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| | number = ML083030544 | | | number = ML083030544 |
| | issue date = 10/29/2008 | | | issue date = 10/29/2008 |
| | title = 10 CFR 50.46 -30-Day Special Report of Significant Changes | | | title = CFR 50.46 -30-Day Special Report of Significant Changes |
| | author name = Smith J D | | | author name = Smith J D |
| | author affiliation = Tennessee Valley Authority | | | author affiliation = Tennessee Valley Authority |
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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
[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.