|
---|
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 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 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 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 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:Licensee 30-Day Written Event Report
MONTHYEARML18018B1582018-01-18018 January 2018 Submittal of 10CFR 50.46 30-Day Report ML17243A0052017-08-30030 August 2017 Submittal of 10 CFR 50.46 30-Day Report ML15322A0552015-11-13013 November 2015 Transmittal of Pressure Temperature Limits Report, Revision 5 and 6 ML13115A2652013-04-23023 April 2013 Submittal of 10 CFR 50.46 - 30-Day Special Report 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 ML12160A3562012-06-0505 June 2012 Submittal of 30-Day Special Report of Changes to Calculated Peak Cladding Temperature ML11199A0052011-07-14014 July 2011 NPDES Permit No. TN0026450 - Written Submission Regarding Diffuser Pond Release ML1106007012011-02-25025 February 2011 Tennessee Valley Authority - Sequoyah Nuclear Plant - Tennessee Storm Water Multi-Sector General Permit for Industrial Activities Permit No. TNRO50015 Sector 0 Exceedance of the Benchmark Monitoring Requirement ML0830305442008-10-29029 October 2008 CFR 50.46 -30-Day Special Report of Significant Changes ML0815706742008-06-0404 June 2008 10 CFR 50.46 - 30-Day Special Report of Significant Changes ML0815706652008-06-0303 June 2008 10 CFR 50.46 - 30-Day Special Report of Significant Changes ML0522203852005-08-0202 August 2005 Technical Specification (TS) 3.3.3.10 - Special Report 2005-01 ML0432700322004-11-16016 November 2004 Changes in Permits and Certifications, Special Report ML0325804392003-09-0202 September 2003 LER 03-S01-00, Sequoyah Units 1 & 2, 30-Day Report Re Uncontrolled Security Weapon in the Protected Area 2018-01-18
[Table view] |
Text
October 29, 2008
10 CFR 50.46
U.S. Nuclear Regulatory Commission
ATTN: Document Control Desk
Washington, D.C. 20555-0001
Gentlemen:
In the Matter of ) Docket No. 50-327 Tennessee Valley Authority (TVA) )
SEQUOYAH NUCLEAR PLANT (SQN) - 10 CFR 50.46 DAY SPECIAL REPORT OF SIGNIFICANT CHANGES - UNIT 1
Reference:
TVA letter to NRC dated June 4, 2008, "Sequoyah Nuclear Plant (SQN) -
10 CFR 50.46 Day Special Report of Significant Changes"
The purpose of this letter is to provide changes to the calculated peak cladding
temperature (PCT) resulting from recent changes to the SQN emergency core cooling
system (ECCS) evaluation model. This subm ittal satisfies the reporting requirements in accordance with 10 CFR 50.46(a)(3)(ii). The enclosure contains a summary of the
recent changes to the SQN Unit 1 ECCS evaluation model and the affect of these
changes on the calculated PCT. The changes for Unit 1 result in an absolute
calculated peak clad temperature change in excess of 50 degrees Fahrenheit from that
reported in the last annual report.
TVA submitted a license amendment request (LAR) on April 14, 2008, for reanalysis of
the large break loss-of-coolant accident to support the spring 2009 Unit 1 refueling
outage. The amendment was approved on September 24, 2008.
There are no regulatory commitments in this letter. Please direct questions concerning
this issue to me at (423) 843-7170.
Sincerely, Original signed by James D. Smith
Manager, Site Licensing and
Industry Affairs
U.S. Nuclear Regulatory Commission
Page 2 October 29, 2008
cc (Enclosure):
Mr. Brendan T. Moroney, Senior Project Manager
U.S. Nuclear Regulatory Commission
Mail Stop 08G-9a
One White Flint North
11555 Rockville Pike
Rockville, Maryland 20852-2739
E1 ENCLOSURE TENNESSEE VALLEY AUTHORITY (TVA)
SEQUOYAH NUCLEAR PLANT (SQN)
UNIT 1 10 CFR 50.46 SPECIAL REPORT OF SIGNIFICANT CHANGES In accordance with the reporting requirements of 10 CFR 50.46 (a)(3)(ii), the following is a
summary of the limiting design basis accident (loss-of-coolant accident) analysis results
established using the current SQN emergency core cooling system (ECCS) evaluation model.
Large Break Loss-of-Coolant Accident (LB LOCA)
PCT Previous Licensing Basis peak cladding temperature (PCT) 2197°F
- 1. Reanalysis using AREVA realistic - 388°F analysis methodology Updated Licensing Basis PCT 1809°F
Net Change -388°F
The LB LOCA for SQN Unit 1 has been re-analyzed using the realistic large break loss of
coolant accident (RLBLOCA) methodology described in Topical Report No. EMF-2103, Revision
00, "Realistic Large Break LOCA Methodology for Pressurized Water Reactors." The realistic
analysis methodology replaces the deterministic methodology used in the previous LB LOCA analysis of record (i.e., the methodology described in Topical Report No. BAW-10168P-A, "B&W
Loss of Coolant Accident Evaluation Model for Recirculating Steam Generator Plants"). The
SQN Unit 1 plant specific analysis is detailed in Topical Report No. ANP-2695(P), Revision 00, "Sequoyah Unit 1 Realistic Large Break Loss-of-Coolant Accident Analysis." This report was
submitted to NRC as part of SQN Technical Specification Change TS-08-01. The plant-specific
application analysis was found to be acceptable as discussed in the NRC Safety Evaluation
Report dated September 24, 2008.
Results The results of the SQN Unit 1 LB LOCA are summarized in Section 3.5 of Topical Report
No. ANP-2695(P), Revision 00. The analysis meets the 10 CFR 50.46 acceptance criteria. The
limiting calculated fuel cladding temperature was determined to be 1809 degrees Fahrenheit (F). This result represents a net reduction in the calculated peak clad temperature from the
previous analysis of record of 388 degrees F.