Letter Sequence Request |
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TAC:MD6311, Clarify Application of Setpoint Methodology for LSSS Functions, Control Room Habitability, Steam Generator Tube Integrity (Approved, Closed) TAC:MD8314, Clarify Application of Setpoint Methodology for LSSS Functions, Control Room Habitability, Steam Generator Tube Integrity (Open) |
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement, Supplement, Supplement, Supplement
Results
Other: CNL-14-154, Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 12 (TAC No. MD6311), and Status of Generic Communications for Unit 2 - Revision 12, CNL-15-137, Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 13 (TAC No. MD6311) and Status of Generic Communications for Unit 2 - Revision 13, ML080860026, ML080860040, ML081700293, ML082410088, ML083460177, ML090480486, ML101260469, ML102170077, ML102290258, ML103010299, ML11213A130, ML11362A056, ML12234A688, ML13023A315, ML13213A194
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MONTHYEARML0732401242007-11-26026 November 2007 Summary of Meeting with Tennessee Valley Authority on Use of Eagle 21 at Watts Bar Unit 2 Project stage: Meeting ML0734400222007-12-0505 December 2007 Westinghouse Eagle - 21 Process Protection System Project stage: Request ML0801705432008-01-0303 January 2008 Summary of December 12, 2007, Meeting with Tennessee Valley Authority on Reconstruction of the Licensing Basis for Watts Bar Unit 2 Project stage: Meeting ML0735209712008-01-0303 January 2008 Summary of Meeting with Tennessee Valley Authority on Reconstitution of the Licensing Basis for Watts Bar, Unit 2 Project stage: Meeting ML0803701852008-02-0101 February 2008 Request to Use American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Code Case N-520-2, Alternative Rules for Renewal of Active or Expired N-Type Certificates for Plants Not in Active Construction. Project stage: Other ML0812105062008-05-0707 May 2008 Request for Additional Information Regarding Eagle-21 Process Protection System (Tac No. MD6311) Project stage: RAI ML0810101162008-05-0808 May 2008 Review Topics for Safety Evaluation, Attachment 1 Project stage: Approval ML0808600402008-05-0808 May 2008 Enclosure 1- Watts Bar Nuclear Plant, Unit 2 - Assessment of Remaining Operating License Application Review Scope Project stage: Other ML0808600262008-05-0808 May 2008 Assessment of Remaining Operating License Application Review Scope Project stage: Other ML0814300282008-05-14014 May 2008 Transmittal of Annual Radiological Environmental Operating Report of 2007 Project stage: Request ML0813008092008-05-22022 May 2008 Request for Additional Information, Renewal of Active or Expired N-Type Certificates for Plants Project stage: RAI ML0814901102008-05-28028 May 2008 Status of Generic Communications for Review (Tac No. MD8314) Project stage: Other ML0814901182008-05-28028 May 2008 NRC Review: Generic Communications Status for TVA Watts Bar Unit 2 Project stage: Other ML0817002932008-06-16016 June 2008 Response to Additional Information Request on Regulatory Framework for the Completion of Construction and Licensing, Revision 1 Project stage: Other ML0818504592008-07-0202 July 2008 Response to Request for Additional Information Project stage: Response to RAI ML0818504602008-07-0202 July 2008 Final Supplemental Environmental Impact Statement - Request for Additional Information Project stage: Supplement ML0821402382008-07-29029 July 2008 Generic Communications Status, Revision 1 Project stage: Other ML0824100882008-08-25025 August 2008 Westinghouse Eagle-21 Process Protection System Project stage: Other ML0827500192008-09-26026 September 2008 Regulatory Framework for the Completion of Construction and Licensing Activities for Unit 2 - Corrective Action and Special Programs, and Unresolved Safety Issues Project stage: Other ML0825603732008-10-0202 October 2008 Request for Relief Regarding Alternative Rules for Renewal of Active or Expired N-Type Certificates Project stage: Other ML0834601772008-12-0909 December 2008 Unit 2 - Licensing Basis Preservation and Construction Refurbishment Program for Structures, Systems and Components (Sscs) Project stage: Other ML0904804862009-02-23023 February 2009 TVA December 11, 2008 - Public MtgR1 Project stage: Other ML0904804362009-02-23023 February 2009 Summary of December 11, 2008, Meeting with Tennessee Valley Authority on Status of Construction and Licensing Activities Project stage: Meeting ML0904804662009-02-23023 February 2009 NRR - Public Meeting WBN2 Status 12-11-08 Project stage: Meeting ML0904804712009-02-23023 February 2009 Region II - December 2008 Public Meeting with Notes Project stage: Meeting ML1001204872009-11-12012 November 2009 Application for Special Nuclear Material License in Accordance with 10 CFR 70, Domestic Licensing of Special Nuclear Material Project stage: Request ML1001916842010-01-11011 January 2010 Final Safety Analysis Report, Amendment 97, Section 3 - Design of Structures, Components, Equipment, and Systems, Page 3.8.5-1 Through Page 3.11-9 Project stage: Request ML1001914212010-01-11011 January 2010 Final Safety Analysis Report, Amendment 97 Project stage: Request ML1012002042010-04-20020 April 2010 Preservice Inspection Program Plan and Additional Information Project stage: Other ML1012604692010-04-29029 April 2010 Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 2, and Status of Generic Communications for Unit 2 - Revision 2 Project stage: Other ML1016805612010-06-17017 June 2010 Preservice Inspection Program Plan and Additional Information Project stage: Other ML1019402362010-06-18018 June 2010 Instrumentation and Controls Staff Information Requests Project stage: Request ML1017602222010-06-25025 June 2010 Request to Use ASME Boiler and Pressure Vessel Code, Code Case N-520-3, Alternative Rules for Renewal of Active or Expired N-Type Certificates for Plants Not in Active Construction, Section III, Division 1 Project stage: Other ML1021700772010-07-30030 July 2010 Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 3, and Status of Generic Communications for Unit 2 - Revision 3 Project stage: Other ML1022902582010-07-31031 July 2010 Final Safety Analysis Report - Response to Preliminary Requests for Additional Information and Requests for Additional Information Project stage: Other ML1025001712010-09-0101 September 2010 OL - TVA Letter to NRC - WBN U2 FSAR A100 Project stage: Request ML1027005272010-09-29029 September 2010 Request for Relief Regarding Alternative Rules for Renewal of Active or Expired N-Type Certification Project stage: Other ML1030102992010-10-28028 October 2010 Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 4, and Status of Generic Communications for Unit 2 - Revision 4 Project stage: Other ML1031207112010-10-29029 October 2010 Instrumentation and Controls Staff Information Requests Project stage: Request ML1031207122010-10-29029 October 2010 Edcr 52321 Draft Scope and Intent, Unit Difference and Technical Evaluation, Enclosure 2, Attachment 1 Project stage: Request ML1031403142010-11-0101 November 2010 OL - TVA Letter to NRC_10-29-10_WBN U2 FSAR 101 Project stage: Request ML1032001462010-11-0909 November 2010 Final Safety Analysis Report (FSAR) - Response to Requests for Additional Information Project stage: Response to RAI ML1032106442010-11-17017 November 2010 Revision of Commitment for Implementation of the Maintenance Rule Project stage: Request ML1035405602010-12-17017 December 2010 Safety Evaluation Report Supplement 22 (SSER22) - Response to Requests for Additional Information Project stage: Supplement ML1102104862011-01-21021 January 2011 Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 5 and Status of Generic Communications for Unit 2 - Revision 5 Project stage: Other ML1106202192011-02-25025 February 2011 Instrumentation and Controls Staff Information Requests Project stage: Request ML1110500092011-04-0808 April 2011 OL - FW: Updated OI List Project stage: Request ML11136A0532011-04-18018 April 2011 OL - TVA Letter to NRC_04-15-11_I&C RAI Response Project stage: Request ML11129A2052011-05-0606 May 2011 Instrumentation and Controls Staff Information Requests Project stage: Request ML11178A1552011-06-0303 June 2011 Final Safety Analysis Report (Fsar), Amendment 104 Project stage: Request 2010-10-28
[Table View] |
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Category:Final Safety Analysis Report (FSAR)
MONTHYEARWBL-23-053, Updated Final Safety Analysis Report (UFSAR) Amendment 5, Redacted Version2023-11-0808 November 2023 Updated Final Safety Analysis Report (UFSAR) Amendment 5, Redacted Version ML23312A1462023-11-0808 November 2023 Updated Final Safety Analysis Report (UFSAR) Amendment 5 - Table of Contents ML20323A3032020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary System WBL-20-047, Amendment 3 to Updated Final Safety Analysis Report, Chapter 8, Electric Power (Redacted)2020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 8, Electric Power (Redacted) ML20323A3082020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 14, Initial Test Program ML20323A3142020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment, and Systems, Table of Contents to Sec 3.7 ML20323A3222020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 13, Conduct of Operations ML20323A3192020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 17, Quality Assurance ML20323A3172020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Division of Responsibility (Dor), Abbreviations ML20323A3112020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 4, Reactor ML21123A2262020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment, and Systems, Sections 3.8 to 3.12 (Redacted) ML20323A3152020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 11, Radioactive Waste Management ML20323A3182020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Table of Contents ML20323A3052020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 10, Main Steam and Power Conversion Systems ML20323A3012020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls ML20323A3002020-10-29029 October 2020 Submittal of Amendment 3 to Updated Final Safety Analysis Report ML20323A3202020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System ML21123A2252020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 2, Site Characteristics, Table of Contents to Sec 2.4 (Redacted) ML20323A3092020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 12, Radiation Protection ML20323A3162020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 15, Accident Analyses ML20323A3102020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 2, Sec 2.5, Geology, Seismology, and Geotechnical Engineering Summary of Foundation Conditions ML20323A3062020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant ML20323A3122020-10-29029 October 2020 Amendment 3 to Updated Final Safety Analysis Report, Chapter 16, Technical Specifications ML20142A3892020-05-21021 May 2020 Wbnp PSAR, Chapter 12, Conduct of Operations L-19-022, Amendment 2 to Updated Final Safety Analysis Report, Chapter 8, Electric Power - Redacted2019-03-18018 March 2019 Amendment 2 to Updated Final Safety Analysis Report, Chapter 8, Electric Power - Redacted ML19060A1472019-02-19019 February 2019 Amendment 1 to USAR Chapter 2 Auxiliary System NRC Additional Redactions 2 of 5 ML19060A1762019-02-18018 February 2019 Amendment 1 to USAR Chapter 2 Auxiliary System NRC Additional Redactions 3 of 5 ML19060A1822019-02-18018 February 2019 Amendment 1 to USAR Chapter 2 Auxiliary System NRC Additional Redactions 5 of 5 ML19039A1042019-02-0808 February 2019 Amendment 1 to USAR Chapter 2 Auxiliary System NRC Additional Redactions 1 of 5 ML19060A1492019-02-0808 February 2019 Amendment 1 to USAR Chapter 2 Auxiliary System NRC Additional Redactions 4 of 5 ML17334A1602017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 13, Conduct of Operations ML17334A1732017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 8, Electric Power (Redacted) ML17334A1622017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 14, Initial Test Program ML17334A1692017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 4, Reactor ML17334A1562017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 1, Introduction and General Description of Plant (Redacted) ML17334A1722017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 7, Instrumentation and Controls ML17334A1582017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 11, Radioactive Waste Management ML17334A1592017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 12, Radiation Protection (Redacted) ML17334A1572017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 10, Main Steam and Power Conversion Systems ML17334A1632017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 15, Accident Analyses ML17334A1642017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 16, Technical Specifications ML17334A1702017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 5, Reactor Coolant System ML17334A1652017-11-0202 November 2017 Amendment 1 to Updated Safety Analysis Report, Chapter 17, Quality Assurance ML15279A3192015-09-11011 September 2015 Amendment 114 to Final Safety Analysis Report, Section 2.0 - Site Characteristics, Figure 2.5-583 ML15279A3022015-09-11011 September 2015 Amendment 114 to Final Safety Analysis Report, Section 2.0 - Site Characteristics, Figure 2.5-550 ML15279A2742015-09-11011 September 2015 Amendment 114 to Final Safety Analysis Report, Section 6.0 - Engineered Safety Features, Pages 6.3-1 - 6.9-2 ML15279A3042015-09-11011 September 2015 Amendment 114 to Final Safety Analysis Report, Section 2.0 - Site Characteristics, Figure 2.5-554. Sheet 1 of 2 ML15279A3262015-09-11011 September 2015 Amendment 114 to Final Safety Analysis Report, Section 2.0 - Site Characteristics, Figure 2.5-602 ML15279A2772015-09-11011 September 2015 Amendment 114 to Final Safety Analysis Report, Section 9.0 - Auxiliary Systems, Pages 9-i - 9.3-158 ML15279A2782015-09-11011 September 2015 Amendment 114 to Final Safety Analysis Report, Section 9.0 - Auxiliary Systems, Pages 9.4-1 - 9.5-66 2023-11-08
[Table view] Category:Letter
MONTHYEARML23319A2452024-01-29029 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 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) ML23346A1382024-01-0303 January 2024 Regulatory Audit Summary Related to Request to Increase the Number of Tritium Producing Burnable Absorber Rods 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 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-23-036, 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) 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 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 ML23312A1432023-11-0808 November 2023 Submittal of Dual Unit Updated Final Safety Analysis Report (UFSAR) Amendment 5 CNL-23-059, Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-2023-09-20020 September 2023 Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision ML23251A2002023-09-11011 September 2023 Request for Withholding Information from Public Disclosure for Watts Bar Nuclear Plant, Units 1 and 2 CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 642023-09-0505 September 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 64 IR 05000390/20230052023-08-30030 August 2023 Updated Inspection Plan for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390/2023005 and 05000391/2023005 ML23233A0042023-08-28028 August 2023 Proposed Alternative to the Requirements of the ASME Boiler and Pressure Vessel Code for Upper Head Injection Dissimilar Metal Butt Welds IR 05000390/20230022023-08-16016 August 2023 Reissue - Watts Bar Nuclear Plant - Integrated Inspection Report 05000390/2023002 and 05000391/2023002 ML23220A1582023-08-0909 August 2023 Integrated Inspection Report 05000390/2023002 and 05000391/2023002 CNL-23-045, License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts (WBN-TS-23-010)2023-08-0707 August 2023 License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts (WBN-TS-23-010) CNL-23-028, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06)2023-08-0202 August 2023 Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06) ML23192A4472023-07-31031 July 2023 Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information CNL-23-055, Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills2023-07-25025 July 2023 Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills IR 05000390/20230112023-07-24024 July 2023 Quadrennial Focused Engineering Inspection (FEI) Commercial Grade Dedication Report 05000390 2023011 and 05000391 2023011 CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions CNL-23-020, Application to Revise Technical Specifications to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (WBN-TS-22-06)2023-06-28028 June 2023 Application to Revise Technical Specifications to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (WBN-TS-22-06) CNL-23-049, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan .2023-06-26026 June 2023 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan . ML23122A2322023-06-0707 June 2023 Issuance of Amendment Nos. 162 and 69 Regarding Change to Date in Footnotes for Technical Specification 3.7.11, Control Room Emergency Air Temperature Control System (Creatcs) CNL-23-044, Transmittal of Revision 3 to WCAP-18774-P and WCAP-18774-NP, Addendum to the Rotterdam Dockyard Company Final Stress Report for 173 P.W.R. Vessels TVA III & IV (Report No. 30749-B-030, Rev. 3) - Evaluation of One Closure Stud Out2023-06-0101 June 2023 Transmittal of Revision 3 to WCAP-18774-P and WCAP-18774-NP, Addendum to the Rotterdam Dockyard Company Final Stress Report for 173 P.W.R. Vessels TVA III & IV (Report No. 30749-B-030, Rev. 3) - Evaluation of One Closure Stud Out IR 05000390/20234032023-05-30030 May 2023 Cyber Security Inspection Report 05000390/2023403 and 05000391/2023403 ML23131A1812023-05-23023 May 2023 Correction to Amendment No. 161 to Facility Operating License No. NPF-90 CNL-23-042, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-05-16016 May 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000390/20220032023-05-0909 May 2023 Reissue Watts Bar Nuclear Plant - Integrated Inspection Report 05000390/2022003 and 05000391/2022003 ML23125A2202023-05-0505 May 2023 Issuance of Amendment No. 161 Regarding a Change to Footnotes for Technical Specification Table 1.1-1 Modes (Emergency Circumstances) IR 05000390/20230012023-05-0404 May 2023 Integrated Inspection Report 05000390/2023001 and 05000391/2023001 CNL-23-043, Emergency License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes (WBN-TS-23-09)2023-05-0404 May 2023 Emergency License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes (WBN-TS-23-09) CNL-23-032, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 412023-04-27027 April 2023 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 41 CNL-23-030, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2023-04-27027 April 2023 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-23-033, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-04-24024 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision CNL-23-029, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-04-11011 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML23072A0652023-04-0505 April 2023 Units 1 and 2 Issuance of Amendment Nos. 364 and 358; 160 and 68 Regarding a Revision to Technical Specification 3.4.12 ML23073A2762023-04-0303 April 2023 Individual Notice of Consideration of Issuance of Amendments to Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing (EPID L-2023-LLA-0029) (Letter) CNL-23-023, Annual Insurance Status Report2023-03-30030 March 2023 Annual Insurance Status Report CNL-23-024, TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report2023-03-29029 March 2023 TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report 2024-01-09
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l . q Tennessee Valley Authority, Post Office Box 2000, Spring City, TN 37381-2000 January 11,2010 10 CFR 50.4(b)(6) 10 CFR 50.34(b) 10 CFR 2.390(d)(1) /
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop: OWFN P1-35 Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 2 Docket No. 50-391
Subject:
WATTS BAR NUCLEAR PLANT (WBN) - UNIT 2 - FINAL SAFETY ANALYSIS REPORT (FSAR), AMENDMENT 97
Reference:
TVA letter to the NRC dated December 14, 2009, 'Watts Bar Nuclear Plant (WBN) - Unit 2 - Final Safety Analysis Report Amendment 96" This letter transmits WBN Unit 2 FSAR Amendment 97 (A97), which reflects changes made since the issuance of Amendment 96 on December 14, 2009 (Reference). This Unit 2 amendment incorporates changes resulting from TVA's ongoing design/reverification effort in support of completing the WBN Unit 2 design basis.
Enclosure 1 contains a "Summary Listing" of the location and corresponding Unit 2 FSAR change package numbers associated with the A97 changes. This is a listing of FSAR sections in which TVA has completed its design/reverification review and determined that design-related activities are complete; the verbiage is consistent with the Unit 1 Updated FSAR (UFSAR), as appropriate; and the section is ready for NRC review. Please note that Safety Evaluation Report Section 2.4, "Hydrologic Engineering" which was scheduled to be submitted in this amendment, has been rescheduled for February 2010 to allow incorporation of the most recent probable maximum flood evaluation data.
FSAR A97 is contained on the enclosed Optical Storage Media (OSM #1) (Attachment 1).
The FSAR contains security-related information identified by the designation "Security-Related Information - Withhold Under 10 CFR 2.390." TVA hereby requests this information be withheld from public disclosure in accordance with the provisions of 10 CFR 2.390. A redacted version of the FSAR is contained on OSM #2 (Attachment 2), which is suitable for public disclosure. Enclosure 2 contains a listing of the FSAR pages that have been redacted. Enclosure 3 lists the files and file sizes on the security-related OSM (OSM #1),
and Enclosure 4 lists the files and file sizes on the publicly available OSM (OSM #2).
Printed on recycled paper
U.S. Nuclear Regulatory Commission Page 2 January 11, 2010 TVA (WBN Unit 1) is currently preparing Unit 1 UFSAR Amendment 8 (A8) and will submit A8 on or before April 21, 2010, in accordance with 10 CFR 50.71(e)(4). To support NRC's review of the WBN Unit 2 FSAR, TVA has incorporated the approved Unit 1 A8 changes into Unit 2 A97, as appropriate. This letter does not close any "Generic Communications" or contain any new commitments.
If you have any questions, please contact me at (423) 365-2351.
I declare under the penalty of perjury that the foregoing is true and correct. Executed on January 11, 2010.
Sincerely, Masoud jestani Watts a Unit 2 Vice President
Enclosures:
- 1. List of Unit 2 FSAR Amendment 97, "Completed Sections and Required FSAR Changes"
- 2. Watts Bar Nuclear Plant Unit 2 FSAR Amendment 97, "Summary of Redacted Pages"
- 3. List of files and file sizes on the security-related OSM (OSM #1)
- 4. List of files and file sizes on the publicly available OSM (OSM #2)
Attachments:
- 1. OSM #1: WBNP Unit 2 FSAR Amendment 97 - Security-Related Information - Withhold Under 10 CFR 2.390
- 2. OSM #2: WBNP Unit 2 FSAR Amendment 97 - Public Version cc: See page 3
U.S. Nuclear Regulatory Commission Page 3 January 11, 2010 cc (w/enclosures):
U. S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-8931 NRC Resident Inspector Unit 2 Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381
ENCLOSURE 1 List of Unit 2 FSAR Amendment 97 "Completed Sections and Required FSAR Changes" Item No. Section Section Title Change Package Number 1.0 Introductionand General Description Of Plant 1.0 1.1 Introduction 2-97-41 1.0 1.1 _2-97-42 2.0 1.2 General Plant Description 2-97-15 2-97-55 3.0 1.3 Comparison Tables 2-97-56 4.0 1.6 Material Incorporated By 2-97-59 Reference 5.0 1.7 Electrical, Instrumentation, And 2-97-49 Control Drawings 6.0 1.8 Technical Qualification Of 2-97-50 Applicant 7.0 2.4 Hydraulic Engineering [February 2010]
8.0 3.3 Wind And Tornado Loading 2-97-25 3.8 Design of CategoryI Structures 9.0 3.8.1 Concrete Shield Building 2-97-01 10.0 3.8.2 Steel Containment System 2-97-02 11.0 3.8.3 Concrete Interior Structure 2-97-09 12.0 3.8.4 Other Category I Structures 2-97-53 13.0 3.8.5 Foundation and Concrete 2-97-33 Supports 14.0 3.8.6 Category I(L) Cranes 2-97-32 15.0 3.8 A Shell Temperature Transients 2-97-31 16.0 3.9 Mechanical Systems and 2-97-67 Components Environmental Design of 17.0 3.11 Mechanical And Electrical 2-97-21 Equipment 18.0 5.1 Reactor Coolant System - 2-97-34 Summary Description 19.0 5.2 Integrity of Reactor Coolant 2-97-47 Pressure Boundary -
20.0 5.4 Reactor Vessel And 2-97-03 Appurtenances 5.5 Component And Subsystem Design 21.0 5.5.1 Reactor Coolant Pump 2-97-19 22.0 5.5.3 Reactor Coolant Piping 2-97-04 23.0 5.5.6 Reactor Vessel Head Vent 2-97-05 System 24.0 5.5.7 Residual Heat Removal System 2-97-29 25.0 5.5.13 Safety and Relief Valves 2-97-28 26.0 6.1 Engineered Safety Feature 2-97-06 Materials 2-97-16 6.2 ContainmentSystems 27.0 6.2.1 Containment functional Design 2-97-81 28.0 6.2.2 Containment Heat Removal 2-97-35 System
ENCLOSURE I List of Unit 2 FSAR Amendment 97 "Completed Sections and Required FSAR Changes" Item No. Section Section Title Change Package Number 29.0 6.2.3 Secondary Containment 2-97-63 Functional Design 2-97-63 30.0 6.2.4 Containment Isolation Systems 2-97-39 31.0 6.2.6 Containment Leakage Testing 2-97-46 32.0 6.4 Habitability System 2-97-07 33.0 6.5 Fission Product Removal And 2-97-14 Control System 34.0 6.7 Ice Condenser System 2-97-40 35.0 6.8 Air Return Fans 2-97-18 36.0 6.9 Motor-Operated Valve (MOV) 2-97-08 Programs 37.0 8.2 Offsite (Preferred) Power 2-97-12 System 38.0 9.1.3 Spent Fuel Pool Cooling And 2-97-11 Cleanup System 39.0 9.1.4 Fuel Handling System 2-97-24 40.0 9.3.1 Process Auxiliaries 2-97-13 41.0 9.3.2 Process Sampling System 2-97-26 42.0 9.3.4 Chemical and Volume Control 2-97-51 System 43.0 9.3.6 Auxiliary Charging System 2-97-30 44.0 9.4.1 Control Room Area Ventilation 2-97-22 System 45.0 9.4.2 Fuel Handling Area Ventilation 2-97-23 System 46.0 9.4.3 Auxiliary And Radwaste Area 2-97-43 Ventilation System 47.0 9.4.5 Engineered Safety Feature 2-97-37 Ventilation System 2-97-63 48.0 9.4.6 Reactor Building Purge Ventilating System (RBPVS) 2-97-36 49.0 9.4.7 Containment Air Cooling System 2-97-27 50.0 9.5.1 Fire Protection System 2-97-10 51.0 10.4.3 Turbine Gland Sealing System 2-97-54 52.0 10.4.5 Condenser Circulating Water 2-97-45 System 53.0 10.4.6 Condensate Polishing 2-97-20 Demineralizer System Condensate And Feedwater 54.0 10.4.7 System2-97-68 55.0 10.4.8 Steam Generator Blowdown 2-97-44 System Auxiliary Feedwater System 2-97-38 56.0 10.4.9 2-97-58 2-97-61 57.0 12.3 Radiation Protection Design 2-97-62 1 Features
ENCLOSURE1 List of Unit 2 FSAR Amendment 97 "Completed Sections and Required FSAR Changes" Item No. Section Section Title Change Package Number 58.0 13.5 Site Procedures 2-97-57 14.0 Initial Test Program 59.0 14.2.1 Summary of Test Program And Objectives 60.0 14.2.2 Organization And Staffing 61.0 14.2.3 Test Procedure 62.0 14.2.4 Conduct Of Testing Program 63.0 14.2.5 Test Prerequisites 64.0 14.2.6 Phase Evaluations 65.0 14.2.7 Design Modifications 14.2.8 Utilization of Reactor Operating 66.0 And Testing Experience In 2-97-66 Development Of Test Program 14.2.9 Trial Use of Plant Operating And Emergency Procedure 14.2.10 Initial Fuel Loading, Postloading 68.0 Tests, Initial Criticality, Low Power Tests And Power Ascension 69.0 14.2.11 Test Program Schedule 70.0 14.2.12 Individual Test Description 71.0 15.0 Accident Analysis 2-97-48 72.0 15.1 Condition I - Normal Operation 2-97-73 and Operational Transients 73.0 15.2 Condition II - Faults Of 2-97-16 Moderate Frequency 2-97-79 74.0 15.3 Condition III - Infrequent Faults 2-97-77 75.0 15.4 Condition IV - Limiting Faults 2-97-75 76.0 15.5 Environmental Consequences of Accidents Dose Models Used To Evaluate 2-94-80 77.0 15 A The Environmental Consequences of Accidents 78.0 16.0 Technical Specifications 79.0 16.1 Proposed Technical 2-94-23 Specifications 80.0 16.2 Technical Specification 81.0 17.1 Quality Assurance During Design And Construction 2-97-52 82.0 17.2 Quality Assurance Program For Station Operation
ENCLOSURE 2 Watts Bar Nuclear Plant Unit 2 FSAR Amendment 97 "Summary of Redacted Pages" Chapter Page(S) Section No. Figure No. Basis For Redaction 1 1.2-15 1.2 1.2-1 Security Related, 10CFR2.390(d)(1) 1 1.2-16 1.2 1.2-2 Security Related, 10CFR2.390(d)(1) 1 1.2-17 1.2 1.2-3 Security Related, 10CFR2.390(d)(1) 1 1.2-18 1.2 1.2-4 Security Related, 10CFR2.390(d)(1) 1 1.2-19 1.2 1.2-5 Security Related, 10CFR2.390(d)(1) 1 1.2-20 1.2 1.2-6 Security Related, 10CFR2.390(d)(1) 1 1.2-21 1.2 1.2-7 Security Related, 10CFR2.390(d)(1) 1 1.2-22 1.2 1.2-8 Security Related, 10CFR2.390(d)(1) 1 1.2-23 1.2 1.2-9 Security Related, 10CFR2.390(d)(1) 1 1.2-24 1.2 1.2-10 Security Related, 10CFR2.390(d)(1) 1 1.2-25 1.2 1.2-11 Security Related, 10CFR2.390(d)(1) 1 1.2-26 1.2 1.2-12 Security Related, 10CFR2.390(d)(1) 1 1.2-27 1.2 1.2-13 Security Related, 10CFR2.390(d)(1) 1 1.2-28 1.2 1.2-14 Security Related, 10CFR2.390(d)(1) 1 1.2-29 1.2 1.2-15 Security Related, 10CFR2.390(d)(1) 2 2.2-7 2.2 2.2-1 Security Related, 10CFR2.390(d)(1) 2 2.2-8 2.2 2.2-2 Security Related, 10CFR2.390(d)(1) 2 2.4-90 2.4 2.4-2 Security Related, 10CFR2.390(d)(1) 2 2.4-91 2.4 2.4-3 Security Related, 10CFR2.390(d)(1) 2 2.4-92 2.4 2.4-3a Security Related, 10CFR2.390(d)(1) 2 2.4-93 2.4 2.4-4 Security Related, 10CFR2.390(d)(1) 2 2.4-94 2.4 2.4-5 Security Related, 10CFR2.390(d)(1) 2 2.4-95 2.4 2.4-6 Security Related, 10CFR2.390(d)(1) 2 2.4-96 2.4 2.4-7 Security Related, 10CFR2.390(d)(1) 2 2.4-97 2.4 2.4-8 Security Related, 10CFR2.390(d)(1) 2 2.4-98 2.4 2.4-9 Security Related, 10CFR2.390(d)(1) 2 2.4-99 2.4 2.4-10 Security Related, 10CFR2.390(d)(1) 2 2.4-100 2.4 2.4-11 Security Related, 10CFR2.390(d)(1) 2 2.4-101 2.4 2.4-12 Security Related, 10CFR2.390(d)(1) 2 2.4-102 2.4 2.4-13 Security Related, 10CFR2.390(d)(1) 2 2.4-103 2.4 2.4-14 Security Related, 10CFR2.390(d)(1) 2 2.4-131 2.4 2.4-40a Security Related, 10CFR2.390(d)(1)
Sheet 1 2 2.4-132 2.4 2.4-40a Security Related, 10CFR2.390(d)(1)
Sheet 2 2 2.4-134 2.4 2.4-40b Security Related, 10CFR2.390(d)(1) 2 2.4-135 2.4 2.4-40c Security Related, 10CFR2.390(d)(1) 2 2.4-136 2.4 2.4-40d-1 Security Related, 10CFR2.390(d)(1) 2 2.4-141 2.4 2.4-40f Security Related, 10CFR2.390(d)(1)
Sheet 1 2 2.4-144 2.4 2.4-40g Security Related, 10CFR2.390(d)(1)
Sheet 1 2 2.4-201 2.4 2.4-76 Security Related, 10CFR2.390(d)(1) 2 2.4-204 2.4 2.4-79 Security Related, 10CFR2.390(d)(1) 2 2.4-207 2.4 2.4-82 Security Related, 10CFR2.390(d)(1) 2 2.4-208 2.4 2.4-83 Security Related, 10CFR2.390(d)(1) 2 2.4-213 2.4 2.4-88 Security Related, 10CFR2.390(d)(1)
ENCLOSURE2 Watts Bar Nuclear Plant Unit 2 FSAR Amendment 97 "Summary of Redacted Pages" Chapter Page(S) Section No. Figure No. Basis For Redaction 2 2.4-214 2.4 2.4-89 Security Related, 10CFR2.390(d)(1) 2 2.4-215 2.4 2.4-90 Security Related, 10CFR2.390(d)(1) 2 2.4-223 2.4 2.4-98 Security Related, 10CFR2.390(d)(1) 2 2.5-473 2.5 2.5-185 Security Related, 10CFR2.390(d)(1) 2 2.5-474 2.5 2.5-185a Security Related, 10CFR2.390(d)(1) 2 2.5-515 2.5 2.5-225 Security Related, 10CFR2.390(d)(1) 2 2.5-516 2.5 2.5-226 Security Related, 10CFR2.390(d)(1) 2 2.5-577 2.5 2.5-226a Security Related, 10CFR2.390(d)(1) 2 2.5-577 2.5 2.5-273 Security Related, 10CFR2.390(d)(1) 2 2.5-692 2.5 2.5-358 Security Related, 10CFR2.390(d)(1) 2 2.5-936 2.5 2.5-592 Security Related, 1 OCFR2.390(d)(1) 3 3.5-53 3.5 3.5-3 Security Related, 10CFR2.390(d)(1) 3 3.5-54 3.5 3.5-4 Security Related, 10CFR2.390(d)(1) 3 3.6-73 3.6 3.6-21 Security Related, 10CFR2.390(d)(1) 3 3.6-74 3.6 3.6-22 Security Related, 10CFR2.390(d)(1) 3 3.6-75 3.6 3.6-23 Security Related, 10CFR2.390(d)(1) 3 3.6-76 3.6 3.6-24 Security Related, 10CFR2.390(d)(1) 3 3.7-217 3.7 3.7-39 Security Related, 10CFR2.390(d)(1) 3 3.7-218 3.7 3.7-40 Security Related, 10CFR2.390(d)(1) 3 3.7-219 3.7 3.7-41 Security Related, 10CFR2.390(d)(1) 3 3.7-222 3.7 3.7-44 Security Related, 10CFR2.390(d)(1) 3 3.8.3-62 3.8.3 3.8.3-6 Security Related, 10CFR2.390(d)(1) 3 3.8.3-63 3.8.3 3.8.3-7 Security Related, 10CFR2.390(d)(1) 3 3.8.4-88 3.8.4 3.8.4-2 Security Related, 10CFR2.390(d)(1) 3 3.8.4-89 3.8.4 3.8.4-3 Security Related, 10CFR2.390(d)(1) 3 3.8.4-90 3.8.4 3.8.4-4 Security Related, 10CFR2.390(d)(1) 3 3.8.4-91 3.8.4 3.8.4-5 Security Related, 10CFR2.390(d)(1) 3 3.8.4-92 3.8.4 3.8.4-6 Security Related, 10CFR2.390(d)(1) 3 3.8.4-95 3.8.4 3.8.4-9 Security Related, 10CFR2.390(d)(1) 3 3.8.4-103 3.8.4 3.8.4-17 Security Related, 10CFR2.390(d)(1) 3 3.8.4-104 3.8.4 3.8.4-18 Security Related, 10CFR2.390(d)(1) 3 3.8.4-105 3.8.4 3.8.4-19 Security Related, 10CFR2.390(d)(1) 3 3.8.4-106 3.8.4 3.8.4-20 Security Related, 10CFR2.390(d)(1) 3 3.8.4-110 3.8.4 3.8.4-24 Security Related, 10CFR2.390(d)(1) 3 3.8.4-114 3.8.4 3.8.4-28 Security Related, 10CFR2.390(d)(1) 3 3.8.4-121 3.8.4 3.8.4-35 Security Related, 10CFR2.390(d)(1) 3 3.8.4-122 3.8.4 3.8.4-36 Security Related, 10CFR2.390(d)(1) 3 3.8.4-123 3.8.4 3.8.4-36a Security Related, 10CFR2.390(d)(1) 3 3.8.4-126 3.8.4 3.8.4-37 Security Related, 10CFR2.390(d)(1) 3 3.8.4-143 3.8.4 3.8.4-50 Security Related, 10CFR2.390(d)(1) 3 3.8.4-144 3.8.4 3.8.4-51 Security Related, 10CFR2.390(d)(1) 3 3.8.6-19 3.8.6 3.8.6-7 Security Related, 10CFR2.390(d)(1) 6 6.2.2-14 6.2.2 6.2.2-4 Security Related, 10CFR2.390(d)(1) 6 6.2.3-64 6.2.3 6.2.3-4 Security Related, 10CFR2.390(d)(1) 6 6.2.3-65 6.2.3 6.2.3-5 Security Related, 10CFR2.390(d)(1) 6 6.2.3-66 6.2.3 6.2.3-6 Security Related, 10CFR2.390(d)(1) 6 6.2.3-67 6.2.3 6.2.3-7 Security Related, 10CFR2.390(d)(1)
ENCLOSURE2 Watts Bar Nuclear Plant Unit 2 FSAR Amendment 97 "Summary of Redacted Pages" Chapter Page(S) Section No. Figure No. Basis For Redaction 6 6.2.3-68 6.2.3 6.2.3-8 Security Related, 10CFR2.390(d)(1) 6 6.2.3-69 6.2.3 6.2.3-9 Security Related, 10CFR2.390(d)(1) 6 6.2.3-70 6.2.3 6.2.3-10 Security Related, 10CFR2.390(d)(1) 6 6.2.3-79 6.2.3 6.2.3-18 Security Related, 10CFR2.390(d)(1) 6 6.2.3-80 6.2.3 6.2.3-19 Security Related, 10CFR2.390(d)(1) 8 8.1-23 8.1 8.1-1 Security Related, 10CFR2.390(d)(1) 8 8.2-13 8.2 Security Related, 10CFR2.390(d)(1) and 8.2-14 8 8.2-30 8.2 8.2-3 Security Related, 10CFR2.390(d)(1) 8 8.2-31 8.2 8.2-4 Security Related, 10CFR2.390(d)(1) 8 8.2-44 8.2 8.2-11 Security Related, 10CFR2.390(d)(1) 8 8.3-99 8.3 8.3-1 Security Related, 10CFR2.390(d)(1) 8 8.3-101 8.3 8.3-2 Security Related, 10CFR2.390(d)(1) 8 8.3-102 8.3 8.3-3 Security Related, 10CFR2.390(d)(1) 8 8.3-104 8.3 8.3-4b Security Related, 10CFR2.390(d)(1) 8 8.3-207 8.3 8.3-46 Security Related, 10CFR2.390(d)(1) 8 8.3-220 8.3 8.3-59 Security Related, 10CFR2.390(d)(1) 9 9.2-208 9.2 9.2-40 Security Related, 10CFR2.390(d)(1) 9 9.4-286 9.4 9.4-21 Security Related, 10CFR2.390(d)(1) 9 9.4-290 9.4 9.4-22c Security Related, 10CFR2.390(d)(1) 9 9.4-291 9.4 9.4-23 Security Related, 10CFR2.390(d)(1) 9 9.4-292 9.4 9.4-24 Security Related, 1 OCFR2.390(d)(1) 12 12.3-41 12.3 12.3-1 Security Related, 10CFR2.390(d)(1) 12 12.3-42 12.3 12.3-2 Security Related, 10CFR2.390(d)(1) 12 12.3-43 12.3 12.3-3 Security Related, 10CFR2.390(d)(1) 12 12.3-44 12.3 12.3-4 Security Related, 10CFR2.390(d)(1) 12 12.3-45 12.3 12.3-5 Security Related, 10CFR2.390(d)(1) 12 12.3-46 12.3 12.3-6 Security Related, 10CFR2.390(d)(1) 12 12.3-47 12.3 12.3-7 Security Related, 10CFR2.390(d)(1) 12 12.3-48 12.3 12.3-8 Security Related, 10CFR2.390(d)(1) 12 12.3-49 12.3 12.3-9 Security Related, 10CFR2.390(d)(1) 12 12.3-50 12.3 12.3-10 Security Related, 10CFR2.390(d)(1) 12 12.3-51 12.3 12.3-11 Security Related, 10CFR2.390(d)(1) 12 12.3-52 12.3 12.3-12 Security Related, 10CFR2.390(d)(1) 12 12.3-53 12.3 12.3-13 Security Related, 10CFR2.390(d)(1) 12 12.3-54 12.3 12.3-14 Security Related, 10CFR2.390(d)(1) 12 12.3-55 12.3 12.3-15 Security Related, 10CFR2.390(d)(1) 12 12.3-56 12.3 12.3-16 Security Related, 10CFR2.390(d)(1) 12 12.3-57 12.3 12.3-17 Security Related, 10CFR2.390(d)(1) 12 12.3-58 12.3 12.3-18 Security Related, 10CFR2.390(d)(1) 12 12.3-59 12.3 12.3-19 Security Related, 10CFR2.390(d)(1) 12 12.4-7 12.4 12.4-1 Security Related, 10CFR2.390(d)(1)
ENCLOSURE 3 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 97 - List of Files on Security-Related OSM File Name File Size - Bytes TVAWBN-2_FSARFiles 001 TVAWBFSAR TOC.pdf 509,936 002_TVA WB FSAR LEP.pdf 775,175 003_TVA WB FSARSection_1.pdf 4,594,992 004_TVA WB FSAR Section 2 A.pdf 9,878,078 005 TVA WB FSAR Section 2 B.pdf 21,212,923 006 TVA WB FSAR Section 2 C.pdf 2,073,213 007 TVA WB FSAR Section 2 D.pdf 31,335,862 008 TVA WB FSAR Section 2_E.pdf 47,242,160 009 TVA WB FSAR Section 3 A.pdf 2,579,000 010 TVAW B FSARSection_3_B.pdf 7,000,216 01 1_TVA WB FSAR Section 3 C.pdf 29,112,674 012 TVA WB FSAR Section_3 D.pdf 5,916,854 013_TVAWBFSAR Section 4.pdf 26,735,846 014 TVA WB FSAR Section 5.pdf 1,151,362 015 TVA WB FSAR Section 6 A.pdf 21,008,717 016 TVAWBFSAR Section 6 B.pdf 7,890,345 017 TVA WB FSAR Section 7.pdf 8,679,801 018_TVA WB FSAR Section 8. pdf 29,665,984' 019_TVA WB FSAR Section 9 A.pdf 24,538,951 020_TVAWBFSAR Section 9 B.pdf 15,199,734 021 TVA WB FSAR Section_ 10.pdf 13,389,739 022 TVA WB FSAR Section 11.pdf 4,050,723 023_TVA WB FSAR Section 12.pdf 5,937,596 024 TVA WB FSARSection_ 13.pdf 3,467,635 025 TVA WB FSAR Section 14.pdf 1,151,362 026 TVA WB FSAR Section 15.pdf 36,282,040 Page 1 of 3
ENCLOSURE 3 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 97 - List of Files on Security-Related OSM File Name File Size - Bytes 027 TVA WB FSAR Section 16.pdf 161,788 028 TVA WB FSARSection_ 17.pdf 134,324 Total 361,677,030 TVAWBN-2_OversizedFSAR_Figures 001_TVA WB FSAR Figure 2.5 3.pdf 1,757,743 002_TVAWBFSARFigure 2.5 11.pdf 1,689,538 003_TVA WB FSAR Figure 2.5 71.pdf 2,263,087 004_TVAWBFSARFigure 2.5 222.pdf 909,429 005_TVAWBFSAR Figure 2.5 281_1.pdf 2,155,627 006_TVA WB FSAR Figure 2.5 281 2.pdf 2,117,562 007_TVAWBFSAR Figure 2.5 549 1.pdf 3,600,807 008 TVA WB FSAR Figure 2.5 549 2.pdf 3,989,180 009_TVA WB FSAR Figure 2.5 549 3.pdf 2,863,719 010_TVA WB FSARFigure 2.5 549 4.pdf 2,809,599 011_TVA WB FSARFigure 2.5 550.pdf 1,803,985 012_TVAWBFSAR Figure 2.5 551.pdf 1,996,869 013_TVA WBFSAR Figure 2.5 554 1.pdf 3,081,060 014_TVAWBFSAR Figure 2.5 554 2.pdf 1,996,707 015 TVA WB FSARFigure 2.5 555.pdf 1,993,312 016_TVA WB FSAR Figure 2.5 556.pdf 2,998,087 017_TVAWBFSAR Figure 2.5 571 1.pdf 844,484 018_TVAWBFSAR Figure 2.5 571 2.pdf 3,128,329 019_TVA WB FSAR Figure 2.5 571 3.pdf 3,284,555 020_TVAWB FSAR Figure 2.5 571 4.pdf 2,142,316 021 TVAWBFSARFigure 2.5 572.pdf 2,196,945 022_TVAWBFSAR Figure 2.5 573.pdf 2,013,286 Page 2 of 3
ENCLOSURE 3 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 97 - List of Files on Security-Related OSM File Name File Size - Bytes 023 TVA WB FSAR Figure 2.5 576 1.pdf 3,238,525 024_TVAWBFSARFigure 2.5 576 2.pdf 2,151,750 025 TVA WB FSARFigure 2.5 577.pdf 2,207,622 026_TVAWBFSAR Figure 2.5 578.pdf 2,080,032 027_TVAWBFSARFigure 2.5 579.pdf 2,308,985 028_TVAWBFSARFigure 2.5 583.pdf 2,487,346 029_TVAWBFSARFigure 2.5 588.pdf 2,528,515 030_TVA WB FSAR Figure 2.5 589.pdf 2,480,438 031 TVAWBFSAR Figure 2.5 594.pdf 13,054,127 032_TVA WB FSAR Figure 2.5 595.pdf 2,323,267 033_TVAWBFSARFigure 2.5 596.pdf 5,732,107 034_TVAWBFSAR Figure 2.5 597.pdf 1,287,336 035_TVA WB FSAR Figure 2.5 602.pdf 5,549,537 036_TVAWBFSAR Figure 2.5 603.pdf 4,830,835 037_TVA WB FSARFigure 2.5 604.pdf 6,392,279 038_TVAWBFSARFigure 2.5 605.pdf 20,823,108 Total 131,112,035 TVA_WBN -2_OversizedFSARTable 001 TVA WB FSAR Table 6.2.4-1.pdf 1,330,665 Total 1,330,665 Page 3 of 3
ENCLOSURE 4 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 97 List of Files on PubliclyAvailable OSM File Name File Size - Bytes TVA_WBN-2_FSARFiles 001_TVA WB FSARTOC.pdf 509,936 002_TVA WB FSARLEP.pdf 775,175 003 TVA WB FSAR Section l.pdf 795,809 004_TVA WB FSAR Section 2_A.pdf 9,54Z875 005 TVA WB FSAR Section 2 B.pdf 15,820,719 006-TVA WB FSAR Section 2_C.pdf 2,073,197 007_TVA WB FSAR Section 2_D.pdf 31,335,862 008_TVAWBFSARSection_2_E.pdf 46,018,892 009_TVA WB FSAR Section 3_A.pdf Z294,224 010_TVA WB FSAR Section 3_B.pdf 5,703,812 01 ITVAWBFSAR Section 3_C.pdf 24,550,061 012 WVA WB FSAR Section 3_D.pdf 5,655,215 013_TVA WB FSARSection 4.pdf 26,735,872 014_TVA WB FSAR Section 5.pdf 8,080,417 015 TVA WB FSARSection 6_A.pdf 18,155,041 016_TVAWBFSARSection 6_B.pdf 7,890,345 017_TVA WB FSAR Section 7.pdf 8,679,801 018 TVAWBFSAR Section 8.pdf 27,044,134 019_TVAWB FSAR Section 9_A.pdf 24,303,441 020_TVA WB FSAR Section 9_B.pdf 14,029,712 021_TVA WB FSAR Section 10.pdf 13,389,739 022_TVAWBFSARSection_ 1 .pdf 3,956,551 023_TVAWBFSARSection_ 2.pdf 1,683,593 024_TVAWBFSARSection 13.pdf 3,467,635 025_TVA WB FSAR Section_14.pdf 1,151,362 026 TVA WB FSAR Section 15.pdf 36,282,040 027 TVAWBFSAR Section 16.pdf 161,788 Note: Byte amounts in italics are redacted files. Page 1 of 3
ENCLOSURE 4 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 97 List of Files on PubliclyAvailable OSM File Name File Size - Bytes 028 TVA WB FSAR Section 17.pdf 134,324 Total 340,221,572 TVA_WBN-2_OversizedFSARFigures 001 TVA WB FSAR Figure 2.5 3.pdf 1,757,743 002_TVA WB FSARFigure 2.5 11.pdf 1,689,538 003_TVAWBFSAR Figure 2.5 71.pdf 2,263,087 004_TVAWB FSAR Figure 2.5 222.pdf 909,429 005 TVA WB FSAR Figure 2.5 281_1.pdf 2,155,627 006_TVA WB FSAR Figure 2.5 281 2.pdf 2,117,562 007_TVAWB FSAR Figure 2.5 549 1.pdf 3,600,807 008_TVAWBFSAR Figure 2.5 549 2.pdf 3,989,180 009_TVAWB FSAR Figure 2.5 549 3.pdf 2,863,719 010 TVA WB FSAR Figure 2.5 549 4.pdf 2,809,599 011 TVAWBFSAR Figure 2.5 550.pdf 1,803,985 012_TVAWBFSAR Figure 2.5 551.pdf 1,996,869 013 TVA WB FSARFigure 2.5 554_1.pdf 3,081,060 014_TVAWBFSAR Figure 2.5 554 2.pdf 1,996,707 015_TVA WBFSAR Figure 2.5 555.pdf 1,993,312 016 TVA WB FSAR Figure 2.5 556.pdf 2,998,087 017_TVAWB FSARFigure 2.5 571_1 .pdf 844,484 018_TVAWB FSAR Figure 2.5 571 2.pdf 3,128,329 019_TVAWB FSAR Figure 2.5 571_3.pdf 3,284,555 020_TVAWBFSAR Figure 2.5 571 4.pdf 2,142,316 021_TVAWBFSAR Figure 2.5 572.pdf 2,196,945 022_TVA WB FSAR Figure 2.5 573.pdf 2,013,286 023_TVA WBFSAR Figure 2.5 576 1.pdf 3,238,525 024_TVAWBFSAR Figure 2.5 576 2.pdf 2,151,750 Note: Byte amounts in italics are redacted files. Page 2 of 3
ENCLOSURE 4 TVA Watts Bar Nuclear Plant Unit 2 FSAR Amendment 97 List of Files on Publicly Available OSM File Name File Size - Bytes 025 TVA WB FSARFigure 2.5 577.pdf 2,207,622 026_TVAWBFSAR Figure 2.5 578.pdf 2,080,032 027_TVAWBFSAR Figure 2.5 579.pdf 2,308,985 028 TVA WB FSAR Figure 2.5 583.pdf 2,487,346 029_TVAWBFSAR Figure 2.5 588.pdf 2,528,515 030_TVAWBFSARFigure 2.5 589.pdf 2,480,438 031 TVA WB FSAR Figure 2.5 594.pdf 13,054,127 032_TVAWBFSAR Figure 2.5 595.pdf 2,323,267 033 TVA WB FSAR Figure 2.5 596.pdf 5,732,107 034_TVAWBFSAR Figure 2.5 597.pdf 1,287,336 035 TVA WB FSAR Figure 2.5 602.pdf 5,549,537 036 TVAWBFSAR Figure 2.5 603.pdf 4,830,835 037_TVAWBFSAR Figure 2.5 604.pdf 6,392,279 038 TVA WB FSAR Figure 2.5 605.pdf 20,823,108 Total 131,112,035 TVA_WBN-2_OversizedFSARTable 001 _TVA WB FSAR Table 6.2.4-1.pdf 1,330,665 Total 1,330,665 Note: Byte amounts in italics are redacted files. Page 3 of 3