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
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
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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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