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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
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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:Proprietary Information Review
MONTHYEARML23251A2002023-09-11011 September 2023 Request for Withholding Information from Public Disclosure for Watts Bar Nuclear Plant, Units 1 and 2 ML23156A0052023-07-0303 July 2023 Request for Withholding Information from Public Disclosure for Watts Bar Nuclear Plant ML22020A3932022-02-18018 February 2022 Request for Withholding Information from Public Disclosure (EPID L-2020-LA-0004) ML21245A1822022-02-15015 February 2022 SDR 16-01, Revision 3 Request for Withholding Information from Public Disclosure (EPID L-2020-LA-0004) ML21015A0772022-01-18018 January 2022 Request for Withholding Information from Public Disclosure for Watts Bar Nuclear Plant, Units 1 and 2 ML22010A0792022-01-14014 January 2022 Request for Withholding Information from Public Disclosure for Watts Bar Nuclear Plant, Unit 2 ML21251A2422021-09-14014 September 2021 Request for Withholding Information from Public Disclosure ML21250A1682021-09-0808 September 2021 Request for Withholding Information from Public Disclosure for Watts Bar Nuclear Plant, Unit 2 ML21246A1172021-09-0202 September 2021 Affidavit Dated September 2, 2021, Executed by Anthony J. Schoedel ML21196A0112021-08-0606 August 2021 Request for Withholding Information from Public Disclosure (EPID L-2020-LA-0004) ML21102A1312021-04-19019 April 2021 Request for Withholding Information from Public Disclosure for Watts Bar Nuclear Plant, Unit 1 ML21062A1892021-04-14014 April 2021 Request for Withholding Information from Public Disclosure for Watts Bar Nuclear Plant, Unit 2 ML20346A0992021-03-0303 March 2021 Request for Withholding Information from Public Disclosure for Watts Bar Nuclear Plant, Units 1 and 2 ML21027A1102021-02-23023 February 2021 Request for Withholding Information from Public Disclosure Watts Bar Nuclear Plant, Unit 2 ML21021A2412021-02-0808 February 2021 Request for Withholding Information from Public Disclosure ML20343A1182021-01-12012 January 2021 Request for Withholding Information from Public Disclosure ML20304A1872020-11-10010 November 2020 Request for Withholding Information from Public Disclosure ML20141L7672020-05-28028 May 2020 Request for Withholding Information from Public Disclosure ML20098D5332020-04-10010 April 2020 Request for Withholding Information from Public Disclosure ML19339E0882020-01-0707 January 2020 Request for Withholding Information from Public Disclosure ML19339E0862020-01-0707 January 2020 Request for Withholding Information from Public Disclosure ML18129A1172018-05-15015 May 2018 Request for Withholding Information from Public Disclosure ML16015A2992016-01-28028 January 2016 Request for Withholding Information from Public Disclosure for Watts Bar Nuclear Plant, Unit 2 ML15274A0322015-10-0505 October 2015 Request for Withholding Information from Public Disclosure ML14155A3602014-07-0303 July 2014 Request for Withholding Information from Public Disclosure ML14121A1792014-05-28028 May 2014 Request for Withholding Information from Public Disclosure for the Review of the Sequoyah Nuclear Plant, Units 1 and 2, License Renewal Application (TAC Nos. MF0481 and MF0482) ML12240A1992012-09-0606 September 2012 PI for Sequoyah 1 and 2- Permit Use of Advanced W17 Htp Fuel (TAC Nos. ME6538/6539) ML12185A0772012-07-0909 July 2012 Request for Withholding Proprietary Information from Public Disclosure Regarding Use of Areva Advanced W17 High Thermal Performance Fuel ML12125A1892012-05-29029 May 2012 Request for Withholding Proprietary Information from Public Disclosure Regarding Use of Areva Advanced W17 High Thermal Performance Fuel ML12086A3112012-05-0404 May 2012 Request for Withholding Proprietary Information from Public Disclosure Regarding Use of Areva Advanced W17 High Thermal Performance Fuel (TAC Nos. ME6538 and ME6539) ML11320A0262011-12-27027 December 2011 Request for Withholding Proprietary Information from Public Disclosure Regarding Use of Areva Advanced W17 High Thermal Performance Fuel ML11230B2502011-11-0303 November 2011 Request for Withholding Proprietary Information from Public Disclosure Related to Generic Letter 2004-02 ML11214A2052011-08-16016 August 2011 Plants, Units 1 & 2 - Request for Withholding Proprietary Information from Public Disclosure Regarding 10 CFR 5046 Annual Report (TAC ME5168 & ME5169) ML11207A0532011-08-0909 August 2011 Request for Withholding Proprietary Information from Public Disclosure Regarding Use of Areva Advanced W17 High Thermal Performance Fuel. ML11154A0932011-06-28028 June 2011 Request for Withholding Proprietary Information from Public Disclosure Related to Generic Letter 2004-02 ML1020900192010-07-29029 July 2010 Request for Withholding Information from Public Disclosure Regarding Watts Bar Nuclear Plant Cyber Security Plan and Cyber Security Plan Implementation Schedule (Tac No. ME2677 and ME2679) ML1015905562010-06-0909 June 2010 Request for Withholding Proprietary Information from Public Disclosure Related to Generic Letter 2004-02 ML1011303512010-05-0505 May 2010 Request for Withholding Information from Public Disclosure (Tac No. ME2731) ML1012502952010-04-30030 April 2010 Information Request for Withholding ML0914701812009-06-22022 June 2009 Withholding from Public Disclosure, Attachment 3 to Enclosure of the 05/21/2009 Application, Application of W* Alternate Repair Criteria to Sequoyah Unit 2 Cold Leg Tubes. ML0900600402009-01-26026 January 2009 Request for Withholding Information from Public Disclosure for Watts Bar Nuclear Plant, Unit 1 ML0820406072008-08-0808 August 2008 Areva Np, Inc. Request for Withholding Information Regarding Sequoyah Nuclear Plant, Unit 1, from Public Disclosure ML0812701582008-05-21021 May 2008 Withholding from Public Disclosure, SG-CDME-07-21-P, Revision 0, Examination of a Steam Generator Tube Removed from Sequoyah Unit 2 (Proprietary), Dated September 2007 ML0812802552008-05-21021 May 2008 Areva Np, Inc., Request for Withholding Information Regarding Sequoyah, Unit 2, from Public Disclosure ML0726400062007-09-28028 September 2007 Request for Withholding Information from Public Disclosure ML0719004292007-08-10010 August 2007 Request for Withholding Information from Public Disclosure ML0700403902007-01-24024 January 2007 Withholding from Public Disclosure, SER Compliance with WCAP-16260-P-A, the Spatially Corrected Inverse Count Rate (Scicr) Method for Subcritical Reactivity Measurement (Proprietary) ML0624302842006-09-15015 September 2006 Westinghouse Electric Corporation LLC - Request for Withholding Information from Public Disclosure for Watts Bar, Unit 1 ML0621800772006-08-11011 August 2006 Proprietary Letter, Request for Withholding Information from Public Disclosure, Containment Sump Modifications ML0508104752004-03-30030 March 2004 Withholding from Public Disclosure, LTR-CDME-04-147, Rev. 1, Operation of W* Alternate Repair Criteria to Sequoyah Unit 2 (Tac No. MC5212) 2023-09-11
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 9, 2010 Mr. R. M. Krich Vice President, Nuclear Licensing Tennessee Valley Authority 3R Lookout Place 11 01 Market Street Chattanooga, TN 37402-2801
SUBJECT:
SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 AND WATTS BAR NUCLEAR PLANT, UNIT 1 - REQUEST FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE RELATED TO GENERIC LETTER 2004-02 (TAC NOS. MC4717, MC4718, AND MC4730)
Dear Mr. Krich:
By letter dated June 3, 2010, the Tennessee Valley Authority (TVA) submitted the draft responses to requests for additional information related to Nuclear Regulatory Commission (NRC) Generic Letter (GL) 2004-02, "Potential Impact of Debris Blockage During Design Basis Accidents at Pressurized-Water Reactors," for Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Unit 1. In this letter, TVA submitted GL 2004-02 draft test procedures, and requested that AREVA NP Incorporated proprietary information included in Enclosures 6 and 7 of this letter be withheld from public disclosure pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Part 2, Section 2.390. An affidavit dated June 2, 2010, executed by Gayle F. Elliott of AREVA NP Incorporated, and included as Enclosure 8 to your letter dated June 3, 2010, was provided requesting that information contained in the following documents be withheld from public disclosure pursuant to 10 CFR 2.390:
- Enclosure 6 to a letter dated June 3, 2010 -AREVA NP Inc. Test Procedure, Document No. 63-9138557-Dft, "Test Plan for Sequoyah Unit 1 and Unit 2 ECCS [Emergency Core Cooling System] Strainer Performance Testing" (Draft) (Proprietary).
- Enclosure 7 to a letter dated June 3, 2010 - AREVA NP Inc. Test Procedure, Document No. 63-9138557-Dft, "Test Plan for Watts Bar Unit 1 ECCS Strainer Performance Testing" (Draft) (Proprietary).
R. Krich -2 The affidavit stated that the submitted information should be considered exempt from mandatory public disclosure for the following reasons:
(b) Use of the information by a competitor would permit the competitor to significantly reduce its expenditures, in time or resources, to design, produce, or market a similar product or service.
(c) The information includes test data or analytical techniques concerning a process, methodology, or component, the application of which results in a competitive advantage for AREVA NP.
We have reviewed your letter dated June 3, 2010, and the enclosed material in accordance with the requirements of 10 CFR 2.390 and, on the basis of your statements, have determined that the submitted information sought to be withheld contains proprietary commercial information and should be withheld from public disclosure.
Therefore, the enclosure of the submitted information marked as proprietary will be withheld from public disclosure pursuant to 10 CFR 2.390(b)(5) and Section 103(b) of the Atomic Energy Act of 1954, as amended.
Withholding from public inspection shall not affect the right, if any, of persons properly and directly concerned to inspect the documents. If the need arises, we may send copies of this information to our consultants working in this area. We will, of course, ensure that the consultants have signed the appropriate agreements for handling proprietary information.
If the basis for withholding this information from public inspection should change in the future such that the information could then be made available for public inspection, you should promptly notify the NRC. You also should understand that the NRC may have cause to review this determination in the future, for example, if the scope of a Freedom of Information Act request includes your information. In all review situations, if the NRC makes a determination adverse to the above, you will be notified in advance of any public disclosure.
R. Krich -3 If you have any questions regarding this matter, I may be reached at 301-415-1564.
Sincerely,
~ f' oVvv-(}""'""
Siva P. Lingam, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-327, 50-328, and 50-390 cc: Ms. Gayle F. Elliott, Manager Product Licensing AREVA NP Inc.
3315 Old Forge Road Lynchburg, VA 24501 Additional Distribution via Listserv
R. Krich - 3 If you have any questions regarding this matter, I may be reached at 301-415-1564.
Sincerely, IRA!
Siva P. Lingam, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-327,50-328, and 50-390 cc: Ms. Gayle F. Elliott, Manager Product Licensing AREVA NP Inc.
3315 Old Forge Road Lynchburg, VA 24501 Additional Distribution via Listserv DISTRIBUTION:
PUBLIC LPL2-2 R1F RidsNrrDorlLpl2-2 Ridsl\lrrPMSequoyah RidsNrrLABClayton RidsNrrDorlDpr RidsOgcMailCenter RidsAcrsAcnw_MailCTR RidsNrrDssSsib RidsRgn2MailCenter RidsNrrPMWattsBar1 RidsNrrDorlLp-Wb RidsNrrLACSola ADAMS Accession No* ML101590556 OFFICE LPL2-2/PM LP-WB/PM LPL2-2/LA LP-WB/LA NRRlDSS/SSIB/BC LPL2-2/BC NAME SLingam JLamb CSoia BClayton MScott DBroaddus (BClayton for) (EBrown for)
DATE 06/08/10 06/09/10 06/08/10 06/08/10 06/09/10 06/09/10 OFFICIAL RECORD COpy