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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: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
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June 4, 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 Nos. 50-327 Tennessee Valley Authority (TVA) ) 50-328 SEQUOYAH NUCLEAR PLANT (SQN) - 10 CFR 50.46 DAY SPECIAL REPORT OF SIGNIFICANT CHANGES
Reference:
TVA letter to NRC dated November 14, 2007, Sequoyah Nuclear Plant (SQN) - 10 CFR 50.46 Annual Report of Non-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 submittal 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 Units 1 and 2 ECCS evaluation model and the affect of these changes on the calculated PCT. The changes result in an absolute calculated peak clad temperature change in excess of 50 degrees Fahrenheit from that reported in the last annual report.
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 June 4, 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
ENCLOSURE TENNESSEE VALLEY AUTHORITY (TVA)
SEQUOYAH NUCLEAR PLANT (SQN)
UNITS 1 AND 2 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) (LOCA) analysis results established using the current SQN emergency core cooling system (ECCS) evaluation model.
Small Break LOCA (SB LOCA)
PCT Previous Licensing Basis PCT 1162 degrees Fahrenheit (F)
(November 08, 2004)
Reanalysis for revised ECCS pump +241 degrees F performance and core power peaking analytical input assumptions.
Updated Licensing Basis PCT 1403 degrees F Net Change +241 degrees F The SQN large break LOCA (LB LOCA) has been recently analyzed using the realistic (LB LOCA) methodology described in Topical Report No. EMF-2103, Revision 00, Realistic Large Break LOCA Methodology for Pressurized Water Reactors. A number of modified analytical input parameters were incorporated into the realistic LB LOCA analysis to support improved fuel utilization and expand the operating margin for the ECCS pumps.
For consistency with the realistic large break LOCA analysis, the SQN SB LOCA analysis has recently been analyzed to apply similar changes to the SB LOCA analytical input parameters.
The analysis was performed using the same SQN plant-specific evaluation model with the same evaluation methodology (i.e., Topical Report No. BAW-10168P-A, Revision 03, BWNT Loss-of-Coolant Accident Evaluation Model for Recirculating Steam Generator Plants - Volume II - Small Break) as the current analysis of record. Specific changes to the SB LOCA analytical input parameters include 1) an increase in the core power peaking factor (Fq) from 2.5 to 2.65, 2) an increase in the hot channel enthalpy factor (fh) from 1.70 to 1.89, and 3) a 5 percent reduction in the minimum developed head values for the ECCS charging (high head) and safety injection (intermediate head) pumps.
Results The SB LOCA analysis with the revised analytical input parameters discussed above meet the 10 CFR 50.46 acceptance criteria. The limiting calculated fuel cladding temperature was determined to be 1403 degrees F for a 2.75-inch diameter break size. This result represents a net increase in the calculated peak clad temperature from the previous analysis of record of 241 degrees F.
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