Letter Sequence Supplement |
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TAC:MD2621, Allowed Outage Time - Ultimate Heat Sink (Approved, Closed) TAC:MD2622, Allowed Outage Time - Ultimate Heat Sink (Approved, Closed) |
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MONTHYEARML0631304422006-11-22022 November 2006 RAI, Technical Specification Change Request for Ultimate Heat Sink Project stage: RAI ML0634700292006-12-0707 December 2006 Technical Specifications (TS) Change 06-03 Ultimate Heat Sink (UHS) Temperature Increase and Elevation Changes Supplemental Information Project stage: Supplement ML0705301432007-01-26026 January 2007 Units 1 and 2 - Response to Request for Additional Information (RAI) for Technical Specifications (TS) Change 06-03 Project stage: Response to RAI ML0711601902007-04-26026 April 2007 Memo for Thomas H. Boyce - Staff Hydrologic Technical Evaluation Report for the Sequoyah Nuclear Plant, Units 1 & 2- Technical Specification Change Request for Ultimate Heat Sink Temperature (Tac No. MD2621) Project stage: Other ML0713502462007-05-0808 May 2007 Technical Specifications Change 06-03 Ultimate Heat Sink Temperature Increase and Elevation Changes - Supplemental Information No. 2. Project stage: Supplement ML0718305852007-07-0505 July 2007 Request for Additional Information Regarding Ultimate Heat Sink Project stage: RAI ML0720103892007-07-20020 July 2007 Technical Specifications (TS) Change 06-03 Ultimate Heat Sink (UHS) Temperature Increase and Elevation Changes - Request for Information (RAI) No. 2 Extension Project stage: Request ML0722903262007-08-14014 August 2007 Technical Specifications (TS) Change 06-03 Ultimate Heat Sink (UHS) Temperature Increase and Elevation Changes - Request for Information (RAI) No. 2 (TAC Nos. MD2621 & MD2622) Project stage: Request ML0723602942007-08-22022 August 2007 Units 1 and 2 - Technical Specifications (TS) Change 06-03 Ultimate Heat Sink (UHS) Temperature Increase and Elevation Changes - Request for Information (RAI) No. 2 Supplement. Project stage: Supplement ML0727003212007-09-27027 September 2007 Memo: Temperature Issue for the Sequoyah Nuclear Plant, Units 1 & 2 - Technical Specification Change Request for Ultimate Heat Sink Temperature Increase and Elevation Changes Project stage: Other ML0724200432007-09-28028 September 2007 License Amendment, Increased Temperature and Level Limits of Ultimate Heat Sink Project stage: Acceptance Review ML0727404672007-09-28028 September 2007 Technical Specifications, Increased Temperature and Level Limits of Ultimate Heat Sink Project stage: Other ML0733807402007-12-10010 December 2007 Corrected Pages to Safety Evaluation for Amendments Regarding Increased Temperature and Level Limits of Ultimate Heat Sink (TAC Nos. MD2621 and MD2622) Project stage: Approval 2007-05-08
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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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Text
Tennessee Valley Authority, Post Office Box 2000, Soddy-Daisy, Tennessee 37384-2000 August 22, 2007 TVA-SQN-TS-06-03 10 CFR 50.90 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 ) 50-328 SEQUOYAH NUCLEAR PLANT (SQN) - UNITS 1 AND 2 - TECHNICAL SPECIFICATIONS (TS) CHANGE 06-03 "ULTIMATE HEAT SINK (UHS)
TEMPERATURE INCREASE AND ELEVATION CHANGES - REQUEST FOR INFORMATION (RAI) NO. 2 SUPPLEMENT" (TAC NOS. MD2621 &
MD2622)
References:
- 1. TVA letter to NRC dated, July, 12, 2006, "Sequoyah Nuclear Plant (SQN) - Units 1 and 2 - Technical Specifications (TS) Change 06-03 'Ultimate Heat Sink (UHS) Temperature Increase and Elevation Changes'"
- 2. TVA letter to NRC dated, December 7, 2006, "Sequoyah Nuclear Plant (SQN) - Units 1 and 2 - Technical Specifications (TS) Change 06-03 'Ultimate Heat Sink (UHS) Temperature Increase and Elevation Changes Supplemental Information' (TAC Nos. MD2621 and MD2622)"
- 3. NRC letter to TVA dated November 22, 2006, "Sequoyah Nuclear Plant, Units 1 and 2 -
Request for Additional Information Regarding Technical Specification Change Request for Ultimate Heat Sink Temperature (TAC Nos. MD2621 and MD2622)"
Printed on recycled paper
U.S. Nuclear Regulatory Commission Page 2 August 22, 2007
- 4. TVA letter to NRC dated January 26, 2007, "Sequoyah Nuclear Plant, Units 1 and 2 -
Response to Request for Additional Information (RAI) for Technical Specifications (TS) Change 06-03 (TAC Nos.
MD2621 and MD2622)"
- 5. TVA letter to NRC dated May 8, 2007, "Sequoyah Nuclear Plant, Units 1 and 2 -
Technical Specifications (TS) Change 06-03
'Ultimate Heat Sink (UHS) Temperature Increase and Elevation Changes -
Supplemental Information No. 2' (TAC Nos.
MD2621 and MD2622)"
- 6. NRC letter to TVA dated July 5, 2007, "Sequoyah Nuclear Plant, Units 1 and 2 -
Request Regarding Ultimate Heat Sink (TAC Nos. MD2621 and MD2622)"
- 7. TVA letter to NRC dated July 20, 2007, "Sequoyah Nuclear Plant, Units 1 and 2 -
Technical Specifications (TS) Change 06-03
'Ultimate Heat Sink (UHS) Temperature Increase and Elevation Changes - Request for Information (RAI) No. 2 Extension' (TAC Nos. MD2621 and MD2622)"
- 8. TVA letter to NRC dated August 20, 2007, "Sequoyah Nuclear Plant, Units 1 and 2 -
Technical Specifications (TS) Change 06-03
!Ultimate Heat Sink (UHS) Temperature Increase and Elevation Changes - Request for Information (RAI) No. 2' (TAC Nos.
MD2621 and MD2622)"
Pursuant to 10 CFR 50.90, Tennessee Valley Authority (TVA) submitted a request for a TS change to Licenses DPR-77 and DPR-79 for SQN Units 1 and 2 by Reference 1. Additional information was requested and/or provided by References 2, 3, 4, 5, 6, 7, and 8. NRC reviewed the TVA response under Reference 8 and the SQN NRC Project Manager requested clarification of the auxiliary building shutdown boardroom chiller unit operating parameter at the proposed UHS temperature limit. This letter provides the clarification.
U.S. Nuclear Regulatory Commission Page 3 August 22, 2007 The clarification does not change the "No Significant Hazards Considerations" associated with the proposed change in Reference 1.
TVA requests that NRC extend the implementation date of the approved TS to be within 90 days of NRC approval.
Additionally, in accordance with 10 CFR 50.91(b) (1), TVA is sending a copy of this letter and enclosures to the Tennessee State Department of Public Health.
If you have any questions about this change, please contact me at (423) 843-7170.
I declare under penalty of perjury that the foregoing is true and correct. Executed on this 22nd day of August, 2007.
Sincerely, James ýW. Proffit Acting Licensing Supervisor
Enclosure:
TVA's Clarifying Information Enclosure 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 Mr. Lawrence E. Nanney, Director Division of Radiological Health Third Floor L&C Annex 401 Church Street Nashville, Tennessee 37243-1532
ENCLOSURE TENNESSEE VALLEY AUTHORITY (TVA)
SEQUOYAH NUCLEAR PLANT (SQN)
UNITS 1 AND 2 TVA's Clarifying Information NRC Question:
The auxiliary building (AB) shutdown boardroom (SDBR) open chiller package data sheet, provided in response to Question 19 of the August 14, 2007, submittal, lists an operational point of 85 degrees Fahrenheit (*F). Has this chiller package been evaluated at the proposed ultimate heat sink (UHS) temperature to provide the necessary heat removal for the worst-case condition?
TVA Response:
The TVA supplemental response to Question No. 3, dated December 7, 2006, indicated that the SDBR chillers (i.e., SDBR condensers) required additional evaluation as a result of the criteria set for identifying equipment with less than sufficient essential raw cooling water (ERCW) flow margin (i.e., sufficient cooling). It was noted in Table 8 Extract that the SDBR condensers would adequately operate at an ERCW flow rate of 330 gallons per minute (gpm) at less than 91*F. TVA has reviewed additional information in regards to the vendor data and worst heat load event for the main control room (MCR) condensing unit, the electric boardroom (EBR) condensing unit, and the SDBR condenser, provided in the August 14, 2007, request for information submittal. The information provided below, shows that the equipment can provide the necessary heat removal at the proposed UHS temperature.
Design Condensing Condensing TVA Lowest Cooling Tons Basis Temperature Temp. less Required Available available vs.
LOCA Heat (°F) ERCW Entering Design LOCA required at Load Temp. ( 0F) Flow @ Flow 870 F (BTU/hr) 87 0 F (gpm)
- MCR 829,326 110 110 - 87 = 23 95.4 129.5 117 Condenser 69 EBR 1,120,934 105 105 - 87 = 18 163.9 188.6 127 Condenser 1 1 93 SDBR 2,307,090 105 105 - 87 = 18 380" 374.3 219 Condenser 192
- Values include 5 percent flow reduction for measurement uncertainty.
4 Minimum flow to the SDBR chiller will be increased to at least 380 gpm by re-balancing a portion of the ERCW system before implementing the TS change to retain the existing margins.
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