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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-Operating (New/Renewal/Amendments) DKT 50
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 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 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) ML23131A1812023-05-23023 May 2023 Correction to Amendment No. 161 to Facility Operating License No. NPF-90 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) 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 ML22348A0052023-01-25025 January 2023 Issuance of Amendment Nos. 326, 349, and 309; 363 and 35; 159 and 67 Regarding Adoption of TSTF-554, Revise Reactor Coolant Leakage Requirements ML22349A6472023-01-20020 January 2023 Issuance of Amendment Nos. 325, 348, and 308; 362 and 356; and 158 and 66 Regarding Adoption of TSTF-529, Rev. 4, Clarify Use and Application Rules ML22271A9142022-12-0707 December 2022 Issuance of Amendment Nos. 324, 347, and 307; 360 and 354; 157 and 65 Regarding a Revision to the Emergency Action Level Scheme ML22257A0512022-11-0404 November 2022 Issuance of Amendment Nos. 156 and 64 Regarding Adoption of TSTF-205-A, Revision 3, and TSTF-563-A ML22276A1612022-10-24024 October 2022 Issuance of Amendment Nos. 359, 353, 155, & 63 Regarding Adoption of TSTF Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML22187A0192022-09-20020 September 2022 Issuance of Amendment No. 154 Regarding Revision to Technical Specification 3.3.2 to Revise Allowable Value for Trip of Turbine-Driven Main Feedwater Pumps ML22187A1812022-09-20020 September 2022 Issuance of Amendment Nos. 153 and 62 Regarding Extension of Completion Time for Technical Specification 3.7.8 for Inoperable Essential Raw Cooling Water Train ML22014A2062022-05-0404 May 2022 Issuance of Amendment Nos. 152 and 61 Regarding Revision to Technical Specifications to Delete a Redundant Unit of Measure for Certain Radiation Monitors ML21347A9672022-02-0101 February 2022 Correction of Errors Incurred During Issuance of the Initial Facility Operating License, and Issuance of License Amendment Nos. 6, 21, and 39 ML21306A2872022-01-25025 January 2022 Issuance of Amendment No. 60 Regarding Revision of Technical Specification Requirements Specific to the Model D3 Steam Generators That Will No Longer Apply Following Steam Generator Replacement ML21334A2952022-01-18018 January 2022 Issuance of Amendment No. 151 Regarding Revision to TS 3.7.12 for One-Time Exception to Permit Continuous Opening of Auxiliary Building Secondary Containment Enclosure During Unit 2 Steam Generator Replacement ML21334A3892022-01-12012 January 2022 Issuance of Amendment No. 59 Regarding Revision to Steam Generator Tube Rupture Dose Analysis ML21271A1372021-12-16016 December 2021 Issuance of Amendment Nos. 150 and 58 Regarding Modification of Technical Specification Surveillance Requirement 3.6.15.4, Shield Building ML21260A2102021-11-22022 November 2021 Issuance of Amendment No. 57 to Revise Technical Specifications to Change the Steam Generator Secondary Side Water Level ML21189A3072021-11-0303 November 2021 Issuance of Amendment Nos. 149 and 56 Regarding Modification of Technical Specification 5.7.2.19, Containment Leakage Rate Testing Program ML21158A2842021-09-17017 September 2021 Issuance of Amendment Nos. 148 and 55 to Revise Technical Specifications for Function 6.E of Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation ML21153A0492021-07-26026 July 2021 Issuance of Amendment No. 147 Regarding Change to Steam Generator Tube Inspection Frequency and Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-510 ML21161A2392021-06-24024 June 2021 Issuance of Amendment No. 54 Regarding Use of Temperature Adjustment to Voltage Growth Rate for the Generic Letter 95-05 Steam Generator Tube Repair Criteria ML21148A1002021-06-17017 June 2021 Issuance of Amendment No. 53 Regarding Neutron Fluence Calculation Methodology ML21099A2462021-05-14014 May 2021 Issuance of Amendment Nos. 146 and 52 to Adopt TSTF-490, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec ML21078A4842021-05-0505 May 2021 Issuance of Amendment Nos. 145 and 51 for One-Time Change to Technical Specification 3.7.11 to Extend the Completion Time for Main Control Room Chiller Modifications ML21015A0342021-03-0909 March 2021 Issuance of Amendment No. 144 Regarding Post Accident Monitoring Instrumentation ML21034A1692021-02-26026 February 2021 Issuance of Amendment Nos. 143 and 50 Regarding Implementation of Full Spectrumtm Loss-of-Coolant Accident Analysis (LOCA) and New LOCA-Specific Tritium Producing Burnable Absorber Rod Stress Analysis Methodology ML20232C6222021-02-11011 February 2021 Issuance of Amendment Nos. 142 and 49 Regarding Revision to Technical Specifications to Implement WCAP-17661-P-A, Revision 1, Improved RAOC and CAOC Fq Surveillance Technical Specifications (EPID L-2020-LLA-0037 ML21027A1672021-02-0909 February 2021 Issuance of Amendment No. 48 Regarding Use of Alternate Probability of Detection Values for Beginning of Cycle in Support of Operational Assessment ML20350B4932021-01-25025 January 2021 Issuance of Amendment Nos. 352, 346, 141, and 47 Regarding the Adoption of Technical Specification Task Force Traveler, TSTF-569, Revision 2, Revise Response Time Testing Definition ML21005A1252021-01-12012 January 2021 Correction of Errors Incurred During Issuance of License Amendment Nos. 43 and 45 ML20268A0822021-01-12012 January 2021 Issuance of Amendment Nos. 314, 337, and 297; 351 and 345; 140 and 46 Regarding Changes to the Technical Specifications ML20245E4132020-12-0808 December 2020 Issuance of Amendment Nos. 139 and 45 Regarding Revisions to Technical Specification 3.6.15, Shield Building ML20282A3452020-11-19019 November 2020 Issuance of Amendment Nos. 313, 336, 296, 350, 344, 138, and 44 Revise Emergency Plan On-Shift Emergency Medical Technician & Onsite Ambulance Requirements ML20239A7912020-10-28028 October 2020 Issuance of Amendment Nos. 137 and 43 Regarding Revision to Technical Specifications to Adopt Technical Specification Task Force Traveler 541, Revision 2 ML20226A4442020-10-21021 October 2020 Issuance of Amendment No. 42 Regarding Measurement Uncertainty Recapture Power Uprate ML20238C0612020-09-21021 September 2020 Correction of Typographical Error Incurred During Issuance of License Amendment No. 104 ML20167A1482020-08-19019 August 2020 Issuance of Amendment Nos. 136 and 41 Regarding the Automatic Transfer from a Unit Service Station Transformer to a Common Station Service Transformer ML20156A0182020-08-10010 August 2020 Issuance of Amendment No. 40 Regarding Technical Specifications for Steam Generator Tube Repair Sleeve ML20076A1942020-04-30030 April 2020 Issuance of Amendment Nos. 134 and 38 Regarding Adopting the Title 10 CFR Section 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Plants ML20057E2422020-03-30030 March 2020 Issuance of Amendment Nos. 133 and 37 Regarding Changes to Technical Specifications Pertaining to Diesel Generator Start Instrumentation (EPID-L-2020-LLA-0003) ML20028F7332020-02-28028 February 2020 Issuance of Amendment Nos. 132 and 36 Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-425, Revision 3 ML20024F8352020-02-24024 February 2020 Issuance of Amendment No. 35 Regarding One-Time Extension of Completion Time for Technical Specification 3.7.8 for Inoperable Essential Raw Cooling Water Train ML20015A4792020-01-30030 January 2020 Correction to Amendment No. 30 to Facility Operating License Npf-96 Regarding Use of Optimized Zirlo Fuel Rod Cladding ML19336C5192019-12-10010 December 2019 Issuance of Amendment Nos. 131 and 34 Regarding Correction to Unbalanced Voltage Relay Instrumentation Values ML19276E5572019-12-0909 December 2019 Issuance of Amendment Nos. 130 and 33 Regarding Adoption of Technical Specifications Task Force Traveler, TSTF-500, DC Electrical Rewrite - Update to TSTF-360 ML19238A0052019-11-26026 November 2019 Issuance of Amendment Nos. 129 and 32 Regarding Changes to Technical Specifications 3.8.1, 3.8.7, 3.8.8, and 3.8.9 ML18277A1102019-08-27027 August 2019 Units, 1 & 2 Issuance of Amendment Nos. 309, 332, 292, 345, 339, 128, and 31 Regarding Unbalanced Voltage Protection 2024-01-29
[Table view] Category:Safety Evaluation
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 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 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 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) 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 ML23048A3042023-03-0808 March 2023 Tennessee Valley Authority - Request for Relief from Requirements of ASME Boiler and Pressure Vessel Code Regarding Weld Examination Coverage (EPID L-2022-LLR-0045,-0046,-0047) ML22348A0052023-01-25025 January 2023 Issuance of Amendment Nos. 326, 349, and 309; 363 and 35; 159 and 67 Regarding Adoption of TSTF-554, Revise Reactor Coolant Leakage Requirements ML22349A6472023-01-20020 January 2023 Issuance of Amendment Nos. 325, 348, and 308; 362 and 356; and 158 and 66 Regarding Adoption of TSTF-529, Rev. 4, Clarify Use and Application Rules ML22271A9142022-12-0707 December 2022 Issuance of Amendment Nos. 324, 347, and 307; 360 and 354; 157 and 65 Regarding a Revision to the Emergency Action Level Scheme ML22293A4082022-11-14014 November 2022 Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule ML22257A0512022-11-0404 November 2022 Issuance of Amendment Nos. 156 and 64 Regarding Adoption of TSTF-205-A, Revision 3, and TSTF-563-A ML22276A1612022-10-24024 October 2022 Issuance of Amendment Nos. 359, 353, 155, & 63 Regarding Adoption of TSTF Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML22272A5682022-10-12012 October 2022 Authorization of Alternatives to Certain Inservice Testing Requirements in the American Society of Mechanical Engineers Operating and Maintenance Code ML22187A0192022-09-20020 September 2022 Issuance of Amendment No. 154 Regarding Revision to Technical Specification 3.3.2 to Revise Allowable Value for Trip of Turbine-Driven Main Feedwater Pumps ML22187A1812022-09-20020 September 2022 Issuance of Amendment Nos. 153 and 62 Regarding Extension of Completion Time for Technical Specification 3.7.8 for Inoperable Essential Raw Cooling Water Train ML22014A2062022-05-0404 May 2022 Issuance of Amendment Nos. 152 and 61 Regarding Revision to Technical Specifications to Delete a Redundant Unit of Measure for Certain Radiation Monitors ML22084A0012022-04-0505 April 2022 Clinch River Nuclear Site; Sequoyah Nuclear Plant, Units 1 and 2; Watts Bar Nuclear Plant, Units 1 and 2, Review of Quality Assurance Plan Changes ML22070A0022022-03-28028 March 2022 Review of the Fall 2021 Mid Cycle Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Report ML21306A2872022-01-25025 January 2022 Issuance of Amendment No. 60 Regarding Revision of Technical Specification Requirements Specific to the Model D3 Steam Generators That Will No Longer Apply Following Steam Generator Replacement ML21334A2952022-01-18018 January 2022 Issuance of Amendment No. 151 Regarding Revision to TS 3.7.12 for One-Time Exception to Permit Continuous Opening of Auxiliary Building Secondary Containment Enclosure During Unit 2 Steam Generator Replacement ML21334A3892022-01-12012 January 2022 Issuance of Amendment No. 59 Regarding Revision to Steam Generator Tube Rupture Dose Analysis ML21271A1372021-12-16016 December 2021 Issuance of Amendment Nos. 150 and 58 Regarding Modification of Technical Specification Surveillance Requirement 3.6.15.4, Shield Building ML21260A2102021-11-22022 November 2021 Issuance of Amendment No. 57 to Revise Technical Specifications to Change the Steam Generator Secondary Side Water Level ML21189A3072021-11-0303 November 2021 Issuance of Amendment Nos. 149 and 56 Regarding Modification of Technical Specification 5.7.2.19, Containment Leakage Rate Testing Program ML21158A2842021-09-17017 September 2021 Issuance of Amendment Nos. 148 and 55 to Revise Technical Specifications for Function 6.E of Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation ML21153A0492021-07-26026 July 2021 Issuance of Amendment No. 147 Regarding Change to Steam Generator Tube Inspection Frequency and Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-510 ML21161A2392021-06-24024 June 2021 Issuance of Amendment No. 54 Regarding Use of Temperature Adjustment to Voltage Growth Rate for the Generic Letter 95-05 Steam Generator Tube Repair Criteria ML21148A1002021-06-17017 June 2021 Issuance of Amendment No. 53 Regarding Neutron Fluence Calculation Methodology ML21099A2462021-05-14014 May 2021 Issuance of Amendment Nos. 146 and 52 to Adopt TSTF-490, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec ML21130A6012021-05-13013 May 2021 Correction of Proposed Alternative IST-RR-8 to the Requirements of the ASME OM Code for the Residual Heat Removal Pump 1B-B ML21078A4842021-05-0505 May 2021 Issuance of Amendment Nos. 145 and 51 for One-Time Change to Technical Specification 3.7.11 to Extend the Completion Time for Main Control Room Chiller Modifications ML21110A0372021-04-29029 April 2021 Proposed Alternative IST-RR-8 to the Requirements of the ASME OM Code for the Residual Heat Removal Pump 1B-B ML21064A4082021-03-10010 March 2021 Correction of Safety Evaluation for License Amendment Nos. 143 and 50 (EPID L-2020-LLA-0005) (Non-Proprietary) ML21015A0342021-03-0909 March 2021 Issuance of Amendment No. 144 Regarding Post Accident Monitoring Instrumentation ML21034A1692021-02-26026 February 2021 Issuance of Amendment Nos. 143 and 50 Regarding Implementation of Full Spectrumtm Loss-of-Coolant Accident Analysis (LOCA) and New LOCA-Specific Tritium Producing Burnable Absorber Rod Stress Analysis Methodology ML20232C6222021-02-11011 February 2021 Issuance of Amendment Nos. 142 and 49 Regarding Revision to Technical Specifications to Implement WCAP-17661-P-A, Revision 1, Improved RAOC and CAOC Fq Surveillance Technical Specifications (EPID L-2020-LLA-0037 ML21027A1672021-02-0909 February 2021 Issuance of Amendment No. 48 Regarding Use of Alternate Probability of Detection Values for Beginning of Cycle in Support of Operational Assessment ML20350B4932021-01-25025 January 2021 Issuance of Amendment Nos. 352, 346, 141, and 47 Regarding the Adoption of Technical Specification Task Force Traveler, TSTF-569, Revision 2, Revise Response Time Testing Definition ML20268A0822021-01-12012 January 2021 Issuance of Amendment Nos. 314, 337, and 297; 351 and 345; 140 and 46 Regarding Changes to the Technical Specifications ML20245E4132020-12-0808 December 2020 Issuance of Amendment Nos. 139 and 45 Regarding Revisions to Technical Specification 3.6.15, Shield Building ML20282A3452020-11-19019 November 2020 Issuance of Amendment Nos. 313, 336, 296, 350, 344, 138, and 44 Revise Emergency Plan On-Shift Emergency Medical Technician & Onsite Ambulance Requirements ML20239A7912020-10-28028 October 2020 Issuance of Amendment Nos. 137 and 43 Regarding Revision to Technical Specifications to Adopt Technical Specification Task Force Traveler 541, Revision 2 ML20226A4442020-10-21021 October 2020 Issuance of Amendment No. 42 Regarding Measurement Uncertainty Recapture Power Uprate ML20167A1482020-08-19019 August 2020 Issuance of Amendment Nos. 136 and 41 Regarding the Automatic Transfer from a Unit Service Station Transformer to a Common Station Service Transformer ML20156A0182020-08-10010 August 2020 Issuance of Amendment No. 40 Regarding Technical Specifications for Steam Generator Tube Repair Sleeve ML20076A1942020-04-30030 April 2020 Issuance of Amendment Nos. 134 and 38 Regarding Adopting the Title 10 CFR Section 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Plants ML20057E2422020-03-30030 March 2020 Issuance of Amendment Nos. 133 and 37 Regarding Changes to Technical Specifications Pertaining to Diesel Generator Start Instrumentation (EPID-L-2020-LLA-0003) ML20028F7332020-02-28028 February 2020 Issuance of Amendment Nos. 132 and 36 Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-425, Revision 3 ML20024F8352020-02-24024 February 2020 Issuance of Amendment No. 35 Regarding One-Time Extension of Completion Time for Technical Specification 3.7.8 for Inoperable Essential Raw Cooling Water Train ML19336C5192019-12-10010 December 2019 Issuance of Amendment Nos. 131 and 34 Regarding Correction to Unbalanced Voltage Relay Instrumentation Values 2024-01-29
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 27, 2017 Mr. J. W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority 1101 Market Street, LP 3R-C Chattanooga, TN 37402-2801
SUBJECT:
WATTS BAR NUCLEAR PLANT, UNIT 1 - ISSUANCE OF AMENDMENT REGARDING APPLICATION TO MODIFY TECHNICAL SPECIFICATIONS REGARDING USE OF AN ALTERNATE COMPONENT COOLING SYSTEM PUMP TO SUPPORT COMPONENT COOLING SYSTEM TRAIN B OPERABILITY (CAC NO. MF7997)
Dear Mr. Shea:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No.113 to Facility Operating License No. NPF-90 for the Watts Bar Nuclear Plant, Unit 1. This amendment is in response to your application dated June 7, 2016.
The amendment revises Technical Specification (TS) 3.7.7, Component Cooling System (CCS),
to allow increased flexibility in maintaining CCS operability when the normally aligned C-S pump is inoperable for maintenance, which is consistent with Unit 2 TS 3.7.7.
A copy of the safety evaluation is also enclosed. Notice of issuance will be included in the Commission's biweekly Federal Register notice.
If you have any questions regarding this letter, please contact me at (301) 415-6020.
Sincerely, Robert G. Schaaf, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-390
Enclosures:
- 1. Amendment No. 113 to NPF-90
- 2. Safety Evaluation cc w/enclosures: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-390 WATTS BAR NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 113 License No. NPF-90
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Tennessee Valley Authority (TVA, the licensee) dated June 7, 2016, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I;
- 8. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
Enclosure 1
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-90 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A as revised through Amendment No. 113 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. TVA shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3. This license amendment is effective as of the date of its issuance, and shall be implemented no later than 60 days from the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Benjamin G. Beasley, Chief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Facility Operating License and Technical Specifications Date of Issuance: April 27, 201 7
ATTACHMENT TO AMENDMENT NO. 113 WATTS BAR NUCLEAR PLANT. UNIT 1 FACILITY OPERATING LICENSE NO. NPF-90 DOCKET NO. 50-390 Replace Page 3 of Facility Operating License NPF-90 with the attached Page 3. The revised page is identified by amendment number and contains a marginal line indicating the area of change.
Replace the following page of the Appendix A Technical Specifications with the attached page.
The revised page is identified by amendment number and contains vertical lines indicating the area of change.
REMOVE INSERT 3.7-18 3.7-18
(4) TVA, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required, any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis, instrument calibration, or other activity associated with radioactive apparatus or components; and (5) TVA, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect, and is subject to the additional conditions specified or incorporated below.
(1) Maximum Power Level TVA is authorized to operate the facility at reactor core power levels not in excess of 3459 megawatts thermal.
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A as revised through Amendment No. 113 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. TVA shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3) Safety Parameter Display System (SPDS) (Section 18.2 of SER Supplements 5 and 15)
Prior to startup following the first refueling outage, TVA shall accomplish the necessary activities, provide acceptable responses, and implement all proposed corrective actions related to having the Watts Bar Unit 1 SPDS operational.
(4) Vehicle Bomb Control Program (Section 13.6.9 of SSER 20)
During the period of the exemption granted in paragraph 2.D.(3) of this license, in implementing the power ascension phase of the approved initial test program, TVA shall not exceed 50% power until the requirements of 10 CFR 73.55(c)(7) and (8) are fully implemented. TVA shall submit a letter under oath or affirmation when the requirements of 73.55(c)(7) and (8) have been fully implemented.
Facility License No. NPF-90 Amendment No. 113
ccs 3.7.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.7.1 Verify that the alternate feeder breaker to the C-S pump is 7 days open.
SR 3.7.7.2 --------------------------------N()TE----------------------------------- 31 days lsolation of CCS flow to individual components does not render the CCS inoperable.
Verify each CCS manual, power operated, and automatic valve in the flow path servicing safety related equipment, that is not locked, sealed, or otherwise secured in position, is in the correct position.
SR 3.7.7.3 Verify each CCS automatic valve in the flow path that is 18 months not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.
SR 3.7.7.4 ----------------------------Note----------------------------------------- 18 months Verification of CCS pump 28-8 automatic start on Unit 1 SI is not required when CCS Pump 28-8 is supporting CCS Train 8 ()PERA81LITY.
Verify each CCS pump starts automatically on an actual or simulated actuation signal.
SR 3.7.7.5 ----------------------------Note------------------------------------------ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
()nly required to be met when CCS Pump 28-8 is supporting CCS Train 8 ()PERA81LITY.
Verify CCS pump 28-8 is aligned to CCS Train 8 and is in operation.
Watts Bar-Unit 1 3.7-18 Amendment 113
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 113 TO FACILITY OPERATING LICENSE NO. NPF-90 TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT, UNIT 1 DOCKET NO. 50-390
1.0 INTRODUCTION
By letter dated June 7, 2016 (Agency Documents Access and Management System Accession No. ML16159A403), the Tennessee Valley Authority (the licensee) requested changes to Technical Specification (TS) 3.7.7, "Component Cooling System (CCS)" forthe Watts Bar Nuclear Plant (Watts Bar or WBN), Unit 1.
This proposed change would modify Watts Bar Unit 1TS3.7.7 to allow the use of CCS pump 2B-B to support Watts Bar Unit 1 Train 1B operability when the normal CCS pump C-S is removed from service.
2.0 REGULATORY EVALUATION
2.1 Description of the Component Cooling System The licensee's application states:
The CCS is designed for operation during all phases of plant operation and shutdown. The CCS serves to remove residual and sensible heat from the RCS
[reactor coolant system] via the RHR [residual heat removal] system during plant cooldown; cool the spent fuel pool water and the letdown flow of the chemical and volume control system; provide cooling to dissipate waste heat from various plant components; and provide cooling for safeguard loads after an accident.
The CCS is a shared system with Unit 2 and consists of five CCS pumps, two thermal barrier booster pumps per unit, three HXs [heat exchangers], two surge tanks, one CCS pump seal water collection unit, and associated valves, piping and instrumentation serving both units .... The CCS pumps are designated as 1A-A, 1B-B, C-S, 2A-A, and 2B- B.
Typically one CCS pump is in operation per train. Train 1A can be supplied by either CCS pump 1A-A or CCS pump 1B-B with the non-operating pump in standby. Train 2A can be supplied by either CCS pump 2A-A or CCS pump 2B-B with the non-operating pump in standby. Trains 1B and 2B is [sic] normally supplied by the C-S pump. Although B Train CCS pumps can supply either Unit's Train A, the A Train CCS pump must be operable to consider the Unit's A Train operable.
Enclosure 2
WBN Units 1 and 2 are served by two cooling system trains (A and B) serving ESF
[engineered safety feature] equipment, with CCS Train A also serving miscellaneous non-safety-related components. Except for the RHR HXs, both trains of the safeguards equipment of both units served by the CCS are normally aligned and supplied with CCS water and continue to be supplied with CCS water in a Loss of Coolant Accident (LOCA). However, the RHR HXs may be aligned with CCS water flowing through the HXs during normal operation to meet CCS flow requirements. In the event of an accident, non-safety-related components are not required; therefore, CCS flow to these components may be manually isolated.
Prior to the switchover from injection to recirculation phase of SI [safety injection),
the CCS valves are manually opened at the RHR HXs of the accident unit in order to supply these HXs with cooling water.
Emergency diesel generators (EDGs) 1A, 1B, 2A, and 2B power the respective 6.9-kilovolt (kV)
Shutdown Boards (SDBs), which in turn power the respective 480-Volt (V) SDBs. A SI signal in either unit will start all four EDGs. Table 1 lists the power supplies for each CCS pump.
Table 1 Component Cooling System Pump Power Suoolies CCS Pump 480-Volt Shutdown Board (SOB) 1A-A 1A1-A 1B-B 1B1-B C-S Normal - 2B2-B Alternate - 1A2-A 2A-A 2A1-A 2B-B 2B1-B 2.2 Description of the Proposed Change Watts Bar Unit 1 Surveillance Requirement (SR) 3.7.7.4 currently states:
SURVEILLANCE FREQUENCY SR 3.7.7.4 Verify each CCS pump starts automatically on an actual 18 months or simulated actuation signal.
This license amendment request (LAR) revises SR 3.7.7.4 as follows:
SURVEILLANCE FREQUENCY SR 3. 7. 7. 4 ---------------------------------N 0 TE------------------------------------ 18 months Verificati on of CCS pump 2B-B automatic start on Unit 1 SI is not required when CCS pump 2B-B is supporting CCS Train B OPERABILITY.
Verify each CCS pump starts automatically on an actual or simulated actuation signal.
This LAR also adds new SR 3.7.7.5 as follows:
SURVEILLANCE FREQUENCY SR 3. 7. 7. 5 ---------------------------------NOTE------------------------------------ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Only required to be met when CCS pump 2B-B is supporting CCS Train B OPERABILITY.
Verify CCS pump 28-B is aligned to CCS Train Band is in operation.
As listed above, the change adds a note to SR 3.7.7.4 that deletes the requirement to verify CCS pump 2B-B automatically starts on an SI signal when CCS pump 2B-B is supporting CCS Train B OPERABILITY. The change also adds SR 3.7.7.5 as shown above.
2.3 Regulatory Review The U.S. Nuclear Regulatory Commission (NRC) considered the following regulatory requirements, guidance, and licensing and design basis information during its review of the proposed change.
Title 10 of the Code of Federal Regulations (10 CFR), Paragraph 50.36(c)(3), states Surveillance requirements are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation [LCOs] will be met.
As stated in 10 CFR, 50.36(c)(2)(ii)(C), Criterion 3, the regulations require that TS LCOs be established for: A structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.
In 10 CFR 50.36(a)(1 ), the regulations require each applicant for a license to include a summary statement of the bases or reasons for proposed TSs, however, the bases shall not become part of the TSs.
The Watts Bar plant was designed to meet the intent of the "Proposed General Design Criteria for Nuclear Power Plant Construction Permits" published in July 1967. The Watts Bar construction permit was issued in January 1973. However, in its Updated Final Safety Analysis Report (UFSAR), the licensee addresses the NRC General Design Criteria (GDC) published as Appendix A to 10 CFR Part 50 in July 1971.
In UFSAR Section 3.1.2.1, "Overall Requirements," the licensee describes how the plants meet Criterion 5, "Sharing of structures, systems, and components," which states that structures, systems, and components important to safety shall not be shared among nuclear power units unless it can be shown that such sharing will not significantly impair their ability to perform their safety functions, including, in the event of an accident in one unit, an orderly shutdown and cooldown of the remaining units.
In UFSAR Section 3.1.2.4, "Fluid Systems," the licensee describes how the plants meet Criterion 44, "Cooling water," which states in part, that the system safety function shall be to transfer the combined heat load of these structures, systems, and components under normal operating and accident conditions. Suitable redundancy in components and features, and suitable interconnections, leak detection, and isolation capabilities shall be provided to assure that for onsite electric power system operation (assuming offsite power is not available) and for offsite electric power system operation (assuming onsite power is not available) the system safety function can be accomplished, assuming a single failure.
In UFSAR Section 3.1.2.4, "Fluid Systems," the licensee describes how the plants meet Criterion 46, "Testing of Cooling Water Systems," which states in part that the cooling water system be designed to permit appropriate functional testing to assure, the operability and the performance of the active components of the system, and the operability of the system as a whole and, under conditions as close to design as practical, the performance of the full operational sequence that brings the system into operation for reactor shutdown and for LOCAs, including operation of applicable portions of the protection system and the transfer between normal and emergency power sources.
Standard Review Plan (SRP) for the Review of Safety Analysis Reports for Nuclear Power Plants:
LWR Edition -Auxiliary Systems (NUREG-0800, Chapter 9.2.2, Reactor Auxiliary Cooling Water Systems) provides guidance for staff on how regulatory requirements may be met.
3.0 TECHNICAL EVALUATION
3.1 Method of Review The NRC staff reviewed the licensee's amendment request by comparing the proposed TS change against the requirements and guidelines of 10 CFR 50.36, GDC 5, GDC 44, and GDC 46 as discussed in UFSAR Section 3.1.2, the current TSs, SRP 9.2.2, and UFSAR Chapter 9.2.2.
3.2 Technical Review The CCS system is a shared system with CCS Train 1B/2B supplying both units. CCS Train 1A and CCS Train 2A are separated by isolation valves and do not share components. CCS
pumps 1A-A and 1B-B are normally aligned to the CCS Train 1A header (one pump running and the non-operating pump on standby). CCS pump C-S is normally supplying water to the CCS Train 1B/2B header. This configuration meets the LCO of Unit 1 TS 3.7.7 and meets the CCS design requirements of GDC 5 and 44 as expressed in UFSAR Section 3.1.2. CCS water flow independence is established by a valve lineup as shown in Figure 1 of the LAR.
The CCS system design allows for the alignment of either CCS pump 1B-B or 2B-B to the CCS Train 1B/2B header as a replacement for CCS pump C-S. When CCS pump 2B-B is used as an alternate for CCS pump C-S, CCS Train 1B independence with CCS Train 1A is maintained because CCS pump 2B-B is powered from the 2B1-B 480-V SDB, while CCS pump 1A-A is powered by the 1A1-A 480-V SOB. CCS water flow independence is established by a valve lineup as shown in Figure 2 of the LAR.
The most common reason for substituting CCS pump 2B-B for CCS pump C-S would be the need to remove CCS pump C-S from service for maintenance. However, if CCS pump 2B-B is aligned to CCS Train 1B, the current SR 3.7.7.4 for Unit 1 cannot be satisfied since CCS pump 2B-B will not automatically start on an SI actuation signal in Unit 1. If SR 3.7.7.4 were not met, the LCO of TS 3.7.7 would not be met according to SR 3.0.1, which requires SRs to be met to meet the LCO.
Therefore, the licensee proposed a revision to SR 3.7.7.4 with the addition of SR 3.7.7.5 to enable this alignment to meet TS LCO 3.7.7 for Unit 1. The licensee's proposed changes to the SRs do not change the design of the CCS, but would allow a deviation from normal operation when using CCS pump 2B-B to replace CCS pump C-S. The Unit 2 CCS Train 2A would not be adversely affected as long as CCS pump 2A is OPERABLE. With the licensee's proposed changes, the LCO of TS 3.7.7 would be satisfied by meeting the intent of Unit 1SR3.7.7.4 by adding an exception note for pump 2B-B and adding SR 3.7.7.5. The exception note excludes verifying CCS pump 2B-B will start automatically on an actual or simulated SI actuation signal in Unit 1 when using CCS Pump 2B-B to replace CCS pump C-S. By adding SR 3.7.7.5, the licensee ensures Pump 2B-B will run during an SI in Unit 1 by requiring that Pump 2B-B be aligned to CCS Train B and be in operation. Even with the proposed changes, SR 3.7.7.4 would continue to require verification of an automatic start of CCS pump 2B-B on a simulated or actual loss of the offsite power actuation signal. With the proposed changes, in the event of an SI signal on Unit 1 without a loss of offsite power (LOOP), CCS pump 2B-B will continue to run and provide cooling water to CCS Train 1B.
In the event of a LOOP with or without an SI signal, CCS pump 2B-B will automatically sequence onto the emergency diesel generator bus and provide cooling water to CCS Train 1B. This is so because as stated in the LAR, the Watts Bar 6.9-kV SOB load-shedding and sequencing circuitry actuates on a sustained degraded voltage condition or loss of voltage on its specific SOB. Table 1 lists the normal power supply for CSS pump C-S as 480-V SOB 2B2-B and the power supply for CSS pump 2B-B as 480-V SOB 2B1-B. Figure 3 shows that both 480-V SDBs 2B2-B and 2B1-B are powered from 6.9-kV SOB 2B-B, which on a LOOP is powered from DG 2B-B. Therefore, because load shedding and sequencing of CCS pump 2B-B are specific to the SDB and independent of which CCS train the pump is aligned to, any voltage condition that would affect CCS pump 2B-B would load shed the pump and subsequently sequence the pump to operate.
Figure 4, Figure 5, and Figure 6, "Component Cooling Pump C-S Wiring Diagram," of the LAR show the CCS pump's power supply and controls.
Therefore, to achieve OPERABILITY of CCS Train 1Bas described above, a note will be added to SR 3.7.7.4 to exclude verification of CCS pump 2B-B starting on Unit 1 SI signal when the pump is supporting CCS Train 1B OPERABILITY. SR 3.7.7.4 continues to require verification of an automatic start on a simulated or actual LOOP actuation signal. A new SR 3.7.7.5 requiring CCS
pump 2B-B to be aligned to CCS Train B and be operating will be added for this configuration.
Thus, OPERABILITY of both CCS Trains 1A and 1B will be maintained, and the CCS system for Unit 1 will continue to satisfy the LCO for TS 3.7.7 and GDC 5, 44 and 46.
In accordance with Watts Bar Fire Protection Report (FPR) Operating Requirements, CCS pump 2B-B must be aligned to the CCS 2A header. The FPR allows a deviation from this lineup for 30 days. Therefore, the FPR is consistent with the licensee's proposed change, but limits the time that this configuration can be maintained to no more than 30 days.
3.3 Summary Unit 1 SR 3.7.7.4 assures that the pumping power for each train of CCS actuates for an SI and/or a LOOP in Unit 1. When CCS pump 2B-B is used to replace CCS pump C-S for the CCS Train 1B, CCS Train 1B will not have an assured supply of CCS water during an SI actuation in Unit 1 unless CCS pump 2B-B is aligned to CCS Train B and is in operation. An exception note to SR 3.7.7.4 and a new SR 3.7.7.5 has been added to achieve the intended purpose. Since the design of the CCS is not changed, GDC 5, 44, and 46 continue to be met as discussed in UFSAR Section 3.1.2. The proposed changes to the SRs ensure that TS LCO 3.7.7 and the lowest functional capability of the CCS for safe operation of Unit 1 is met when CCS pump 2B-B is substituted for CCS pump C-S, thus continuing to satisfy 10 CFR 50.36. Therefore, the NRC staff concludes that the proposed change meets the applicable regulatory requirements, and is therefore acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Tennessee State official was notified of the proposed issuance of the amendment on April 10, 2017. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. The NRC staff has determined that the amendment involves no significant increase in the amounts and no significant change in the types of any effluents that may be released offsite and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (81 FR 62932; September 13, 2016). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that 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.
Principal Contributor: Gerard J. Purciarello Date: April 27, 2017
ML17081A263
- via memo ** via e-mail OFFICE NRR/DORL/LPL2-2/PMiT NRR/DORL/LPL2-2/LA OGC- NLO NAME APatel (RSchaaf for) BClavton RNorwood DATE 4/11/17 4/10/17 4/21/17 OFFICE NRR/DSS/SBPB/BC* NRR/DSS/STSB/BC** NRR/DORL/LPL2-2/BC NAME RDenniq AKlein BBeasley DATE 1/24/17 4/12/17 4/27/17 OFFICE NRR/DORL/LPL2-2/PM NAME RSchaaf DATE 4/27/17