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MONTHYEARCNL-13-119, Revision to Watts Bar Nuclear Plant, Unit 1, Reactor Vessel Surveillance Capsule Withdrawal Schedule2013-11-22022 November 2013 Revision to Watts Bar Nuclear Plant, Unit 1, Reactor Vessel Surveillance Capsule Withdrawal Schedule Project stage: Request ML14042A2062014-02-11011 February 2014 E-mail - Request for Additional Information Related to Request Change to the Reactor Vessel Surveillance Capsule Withdrawal Schedule Project stage: RAI CNL-14-031, CNL-14-031, Response to RAI Regarding Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule2014-02-21021 February 2014 CNL-14-031, Response to RAI Regarding Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule Project stage: Request CNL-14-040, Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule, Revision 12014-03-10010 March 2014 Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule, Revision 1 Project stage: Request ML14083A2472014-03-27027 March 2014 Review of Reactor Vessel Materials Surveillance Program - Revised Surveillance Capsule Withdrawal Schedule Project stage: Approval 2014-02-21
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Category:Letter
MONTHYEARCNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description CNL-24-047, Decommitment of Flood Mode Mitigation Improvement Systems2024-09-24024 September 2024 Decommitment of Flood Mode Mitigation Improvement Systems ML24262A0602024-09-23023 September 2024 Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 05000390/LER-2024-002, Automatic Reactor Trip Due to Main Generator Protection Relay Actuation2024-09-0505 September 2024 Automatic Reactor Trip Due to Main Generator Protection Relay Actuation IR 05000390/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390-2024005 and 05000391-2024005 ML24218A1442024-08-27027 August 2024 Issuance of Amendment Nos. 169 and 75 Regarding Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate IR 05000390/20244022024-08-20020 August 2024 – Security Baseline Inspection Report 05000390-2024402 and 05000391/2024402 - Public CNL-24-061, Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08),2024-08-19019 August 2024 Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08), ML24219A0262024-08-12012 August 2024 Request for Withholding Information from Public Disclosure IR 05000390/20240022024-08-0707 August 2024 Integrated Inspection Report 05000390/2024002 and 05000391/2024002 Rev ML24204A2652024-07-25025 July 2024 Regulatory Audit Summary Related to Request to Revise Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter ML24170A8002024-07-15015 July 2024 Issuance of Amendment Nos. 168 and 74 Regarding Revision to Technical Specification Table 1.1-1 for Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts IR 05000390/20244402024-07-12012 July 2024 95001 Supplemental Inspection Supplemental Report 05000390-2024440 and 05000391-2024440 and Follow-Up Assessment Letter ML24131A0012024-07-0202 July 2024 Issuance of Amendment Nos. 167 and 73 Regarding Adoption of Technical Specification Task Force Traveler TSTF-427-A, Revision 2 CNL-24-052, Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-06-27027 June 2024 Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-24-018, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS2024-06-25025 June 2024 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS ML24089A1152024-06-21021 June 2024 Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2) ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24100A7642024-05-16016 May 2024 Issuance of Amendment No. 166 Regarding Revision to Technical Specification 3.8.2, AC Sources-Shutdown, to Remove Reference to C-S Diesel Generator (CNL-23-062) IR 05000390/20240012024-05-14014 May 2024 Integrated Inspection Report 05000390/2024001 and 05000391/2024001 CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000391/20240072024-04-30030 April 2024 Assessment Follow-up Letter for Watts Bar Nuclear Plant, Unit 2 – Report 05000391/2024007 ML24120A1182024-04-29029 April 2024 – Notification of NRC Supplemental Inspection (95001) and Request for Information CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42 ML24087A1912024-04-18018 April 2024 Exemption from Select Requirements of 10 CFR Part 73, Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting CNL-24-010, License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19)2024-04-17017 April 2024 License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19) CNL-24-024, Hydrologic Engineering Center River Analysis System Project Milestone Status Update2024-04-17017 April 2024 Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24072A0052024-04-15015 April 2024 Issuance of Amendment Nos. 165 and 72 Regarding Increase in the Maximum Number of Tritium Producing Burnable Absorber Rods and Supporting Changes, and Revision to the Updated Final Safety Analysis Report CNL-24-004, Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13)2024-04-0404 April 2024 Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13) IR 05000390/20244012024-04-0202 April 2024 – Security Baseline Inspection Report 05000390/2024401 and 05000391/2024401 - (Public) CNL-24-020, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements2024-04-0101 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements CNL-24-007, Annual Insurance Status Report2024-03-27027 March 2024 Annual Insurance Status Report CNL-24-008, Guarantee of Payment of Deferred Premiums - 2023 Annual Report2024-03-27027 March 2024 Guarantee of Payment of Deferred Premiums - 2023 Annual Report CNL-24-025, Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule2024-03-25025 March 2024 Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule ML24081A0262024-03-21021 March 2024 Emergency Plan Implementing Procedure Revisions ML24079A0312024-03-19019 March 2024 Wb 2024-301, Corporate Notification Letter (210-day Ltr) CNL-24-031, Supplement to Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance2024-03-18018 March 2024 Supplement to Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance CNL-24-028, Response to Request for Additional Information Regarding Watts Bar Nuclear Plant, Units 1 and 2, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2024-03-14014 March 2024 Response to Request for Additional Information Regarding Watts Bar Nuclear Plant, Units 1 and 2, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation CNL-24-029, Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 372024-03-14014 March 2024 Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 37 IR 05000390/20240102024-03-0808 March 2024 Age-Related Degradation Inspection Report 05000390/2024010 and 05000391/2024010 CNL-24-012, Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance2024-02-28028 February 2024 Request for Exemption from Various Part 72 Regulations Resulting from Fuel Basket Design Control Compliance IR 05000390/20230062024-02-28028 February 2024 Annual Assessment Letter for Watts Bar Nuclear Plant Units 1 and 2 - Report 05000390/2023006 and 05000391/2023006 CNL-24-023, Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-17, Revision 252024-02-20020 February 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-17, Revision 25 ML24009A1712024-02-16016 February 2024 Environmental Assessment and Finding of No Significant Impact Related to an Increase in the Maximum Number of Tritium Producing Burnable Absorber Rods (EPID L-2023-LLA-0039) - Letter ML24019A0722024-02-14014 February 2024 Request for Withholding Information from Public Disclosure IR 05000390/20230042024-02-13013 February 2024 Integrated Inspection Report 05000390/2023004 and 05000391/2023004 and Apparent Violation 2024-09-05
[Table view] Category:Safety Evaluation
MONTHYEARML24218A1442024-08-27027 August 2024 Issuance of Amendment Nos. 169 and 75 Regarding Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate ML24170A8002024-07-15015 July 2024 Issuance of Amendment Nos. 168 and 74 Regarding Revision to Technical Specification Table 1.1-1 for Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts ML24100A7642024-05-16016 May 2024 Issuance of Amendment No. 166 Regarding Revision to Technical Specification 3.8.2, AC Sources-Shutdown, to Remove Reference to C-S Diesel Generator (CNL-23-062) ML24072A0052024-04-15015 April 2024 Issuance of Amendment Nos. 165 and 72 Regarding Increase in the Maximum Number of Tritium Producing Burnable Absorber Rods and Supporting Changes, and Revision to the Updated Final Safety Analysis Report ML23319A2452024-01-29029 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 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 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 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 2024-08-27
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 27, 2014 Mr. Joseph W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority 1101 Market Street, LP 3D-C Chattanooga, TN 37402-2801 SUBJECT: WATTS BAR NUCLEAR PLANT, UNIT 1 -REVIEW OF REACTOR VESSEL MATERIALS SURVEILLANCE PROGRAM-REVISED SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULE (TAC NO. MF3162) Dear Mr. Shea: By letter dated November 22, 2013, as supplemented by letters dated February 21, 2014, and March 10, 2014, Tennessee Valley Authority (TVA) requested approval of proposed changes to the reactor vessel surveillance capsule withdrawal schedule for the Watts Bar Nuclear Plant, Unit 1 (WBN-1). The proposed changes were submitted pursuant to Title 10 of the Code of Federal Regulations (1 0 CFR) Part 50, Appendix H,Section III.B.3, which requires that: (1) withdrawal schedules be submitted, as specified in 10 CFR 50.4, and (2) the proposed schedule must be approved by the Nuclear Regulatory Commission (NRC) prior to implementation. The NRC staff has reviewed TVA's submittals and concludes that the changes to the reactor pressure vessel surveillance capsule withdrawal schedule for WBN-1 is acceptable for implementation and satisfied the requirements of 10 CFR Part 50, Appendix H. The NRC staff's evaluation is enclosed. Please contact me at (301) 415-8480 if you have any questions. Docket No. 50-390 Enclosure: Safety Evaluation cc w/enclosure: Distribution via Listserv Sincerely, Andrew Han, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REVISION TO REACTOR VESSEL SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULE 1.0 INTRODUCTION WATTS BAR NUCLEAR PLANT, UNIT 1 DOCKET NO. 50-390 By letter dated November 22, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 13333A 165), Tennessee Valley Authority (TVA or the licensee) requested approval of proposed changes to the reactor vessel surveillance capsule withdrawal schedule for the Watts Bar Nuclear Plant, Unit 1 (WBN-1). Also, in response to a Request for Additional Information (RAI), the licensee provided additional clarification by letters dated February 21, 2014 (ADAMS Accession No. ML 14056A290) and March 10, 2014 (ADAMS Accession No. ML 14070A162). The proposed changes were submitted pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix H,Section III.B.3, which requires that: (1) withdrawal schedules be submitted, as specified in 10 CFR Part 50.4, and (2) the proposed schedule must be approved by the Nuclear Regulatory Commission (NRC) prior to implementation. 2.0 REGULATORY EVALUATION 2.1 Section 50.60 of Part 50 of 10 CFR and Appendix H to 10 CFR Part 50 The NRC has established requirements and criteria in 10 CFR 50.60 for protecting the reactor vessels (RVs) of U.S. light-water reactors (LWRs) against fracture. The rule requires LWRs to meet the RV materials surveillance program requirements set forth in Appendix H to 10 CFR Part 50. Appendix H to 10 CFR Part 50 provides the NRC staff's criteria for the design and implementation of RV material surveillance programs for operating LWRs. The rule, in part, requires RV surveillance program designs and withdrawal schedules to meet the requirements of the edition of American Society for Testing and Materials (ASTM) Standard Practice E185, "Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels," which is current on the issue date of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code to which the RV was purchased, although later editions of ASTM E185 may be used inclusive of the 1982 Edition of ASTM E185 (ASTM E185-82). The rule also requires proposed RV surveillance programs to be submitted to the NRC and approved prior to implementation. The applicable criteria in ASTM E 185-82 are discussed below. Enclosure
-2-Table 1 of ASTM E 185-82 requires that either a minimum of three, four, or five surveillance capsules be removed from the RVs, based on the limiting amount of RT NDT shift (limiting b.RT NDT) that is projected to occur at the clad-vessel interface location of the RV at the end-of-licensed plant life (EOL). ASTM E185-82 establishes the following criteria for determining the minimum number of capsules that are to be removed in accordance with a withdrawal schedule and the number of capsules that are to be tested: 1. For plants with projected b.RT NDT less than or equal to 100 oF (degree Fahrenheit) or 56 oc (degree Celsius), three capsules are required to be removed from the RV and the first two capsules are required to be tested (for dosimetry, tensile-ductility, Charpy-V impact toughness, and alloying chemistry). 2. For plants with projected b.RT NDT greater than 100 oF (56° C) but less than or equal to 200 oF (111 °C), four surveillance capsules are to be removed from the RV and the first three capsules are required to be tested. 3. For plants with projected b.RT NDT above 200 °F (111 °C), five surveillance capsules are required to be removed from the RV and the first four capsules are required to be tested. ASTM E185-82 also provides specific criteria for removal of surveillance capsules. The removal times are based on criteria that the surveillance capsules be removed after a certain amount of power operation has elapsed or at various times when the RV shell is projected to achieve certain levels of neutron fluence. The intent of the Standard Practice is to achieve a set of testing data over a range of neutron fluences for the RV that bounds the current life of the plant. Of key importance are the removal criteria for the second to last and final capsules required for capsule withdrawal. For the second-to-last required capsule in a withdrawal schedule, ASTM E 185-82 requires that the capsules be pulled at either 15 effective full-power years (EFPYs) or at the time when the capsule is equivalent to the limiting fluence projected for the clad-based metal interface of the RV at EOL, whichever time comes first. For the final capsule that is required for removal, ASTM E185-82 requires that the capsule be removed at a time when the neutron fluence projected for the capsule is between the limiting fluence value projected for the RVs at the EOL and two times that value. 2.2 NRC Administrative Letter (AL)97-004 and NRC Memorandum and Order CLI-96-13 On September 30, 1997, the NRC issued AL 97-004 to all holders of operating licenses for domestic nuclear power plants (with the exception of those who have ceased operations of their facilities or have certified that fuel has been permanently removed from the reactor). In this AL, the NRC staff summarized the Commission's decision promulgated in Commission Memorandum and Order CLI-96-13, which was issued "In the Matter of the Cleveland Electric Illuminating Company (Perry Nuclear Power Plant, Unit 1 )" on December 6, 1996. In this Memorandum and Order, the Commission found that, while 10 CFR Part 50, Appendix H, 111.8.3 requires prior NRC approval for all withdrawal schedule changes, only certain changes require the NRC staff to review and approve the changes through the NRC's license amendment process (10 CFR 50.90 process). Specifically, only those changes that are not in conformance with the ASTM standard referenced in 10 CFR Part 50, Appendix H (i.e., ASTM E-185,) are required to be approved
-3-through the license amendment process, whereas changes that are determined to conform to the ASTM standard only require that the staff document its review and verification of such conformance. 2. 3 GALL Report Guidelines The licensee may apply for license renewal with an additional 20 year period of extended operation (PEO) based on NUREG-1801, Generic Aging Lessons Learned (GALL) Report.Section XI.M31 of the current GALL Report (Revision 2) includes recommended changes to the surveillance capsule withdrawal schedule that depends on whether the program for the original license period includes a capsule that bounds the projected maximum fluence for the additional 20-year PEO. If no capsule has been pulled that would bound the fluence for the PEO, the GALL Report would allow the licensee to delay withdrawal and testing of the final capsule until the fluence exceeds the projected maximum fluence for the additional 20-year PEO. The GALL Report, Revision 2, also includes detailed guidance on the disposition of all pulled and tested samples or capsules placed in storage. If and when WBN-1 applies for license renewal, the plant will have to address the GALL Report version that is current at that time. 3.0 TECHNICAL EVALUATION 3.1 Changes Proposed to the Withdrawal Schedule for WBN-1 For WBN-1, the licensee is applying the requirements of ASTM E 185-82 as its basis for meeting the RV surveillance capsule withdrawal requirements of 10 CFR Part 50, Appendix H. With respect to the EOL, the NUREG-1511, "Reactor Pressure Vessel Status Report," December 1994, lists the WBN-1 RV with a limiting value of 172 °F. As stated above in paragraph 2.1' since the NOT value is greater than 100 °F, but less than 200 °F, ASTM E185-82 requires that the licensee, at a minimum, remove four capsules from the reactor during the licensed operating period. The licensee's November 22, 2013, letter provides the proposed revision to the RV surveillance capsule withdrawal schedule for WBN-1. The letter indicated that Capsules U, W, X, and Z were removed from WBN-1 and tested. The results are summarized in Westinghouse Report WCAP-16760-NP, "Analysis of Capsule Z from the Tennessee Valley Authority Watts Bar, Unit 1 Reactor Vessel Radiation Surveillance Program," dated November 2007. The neutron fluences reported for capsules U, W, X, and Z at the time of withdrawal are 4.47x1018 n/cm2, 1.08x1019 n/cm2, 1.71x1019 n/cm2, and 2.40x1019 n/cm2, respectively, as reported in WCAP-16760-NP. Based on the data provided by the licensee, the staff notes that the withdrawal schedule for Capsules U, W, X, and Z is consistent with the guidelines of ASTM E-185-82 for the four capsules required to be withdrawn for the current 40-year license period. The licensee indicated in its November 22, 2013, letter that in addition to the four capsules that have already been withdrawn and tested, that one standby capsule (Capsule V) would be removed from the WBN-1 RV at approximately 25.9 EFPYs, with a projected fluence of 6.02x1 019 n/cm2. The staff concludes that the withdrawal schedule for Capsule Vis consistent with the guidelines of the GALL Report, Revision 2, for the extra capsule required to be withdrawn to cover the period of extended operation.
-4-The licensee also indicated in the November 22, 2013, letter that, given the proposed change to the withdrawal schedule, it will still have one standby capsule (Capsule Y) that will remain inserted in the RV on standby until needed to fulfill potential future requirements. This is not a change from the current withdrawal schedule. During the review, the staff noted that the lead factors in the table from Attachment 2 are not consistent with the text of the enclosure. In response to an RAI, the licensee clarified by letter dated February 14, 2014, that the lead factors in the table of Attachment 2 are correct and in the March 10, 2014, letter, changed the text of the enclosure to the November 22, 2013, letter to make the text consistent with the table. The staff has reviewed the revised text and finds the description in the text is consistent with the information in the table. The staff's concern expressed in the RAI is resolved. In summary, the licensee has proposed a change to the surveillance capsule withdrawal schedule for WBN-1. The proposed schedule will withdraw Capsule V when the fluence on the capsule is approximately 6.02x1 019 n/cm2, which is less than 2x the projected 60-year inner diameter fluence for the WBN-1 RV. The change does not affect Capsule Y, which will remain in the vessel for future use. Therefore, the licensee's proposed change to the surveillance capsule withdrawal schedule is based on the requirements of the ASTM E 185-82, as required by Appendix H to 10 CFR Part 50, and also meets the requirements of GALL Report Section XI.M31. Since the licensee's proposed change is in conformance with ASTM 185 referenced in 10 CFR Part 50, Appendix H, the change is not required to be approved through the license amendment process as discussed above in paragraph 2.2. 4.0 CONCLUSION The NRC staff has reviewed TVA's proposed withdrawal schedules for WBN-1 and has determined that the changes to the schedule will continue to meet the RV surveillance capsule withdrawal schedule criteria in ASTM E185-82, and will be in compliance with 10 CFR Part 50, Appendix H, AL 97-004, and GALL Report Section XI.M31. The staff, therefore, concludes that the RV withdrawal schedule, as proposed in the licensee's November 22, 2013, letter and modified by the March 10, 2014, letter, is acceptable for implementation. Principal Contributor: P. Purtscher Date: March 27, 2014 March 27, 2014 Mr. Joseph W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority 1101 Market Street, LP 3D-C Chattanooga, TN 37402-2801 SUBJECT: WATTS BAR NUCLEAR PLANT, UNIT 1-REVIEW OF REACTOR VESSEL MATERIALS SURVEILLANCE PROGRAM-REVISED SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULE (TAC NO. MF3162) Dear Mr. Shea: By letter dated November 22, 2013, as supplemented by letters dated February 21, 2014, and March 10, 2014, Tennessee Valley Authority (TVA) requested approval of proposed changes to the reactor vessel surveillance capsule withdrawal schedule for the Watts Bar Nuclear Plant, Unit 1 (WBN-1 ). The proposed changes were submitted pursuant to Title 10 of the Code of Federal Regulations (1 0 CFR) Part 50, Appendix H, Section lli.B.3, which requires that: (1) withdrawal schedules be submitted, as specified in 10 CFR 50.4, and (2) the proposed schedule must be approved by the Nuclear Regulatory Commission (NRC) prior to implementation. The NRC staff has reviewed TVA's submittals and concludes that the changes to the reactor pressure vessel surveillance capsule withdrawal schedule for WBN-1 is acceptable for implementation and satisfied the requirements of 10 CFR Part 50, Appendix H. The NRC staff's evaluation is enclosed. Please contact me at (301) 415-8480 if you have any questions. Docket No. 50-390 Enclosure: Safety Evaluation Sincerely, IRA/ Andrew Hon, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation cc w/enclosure: Distribution via Listserv DISTRIBUTION: RidsNrrDorllpl2-2 RidsNrrPMWattBar1 PUBLIC RidsNrrDoriDpr LPL2-2 R/F RidsRg n2Mai1Center RidsAcrsAcnw _MaiiCTR RidsNrrLABCiayton RidsNrrDeEvib PPurtscher, NRR ADAMS A ccess1on N o.: M L 14083A24 7 *b )_"j_memo ML 14077A254 OFFICE LPLII-2/PM LPLII-2/LA NRR/DE/EVI B/BC* LPLII-2/BC LPLII-2/PM NAME AHon BCiayton SRosenburg JQuichocho AHon DATE 3/25/14 3/25/14 03/20/14 3/27/14 3/27/14 OFFICIAL RECORD COPY