Letter Sequence Request |
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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, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Administration
- Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance
- Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting
Results
Other: ML070370281, ML073100027, ML073510180, ML080360067, ML080430700, ML080500171, ML080530256, ML081010450, ML081010451, ML081120502, ML081700294, ML081720078, ML081760295, ML082040065, ML082050462, ML082100425, ML082810470, ML083120308, ML083240224, ML083250083, ML090130718, ML090340528, ML090720951, ML090760630, ML091320366, ML092020345, ML092430520, ML092440518, ML092460495, ML092460496, ML092460497, ML092460498, ML092460500, ML092540483, ML092680057, ML12319A076, ML13044A498
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MONTHYEARML0711503712007-04-24024 April 2007 Technical Specifications (TS) Changes TS-431 and TS-418 - Extended Power Uprate (EPU) - Steam Dryer Evaluations Project stage: Request ML0712905652007-05-16016 May 2007 Withholding Information from Public Disclosure, Response to Nuclear Regulatory Commission (NRC) Request for Additional Information - Round 12 for Browns Ferry EPU: Supplemental to SBWB-64 Project stage: RAI ML0716303492007-06-15015 June 2007 Meeting with the Tennessee Valley Authority Concerning the Status of Browns Ferry Nuclear Plant, Units 1, 2 and 3, Steam Dryer Review Project stage: Meeting ML0718700242007-07-0303 July 2007 Technical Specifications (TS) Change TS-461 - Modification of Restart Large Transient Testing License Condition 2. (G) 2 - Supplement 1 Project stage: Request ML0717801902007-07-0505 July 2007 Request for Additional Information for Extended Power Uprate - Round 13 (TS-431 and TS-418 (TAC Nos. MD5262, MD5263, and MD5264) Project stage: RAI ML0719004762007-07-10010 July 2007 Meeting with the Tennessee Valley Authority (TVA) Concerning the Pending ACRS Meeting on the Browns Ferry Extended Power Uprate Project stage: Meeting ML0721501562007-07-18018 July 2007 Slides from Meeting with Tennessee Valley Authority on the Browns Ferry Power Uprate ACRS Presentation Project stage: Meeting ML0721303712007-07-27027 July 2007 Technical Specifications Changes TS-431 and TS-418, Extended Power Uprate - Steam Dryer Evaluations Project stage: Request ML0721400442007-08-0808 August 2007 Summary of Meeting with Tennessee Valley Authority on the Browns Ferry Power Uprate ACRS Presentation Project stage: Meeting ML0724805472007-08-31031 August 2007 Technical Specifications (TS) Changes TS-431 and TS-418 - Extended Power Uprate (EPU) - Response to Round 13 Request for Additional Information (RAI) - Containment Overpressure Project stage: Request ML0727606602007-10-0909 October 2007 Request for Additional Information for Extended Power Uprate - Round 14 (TS-418) Project stage: RAI ML0728902372007-10-18018 October 2007 Request for Withholding Information from Public Disclosure Concerning Round 13 Request for Additional Information for Browns Ferry Nuclear Plant (Tac Nos. MD5262, MD5263 and MD5264) Project stage: RAI ML0729603112007-10-22022 October 2007 Technical Specification (TS) Changes TS-431 & TS-418, Extended Power Uprate - EPU Large Transient Testing Project stage: Request ML0731000272007-11-0909 November 2007 Request for Schedule Regarding Analysis for Steam Dryers on Extended Power Uprate Amendment Requests (TAC Nos. MD5262, MD5263, and MD5264) (TS-431 and TS-418-S) Project stage: Other ML0732303482007-11-15015 November 2007 Units 1, 2, and 3 - Technical Specifications (TS) Changes TS-431 and TS-418 - Extended Power Uprate (EPU) - Response to Round 13 Request for Additional Information (RAI) - Containment Overpressure APLA-35/37 Project stage: Request ML0733304832007-11-21021 November 2007 Technical Specifications (TS) Changes TS-431 and TS-418 - Extended Power Uprate (EPU) - Response to Preliminary Findings on Steam Dryer Stress Analysis Project stage: Request ML0735101802007-12-14014 December 2007 Technical Specifications Changes TS-431 and TS-418 - Extended Power Uprate - Schedule Regarding Analysis for Steam Dryers Project stage: Other ML0734607572007-12-19019 December 2007 Request for Withholding Information from Public Disclosure for Browns Ferry Nuclear Plant (Tac No. MD5262, MD5263 and MD5264) Project stage: Withholding Request Acceptance ML0735400102008-01-25025 January 2008 Summary of Meeting with Tennessee Valley Authority on Steam Dryer Portion of the Extended Power Uprate Review (TAC Nos. MD5262, MD5263, and MD5264), Browns Ferry Units 1, 2, and 3 Project stage: Meeting ML0801504182008-01-25025 January 2008 Plants, Units 1, 2, and 3 - (Public Version) - Summary of December 10, 2007 Meeting with TVA on Steam Dryer Portion of the Extended Power Uprate Review Project stage: Meeting ML0803205212008-01-25025 January 2008 Technical Specifications (TS) Changes TS-431 and TS-418 - Extended Power Uprate (EPU) Response to Round 15 Request for Additional Information (RAI) - APLA-38/40, SRXB-71, and SRXB-72 Project stage: Request ML0803600672008-01-25025 January 2008 Steam Dryer RAI 15 Status, Slides Project stage: Other ML0802501652008-01-30030 January 2008 Request for Withholding Information from Public Disclosure for Browns Ferry Nuclear Plant (Tac Nos. MD5262, MD5263, and MD5264) Project stage: Withholding Request Acceptance ML0803805602008-01-31031 January 2008 Technical Specifications (TS) Change TS-431 and TS-418 - Extended Power Uprate (EPU) - Response to Round 15 Request for Additional Information (RAI) Regarding Steam Dryer Analyses Project stage: Request ML0804307002008-02-11011 February 2008 Technical Specifications (TS) Changes TS-431 and TS-418 - Extended Power Uprate (EPU) - Schedule Regarding EPU Project stage: Other ML0803503812008-02-14014 February 2008 Summary of Meeting with Tennessee Valley Authority - on Extended Power Uprate Review Project stage: Meeting ML0805302562008-02-21021 February 2008 Unit 1 - Technical Specifications (TS) Change TS-431 - Extended Power Uprate (EPU) - Fuels Methods Commitments Project stage: Other ML0806501012008-02-21021 February 2008 Response to Round 16 Request for Additional Information SRXB-73 Project stage: Request ML0804506472008-02-27027 February 2008 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML0803506982008-02-29029 February 2008 Request for Additional Information for Extended Power Uprate - Round 16 (TS-431 and TS-418) (TACs MD5262, MD5263, MD5264) Project stage: RAI ML0807104982008-03-0606 March 2008 (BFN) - Units 1, 2, and 3 - Technical Specifications (TS) Change TS-418 and TS-431 - Extended Power Uprate (EPU) - Response to Round 16 Request for Additional Information (RAI) - SRXB-74/86 and SRXB-87 Through SRXB-90 Project stage: Request ML0811205102008-03-20020 March 2008 Summary of March 20, 2008, Meeting with Tennessee Valley Authority Regarding Steam Dryer Portion of the Extended Power Uprate Review (TAC Nos. MD5262, MD5263, and MD5264) - Slides Project stage: Meeting ML0810104512008-04-0404 April 2008 Technical Specifications (TS) Changes TS-431 and TS-418 Extended Power Uprate (EPU) BFN Steam Monitoring Plan Project stage: Other ML0810104502008-04-0404 April 2008 (BFN) - Units 1, 2, and 3 - Technical Specifications (TS) Changes TS-431 and TS-418 - Extended Power Uprate (EPU) - Response to Round 15 and Round 16 Requests for Additional Information (RAI) Regarding Steam Dryer Analyses Project stage: Other ML0817602952008-04-0909 April 2008 Units 1, 2, & 3 - Technical Specifications Changes TS-431 and TS-418 - Extended Power Uprate - Confirmation of Commitment Completions Project stage: Other ML0811205022008-04-16016 April 2008 CDI Incoming Letter Dated April 16, 2008 Regarding NRC Presentation Entitled, Tennessee Valley Authority Browns Ferry Nuclear Plant - Extended Power Uprate Steam Dryers. Project stage: Other ML0811302312008-04-17017 April 2008 Public Slides - Summary of April 17, 2008, Meeting Regarding Steam Dryer Portion of the Extended Power Uprate Review, Project stage: Meeting ML0811200332008-04-30030 April 2008 Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Withholding Information from Public Disclosure for Round 15 Fuels Responses Project stage: Withholding Request Acceptance ML0812806272008-05-0101 May 2008 Technical Specifications Change TS-418, Extended Power Uprate Supplemental Response to Round 16 Request for Additional Information - SRXB-87 & SRXB-89 Project stage: Supplement ML0813502222008-05-0202 May 2008 Request for Additional Information for Extended Power Uprate - Round 17 (TS-431 and TS-410) Project stage: RAI ML0805001712008-05-0202 May 2008 - Schedule Regarding Analysis for Steam Dryers on Extended Power Uprate Amendment Requests (TAC Nos. MD5262, MD5263, and MD5264) (TS-431 and TS-418) Project stage: Other ML0812804712008-05-0202 May 2008 Request for Additional Information for Extended Power Uprate - Round 17 Project stage: RAI ML0813602912008-05-22022 May 2008 Summary of April 17, 2008, Meeting Regarding Steam Dryer Portion of the Extended Power Uprate Review Project stage: Meeting ML0815805532008-05-22022 May 2008 Summary of 5/22/08 Meeting Regarding Containment Overpressure Portion of the Extended Power Uprate Review - Browns Ferry - Handouts Project stage: Meeting ML0810604452008-06-0202 June 2008 Request for Withholding Information from Public Disclosure for Partial Round 13 Responses (Tacs. MD5262, MD5263 and MD5264) Project stage: Withholding Request Acceptance ML0810606162008-06-0202 June 2008 Request for Withholding Information from Public Disclosure for Browns Ferry Nuclear Plant Project stage: Withholding Request Acceptance ML0810607222008-06-0202 June 2008 Request for Withholding Information from Public Disclosure for Partial Response to Round 13 Project stage: Withholding Request Acceptance ML0816403252008-06-0303 June 2008 Units 2 & 3 - Technical Specifications Change TS-418 - Extended Power Uprate - Supplemental Response to Round 16 Request for Additional Information - SRXB-88 Project stage: Supplement ML0812607122008-06-0505 June 2008 Summary of Meeting with TVA Steam Dryer Portion of the Extended Power Uprate Review Project stage: Meeting ML0817002942008-06-12012 June 2008 Technical Specifications Changes TS-431 and TS-418 - Extended Power Uprate - Response to ACRS Conclusions and Recommendations Regarding Containment Overpressure Credit Project stage: Other 2008-01-30
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Category:Calculation
MONTHYEARML24122A6852024-05-0101 May 2024 2023 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual ML16123A1492016-04-30030 April 2016 Transmittal of 2015 Annual Radioactive Effluent Release Report, and Revisions 22 and 23 to the Offsite Dose Calculation Manual CNL-14-068, (Bfn), Units 1, 2 and 3 - Supplement to Proposed Technical Specification Change to Revise the Leakage Rate Through MSIVs (TS-485)2015-01-29029 January 2015 (Bfn), Units 1, 2 and 3 - Supplement to Proposed Technical Specification Change to Revise the Leakage Rate Through MSIVs (TS-485) ML14015A4042013-11-22022 November 2013 Attachment 6 - NDQ099920010019 - Ex-Containment Removal Coefficients for Alternative Source Term Analyses, Through Attachment 11 - List of Regulatory Commitments ML12123A0182011-07-0505 July 2011 0-ODCM-001, Revision 0021, Offsite Dose Calculation Manual, Enclosure 5 ML1012604712010-04-30030 April 2010 Enclosure 5, Browns Ferry Nuclear Plant Offsite Dose Calculation Manual 0-OCDM-001, Revision 20 ML0924604982009-08-19019 August 2009 Calculation Package 0900833.302, Rev. 0, Steam Dryer Hood Stiffener Stress Relief Modification Stress Reduction Factor (Srf) Computation, Enclosure 4 ML0912802642009-04-30030 April 2009 Offsite Dose Calculation Manual 0-ODCM-001, Revision 0019 ML0910002912009-04-0303 April 2009 (BFN) - Unit 1 - Technical Specifications (TS) Change TS-431 - Extended Power Uprate (EPU) - Response to Round 23 Request for Additional Information (RAI) EMCB.205 and EMCB.206 ML0918201692009-01-27027 January 2009 Letter from F. Godwin, TVA to NRC on Browns Ferry Proposed Request for Exemption from 10 CFR 50, Appendix R. Paragraph lll.G.2, Fire Protection of Safe Shutdown Capacity ML0902203942009-01-0808 January 2009 Response to Round 23 RAI Technical Specifications Changes TS-431 and TS-418, Extended Power Uprate, Enclosure 2 - Structural Integrity Associates, Inc. Calculation Package 0006982.304, Revision 1 and Encls 4 and 5 ML0831203082008-10-30030 October 2008 Calculation Package 0006982.304, Extended Power Uprate Main Steam Line Strain Gauge Vibration Monitoring. ML0817500812008-06-16016 June 2008 Encl. 6, Calculation Package 0006982.301, Extended Power Uprate Main Steam Line Strain Gage Vibration Monitoring, and Encl. 7, Response to Round 15 Group 4 and Round 17 Request for Additional Information ML0721304152007-07-31031 July 2007 CDI Report No. 07-11NP, Revision 0, Dynamics of BWR Steam Dryer Components ML0721303752007-07-31031 July 2007 CDI Report No. 07-05NP, Revision 0, Finite Element Model for Stress Assessment of Browns Ferry, Unit 1, Steam Dryer to 250 Hz ML0721303822007-07-31031 July 2007 CDI Report No. 07-06NP, Revision 0, Finite Element Model for Stress Assessment of Browns Ferry, Unit 2 & 2 Steam Dryer to 250 Hz ML0721304012007-07-31031 July 2007 CDI Report No. 07-10NP, Revision 0, Acoustic and Low Frequency Hydrodynamic Loads at CLTP Power Level on Browns Ferry, Unit 2, Steam Dryer to 250 Hz ML0721304292007-07-31031 July 2007 C.D.I. Technical Memorandum No. 07-26NP, Revision 0, Comparison of Browns Ferry Unit 1 & Unit 2 Main Steam Line Strain Gage / Pressure Readings ML0721303862007-07-31031 July 2007 CDI Report No. 07-09NP, Revision 0, Methodology to Predict Full Scale Steam Dryer Loads from In-Plant Measurements, with Inclusion of a Low Frequency Hydrodynamic Contribution ML0625103822006-08-21021 August 2006 Enclosure 2, Browns Ferry, Units 1, 2 & 3 - Calculation MDQ099920060011, Revision 1, Transient Npsh/Containment Pressure Evaluation of RHR and Core Spray Pumps. ML0625103742006-08-21021 August 2006 Enclosure 1, Browns Ferry, Units 1, 2 & 3 - Calculation MDQ0999970046, Rev 10, NPSH Evaluation of Browns Ferry RHR and CS Pumps. ML0622300632006-08-0404 August 2006 Calculation MDQ099920060011, Rev. 0, Transient Npsh/Containment Pressure Evaluation of RHR and Core Spray Pumps. ML0622300582006-08-0404 August 2006 Calculation MDQ099970046, Rev. 9, NPSH Evaluation of Browns Ferry RHR and CS Pumps. ML0608804692006-03-23023 March 2006 Calculation MDQ0999970046 NPSH Evaluation of Browns Ferry RHR and CS Pumps ML0608804152006-03-0909 March 2006 Calculation MDQ0999970046, Rev. 008, NPSH Evaluation of Browns Ferry RHR and CS Pumps ML0512506002005-04-28028 April 2005 Offsite Dose Calculation Manual, Revision 0016 ML0507703702005-03-11011 March 2005 Technical Specifications (TS) Change TS-447, Request for Additional Information (RAI) - Extension of Channel Calibration Surveillance Requirement Performance Frequency and Allowable Value Revision ML0612206472005-02-0404 February 2005 Offsite Dose Calculation Manual, Revision 17 ML0603806772004-06-0909 June 2004 TVA Calculation CDQ1 074 2004 0160, Rev 0, HCLPF Calculations of RHR Heat Exchanger Anchorage for Seismic IPEEE Program. ML0603806762004-06-0909 June 2004 TVA Calculation CDQ1 999 2004 0156, Rev. 0, HCLPF Calculations of MCC Anchorage for Seismic IPEEE Program. ML0614405592004-03-0606 March 2004 Enclosure 5, Browns Ferry, Units 1, 2 & 3 - Changes to the Offsite Dose Calculation Manual 2004, Rev 16 ML0424500612004-03-0404 March 2004 Calculation CDN1-000-2004, Seismic Verification of Condenser and Its Anchorage, MSIV Ruggedness Seismic Analysis - Resolution of Pos 15-1. ML0603806721996-06-14014 June 1996 Calculation CD-Q0000-940339, Rev. 1, Calculation of Basic Parameters for A46 and Individual Plant Examination of External Events (IPEEE) Seismic Program. 2024-05-01
[Table view] Category:Letter
MONTHYEARIR 05000259/20240032024-11-0404 November 2024 Integrated Inspection Report 05000259/2024003 and 05000260/2024003 and 05000296/2024003 CNL-24-043, Application for Subsequent Renewed Operating Licenses, Second Safety Supplement2024-11-0101 November 2024 Application for Subsequent Renewed Operating Licenses, Second Safety Supplement ML24305A1692024-10-31031 October 2024 Site Emergency Plan Implementing Procedure Revision 05000259/LER-2024-003, Valid Specified System Actuation Caused the Automatic Start of Emergency Diesel Generators2024-10-29029 October 2024 Valid Specified System Actuation Caused the Automatic Start of Emergency Diesel Generators 05000259/LER-2024-001-02, Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure2024-10-28028 October 2024 Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure ML24299A2632024-10-25025 October 2024 Response to Apparent Violation in NRC Inspection Report 05000260/2024090, EA-24-075 ML24289A1232024-10-24024 October 2024 Letter to James Barstow Re Environmental Scoping Summary Report for Browns Ferry CNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24308A0042024-10-16016 October 2024 Ahc 24-1578 Environmental Review of the Browns Ferry Nuclear Plant, Units 1, 2 and 3 Subsequent License Renewal Application Limestone County CNL-24-077, Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 12024-10-0909 October 2024 Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 1 ML24270A2162024-09-27027 September 2024 Notice of Intentions Regarding Preliminary Finding from NRC Inspection Report 05000260/2024090, EA-24-075 CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description ML24262A1502024-09-24024 September 2024 Requalification Program Inspection - Browns Ferry Nuclear Plant ML24262A0602024-09-23023 September 2024 Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan ML24263A2952024-09-19019 September 2024 Site Emergency Plan Implementing Procedure Revision CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000260/20240902024-09-17017 September 2024 NRC Inspection Report 05000260/2024090 and Preliminary White Finding and Apparent Violation - 1 CNL-24-062, Cycle 16 Reload Analysis Report2024-09-16016 September 2024 Cycle 16 Reload Analysis Report ML24255A8862024-09-10010 September 2024 Core Operating Limits Report for Cycle 16 Operation, Revision 0 ML24239A3332024-09-0303 September 2024 Full Audit Plan IR 05000259/20244042024-09-0303 September 2024 Cyber Security Inspection Report 05000259/2024404 and 05000260-2024404 and 05000296/2024404-Cover Letter IR 05000259/20240052024-08-26026 August 2024 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2024005, 05000260/2024005 and 05000296/2024005 ML24225A1682024-08-16016 August 2024 – Notification of Inspection and Request IR 05000259/20244022024-08-0606 August 2024 Security Baseline Inspection Report 05000259/2024402 and 05000260/2024402 and 05000296/2024402 ML24219A0272024-08-0606 August 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000259/20240022024-08-0202 August 2024 Brown Ferry Nuclear Plant – Integrated Inspection Report05000259/2024002 and 05000260/2024002 and 05000296/2024002 ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter ML24183A4142024-07-10010 July 2024 – License Renewal Regulatory Limited Scope Audit Regarding the Environmental Review of the License Renewal Application (EPID Number: L-2024-SLE-0000) (Docket Numbers: 50-259, 50-260, and 50-296) 05000296/LER-2024-003, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints2024-07-0808 July 2024 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints 05000259/LER-2024-001-01, Inoperability of Unit 3 Diesel Generator Due to Relay Failure2024-07-0303 July 2024 Inoperability of Unit 3 Diesel Generator Due to Relay Failure ML24184A1142024-07-0202 July 2024 Site Emergency Plan Implementing Procedure Revision ML24183A3842024-07-0101 July 2024 Registration of Use of Cask to Store Spent Fuel (MPC-364, -365) ML24179A0282024-06-26026 June 2024 Evaluation of Effects of Out-of-Limits Condition as Described in IWB-3720(a) 05000259/LER-2024-002, Reactor Scram Due to Generator Step-Up Transformer Failure2024-06-24024 June 2024 Reactor Scram Due to Generator Step-Up Transformer Failure ML24175A0042024-06-23023 June 2024 Interim Report of a Deviation or Failure to Comply Associated with a Valve in the Unit 3 High Pressure Coolant Injection System ML24176A1132024-06-23023 June 2024 American Society of Mechanical Engineers, Section XI, Fourth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner’S Activity Report Cycle 21 Oper ML24089A1152024-06-21021 June 2024 Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2) ML24155A0042024-06-18018 June 2024 Proposed Alternative to the Requirements of the ASME Code (Revised Alternative Request 0-ISI-47) ML24158A5312024-06-0606 June 2024 Registration of Use of Cask to Store Spent Fuel (MPC-361, -362, -363) ML24071A0292024-06-0505 June 2024 Subsequent License Renewal Application Enclosure 3 - Proprietary Determination Letter ML24068A2612024-06-0505 June 2024 SLRA Fluence Methodology Report - Proprietary Determination Letter IR 05000259/20244032024-05-22022 May 2024 – Security Baseline Report 05000259/2024403 and 05000260/2024403 and 05000296/2024403 05000260/LER-2024-002, High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation2024-05-20020 May 2024 High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24136A0702024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report IR 05000259/20240012024-05-14014 May 2024 Integrated Inspection Report 05000259/2024001, 05000260/2024001, and 05000296/2024001 CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24123A2012024-05-0202 May 2024 NRC Cybersecurity Baseline Inspection (NRC Inspection Report 05000259/2024404, 05000260-2024404, 05000296/2024404) and Request for Information ML24122A6852024-05-0101 May 2024 2023 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual 2024-09-03
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Text
Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 April 3, 2009 TVA-BFN-TS-431 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop OWFN, P1-35 Washington, D. C. 20555-0001 In the Matter of ) Docket Nos. 50-259 Tennessee Valley Authority )
BROWNS FERRY NUCLEAR PLANT (BFN) - UNIT 1 - TECHNICAL SPECIFICATIONS (TS) CHANGE TS-431 - EXTENDED POWER UPRATE (EPU) - RESPONSE TO ROUND 23 REQUEST FOR ADDITIONAL INFORMATION (RAI) EMCB.205 AND EMCB.206 (TAC NO. MD5262)
By letter dated June 28, 2004 (ADAMS Accession No. ML041840109), TVA submitted a license amendment application to NRC for the EPU of BFN Unit 1. The proposed amendment would change the operating license to increase the maximum authorized core thermal power level by approximately 14 percent to 3952 megawatts. provides the responses for draft Round 23 RAIs EMCB.205 and EMCB.206 which were received by e-mail dated March 23, 2009. These RAIs are associated with the steam dryer stress analyses performed for EPU. As described in the response to EMCB.205, the Unit 1 limit curves have been revised and are provided in Enclosure 2, CDI Technical Note No.07-30P, "Limit Curve Analysis with ACM Rev. 4 for Power Ascension at Browns Ferry Nuclear Unit 1." provides a revision to CDI Report No.08-04P, "Acoustic and Low Frequency Hydrodynamic Loads at CLTP Power Level on Browns Ferry Nuclear Unit 1 Steam Dryer to 250 Hz." This revision updates Reference 5 from the 1/5 Scale Model Test (SMT) report to the 1/8 SMT report. The 1/5 SMT was a preliminary test to determine if safety relief valve resonance onset is possible within the EPU operating range. Based on the results of the 1/5 SMT, the 1/8 SMT was performed to help predict increases in dryer stress that will be seen during power ascension to EPU. The 1/8 SMT report (CDI Report No.08-14P, "Flow-Induced Vibration in the Main Steam Lines at Browns Ferry Nuclear Units 1 and 2, With and Without Acoustic Side Branches, and Resulting Steam Dryer Loads") was previously submitted as Enclosure 5 of the letter dated October 31, 2008,
U.S. Nuclear Regulatory Commission Page 2 April 3, 2009 "Supplemental Response to Round 19 RAI and Response to Round 22 RAIs Regarding Steam Dryers," (ML083120307).
Note that Enclosures 1, 2 and 3 contain information that Continuum Dynamics, Inc. (CDI) considers to be proprietary in nature and subsequently, pursuant to 10 CFR 2.390(a)(4),
CDI requests that such information be withheld from public disclosure. Enclosure 7 provides an affidavit from CDI supporting this request. Enclosures 4, 5 and 6 contain the redacted versions of the proprietary enclosures with the CDI proprietary material removed, which is suitable for public disclosure.
TVA has determined that the additional information provided by this letter does not affect the no significant hazards considerations associated with the proposed TS change. The proposed TS change still qualifies for a categorical exclusion from environmental review pursuant to the provisions of 10 CFR 51.22(c)(9).
No new regulatory commitments are made in this submittal. If you have any questions regarding this letter, please contact J. D. Wolcott at (256) 729-2495.
I declare under penalty of perjury that the foregoing is true and correct. Executed on this 3 rd day of April, 2009.
Sincerely, R. G. West Site Vice President
Enclosures:
- 1. Response to Round 23 Request for Additional Information (RAI) EMCB.205 and EMCB.206 (Proprietary Version)
- 2. CDI Technical Note No.07-30P, "Limit Curve Analysis with ACM Rev. 4 for Power Ascension at Browns Ferry Nuclear Unit 1," Revision 3 (Proprietary Version)
- 3. CDI Report No.08-04P, "Acoustic and Low Frequency Hydrodynamic Loads at CLTP Power Level on Browns Ferry Nuclear Unit 1 Steam Dryer to 250 Hz,"
Revision 4 (Proprietary Version)
- 4. Response to Round 23 Request for Additional Information (RAI) EMCB.205 and EMCB.206 (Non-proprietary Version)
- 5. CDI Technical Note No. 07-30NP, "Limit Curve Analysis with ACM Rev. 4 for Power Ascension at Browns Ferry Nuclear Unit 1," Revision 3 (Non-proprietary Version)
U.S. Nuclear Regulatory Commission Page 3 April 3, 2009
- 6. CDI Report No. 08-04NP, "Acoustic and Low Frequency Hydrodynamic Loads at CLTP Power Level on Browns Ferry Nuclear Unit 1 Steam Dryer to 250 Hz,"
Revision 4 (Non-proprietary Version)
- 7. CDI Affidavit
U.S. Nuclear Regulatory Commission Page 4 April 3, 2009 Enclosures cc (Enclosures):
State Health Officer Alabama State Department of Public Health RSA Tower - Administration Suite 1552 P.O. Box 303017 Montgomery, Alabama 36130-3017 Ms. Eva Brown, Project Manager U.S. Nuclear Regulatory Commission (MS 08G9)
One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 Ms. Heather J. Gepford, 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 Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611-6970
ENCLOSURE 4 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNIT 1 TECHNICAL SPECIFICATIONS (TS) CHANGE TS-431 EXTENDED POWER UPRATE (EPU)
RESPONSE TO ROUND 23 REQUEST FOR ADDITIONAL INFORMATION (RAI) EMCB.205 AND EMCB.206 (NON-PROPRIETARY VERSION)
Attached is the non-proprietary version of the Response to Round 23 RAI EMCB.205 and EMCB.206.
NON-PROPRIETARY INFORMATION NRC RAI EMCB.205 (Unit 1)
CDI Technical Note No.07-30P, Rev. 2, March 2009, states:
Limit curves were generated from the in-plant CLTP strain gage data collected on Unit 1 and reported in CDI Report No. 08-04 [1]. These data were filtered across the frequency ranges shown in Table 5 to remove noise and extraneous signal content, as suggested in SIA Letter Report No. KKF-07-012 [16]. The resulting PSD curves for each of the eight strain gage locations were used to develop the limit curves, shown in Figures 1 to 4. Level 1 limit curves are found by multiplying the main steam line pressure PSD base traces by the square of the corrected limiting stress ratio (2.802 = 7.84),
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TVA Response to EMCB.205 (Unit 1)
For Unit 1, the steam dryer stress analysis determines a limiting stress ratio (SR) factor based on MSL strain gage signals where the non-acoustical noise (determined at LF conditions) has been removed. As identified in the NRC RAI, the limit curves (LC) should be determined based on applying the limiting stress ratio only to the portion of the signal with the noise removed. The Unit 1 limit curves have been revised as requested and are included as Enclosure 2, CDi Technical Note No.07-30P, "Limit Curve Analysis with ACM Rev. 4 for Power Ascension at Browns Ferry Nuclear Unit 1," Revision 3. The limit curves were generated as described below.
- 1. EIC is spectrally removed from the CLTP and LF signals for each of the eight MSL strain gage locations as follows:
CLTP'(co) = CLTP(o6)* 1 EICLTP(Co)
LF'o)= LFQ~o)*! 1 IL (c-1-LF(w~j
(
where the factors 1EICcLTP ECLTp(o)
CLTP(co) and ILF(c)
LF(o)) can each be no larger than 1.0.
- 2. Notch filters are then applied at identified noise frequencies listed in the steam dryer load reports, such as alternating current (AC) line noise, variable frequency drive AC line noise, and recirculation system pump vane passing frequencies.
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NON-PROPRIETARY INFORMATION
- 3. Non-acoustic noise (LF) is removed from the CLTP signal for each of the eight MSL strain gage locations as follows:
CLTP"(o) = CLTP'( o) * [I- IL'(o where the factor ICL'( o)l can be no larger than 0.5.
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As indicated above, the limit curves provided in Enclosure 2 reflect MSL signals that have EIC removed and notch filters applied. During EPU power ascension, MSL signals will have EIC removed and notch filters applied when comparing to the limit curves.
NRC RAI EMCB.206 (Unit 1)
In a letter dated March 11, 2009, TVA presented the Unit 1 steam dryer support beam analysis in Enclosure 1. The submittal indicates the support beams are the secondary structural members because they play no role in providing structural integrity to steam dryer. As such the main concern related to partially unattached support beams is the generation of loose parts.
TVA claims that the generation of loose parts is not a concern because the stresses in the remaining attached welds on the support beams are acceptable. Therefore, the NRC staff requests TVA to show that galloping of the unattached portion due to cross flow of the support beams is not a problem. Additionally, the licensee should address whether these welds are/will be included in the BFN inspection program.
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NON-PROPRIETARY INFORMATION TVA Response to EMCB.206 (Unit 1)
The support beams were illustrated in Figures 1 through 3 of the March 11, 2009, submittal, "Steam Dryer Analyses Additional Information." Figure 1 is reproduced below with additional notations depicting direct steam flow paths (cover plates which were inadvertently left off the previous version have also been added). The portion of the support beam which would become a free end if no credit were taken for the welds is not in the flow path of the steam entering the steam dryer vane banks. This portion of the support beam is located adjacent to and under the steel plate beneath the vane bank and inner plenum (see Figure 3 of the March 11, 2009 submittal for details of this weld area). Accordingly, it is not exposed to significant cross flow and flow induced excitation is not expected.
Upper Support Ring Welds not credited Support Beams J (welded to plates)
I 77 Blue areas indicate plates (no steam path)
X' XWhtaea indicate direct steam, flow paths into vane barks Figure 1: Steam Dryer Bottom Plan View of Support Beams In order to bound the possibility of galloping of the free end of the support beam, additional analyses were performed. For these analyses, the steam flow rate directed into the vane banks was conservatively applied across the bottom of the vane banks directed at the 14.5 inch (in) free end. This analysis follows.
Summary The part of the support beam located in the BFN Unit 1 steam dryer under the inner base plates is considered here. For a conservative analysis, this part (14.5 inches in length and extending from the center of the support beam length to the first vane bank) is assumed to be detached from the inner base plates as shown in Figure 1. The beam is subjected to steam flow, and the possibility of flutter vibrations or galloping of this part is investigated. A E4-3
NON-PROPRIETARY INFORMATION horizontal onset velocity of 15 feet/second (ft/sec) is assumed to act on this part. This velocity corresponds to the average vertical flow velocity through the inlet plenum at EPU conditions. In actuality, no vertical flow is possible in the vicinity of the support beam part, due to the bounding inner base plates immediately above the support beam. Also, the steady state horizontal flow component should be virtually zero, due to the location of the support beam in a plane of symmetry. Despite this over-estimate in cross flow velocity, it will be demonstrated that no galloping can occur. Using the most conservative analysis, where the drag coefficient (which increases damping) of the member is neglected, the energy supplied by the flow is only 1.2% of the level needed for galloping to be possible.
Therefore, galloping of this member will not occur.
Analysis Acoustic loading due to unsteady pressure fluctuations is fully accounted for in the present steam dryer calculations, and it is shown that the associated structural vibrations do not result in excessive stresses. A remaining concern is whether steady steam flow can cause oscillations of the cantilevered support beam, similar to the vibrations of power lines in a cross wind. The cause of such galloping vibrations is negative aerodynamic damping arising under specific flow conditions. However, such adverse aerodynamic damping, when it is present, has to be sufficiently large to overcome the structural damping, which is conservatively set at 1%. In what follows, the quantitative values of the support beam geometrical configuration and steam flow are used, and it is shown that adverse aerodynamic damping is significantly smaller than structural damping and, thus, no galloping vibration of the support beam is possible.
The following notation is introduced:
Steam density Ps = 2.24 pounds/ft 3 (Ibs/ft3)
Beam height H = 4 inches = 0.33 ft Flow speed U = 15 ft/sec 3 Steel density p = 0.284 lbs/in = 491 Ibs/ft3 Cross sectional area S = 3.5 in2 = 0.024 ft2 Damping ratio , = 0.01 Frequency w = 2Trf, where f = 285 Hertz (Hz) (mode 1) and 650 Hz (mode 2)
Beam length x = 14.5 inches Young's modulus of steel E = 25.55x1 06 pounds per square inch (psi)
The support beam has a height of 4 inches (vertical part only) and a base width of 3 inches.
The thickness of both parts is 0.5 inch and the length of the beam is 14.5 inches. The flow speed U corresponds to the average speed through the vane bank inlet plenum. This speed is conservative, since no vertical velocity can occur at the end of the support beam (the flow is bounded by the base plates) and horizontal cross-velocities are expected to be small in the plane of symmetry containing the support beam.
Cross flow can cause galloping vibrations in the mode shown in Figure 2. The first natural frequency occurs at approximately 285 Hz and corresponds to the mode shown in Figure 3.
Since this frequency does not correspond to the galloping motion, the second natural frequency (which occurs at approximately 650 Hz) is used in the analysis. Both frequencies are computed from the cross section geometry and cantilever support condition.
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NON-PROPRIETARY INFORMATION Vibration mode
" ""Steam Flow Fiue2: Galloping in the cross flow. Estimated frequency
=650 Hz.
- - - I *--
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4 F First Vibration mode Figure 3: First vibration mode of the cantilevered support beam.
Estimated frequency Hz. =285 It can be shown [1, 2] that the equation of motion for a body in cross flow can be written as:
pS[+2, +W2y]= I U2H dC D 2 Lda E4-5
NON-PROPRIETARY INFORMATION Here y is the displacement of the support beam in a given cross section; CL and CD are lift and drag coefficients, respectively, for the support beam cross-section; and a is the angle of attack. Collecting terms in the equation results in the combined damping term (j term) of:
D = 2pScw+ I psUH [d-L +CD]
A negative value of D corresponds to negative damping and thus an unstable system.
Clearly, there is always a positive part coming from structural damping (, term) and drag CD.
However, the derivative OCL/Oa can, for some cross-sections and incidence angles, be negative, corresponding to a sharp drop in lift at certain angles of attack (stall). For the T shape cross section the lift curve indeed has a negative slope even for small angles of attack, as reported in [3]. Thus, even at small vibrations the aerodynamic forces will add energy to the system rather than dissipate it. The question then reduces to whether this energy Esupplied is less than the energy dissipated through the structural damping Edissipated.
Following [3], the cross sectional vibration may be assumed in the form:
AU .2, y - sincot; j,=AUcoscot; .j42dyu=2uz o) o where A is a non-dimensional vibration amplitude. Using the expression for D, the net energy over a cycle can be calculated:
271 227 27t 2 Edissipated - Esupplied f D ý2 dt- PS' +/-f2dt dCL f dt 2Tc 471 dc A2U2 [PS(o+/- PsUHdCL]4 da Here, for conservatism, CD is set to zero. The first term on the right hand side. of the equation represents energy losses through structural damping, while the second term.
represents losses or gains of energy from aerodynamic forces. If the right hand side becomes negative, then the energy supplied to the system is not fully dissipated and vibrations will grow.
Using the provided numerical values:
Edissipated Esupplied A2 U2 [491.0.024-0.01-27-650- 2.24.15-0.33 dCL.1 -
L 4 da
=A 2 U [481+2.8. dCL1 2
L ~dx Galloping can occur if aCL/aa < -172. The lift curve slope for a support beam in cross flow is provided in [3] and has a value of only -2. Therefore, galloping will not occur and the ratio of the supplied energy is only 1.2% of that required for galloping to become possible.
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NON-PROPRIETARY INFORMATION Reference [3] provides a more rigorous expression for the energy supplied to a support beam in one cycle, with the lift curve slope integrated and the drag coefficient included. As before, the energy dissipated by the structure per cycle is:
Er.+p,+ 2pS/'Zd,-
2 )r PS° A2 U 2 2dr Jsin2 wotdt = S~oAzU 2 Edtisipated 2 f = if A According to [3], the energy supplied to the structure by aerodynamic forces depends on vibration amplitude. The maximum supplied energy occurs approximately at the non-dimensional amplitude A = 0.15, and is equal to:
Esupplied = PsHU3 *0.007 The ratio of supplied and dissipated energies is then:
Esupplied _- psHU .(0.007) 2 Edissipated 2 pSýomA which, using the values corresponding to the current support beam configuration and A=0.15, results in:
Esupplied - 0.0036 Edissipated Thus, the energy supplied to the system per cycle by aerodynamic forces is less than 1% of the energy dissipated, which implies that no galloping vibrations are possible. This result is in agreement with observations above. The reason why the supplied energy is lower in the second estimate is that drag is accounted for, whereas the first estimate conservatively set the drag to zero.
References
- 1. Dowell, E. H., Curtiss, Jr., H. C., Scanlan, R. H., Sisto, F., A Modern Course in Aeroelasticity, 3rd Edition, Kluwer Publishers, Dordrecht, 1995.
- 2. Den Hartog, J. P., Mechanical Vibrations, Dover, New York, 1985.
- 3. Carpena, A., Diana, G., Behavior to Wind Action of Angle and T bars on H.V. Lattice Structures, IEEE Transactions on PowerApparatusand Systems, Volume PAS-91, Issue 2, 1972, p. 536-544.
TVA plans to perform inspections of the steam dryers as described by BWRVIP-139, "BWR Vessel and Internals Project Steam Dryer Inspection and Flaw Evaluation Guidelines," which does not specify inspections of the support beams. The support beams are difficult to access for inspection as they are located on the bottom of the vane banks inside the lower support skirt.
The credited welds on the support beams have SR-a > 2.0 at EPU conditions which provides margin to the stress limits.
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