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MONTHYEARML13154A3682013-06-0404 June 2013 Request for Additional Information Regarding Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedule Revision Project stage: RAI ML13192A0342013-07-0303 July 2013 Response to NRC Request for Additional Information Regarding Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedule Revision Project stage: Response to RAI ML13240A3202013-09-27027 September 2013 Revise the Reactor Pressure Vessel Material Surveillance Capsule Withdrawal Schedule Due to License Renewal Amendment (TAC Nos. MF0631 and MF0632) Project stage: Other CNL-16-111, Capsule Withdrawal Schedule Revision2016-12-23023 December 2016 Capsule Withdrawal Schedule Revision Project stage: Other 2013-07-03
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Category:Letter
MONTHYEARML24032A0202024-01-31031 January 2024 NPDES Biocide/Corrosion Treatment Plan Annual Report, Cy 2023 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 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 ML24018A0142024-01-17017 January 2024 Engine Systems, Inc., Report No. 10CFR21-0137, Rev. 1, 56913-EN 56913 ML24011A3182024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), October 2023 ML24011A3172024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), September 2023 ML24011A3202024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), December 2023 ML24011A3162024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), August 2023 ML24011A3192024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), November 2023 IR 05000327/20234422024-01-11011 January 2024 95001 Supplemental Inspection Report 05000327/2023442 and 05000328/2023442 and Follow-Up Assessment Letter ML24010A2132024-01-10010 January 2024 CFR 21.21 Final Report Regarding Siemens Medium Voltage Circuit Breakers ML24018A0952024-01-0404 January 2024 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance Report No. 10CFR21-0137, Rev. 0 ML24004A0332024-01-0303 January 2024 Interim Report of a Deviation or Failure to Comply Crompton Instruments Type 077 Ammeter ML24004A0402024-01-0303 January 2024 Response to NRCs November 8, 2023, Request for Additional Information - Related to Independent Spent Fuel Storage Installation CNL-23-068, 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) ML23346A1222023-12-12012 December 2023 Annual Non-Radiological Environmental Operating Report - 2023 IR 05000327/20234202023-11-28028 November 2023 Security Baseline Inspection Report 05000327/2023420 and 05000328/2023420 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 ML23324A4362023-11-0909 November 2023 Exam Corporate Notification Letter Aka 210-day Letter ML23307A0822023-11-0808 November 2023 Request for Additional Information August 4, 2022, Exemption Request for Deviating from the Conditions of Certificate of Compliance No. 1032, Amendment No. 3, Related to Sequoyah Nuclear Plant Independent Spent Fuel Storage Installation IR 05000327/20230032023-11-0303 November 2023 Integrated Inspection Report 05000327/2023003 and 05000328/2023003 ML23306A1592023-11-0202 November 2023 Enforcement Action EA-22-129 Inspection Readiness Notification ML23292A0792023-10-19019 October 2023 Tennessee Valley Authority - Emergency Plan Implementing Procedure Revision, Includes EPIP-5, Revision 58, General Emergency IR 05000327/20230112023-10-16016 October 2023 Triennial Fire Protection Inspection Report 05000327/2023011 and 05000328/2023011 ML23285A0882023-10-12012 October 2023 Submittal of Sequoyah Nuclear Plant, Units 1 and 2, Submittal of Updated Final Safety Analysis Report Amendment 31 ML23284A4252023-10-11011 October 2023 10 CFR 50.59 and 10 CFR 72.48 Changes, Tests, and Experiments Summary Report; Commitment Summary Report; and Update to the Fire Protection Report ML23283A2792023-10-10010 October 2023 Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Requirements Manual ML23279A0612023-10-0505 October 2023 Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23277A0462023-10-0404 October 2023 Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Specification Bases ML23275A0272023-09-29029 September 2023 Submittal of Discharge Monitoring Report (DMR) Quality Assurance Study 43 Final Report 2023 ML23271A1662023-09-28028 September 2023 Registration of Spent Fuel Storage Cask Pursuant to 10 CFR 72.212(b)(2) 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 IR 05000327/20234032023-09-14014 September 2023 Cyber Security Inspection Report 05000327/2023403 and 05000328/2023403 (Cover Letter) ML23257A0062023-09-14014 September 2023 Enforcement Action EA-22-129 Inspection Postponement Request ML23254A2192023-09-11011 September 2023 Emergency Plan Implementing Procedure Revisions ML23254A0652023-09-0707 September 2023 Registration of Spent Fuel Storage Cask Pursuant to 10 CFR 72.212(b)(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 05000327/20230052023-08-29029 August 2023 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2023005 and 05000328/2023005 ML23233A0122023-08-17017 August 2023 Unit 1 Cycle 25 Refueling Outage - 90-Day Inservice Inspection Summary Report - Supplement ML23233A0142023-08-15015 August 2023 Discharge Monitoring Report (Dmr), July 2023 ML23215A1212023-08-0303 August 2023 301 Exam Administrative Items (2B) Normal Release ML23215A1572023-08-0303 August 2023 Enforcement Action EA-22-129 Inspection Readiness Notification 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 2024-01-04
[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 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) ML22334A0732023-02-0606 February 2023 Issuance of Amendment Nos. 363 and 357 Regarding Modification of the Approved Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors 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 ML22304A1862022-12-0101 December 2022 Revised Authorization of Alternative Request RV-02 for Pressure Isolation Valve Seat Leakage ML22284A0072022-11-0707 November 2022 Authorization of Alternative Request RP-12 for Testing of Centrifugal Charging Pump 1B-B 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 ML22259A2042022-09-29029 September 2022 Correction to Amendment Nos. 358 and 352 Regarding Technical Specifications Task Force Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B ML22263A3752022-09-29029 September 2022 Authorization of Alternative Request RV-02 for Pressure Isolation Valve Seat Leakage ML22210A1182022-08-24024 August 2022 Issuance of Amendment Nos. 358 and 352 Regarding Technical Specifications Task Force Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B ML22165A1052022-07-12012 July 2022 Issuance of Amendment Nos. 357 and 351 Regarding Revision to Technical Specification Table 3.3.1-1, Reactor Trip System Instrumentation 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 ML21298A0312021-10-27027 October 2021 Issuance of Exigent Amendment No. 350 Regarding One-Time Change to Technical Specification 3.4.12, Low Temperature Overpressure Protection System, ML21245A2672021-10-27027 October 2021 NON-PROPRIETARY - Sequoyah Nuclear Plant, Units 1 and 2 - Issuance of Amendment Nos. 356 and 349 Regarding the Transition to Westinghouse Robust Fuel Assembly-2 (RFA-2) Fuel ML21266A3832021-10-0101 October 2021 Authorization of Alternative Request RP-10 for the 1B-B Motor Driven Auxiliary Feedwater Pump ML21131A1632021-05-28028 May 2021 Authorization and Safety Evaluation for Alternative Request No. 21-ISI-1 ML21084A1902021-05-0404 May 2021 Issuance of Amendment Nos. 355 and 348 Regarding Revision to Technical Specification Table 3.3.3-1, Post Accident Monitoring Instrumentation ML21021A3492021-03-0303 March 2021 Issuance of Amendment Nos. 354 and 347 Regarding Revision to Technical Specification 4.2.2, Control Rod Assemblies ML20337A0372021-02-0101 February 2021 Issuance of Amendment No. 353 Regarding Steam Generator Tube Inspection Frequency 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 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 ML20262H0262020-11-12012 November 2020 Issuance of Amendment Nos. 349 and 343 Regarding Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Fluid Oil Pressure ML20108F0492020-04-23023 April 2020 Issuance of Amendment No. 342 Exigent Amendment to Operate One Cycle with One Control Rod Removed ML19319C8312019-11-21021 November 2019 Issuance of Exigent Amendment No. 348 to Operate One Cycle with One Control Rod Removed ML19281B5542019-11-18018 November 2019 Issuance of Amendment Nos. 347 and 341 Request to Adopt TSTF-563, Revision 0, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML19234A0132019-09-23023 September 2019 Alternative Request 18-ISI-1 Regarding Examination of Dissimilar Metal Welds in Reactor Vessel Head ML19179A1352019-09-18018 September 2019 Issuance of Amendment Nos. 346 and 340, Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML18277A1102019-08-27027 August 2019 Units, 1 & 2 Issuance of Amendment Nos. 309, 332, 292, 345, 339, 128, and 31 Regarding Unbalanced Voltage Protection ML19227A1102019-08-26026 August 2019 Alternative Request for the Turbine Driven Auxiliary Feedwater Pumps 10-Year Interval Inservice Testing Program ML19196A2212019-07-18018 July 2019 Issuance of Exigent Amendment Technical Specification Change - Reactor Vessel Level Instrumentation Inoperable ML19058A0292019-05-0707 May 2019 Issuance of Amendments Request to Modify Essential Raw Cooling Water Control Center Breakers and to Revise the Updated Final Safety Analysis Report (SQN-TS-17-04) ML19010A2742019-03-18018 March 2019 Final Safety Evaluation by the Office of Nuclear Reactor Regulation Topical Report- TVA Overall Basin Probable Maximum Precipitation and Local Intense Precipitation, Calculation, CDQ0000002016000041 Tennessee Valley Authority ML18197A3072018-08-30030 August 2018 Issuance of Amendments Regarding Request to Change Technical Specification 3.3.1 and Surveillance Requirement 3.2.4 ML18159A4612018-08-0606 August 2018 Issuance of Amendments Regarding Request to Change Emergency Plan ML18138A4522018-05-29029 May 2018 Bf, Units 1, 2, and 3; Sequoyah, Units 1 and 2; Watts Bar, Units 1 and 2 - Correction to an Omitted Reference for License Amendment Regarding Request to Upgrade (CAC Nos. MF9054, MF9055, MF9056, MF9057, MF9058, MF9059, and MF9060, EPID L-20 ML17289A0322017-12-22022 December 2017 Issuance of Amendments Regarding Request to Upgrade Emergency Action Level Scheme (CAC Nos. MF9054-60; EPID L2017-LLA-0160) ML17034A3602017-03-27027 March 2017 Issuance of Amendment Nos. 298, 322, 282, and 338 and 331 - Revise Technical Specification 5.3, Unit Staff Qualifications to Replace References to Rg 1.8, Rev. 2 with TVA Nuclear Quality ... ML16340A0092017-03-0909 March 2017 Safety Evaluation Regarding Implementation of Mitigation Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML17059B7912017-03-0202 March 2017 Sequoyah Nuclear Plant, Units 1 and 2 - Relief from the Requirements of the American Society of Mechanical Engineer OM Code (CAC Nos. MF9305 and MF9306) ML16228A0962016-10-0303 October 2016 Issuance of Amendments to Change the Completion Date of Cyber Security Plan Implementation Milestone 8 ML16225A2762016-09-29029 September 2016 Issuance of Amendments to Revise Technical Specification for Essential Raw Cooling Water System Allowed Completion Time ML16225A6332016-09-0202 September 2016 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Sequoyah Nuclear Plant, Units 1 and 2; Watts Bar Nuclear Plant, Unit 1 and 2 - Relief Request for Use of Alternate Calibration Block Reflector Requirements 16-PDI-5 (TAC Nos. MF7754-MF7760) ML16123A1312016-05-12012 May 2016 Relief Requests RP-01, RP-02, RP-06, RP-08, and RV-01 Related to the Inservice Testing Program, Fourth 10-Year Interval (CAC Nos. MF7099 and MF7100) ML15329A1862015-12-0404 December 2015 Request for Relief PR-07 for Alternative Inservice Pump Testing at Reference Values ML15320A2182015-11-30030 November 2015 Issuance of Amendments to Revise Technical Specification for Containment Leakage Rate Program 2024-01-29
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UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 September 27, 2013 Mr. Joseph W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 SEOUOYAH NUCLEAR PLANT, UNITS 1 AND 2 -REVISE THE REACTOR PRESSURE VESSEL MATERIAL SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULE DUE TO LICENSE RENEWAL AMENDMENT (TAC NOS. MF0631 AND MF0632) Dear Mr. Shea: By letter dated January 10, 2013, and supplemented by letter dated July 3, 2013, Tennessee Valley Authority submitted a revised reactor pressure vessel (RPV) material surveillance specimen withdrawal schedule for Sequoyah Nuclear Plant (SON), Units 1 and 2. The revised schedule will support license renewal of the SON, Units 1 and 2 operational licenses for an additional 20 years. The NRC staff has completed its review of the revised RPV surveillance capsule withdrawal schedule and concludes that, given the relocation of Capsules Sand W occurs during the 19th or 20th refueling outages, the revised withdrawal dates of end of cycle (EOC) 28 for Unit 1 and EOC 27 for Unit 2, for surveillance capsule S at SON, are acceptable. The revised schedule will meet the expectations of American Society for Testing and Materials E 185-82, NUREG-1801 , Revision 2, "Generic Aging Lessons Learned (GALL) Report," and the requirements of Title 10 of the Code of Federal Regulations, Part 50, Appendix H. Sincerely, Siva P. Lingam, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-327 and Safety cc w/encl: Distribution via UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION OF THE REVISED REACTOR PRESSURE VESSEL MATERIAL SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULE TENNESSEE VALLEY AUTHORITY SEOUOYAH NUCLEAR PLANT. UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328 1.0 INTRODUCTION By letter dated January 10, 2013, (Reference 1), as supplemented by letter dated July 3,2013 (Reference 2), Tennessee Valley Authority (TVA or the licensee) submitted a request to the U.S. Nuclear Regulatory Commission (NRC) to revise the withdrawal date for reactor pressure vessel (RPV) surveillance capsules for Sequoyah Nuclear Plant (SON). Units 1 and 2. The purpose of the licensee's submittal was to obtain NRC approval of a revision to the RPV surveillance specimen withdrawal schedules for the two units at SON. The revised schedules will support license renewal of the SON, Units 1 and 2 operational licenses for an additional 20 years. 2.0 REGULATORY EVALUATION Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Appendix H, "Reactor Vessel Material Surveillance Program Requirements," requires licensees to monitor changes in the fracture toughness properties of ferritic materials in the RPV beltline region of light water nuclear power reactors, which result from exposure of these materials to neutron irradiation and the thermal environment. Appendix H states, "The design of the surveillance program and the withdrawal schedule must meet the requirements of the edition of ASTM [American Society for Testing and Materials] E185 that is current on the issue date of the ASME [American Society of Mechanical Engineers] Boiler and Pressure Vessel Code to which the reactor vessel was purchased. Later editions of ASTM E185 may be used, but including only those editions through 1982." The applicable edition of ASTM E185 for SON, Units 1 and 2 is ASTM E185-82, "Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels." Additionally, Appendix H requires that the licensee submit the ASTM E185 compliant schedules to the NRC for staff approval. The licensee's RPV material surveillance program for the current operating license, which will expire on September 7,2020, for Unit 1 and September 15, 2021, for Unit 2, conforms to ASTM E185-82. ASTM E185-82 recommends that sets of specimens be removed at three or more separate times. As summarized in the Updated Final Safety Analysis Report (UFSAR) and the current submittal, four capsules were used in the existing withdrawal plan; an additional four Enclosure
-2 standby capsules are located in lower fluence regions around the core. The final capsule associated with the current surveillance program at each unit was Surveillance Capsule Y; Capsule Y was removed at 10.03 effective full power years (EFPY) for Unit 1 and at 10.54 EFPY for Unit 2. The most recent change to the surveillance program for each unit (described in Enclosure 2 to Reference 1) involves relocating two of the standby surveillance capsules (Capsules Sand W) from the low fluence regions to higher fluence locations in each unit's RPV. The move would take place at the end of cycle (EOC) 19 or 20 at each unit. The objective of this relocation is to have meaningful data for license renewal and possible subsequent license renewal. The capsule relocation satisfies the criteria for changes under 10 CFR 50.59(c)(1) so that NRC approval for moving the capsules from the low-fluence region to the position with a higher lead factor is not required. To be consistent with NUREG-1801, Revision 2 (the Generic Aging Lessons Learned (GALL) report, Reference 3), the surveillance program must be revised for license renewal so that a capsule will be withdrawn at a neutron fluence level exceeding, but not greater than twice, the peak RPV neutron fluence at 60 years of operation (52 EFPY for SON). This guidance is also consistent with an extrapolation of ASTM E185-82 for the extended license period. The license renewal application (Reference 4) for SON, Units 1 and 2 is currently under NRC staff review. 3.0 TECHNICAL EVALUATION In the process of reviewing the request, the NRC staff determined that additional information was needed to complete the evaluation. The ASTM E185-82 standard practice describes the withdrawal schedule in terms of either a target fluence for the capsule or the EFPY of the RPV, whichever comes first. The licensee's submittal is written in terms of EFPY without the target fluence for the capsule. In request for additional information (RAI) 1, the NRC staff asked the licensee to describe the withdrawal schedule (Tables 1 through 4) in terms of the fast neutron fluence (E>1 million electron volts (MeV)) in addition to the EFPY. Bya letter dated July 3, 2013, TVA provided revisions to Tables 2 through 4 so that the equivalent fast neutron fluence (E>1 MeV) is shown in addition to the plant-specific EFPY values. The licensee points out that Table 1 is a direct copy from the UFSAR and does not need to be updated. The NRC staff has reviewed the revised tables and notes that the information in Table 1 (not revised as part of this RAI response) is included in the revision to Table 4. The NRC staff finds the response acceptable because the information in the revisions to Tables 2 through 4 is adequate to allow the staff to make a regulatory decision. This resolves the issue raised in RAI 1. In the second RAI, the NRC staff asked the licensee to provide a list of all materials included in Capsule S and state if the contents of all the remaining capsules are the same. Furthermore, the NRC staff asked if any other pressurized-water reactor sister plants would use the results from the SON program. In the letter dated July 3,2013, the licensee reproduced the tables from the original WCAP reports (References 5 and 6) where the number and type of specimens included in each capsule for the two units is described. In addition, the licensee clarified that there are no other pressurized-water reactors that would use the results from the SON program. The NRC staff finds the information in the response to RAI 2 acceptable because it clarifies the details regarding the contents of each capsule, resolving the issue raised in RAI2.
-3 For the third RAI, the NRC staff requested technical justification for why the fluence values of the withdrawn capsules reported in Table 4 of the January 10, 2013, submittal are different from those described in the previous capsule analysis reports such as WCAP-15224, Revision 0 and WCAP-15320, Revision 0 (References 7 and 8). In the letter dated July 3, 2013, the licensee summarized the differences as follows. The previous capsule analysis reports were based on the guidance from Draft Regulatory Guide DG-1053, and included a less detailed synthesis approach. The methodology used in the 2012 analysis (Reference 9) reported in Table 4 of the January 10, 2013, submittal is based on a more detailed approach that is described in Equation 4 of Regulatory Guide (RG) 1.190. This methodology has been approved by the NRC staff in WCAP-16083-NP-A (Reference 10). The updated, NRC-approved methodology removes three conservatisms from the analysis and, also, used more cycles of actual reactor performance to project the end of life fluence rather than estimates. The NRC staff has reviewed the response and finds the information to be an adequate summary of the steps taken by the licensee to estimate the neutron fluence at the inside surface of the RPV. Given the explanation in the RAI response, the NRC staff considers the issue resolved since the updated fluence was still determined using NRC-approved, RG 1.190-adherent methods. The original surveillance capsule withdrawal plan spanning the initial license period, ending in 2020 for Unit 1 and 2021 for Unit 2, has already been completed and, as such, 1brms no part of this evaluation. The licensee stated in the submittal that the levi sed plan is to withdraw Capsule S from Unit 1 at the EOC 28. Given that Surveillance Capsule S is moved to the higher fluence location at the EOC 19 or 20, the requested change to the withdrawal schedule would provide a neutron fluence for the Capsule S test samples at SON, Unit 1 of between 2.81 to 2.96 X 1019 n/cm2 (E >1 MeV). The maximum fluence at the RPV inside diameter for the license renewal period at SON, Unit 1 (52 EFPY) has been estimated to be 2.66 X 1019 n/cm2 (E >1 MeV). Therefore, the revised schedule for Unit 1 will result in the fluence on Capsule S exceeding the peak RPV neutron fluence at 60 years of operation, but will not be greater than twice the peak. For Unit 2, the licensee stated in the submittal that the revised plan is to withdraw Capsule S from the RPV at the EOC 27. Provided that Surveillance Capsule S is moved to the higher fluence location at the EOC 19 or 20, the requested change to the withdrawal schedule would produce a neutron fluence for the Capsule S test samples of between 2.65 to 2.78X 1019 n/cm2 (E>1 MeV). The maximum fluence at the RPV inside diameter for the license renewal period at SON, Unit 2 (52 EFPY) has been estimated to be 2.57 X 1019 n/cm2 (E>1 MeV). Therefore, the revised schedule for Unit 2 will result in the fluence on Capsule S exceeding the peak RPV neutron fluence at 60 years of operation, but will not be greater than twice the peak. In summary, given the standby capsules are relocated to the high fluence locations during the 19th or 20th refueling cycle, the removal of Surveillance Capsule S at the EOC 28 for SON, Unit 1 and at the EOC 27 for Unit 2 meets the intent of ASTM E 185-82, the expectation of the GALL report for the period of extended operation, and the requirements of 10 CFR Part 50, Appendix H; therefore, the NRC staff concludes that the proposed changes to the schedules are acceptable.
-4 CONCLUSION Based on the NRC staff's review of the licensee's January 10, 2013, and July 3, 2013, submittals, the NRC staff concludes that, given the relocation of Capsules Sand W occurs during either the 19th or 20th refueling outages, the revised withdrawal dates of EOC 28 for Unit 1 and EOC 27 for Unit 2, for Surveillance Capsule S at SON, are acceptable and will meet the expectations of ASTM E185-82, the GALL report, and the requirements of 10 CFR Part 50, Appendix H. REFERENCES Shea, J. W., Tennessee Valley Authority, letter to U.S. Nuclear Regulatory Commission, "Sequoyah Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedule Revision Due to License Renewal Amendment," dated January 1 0, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 130320295). Shea, J. W., Tennessee Valley Authority, letter to U.S. Nuclear Regulatory Commission, "Response to NRC Request for Additional Information Regarding Reactor Pressure Vessel Surveillance Capsule Withdrawal Schedule Revision," dated July 3, 2013 (ADAMS Accession No. ML13192A034).Section XI.M31 , NUREG-1801, Revision 2, "Generic Aging Lessons Learned (GALL) Report," Nuclear Regulatory Commission, December 2010. Tennessee Valley Authority, submittal to U.S. Nuclear Regulatory Commission, "Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application," dated January 7,2013 (ADAMS Accession No. ML 130240007). Westinghouse Report WCAP-8233, Revision 0, "Tennessee Valley Authority Sequoyah, Unit No.1 Reactor Vessel Radiation Surveillance Program," December 1973. Westinghouse Report WCAP-8513, Revision 0, "Tennessee Valley Authority Sequoyah, Unit No.2 Reactor Vessel Radiation Surveillance Program," November 1975. Westinghouse Report WCAP-15224, Revision 0, "Analysis of Capsule Y from the Tennessee Valley Authority Sequoyah Unit 1 Reactor Vessel Radiation Surveillance Program," dated June 1999. Westinghouse Report WCAP-15320, Revision 0, "Analysis of Capsule Y from the Tennessee Valley Authority Sequoyah Unit 2 Reactor Vessel Radiation Surveillance Program," dated December 1999. Westinghouse Report WCAP-17539-NP, Revision 0, "Sequoyah Units 1 and 2 Time-Limited Aging Analysis on Reactor Vessel Integrity."
-Westinghouse Report WCAP-16083-NP-A, Revision 0, "Benchmark Testing of the FERRET Code for Least Squares Evaluation of Light Water Reactor Dosimetry," dated May 31, 2006 (ADAMS Accession No. ML061600256). Principal Contributor: P. Purtscher Date: September 27,2013 September 27,2013 Mr. Joseph W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 SEOUOYAH NUCLEAR PLANT, UNITS 1 AND 2 -REVISE THE REACTOR PRESSURE VESSEL MATERIAL SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULE DUE TO LICENSE RENEWAL AMENDMENT (TAC NOS. MF0631 AND MF0632) Dear Mr. Shea: By letter dated January 10, 2013, and supplemented by letter dated July 3, 2013, Tennessee Valley Authority submitted a revised reactor pressure vessel (RPV) material surveillance specimen withdrawal schedule for Sequoyah Nuclear Plant (SON), Units 1 and 2. The revised schedule will support license renewal of the SON, Units 1 and 2 operational licenses for an additional 20 years. The NRC staff has completed its review of the revised RPV surveillance capsule withdrawal schedule and concludes that, given the relocation of Capsules Sand W occurs during the 19th or 20th refueling outages, the revised withdrawal dates of end of cycle (EOC) 28 for Unit 1 and EOC 27 for Unit 2, for surveillance capsule S at SON, are acceptable. The revised schedule will meet the expectations of American Society for Testing and Materials E 185-82, NUREG-1801, Revision 2, "Generic Aging Lessons Learned (GALL) Report," and the requirements of Title 10 of the Code of Federal Regulations, Part 50, Appendix H. Sincerely, IRA! Siva P. Lingam, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-327 and Safety cc w/encl: Distribution via Distribution: Public RidsNrrDoriDpr RidsNrrLABClayton RidsAcrsAcnw_MailCTR LPL2-2 RlF RidsNrrDorlLpl2-2 P. Purtscher, NRR RidsRgn2MailCenter RidsNrrDeEvib RidsNrrDlrRarb RidsNrrPMSequoyah J. Medoff, NRR NRR-058ADAMS ACCESSION N 0.: ML13240A *b OFFICE LPL2-2/PM LPL2-2/LA EVIB/BC* RARB/BC C (NLO) LPLlI-2/BC (A) NAME SLingam BClayton SRosenberg DMorey BHarris DBroaddus ( FSaba for) DATE 9/27/13 9/27/13 8/22/13 8/30/13 9/4113 9/27/13 OFFICIAL RECORD