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| | number = ML063130442 | | | number = ML063130442 |
| | issue date = 11/22/2006 | | | issue date = 11/22/2006 |
| | title = Sequoyah, RAI, Technical Specification Change Request for Ultimate Heat Sink | | | title = RAI, Technical Specification Change Request for Ultimate Heat Sink |
| | author name = Pickett D V | | | author name = Pickett D |
| | author affiliation = NRC/NRR/ADRO/DORL/LPLII-2 | | | author affiliation = NRC/NRR/ADRO/DORL/LPLII-2 |
| | addressee name = Singer K W | | | addressee name = Singer K |
| | addressee affiliation = Tennessee Valley Authority | | | addressee affiliation = Tennessee Valley Authority |
| | docket = 05000327, 05000328 | | | docket = 05000327, 05000328 |
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| =Text= | | =Text= |
| {{#Wiki_filter:November 22, 2006Mr. Karl W. SingerChief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 | | {{#Wiki_filter:November 22, 2006 Mr. Karl W. Singer Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 - REQUEST FORADDITIONAL INFORMATION REGARDING TECHNICAL SPECIFICATION CHANGE REQUEST FOR ULTIMATE HEAT SINK TEMPERATURE (TAC NOS. MD2621 AND MD2622) | | 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) |
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| ==Dear Mr. Singer:== | | ==Dear Mr. Singer:== |
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| By letter dated July 12, 2006, the Tennessee Valley Authority (TVA, the licensee) submittedTechnical Specification Change Request, Section 3.7.9.1, "Ultimate Heat Sink (UHS) | | By letter dated July 12, 2006, the Tennessee Valley Authority (TVA, the licensee) submitted Technical Specification Change Request, Section 3.7.9.1, Ultimate Heat Sink (UHS) |
| Temperature Increase and Elevation Changes," for Sequoyah Nuclear Plant, Units 1 and 2. | | Temperature Increase and Elevation Changes, for Sequoyah Nuclear Plant, Units 1 and 2. |
| This revision will change the minimum UHS water elevation in Section 3.7.5.a from 670 feet to 674 feet. The essential raw cooling water temperature requirement in Section 3.7.5b will be increased from 83 degrees Fahrenheit (°F) to 87 °F.In order for the staff to complete its review of the information provided by the licensee, werequest that TVA provide responses to the enclosed request for additional information (RAI). | | This revision will change the minimum UHS water elevation in Section 3.7.5.a from 670 feet to 674 feet. The essential raw cooling water temperature requirement in Section 3.7.5b will be increased from 83 degrees Fahrenheit (°F) to 87 °F. |
| Based on discussions with your staff, we understand that you plan to respond to the enclosed RAI within 60 days of receipt of this letter. If you have any questions about this material, please contact me at (301) 415-1364.Sincerely,/RA/Douglas V. Pickett, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-327 & 50-328 | | In order for the staff to complete its review of the information provided by the licensee, we request that TVA provide responses to the enclosed request for additional information (RAI). |
| | Based on discussions with your staff, we understand that you plan to respond to the enclosed RAI within 60 days of receipt of this letter. If you have any questions about this material, please contact me at (301) 415-1364. |
| | Sincerely, |
| | /RA/ |
| | Douglas V. Pickett, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-327 & 50-328 |
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| ==Enclosure:== | | ==Enclosure:== |
| Request for Additional Informationcc: See next page
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| ML063130442NRR-088OFFICELPLI2-2LPL2-2/PMLPL2-2/LAEGCB/BCLPL2-2/BC (A)NAMEJPaigeDPickettRSolaRKaras assigned onDPickett (A)LOlshan forDATE11/ 20 /06 11/ 21 /06 11 / 20 /06 10 / 30 /06 / 11/22 /06
| | Request for Additional Information cc: See next page |
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| EnclosureREQUEST FOR ADDITIONAL INFORMATIONSEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2, TECHNICAL SPECIFICATION CHANGE REQUEST FOR ULTIMATE HEAT SINK TEMPERATURE DOCKET NOS. 50-327 AND 50-3281.While the applicant assumed a Chickamauga earthdam breach width of 400 feet whichis about 5 times dam height as suggested by the U.S. Bureau of Reclamation (1998), arecent study by Wahl (2004; "Uncertainty of Predictions of Embankment Dam BreachParameters," ASCE J. of Hydraulic Engr. V.130, No. 5) argued that the uncertainties in breach width estimates are widely recognized to be large. For large storage dams, breach width is a function of both breach height and reservoir storage volume.
| | ML063130442 NRR-088 OFFICE LPLI2-2 LPL2-2/PM LPL2-2/LA EGCB/BC LPL2-2/BC (A) |
| Therefore, the applicant should consider both breach width and storage volume in estimating breach width. It is expected that the licensee's estimate of breach width will consider reasonable assurance for protection of ultimate heat sink (UHS) volume and intake head.2.Please clarify that there is enough margin to ensure the provision of "at least 4 hours ofriver level above 670 feet following a loss of downstream dam" considering the uncertainty in the reservoir recession (drawdown) curves (Graph on Page E1-15) caused by the uncertainty in estimating breach width.3.Please revise the recession curves in Page E1-15 by taking into account the backwatereffect at the Sequoyah Nuclear Plant emergency raw cooling water intake site, which is located about 14 miles upstream of Chickamauga Dam.4.For the staff to perform its confirmatory analysis, please provide input, output, andsource code of the simulated open channel hydraulics model used to construct the tailwater rating curve at the Chickamauga Dam site.5.While the initial pool level of the Chickamauga reservoir is very sensitive to the rate ofreservoir recession, the applicant should justify the use of an initial pool level of 680 feet in simulating reservoir recession curves. Or, please explain why one of driest/wettest water levels should not be used as an initial condition to be conservative.6.Page 4 in reference #8 of Enclosure 1 states that "the reservoir levels are lower at othertimes of the year, but the ultimate heat sink limit is not approached during this time," | | NAME JPaige DPickett RSola RKaras as DPickett (A)LOlshan for signed on DATE 11/ 20 /06 11/ 21 /06 11 / 20 /06 10 / 30 /06 / 11/22 /06 REQUEST FOR ADDITIONAL INFORMATION SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2, TECHNICAL SPECIFICATION CHANGE REQUEST FOR ULTIMATE HEAT SINK TEMPERATURE DOCKET NOS. 50-327 AND 50-328 |
| which is from December to March. The applicant should verify this statement based on historical water temperatures, water levels, and recorded UHS shutdowns.7.Please clarify the condition of simulation for the recession curve in Page 18 ofReference #8. | | : 1. While the applicant assumed a Chickamauga earthdam breach width of 400 feet which is about 5 times dam height as suggested by the U.S. Bureau of Reclamation (1998), a recent study by Wahl (2004; "Uncertainty of Predictions of Embankment Dam Breach Parameters," ASCE J. of Hydraulic Engr. V.130, No. 5) argued that the uncertainties in breach width estimates are widely recognized to be large. For large storage dams, breach width is a function of both breach height and reservoir storage volume. |
| Mr. Karl W. SingerSEQUOYAH NUCLEAR PLANTTennessee Valley Authority cc: Mr. Ashok S. Bhatnagar, Senior Vice President Nuclear Operations Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Larry S. Bryant, Vice PresidentNuclear Engineering & Technical Services Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801Mr. Robert J. Beecken, Vice PresidentNuclear Support Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Randy DouetSite Vice President Sequoyah Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Soddy Daisy, TN 37384-2000General CounselTennessee Valley Authority ET 11A 400 West Summit Hill Drive Knoxville, TN 37902Mr. John C. Fornicola, ManagerNuclear Assurance and Licensing Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801Mr. Glenn W. Morris, Manager Corporate Nuclear Licensing and Industry Affairs Tennessee Valley Authority 4X Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801Mr. Paul L. Pace, ManagerLicensing and Industry Affairs ATTN: Mr. James D. Smith Sequoyah Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Soddy Daisy, TN 37384-2000Mr. David A. Kulisek, Plant ManagerSequoyah Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Soddy Daisy, TN 37384-2000Senior Resident InspectorSequoyah Nuclear Plant U.S. Nuclear Regulatory Commission 2600 Igou Ferry Road Soddy Daisy, TN 37379Mr. Lawrence E. Nanney, DirectorDivision of Radiological Health Dept. of Environment & Conservation Third Floor, L and C Annex 401 Church Street Nashville, TN 37243-1532County MayorHamilton County Courthouse Chattanooga, TN 37402-2801Ms. Ann P. Harris341 Swing Loop Road Rockwood, Tennessee 37854}} | | Therefore, the applicant should consider both breach width and storage volume in estimating breach width. It is expected that the licensees estimate of breach width will consider reasonable assurance for protection of ultimate heat sink (UHS) volume and intake head. |
| | : 2. Please clarify that there is enough margin to ensure the provision of at least 4 hours of river level above 670 feet following a loss of downstream dam considering the uncertainty in the reservoir recession (drawdown) curves (Graph on Page E1-15) caused by the uncertainty in estimating breach width. |
| | : 3. Please revise the recession curves in Page E1-15 by taking into account the backwater effect at the Sequoyah Nuclear Plant emergency raw cooling water intake site, which is located about 14 miles upstream of Chickamauga Dam. |
| | : 4. For the staff to perform its confirmatory analysis, please provide input, output, and source code of the simulated open channel hydraulics model used to construct the tailwater rating curve at the Chickamauga Dam site. |
| | : 5. While the initial pool level of the Chickamauga reservoir is very sensitive to the rate of reservoir recession, the applicant should justify the use of an initial pool level of 680 feet in simulating reservoir recession curves. Or, please explain why one of driest/wettest water levels should not be used as an initial condition to be conservative. |
| | : 6. Page 4 in reference #8 of Enclosure 1 states that the reservoir levels are lower at other times of the year, but the ultimate heat sink limit is not approached during this time, which is from December to March. The applicant should verify this statement based on historical water temperatures, water levels, and recorded UHS shutdowns. |
| | : 7. Please clarify the condition of simulation for the recession curve in Page 18 of Reference #8. |
| | Enclosure |
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| | Mr. Karl W. Singer SEQUOYAH NUCLEAR PLANT Tennessee Valley Authority cc: |
| | Mr. Ashok S. Bhatnagar, Senior Vice President Mr. Glenn W. Morris, Manager Nuclear Operations Corporate Nuclear Licensing Tennessee Valley Authority and Industry Affairs 6A Lookout Place Tennessee Valley Authority 1101 Market Street 4X Blue Ridge Chattanooga, TN 37402-2801 1101 Market Street Chattanooga, TN 37402-2801 Mr. Larry S. Bryant, Vice President Nuclear Engineering & Technical Services Mr. Paul L. Pace, Manager Tennessee Valley Authority Licensing and Industry Affairs 6A Lookout Place ATTN: Mr. James D. Smith 1101 Market Street Sequoyah Nuclear Plant Chattanooga, TN 37402-2801 Tennessee Valley Authority P.O. Box 2000 Mr. Robert J. Beecken, Vice President Soddy Daisy, TN 37384-2000 Nuclear Support Tennessee Valley Authority Mr. David A. Kulisek, Plant Manager 6A Lookout Place Sequoyah Nuclear Plant 1101 Market Street Tennessee Valley Authority Chattanooga, TN 37402-2801 P.O. Box 2000 Soddy Daisy, TN 37384-2000 Mr. Randy Douet Site Vice President Senior Resident Inspector Sequoyah Nuclear Plant Sequoyah Nuclear Plant Tennessee Valley Authority U.S. Nuclear Regulatory Commission P.O. Box 2000 2600 Igou Ferry Road Soddy Daisy, TN 37384-2000 Soddy Daisy, TN 37379 General Counsel Mr. Lawrence E. Nanney, Director Tennessee Valley Authority Division of Radiological Health ET 11A Dept. of Environment & Conservation 400 West Summit Hill Drive Third Floor, L and C Annex Knoxville, TN 37902 401 Church Street Nashville, TN 37243-1532 Mr. John C. Fornicola, Manager Nuclear Assurance and Licensing County Mayor Tennessee Valley Authority Hamilton County Courthouse 6A Lookout Place Chattanooga, TN 37402-2801 1101 Market Street Chattanooga, TN 37402-2801 Ms. Ann P. Harris 341 Swing Loop Road Rockwood, Tennessee 37854}} |
Letter Sequence RAI |
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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
MONTHYEARCNL-24-021, Application to Revise Technical Specification Limiting Condition of Operation 3.5.2, ECCS – Operating, Note 1 to Include Residual Heat Removal Pump Flow Paths (SQN-TS-23-04 and WBN-TS-23-020)2024-11-12012 November 2024 Application to Revise Technical Specification Limiting Condition of Operation 3.5.2, ECCS – Operating, Note 1 to Include Residual Heat Removal Pump Flow Paths (SQN-TS-23-04 and WBN-TS-23-020) ML24312A1552024-11-0606 November 2024 Cycle 27 Core Operating Limits Report, Revision 1 IR 05000327/20240032024-11-0606 November 2024 Integrated Inspection Report 05000327/2024003 and 05000328/2024003 CNL-24-014, License Amendment Request to Revise the Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications to Use Online Monitoring Methodology (SQN-TS-24-02 and WBN-TS-23-22)2024-11-0404 November 2024 License Amendment Request to Revise the Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications to Use Online Monitoring Methodology (SQN-TS-24-02 and WBN-TS-23-22) ML24304A8492024-10-31031 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-24-047, 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 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 ML24144A2322024-04-20020 April 2024 Tennessee Multi-Sector Permit (Tmsp), 2024 Annual Discharge Monitoring Report for Outfalls SW-3, SW-3, and SW-9 ML24144A2362024-04-20020 April 2024 Discharge Monitoring Report (Dmr), March 2024 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-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 2024-09-08
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24309A0552024-11-0101 November 2024 NRR E-mail Capture - Request for Additional Information - TVA LAR to Revised Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2 Re TS Table 3.3.2-1, Function 5 ML24152A1542024-05-31031 May 2024 Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2024-03 ML24116A2012024-04-17017 April 2024 Nrctva ISFSI CBS (RFI) ML24045A1002024-02-13013 February 2024 NRR E-mail Capture - Request for Additional Information Related to the Sequoyah Exemption Request for the 10 CFR Part 73 Enhanced Weapons Rule ML23307A0832023-11-0808 November 2023 Enclosure - Request for Additional Information HDI-Sequoyah NDE Exemption Request 10-30-2023 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 ML23062A5942023-02-27027 February 2023 Enclosure - NRC SQN Exemption Rsi Response Staff Follow Up Questions ML23062A5952023-02-27027 February 2023 Staff follow-up Questions to TVAs 12/19/2022 Response of the Staffs Rsi Regarding 08/04/2022 SQN Exemption Request ML22343A0692022-12-0808 December 2022 NRR E-mail Capture - Request for Additional Information - Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.4.12 (L-2022-LLA-0103) ML22257A0622022-09-14014 September 2022 Requalification Program Inspection - Sequoyah Nuclear Plant ML22255A0842022-09-0909 September 2022 Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2022-04 ML22227A0272022-08-11011 August 2022 NRR E-mail Capture - Request for Additional Information Related to Alternative Requests RP-11 for Sequoyah Nuclear Plant, Units 1 and 2, and IST-RR-9 for Watts Bar Nuclear Plant, Units 1 and 2 ML22214A1582022-08-0202 August 2022 NRR E-mail Capture - Request for Additional Information for Sequoyah Units 1 and 2 License Amendment Request for Fire and Seismic PRA Modification to 10 CFR 50.69 (L-2022-LLA-0033) ML22151A0102022-05-27027 May 2022 NRR E-mail Capture - Revised Request for Additional Information Re Sequoyah Nuclear Plant Alternative Request RV-02 ML22151A0092022-05-26026 May 2022 NRR E-mail Capture - Request for Additional Information Re Sequoyah Nuclear Plant Alternative Request RV-02 ML22146A3322022-05-26026 May 2022 NRR E-mail Capture - Request for Additional Information Related to Sequoyah Nuclear Plants LAR to Adopt TSTF-505 ML22144A1002022-05-12012 May 2022 NRR E-mail Capture - Request for Additional Information Related to TVAs Request to Revised the TVA Plants Radiological Emergency Plans ML21237A4952021-08-25025 August 2021 Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2021-04 ML21160A0352021-06-0303 June 2021 Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2021-03 ML21095A0482021-04-0505 April 2021 NRR E-mail Capture - Sequoyah Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding Request to Transition to Westinghouse Fuel ML21092A0972021-04-0202 April 2021 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML20259A4782020-09-15015 September 2020 Emergency Preparedness Program Inspection Request for Information ML20261H4172020-09-14014 September 2020 NRR E-mail Capture - Sequoyah Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding Hydrologic UFSAR Update ML20261H4162020-09-0202 September 2020 NRR E-mail Capture - Draft Request for Additional Information - Sequoyah Nuclear Plant, Units 1 and 2, Request to Revise UFSAR Hydrologic Analysis ML20189A2112020-07-0101 July 2020 Request for Additional Information Regarding Hydrologic UFSAR Update ML20106F1042020-04-14014 April 2020 Request for Additional Information Regarding the Hydrologic Analysis LAR ML20161A3902020-04-0909 April 2020 Request for Supporting Information for the Sequoyah SPRA Audit Review - Follow-up to Plant Response Question 5 ML20098D8612020-04-0707 April 2020 Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000327/2020012 and 05000328/2020012) and Request for Information) ML20036E2842020-02-0505 February 2020 20200123 - Sequoyah Radiation Safety Inspection Document Request Letter ML19323D7562019-11-18018 November 2019 Nrc'S Request for Additional Information - Exigent Amendment ML19235A0992019-08-22022 August 2019 Emergency Preparedness Program Inspection Request for Information ML19162A2462019-06-11011 June 2019 RP Inspection Document Request 2019-03 ML19149A6222019-05-29029 May 2019 NRR E-mail Capture - Request for Additional Information - Sequoyah Nuclear Plant, Units 1 and 2, Request for Alternative to 18-ISI-1 EPID: L-2019-LLR-0006 ML19148A7912019-05-28028 May 2019 NRR E-mail Capture - Sequoyah Nuclear Plant and Watts Bar Nuclear Plant - Final Request for Additional Information Related to Request for Alternative to OM Code Requirements ML19015A4192019-01-15015 January 2019 NRR E-mail Capture - RAI - Sequoyah Nuclear Plant, Units 1 and 2, LAR to Adopt 10 CFR50.69 Risk-informed SSC ML18344A0752018-12-10010 December 2018 NRR E-mail Capture - Request for Additional Information - Sequoyah 1 and 2, Request to Modify Essential Raw Cooling Water Motor Control Center Breakers and to Revise Updated Final Analysis Report (SQN-TS-17-04) ML18296A0022018-10-22022 October 2018 NRR E-mail Capture - Additional Information Needs - Sequoyah Units 1 and 2, Request to Modify Essential Raw Cooling Water Motor Control Center Breakers Revise Updated Final Analysis Report (SQN-TS-17-04) ML18283B0592018-10-10010 October 2018 NRR E-mail Capture - Additional Information Needs Identified During Audit - Sequoyah 1 and 2, Request to Modify Essential Raw Cooling Water Motor Control Center Breakers Revise Updated Final Analysis Report (SQN-TS-17-04) ML18283A6232018-09-25025 September 2018 04 RP Inspection Document Request ML18233A1942018-08-21021 August 2018 NRR E-mail Capture - Additional Information Needs Identified - Sequoyah 1 and 2, Request to Modify Essential Raw Cooling Water Motor Control Center Breakers and to Revise Updated Final Analysis Report (SQN-TS-17-04) ML18138A1102018-05-17017 May 2018 Enclosurequest for Additional Information (Letter to E. D. Schrull Request for Additional Information Regarding Tennessee Valley Authority'S Decommissioning Funding Plan Update for Browns Ferry and Sequoyah Isfsis) ML18057A6372018-02-23023 February 2018 NRR E-mail Capture - Request for Additional Information Related to TVA Fleet Topical Report TVA-NPG-AWA16 - EPIC: L-2016-TOP-0011) ML17191A2062017-07-0606 July 2017 NRR E-mail Capture - Sequoyah Nuclear Station, Unit 1 & 2 - Request for Additional Information Related to LAR for Technical Specification 3.8.1.17 Note Modification (CAC Nos. MF9398 and MF9399) ML17150A0792017-05-23023 May 2017 NRR E-mail Capture - Request for Additional Information Related to TVA Fleet LAR for EAL Change to Adopt NEI-99-01 Rev.6 (CAC Nos. MF9054 - MF9060) ML17112A0402017-04-20020 April 2017 NRR E-mail Capture - Sequoyah Nuclear Station, Unit 1 & 2 - Request for Additional Information Related to LAR for Technical Specification 3.8.1, AC SOURCES-OPERATING ML17004A0612017-01-0404 January 2017 Notification of NRC Triennial Fire Protection Inspection (Team)(Report 05000327/2017007 and 05000328/2017007) ML15194A3882015-07-13013 July 2015 Request for Additional Information Related to LAR to Revise Ice Condenser Ice Mas Tech Spec ML15175A2912015-06-24024 June 2015 E-mail Re. Request for Additional Information RR RP-07 ML15159B1642015-06-22022 June 2015 Requests for Additional Information for the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application-Set 25 (TAC Nos. MF0481 and MF0482) ML15050A0962015-02-19019 February 2015 E-mail Re. Request for Additional Information Related to LAR to Ice Condendser Inc Mass Tech Spec 2024-05-31
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November 22, 2006 Mr. Karl W. Singer Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT:
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)
Dear Mr. Singer:
By letter dated July 12, 2006, the Tennessee Valley Authority (TVA, the licensee) submitted Technical Specification Change Request, Section 3.7.9.1, Ultimate Heat Sink (UHS)
Temperature Increase and Elevation Changes, for Sequoyah Nuclear Plant, Units 1 and 2.
This revision will change the minimum UHS water elevation in Section 3.7.5.a from 670 feet to 674 feet. The essential raw cooling water temperature requirement in Section 3.7.5b will be increased from 83 degrees Fahrenheit (°F) to 87 °F.
In order for the staff to complete its review of the information provided by the licensee, we request that TVA provide responses to the enclosed request for additional information (RAI).
Based on discussions with your staff, we understand that you plan to respond to the enclosed RAI within 60 days of receipt of this letter. If you have any questions about this material, please contact me at (301) 415-1364.
Sincerely,
/RA/
Douglas V. Pickett, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-327 & 50-328
Enclosure:
Request for Additional Information cc: See next page
ML063130442 NRR-088 OFFICE LPLI2-2 LPL2-2/PM LPL2-2/LA EGCB/BC LPL2-2/BC (A)
NAME JPaige DPickett RSola RKaras as DPickett (A)LOlshan for signed on DATE 11/ 20 /06 11/ 21 /06 11 / 20 /06 10 / 30 /06 / 11/22 /06 REQUEST FOR ADDITIONAL INFORMATION SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2, TECHNICAL SPECIFICATION CHANGE REQUEST FOR ULTIMATE HEAT SINK TEMPERATURE DOCKET NOS. 50-327 AND 50-328
- 1. While the applicant assumed a Chickamauga earthdam breach width of 400 feet which is about 5 times dam height as suggested by the U.S. Bureau of Reclamation (1998), a recent study by Wahl (2004; "Uncertainty of Predictions of Embankment Dam Breach Parameters," ASCE J. of Hydraulic Engr. V.130, No. 5) argued that the uncertainties in breach width estimates are widely recognized to be large. For large storage dams, breach width is a function of both breach height and reservoir storage volume.
Therefore, the applicant should consider both breach width and storage volume in estimating breach width. It is expected that the licensees estimate of breach width will consider reasonable assurance for protection of ultimate heat sink (UHS) volume and intake head.
- 2. Please clarify that there is enough margin to ensure the provision of at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of river level above 670 feet following a loss of downstream dam considering the uncertainty in the reservoir recession (drawdown) curves (Graph on Page E1-15) caused by the uncertainty in estimating breach width.
- 3. Please revise the recession curves in Page E1-15 by taking into account the backwater effect at the Sequoyah Nuclear Plant emergency raw cooling water intake site, which is located about 14 miles upstream of Chickamauga Dam.
- 4. For the staff to perform its confirmatory analysis, please provide input, output, and source code of the simulated open channel hydraulics model used to construct the tailwater rating curve at the Chickamauga Dam site.
- 5. While the initial pool level of the Chickamauga reservoir is very sensitive to the rate of reservoir recession, the applicant should justify the use of an initial pool level of 680 feet in simulating reservoir recession curves. Or, please explain why one of driest/wettest water levels should not be used as an initial condition to be conservative.
- 6. Page 4 in reference #8 of Enclosure 1 states that the reservoir levels are lower at other times of the year, but the ultimate heat sink limit is not approached during this time, which is from December to March. The applicant should verify this statement based on historical water temperatures, water levels, and recorded UHS shutdowns.
- 7. Please clarify the condition of simulation for the recession curve in Page 18 of Reference #8.
Enclosure
Mr. Karl W. Singer SEQUOYAH NUCLEAR PLANT Tennessee Valley Authority cc:
Mr. Ashok S. Bhatnagar, Senior Vice President Mr. Glenn W. Morris, Manager Nuclear Operations Corporate Nuclear Licensing Tennessee Valley Authority and Industry Affairs 6A Lookout Place Tennessee Valley Authority 1101 Market Street 4X Blue Ridge Chattanooga, TN 37402-2801 1101 Market Street Chattanooga, TN 37402-2801 Mr. Larry S. Bryant, Vice President Nuclear Engineering & Technical Services Mr. Paul L. Pace, Manager Tennessee Valley Authority Licensing and Industry Affairs 6A Lookout Place ATTN: Mr. James D. Smith 1101 Market Street Sequoyah Nuclear Plant Chattanooga, TN 37402-2801 Tennessee Valley Authority P.O. Box 2000 Mr. Robert J. Beecken, Vice President Soddy Daisy, TN 37384-2000 Nuclear Support Tennessee Valley Authority Mr. David A. Kulisek, Plant Manager 6A Lookout Place Sequoyah Nuclear Plant 1101 Market Street Tennessee Valley Authority Chattanooga, TN 37402-2801 P.O. Box 2000 Soddy Daisy, TN 37384-2000 Mr. Randy Douet Site Vice President Senior Resident Inspector Sequoyah Nuclear Plant Sequoyah Nuclear Plant Tennessee Valley Authority U.S. Nuclear Regulatory Commission P.O. Box 2000 2600 Igou Ferry Road Soddy Daisy, TN 37384-2000 Soddy Daisy, TN 37379 General Counsel Mr. Lawrence E. Nanney, Director Tennessee Valley Authority Division of Radiological Health ET 11A Dept. of Environment & Conservation 400 West Summit Hill Drive Third Floor, L and C Annex Knoxville, TN 37902 401 Church Street Nashville, TN 37243-1532 Mr. John C. Fornicola, Manager Nuclear Assurance and Licensing County Mayor Tennessee Valley Authority Hamilton County Courthouse 6A Lookout Place Chattanooga, TN 37402-2801 1101 Market Street Chattanooga, TN 37402-2801 Ms. Ann P. Harris 341 Swing Loop Road Rockwood, Tennessee 37854