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MONTHYEARML11249A0612011-08-31031 August 2011 Application for Temporary Change to TS to Allow Use of Penetrations in Shield Building Dome During Modes 1 Through 4;and Request for Specific Usage of Alternate Source Term Methodology for Calculating Radiation Doses Associated. Project stage: Request ML11273A1692011-09-29029 September 2011 Application to Revise Sequoyah Nuclear Plant, Unit 1, Operating License and Technical Specification 3.7.5, Ultimate Heat Sink, to Support Steam Generator Replacement Project (TS-SQN-2011-05) Project stage: Request ML11285A0042011-10-11011 October 2011 NRR E-mail Capture - Sequoyah 2 - Acceptance Review of LAR Requesting to Allow Use of One of the SB Dome Penetrations Project stage: Acceptance Review ML11334A0542011-11-28028 November 2011 Request for Expedited Review of a Licensing Amendment Request Supporting the Unit 2, Steam Generator Replacement Project Project stage: Request ML11356A2262011-12-29029 December 2011 Request for Additional Information Regarding the Proposed Technical Specification Changes to Allow Use of Shield Building Dome Penetrations During Modes 1 Through 4 Project stage: RAI ML12032A2702012-01-27027 January 2012 Response to NRC Request for Additional Information Regarding Proposed Technical Specification Changes to Allow Use of Shield Building Dome Penetrations During Modes 1 Through 4 Project stage: Response to RAI ML12011A0272012-01-30030 January 2012 Request for Additional Information Regarding the Proposed Technical Specification Changes to Allow Used of Shield Building Dome Penetrations During Modes 1 Through 4 Project stage: RAI ML12038A2492012-02-0707 February 2012 NRR E-mail Capture - Sequoyah, Unit 2 - Allow Use of Penetrations in SB Dome During Modes 1 Through 4 Project stage: Other ML12074A0362012-02-29029 February 2012 Response to NRC Second Request for Additional Information Regarding the Proposed Technical Specification Changes to Allow Use of Shield Building Dome Penetrations During Modes 1 Through 4 Project stage: Request ML12072A2362012-03-0808 March 2012 Response to NRC Third Request for Additional Information Regarding the Proposed Technical Specification Changes to Allow Use of Shield Building Dome Penetrations During Modes 1 Through 4 Project stage: Request ML12121A3442012-05-15015 May 2012 Request for Additional Information Regarding the Proposed Technical Specification Changes to Allow Use of Shield Building Dome Penetrations During Modes 1-4 Project stage: RAI ML12160A3572012-06-0707 June 2012 Response to Request for Additional Information on License Amendment Regarding Proposed Technical Specification Changes to Allow Use of Shield Building Dome Penetrations During Modes 1 Through 4; Withdrawal of Request Project stage: Withdrawal ML12165A6932012-06-27027 June 2012 Federal Register Notice - Notice of Withdrawal of an Amendment Project stage: Withdrawal ML12165A6912012-06-27027 June 2012 Letter - Withdrawal of an Amendment Request to Allow Use of Shield Building Dome Penetrations During Modes 1 Through 4 Project stage: Withdrawal NRC-2012-0160, Federal Register Notice - Notice of Withdrawal of an Amendment2012-06-27027 June 2012 Federal Register Notice - Notice of Withdrawal of an Amendment Project stage: Withdrawal 2012-01-30
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Category:Letter
MONTHYEARML24304A8492024-10-31031 October 2024 December 2024 Requalification Inspection Notification Letter IR 05000327/20250102024-10-29029 October 2024 Notification of Sequoyah, Units 1 and 2 - Comprehensive Engineering Team Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000327/2025010 and 05000328/2025010 ML24298A1172024-10-24024 October 2024 Cycle 26, 180-Day Steam Generator Tube Inspection Report CNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 05000327/LER-2024-001, Reactor Trip Due to a Turbine Trip2024-10-17017 October 2024 Reactor Trip Due to a Turbine Trip ML24282B0412024-10-15015 October 2024 Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 ML24260A1682024-10-0404 October 2024 Regulatory Audit Summary Related to Request to Add and Revise Notes Related to Technical Specification Table 3.3.2-1, Function 5 ML24284A1072024-09-26026 September 2024 Affidavit for Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2 05000328/LER-2024-001, Reactor Trip Due to an Electrical Trouble Turbine Trip2024-09-25025 September 2024 Reactor Trip Due to an Electrical Trouble Turbine Trip 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 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 ML24267A0402024-09-19019 September 2024 Cycle 27 Core Operating Limits Report Revision 0 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 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 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 ML24211A0572024-07-29029 July 2024 Submittal of Emergency Plan Implementing Procedure Revision ML24211A0542024-07-29029 July 2024 Operator License Examination Report 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 ML24144A2362024-04-20020 April 2024 Discharge Monitoring Report (Dmr), March 2024 ML24144A2322024-04-20020 April 2024 Tennessee Multi-Sector Permit (Tmsp), 2024 Annual Discharge Monitoring Report for Outfalls SW-3, SW-3, and SW-9 ML24089A0882024-04-18018 April 2024 – Exemption from Select Requirements of 10 CFR Part 73; Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting 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 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 IR 05000327/20240012024-04-17017 April 2024 Integrated Inspection Report 05000327/2024001 and 05000328/2024001 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 2024-09-08
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Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 November 28, 2011 10 CFR 50.4 10 CFR 50.90 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Unit 2 Facility Operating License No. DPR-79 NRC Docket No. 50-328
Subject:
Request for Expedited Review of a Licensing Amendment Request Supporting the Sequoyah Nuclear Plant, Unit 2, Steam Generator Replacement Project
Reference:
Letter from TVA to NRC, "Application for Temporary Change to Technical Specifications to Allow Use of Penetrations in Shield Building Dome During Modes 1 through 4; and Request for Specific Usage of Alternate Source Term Methodology for Calculating Radiation Doses Associated with the Proposed Temporary Change to Technical Specifications (TS-SQN-2011-03)," dated August 31, 2011 The purpose of this letter is to request a revised approval date for the reference License Amendment Request (LAR) to support the Sequoyah Nuclear Plant (SQN), Unit 2, Steam Generator Replacement Project. The proposed change requested in the reference LAR will allow opening one of the penetration hatches in the SQN, Unit 2, Shield Building dome for up to five hours per day, six days per week, while in Modes 1 through 4 during Unit 2 Cycle 18. The Tennessee Valley Authority (TVA) plans to replace the SQN, Unit 2, steam generators in the Unit 2 Cycle 18 Refueling Outage (U2R18), scheduled to start in the fall of 2012.
~I~3O0
U.S. Nuclear Regulatory Commission Page 2 November 28, 2011 As discussed in the cover letter for the LAR, use of the Shield Building penetration hatches will provide Steam Generator Replacement Project workers an alternate path for moving materials inside the annulus to support on-line work. The annulus is the area between the concrete Shield Building and the steel containment vessel. Without use of the Shield Building penetration hatches, materials would have to be transported through the Auxiliary Building to the annulus access door and subsequently be hoisted up the annulus access ladders. By bypassing the Auxiliary Building and the annulus access ladders, the risk of potential adverse effects to sensitive equipment along that transport path and resulting challenges to nuclear safety are reduced. The alternate path is estimated to save approximately 2.8 rem by allowing material to be passed through the open dome penetration hatch in lieu of transporting the material through higher dose areas. In addition, passing material through the open dome hatch will improve the industrial safety aspect of the work and will provide an inherent enhancement to material handling safety since material will be staged closer to the point of use.
To facilitate the Steam Generator Replacement Project, TVA requests approval of the reference LAR by May 1, 2012, to support work in advance of SQN U2R18, during which the replacement steam generators will be installed. The reference LAR originally requested approval by August 2012.
Should you have any questions, please contact Clyde Mackaman at (423) 751-2834.
Respectfully, Shea cc:
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Sequoyah Nuclear Plant