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Other: ML040650206, ML040910016, ML041310029, ML042240255, ML042990519, ML051180464, ML051250308, ML060410288, ML060450582, ML060950060, ML061110094, ML061110102, ML061110126, ML061140322, ML061730464, ML091870509, ML11171A037, ML11171A038, ML11308A018
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MONTHYEARML0400603592003-12-31031 December 2003 Letter Transmitting Browns Ferry, Units 1, 2 and 3, Application for Renewed Operating Licenses Project stage: Request ML0406502062004-03-0404 March 2004 Determination of Acceptability and Sufficiency for Docketing and Opportunity for a Hearing Regarding the Application from Tennesssee Valley Authority for Renewal of the Operating Licenses for Browns Ferry, Units 1, 2 & 3 Project stage: Other ML0409100162004-03-31031 March 2004 Review Schedule for Application for Renewal of the Operating Licenses for the Browns Ferry Nuclear Plant, Units 1, 2 and 3 Project stage: Other ML0413100292004-05-0606 May 2004 & 03/31/2004 Summary of Telephone Conferences with Tennesssee Valley Authority Concerning Activities on Browns Ferry Nuclear Plant, Units 1, 2 & 3 LRA Project stage: Other ML0419501002004-06-10010 June 2004 Audit and Review Plan for Plant Aging Management Programs and Reviews - Browns Ferry Nuclear Plant, Units 1, 2 and 3 Project stage: Request ML0418101682004-06-28028 June 2004 Summary of Telephone Conference on May 27, 2004, Between the U.S. NRC and the Tennessee Valley Authority Concerning Draft Requests for Additional Information on Browns Ferry Nuclear Plant, Units 1, 2 and 3 LRA Project stage: Draft RAI ML0421104852004-07-28028 July 2004 Summary of Telephone Conference Held on July 1, 2004, Between NRC and TVA Concerning Draft Requests for Additional Information (D-RAI) on Browns Ferry Nuclear Plant Units 1, 2,& 3 Project stage: Draft RAI ML0422402552004-08-10010 August 2004 Audit and Review Plan for Plant Aging Management Reviews and Programs at the Browns Ferry Nuclear Power Plants, Units 1, 2 and 3 Project stage: Other ML0424005502004-08-26026 August 2004 Summary of Telephone Conference Held on July 27, 2004, Between U.S. Nuclear Regulatory Commission & Tennessee Valley Authority Concerning Draft Requests for Additional Information on Browns Ferry Nuclear Plant, Units 1, 2 & 3, License Renew Project stage: Draft RAI ML0424502112004-08-31031 August 2004 Summary of Telephone Conference Held on July 12, 2004, Between the U.S. Nuclear Regulatory Commission (NRC) and the Tennessee Valley Authority (TVA) Concerning Requests for Additional Information (RAI) on Browns Ferry Nuclear Plant, Unts 1, Project stage: RAI ML0426005222004-09-16016 September 2004 Summary of Telephone Conference Held on August 19, 2004, Between the U.S. Nuclear Regulatory Commission and the Tennessee Valley Authority Concerning Draft Requests for Additional Information on Browns Ferry Nuclear Plant, Units 1, 2 & 3 LR Project stage: Draft RAI ML0429905192004-10-21021 October 2004 Summary of Telephone Conference Held on September 22, 2004, Between the U.S. Nuclear Regulatory Commission and the Tennessee Valley Authority Concerning Browns Ferry Nuclear Plant, Units 1, 2 and 3, LRA Project stage: Other ML0430905772004-11-0404 November 2004 Request for Additional Information for the Review of the Browns Ferry Nuclear Plant, Units 1, 2 and 3, LRA (TAC Nos. MC1704, MC1705 and MC1706.) Project stage: RAI ML0430905732004-11-0404 November 2004 Request for Additional Information for the Review of the Browns Ferry Nuclear Plant, Units 1, 2 and 3, LRA Project stage: RAI ML0511804642005-04-26026 April 2005 Audit and Review Report for Plant Aging Management Programs (Amps) and Aging Management Reviews (Amrs), Browns Ferry Nuclear Plant, Untis 1, 2 and 3 and Memo Project stage: Other ML0512503082005-05-0404 May 2005 Memo, Audit and Review Report for Plant Aging Management Reviews and Programs at the Browns Ferry Nuclear Power Plant Project stage: Other ML0535603282005-12-20020 December 2005 License Renewal Application - Supplemental Information for the Time Limited Aging Analysis for Stress Relaxation of the Core Plate Hold-Down Bolts and the Unit 1 Periodic Inspection Program (TAC Nos. MC1704. Project stage: Supplement ML0601204532006-01-12012 January 2006 Safety Evaluation Report Related to the License Renewal of Browns Ferry Nuclear Plant, Units 1, 2, and 3 (Tac Nos. MC1704, MC1705, MC1706) Project stage: Approval ML0601103412006-01-12012 January 2006 Transmittal Letter to K. Singer: Safety Evaluation Report Related to the License Renewal of Browns Ferry Nuclear Plant, Units 1, 2, and 3 Project stage: Approval ML0604102882006-01-31031 January 2006 License Renewal Application (LRA) - Annual Update Project stage: Other ML0603302952006-01-31031 January 2006 Safety Evaluation Report Related to the License Renewal of Browns Ferry Nuclear Plant, Units 1,2, and 3 (TAC Nos. MC1704, MC1705, and MC1706) - Request for Additional Information Related to Appendix F Items in the Application Project stage: Approval ML0604505822006-02-14014 February 2006 License Renewal Application (LRA) - Revised Commitment Tables Project stage: Other ML0606203532006-03-0303 March 2006 Safety Evaluation Report Related to the License Renewal of Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Request for Additional Information Related to Appendix F Items in the Application and the Topics Discussed in the Public Meeting... Project stage: Approval ML0606603742006-03-0707 March 2006 (BFN) Units 1, 2, and 3 License Renewal Application (LRA) - Supplemental Information for the Unit 1 Periodic Inspection (TAC MC1704, MC1705 and MC1706) Project stage: Supplement ML0607903762006-03-0707 March 2006 License Renewal Application (LRA) - Supplemental Information for Open Item 2.4-3 Project stage: Supplement ML0609500602006-04-0404 April 2006 (BFN) - Units 1, 2, and 3 License Renewal Application (LRA) - Unit 1 Lower Drywell Liner Inspections, Unit 1 Periodic Inspection Program, and Residual Heat Removal Service Water Piping Inspections Project stage: Other ML0609701682006-04-21021 April 2006 Transmittal of Supplement 1 to the Safety Evaluation Report (NUREG-1843) - Supplemental Safety Evaluation Report Related to the License Renewal of Browns Ferry Nuclear Plant, Units 1, 2, and 3 (TAC Nos. MC1704, MC1705, MC1706) Project stage: Approval ML0611403222006-04-21021 April 2006 Brown Ferry Units 1, 2, and 3 - License Renewal Application - Revised Commitment List Project stage: Other ML0611401822006-05-0404 May 2006 Improved Technical Specifications for Browns Ferry Nuclear Plant, Unit 3 Project stage: Acceptance Review ML0611403522006-05-0404 May 2006 Improved Technical Specifications for Browns Ferry Nuclear Plant, Unit 1 Project stage: Acceptance Review ML0609703322006-05-0404 May 2006 Ltr to Karl W. Singer - Issuance of Renewed Facility Operating License Nos. DPR-33, DPR-52 and DPR-68 for Browns Ferry Nuclear Plant, Units 1, 2, and 3 Project stage: Approval ML0611101022006-05-0404 May 2006 Renewed Facility Operating License DPR-52 Project stage: Other ML0611101262006-05-0404 May 2006 Renewed Facility Operating License No. DPR-68 Project stage: Other ML0611100942006-05-0404 May 2006 Renewed Facility Operating License DPR-33 Project stage: Other ML0611402092006-05-0404 May 2006 Improved Technical Specifications for Browns Ferry Nuclear Plant, Unit 2 Project stage: Acceptance Review ML0609703552006-05-0404 May 2006 Federal Register Notice - Notice of Issuance of Renewed Facility Operating License Nos. DPR-33, DPR-52 and DPR-68 for an Additional 20-year Period Project stage: Approval ML0613600442006-06-0707 June 2006 Agenda for Public Meeting with Entergy Operations Incorporated Regarding Spent Fuel Pool Rack Configuration Changes at ANO-1 and ANO-2 on Wednesday 06/07/2006, TAC Nos. MC1704, MC1705 Project stage: Meeting ML0617304642006-06-22022 June 2006 Corrections to Technical Specifications and Renewed Facility Operating License No. DPR-33, for Unit 1 Project stage: Other ML0619102062006-07-0606 July 2006 03/01/2006 - Summary of Meeting with TVA on the License Renewal Application for the Browns Ferry Nuclear Plant, Units 1, 2 and 3 Project stage: Meeting ML0618803982006-07-0606 July 2006 03/09/2006 Summary of a Meeting Held Between the U.S. Nuclear Regulatory Commission and the Tennessee Valley Authority on the License Renewal Application for the Browns Ferry Nuclear Plant, Units 1, 2 and 3 Project stage: Meeting ML0918705092009-07-17017 July 2009 G20090346/LTR-09-0303/EDATS: SECY-2009-0304 - Ltr. Mario Bonaca Report on the Safety Aspects of the License Renewal Application for the National Bureau of Standards Test Reactor Project stage: Other ML11171A0382010-12-31031 December 2010 NEDO-33632, Rev. 0, Browns Ferry (Units 1-3), Core Plate Bolt Analysis Stress Analysis Report. Project stage: Other ML11171A0372011-06-15015 June 2011 BWRVIP-25 Core Plate Bolt Stress Analysis Project stage: Other ML11308A0182011-11-0101 November 2011 One-Time Inspection Procedure, 0-TI-565, Rev. 0003 Project stage: Other 2005-05-04
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Category:Letter
MONTHYEARML24032A4762024-02-0101 February 2024 Final Report of a Part 21 Evaluation Associated with Starter Contactors for the BFN Unit 1 High Pressure Coolant Injection Suppression Pool Inboard Suction Valve ML24023A2802024-01-23023 January 2024 Final Report of a Deviation or Failure to Comply Associated with a Relay in the Reactor Core Isolation Cooling Condensate Pump 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 ML24016A3042024-01-16016 January 2024 Final Report of a Part 21 Evaluation Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump CNL-23-071, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472024-01-11011 January 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 ML24022A1732024-01-0303 January 2024 Receipt and Availability of the Subsequent License Renewal Application ML23319A1992024-01-0303 January 2024 Issuance of Amendment Nos. 333, 356, and 316 Regarding the Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves ML23355A2062023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23348A3942023-12-14014 December 2023 Interim Part 21 Report of a Potential Deviation or Failure to Comply Associated with Starter Contactors for the High Pressure Coolant Injection Suppression Pool Inboard Suction Valve IR 05000259/20230102023-12-11011 December 2023 Commercial Grade Dedication Inspection Report 05000259/2023010 and 05000260/2023010 and 05000296/2023010 ML23335A0722023-12-0101 December 2023 Interim Report of a Deviation or Failure to Comply Associated with a Relay in the Unit 2 Reactor Core Isolation Cooling Condensate Pump ML23334A2492023-11-30030 November 2023 Site Emergency Plan Implementing Procedure Revision CNL-23-070, Submittal of Fifth 10-Year Interval Inservice Testing Program Plan2023-11-29029 November 2023 Submittal of Fifth 10-Year Interval Inservice Testing Program Plan ML23331A2532023-11-27027 November 2023 Summary Report for 10 CFR 50.9 Evaluations, Technical Specifications Bases Changes, Technical Requirement Manual Changes, and NRC Commitment Revisions 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 ML23325A1102023-11-21021 November 2023 Anchor Darling Double Disc Gate Valve Commitment Revision ML23320A2542023-11-16016 November 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump IR 05000259/20230032023-11-13013 November 2023 Integrated Inspection Report 05000259/2023003, 05000260/2023003 and 05000296/2023003 IR 05000259/20230402023-11-0202 November 2023 Supplemental Inspection Supplemental Report 05000259 2023040 and Follow-Up Assessment Letter ML23292A2532023-10-18018 October 2023 BFN 2024-301, Corporate Notification Letter (210-day Ltr) ML23282A0022023-10-0606 October 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump ML23278A0122023-10-0505 October 2023 Updated Final Safety Analysis Report, Amendment 30 ML23271A1702023-09-28028 September 2023 Site Emergency Plan Implementing Procedure Revision ML23270A0702023-09-26026 September 2023 SLRA Pre-Application Meeting Summary 09-13-2023 ML23257A1232023-09-22022 September 2023 Administrative Changes to Technical Specification Pages Issued for License Amendment Nos. 332, 355, and 315 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 ML23263B1042023-09-20020 September 2023 Special Report 260/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation ML23205A2132023-09-0808 September 2023 Issuance of Amendment Nos. 332, 355, and 315 Regarding the Revision of Technical Specifications to Adopt TSTF-566-A and TSTF-580-A, Rev. 1 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 05000259/20230052023-08-29029 August 2023 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2023005, 05000260/2023005 and 05000296/2023005 ML23233A0432023-08-18018 August 2023 Enforcement Action EA-22-122 Inspection Readiness Notification ML23219A1542023-08-17017 August 2023 Request to Use Later Edition of ASME Code for Operation and Maintenance and Alternative Requests BFN-IST-01 Through 05 for the Fifth 10-Year Interval Inservice Testing Program ML23228A1642023-08-16016 August 2023 Site Emergency Plan Implementing Procedure Revision ML23228A0202023-08-15015 August 2023 (BFN) Unit 1 - Special Report 259/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation IR 05000259/20230022023-08-10010 August 2023 Integrated Inspection Report 05000259/2023002, 05000260/2023002, 05000296/2023002 and 07200052/2023001 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 ML23171A8862023-07-24024 July 2023 Issuance of Amend. Nos. 331, 354, and 314; 365 and 359 Regarding Adoption of TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML23201A2182023-07-20020 July 2023 Registration of Use of Cask to Store Spent Fuel (MPC-298 and -299) ML23159A2552023-07-20020 July 2023 Proposed Alternative to the Requirements of the ASME Code Regarding Volumetric Inspection of Standby Liquid Control Nozzles ML23199A3072023-07-18018 July 2023 Site Emergency Plan Implementing Procedure Revision CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions IR 05000259/20233012023-07-18018 July 2023 NRC Operator License Examination Report Nos. 05000259/2023301, 05000260/2023301, and 05000296/2023301 2024-02-01
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML23331A2532023-11-27027 November 2023 Summary Report for 10 CFR 50.9 Evaluations, Technical Specifications Bases Changes, Technical Requirement Manual Changes, and NRC Commitment Revisions CNL-23-018, Request for Amendment Regarding Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves (BFN TS-540)2023-03-30030 March 2023 Request for Amendment Regarding Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves (BFN TS-540) CNL-23-027, Second Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505-A, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b (BFN TS-524)2023-03-29029 March 2023 Second Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505-A, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b (BFN TS-524) CNL-22-045, Application to Revise Technical Specifications to Adopt TSTF-566-A, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, and TSTF-580-A, Revision 1, Provide Exception from Entering Mode 42023-03-10010 March 2023 Application to Revise Technical Specifications to Adopt TSTF-566-A, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, and TSTF-580-A, Revision 1, Provide Exception from Entering Mode 4 CNL-22-037, Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533)2023-01-31031 January 2023 Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533) CNL-22-089, License Amendment Request for Adoption of TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control (BFN TS-546)2022-12-20020 December 2022 License Amendment Request for Adoption of TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control (BFN TS-546) CNL-22-055, Application to Delete Acreage Value Discussion from Technical Specifications (BFN TS-543)2022-09-29029 September 2022 Application to Delete Acreage Value Discussion from Technical Specifications (BFN TS-543) CNL-22-083, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3, in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535).2022-09-13013 September 2022 to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3, in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535). CNL-22-039, Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements (BFN TS-537) (SQN-21-05) (WBN-TS-21-04)2022-07-13013 July 2022 Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements (BFN TS-537) (SQN-21-05) (WBN-TS-21-04) CNL-22-008, and Watts Bar Nuclear Plant - Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules (BFN-TS-541, SQN-TS-21-09, and WBN-TS-22-002)2022-06-13013 June 2022 and Watts Bar Nuclear Plant - Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules (BFN-TS-541, SQN-TS-21-09, and WBN-TS-22-002) CNL-22-057, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel Use2022-05-27027 May 2022 to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel Use CNL-22-056, Supplement to License Amendment Request Regarding Criticality Safety Analysis of Spent Fuel Pool Storage of Atrium 11 Fuel (TS-534)2022-04-28028 April 2022 Supplement to License Amendment Request Regarding Criticality Safety Analysis of Spent Fuel Pool Storage of Atrium 11 Fuel (TS-534) CNL-21-009, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505-A, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative2022-03-31031 March 2022 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505-A, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative CNL-21-002, Application to Adopt TSTF-205-A, Revision of Channel Calibration, Channel Functional Test, and Related Definitions, TSTF-563-A, Revise Instrument Testing Definitions to Incorporate the Surveillance.2021-12-0303 December 2021 Application to Adopt TSTF-205-A, Revision of Channel Calibration, Channel Functional Test, and Related Definitions, TSTF-563-A, Revise Instrument Testing Definitions to Incorporate the Surveillance. CNL-21-090, Application to Adopt TSTF-568-A, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.2, Revision 2 (BFN TS-539)2021-11-19019 November 2021 Application to Adopt TSTF-568-A, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.2, Revision 2 (BFN TS-539) CNL-21-020, Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie Modification to Support System Operability (BFN-TS-518)2021-11-0505 November 2021 Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie Modification to Support System Operability (BFN-TS-518) CNL-21-053, Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2, in Support of Atrium 11 Fuel Use (TS-535)2021-07-23023 July 2021 Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2, in Support of Atrium 11 Fuel Use (TS-535) CNL-21-050, License Amendment Request Regarding Criticality Safety Analysis of Spent Fuel Pool Storage of Atrium 11 Fuel (TS-534)2021-05-29029 May 2021 License Amendment Request Regarding Criticality Safety Analysis of Spent Fuel Pool Storage of Atrium 11 Fuel (TS-534) CNL-21-045, Bellefonte Nuclear Plant, Units 1 and 2; Browns Ferry Nuclear Plant, Units 1, 2, and 3; Clinch River Nuclear Site; Sequoyah Nuclear Plant, Units 1 and 2; Watts Bar Nuclear Plant, Unit 1 and 2 - Nuclear Quality Assurance Plan, TVA-NQA-PLN82021-04-29029 April 2021 Bellefonte Nuclear Plant, Units 1 and 2; Browns Ferry Nuclear Plant, Units 1, 2, and 3; Clinch River Nuclear Site; Sequoyah Nuclear Plant, Units 1 and 2; Watts Bar Nuclear Plant, Unit 1 and 2 - Nuclear Quality Assurance Plan, TVA-NQA-PLN89- CNL-21-008, Application to Revise Technical Specifications to Adopt TSTF-582, RPV WIC Enhancements (BFN TS-532)2021-03-0505 March 2021 Application to Revise Technical Specifications to Adopt TSTF-582, RPV WIC Enhancements (BFN TS-532) CNL-20-041, License Amendment Request to Remove Licensee Control (BFN TS-527, SQN-TS-20-08, and WBN-TS-20-016)2020-08-14014 August 2020 License Amendment Request to Remove Licensee Control (BFN TS-527, SQN-TS-20-08, and WBN-TS-20-016) CNL-20-047, Brown Ferry Nuclear Plant, Sequoyah Nuclear Plant & Watts Bar Nuclear Plant - Tennessee Valley Authority License Amendment Request to Revise Radiological Emergency Plan Regarding On-shift Emergency Medical Technician and Onsite Ambulance2020-07-31031 July 2020 Brown Ferry Nuclear Plant, Sequoyah Nuclear Plant & Watts Bar Nuclear Plant - Tennessee Valley Authority License Amendment Request to Revise Radiological Emergency Plan Regarding On-shift Emergency Medical Technician and Onsite Ambulance Re CNL-20-002, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors (TS-BFN-529)2020-07-17017 July 2020 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors (TS-BFN-529) CNL-20-044, License Amendment Request to Incorporate Tornado Missile Risk Evaluation Into the Licensing Basis2020-05-0606 May 2020 License Amendment Request to Incorporate Tornado Missile Risk Evaluation Into the Licensing Basis CNL-20-003, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (BFN-TS-516)2020-03-27027 March 2020 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (BFN-TS-516) CNL-19-125, Proposed Technical Specifications (TS) Change 510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 12, Additional License Condition2019-12-19019 December 2019 Proposed Technical Specifications (TS) Change 510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 12, Additional License Condition CNL-19-009, License Amendment Request to Revise Emergency Plan Staff Augmentation Times (TS-515)2019-09-18018 September 2019 License Amendment Request to Revise Emergency Plan Staff Augmentation Times (TS-515) CNL-19-070, TVA Request for Extension of Implementation Due Dates of Modifications 102 and 106 Related to NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor2019-07-0303 July 2019 TVA Request for Extension of Implementation Due Dates of Modifications 102 and 106 Related to NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor CNL-19-034, to TVA Request for Revision of Modifications 85, 102, and 106 Related to NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants for the Browns Ferry Nuclear Plant, Units 1, 2, and 3..2019-03-0808 March 2019 to TVA Request for Revision of Modifications 85, 102, and 106 Related to NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants for the Browns Ferry Nuclear Plant, Units 1, 2, and 3.. CNL-19-010, Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF)-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 (BFN-TS-513)2019-01-25025 January 2019 Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF)-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 (BFN-TS-513) CNL-18-134, Extended Power Uprate - Replacement Steam Dryer Revised Analysis and Limit Curves Report2018-11-29029 November 2018 Extended Power Uprate - Replacement Steam Dryer Revised Analysis and Limit Curves Report CNL-18-130, Revised Application to Modify the Technical Specifications for Unbalanced Voltage Relays2018-11-19019 November 2018 Revised Application to Modify the Technical Specifications for Unbalanced Voltage Relays CNL-18-099, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 2, Operator Training Results2018-07-23023 July 2018 Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 2, Operator Training Results ML18171A3372018-07-10010 July 2018 Issuance of Amendment to Revise License Condition 2.C(18)(a)3 CNL-18-085, License Amendment Request to Change the Implementation Date for License Amendments to Upgrade Emergency Action Level Scheme2018-06-15015 June 2018 License Amendment Request to Change the Implementation Date for License Amendments to Upgrade Emergency Action Level Scheme CNL-18-041, Request for Proposed Technical Specification (TS) Change TS-519 License Amendment Request - Change to License Condition 2.C(18)(a)32018-03-16016 March 2018 Request for Proposed Technical Specification (TS) Change TS-519 License Amendment Request - Change to License Condition 2.C(18)(a)3 ML18079B1402018-02-23023 February 2018 Browns Ferry Nuclear Plant, Units 1, 2, and 3: Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus NL-17-034, Application to Modify the Technical Specifications for Browns Ferry (TS-512), Sequoyah (TS-17-03), and Watts Bar (TS-17-20) to Resolve the Open Phase Issue Identified in NRC Bulletin 2012-01, Design Vulnerability in Electrical Power System2017-11-17017 November 2017 Application to Modify the Technical Specifications for Browns Ferry (TS-512), Sequoyah (TS-17-03), and Watts Bar (TS-17-20) to Resolve the Open Phase Issue Identified in NRC Bulletin 2012-01, Design Vulnerability in Electrical Power System. CNL-17-034, Application to Modify the Technical Specifications for Browns Ferry (TS-512), Sequoyah (TS-17-03), and Watts Bar (TS-17-20) to Resolve the Open Phase Issue Identified in NRC Bulletin 2012-01, Design Vulnerability in Electrical Power Syste2017-11-17017 November 2017 Application to Modify the Technical Specifications for Browns Ferry (TS-512), Sequoyah (TS-17-03), and Watts Bar (TS-17-20) to Resolve the Open Phase Issue Identified in NRC Bulletin 2012-01, Design Vulnerability in Electrical Power System. CNL-17-056, Application to Revise Technical Specification 5.5.12 Primary Containment Leakage Rate Testing Program (BFN-TS-497)2017-08-15015 August 2017 Application to Revise Technical Specification 5.5.12 Primary Containment Leakage Rate Testing Program (BFN-TS-497) CNL-17-014, Application to Revise Technical Specifications to Adopt Technical Specification Task Force (TSTF)-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Using the Consolidated Line Item Improvement Pro2017-04-0505 April 2017 Application to Revise Technical Specifications to Adopt Technical Specification Task Force (TSTF)-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Using the Consolidated Line Item Improvement Proce CNL-16-155, Application to Revise Technical Specifications to Adopt TSTF-545, Rev. 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, to Request Alternative to the ASME Code, and To..2017-01-17017 January 2017 Application to Revise Technical Specifications to Adopt TSTF-545, Rev. 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, to Request Alternative to the ASME Code, and To.. CNL-16-169, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 35, Consolidated Power Uprate Safety Analysis Report Revision2016-10-28028 October 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 35, Consolidated Power Uprate Safety Analysis Report Revision CNL-16-010, Application to Modify Technical Specification 4.3.1.2, Fuel Storage Criticality (TS-508)2016-08-12012 August 2016 Application to Modify Technical Specification 4.3.1.2, Fuel Storage Criticality (TS-508) CNL-16-016, License Amendment Request (BFN TS-509) to Change the Completion Date of Cyber Security Plan Implementation Milestone 82016-07-14014 July 2016 License Amendment Request (BFN TS-509) to Change the Completion Date of Cyber Security Plan Implementation Milestone 8 CNL-16-068, Update to License Amendment Request, Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limits (TS-506)2016-03-28028 March 2016 Update to License Amendment Request, Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limits (TS-506) CNL-15-056, Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limits (TS-506)2015-09-25025 September 2015 Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limits (TS-506) CNL-15-073, Application to Modify the Technical Specifications by Adding New Specification TS 3.3.8.3, Emergency Core Cooling System Preferred Pump Logic, Common Accident Signal (CAS) Logic, and Unit Priority Re-Trip Logic, And.2015-09-16016 September 2015 Application to Modify the Technical Specifications by Adding New Specification TS 3.3.8.3, Emergency Core Cooling System Preferred Pump Logic, Common Accident Signal (CAS) Logic, and Unit Priority Re-Trip Logic, And. CNL-15-074, Update to License Amendment Request to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants2015-06-19019 June 2015 Update to License Amendment Request to Adopt NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants CNL-15-029, License Amendment Request for the Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-535, Revision 0, Revise Shutdown Margin Definition to Address Advanced Fuel Designs (TS-502)2015-03-0909 March 2015 License Amendment Request for the Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-535, Revision 0, Revise Shutdown Margin Definition to Address Advanced Fuel Designs (TS-502) 2023-03-30
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January 31, 2006 10 CFR 54 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop: OWFN P1-35 Washington, D.C. 20555-0001 Gentlemen:
In the Matter of
) Docket Nos. 50-259 Tennessee Valley Authority ) 50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - UNITS 1, 2, AND 3 LICENSE RENEWAL APPLICATION (LRA) - ANNUAL UPDATE (TAC NOS. MC1704, MC1705, AND MC1706)
By letter dated December 31, 2003, TVA submitted, for NRC review, an application pursuant to 10 CFR 54 to renew the operating licenses for the Browns Ferry Nuclear Plant (BFN), Units 1, 2, and 3.
TVA is required by 10 CFR 54.21(b) to report changes annually to the BFN current licensing basis that materially affect the contents of the LRA, including the Updated Final Safety Analysis Report supplement.
TVA has completed a review of the pertinent documentation and identified changes which materially affect the contents of the BFN LRA. The enclosure to this letter contains the changes to the BFN LRA.
U.S. Nuclear Regulatory Commission Page 2 January 31, 2006 If you have any questions regarding this information, please contact Ken Brune, Browns Ferry License Renewal Project Manager, at (423) 751-8421.
I declare under penalty of perjury that the foregoing is true and correct. Executed on this 31 st day of January, 2006.
Sincerely, Original signed by Brian O'Grady
Enclosure:
cc: See page 3 U.S. Nuclear Regulatory Commission Page 3 January 31, 2006 Enclosure cc (Enclosure): State Health Officer Alabama Department of Public Health RSA Tower - Administration Suite 1552 P.O. Box 303017 Montgomery, Alabama 36130-3017 Chairman Limestone County Commission 310 West Washington Street Athens, Alabama 35611 (Via NRC Electronic Distribution)
Enclosure cc (Enclosure):
U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-8931 Mr. Stephen J. Cahill, Branch Chief U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-8931 NRC Senior Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611-6970 NRC Unit 1 Restart Senior Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611-6970 cc: continued page 4 U.S. Nuclear Regulatory Commission Page 4 January 31, 2006 cc: (Enclosure)
Margaret Chernoff, Project Manager U.S. Nuclear Regulatory Commission (MS 08G9)
One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 Eva A. Brown, Project Manager U.S. Nuclear Regulatory Commission (MS 08G9)
One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 Yoira K. Diaz-Sanabria, Project Manager U.S. Nuclear Regulatory Commission (MS 011F1)
One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 Ramachandran Subbaratnam, Project Manager U.S. Nuclear Regulatory Commission (MS 011F1)
One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739
ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNITS 1, 2, AND 3 LICENSE RENEWAL APPLICATION (LRA), ANNUAL UPDATE (SEE ATTACHED)
BROWNS FERRY NUCLEAR PLANT (BFN)
UNITS 1, 2, AND 3 LICENSE RENEWAL APPLICATION (LRA), ANNUAL UPDATE By letter dated December 31, 2003, TVA submitted, for NRC review, an application pursuant to 10 CFR 54, to renew the operating licenses for the Browns Ferry Nuclear Plant (BFN), Units 1, 2, and 3.
TVA is required by 10 CFR 54.21(b) to report changes annually to the BFN current licensing basis that materially affect the contents of the LRA, including the Updated Final Safety Analysis Report supplement.
Listed below are the changes which materially affect content of the BFN License Renewal Application.
CONDENSATE AND DEMINERALIZED WATER SYSTEM (002)
Plant modification removed components from scope on drawing 1-47E1847-4-LR. Therefore, drawing 1-47E1847-4-LR is no longer a Condensate and Demineralized Water System boundary drawing and is deleted from Section 2.3.4.2 on page 2.3-113. There are no changes to the component types, materials, or environments for this system as a result of these changes.
E-1 AUXILIARY BOILER SYSTEM (012)
Plant modification deleted cast iron valves. This deletes "Cast iron and cast iron alloy" from the materials listed in Section 3.3.2.1.1 on page 3.3-6 and also deletes the following line items from Table 3.3.2.1 on page 3.3-65:
Table 3.3.2.1: Auxiliary Boiler System (012) - Summary of Aging Management Evaluation Component Type Intended Function M a t e r i a l E n v i r o n m e n t Aging Effect Requiring Management Aging Management Program NUREG -1801 Vol. 2 Item Table 1 Item Notes V a l v e s P B Cast I r o n and Cast Iron Alloy Air/gas (internal) - moist air Loss of material due to selective leaching.
Selective Leaching of Materials Program (B.2.1.30)
V.D2.3-b N o n e F , 4 V a l v e s P B Cast I r o n and Cast Iron Alloy Air/gas (internal) - moist air Loss of material due to crevice, general, and pitting corrosion.
One-Time Inspection Program (B.2.1.29)
V.D2.3-b N o n e F , 2 V a l v e s P B Cast I r o n and Cast Iron Alloy Inside Air (external)
Loss of material due to general corrosion.
System Monitoring Program (B.2.1.39)
V.E.1-b N o n e F, 2 E-2 HIGH PRESSURE FIRE PROTECTION SYSTEM (026)
Plant modifications added Cast Austenitic Stainless Steel (CASS) material for Strainers and stainless steel material for Restricting Orifices. This adds the following line items and new Note D to Table 3.3.2.6 as shown below:
Table 3.3.2.6: High Pressure Fire Protection System (026) -
Summary of Aging Management Evaluation Component Type Intended Function M a t e r i a l E n v i r o n m e n t Aging Effect Requiring Management Aging Management Program NUREG -1801 Vol. 2 Item Table 1 Item Notes Restricting Orifice P B S t a i n l e s s Steel Inside Air (external)
N o n e N o n e VII.I.1-b N o n e F , 3 Restricting Orifice P B S t a i n l e s s Steel Raw Water (internal)
Loss of material due to biofouling, MIC, crevice, and pitting corrosion.
Fire Water System Program (B.2.1.24)
VII.G.6-a 3.3.1.21 D, 1 S t r a i n e r s P B S t a i n l e s s Steel-CASS Inside Air (external)
N o n e N o n e VII.I.1-b N o n e F , 3 Table Notes:
Industry Standard Notes
- Note D Component is different, but consistent with NUREG-1801 item for material, environment, and aging effect. The AMP takes some exceptions to NUREG-1801.
CONTROL AIR SYSTEM (032)
Plant modification added components in scope on drawings 1-47E1847-7-LR, 1-47E1847-8-LR, 2-47E2847-8-LR, and 3-47E3847-8-LR. Therefore, these drawings need to be added to the Control Air System boundary drawing list in Section 2.3.3.10 on page 2.3-56. There are no changes to the component types, materials, or environments for this system as a result of these h a n g e s. c EMERGENCY EQUIPMENT COOLING WATER SYSTEM (EECW) (067)
Plant modification added components in scope to drawing 1-47E1847-6-LR. Therefore, drawing 1-47E1847-6-LR is a new Emergency Equipment Cooling Water System boundary drawing and is being added to Section 2.3.3.20 on page 2.3-77. There are no changes to the component types, materials, or environments for this system as a result of these changes.
E-3 REACTOR WATER CLEANUP SYSTEM (069)
Plant modification deleted carbon steel valves from RCPB. This deletes the following line items from Table 3.3.2.21 on page 3.3-205: Table 3.3.2.21: Reactor Water Cleanup System (069) - Summary of Aging Management Evaluation Component Type Intended Function M a t e r i a l E n v i r o n m e n t Aging Effect Requiring Management Aging Management Program NUREG -1801 Vol. 2 Item Table 1 Item Notes Valves - RCPB P B C a r b o n and Low Alloy Steel Inside Air (external)
N o n e N o n e IV.C1.3-a N o n e G , 5 Valves - RCPB P B C a r b o n and Low Alloy Steel Treated Water (internal)
Loss of material due to crevice, general, galvanic, and pitting corrosion.
Chemistry Control Program (B.2.1.5)
One-Time Inspection Program (B.2.1.29)
IV.C1.3-a N o n e H , 4 Valves - RCPB P B C a r b o n and Low Alloy Steel Treated Water (internal)
Crack initiation/growth due to fatigue.
N o n e I V.C 1.3-d 3.1.1.1 A E-4 REACTOR BUILDING CLOSED COOLING WATER SYSTEM (070)
Plant modification added stainless steel as material type for heat exchangers. This adds the following line item to Table 3.3.2.22 as shown below:
Table 3.3.2.22: Reactor Building Closed Cooling Water System (070) -
Summary of Aging Management Evaluation Component Type Intended F u n c t i o n M a t e r i a l E n v i r o n m e n t Aging Effect Requiring Management Aging Management Program NUREG -1801 Vol. 2 Item Table 1 I t e m N o t e s Heat Exchangers P B S t a i n l e s s Steel Raw Water (internal)
Loss of material due to biofouling, MIC, crevice, and pitting corrosion.
Open-Cycle Cooling Water System Program (B.2.1.17)
N o n e N o n e J, 2 Heat Exchangers P B S t a i n l e s s Steel Treated Water (internal)
Loss of material due to crevice and pitting corrosion Closed-Cycle Cooling Water System Program (B.2.1.18)
N o n e N o n e J, 2 RADIATION MONITORING SYSTEM (090)
Plant modification added copper alloy as material type for tubing. This adds the following line items to Table 3.3.2.31 as shown below:
Table 3.3.2.31: Radiation Monitoring System (090) - Summary of Aging Management Evaluation Component Type Intended Function M a t e r i a l E n v i r o n m e n t Aging Effect Requiring Management Aging Management Program NUREG -1801 Vol. 2 Item Table 1 Item Notes T u b i n g P B C o p p e r Alloy Inside Air (external)
N o n e N o n e V.E.1-b N o n e F , 2 T u b i n g P B C o p p e r Alloy Air/Gas (internal)
N o n e N o n e N o n e N o n e J , 2 E-5 LICENSE RENEWAL BOUNDARY DRAWINGS License renewal boundary drawings have been maintained to reflect the current license renewal boundaries such that they are consistent with the LRA, RAI responses, change documentation, etc. Examples of some of the administrative changes made to the boundary drawings include:
The reference drawing interface arrows for piping runs are corrected as interfaces between drawings change.
Other valves and fittings are added on drawings; however, these changes do not impact the portion of the drawings that are in the license renewal boundary scope.
Changes in specific BFN Unit IDs (e.g., valve numbers are updated for a commodity that is already in scope.).
Leak off / drain valves are removed from the license renewal boundary drawings when they were found to be removed from the system. Components were added in scope on drawings but these changes did not add additional component types, materials, or environments that resulted in system changes that were not already contained in the LRA.
These drawing changes do not materially affect the contents of the LRA.
E-6 TIME LIMITED AGING ANALYSIS Some of the calculations associated with Section 4.3.4, Effects of Reactor Coolant Environment on Fatigue Life of Components and Piping (Generic Safety Issue 190), were revised to remedy errors found in the F en formulas.
As a result of revised calculations, several of the line items in Table 4.3.4.1 on page 4.3-8 have been revised. Replace existing Table 4.3.4.1 with revised Table 4.3.4.1 shown below:
Table 4.3.4.1 Summary of Environmental Fatigue Calculations for Browns Ferry Nuclear Plant N o. C o m p o n e n t M a t e r i a l CUF 40-Year Design CUF 60-Year* Overall Environment al Multiplier Environment al CUF Yea r 1 Reactor Ves sel Shell and L ower Head SA-302 (Low Alloy Steel) 0.0 3 2 0.0 0 0 3 2 5.0 9 0.0 0 8 2 Reactor Ves sel Feedwater N ozzle SA-508 (Low Alloy Steel) 0.7 0 0 0.0 9 5 1 0.5 0 0.9 9 8 Reactor Recirculati on Piping SA-358 Type 304 (Stainless Steel) 0.3 9 7 0.7 9 1 5.2 9 4.1 8 1 Reactor Recirculati on Outlet Nozz le SA-508 Class II (Low Alloy Steel) 0.0 4 5 0.0 6 8 1 4.6 7 0.9 9 6 3 Reactor Recirculati on Inlet Nozzl e SA-508 Class II (Low Alloy Steel) 0.2 0 6 0.1 0 4 9.5 8 0.9 9 5 Core Spray Nozzle Low Alloy Steel 0.0 7 3 0.0 6 2 1 6.0 3 0.9 9 1 4 Core Spray Nozzle Safe End Stainless Steel 0.0 0 6 0.0 0 5 1 5.3 5 0.0 8 3 E-7 N o. C o m p o n e n t M a t e r i a l CUF 40-Year Design CUF 60-Year* Overall Environment al Multiplier Environment al CUF Yea r 5 RHR Return Line Class 1 Pip ing SA-358 Type 304 (Stainless Steel) 0.0 3 2 0.0 4 2 1 5.3 5 0.6 4 4 6 Feedwater L ine Class 1 Pip ing SA-106 Grade B (Carbon Steel) 0.4 2 7 0.9 3 9 1.9 7 1.8 5 0
- The 60-ye ar C UF val ues were c alcu lated usin g anti cipa ted cy cles and r emov ing ana lysis cons ervati sms. E-8 UNIT 1 PERIODIC INSPECTION PROGRAM In Enclosure 2 of the TVA Letter to the NRC dated December 20, 2005, TVA committed to revising the Section 3 tables for the piping/fittings included in scope of the Unit 1 Periodic Inspection Program. The following provides the line items to be added to the Section 3 tables for the various systems.
MAIN STEAM SYSTEM (01)
The following line items and Notes are added to Table 3.4.2.1 for the Unit 1 Periodic Inspection Program:
Table 3.4.2.1: Main Steam System (01) - Summary of Aging Management Evaluation Component Type Intended Function M a t e r i a l E n v i r o n m e n t Aging Effect Requiring Management Aging Management Program NUREG -1801 Vol. 2 Item Table 1 Item Notes Fittings (Unit 1 Only) P B C a r b o n and Low Alloy Steel Treated Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E , 9 Fittings (Unit 1 Only) P B S t a i n l e s s Steel Treated Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E, 9 Piping (Unit 1 Only) P B C a r b o n and Low Alloy Steel Treated Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E , 9 Piping (Unit 1 Only) P B S t a i n l e s s Steel Treated Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E , 9 Table Notes:
Industry Standard Notes
- Note E Consistent with NUREG-1801 item for material, environment, and aging effect, a different AMP is credited.
Plant Specific Notes
- 9 Only specific to locations identified in TVA letter to the NRC concerning Unit 1 Lay-up Program dated May 18, 2005.
E-9 FEEDWATER SYSTEM (03)
The following line items and Notes are added to Table 3.4.2.3 for the Unit 1 Periodic Inspection Program:
Table 3.4.2.3: Feedwater System (03) - Summary of Aging Management Evaluation Component Type Intended Function M a t e r i a l E n v i r o n m e n t Aging Effect Requiring Management Aging Management Program NUREG -1801 Vol. 2 Item Table 1 Item Notes Fittings (Unit 1 Only) P B C a r b o n and Low Alloy Steel Treated Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E , 7 Fittings (Unit 1 Only) P B S t a i n l e s s Steel Treated Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E, 7 Piping (Unit 1 Only) P B C a r b o n and Low Alloy Steel Treated Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E , 7 Piping (Unit 1 Only) P B S t a i n l e s s Steel Treated Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E , 7 Table Notes:
Industry Standard Notes
- Note E Consistent with NUREG-1801 item for material, environment, and aging effect, a different AMP is credited.
Plant Specific Notes
- 7 Only specific to locations identified in TVA letter to the NRC concerning Unit 1 Lay-up Program dated May 18, 2005.
E-10 RESIDUAL HEAT REMOVAL SERVICE WATER SYSTEM (23)
The following line items and Notes are added to Table 3.3.2.3 for the Unit 1 Periodic Inspection Program:
Table 3.3.2.3: Residual Heat Removal Service Water System (23) -
Summary of Aging Management Evaluation Component Type Intended Function M a t e r i a l E n v i r o n m e n t Aging Effect Requiring Management Aging Management Program NUREG -1801 Vol. 2 Item Table 1 Item Notes Fittings (Unit 1 Only) P B C a r b o n and Low Alloy Steel Raw Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E , 9 Fittings (Unit 1 Only) P B S t a i n l e s s Steel Raw Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E, 9 Piping (Unit 1 Only) P B C a r b o n and Low Alloy Steel Raw Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E , 9 Piping (Unit 1 Only) P B S t a i n l e s s Steel Raw Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E , 9 Table Notes:
Plant Specific Notes
- Note E Consistent with NUREG-1801 item for material, environment, and aging effect, a different AMP is credit.
Plant Specific Notes
- 9 Only specific to locations identified in TVA letter to the NRC concerning Unit 1 Lay-up Program dated May 18, 2005.
E-11 RAW COOLING WATER SYSTEM (24)
The following line items and Notes are added to Table 3.3.2.4 for the Unit 1 Periodic Inspection Program:
Table 3.3.2.4: Raw Cooling Water System (24) - Summary of Aging Management Evaluation Component Type Intended Function M a t e r i a l E n v i r o n m e n t Aging Effect Requiring Management Aging Management Program NUREG -1801 Vol. 2 Item Table 1 Item Notes Fittings (Unit 1 Only) P B C a r b o n and Low Alloy Steel Raw Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E , 1 0 Fittings (Unit 1 Only) P B S t a i n l e s s Steel Raw Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E, 10 Piping (Unit 1 Only) P B C a r b o n and Low Alloy Steel Raw Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E , 1 0 Piping (Unit 1 Only) P B S t a i n l e s s Steel Raw Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E , 1 0 Table Notes:
Industry Standard Notes
- Note E Consistent with NUREG-1801 item for material, environment, and aging effect, a different AMP is credit.
Plant Specific Notes
- 10 Only specific to locations identified in TVA letter to the NRC concerning Unit 1 Lay-up Program dated May 18, 2005.
E-12 HIGH PRESSURE FIRE PROTECTION SYSTEM (26)
The following line items and Notes are added to Table 3.3.2.6 for the Unit 1 Periodic Inspection Program:
Table 3.3.2.6: High Pressure Fire Protection System (26) - Summary of Aging Management Evaluation Component Type Intended Function M a t e r i a l E n v i r o n m e n t Aging Effect Requiring Management Aging Management Program NUREG -1801 Vol. 2 Item Table 1 Item Notes Fittings (Unit 1 Only) P B C a r b o n and Low Alloy Steel Raw Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E , 9 Fittings (Unit 1 Only) P B S t a i n l e s s Steel Raw Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E, 9 Piping (Unit 1 Only) P B C a r b o n and Low Alloy Steel Raw Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E , 9 Piping (Unit 1 Only) P B S t a i n l e s s Steel Raw Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E , 9 Table Notes:
Industry Standard Notes
- Note E Consistent with NUREG-1801 item for material, environment, and aging effect, a different AMP is credit.
Plant Specific Notes
- 9 Only specific to locations identified in TVA letter to the NRC concerning Unit 1 Lay-up Program dated May 18, 2005.
E-13 EMERGENCY EQUIPMENT COOLING WATER SYSTEM (67)
The following line items and Notes are added to Table 3.3.2.20 for the Unit 1 Periodic Inspection Program:
Table 3.3.2.20: Emergency Equipment Cooling Water System (67) -
Summary of Aging Management Evaluation Component Type Intended Function M a t e r i a l E n v i r o n m e n t Aging Effect Requiring Management Aging Management Program NUREG -1801 Vol. 2 Item Table 1 Item Notes Fittings (Unit 1 Only) P B C a r b o n a n d Low Alloy Steel Raw Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E , 5 Fittings (Unit 1 Only) P B S t a i n l e s s Steel Raw Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E, 5 Piping (Unit 1 Only) P B C a r b o n a n d Low Alloy Steel Raw Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E , 5 Piping (Unit 1 Only) P B S t a i n l e s s Steel Raw Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E , 5 Table Notes:
Industry Standard Notes
- Note E Consistent with NUREG-1801 item for material, environment, and aging effect, a different AMP is credit.
Plant Specific Notes
- 5 Only specific to locations identified in TVA letter to the NRC concerning Unit 1 Lay-up Program dated May 18, 2005.
E-14 REACTOR BUILDING CLOSED COOLING WATER SYSTEM (70)
The following line items and Notes are added to Table 3.3.2.22 for the Unit 1 Periodic Inspection Program:
Table 3.3.2.22: Reactor Building Closed Cooling Water System (70) -
Summary of Aging Management Evaluation Component Type Intended Function M a t e r i a l E n v i r o n m e n t Aging Effect Requiring Management Aging Management Program NUREG -1801 Vol. 2 Item Table 1 Item Notes Fittings (Unit 1 Only) P B C a r b o n and Low Alloy Steel Treated Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E , 5 Fittings (Unit 1 Only) P B S t a i n l e s s Steel Treated Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E, 5 Piping (Unit 1 Only) P B C a r b o n and Low Alloy Steel Treated Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E , 5 Piping (Unit 1 Only) P B S t a i n l e s s Steel Treated Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E , 5 Table Notes:
Industry Standard Notes
- Note E Consistent with NUREG-1801 item for material, environment, and aging effect, a different AMP is credited.
Plant Specific Notes
- 5 Only specific to locations identified in TVA letter to the NRC concerning Unit 1 Lay-up Program dated May 18, 2005.
E-15 REACTOR CORE ISOLATION COOLING SYSTEM (71)
The following line items and Notes are added to Table 3.3.2.23 for the Unit 1 Periodic Inspection Program:
Table 3.3.2.23: Reactor Core Isolation Cooling System (71) - Summary of Aging Management Evaluation Component Type Intended Function M a t e r i a l E n v i r o n m e n t Aging Effect Requiring Management Aging Management Program NUREG -1801 Vol. 2 Item Table 1 Item Notes Fittings (Unit 1 Only) P B C a r b o n and Low Alloy Steel Treated Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E , 8 Fittings (Unit 1 Only) P B S t a i n l e s s Steel Treated Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E, 8 Piping (Unit 1 Only) P B C a r b o n and Low Alloy Steel Treated Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E , 8 Piping (Unit 1 Only) P B S t a i n l e s s Steel Treated Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E , 8 Table Notes:
Industry Standard Notes
- Note E Consistent with NUREG-1801 item for material, environment, and aging effect, a different AMP is credited.
Plant Specific Notes
- 8 Only specific to locations identified in TVA letter to the NRC concerning Unit 1 Lay-up Program dated May 18, 2005.
E-16 HIGH PRESSURE COOLANT INJECTION SYSTEM (73)
The following line items and Notes are added to Table 3.2.2.3 for the Unit 1 Periodic Inspection Program:
Table 3.2.2.3: High Pressure Coolant Injection System (73) - Summary of Aging Management Evaluation Component Type Intended Function M a t e r i a l E n v i r o n m e n t Aging Effect Requiring Management Aging Management Program NUREG -1801 Vol. 2 Item Table 1 Item Notes Fittings (Unit 1 Only) P B C a r b o n and Low Alloy Steel Treated Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E , 9 Fittings (Unit 1 Only) P B S t a i n l e s s Steel Treated Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E, 9 Piping (Unit 1 Only) P B C a r b o n and Low Alloy Steel Treated Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E , 9 Piping (Unit 1 Only) P B S t a i n l e s s Steel Treated Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E , 9 Table Notes:
Industry Standard Notes
- Note E Consistent with NUREG-1801 item for material, environment, and aging effect, a different AMP is credited.
Plant Specific Notes
- 9 Only specific to locations identified in TVA letter to the NRC concerning Unit 1 Lay-up Program dated May 18, 2005.
E-17 RESIDUAL HEAT REMOVAL SYSTEM (74)
The following line items and Notes are added to Table 3.2.2.4 for the Unit 1 Periodic Inspection Program:
Table 3.2.2.4: Residual Heat Removal System (74) - Summary of Aging Management Evaluation Component Type Intended Function M a t e r i a l E n v i r o n m e n t Aging Effect Requiring Management Aging Management Program NUREG -1801 Vol. 2 Item Table 1 Item Notes Fittings (Unit 1 Only) P B C a r b o n and Low Alloy Steel Treated Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E , 7 Fittings (Unit 1 Only) P B S t a i n l e s s Steel Treated Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E, 7 Piping (Unit 1 Only) P B C a r b o n and Low Alloy Steel Treated Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E , 7 Piping (Unit 1 Only) P B S t a i n l e s s Steel Treated Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E , 7 Table Notes:
Plant Specific Notes
- Note E Consistent with NUREG-1801 item for material, environment, and aging effect, a different AMP is credited.
Plant Specific Notes
- 7 Only specific to locations identified in TVA letter to the NRC concerning Unit 1 Lay-up Program dated May 18, 2005.
E-18 CORE SPRAY SYSTEM (75)
The following line items and Notes are added to Table 3.2.2.5 for the Unit 1 Periodic Inspection Program:
Table 3.2.2.5: Core Spray System (75) - Summary of Aging Management Evaluation Component Type Intended Function M a t e r i a l E n v i r o n m e n t Aging Effect Requiring Management Aging Management Program NUREG -1801 Vol. 2 Item Table 1 Item Notes Fittings (Unit 1 Only) P B C a r b o n and Low Alloy Steel Treated Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E , 9 Fittings (Unit 1 Only) P B S t a i n l e s s Steel Treated Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E, 9 Piping (Unit 1 Only) P B C a r b o n and Low Alloy Steel Treated Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E , 9 Piping (Unit 1 Only) P B S t a i n l e s s Steel Treated Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E , 9 Table Notes:
Industry Standard Notes
- Note E Consistent with NUREG-1801 item for material, environment, and aging effect, a different AMP is credited.
Plant Specific Notes
- 9 Only specific to locations identified in TVA letter to the NRC concerning Unit 1 Lay-up Program dated May 18, 2005.
E-19 CONTROL ROD DRIVE SYSTEM (85)
The following line items and Notes are added to Table 3.3.2.29 for the Unit 1 Periodic Inspection Program:
Table 3.3.2.29: Control Rod Drive System (85) - Summary of Aging Management Evaluation Component Type Intended Function M a t e r i a l E n v i r o n m e n t Aging Effect Requiring Management Aging Management Program NUREG -1801 Vol. 2 Item Table 1 Item Notes Fittings (Unit 1 Only) P B C a r b o n and Low Alloy Steel Treated Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E , 8 Fittings (Unit 1 Only) P B S t a i n l e s s Steel Treated Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E, 8 Piping (Unit 1 Only) P B C a r b o n and Low Alloy Steel Treated Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E , 8 Piping (Unit 1 Only) P B S t a i n l e s s Steel Treated Water (internal)
Loss of material Unit 1 Periodic Inspection Program (B.2.1.42)
N o n e N o n e E , 8 Table Notes:
Industry Standard Notes
- Note E Consistent with NUREG-1801 item for material, environment, and aging effect, a different AMP is credited.
Plant Specific Notes
- 8 Only specific to locations identified in TVA letter to the NRC concerning Unit 1 Lay-up Program dated May 18, 2005.
E-20