Letter Sequence RAI |
|---|
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MONTHYEARML0630602512003-10-15015 October 2003
WB1-DWD-015A, Containment Debris Walkdown Package Watts Bar N. P. Unit 1.
Project stage: Other
ML0629105222003-11-0505 November 2003
WB1-DWD-024A, Containment Debris Walkdown Package Watts Bar N. P. Unit 1.
Project stage: Other
ML0629105132004-08-24024 August 2004
TVAW001-RPT-001, Rev. 0, Report on Watts Bar, Unit 1 Containment Building Walkdowns for Emergency Sump Strainer Issues.
Project stage: Other
ML0515205802005-06-0303 June 2005
Request for Additional Information Related to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-water Reactors
Project stage: RAI
ML0603704802006-02-10010 February 2006
Request for Additional Information Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-basis Accidents at Pressurized-water Reactors
Project stage: RAI
ML0603800822006-02-10010 February 2006
RAI, Response to GL-2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-water Reactors
Project stage: RAI
ML0610203132006-04-11011 April 2006
Generic Letter 2004-02 - Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized Water Reactors - Response to Request for Additional Information
Project stage: Response to RAI
ML0610402192006-04-11011 April 2006
Generic Letter 2004-02 - Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized Water Reactors - Response to Request for Additional Information
Project stage: Response to RAI
ML0610101802006-05-10010 May 2006
Request for Additional Info the Nuclear Regulatory Commission Staff Audit on the Containment Sump Modification
Project stage: Acceptance Review
ML0621204722006-07-0303 July 2006
Watts Bar Nuclear Plant (WBN) Unit 1 - Generic Letter 2004-02 - Request for Additional Information Regarding the Nuclear Regulatory Commission Staff Audit on the Containment Sump Modifications
Project stage: Request
ML0629105082006-07-0303 July 2006
Generic Letter 2004-02 - Request for Additional Information Regarding NRC Staff Audit on Containment Sump Modifications
Project stage: Request
ML0621800772006-08-11011 August 2006
Proprietary Letter, Request for Withholding Information from Public Disclosure, Containment Sump Modifications
Project stage: Withholding Request Acceptance
ML0636204112006-12-21021 December 2006
Nuclear Regulatory Commission (NRC) Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Supplemental Response
Project stage: Supplement
ML0721501092007-08-0101 August 2007
Generic Letter 2004-02 - Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized Water Reactors - Request for Extension of Completion Date for Corrective Actions
Project stage: Request
ML0727604492007-10-0202 October 2007
Watts Bar Nuclear Plant (WBN) Unit 1, Generic Letter 2004-02, Recirculation During Design-Basis Accidents at Pressurized Water Reactors - Request for Extension of Completion Date for Corrective Actions
Project stage: Request
ML0733703172007-11-28028 November 2007
Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (PWR) - Notice of Completion
Project stage: Other
ML0733801522007-12-0606 December 2007
Generic Letter 2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Extension Request Evaluation
Project stage: Other
ML0806402052008-02-29029 February 2008
Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accident at Pressurized-Water Reactors (PWR) - Notice of Completion
Project stage: Supplement
ML0811201592008-03-31031 March 2008
Enclosure 1, Supplemental Response Addressing GL-04-002 Actions, Calculation No. PCI-5343-S01, Rev. 0, Attachment D, Page 374 of 575 Through Calculation No. PCI-5343-S02, Rev 0, Attachment B, Page 100 of 631
Project stage: Supplement
ML0810905032008-03-31031 March 2008
Enclosure 1, Supplemental Response Addressing GL-04-002 Actions, Calculation No. PCI-5464-S01, Rev. 2, Attachments a and B, Page 384 of 680
Project stage: Supplement
ML0810905022008-03-31031 March 2008
Enclosure 1, Supplemental Response Addressing GL-04-002 Actions, Figure 4.25 - Case 3 Through Calculation PCI-5464-S01, Page 107
Project stage: Supplement
ML0810905002008-03-31031 March 2008
Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors - Notice of Completion
Project stage: Supplement
ML0810905012008-03-31031 March 2008
Enclosure 1, Supplemental Response Addressing GL-04-002 Actions, Pages E1-1 Through Figure 4.24 - Case 3
Project stage: Supplement
ML0810905082008-03-31031 March 2008
Enclosure 1, Supplemental Response Addressing GL-04-002 Actions, Calculation No. PCI-5464-S02, Rev. 0, Attachment B Page 101 Through End
Project stage: Supplement
ML0810905052008-03-31031 March 2008
Enclosure 1, Supplemental Response Addressing GL-04-002 Actions, Calculation No. PCI-5464-S01, Rev. 2, Attachment B, Page 385 Through 680
Project stage: Supplement
ML0832308232008-11-25025 November 2008
Request for Additional Information Regarding Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors (Tac Nos. MC4717 and MC4718)
Project stage: RAI
ML0833700332008-12-0303 December 2008
Request for Additional Information Regarding Generic Letter 2004-02. Potential Impact of Debris Blockage During Design Basis Accidents at Pressurized-Water Reactors (Tac No. MC4730)
Project stage: RAI
ML0905408572009-02-23023 February 2009
Generic Letter 2004-02 - Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized Water Reactors - Response to Request for Additional Information
Project stage: Response to RAI
ML0907208692009-02-25025 February 2009
Calculation, ALION-CAL-TVA-2739-03, Rev. 4, Watts Bar Reactor Building GSI-191 Debris Generation Calculation.
Project stage: Other
ML0907208682009-03-0303 March 2009
Response to Request for Additional Information Regarding Generic Letter 2004-02,.Potential Impact of Debris Blockage During Design Basis Accidents at Pressurized-Water Reactors.
Project stage: Response to RAI
ML0926502602009-09-29029 September 2009
RAI, Regarding Generic Letter 2004-02, Potential Impact of Debris Blockage During Design Basis Accidents at Pressurized-Water Reactors
Project stage: RAI
ML0936502182009-12-23023 December 2009
GL 2004-02 Final RAI Responses Due Date
Project stage: RAI
ML1000601162010-01-0707 January 2010
Change of Response Date Regarding Request for Additional Information for Generic Letter 2004-02 Potential Impact of Debris Blockage During Design-Basis Accidents at Pressurized
Project stage: RAI
ML1015905562010-06-0909 June 2010
Request for Withholding Proprietary Information from Public Disclosure Related to Generic Letter 2004-02
Project stage: Other
ML1016600442010-06-17017 June 2010
Summary of Conference Call with TVA on Proposed Response to Request for Additional Information on Generic Letter 2004-02
Project stage: RAI
ML1107000312011-04-15015 April 2011
Notice of Meeting with Tennessee Valley Authority to Discuss Responses to NRC Requests for Additional Information for Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accident at Pre
Project stage: RAI
ML11152A1702011-05-12012 May 2011
05/12/2011-Meeting Slides from Meeting with TVA on Their Proposed Response to a Request for Additional Information on Generic Letter 2004-02
Project stage: Response to RAI
ML11154A0932011-06-28028 June 2011
Request for Withholding Proprietary Information from Public Disclosure Related to Generic Letter 2004-02
Project stage: Other
ML11152A1632011-06-28028 June 2011
Summary of Meeting with TVA on Their Proposed Response to a Request for Additional Information on Generic Letter 2004-02
Project stage: RAI
ML11230B2502011-11-0303 November 2011
Request for Withholding Proprietary Information from Public Disclosure Related to Generic Letter 2004-02
Project stage: Other
CNL-14-114, Resolution of Generic Safety Issue (GSI)-1912014-06-27027 June 2014
Resolution of Generic Safety Issue (GSI)-191
Project stage: Request
ML14283A5132014-11-17017 November 2014
NRC Staff Review Documentation Provided by TVA for the Sequoyah Nuclear Plant, Units 1 and 2 Concerning Resolution of GL2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurizer-Wate
Project stage: Approval
ML14283A5262014-11-17017 November 2014
Closeout of GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactor
Project stage: Other
CNL-15-009, Resolution of Generic Safety Issue 1912015-04-17017 April 2015
Resolution of Generic Safety Issue 191
Project stage: Request
ML15191A1832015-09-17017 September 2015
Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
Project stage: Other
CNL-15-252, License Amendment Request and Request for Deviation from 10 CFR 50, Appendix R in Support of Closure of Generic Safety Issue 191 (WBN-TS-16-01)2016-02-23023 February 2016
License Amendment Request and Request for Deviation from 10 CFR 50, Appendix R in Support of Closure of Generic Safety Issue 191 (WBN-TS-16-01)
Project stage: Request
2008-03-31
[Table View] |
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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
ML24008A2462024-01-18018 January 2024
Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule
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
IR 05000327/20234422024-01-11011 January 2024
95001 Supplemental Inspection Report 05000327/2023442 and 05000328/2023442 and Follow-Up Assessment Letter
ML24011A3162024-01-11011 January 2024
Submittal of Discharge Monitoring Report (Dmr), August 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
ML24011A3192024-01-11011 January 2024
Submittal of Discharge Monitoring Report (Dmr), November 2023
ML24011A3182024-01-11011 January 2024
Submittal of Discharge Monitoring Report (Dmr), October 2023
ML24010A2132024-01-10010 January 2024
CFR 21.21 Final Report Regarding Siemens Medium Voltage Circuit Breakers
CNL-24-016, Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-01-10010 January 2024
Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)
CNL-23-052, Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability2024-01-0909 January 2024
Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability
CNL-23-062, Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018)2024-01-0808 January 2024
Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018)
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
ML23346A1382024-01-0303 January 2024
Regulatory Audit Summary Related to Request to Increase the Number of Tritium Producing Burnable Absorber Rods
IR 05000390/20234412023-12-21021 December 2023
Plantfinal Significance Determination for a Security-Related Greater than Green Finding, Nov, and Assessment Follow-up, 05000390-2023441 and 05000391-2023441-Public
CNL-23-069, 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-23-068, 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)
IR 05000390/20234042023-12-14014 December 2023
Security Baseline Inspection Report 05000390/2023404 and 05000391/2023404
CNL-23-001, Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01)2023-12-13013 December 2023
Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01)
ML23346A1222023-12-12012 December 2023
Annual Non-Radiological Environmental Operating Report - 2023
ML23293A0572023-12-0606 December 2023
Issuance of Amendment Nos. 163 and 70 Regarding Adoption of TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control
IR 05000390/20230102023-11-30030 November 2023
RE-Issue Watts Bar Nuclear Plant - Biennial Problem Identification and Resolution Inspection Report 050000390/2023010 and 05000391/2023010 and Apparent Violation
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
IR 05000390/20230032023-11-13013 November 2023
Integrated Inspection Report 05000390/2023003 and 05000391/2023003 and Apparent Violation
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
ML23312A1432023-11-0808 November 2023
Submittal of Dual Unit Updated Final Safety Analysis Report (UFSAR) Amendment 5
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-23-061, 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
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
2024-01-09
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML23307A0822023-11-0808 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
ML23307A0832023-11-0808 November 2023
Enclosure - Request for Additional Information HDI-Sequoyah NDE Exemption Request 10-30-2023
ML23166A1142023-06-15015 June 2023
Document Request for Watts Bar Nuclear Plant - Radiation Protection Inspection - Inspection Report 2023-03
ML23067A2372023-03-0808 March 2023
WB_2023-02_RP_inspection_doc_request
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
ML23030A3512023-01-25025 January 2023
Notification of Watts Bar Nuclear Plant - Design Bases Assurance Inspection (Programs) and Initial Information 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
ML22115A1402022-04-25025 April 2022
NRR E-mail Capture - Requests for Confirmation of Information and Additional Information Regarding Watts Bar Nuclear Plant, Unit 2 Exemption Request Re 10 CFR Part 26 (L-2022-LLE-0017)
ML22083A2372022-03-24024 March 2022
NRR E-mail Capture - Request for Additional Information and Confirmation of Information Related to Tva'S Request for Changes to Watts Bar Nuclear Plant, Units 1 and 2, Technical Specification 3.7.8
ML22056A3802022-02-25025 February 2022
Document Request for Watts Bar Nuclear Plant - Radiation Protection Inspection - Inspection Report 2022-02
ML21267A1392021-09-23023 September 2021
Document Request for Upcoming RP Inspection at Watts Bar
ML21237A4952021-08-25025 August 2021
Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2021-04
ML21221A2602021-08-0909 August 2021
NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Revise Watts Bar, Unit 1 Tech Specs Related to Continuous Opening of the Auxiliary Building Secondary Containment Enclosure Boundary
ML21160A0352021-06-0303 June 2021
Document Request for Sequoyah Nuclear Plant - Radiation Protection Inspection - Inspection Report 2021-03
ML21102A1312021-04-19019 April 2021
Request for Withholding Information from Public Disclosure for Watts Bar Nuclear Plant, Unit 1
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
ML21095A0422021-04-0202 April 2021
NRR E-mail Capture - Added Clarification to RAI 2 for Thot LAR
ML21095A0402021-04-0202 April 2021
NRR E-mail Capture - Request for Additional Information Re Generic Letter 95-05 90-Day Report and LAR to Adjust Growth Rate for Thot (EPIDs L-2021-LRO-0003 and L-2021-LLA-0026)
ML21091A0772021-04-0101 April 2021
NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Revise Technical Specification 5.7.2.19, Containment Leakage Rate Testing Program
ML21095A0442021-04-0101 April 2021
NRR E-mail Capture - Revised Draft RAI - Combined RAI Set for Watts Bar Unit 2 90-Day Report and Thot LAR (EPIDs L-2021-LRO-0003 and L-2021-LLA-0026)
ML21095A0412021-04-0101 April 2021
NRR E-mail Capture - Revised Draft RAI - Combined RAI Set for Watts Bar Unit 2 90-Day Report and Thot LAR (EPIDs L-2021-LRO-0003 and L-2021-LLA-0026)
ML21095A0462021-03-22022 March 2021
NRR E-mail Capture - Draft Request for Additional Information Regarding Tva'S Generic Letter 95-05 90-Day Report for Watts Bar Unit 2
ML21039A6402021-02-0808 February 2021
NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Revise the Watts Bar Nuclear Plant, Unit 1 Technical Specifications Related to Steam Generator Tube Inspection Frequency
ML21012A2032021-01-11011 January 2021
NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Revise the Watts Bar UFSAR to Use Alternate Probability of Detection
ML20350B5592020-12-15015 December 2020
NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Adopt Traveler TSTF-490 Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec
ML20338A3202020-12-0303 December 2020
Notification of an NRC Fire Protection Team Inspection (NRC Inspection Report 05000390/2021011 and 05000391/2021011) and Request for Information
ML20322A4412020-11-17017 November 2020
NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Revise TS 3.7.11 Related to the MCR Chiller Replacement
ML20322A4392020-11-0505 November 2020
NRR E-mail Capture - Draft Request for Additional Information Regarding Tva'S Request to Revise TS 3.7.11 Related to the MCR Chiller Replacement
ML20308A3512020-11-0202 November 2020
Request for Additional Information on WBN Request for Exemption from 10 CFR Part 73, Appendix B, Section VI for the Conduct of an Annual Force-on-Force Exercise (EPID L-2020-LLE-0165 (COVID-19))
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
ML20253A1782020-09-0909 September 2020
Emergency Preparedness Program Inspection Request for Information
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
ML20266G4592020-08-14014 August 2020
Notification of Inspection and Request for Information
ML20196L8622020-07-14014 July 2020
NRR E-mail Capture - Watts Bar Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding Request to Implement the Full Spectrum LOCA Methodology
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)
ML20086G4802020-03-26026 March 2020
NRR E-mail Capture - Request for Additional Information for WBN2 Request Measurement Uncertainty Recapture Power Uprate (L-2019-LLS-0000) - Part 2
2023-06-15
[Table view] |
Text
June 3, 2005 Mr. Karl W. Singer Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, Tennessee 37402-2801
SUBJECT:
SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 AND WATTS BAR NUCLEAR PLANT, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO GENERIC LETTER 2004-02, POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY SUMP RECIRCULATION AT PRESSURIZED-WATER REACTORS (TAC NOS. MC4717, MC4718, AND MC4730)
Dear Mr. Singer:
By letter dated March 7, 2005, the Tennessee Valley Authority (the licensee) provided the 90-day response to U.S. Nuclear Regulatory Commission (NRC) Generic Letter (GL) 2004-02 for the Sequoyah Nuclear Plant, Units 1 and 2, and the Watts Bar Nuclear Plant, Unit 1. The GL requested the licensee perform an evaluation of the emergency core cooling system and containment spray system recirculation functions in light of the information provided in the GL and, if appropriate, take additional actions to ensure system function. Additionally, addressees were requested to submit to the NRC the information specified in the GL.
The NRC staff has completed its preliminary review of your response and has determined that additional information will be necessary to complete our review. The enclosure seeks information regarding your overall plans and schedules and not on detailed plans or analyses.
In light of this, we request that you provide the information described in the enclosure within 45 days of receipt of this letter.
If you have any questions, please call me at (301) 415-1364.
Sincerely,
/RA/
Douglas V. Pickett, Senior Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-327, 50-328, and 50-390
Enclosure:
Request for Additional Information cc w/encl: See next page
June 3, 2005 Mr. Karl W. Singer Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, Tennessee 37402-2801
SUBJECT:
SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 AND WATTS BAR NUCLEAR PLANT, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO GENERIC LETTER 2004-02, POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY SUMP RECIRCULATION AT PRESSURIZED-WATER REACTORS (TAC NOS. MC4717, MC4718, AND MC4730)
Dear Mr. Singer:
By letter dated March 7, 2005, the Tennessee Valley Authority (the licensee) provided the 90-day response to U.S. Nuclear Regulatory Commission (NRC) Generic Letter (GL) 2004-02 for the Sequoyah Nuclear Plant, Units 1 and 2, and the Watts Bar Nuclear Plant, Unit 1. The GL requested the licensee perform an evaluation of the emergency core cooling system and containment spray system recirculation functions in light of the information provided in the GL and, if appropriate, take additional actions to ensure system function. Additionally, addressees were requested to submit to the NRC the information specified in the GL.
The NRC staff has completed its preliminary review of your response and has determined that additional information will be necessary to complete our review. The enclosure seeks information regarding your overall plans and schedules and not on detailed plans or analyses.
In light of this, we request that you provide the information described in the enclosure within 45 days of receipt of this letter.
If you have any questions, please call me at (301) 415-1364.
Sincerely,
/RA/
Douglas V. Pickett, Senior Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-327, 50-328, and 50-390
Enclosure:
Request for Additional Information cc w/encl: See next page DISTRIBUTION PUBLIC PDII-2 r/f RidsOgcRp RidsAcrsAcnwMailCenter MMarshall RidsNrrPM[DPickett]
RidsNrrLA[BClayton] RidsRgn[2]MailCenter[SCahill] DCullison/DSolorio RidsNrrDlpmDpr RidsNrrDssaDpr MWebb Accession No.: ML051520580 *RAI input from staff w/o major changes NRR-088 OFFICE PDII-2:PM PDII-2:LA DSSA/SPLB/SP* PDII-2:SC NAME DPickett LFeizollahi DCullison/DSolorio GSuh for for BClayton MMarshall DATE 06/03/05 06/03/05 5/23/05 06 /03/05 OFFICIAL COPY
Page 1 of 2 Mr. Karl W. Singer SEQUOYAH NUCLEAR PLANT Tennessee Valley Authority WATTS BAR NUCLEAR PLANT cc:
Mr. Ashok S. Bhatnagar, Senior Vice President Mr. Fredrick C. Mashburn Nuclear Operations Senior Program Manager Tennessee Valley Authority Nuclear Licensing 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, General Manager Nuclear Engineering Mr. Paul L. Pace, Manager Tennessee Valley Authority Licensing and Industry Affairs 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. William R. Lagergren, Site Vice President Watts Bar Nuclear Plant Mr. David A. Kulisek, Plant Manager Tennessee Valley Authority Sequoyah Nuclear Plant P.O. Box 2000 Tennessee Valley Authority Spring City, TN 37381 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 County Mayor Tennessee Valley Authority Hamilton County Courthouse ET 11A Chattanooga, TN 37402-2801 400 West Summit Hill Drive Knoxville, TN 37902 Mr. Paul L. Pace, Manager Licensing and Industry Affairs Mr. John C. Fornicola, Manager Watts Bar Nuclear Plant Nuclear Assurance and Licensing Tennessee Valley Authority Tennessee Valley Authority P.O. Box 2000 6A Lookout Place Spring City, TN 37381 1101 Market Street Chattanooga, TN 37402-2801 Jay Laughlin, Plant Manager Watts Bar Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Spring City, TN 37381
Page 2 of 2 Mr. Karl W. Singer SEQUOYAH NUCLEAR PLANT Tennessee Valley Authority WATTS BAR NUCLEAR PLANT cc:
Senior Resident Inspector Watts Bar Nuclear Plant U.S. Nuclear Regulatory Commission 1260 Nuclear Plant Road Spring City, TN 37381 County Executive 375 Church Street Suite 215 Dayton, TN 37321 County Mayor P. O. Box 156 Decatur, TN 37322 Mr. Lawrence E. Nanney, Director Division of Radiological Health Dept. of Environment & Conservation Third Floor, L and C Annex 401 Church Street Nashville, TN 37243-1532 Ms. Ann P. Harris 341 Swing Loop Road Rockwood, Tennessee 37854
REQUEST FOR ADDITIONAL INFORMATION REGARDING GENERIC LETTER 2004-02 POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY SUMP RECIRCULATION AT PRESSURIZED-WATER REACTORS TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 WATTS BAR NUCLEAR PLANT, UNIT 1 DOCKET NOS. 50-327, 50-328, AND 50-390 By letter dated March 7, 2005, Tennessee Valley Authority (the licensee) provided the 90-day response to U.S. Nuclear Regulatory Commission (NRC) Generic Letter (GL) 2004-02 for Watts Bar Nuclear Plant, Unit 1 and Sequoyah Nuclear Plant, Units 1 and 2. The GL requested that addressees perform an evaluation of the emergency core cooling system and containment spray system recirculation functions in light of the information provided in the GL and, if appropriate, take additional actions to ensure system function. Additionally, addressees were requested to submit to the NRC the information specified in the GL. The staff has completed its preliminary review of your response and has determined it needs the following additional information to complete our review:
As a result of the review of the 90-day responses for all licensees and recent discussions with industry, the staff is concerned that some licensees may be delaying the evaluation of chemical effects until after the September 1, 2005, due date for the next response to the GL. This would result in an incomplete response and is not in accordance with the schedule in the GL. Your 90-day response indicated that your analysis will be completed by September 1, 2005, but did not discuss the evaluation of chemical effects. Although the GL did not specifically request that the evaluation of chemical effects be discussed in the 90-day response, please discuss your plans and schedule for evaluating chemical effects and verify whether your September 1, 2005, response will include such an evaluation.
ENCLOSURE
