC 45W1787-1 RG 45W2761-1 RJ 45W2763-1 RL 45W2780-1 RK, -2 RE, -3 RH, -4 RG, -5 RC, -6 RF 45W2781-1 RL, -2 RE, -3 RF, -4 RH, -5 RB, -6 RE 47E235-29 R04, -30 R03 Vendor Documents
/?.II Contract 83090 DG Manual VOl 1 & 2, TVA IDs 979, 980 (DG lA-A, lB-B, 2A-A, 2B-B); DG Manual Vol 1 & 2, TVA IDs 1548, 1549 (DG C-S) 650-242, 244; 655-241 6036B11010 RD, SHEETS 1-10 6036C04501 RB C379C11501 R904 6036C11501 R901 6036C11501 R902 6036F11502 RB 3.5 DS-ES.1.1 RS,"Substitution standard for Low-Voltage Power and control Fuses (600 Volts or Less)".
IEEE Standard 485 (1978), IEEE Recommended Practice for Sizing Large Lead Storage Batteries for Generating Stations and Substations".
3.7 SQN Calculation SQN-CPS-007 RO, "Diesel Generator Battery Capacity", B43861210901.
- 3. 8 SQN Calculation SQN-CPS-012 Rl, "Diesel Generator I~ If Lube Oil Pump Voltage", B87910118002.
3.9 Walkdown data for DG distribution panels included as attachment to memo from R.W. Bradford to H.B.
Bounds, dated Nov. 28, 1988, "Watts Bar Nuclear Plant-Unit 1 and 2-Walkdown of Electrical Equipment
-Walkdown Procedure WP-37 11 , C24881128629.
3.10 National Electric Code, 1987, Chapter 9, Table 8, "Properties of Conductors" (de resistance at 25° C) .
This Sheet Added By Rev 11
WBN EEB-MS-Till-0062 Prepared By: _ _?__~__.;?_'k.____ Date: 6/2-Y/t:/5""'
7 Checked By: _ _ -#-~<..-=----- Date: ~/'24!f )'b-Page 10 5.0
- 5. The minimum ambient temperature of the rooms containing the diesel batteries is 50° F.
Justifioation: TVA drawings 47E235-29R2 and 47E235-30RO list the average DG room temperature at 75° F and a normal minimum of so° F. Ref. DCN M11594A.
5.2 The diesel batteries shall support three start attempts; one at the beginning of its 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> duty cycle, one at the 29 minute mark and the other at the end of the 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Justification: DCN S-34918-A limits the number of starting attempts to three during the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Station Blackout event. If the diesel fails to RJ°l reach 200 rpm within 5 seconds of initial start, a fail to start condition exists and the diesel is locked out, requiring a manual reset for a restart attempt. Experience with the diesel has proven that if it does not start at the initial start command, the time required for response and problem correction is significant such that it is reasonable to assume that the first restart attempt will occur in the first 30 minute period. Assuming the third and final starting attempt occurs in the final minute is conservative.
5.3 It is assumed for short-circuit analysis that the DG battery system voltage is determined by the base emf of the battery at 2.06 volts-per-cell such that the battery voltage used in analysis is 119.5V (58 cells x 2.06V).
Justification: Under short-circuit conditions, the charger voltage declines as the output is current-limited. The use of 2.06 volts per cell will provide conservative results.
This Sheet Added By Rev 19
WBN EEB-MS-Ti ll- 006 2 PREPARED BY -fJ.?t.,'){
PAGE 15 11 CHECKED BY ~--
Battery Sizing Calculation IEEE 485-1983 Work Sheet DIESEL BATTERIES SIMULTANEOUS MOTOR STARTS Period load Change Duration Time to End Capacity Required In Load of Period of Section At T Min Section Section (A) (Amps) (minutes) Size Pos Pl Section 1 - First Period Only / o~. 't I 1 A1=
10824
~ A1-0= ~ M1= T=M1 72 .33
-f00*£1 I Of.4 Section 2 - deleted for clarity
. F Section 3 ; 1* ~Ist Th s . o ree ect1ons nly IOi I 02.'24y l 1 A1 1
- . . 1oe .;~ .. A1-0 = ~ M1 = '2 -29 .
1 T;:M1 :M3 30 47.33 ~
2 A2=n.:l11s .e *&4A2-A1 = (91 .2) M2= 28 T=M2:M3 29 47.33 (1 .93) 3 A3= -&+:e
-8'1; . o4 A3-A2 = 65.0 M3= T=M3 72 .33 o.9o R/'1
.?;2. ;i I Total .. . ~
1*'26 ~
Section 4 - deleted for clarity Section 51.PS.FJ.rst Five Periods Only A1-:-
.Jii* i~ (,.1i
~
1 M1= T= M1 : ~A5 240 ; 6.:: ~
2 A2=f7.~l Mi.!H7-04 A2-A1 = (91 .2) M2= 28 T='= M2 :M5 239 1 e.,'J0 (5.70) 3 A3=8'J..:lla1 .a ea e4A3-A2 = 65.0 M3= 1 T=M3 :M5 21 1 19.00 3.42 4 A4=1Pil 1i.O1Su24A4-A3 = (66.8) M4= 209 T=M4 :M5 210 19.00 (3.52) 5 A5=78.~f +M A5-A4 = 63.4 *Ms= °T=M5 72 .33
. 78* 64 0.88 Total ... 4-:88-
/.81;,
Battery Cell Size (No. Of Pos Plates) = Temp Car Factor X Aging Factor X Design Margin
). 8 b
= 1.19 x 1 .2s x 1 .ox 1 .aa ~ 85
= ~*~ Positive Plates
- .,;7 P,27 THIS PAGE ADDED BY REVISION 19
ATTACHMENT 2 IEEE Std 485-1997(R2003)
IEEE Recommended Practice for Sizing Lead-Acid Batteries for Stationary Applications Extracted Pages
IEEE Std 485-1997(R2003)
(Revision of IEEE Std 485-1983)
IEEE Recommended Practice for Sizing Lead-Acid Batteries for Stationary Applications Sponsor IEEE Standards Coordinating Committee 29 on Stationary Batteries Reaffirmed 11 September 2003 Approved 20 March 1997 IEEE Standards Board Abstract: Methods for defining the de load and for sizing a lead-acid battery to supply that load for stationary battery applications in full float operations are described . Some factors relating to cell selection are provided for consideration. Installation , maintenance, qualification , testing proce-dures, and consideration of battery types other than lead-acid are beyond the scope of this recom-mended practice. Design of the de system and sizing of the battery charger(s) are also beyond the scope of this recommended practice.
Keywords: battery duty cycle , cell selection , de load, full float operation , lead-acid batteries, rated capacity, sizing , stationary applications, valve-regulated lead-acid (VRLA) cell , vented battery The Institute of Electrical and Electronics Engineers, Inc.
345 East 47th Street, New York , NY 10017-2394, USA Copyright © 1997 by the Institute of Electrical and Electronics Engineers, Inc.
All rights reserved . Published 1997. Printed in the United States of America .
ISBN 1-55937-913-8 No part of this publication may be reproduced in any form, in an electronic retrieval system or otherwise, without the prior written permission of the publisher.
Copyright The Institute of Electrical and Electronics Engineers , Inc . Document provided by IHS Licensee=Tennessee Valley Authority/5919845100, Provided by IHS under license with IEEE User,,,ACBANGAL, 03/09/2004 12:55 :52 MST Questions or comments about this message: please call the Document Policy Group at 303*397-2295.
IEEE Std 485-1997 IEEE RECOMMENDED PRACTICE FOR Note that the "margins" required by 6.3.1.5 and 6.3.3 of IEEE Std 323-1 983 are to be applied during "quali-fication" and are not related to "design margin."
Table 1-Cell size correction factors for temperature Electrolyte temperature Cell size Electrolyte temperature Cell size correction correction (o F) (0 C) factor (o F) (o C) factor 25 -3.9 1.520 78 25.6 0.994 30 - I.I 1.430 79 26.1 0.987 35 1.7 1.350 80 26.7 0.980 r:
40 4.4 1.300 81 27.2 0.976
"-"- _ 72 - J .22_0 82 27.8 0.972
'{ 'I" '[ y rt" y v ~
50 10.0 1.190 A 83 28.3 0.968
.... - ... "TZ....u ,. - l.. -
-- l.. l..
A A
- ~ ~~
0.964
~
) J" ~ J~ - -~ 84 28.9 60 15.6 1.110 85 29.4 0.960 65 18.3 1.080 86 30.0 0.956 66 18.9 1.072 87 30.6 0.952 67 19.4 1.064 88 31.1 0.948 68 20.0 1.056 89 31.6 0.944 69 20.6 1.048 90 32.2 0.940 70 21. 1 1.040 95 35.0 0.930 71 21.7 1.034 100 37.8 0.910 72 22.2 1.029 105 40.6 0.890 73 22.8 1.023 110 43.3 0.880 74 23.4 1.017 11 5 46.1 0.870 75 23.9 1.011 120 48.9 0.860 76 24.5 1.006 125 51.7 0.850 77 25 .0 1.000 NOTE-This table is based on vented lead-acid nominal 1.215 specific gravity. However, it may be used for vented cells with up to a 1.300 specific gravity. For cells of other designs, refer to the manufacturer.
6.2.3 Aging factor As a rule, the performance of a lead-acid battery is relatively stable throughout most of its life, but begins to decline with increasing rapidity in its latter stages, with the "knee" of its life versus performance curve occurring at approximately 80% of its rated performance.
IEEE Std 450-1995 recommends that a battery be replaced when its actual performance drops to 80% of its rated performance because there is little life to be gained by allowing operation beyond this point. Therefore, to ensure that the battery is capable of meeting its design loads throughout its service life, the battery's rated capacity should be at least 125% ( 1.25 aging fac tor) of the load expected at the end of its service life.
Exceptions to this rule exist. For example, some manufacturers recommend that vented batteries with Plante, modified Plante, and round plate designs be replaced when their measured capacity drops below 100% of R
Co pyright The Institute of Electrical and Electronics Engineers , Inc. Document provided by IHS licensee=Tennessee Valley Authority/5919845100, Provided by IHS under license with IEEE User=ACBANGAL, 03/09/2004 12:55 :52 MST Questions or comments about this message: please call the Document Policy Group at 303-397-2295.