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Results
Other: CNL-13-117, 10 CFR 50.46 - Combined Annual and 30-Day Report, ML11203A113, ML11207A053, ML11320A026, ML12086A311, ML12118A166, ML12125A028, ML12125A189, ML12137A298, ML12138A158, ML12153A378, ML12178A564, ML12185A077, ML12240A199, ML13037A106
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MONTHYEARML11203A1132011-07-21021 July 2011 NRR E-mail Capture - Sequoyah 1 & 2 - LAR Regarding Areva Advanced W17 Htp Fuel (ME6538/6539) Project stage: Other ML11207A0532011-08-0909 August 2011 Request for Withholding Proprietary Information from Public Disclosure Regarding Use of Areva Advanced W17 High Thermal Performance Fuel. Project stage: Other ML11269A0532011-10-14014 October 2011 Request for Additional Information Regarding the Proposed Technical Specification Changes to Allow Use of Areva Advanced W17 High Thermal Performance Fuel Project stage: RAI ML11320A0262011-12-27027 December 2011 Request for Withholding Proprietary Information from Public Disclosure Regarding Use of Areva Advanced W17 High Thermal Performance Fuel Project stage: Other ML12025A0272012-02-0808 February 2012 Request for Additional Information Regarding the Proposed Technical Specification Changes to Allow Use of Areva Advance W17 High Thermal Performance Fuel (TAC Nos. ME6538 & ME6539) Project stage: RAI ML12088A1702012-03-23023 March 2012 Response to NRC Second Request for Additional Information Regarding Application to Modify Technical Specifications for Use of Areva Advanced W17 Htp Fuel (TS-SQN-2011-07) Project stage: Request ML12118A1652012-04-26026 April 2012 Response to NRC Third Request for Additional Information Regarding Application to Modify Technical Specifications for Use of Areva Advanced W17 Htp Fuel (TS-SQN-2011-07) Project stage: Request ML12118A1662012-04-26026 April 2012 ANP-2970Q1(NP), Revision 000, Htp Fuel Realistic Large Break LOCA Analysis, April 2012 (Non-Proprietary Version), Enclosure 2 Project stage: Other ML12125A0282012-05-0202 May 2012 NRR E-mail Capture - Sequoyah, Units 1 & 2 - Areva Advanced W17 Htp Fuel Transition Project stage: Other ML12086A3112012-05-0404 May 2012 Request for Withholding Proprietary Information from Public Disclosure Regarding Use of Areva Advanced W17 High Thermal Performance Fuel (TAC Nos. ME6538 and ME6539) Project stage: Other ML12137A2982012-05-15015 May 2012 ANP-2970Q2(NP), Rev 0, Sequoyah, Units 1 and 2 Htp Fuel Realistic Large Break LOCA Analysis Project stage: Other ML12137A2972012-05-15015 May 2012 Response to NRC Fourth Request for Additional Information Regarding Application to Modify Technical Specifications for Use of Areva Advanced W17 Htp Fuel (TS-SQN-2011-07) Project stage: Request ML12153A3772012-05-24024 May 2012 Response to NRC Fifth Request for Additional Information Regarding Application to Modify Technical Specifications for Use of Areva Advanced W17 Htp Fuel (TS-SQN-2011-07) Project stage: Request ML12138A1582012-05-29029 May 2012 Request for Withholding Proprietary Information from Public Disclosure Regarding Use of Areva Advanced W17 Thermal Performance Fuel Project stage: Other ML12125A1892012-05-29029 May 2012 Request for Withholding Proprietary Information from Public Disclosure Regarding Use of Areva Advanced W17 High Thermal Performance Fuel Project stage: Other ML12153A3782012-05-31031 May 2012 Enclosure 2, Sequoyah Nuclear Plant, Units 1 & 2 - ANP-3053 (Np), Revision 3, Sequoyah Htp Fuel Transition - NRC RAIs and Responses Project stage: Other ML1218500092012-06-26026 June 2012 Response to NRC Sixth Request for Additional Information Regarding Application to Modify Technical Specifications for Use of Areva Advanced W17 Htp Fuel (TS-SQN-2011-07) Project stage: Request ML12178A5642012-07-0505 July 2012 Request for Withholding Proprietary Information from Public Disclosure Regarding Use of Areva Advanced W17 High Thermal Performance Fuel (TAC Nos. ME6538 and ME6539) Project stage: Other ML12185A0772012-07-0909 July 2012 Request for Withholding Proprietary Information from Public Disclosure Regarding Use of Areva Advanced W17 High Thermal Performance Fuel Project stage: Other ML12240A1992012-09-0606 September 2012 PI for Sequoyah 1 and 2- Permit Use of Advanced W17 Htp Fuel (TAC Nos. ME6538/6539) Project stage: Other ML12249A3942012-09-26026 September 2012 Issuance of Amendments to Revise the Technical Specification to Allow Use of Areva Advanced W17 High Thermal Performance Fuel (TS-SQN-2011-07) Project stage: Approval ML13037A1062013-01-31031 January 2013 10 CFR 50.46 - 30-Day Special Report for Sequoyah Nuclear Plant, Unit 2 Regarding Changes to the Calculated Peak Cladding Temperature Emergency Core Cooling System Evaluation Models Project stage: Other CNL-13-117, 10 CFR 50.46 - Combined Annual and 30-Day Report2013-11-18018 November 2013 10 CFR 50.46 - Combined Annual and 30-Day Report Project stage: Other 2012-05-24
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Category:Letter
MONTHYEARCNL-24-047, Decommitment of Flood Mode Mitigation Improvement Systems2024-09-24024 September 2024 Decommitment of Flood Mode Mitigation Improvement Systems CNL-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 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 ML24267A0402024-09-19019 September 2024 Cycle 27 Core Operating Limits Report Revision 0 ML24185A1742024-09-18018 September 2024 Cover Letter - Issuance of Exemption Related to Non-Destructive Examination Compliance Regarding Sequoyah Nuclear Plant Independent Spent Fuel Storage Installation 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 ML24253A0152024-09-0808 September 2024 Emergency Plan Implementing Procedure Revisions ML24247A2212024-08-29029 August 2024 Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) Letter OG-21-160, NEI 03-08 Needed Guidance: PWR Lower Radial Support Clevis Insert X-750 Bolt Inspection Requirements, September 1, 2021 ML24247A1802024-08-28028 August 2024 Application to Revise the Fuel Handling Accident Analysis, to Delete Technical Specification 3.9.4, Containment Penetrations, and to Modify Technical Specification 3.3.6, Containment Ventilation Isolation Instrumentation for Sequoyah Nuclea IR 05000327/20240052024-08-26026 August 2024 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2024005 and 05000328/2024005 ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 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), IR 05000327/20240022024-07-31031 July 2024 Integrated Inspection Report 05000327/2024002 and 05000328/2024002 ML24211A0542024-07-29029 July 2024 Operator License Examination Report ML24211A0572024-07-29029 July 2024 Submittal of Emergency Plan Implementing Procedure Revision ML24211A0412024-07-26026 July 2024 Unit 1 Cycle 26 Refueling Outage - 90-Day Inservice Inspection Summary Report 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 ML24191A4652024-07-0909 July 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24177A0282024-06-25025 June 2024 Emergency Plan Implementing Procedure Revisions ML24176A0222024-06-24024 June 2024 Retraction of Interim Report of a Deviation or Failure to Comply – Transducer Model 8005N 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) ML24145A0852024-05-30030 May 2024 1B-B Diesel Generator Failure - Final Significance Determination Letter ML24145A1052024-05-29029 May 2024 301 Exam Approval Letter ML24134A1762024-05-13013 May 2024 Submittal of 2023 Annual Radiological Environmental Operating Report 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 ML24128A0352024-05-0707 May 2024 Providing Supplemental Information to Apparent Violation ML24120A0582024-04-26026 April 2024 10 CFR 50.46 Annual Report for Sequoyah Nuclear Plant Units 1 and 2 ML24116A2612024-04-25025 April 2024 Interim Report of a Deviation or Failure to Comply - Transducer Model 8005N ML24114A0482024-04-23023 April 2024 Annual Radioactive Effluent Release Report for 2023 Monitoring Period 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 ML24144A2322024-04-20020 April 2024 Tennessee Multi-Sector Permit (Tmsp), 2024 Annual Discharge Monitoring Report for Outfalls SW-3, SW-3, and SW-9 ML24144A2362024-04-20020 April 2024 Discharge Monitoring Report (Dmr), March 2024 ML24102A1212024-04-18018 April 2024 Summary of Conference Call with Tennessee Valley Authority Regarding Sequoyah Nuclear Plant, Unit 1 Spring 2024 Steam Generator Tube Inspections ML24089A0882024-04-18018 April 2024 – Exemption from Select Requirements of 10 CFR Part 73; Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting 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 IR 05000327/20240012024-04-17017 April 2024 Integrated Inspection Report 05000327/2024001 and 05000328/2024001 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 ML24109A0272024-04-16016 April 2024 Cycle 27 Core Operating Limits Report Revision 0 CNL-23-006, Application to Modify Technical Specifications 3.8.1, AC Sources – Operating, and 3.8.2, AC Sources – Shutdown, for Sequoyah Nuclear Plant (SQN-TSC-22-03)2024-04-15015 April 2024 Application to Modify Technical Specifications 3.8.1, AC Sources – Operating, and 3.8.2, AC Sources – Shutdown, for Sequoyah Nuclear Plant (SQN-TSC-22-03) ML24106A0502024-04-12012 April 2024 Discharge Monitoring Report (Dmr), February 2024 ML24100A0162024-04-11011 April 2024 Request for Regulatory Conference (Tennessee Valley Authority - Sequoyah Nuclear Plant) 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 ML24088A0332024-03-28028 March 2024 Request for Regulatory Conference (Tennessee Valley Authority) 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-24-007, Annual Insurance Status Report2024-03-27027 March 2024 Annual Insurance Status Report ML24040A2062024-03-26026 March 2024 Issuance of Amendment Nos. 367 and 361 Regarding Changes to the Hydrologic Analyses (EPID L-2020-LLA-0004) - Public IR 05000327/20240902024-03-19019 March 2024 NRC Inspection Report 05000327-2024090 and 05000328-2024090 and Preliminary Greater than Green Finding and Apparent Violation CNL-24-027, Response to Request for Additional Information Regarding Sequoyah 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 Sequoyah 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 2024-09-08
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24152A1542024-05-31031 May 2024 Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2024-03 ML24116A2012024-04-17017 April 2024 Nrctva ISFSI CBS (RFI) ML24045A1002024-02-13013 February 2024 NRR E-mail Capture - Request for Additional Information Related to the Sequoyah Exemption Request for the 10 CFR Part 73 Enhanced Weapons Rule 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 ML23307A0832023-11-0808 November 2023 Enclosure - Request for Additional Information HDI-Sequoyah NDE Exemption Request 10-30-2023 ML23062A5942023-02-27027 February 2023 Enclosure - NRC SQN Exemption Rsi Response Staff Follow Up Questions ML23062A5952023-02-27027 February 2023 Staff follow-up Questions to Tva'S 12/19/2022 Response of the Staff'S Rsi Regarding 08/04/2022 SQN Exemption Request ML22343A0692022-12-0808 December 2022 NRR E-mail Capture - Request for Additional Information - Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.4.12 (L-2022-LLA-0103) ML22257A0622022-09-14014 September 2022 Requalification Program Inspection - Sequoyah Nuclear Plant ML22255A0842022-09-0909 September 2022 Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2022-04 ML22227A0272022-08-11011 August 2022 NRR E-mail Capture - Request for Additional Information Related to Alternative Requests RP-11 for Sequoyah Nuclear Plant, Units 1 and 2, and IST-RR-9 for Watts Bar Nuclear Plant, Units 1 and 2 ML22214A1582022-08-0202 August 2022 NRR E-mail Capture - Request for Additional Information for Sequoyah Units 1 and 2 License Amendment Request for Fire and Seismic PRA Modification to 10 CFR 50.69 (L-2022-LLA-0033) ML22151A0102022-05-27027 May 2022 NRR E-mail Capture - Revised Request for Additional Information Re Sequoyah Nuclear Plant Alternative Request RV-02 ML22146A3322022-05-26026 May 2022 NRR E-mail Capture - Request for Additional Information Related to Sequoyah Nuclear Plant'S LAR to Adopt TSTF-505 ML22151A0092022-05-26026 May 2022 NRR E-mail Capture - Request for Additional Information Re Sequoyah Nuclear Plant Alternative Request RV-02 ML22144A1002022-05-12012 May 2022 NRR E-mail Capture - Request for Additional Information Related to Tva'S Request to Revised the TVA Plants' Radiological Emergency Plans ML21237A4952021-08-25025 August 2021 Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2021-04 ML21160A0352021-06-0303 June 2021 Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2021-03 ML21095A0482021-04-0505 April 2021 NRR E-mail Capture - Sequoyah Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding Request to Transition to Westinghouse Fuel ML21092A0972021-04-0202 April 2021 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML20259A4782020-09-15015 September 2020 Emergency Preparedness Program Inspection Request for Information ML20261H4172020-09-14014 September 2020 NRR E-mail Capture - Sequoyah Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding Hydrologic UFSAR Update ML20261H4162020-09-0202 September 2020 NRR E-mail Capture - Draft Request for Additional Information - Sequoyah Nuclear Plant, Units 1 and 2, Request to Revise UFSAR Hydrologic Analysis ML20189A2112020-07-0101 July 2020 Request for Additional Information Regarding Hydrologic UFSAR Update ML20106F1042020-04-14014 April 2020 Request for Additional Information Regarding the Hydrologic Analysis LAR ML20161A3902020-04-0909 April 2020 Request for Supporting Information for the Sequoyah SPRA Audit Review - Follow-up to Plant Response Question 5 ML20098D8612020-04-0707 April 2020 Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000327/2020012 and 05000328/2020012) and Request for Information) ML20036E2842020-02-0505 February 2020 20200123 - Sequoyah Radiation Safety Inspection Document Request Letter ML19323D7562019-11-18018 November 2019 Nrc'S Request for Additional Information - Exigent Amendment ML19235A0992019-08-22022 August 2019 Emergency Preparedness Program Inspection Request for Information ML19162A2462019-06-11011 June 2019 RP Inspection Document Request 2019-03 ML19149A6222019-05-29029 May 2019 NRR E-mail Capture - Request for Additional Information - Sequoyah Nuclear Plant, Units 1 and 2, Request for Alternative to 18-ISI-1 EPID: L-2019-LLR-0006 ML19148A7912019-05-28028 May 2019 NRR E-mail Capture - Sequoyah Nuclear Plant and Watts Bar Nuclear Plant - Final Request for Additional Information Related to Request for Alternative to OM Code Requirements ML19015A4192019-01-15015 January 2019 NRR E-mail Capture - RAI - Sequoyah Nuclear Plant, Units 1 and 2, LAR to Adopt 10 CFR50.69 Risk-informed SSC ML18344A0752018-12-10010 December 2018 NRR E-mail Capture - Request for Additional Information - Sequoyah 1 and 2, Request to Modify Essential Raw Cooling Water Motor Control Center Breakers and to Revise Updated Final Analysis Report (SQN-TS-17-04) ML18296A0022018-10-22022 October 2018 NRR E-mail Capture - Additional Information Needs - Sequoyah Units 1 and 2, Request to Modify Essential Raw Cooling Water Motor Control Center Breakers Revise Updated Final Analysis Report (SQN-TS-17-04) ML18283B0592018-10-10010 October 2018 NRR E-mail Capture - Additional Information Needs Identified During Audit - Sequoyah 1 and 2, Request to Modify Essential Raw Cooling Water Motor Control Center Breakers Revise Updated Final Analysis Report (SQN-TS-17-04) ML18283A6232018-09-25025 September 2018 04 RP Inspection Document Request ML18233A1942018-08-21021 August 2018 NRR E-mail Capture - Additional Information Needs Identified - Sequoyah 1 and 2, Request to Modify Essential Raw Cooling Water Motor Control Center Breakers and to Revise Updated Final Analysis Report (SQN-TS-17-04) ML18138A1102018-05-17017 May 2018 Enclosurequest for Additional Information (Letter to E. D. Schrull Request for Additional Information Regarding Tennessee Valley Authority'S Decommissioning Funding Plan Update for Browns Ferry and Sequoyah Isfsis) ML18057A6372018-02-23023 February 2018 NRR E-mail Capture - Request for Additional Information Related to TVA Fleet Topical Report TVA-NPG-AWA16 - EPIC: L-2016-TOP-0011) ML17191A2062017-07-0606 July 2017 NRR E-mail Capture - Sequoyah Nuclear Station, Unit 1 & 2 - Request for Additional Information Related to LAR for Technical Specification 3.8.1.17 Note Modification (CAC Nos. MF9398 and MF9399) ML17150A0792017-05-23023 May 2017 NRR E-mail Capture - Request for Additional Information Related to TVA Fleet LAR for EAL Change to Adopt NEI-99-01 Rev.6 (CAC Nos. MF9054 - MF9060) ML17112A0402017-04-20020 April 2017 NRR E-mail Capture - Sequoyah Nuclear Station, Unit 1 & 2 - Request for Additional Information Related to LAR for Technical Specification 3.8.1, AC SOURCES-OPERATING ML17004A0612017-01-0404 January 2017 Notification of NRC Triennial Fire Protection Inspection (Team)(Report 05000327/2017007 and 05000328/2017007) ML15194A3882015-07-13013 July 2015 Request for Additional Information Related to LAR to Revise Ice Condenser Ice Mas Tech Spec ML15175A2912015-06-24024 June 2015 E-mail Re. Request for Additional Information RR RP-07 ML15159B1642015-06-22022 June 2015 Requests for Additional Information for the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application-Set 25 (TAC Nos. MF0481 and MF0482) ML15050A0962015-02-19019 February 2015 E-mail Re. Request for Additional Information Related to LAR to Ice Condendser Inc Mass Tech Spec ML15042A4702015-02-11011 February 2015 E-mail Re. Request for Additional Information Related to License Amendment Request to Revise Technical Specification on Ultimate Heat Sink 2024-05-31
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 14, 2011 Mr. R. M. Krich Vice President, Nuclear Licensing Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION REGARDING THE PROPOPSED TECHNICAL SPECIFICATION CHANGES TO ALLOW USE OF AREVA ADVANCED W17 HIGH THERMAL PERFORMANCE FUEL (TAC NOS. ME6538 AND ME6539)
Dear Mr. Krich:
By letter dated June 17, 2011, and supplemented by letter dated July 27, 2011, you submitted an application for license amendment to revise the Sequoyah Nuclear Plant, Units 1 and 2 Technical Specifications to allow the use of AREVA Advanced W17 High Thermal Performance Fuel to address fuel assembly distortion and its resultant fuel handling issues. The Nuclear Regulatory Commission staff is reviewing the submittal and has determined that additional information is required to complete its evaluation. This request was discussed with Mr. Dan Green of your staff on September 26, 2011, and it was agreed that a response would be provided within 30 days from the date of this letter. If you have any questions regarding this matter, I can be reached at 301-415-1564. Sincerely, Siva P. Lingam, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-327 and 50-328
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv REQUEST FOR ADDITIONAL I NFORMA TION REGARDING TECHNICAL SPECIFICATION CHANGES TO ALLOW USE OF AREVA ADVANCED W17 HIGH THERMAL PERFORMANCE FUEL SEQUOYAH NUCLEAR PLANT. UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328 By letter dated June 17, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 111720780), and supplemented by letter dated July 27,2011 (ADAMS Accession No. ML 112101798), the Tennessee Valley Authority (the licensee), submitted a license amendment request to revise the Sequoyah Nuclear Plant, Units 1 and 2, Technical Specifications to allow the use of AREVA Advanced W17 High Thermal Performance Fuel to address fuel assembly distortion and its resultant fuel handling issues. In order to complete its review of the above documents, the Nuclear Regulatory Commission (NRC) staff needs the following additional information: Question 1 Title 10 of the Code ofFederal Regulations (10 CFR), Section 100.11, "Determination of exclusion area, low population zone, and population center distance," and 10 CFR Part 50, Appendix A, "General Design Criteria for Nuclear Power Plants," Criterion 19, "Control room," set regulatory dose limits for offsite and control room after a design basis accident. Section 50.67, "Accident source term," of 10 CFR. states that the NRC may issue amendments only if the applicant's analysis demonstrates that certain onsite and control room dose limits are met. Regulatory Guide (RG) 1.183, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors," (ADAMS Accession No. ML003716792) provides guidance to licensees on performing evaluations and reanalyses in support of meeting the dose limits in 10 CFR 50.67. RG 1.195, "Methods and Assumptions for Evaluating Radiological Consequences of Design Basis Accidents at Nuclear Power Reactors," (ADAMS Accession No. ML031490640) provides guidance to licensees for performing evaluations and reanalysis in support of meeting 10 CFR 100.11. Standard Review Plan 15.0.1, "Radiological Consequence Analyses Using Alternative Source Terms," (ADAMS Accession No. ML003734190) states: The reviewer should evaluate the AST [Alternative Source Term] proposed by the licensee against the guidance in RG-1.183. Differences between the licensee's proposal and the guidance should be resolved with the licensee. Although the licensee is allowed to propose alternatives to the guidance, large amounts of staff resources were expended in developing the revised source term (Ref. 5) from which the RG-1.183 source term was derived. Section 2.0 of RG-1.183 provides generic guidance on what would be Enclosure
-2 expected before the staff would approve an AST with deviations from AST in Section 3.0 of the Standard Review Plan 15.0.1 also states: The analysis methods and assumptions used by the licensee in determining the core inventory should be reviewed to ensure that they are based on current licensing basis rated thermal power, enrichment, and burnup. A modification to the licensing basis fuel type can have the potential to change the core isotopic distribution and inventory assumed in post accident conditions. The impacts regarding the core inventory and enrichment are not discussed in the proposed amendment. The amendment states that burnup limits are "similar" to the current fuel, but does not provide the new burnup limits. Please verify that the core inventory, enrichment, and burnup are not changed or are bounded by the proposed amendment. If these parameters are bounded, please provide a justification for the statement that they are bounded. Please confirm that the burnup and linear heat generation rates in footnote 11, Regulatory Position 3.2 of RG 1.183 are met, or justify the source terms used. Question 2 Regulatory Position 1.3.2, liRe-Analysis Guidance," of RG 1.183 states: Any implementation of an AST, full or selective, and any associated facility modification should be supported by evaluations of all significant radiological and nonradiological impacts of the proposed actions. This evaluation should consider the impact of the proposed changes on the facility's compliance with the regulations and commitments listed above as well as any other facility-specific requirements. These impacts may be due to (1) the associated facility modifications or (2) the differences in the AST characteristics. The scope and extent of the re-evaluation will necessarily be a function of the specific proposed facility modification2 and whether a full or selective implementation is being pursued. The NRC staff does not expect a complete recalculation of all facility radiological analyses, but does expect licensees to evaluate all impacts of the proposed changes and to update the affected analyses and the design bases appropriately. An analysis is considered to be affected if the proposed modification changes one or more assumptions or inputs used in that analysis such that the results, or the conclusions drawn on those results, are no longer valid. The proposed amendment states that the fuel rod and fuel pellet materials and design are "similar" to the current fuel, but does not provide any specific details regarding the impact of the proposed change on the analysis of record. For example, changes to the structure of the fuel rod could impact the assumed amount of fuel damage as a result of a fuel handling accident. In order for the NRC staff to evaluate the impact of the proposed change, please provide any changes to the parameters, assumptions, or methodologies in the radiological design-basis
-3 accident (DBA) analyses and a justification for those changes. If there are changes to the radiological DBA analyses, please provide the resulting change to the calculated radiological consequence of the DBA.
October 14, 2011 Mr. R. M. Krich Vice President, Nuclear Licensing Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION REGARDING THE PROPOPSED TECHNICAL SPECIFICATION CHANGES TO ALLOW USE OF AREVA ADVANCED W17 HIGH THERMAL PERFORMANCE FUEL (TAC NOS. ME6538 AND ME6539)
Dear Mr. Krich:
By letter dated June 17, 2011, and supplemented by letter dated July 27,2011, you submitted an application for license amendment to revise the Sequoyah Nuclear Plant, Units 1 and 2 Technical Specifications to allow the use of AREVA Advanced W17 High Thermal Performance Fuel to address fuel assembly distortion and its resultant fuel handling issues. The Nuclear Regulatory Commission staff is reviewing the submittal and has determined that additional information is required to complete its evaluation. This request was discussed with Mr. Dan Green of your staff on September 26, 2011, and it was agreed that a response would be provided within 30 days from the date of this letter. If you have any questions regarding this matter, I can be reached at 301-415-1564. Sincerely, IRA! Siva P. Lingam, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-327 and 50-328
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION: PUBLIC LPL2-2 R/F RidsNrrDorlLpl2-2 RidsNrrPMSequoyah RidsNrrLACSola RidsOgcMailCenter RidsNrrDorlDpr RidsAcrsAcnw _MaiICTR RidsNrrDraAadb RidsRgn2MailCenter M. Blumberg. MDB ADAMS Accession No: ML 11269A053 OFFICE LPL2-2/PM LPL2-2/LA NAME SUngam CSoia 09/27/11 *transmitted b memo dated NRR/DRNMDB/BC LPL2-2/BC LPL2-2/PM nate SUngam 09/20/11
- 10114/11 OFFICIAL RECORD COpy