|
|
(One intermediate revision by the same user not shown) |
Line 2: |
Line 2: |
| | number = ML092720772 | | | number = ML092720772 |
| | issue date = 10/02/2009 | | | issue date = 10/02/2009 |
| | title = Request for Additional Information Regarding the Upgrade of Emergency Core Cooling System Requirements Per NUREG-1431 (TAC No. ME1115 and ME1116) | | | title = Request for Additional Information Regarding the Upgrade of Emergency Core Cooling System Requirements Per NUREG-1431 |
| | author name = Lingam S | | | author name = Lingam S |
| | author affiliation = NRC/NRR/DORL/LPLII-2 | | | author affiliation = NRC/NRR/DORL/LPLII-2 |
Line 18: |
Line 18: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 October 2, 2009 Mr. Preston D. | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 2, 2009 Mr. Preston D. Swafford Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 SUB~IECT: SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING THE UPGRADE OF EMERGENCY CORE COOLING SYSTEM REQUIREMENTS PER NUREG-1431 (TAC NOS. ME1115 AND ME1116) |
| Swafford Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 - | |
| REQUEST FOR ADDITIONAL INFORMATION REGARDING THE UPGRADE OF EMERGENCY CORE COOLING SYSTEM REQUIREMENTS PER NUREG-1431 (TAC NOS. | |
| ME1115 AND ME1116) | |
|
| |
|
| ==Dear Mr. Swafford:== | | ==Dear Mr. Swafford:== |
| By letter dated April 21, 2009, and supplemented by letter dated September 8, 2009, you submitted an application for license amendment to revise the Sequoyah Nuclear Plant, Units 1 and 2 (SQN) Technical Specifications (TSs), and upgrade the Emergency Core Cooling System (ECCS) requirements to be more consistent with NUREG-1431, Revision 3, "Standard Technical Specifications | | |
| -Westinghouse Plants." The upgrade revises SQN TS Section 3/4.5.2, "ECCS Subsystems -Tav9 Greater Than or Equal to 350 "F." TS Section 3/4.5.3, "ECCS Tav9 Less Than 350 "F." and the corresponding surveillance requirements (SRs) that will resolve a nonconforming condition associated with SR 4.5.2.f. | | By letter dated April 21, 2009, and supplemented by letter dated September 8, 2009, you submitted an application for license amendment to revise the Sequoyah Nuclear Plant, Units 1 and 2 (SQN) Technical Specifications (TSs), and upgrade the Emergency Core Cooling System (ECCS) requirements to be more consistent with NUREG-1431, Revision 3, "Standard Technical Specifications - Westinghouse Plants." The upgrade revises SQN TS Section 3/4.5.2, "ECCS Subsystems - T av9 Greater Than or Equal to 350 "F." TS Section 3/4.5.3, "ECCS SUbsystems T av9 Less Than 350 "F." and the corresponding surveillance requirements (SRs) that will resolve a nonconforming condition associated with SR 4.5.2.f. |
| The Nuclear Regulatory Commission staff is reviewing the submittal and has determined that additional information is required to complete its evaluation. | | The Nuclear Regulatory Commission staff is reviewing the submittal and has determined that additional information is required to complete its evaluation. This request was discussed with Mr. Fred Mashburn of your staff on September 29, 2009, and it was agreed that a response would be provided by October 9,2009. |
| This request was discussed with Mr. Fred Mashburn of your staff on September 29, 2009, and it was agreed that a response would be provided by October 9,2009. If you have any questions regarding this matter, I can be reached at 301-415-1564. | | If you have any questions regarding this matter, I can be reached at 301-415-1564. |
| Sincerely, Siva P. Lingam, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-327 and 50-328 | | Sincerely, |
| | ~fj'~. |
| | Siva P. Lingam, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-327 and 50-328 |
|
| |
|
| ==Enclosure:== | | ==Enclosure:== |
| | Request for Additional Information cc w/encl: Distribution via Listserv |
|
| |
|
| Request for Additional Information cc w/encl:
| | REQUEST FOR ADDITIONAL INFORMATION REGARDING TECHNICAL SPECIFICATION CHANGES AND UPGRADE OF EMERGENCY CORE COOLING SYSTEM REQUIREMENTS PER NUREG-1431, REVISION 3 SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328 By letter dated April 21, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML091120193), and supplemented by letter dated September 8,2009 (ADAMS Accession No. ML092530721), the Tennessee Valley Authority (the licensee), |
| Distribution via Listserv REQUEST FOR ADDITIONAL INFORMATION REGARDING TECHNICAL SPECIFICATION CHANGES AND UPGRADE OF EMERGENCY CORE COOLING SYSTEM REQUIREMENTS PER NUREG-1431, REVISION 3 SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328 By letter dated April 21, 2009 (Agencywide Documents Access and Management (ADAMS) Accession No. ML091120193), and supplemented by letter dated September (ADAMS Accession No. ML092530721), the Tennessee Valley Authority (the submitted a license amendment request to revise the Sequoyah Nuclear Plant, Units 1 and (SQN) Technical Specifications (TSs) and upgrade the Emergency Core Cooling (ECCS) requirements to be more consistent with NUREG-1431, Revision 3, "Standard Specifications
| | submitted a license amendment request to revise the Sequoyah Nuclear Plant, Units 1 and 2 (SQN) Technical Specifications (TSs) and upgrade the Emergency Core Cooling System (ECCS) requirements to be more consistent with NUREG-1431, Revision 3, "Standard Technical Specifications - Westinghouse Plants." The upgrade revises SQN TS Section 3/4.5.2, "ECCS Subsystems - Tavg Greater Than or Equal to 350 "F," TS Section 3/4.5.3, "ECCS Subsystems T avg Less Than 350 "F," and the corresponding surveillance requirements (SRs) that will resolve a nonconforming condition associated with SR 4.5.2.f. In order to complete its review of the above documents, the Nuclear Regulatory Commission (NRC) staff needs the following additional information: |
| -Westinghouse Plants." The upgrade revises SQN TS Section 3/4.5.2, Subsystems -Tavg Greater Than or Equal to 350 "F," TS Section 3/4.5.3, "ECCS Tavg Less Than 350 "F," and the corresponding surveillance requirements (SRs) that will a nonconforming condition associated with SR 4.5.2.f. In order to complete its review of above documents, the Nuclear Regulatory Commission (NRC) staff needs the additional On page E-11 of the licensee's letter dated April 21, 2009, it is noted that new action b TS 3.5.3 is less restrictive than current requirements because it will allow an extra 3 hours the plant to be in Mode 4 when the required ECCS centrifugal charging pump is There is no technical justification provided for this extra Provide justification for the extra 3 hours for the plant to be in Mode 4 when the required ECCS centrifugal charging pump is inoperable. | | On page E-11 of the licensee's letter dated April 21, 2009, it is noted that new action b of TS 3.5.3 is less restrictive than current requirements because it will allow an extra 3 hours for the plant to be in Mode 4 when the required ECCS centrifugal charging pump is inoperable. |
| Enclosure | | There is no technical justification provided for this extra time. |
| | : 1. Provide justification for the extra 3 hours for the plant to be in Mode 4 when the required ECCS centrifugal charging pump is inoperable. |
| | Enclosure |
|
| |
|
| ML092720772 "transmitted bv memo dated OFFICE LPL2-2/PM LPL2-2/LA NRR/DIRS/ITSB/BC LPL2-2/BC NAME SLinaam CSoia RElliott TBovce DATE 10101/09 10101/09 914/09* 10102/09}} | | ML092720772 "transmitted bv memo dated OFFICE LPL2-2/PM LPL2-2/LA NRR/DIRS/ITSB/BC LPL2-2/BC NAME SLinaam CSoia RElliott TBovce DATE 10101/09 10101/09 914/09* 10102/09}} |
Letter Sequence RAI |
---|
|
|
MONTHYEARML0911201932009-04-21021 April 2009 Technical Specification Change No. 07-05, Emergency Core Cooling System (Eccs). Project stage: Other ML0920203492009-08-13013 August 2009 Request for Additional Information Regarding the Upgrade of Emergency Core Cooling System Requirements Per NUREG-1431 Project stage: RAI ML0927207722009-10-0202 October 2009 Request for Additional Information Regarding the Upgrade of Emergency Core Cooling System Requirements Per NUREG-1431 Project stage: RAI ML0929602402009-10-0909 October 2009 Response to Request for Additional Information Concerning Technical Specifications Change 07-05 - Upgrade of Emergency Core Cooling System Requirements Project stage: Response to RAI ML1002900232010-01-26026 January 2010 Correction of Errata for Technical Specifications Change 07-05 - Upgrade of Emergency Core Cooling System Requirements Project stage: Other ML0933104032010-01-28028 January 2010 Issuance of Amendments Regarding Upgrade of Emergency Core Cooling System Requirements Per NUREG-1431 (TS 07-05) Project stage: Approval ML1003607402010-02-16016 February 2010 Corrections for Amendment Nos. 326 and 319 Project stage: Other 2009-08-13
[Table View] |
|
---|
Category:Letter
MONTHYEARIR 05000327/20240022024-07-31031 July 2024 Integrated Inspection Report 05000327/2024002 and 05000328/2024002 ML24211A0542024-07-29029 July 2024 Operator License Examination Report ML24211A0572024-07-29029 July 2024 Submittal of Emergency Plan Implementing Procedure Revision 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 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 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 ML24089A0882024-04-18018 April 2024 – Exemption from Select Requirements of 10 CFR Part 73; Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting 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 ML24100A0162024-04-11011 April 2024 Request for Regulatory Conference (Tennessee Valley Authority - Sequoyah Nuclear Plant) CNL-24-020, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements2024-04-0101 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements ML24088A0332024-03-28028 March 2024 Request for Regulatory Conference (Tennessee Valley Authority) CNL-24-007, Annual Insurance Status Report2024-03-27027 March 2024 Annual Insurance Status Report CNL-24-008, Guarantee of Payment of Deferred Premiums - 2023 Annual Report2024-03-27027 March 2024 Guarantee of Payment of Deferred Premiums - 2023 Annual Report ML24040A2062024-03-26026 March 2024 Issuance of Amendment Nos. 367 and 361 Regarding Changes to the Hydrologic Analyses (EPID L-2020-LLA-0004) - Public IR 05000327/20240902024-03-19019 March 2024 NRC Inspection Report 05000327-2024090 and 05000328-2024090 and Preliminary Greater than Green Finding and Apparent Violation CNL-24-029, Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 372024-03-14014 March 2024 Response to Request for Additional Information Regarding Tennessee Valley Authority - Request for Exemption from Specific Requirements of 10 CFR Part 37 CNL-24-027, Response to Request for Additional Information Regarding Sequoyah Nuclear Plant, Units 1 and 2, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2024-03-14014 March 2024 Response to Request for Additional Information Regarding Sequoyah Nuclear Plant, Units 1 and 2, Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000327/20244012024-03-12012 March 2024 – Security Baseline Inspection Report 05000327/2024401 and 05000328/2024401 IR 05000259/20230062024-02-28028 February 2024 Annual Assessment Letter for Sequoyah Nuclear Plant, Units 1, 2 - Report 05000259/2023006, 05000260/2023006 and 05000296/2023006 ML24053A3932024-02-22022 February 2024 Final Report of a Deviation or Failure to Comply - Crompton Instruments Type 077 Ammeter CNL-24-023, Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-17, Revision 252024-02-20020 February 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-17, Revision 25 ML24046A2072024-02-15015 February 2024 Emergency Plan Implementing Procedure Revisions. Includes EPIP-6, Revision 59 and EPIP-7, Revision 38 ML24046A2372024-02-15015 February 2024 Annual Water Withdrawal Report 2023 ML24046A2362024-02-15015 February 2024 Discharge Monitoring Report (Dmr), January 2024 ML24046A0252024-02-14014 February 2024 Final Report of a Deviation or Failure to Comply Lube Oil Scavenging and Fuel Oil Engine Driven Pump IR 05000327/20230042024-02-12012 February 2024 Integrated Inspection Report 05000327/2023004 and 05000328/2023004 and Apparent Violation ML24039A0792024-02-12012 February 2024 – Summary of Regulatory Audit Regarding the License Amendment Request for Hydrologic Analysis Changes to the Updated Final Safety Analysis Report (EPID L-2020-LLA-0004) - Public ML24032A0202024-01-31031 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 2024-07-09
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24152A1542024-05-31031 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 Tva'S 12/19/2022 Response of the Staff'S 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 Plant'S LAR to Adopt TSTF-505 ML22144A1002022-05-12012 May 2022 NRR E-mail Capture - Request for Additional Information Related to Tva'S 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 ML15042A4702015-02-11011 February 2015 E-mail Re. Request for Additional Information Related to License Amendment Request to Revise Technical Specification on Ultimate Heat Sink 2024-05-31
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 2, 2009 Mr. Preston D. Swafford Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 SUB~IECT: SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING THE UPGRADE OF EMERGENCY CORE COOLING SYSTEM REQUIREMENTS PER NUREG-1431 (TAC NOS. ME1115 AND ME1116)
Dear Mr. Swafford:
By letter dated April 21, 2009, and supplemented by letter dated September 8, 2009, you submitted an application for license amendment to revise the Sequoyah Nuclear Plant, Units 1 and 2 (SQN) Technical Specifications (TSs), and upgrade the Emergency Core Cooling System (ECCS) requirements to be more consistent with NUREG-1431, Revision 3, "Standard Technical Specifications - Westinghouse Plants." The upgrade revises SQN TS Section 3/4.5.2, "ECCS Subsystems - T av9 Greater Than or Equal to 350 "F." TS Section 3/4.5.3, "ECCS SUbsystems T av9 Less Than 350 "F." and the corresponding surveillance requirements (SRs) that will resolve a nonconforming condition associated with SR 4.5.2.f.
The Nuclear Regulatory Commission staff is reviewing the submittal and has determined that additional information is required to complete its evaluation. This request was discussed with Mr. Fred Mashburn of your staff on September 29, 2009, and it was agreed that a response would be provided by October 9,2009.
If you have any questions regarding this matter, I can be reached at 301-415-1564.
Sincerely,
~fj'~.
Siva P. Lingam, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-327 and 50-328
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION REGARDING TECHNICAL SPECIFICATION CHANGES AND UPGRADE OF EMERGENCY CORE COOLING SYSTEM REQUIREMENTS PER NUREG-1431, REVISION 3 SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328 By letter dated April 21, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML091120193), and supplemented by letter dated September 8,2009 (ADAMS Accession No. ML092530721), the Tennessee Valley Authority (the licensee),
submitted a license amendment request to revise the Sequoyah Nuclear Plant, Units 1 and 2 (SQN) Technical Specifications (TSs) and upgrade the Emergency Core Cooling System (ECCS) requirements to be more consistent with NUREG-1431, Revision 3, "Standard Technical Specifications - Westinghouse Plants." The upgrade revises SQN TS Section 3/4.5.2, "ECCS Subsystems - Tavg Greater Than or Equal to 350 "F," TS Section 3/4.5.3, "ECCS Subsystems T avg Less Than 350 "F," and the corresponding surveillance requirements (SRs) that will resolve a nonconforming condition associated with SR 4.5.2.f. In order to complete its review of the above documents, the Nuclear Regulatory Commission (NRC) staff needs the following additional information:
On page E-11 of the licensee's letter dated April 21, 2009, it is noted that new action b of TS 3.5.3 is less restrictive than current requirements because it will allow an extra 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> for the plant to be in Mode 4 when the required ECCS centrifugal charging pump is inoperable.
There is no technical justification provided for this extra time.
- 1. Provide justification for the extra 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> for the plant to be in Mode 4 when the required ECCS centrifugal charging pump is inoperable.
Enclosure
ML092720772 "transmitted bv memo dated OFFICE LPL2-2/PM LPL2-2/LA NRR/DIRS/ITSB/BC LPL2-2/BC NAME SLinaam CSoia RElliott TBovce DATE 10101/09 10101/09 914/09* 10102/09